ML20133G956
| ML20133G956 | |
| Person / Time | |
|---|---|
| Issue date: | 01/15/1997 |
| From: | Stewart Magruder NRC (Affiliation Not Assigned) |
| To: | Matthews D NRC (Affiliation Not Assigned) |
| References | |
| PROJECT-689 NUDOCS 9701160241 | |
| Download: ML20133G956 (13) | |
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k UNITED STATES a
j Ij NUCLEAR REGULATORY COMMISSION t
WASHINGTON, D.C. 20555-0001 January 15, 1997 MEMORANDUM T0:
David B. Matthews, Chief Generic Issues and Environmental Projects Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation FROM:
Stewart L. Magruder, Project Manager f
Generic Issues and Environmental Projects Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation
SUBJECT:
SUMMARY
OF DECEMBER 19, 1996, MEETING WITH THE NUCLEAR ENERGY INSTITUTE (NEI) REGARDING ACCIDENT MANAGEMENT STRATEGIES On December 19, 1996, representatives of NEI met with representatives of the Nuclear Regulatory Commission (NRC)'at the NRC's offices in Rockville, Maryl and. Attachment I provides a list of meeting attendees.
The purpose of the meeting was to discuss NEI and industry progress with regard to severe accident management guidelines (SAMGs) and identifying candidate volunteers for planned information gathering visits and follow-on pilot inspections, and proposed groundrules and schedules for these visits.
The NEI representatives opened the meeting by summarizing the industry efforts over the past year. The NRC staff then provided a brief description of the status of the boiling water reactor owners group (BWROG) SAMGs. The staff indicated that a technical evaluation report has been written, a submittal from the BWR0G on a SAMG implementation timeline for an example sequence is expected soon, and a meeting with the BWROG is expected in January or February. The NRC staff stated that they still plan to conduct two to four information gathering visits during the first half of 1997 in order to complete the Temporary Instruction developed to aid inspectors in verifying compliance with the industry initiative.
The staff noted that it was their understanding that NEI had committed to identify licensees that would be in a i
position to support these visits.
The NEI representatives stated that the industry is concerned about enforcement issues related to findings during the information gathering visits and about the burden that these visits and the follow-on pilot inspections would place on industry and NRC staff resources.
In response, the staff noted s/
that they plan to perform pilot inspections at about four to six plants.
h' These pilot inspections would look at a licensee's complete program and
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include observing an accident management drill.
Based on the results of the
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pilot inspections, the staff plans to develop an inspection procedure to be used to inspect severe accident management implementation at the remainder of
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the plants. After the initial inspection at each plant, inspections of the I
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accident management program will be held primarily on a for-cause basis.
In '
addition, the emergency planning core inspection procedures will be slightly i
modified to provide a high level inspection of the seve_re accident. management program in order to identify whether a more detailed evaluation is warranted.
1 I
The NEI representatives stated that they have not yet. identified any candidate plants for the NRC information gathering visits.- They then proposed an alternative to NRC's visits and pilot inspections.
Under their proposal, provided as Attachment 2, NEI would take the lead, with NRC staff'as observers, for an Industry Demonstration Process. The NEI representatives stated that they believed that a demonstration would provide an atmosphere more conducive to information gathering and sharing than an NRC visit or pilot inspection. The NRC staff agreed to review the proposal and to provide comments during a meeting tentatively scheduled for the end of January 1997.
The NEI representatives announced that they are planning to hold a workshop in March 1997 and would like NRC participation. The workshop would allow utilities who have started the implementation process to provide " lessons learned" and provide a forum for utility personnel to explore and discuss alternative solutions to issues that have arisen during the process. A draft agenda for the workshop was provided and is included as Attachment 3.
The staff stated that they would probably attend the workshop provided that it is open to the public.
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0FFICIAL RECORD COPY
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i D. Matthews January 15, 1997
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accident management program will be held primarily on a for-cause basis.
In addition, the emergency planning core inspection procedures-will be slightly j
modified to provide a high level inspection of the severe accident management I
program in order to identify whether a more detailed evaluation is warranted.
s The NEI representatives stated that they have not yet identified any candidate i
plants for the NRC information gathering visits.
They then proposed an alternative to NRC's visits and pilot inspections. Under their proposal, j
provided as Attachment 2, NEI would take the lead, with NRC staff as L
observers, for an Industry Demonstration Process.
The NEI representatives j
stated that they believed that a demonstration would. provide an atmosphere more conducive to information gathering and sharing than an'NRC visit or pilot j.
inspection.
The NRC staff agreed to review the proposal'and to provide i
comments during a meeting tentatively scheduled for the end of January 1997.
i The NEI representatives announced that they,are planning to hold a workshop in
].
March 1997 and would like NRC participation. -The workshop would allow l
utilities who have started the implementation process to provide'" lessons learned" and provide a forum for utility personnel to explore and discuss alternative solutions to issues that have arisen during the process. A draft agenda for the workshop was provided and is included as Attachment 3.
The i
staff stated that they would probably attend the workshop provided thatLit is open to the public.
i Project No. 689 Attachments: As stated cc w/atts:
See next page r
e*
t NRC/NEI NEETING ON ACCIDENT MANAGENENT STRATEGIES LIST OF ATTENDEES December 19, 1996 H821E ORGANIZATION l
Dave Modeen NEI i
Fred Emerson NEI 1
Alan Nelson NEI Jim Fulford NUS-LIS Altheia Wyche Bechtel/SERCH Richard Eckenrode NRC Bob Palla NRC l
Jim O'Brien NRC Tom Essig NRC Stu Magruder NRC/NRR i
l l
4 DRAFT 12/18/96 STRAWMAN INDUSTRY SAMG DEMONSTRATION PROCESS I.
Obiective u
Demonstrate that the enhanced accident management capabilities implemented at a particular nuclear power plant are consistent with NEI 91-04, Revision 1, Section 5.
II.
Method A.
Plant visits will be scheduled to demonstrate that Sections 5.2 (Severe Accident Closure Process) and 5.3 (Severe Accident Management Implementing Elements) of NEI 91-04, Revision 1, have been accomplished in a cohesive manner.
B.
Plant visits willinclude a presentation of the approach (e.g., flow chart, administrative procedure or white paper) used by the utility to j
develop the plant-speciSc SAMG materials, emergency preparedness implementing procedures assigning severe accident management responsibilities, key SAMG materials developed for use by plant staff during a severe accident, direct observation of plant staff performance during a table top mini-drill, and the utility critique.
C.
Plant visits will end with a debrief among the cognizant members of the plant staff, NEI and other industry personnel, and NRC staff. The purpose of the debrief would be to capture any concerns or problems identified during the plant visits in order that those issues may be discussed and resolved as part of the generic resolution process.
D.
Any documentation and resolution of generic industry criticisms will be addressed by NEI. This includes such things as exclusion of simulators from SAMG training and drills,10 CFR 50.59 issues and systematic approach to training.
E.
Any documentation and resolution of vendor-specific criticisms related to vendor-specific guidance or issues will be referred by NEI to the cognizant NSSS Owners Group to address. This may include response by more than one NSSS Owners Group to the generic items noted in C and D above.
F.
Any documentation and resolution of plant-specific criticisms is solely the responsibility of the host utility.
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III.
Work Plan - The demonstration will address the process used to:
A.
Develop severe accident management guidance (SAMG), including:
1.
insights from the plant IPE, IPEEE and current capabilities;
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2.
applicable strategies from the NSSS Owners Group materials; and 3.
information (calculational aids, measured parameters, etc.)
required to evaluate SAMG response.
4.
l B.
Interface the SAMG with the plant's Emergency Plan, including:
1.
ERO positions responsible for decision making, evaluation and implementation of SAMG.
C.
Incorporate severe accident material into appropriate training programs, including:
1.
the level of training provided for the applicable ERO positions; i
2.
the form and content of the SAMG training material using a systematic approach to training; and 3.
the feedback process employed to ensure severe accident management capabilities are maintained.
D.
Consider new severe accident management information, including:
1.
insights from self-assessments; and 2.
insights from activities external to the company, i.e., NRC confirmatory research, EPRI/INPO insights, etc.
4 E.
Perform self assessment of severe accident management capabilities, including:
1.
table-top mini-drills; 2.
performance of the relevant parts of the Emergency Plan; and 3.
corrective actions / recommendations resulting from the self-assessment.
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i IV.
Plant Visit Schedule / Content - The demonstration visit will occur over a one and one-half day period and consist of the following elements:
l A.
Advanced table-top mini-drill package - Prepare in accordance with plant administrative procedure and provide to NRC staff and industry participants two weeks in advance of the demonstration visit.
Note: to assure limited dissemination of the drill scenario, detailed description will not be provided until the plant visit.
1.
Drill scope and objectives 2.
Drill conduct including precautions and limitations 3.
Observer / Controller instructions, including assignments, critical roles, types of simulations, if any, etc.
4.
Player information, including general instructions and player guidelines, reference materials, procedures / guidance available 5.
Schedule of events 6.
Radiological information of importance 7.
Self assessment process, criteria and critique B.
Plant Visit -Initial Presentation 1.
Describe approach used to develop SAMG and training materials, including the systematic approach to training used.
2.
Provide key materials available for review, including plant-specific SAMG, calculational aids, target training population (how many decision makers, evaluators, and implementers, normal occupation), lesson plans and training aids, training methods (classroom, self-study, mini-drills). scheduled training time (initial and periodic retraining), administrative practices used to control SAMG materials and training.
3.
Discuss conduct of the table-top mini-drill, including scenario, initial conditions, narrative summary, sequence of events, messages and plant status information C.
Conduct table-top mini-drill - Duration of 3 to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> D.
Conduct table-top mini-drill self-assessment and critique E.
Exit discussion 1.
Discuss NRC staff observations 2.
Develop punch list of NRC staff concerns or comments, if any, requiring follow up through interactions with NEI etE 3
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DRAFT 12/18/96 1
I THE NUCLEAR ENERGY INSTITUTE in cooperation with Westinghouse Owners Group B&W Owners Group l
CE/ABB Owners Group BWR Owners Group presents Severe Accident Management Implementation Workshop March 11-13,1997 Charlotte, NC Purnose:
The purpose of the Severe Accident Implementation Workshop is to provide a forum for utility personnel to explore and discuss alternative solutions to issues that have arisen during the implementation of severe accident management guidance and training at each nuclear power station.
Background:
Each nuclear power station has committed to implementing enhancements to their emergency response capabilities to cover severe accident conditions, according to the formalindustry position on severe accident management in NEI 91-04, Revision 1 [ December 1994).
Generic materials from each of the Owners Groups, the Electric Power Research Institute (EPRI) and the Institute for Nuclear Power Operations (INPO) are available to assist utilities in developing the emergency response enhancements for severe accidents.
There are a number ofissues that must be addressed to incorporate the generic materialinto the site specific emergency response capabilities. Since this is a voluntary industry initiative, there is strong desire to: 1) maintain both the short term implementation and the long term maintenance efforts in a proper balance with other resource requirements of the plant, and 2) to the extent possible, provide a uniform approach to generic implementation issues.
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Attendees:
1 The workshop is aimed at the utility persons responsible for the development of the i
plant specific enhancements to the site emergency response organization to address l
severe accidents. Depending on the utility organization, this may include
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operations, engineering, emergency planning and training organizations. Multiple j
representative from each utility site are welcome at the workshop.
j Workshon Format:
1 j
The NEI workshop will feature several different formats to fit the particular topics i
j being discussed.
i The morning of the first day will be devoted to overall severe accident management issues and will be conducted in a lecturer - audience format with time at the end of i
each topic for discussion.
3 l
The afternoon of the first day will be devoted to severe accident management I
guidance. Due to the differences in guidance content and format between the PWRs i
and BWRs, separate break-out session will be held for the BWRs and the PWRs.
l These session are intended to be open discussions among all of the participants. To j
focus discussions, three to four discussion leaders (e.g., one from each Owners l
i Group) will present a brief, 5 minute summary of the experience at their plant on j
the topic for discussion and then open the discussion to all participants.
i
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The morning and afternoon of the second day will be devoted to SAMG training, validation and administration. Since the topics are generally similar for PWRs and BWRs, only one combined session will be held. The format will be the same as the afternoon of day 1 (i.e., 3 to 4 discussion leaders on each topic).
The morning of the third day will focus on self assessment, including what should be included in a severe accident management table-top drill. A short wrap up discussion will occur prior to the conclusion of the workshop. Again, the format will be the same as the afternoon of day 1 (i.e., 3 to 4 discussion leaders on each topic).
+-r=
PRELIMINARY AGENDA Day 1 Morning: Generic Activities Status Report TIME TOPIC PRESENTER 8:30 a.m.
Opening Remarks NEI 8:45 a.m.
Severe Accident Management: Past, Present and Future an NEI NEI Perspective 9:30 a.m.
NRC Expectations and Perspective on Severe Accident Management NRC 10:00 a.m.
Break 10:30 a.m.
INPO's Role in SAMG INPO 11:00 a.m.
WOG SAMG Scensrio Templates WOG 11:30 a.m.
B&WOG Computer Based Training B&WOG 12:00 p.m.
LUNCH Day 1 Afternoon: Plant Specific Guidance Development (Separate PWR and BWR sessions) 1:30 p.m.
PRA Interface PWR and PWR Utility Reps This session focuses on discussion of the methods used to assure that the results of the plant specific Probabilistic Risk Assessment (PRA) or the Individual Plant Examination (IPE) are reflected in the plant's severe accident management guidance. Specific IPE insights and lessons learned will also be discussed.
2:30 p.m.
BREAK 3:00 p.m.
Interface with E-Plan PWR and BWR utility reps This session focuses on discussion of the process used to assure that the severe accident management guidance is properly interfaced with the plant's Site Emergency Plan. Included in the discussion will be personnel responsibilities, physicallocations, access to plant status information and any special needs identified. Lessons learned will also be discussed.
4:00 p.m.
Plant Approvals PWR and BWR utility reps This session focuses on the method used to finalize the SAMG and place it in the Emergency Response Organization documents. The discussion will focus on the process used to develop and finalize the SAMG including the need for 50.59 reviews, etc.
5:00 p.m.
ADJOURN J
i Day 2: SAMG Training and Validation (Cornbined BWR /PWR session)
TIME TOPIC PRESENTER 8:00 a.m.
Summary ofprevious day's breakout sessions NEl 8:30 a.m.
Initial Training Format PWR and BWR utility reps This session focuses on the type of training materials (classroom, self.
study, computer based, etc.) developed and the process for identifying the scope and depth ofinitial training to be received by the various members of the Emergency Response Organization staff. Included in this session will be a discussion of where training materials were derived.
9:45 a.m.
BREAK 10:15 a.m.
Refresher Training Format PWR and BWR utility reps This session focuses on the type of training, frequency of training, and depth of training to be received by various members of the plant Emergency Response Organization staff.
11:15 a.m.
SAMG Validation -- Type of validation PWR and BWR utility reps This session will focus on the type, scope and depth of any guideline validation efforts that were carried out for the severe accident guidance.
12:00 p.m.
LUNCH 1:30 p.m.
SAMG Validation -- Validation Lessons Learned This session will focus on the lessons learned from the severe accident validation efforts, including those applicable to the design and conduct of periodic table top drills.
3:00 p.m.
BREAK 3:30 p.m.
SAMG Administration PWR and BWR utility reps This session will focus on administrative directions and controls put in place by a licensee to assure that SAMG materials are appropriately maintained. For example, which plant organization has overall responsibility, who conducts reviews of revised materials, how often are table-top drills conducted, participants, etc.
4:30 p.m.
ADJOURN
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a Day 3:
SelfAssessment and Wrap Up (Combined BWR/PWR session)
TIME TOPIC
_ PRESENTER _
8:00 a.m.
SelfAssessment Plans PWR and BWR utility reps This session will focus on the overall method to be used at plant sites to conduct the self assessments required by NEl 9104, Rev.1.
Included in these discussions will be frequency and scope of the self 1
assessments.
4 9:30 a.m.
BREAK 1
10:00 a.m.
SelfAssessment Criteria PWR and BWR utility reps This session will focus on the method and the criteria that is to be used to judge the table top drill performance and how the criteria translate into possible remedial actions. Since most of the severe accident management decisions cannot be judged on a binary (right vs.
wrong) mode, the criteria must focus on overall process used to arrive at decisions as opposed to the actual decisions reached.
11:30 a.m.
Summary Session PWR and BWR utility reps 12:00 p.m.
ADJOURN WORKSHOP
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NEI Project No. 689 1
cc:
Mr. Ralph Beedle Mr. Thomas Tipton, Vice President Senior Vice President Operations and Chief Nuclear Officer Nuclear Energy Institute Nuclear Energy Institute Suite 400 4
Suite 400 1776 I Street, NW 1776 I Street, NW Washinton, DC 20006-3708 Washington', DC 20006-3708 Mr. Alex Marion, Director Mr. Jim Davis, Director Programs Operations Nuclear Energy Institute Nuclear Energy Institute Suite 400 Suite 400 1776 I Street, NW 1776 I Street, NW Washington, DC 20006-3708 Washington, DC 20006-3708 Mr. David Modeen, Director Ms. Lynnette Hendricks, Director Engineering Plant Support Nuclear Energy Institute Nuclear Energy Institute Suite 400 Suite 400 1776 I Street, NW 1776 I Street, NW Washington, DC 20006-3708 Washington, DC 20006-3708 Mr. Anthony Pietrangelo, Director Licensing Nuclear Energy Institute Suite 400 1776 I Street, NW Washington, DC 20006-3708 Mr. Ronald Simard, Director Advanced Technology Nuclear Energy Institute Suite 400 1776 I Street, NW Washington, DC 20006-3708 Mr. Nicholas J. Liparulo, Manager Nuclear Safety and Regulatory Activities Nuclear and Advanced Technology Division Westinghouse Electric Corporation P.O. Box 355 Pittsburgh, Pennsylvania 15230