Safety Culture at the NRC Regulatory Information Conference

NRC Public Meeting

The NRC held their annual Regulatory Information Conference (RIC) March 11-13, 2014.  It included a session on safety culture (SC), summarized below.*

NRC Presentation

The NRC presentation reviewed their education and outreach activities on the SC Policy Statement (SCPS) and their participation in IAEA meetings to develop an implementation strategy for the IAEA Nuclear Safety Action Plan. 

The only new item was Safety Culture Trait Talk, an educational brochure.  Each brochure covers one of the nine SC traits in the SCPS, describing why the trait is important and providing examples of associated behaviors and attitudes, and an illustrative scenario. 

It appears only one brochure, Leadership Safety Values and Actions, is currently available.**  A quick read suggests the brochure content is pretty good.  The “Why is this trait important?” content was derived from an extensive review of SC-related social science literature, which we liked a lot and posted about Feb. 10, 2013.  The “What does this trait look like?” section comes from the SC Common Language initiative, which we have reviewed multiple times, most recently on April 6, 2014.  The illustrative scenario is new content developed for the brochure and provides a believable story of how normalization of deviance can creep into an organization under the skirt of an employee bonus program based on plant production.

Licensee Presentations

There were three licensee presentations, all from entities that the NRC has taken to the woodshed over SC deficiencies.  Presenting at the RIC may be part of their penance but it’s interesting to see what folks who are under the gun to change their SC have to say.

Chicago Bridge & Iron, which is involved in U.S. nuclear units currently under construction, got in trouble for creating a chilled work environment at one of its facilities.  The fixes focus on their Safety Conscious Work Environment and Corrective Action Program.   Detailed activities come from the familiar menu: policy updates, a new VP role, training, oversight, monitoring, etc.  Rapping CB&I’s knuckles certainly creates an example for other companies trying to cash in on the “Nuclear Renaissance” in the U.S.  Whatever CB&I does, they are motivated to make it work because there is probably a lot of money at stake.  The associated NRC Confirmatory Order*** summarizes the history of the precipitating incident and CB&I’s required corrective actions.

Browns Ferry has had SC-related problems for a long time and has been taken to task by both NRC and INPO.  The presentation includes one list of prior plant actions that DIDN’T work while a different list displays current actions that are supposedly working.  Another slide shows improvement in SC metrics based on survey data—regular readers know how we feel about SC surveys.  The most promising initiative they are undertaking is to align with the rest of the TVA fleet on NEI 09-07 “Fostering a Strong Nuclear Safety Culture.”  Click on the Browns Ferry label to see our posts that mention the plant.

Fort Calhoun’s problems started with the 2011 Missouri River floods and just got worse, moving them further down the ROP Action Matrix and forcing them to (among many other things) complete an independent SC assessment.  They took the familiar steps, creating policies, changing out leadership, conducting training, etc.  They also instituted SC “pulse” surveys and use the data to populate their SC performance indicators.  Probably the most important action plant owner OPPD took was to hire Exelon to manage the plant.  Fort Calhoun’s SC-related NRC Confirmatory Action Letter was closed in March 2013 so they are out of the penalty box.

Bottom line: The session presentations are worth a look.


*  RIC Session T11: Safety Culture Journeys: Lessons Learned from Culture Change Efforts (Mar. 11, 2014).  Retrieved April 25, 2014.  Slides for all the presentations are available from this page.

**  “Leadership Safety Values and Actions,” NRC Safety Culture Trait Talk, no. 1 (Mar. 2014).  ADAMS ML14051A543.  Retrieved April 25, 2014.

***  NRC Confirmatory Order EA-12-189 re: Chicago Bridge and Iron (Sept. 16, 2013).  ADAMS ML13233A432.  Retrieved April 25, 2014.

Assessing Safety Culture Using Cultural Attributes

Two weeks ago we posted on NUREG-2165, a document that formalizes a “common language” for describing nuclear safety culture (SC).  The NUREG contains a set of SC traits, attributes that define each trait and examples that would evidence each attribute.  We expressed concern about how traits and attributes could and would be applied in practice to assess SC.

Well, we didn’t have to wait very long.  This post reviews a recent International Nuclear Safety Journal article* that describes the SC oversight process developed by the Romanian nuclear regulatory agency (CNCAN).  The CNCAN process uses the International Atomic Energy Agency (IAEA) SC definition and attributes and illustrates how attributes can be used to evaluate SC.  Note that CNCAN is not attempting to directly regulate SC but they are taking comprehensive steps to evaluate and influence the licensee’s SC.

CNCAN started with the 37 IAEA attributes and decided that 20 were accessible via the normal review and inspection activities.  Some of the 20 could be assessed using licensee and related documentation, others through interviews with licensee and contractor personnel, and others by direct observation of relevant activities. 

CNCAN recognizes there are limitations to using this process, e.g., findings that reflect a reviewer’s subjective opinion, the quality of match (relevance) between an attribute and a specific technical or functional area, the quality of the information gathered and used, and over-reliance on one specific finding.  Time is also an issue.  “[A] large number of review and inspection activities are required, over a relatively long period of time, to gather sufficient data in order to make a judgement on the safety culture of an organisation as a whole.” (p. 4)

However, they are optimistic about longer-term effectiveness.  “. . . evidence of certain attributes not being met for several functional areas and processes would provide a clear indication of a problem that would warrant increased regulatory surveillance.”  In addition, “[t]he implementation of the [oversight process] proved that all the routine regulatory reviews and inspections reveal aspects that are of certain relevance to safety culture.  Interaction with plant staff during the various inspection activities and meetings, as well as the daily observation by the resident inspectors, provide all the necessary elements for having an overall picture of the safety culture of the licensee.” (ibid., emphasis added)

Our Perspective

We reviewed a draft of the CNCAN SC oversight process on March 23, 2012.  We found the treatment of issues we consider important to be generally good.  For example, in the area of decision making, goal conflict is explicitly addressed, from production vs. safety to differing personal opinions.  Corrective action (CA) gets appropriate attention, including CA prioritization based on safety significance and verification that fixes are implemented and effective.  Backlogs in many areas, including maintenance and corrective actions, are addressed.  In general, the treatment is more thorough than the examples included in the NUREG.

However, the treatment of management incentives is weak.  We favor a detailed evaluation of the senior managers’ compensation scheme focusing on how much of their compensation is tied to achieving safety (vs. production or other) goals.

So, do we feel better about the qualms we expressed over the NUREG, viz., that it is a step on the road to the bureaucratization of SC evaluation, a rigid checklist approach that ultimately creates an incomplete and possibly inaccurate picture of a plant’s SC?  Not really.  Our concerns are described below.

Over-simplification

For starters, CNCAN decided to focus on 20 attributes because they believed it was possible to gather relevant information on them.  What about the other 17?  Are they unrelated to SC simply because it might be hard to access them?

A second simplification is limiting the information search to artifacts: documents, interviews and observations.  One does not have to hold some esoteric belief, e.g., that SC is an emergent organizational property that results from the functioning of a socio-technical system, to see that focusing on the artifacts may be similar to the shadows in Plato’s cave.  Early on, the article refers to this problem by quoting from a 1999 NEA report: “the regulator can evaluate the outward operational manifestations of safety culture as well as the quality of work processes, and not the safety culture itself.” (p. 2)

Limited applicability

Romania has a single nuclear plant and what is, at heart, a one-size-fits-all approach is much more practical when “all” equals one.  This type of approach might even work in, say, France, where there are multiple plants but a single operator.  On the other hand, the U.S. currently has 32 operators reporting to 81 owners.**  Developing SC assessment techniques that are comprehensive, consistent and perceived as fair by such a large group is not a simple task.  The U.S. approach will continue to subsume SC evaluation under the ROP, which arguably ties SC evaluation to “objective” safety-related performance but unfortunately leads to de facto regulation of SC, less transparency and incomprehensible results in specific cases.***

(It could be worse.  For an example, just look at DOE where the recent “guidance” on conducting SC self-assessments led to unreliable self-assessment results that can’t be compared with each other.  For more on DOE, see our March 31, 2014 post or click on the DOE label at the bottom of this post.)

Bottom line

Ultimately the article can be summarized as follows: It’s hard, maybe impossible to directly evaluate SC but here’s what we (CNCAN) are doing and we think it works.  We say a CNCAN-style approach may be helpful but one should remain alert to important SC factors that may be overlooked.


*  M. Tronea, “Trends and Challenges in Regulatory Assessment of Nuclear Safety Culture,” International Nuclear Safety Journal, vol. 3 no. 1 (2014), pp. 1-5.  Retrieved April 14, 2014.  Dr. Tronea works for the Romanian nuclear authority (CNCAN) and is the founder/moderator of the LinkedIn Nuclear Safety group.

**  NEI website, retrieved April 15, 2014.

***  For an example, see our Jan. 30, 2013 post on Palisades. 

GM’s CEO Revealing Revelation

GM CEO Mary Barra

As most of our readers are aware General Motors has been much in the news of late regarding a safety issue associated with the ignition switches in the Chevy Cobalt.  At the beginning of April the new CEO of GM, Mary Barra, testified at Congressional hearings investigating the issue.  A principal focus of the hearings was the extent to which GM executives were aware of the ignition switch issues which were identified some ten years ago but did not result in recalls until this February.  Barra has initiated a comprehensive internal investigation of the issues to determine why it took so many years for a safety defect to be announced.

In a general sense this sounds all too familiar as the standard response to a significant safety issue.  Launch an independent investigation to gather the facts and figure out what happened, who knew what, who decided what and why.  The current estimate is that it will take almost two months for this process to be completed.  Also familiar is that accountability inevitably starts (and often ends) at the engineering and low level management levels.  To wit, GM has already announced that two engineers involved in the ignition switch issues have been suspended.

But somewhat buried in Barra’s Congressional testimony is an unusually revealing comment.  According to the Wall Street Journal, Barra said “senior executives in the past were intentionally not involved in details of recalls so as to not influence them.”*  Intentionally not involved in decisions regarding recalls - recalls which can involve safety defects and product liability issues and have significant public and financial liabilities.  Why would you not want the corporation's executives to be involved?  And if one is to believe the rest of Barra’s testimony, it appears executives were not even aware of these issues.

Well, what if executives were involved in these critical decisions - what influence could they have that GM would be afraid of?  Certainly if executive involvement would assure that technical assessments of potential safety defects were rigorous and conservative - that would not be undue influence.  So that leaves the other possibility - that involvement of executives could inhibit or constrain technical assessments from assuring an appropriate priority for safety.  This would be tantamount to the chilling effect popularized in the nuclear industry.  If management involvement creates an implicit pressure to minimize safety findings, there goes the safety conscious work environment and safety.

If keeping executives out of the decision process is believed to yield “better” decisions, it says some pretty bad things about either their competence or ethics.  Having executives involved should at least ensure that they are aware and knowledgeable of potential product safety issues and in a position to proactively assure that decisions and actions are appropriate.   What might be the most likely explanation is that executives don’t want the responsibility and accountability for these types of decisions.  They might prefer to remain protected at the safety policy level but leave the messy reality of comporting those dictates with real world business considerations to lower levels of the organization.  Inevitably accountability rolls downhill to somebody in the engineering or lower management ranks. 

One thing that is certain.  Whatever the substance and process of GM’s decision, it is not transparent, probably not well documented, and now requires a major forensic effort to reconstitute what happened and why.  This is not unusual and it is the standard course in other industries including nuclear generation.  Wouldn’t we be better off if decisions were routinely subject to the rigor of contemporaneous recording including how complex and uncertain safety issues are decided in the context of other business priorities, and by whom?


*  J.B. White and J. Bennett, "Some at GM Brass Told of Cobalt Woe," Wall Street Journal online (Apr. 11, 2014)

NRC Issues Safety Culture Common Language NUREG

The NRC has issued NUREG-2165* which formalizes the safety culture (SC) common language that has been under development since the NRC SC Policy Statement (SCPS) was issued.  On topics important to us the NUREG repeats word-for-word the text of a document** prepared after a common language workshop held January 29-30, 2013.  Both documents contain a set of SC traits, attributes that define each trait and examples that would evidence each attribute.  Because the language is the same, our opinion on the treatment of our important topics remains the same, as described in detail in our Feb. 28, 2013 post.  Specifically, the treatment of

Decision making, including the treatment of goal conflicts, is Good;

Corrective action, part of problem identification and resolution, is Satisfactory;

Management Incentives is Unsatisfactory because the associated attributes focuses on workers, not managers, and any senior management incentive program is not mentioned; and

Work Backlogs are mentioned in a couple of specific areas so the overall grade is Minimally Acceptable.

But we have one overarching concern that transcends our opinion of common language specifics.

Our Perspective

Our biggest issue with the traits, attributes and examples approach is our fear it will lead to the complete bureaucratization of SC evaluation, either consciously or unconsciously.  The examples in particular can morph into soft requirements on a physical or mental checklist.  Such an approach leads to numerous questions.  How many of the 10 traits does a healthy or positive SC exhibit?***  How many of the 40 attributes?  Are the traits equally important?  How about the attributes?  Could the weighting factors vary across plant sites?  How many examples must be observed before an attribute is judged acceptably present?

We understand the value of effective communications among regulators, licensee personnel and other stakeholders.  But we worry about possible unintended consequences as people attempt to apply the guidance in NUREG-2165, especially in the NRC’s Reactor Oversight Process (ROP).****


*  NRC NUREG-2165, “Safety Culture Common Language” (Mar. 2014).  ADAMS ML14083A200.

**  Nuclear Safety Culture Common Language 4th Public Workshop January 29-31, 2013.  ADAMS ML13031A343.

***  The NUREG-2165 text describes a “healthy” SC while the SCPS (published as NUREG/BR-0500, Rev. 1, ADAMS ML12355A122) refers to a “positive” SC.  The correct answer to “how many traits?” may be “more than ten” because the authors note “There may also be traits not included in the SCPS that are important in a healthy safety culture.” (p. 2)

****  The common language “initiative is within the Commission-directed framework for enhancing the ROP treatment of cross-cutting areas to more fully address safety culture.” (p. 3)  This may require a little linguistic jujitsu since the SCPS says “traits were not developed for inspection purposes.”

Our Gaze Returns to DOE and its Safety Culture

The Department of Energy (DOE) recently submitted a report* to the Defense Nuclear Facilities Safety Board (DNFSB) covering DOE’s evaluation of Safety Conscious Work Environment (SCWE) self-assessments at various DOE facilities.  This evaluation was included in the DOE’s Implementation Plan** (IP) developed in response to the DNFSB report, Safety Culture at the Waste Treatment and Immobilization Plant.*** (WTP, or the Vit Plant).  This post provides some background on how WTP safety culture (SC) problems led to a wider assessment of SC in DOE facilities and then reviews the current report.

Background

The DNFSB report on the WTP was issued June 9, 2011; it said the WTP SC was “flawed.”  Issues included discouraging technical dissent, goal conflicts between schedule/budget and safety, and intimidation of personnel.  We posted on the DNFSB report June 15, 2011.  The report’s recommendations included this one: that the Secretary of Energy “conduct an Extent of Condition Review to determine whether these safety culture weaknesses are limited to the WTP Project, . . .” (DNFSB, p. 6) 

After some back-and-forth between DOE and DNFSB, DOE published their IP in December 2011.  We reviewed the IP on Jan. 24, 2012.  Although the IP contained multiple action items, our overall impression was “that DOE believes there is no fundamental safety culture issue. . . . While endlessly citing all the initiatives previously taken or underway, never does the DOE reflect on why these initiatives have not been effective to date.”  So we were not exactly optimistic but DOE did say it would “conduct an Extent of Condition Review to find out whether similar safety culture weaknesses exist at other sites in addition to the WTP and whether there are barriers to strong safety culture at Headquarters and the Department as a whole (e.g., policies or implementation issues). The review will focus on the Safety Conscious Work Environment (SCWE) at each site examined.” (IP, p. 17)  In other words, SC was reduced to SCWE from the get-go.****

Part of the DOE review was to assess SCWE at a group of selected DOE facilities.  DOE submitted SC assessments covering five facilities to DNFSB on Dec. 12, 2012.  We reviewed the package in our post Jan. 25, 2013 and observed “The DOE submittal contained no meta-analysis of the five assessments, and no comparison to Vit Plant concerns.  As far as [we] can tell, the individual assessments made no attempt to focus on whether or not Vit Plant concerns existed at the reviewed facilities.”  We called the submittal “foot dragging” by DOE.

Report on SCWE Self-Assessments

A related DOE commitment was to perform SCWE self-assessments at numerous DOE facilities and then evaluate the results to determine if SCWE issues similar to WTP’s existed elsewhere.  It is important to understand that this latest report is really only the starting point for evaluating the self-assessments because it focuses on the processes used during the self-assessments and not the results obtained. 

The evaluation of the self-assessments was a large undertaking.  The evaluation team visited 22 DOE and contractor organizations and performed document reviews for 9 additional organizations, including the DOE Office of River Protection and Bechtel National, major players in the WTP drama. 

Problems abounded.  Self-assessment guidance was prepared but not distributed to all sites in a timely manner and there was no associated training.  Each self-assessment team had a “subject matter expert” but the qualifications for that role were not specified.  Data collection methods were not consistently applied and data analyses were of variable quality.  As a consequence, the self-assessment approaches used varied widely and the results obtained had variable reliability.

The self-assessment reports exhibited varying quality.  Some were satisfactory but “In many of the self-assessment reports, the overall conclusions did not accurately reflect the information in the data and analysis sections. In some cases, negative results were presented with a statement rationalizing or minimizing the issue, rather than indicating a need to find out more about the issue and resolve it.  In other cases, although data and/or analysis reflected potential problems, those problems were not mentioned in the conclusions or executive summaries, which senior management is most likely to read.” (p. 7)

The evaluation team summarized as follows: “The overall approach ultimately used to self-assess SCWE across the complex did not provide for consistent application of assessment methodologies and was not designed to ensure validity and credibility. . . . The wide variation in the quality of methodologies and analysis of results significantly reduces the confidence in the conclusions of many of the self-assessments.  Consequently, caution should be used in drawing firm conclusions about the state of SCWE or safety culture across the entire DOE complex based on a compilation of results from all the site self-assessments.” (p. iii)

“The Independent Oversight team concluded that DOE needs to take additional actions to ensure that future self-assessments provide a valid and accurate assessment of the status of the safety culture at DOE sites and organizations, . . .” (p. 8)  This is followed by a series of totally predictable recommendations for process improvements: “enhance guidance and communications,” increase management “involvement in, support for, and monitoring of site self-assessments,” and “DOE sites . . . should increase their capabilities to perform self-assessments . . .” (pp. 9-10)

Our Perspective

The steps taken to date do not inspire confidence in the DOE’s interest in determining if and what SCWE (much less more general SC) issues exist in the DOE complex.  For the facilities that were directly evaluated, we have some clues to the existence similar problems.  For the facilities that conducted self-assessments, so far we have—almost nothing.

There is one big step remaining: DOE also said it would “develop a consolidated report from the results of the self-assessments and HSS independent reviews.” (IP, p. 20)  We await that report with bated breath.

For our U.S. readers: This is your tax dollars at work. 


*  DOE Office of Enforcement and Oversight, “Independent Oversight Evaluation of Line Self-Assessments of Safety Conscious Work Environment” (Feb. 2014).

**  U.S. Dept. of Energy, “Implementation Plan for Defense Nuclear Facilities Safety Board Recommendation 2011-1, Safety Culture at the Waste Treatment and Immobilization Plant”  (Dec. 2011).

***  Defense Nuclear Facilities Safety Board, Recommendation 2011-1 to the Secretary of Energy "Safety Culture at the Waste Treatment and Immobilization Plant" (Jun 9, 2011).

****  DOE rationalized reducing the scope of investigation from SC to SCWE by saying “The safety culture issues identified at WTP are primarily SCWE issues. . .” (p. 17)  We posted a lecturette about SC being much more than SCWE here.

NRC "National Report" to IAEA

A March 25, 2014 NRC press release* announced that Chairman Macfarlane presented the Sixth National Report for the Convention on Nuclear Safety** to International Atomic Energy Agency (IAEA) member countries.  The report mentions safety culture (SC) several times, as discussed below.  There is no breaking news in a report like this.  We’re posting about it only because it provides an encyclopedic review of NRC activities including a description of how SC fits into their grand scheme of things.  We also tie the report’s contents to related posts on Safetymatters.  The numbers shown below are section numbers in the report.

6.3.11 Public Participation 

This section describes how the NRC engages with stakeholders and the broader public.  As part of such engagement, the NRC says it expects employers to maintain an open environment where workers are free to raise safety concerns. “These expectations are communicated through the NRC’s Safety Culture Policy Statement” and other regulatory directives and tools. (p. 72)  This is pretty straightforward and we have no comment.

8.1.6.2 Human Resources

Section 8 describes the NRC, from its position in the federal government to how it runs its internal activities.  One such activity is the NRC Inspector General’s triennial General Safety Culture and Climate Survey for NRC employees.  Reporting on the most recent (2012) survey, “the NRC scored above both Federal and private sector benchmarks, although in 2012 the agency did not perform as strongly as it had in the past.” (p. 96)  We posted on the internal SC survey back on April 6, 2013; we felt the survey raised a few significant issues.

10.4 Safety Culture

Section 10 covers activities that ensure that safety receives its “due priority” from licensees and the NRC itself.  Sub-section 10.4 provides an in-depth description of the NRC’s SC-related policies and practices so we excerpt from it at length.

The discussion begins with the SC policy statement and the traits of a positive (sic) SC, including Leadership, Problem identification and resolution, Personal accountability, etc.

The most interesting part is 10.4.1 NRC Monitoring of Licensee Safety Culture which covers “the policies, programs, and practices that apply to licensee safety culture.” (p. 118)  It begins with the Reactor Oversight Process (ROP) and its SC-related enhancements.  NRC staff identified 13 components as important to SC, including decision making, resources, work control, etc.  “All 13 safety culture components are applied in selected baseline, event followup, and supplemental IPs [inspection procedures].” (p. 119)

“There are no regulatory requirements for licensees to perform safety culture assessments routinely. However, depending on the extent of deterioration of licensee performance, the NRC has a range of expectations [emphasis added] about regulatory actions and licensee safety culture assessments, . . .” (p. 119)

“In the routine or baseline inspection program, the inspector will develop an inspection finding and then identify whether an aspect of a safety culture component is a significant causal factor of the finding. The NRC communicates the inspection findings to the licensee along with the associated safety culture aspect. 

“When performing the IP that focuses on problem identification and resolution, inspectors have the option to review licensee self-assessments of safety culture. The problem identification and resolution IP also instructs inspectors to be aware of safety culture components when selecting samples.” (p. 119)

“If, over three consecutive assessment periods (i.e., 18 months), a licensee has the same safety culture issue with the same common theme, the NRC may ask [emphasis added] the licensee to conduct a safety culture self-assessment.” (p. 120)

If the licensee performance degrades to Column 3 of the ROP Action Matrix and “the NRC determines that the licensee did not recognize that safety culture components caused or significantly contributed to the risk-significant performance issues, the NRC may request [emphasis added] the licensee to complete an independent assessment of its safety culture.” (p. 120)

For licensees in Column 4 of the ROP “the NRC will expect [emphasis added] the licensee to conduct a third-party independent assessment of its safety culture. The NRC will review the licensee’s assessment and will conduct an independent assessment of the licensee’s safety culture . . .” (p. 120)

ROP SC considerations “provide the NRC staff with (1) better opportunities to consider safety culture weaknesses . . . (2) a process to determine the need to specifically evaluate a licensee’s safety culture . . . and (3) a structured process to evaluate the licensee’s safety culture assessment and to independently conduct a safety culture assessment for a licensee . . . .  By using the existing Reactor Oversight Process framework, the NRC’s safety culture oversight activities are based on a graded approach and remain transparent, understandable, objective, risk-informed, performance-based, and predictable.” (p. 120)

We described this hierarchy of NRC SC-related activities in a post on May 24, 2013.  We called it de facto regulation of SC.  Reading the above only confirms that conclusion.  When the NRC asks, requests or expects the licensee to do something, it’s akin to a military commander’s “wishes,” i.e., they’re the same as orders.

10.4.2 The NRC Safety Culture 

This section covers the NRC’s actions to strengthen its internal SC.  This actions include appointing an SC Program Manager; integrating SC into the NRC’s Strategic Plan; developing training; evaluating the NRC’s problem identification, evaluation and resolution processes; and establishing clear expectations and accountability for maintaining current policies and procedures. 

We would ask how SC affects (and is affected by) the NRC’s decision making and resource allocation processes, work practices, operating experience integration and establishing personal accountability for maintaining the agency’s SC.  What’s good for the goose (licensee) is good for the gander (regulator).

Institute of Nuclear Power Operations (INPO) 

INPO also provided content for the report.  Interestingly, it is a 39-page Part 3 in the body of the report, not an appendix.  Part 3 covers INPO’s mission, organization, etc. and includes a section on SC.

6. Priority to Safety (Safety Culture)

The industry and INPO have their own definition of SC: “An organization’s values and behaviors—modeled by its leaders and internalized by its members—that serve to make nuclear safety the overriding priority.” (p. 230)

“INPO activities reinforce the primary obligation of the operating organizations’ leadership to establish and foster a healthy safety culture, to periodically assess safety culture, to address shortfalls in an open and candid fashion, and to ensure that everyone from the board room to the shop floor understands his or her role in safety culture.” (p. 231)

We believe our view of SC is broader than INPO’s.  As we said in our July 24, 2013 post “We believe culture, including SC, is an emergent organizational property created by the integration of top-down activities with organizational history, long-serving employees, and strongly held beliefs and values, including the organization's “real” priorities.  In other words, SC is a result of the functioning over time of the socio-technical system.  In our view, a CNO can heavily influence, but not unilaterally define, organizational culture including SC.” 

Conclusion

This 341 page report appears to cover every aspect of the NRC’s operations but, as noted in our introduction, it does not present any new information.  It’s a good reference document to cite if someone asks you what the NRC is or what it does.

We found it a bit odd that the definition of SC in the report is not the definition promulgated in the NRC SC Policy Statement.  Specifically, the report says the NRC uses the 1991 INSAG definition of SC: “that assembly of characteristics and attitudes in organizations and individuals which establishes that, as an overriding priority, nuclear safety issues receive the attention warranted by their significance.” (p. 118)

The Policy Statement says “Nuclear safety culture is the core values and behaviors resulting from a collective commitment by leaders and individuals to emphasize safety over competing goals to ensure protection of people and the environment.”***

Of course, both definitions are different from the INPO definition provided above.  We’ll leave it as an exercise for the reader to figure out what this means.


*  NRC Press Release No: 14-021, “NRC Chairman Macfarlane Presents U.S. National Report to IAEA’s Convention on Nuclear Safety” (Mar. 25, 2014).  ADAMS ML14084A303.

**  NRC NUREG-1650 Rev. 5, “The United States of America Sixth National Report for the Convention on Nuclear Safety” (Oct. 2013).  ADAMS ML13303B021. 

***  NUREG/BR 0500 Rev 1, “Safety Culture Policy Statement” (Dec 2012).  ADAMS ML12355A122.  This definition comports with the one published in the Federal Register Vol. 76, No. 114 (June 14, 2011) p. 34777.

Safety Culture at Tohoku Electric vs. Tokyo Electric Power Co. (TEPCO)

Fukushima No. 1 (Daiichi)

An op-ed* in the Japan Times asserts that the root cause of the Fukushima No. 1 (Daiichi) plant’s failures following the March 11, 2011 earthquake and tsunami was TEPCO’s weak corporate safety culture (SC).  This post summarizes the op-ed then provides some background information and our perspective.

Op-Ed Summary 

According to the authors, Tohoku Electric had a stronger SC than TEPCO.  Tohoku had a senior manager who strongly advocated safety, company personnel participated in seminars and panel discussions about earthquake and tsunami disaster prevention, and the company had strict disaster response protocols in which all workers were trained.  Although their Onagawa plant was closer to the March 11, 2011 quake epicenter and experienced a higher tsunami, it managed to shut down safely.

SC-related initiatives like Tohoku’s were not part of TEPCO’s culture.  Fukushima No. 1’s problems date back to its original siting and early construction.  TEPCO removed 25 meters off the 35 meter natural seawall of the plant site and built its reactor buildings at a lower elevation of 10 meters (compared to 14.7m for Onagawa).  Over the plant’s life, as research showed that tsunami levels had been underestimated, TEPCO “resorted to delaying tactics, such as presenting alternative scientific studies and lobbying”** rather than implementing countermeasures.

Background and Our Perspective

The op-ed is a condensed version of the authors’ longer paper***, which was adapted from a research paper for an engineering class, presumably written by Ms. Ryu.  The op-ed is basically a student paper based on public materials.  You should read the longer paper, review the references and judge for yourself if the authors have offered conclusions that go beyond the data they present.

I suggest you pay particular attention to the figure that supposedly compares Tohoku and TEPCO using INPO’s ten healthy nuclear SC traits.  Not surprisingly, TEPCO doesn’t fare very well but note the ratings were based on “the author’s personal interpretations and assumptions” (p. 26)

Also note that the authors do not mention Fukushima No. 2 (Daini), a four-unit TEPCO plant about 15 km south of Fukushima No. 1.  Fukushima No. 2 also experienced damage and significant challenges after being hit by a 9m tsunami but managed to reach shutdown by March 18, 2011.  What could be inferred from that experience?  Same corporate culture but better luck?

Bottom line, by now it’s generally agreed that TEPCO SC was unacceptably weak so the authors plow no new ground in that area.  However, their description of Tohoku Electric’s behavior is illuminating and useful.


*  A. Ryu and N. Meshkati, “Culture of safety can make or break nuclear power plants,” Japan Times (Mar. 14, 2014).  Retrieved Mar. 19, 2014.

**  Quoted in the op-ed but taken from “The official report of the Fukushima Nuclear Accident Independent Investigation Commission [NAIIC] Executive Summary” (The National Diet of Japan, 2012), p. 28.  The NAIIC report has a longer Fukushima root cause explanation than the op-ed, viz, “the root causes were the organizational and regulatory systems that supported faulty rationales for decisions and actions, . . .” (p. 16) and “The underlying issue is the social structure that results in “regulatory capture,” and the organizational, institutional, and legal framework that allows individuals to justify their own actions, hide them when inconvenient, and leave no records in order to avoid responsibility.” (p. 21)  IMHO, if this were boiled down, there wouldn’t be much SC left in the bottom of the pot.

***  A. Ryu and N. Meshkati, “Why You Haven’t Heard About Onagawa Nuclear Power Station after the Earthquake and Tsunami of March 11, 2011” (Rev. Feb. 26, 2014).