ML20149L832
| ML20149L832 | |
| Person / Time | |
|---|---|
| Issue date: | 11/06/1996 |
| From: | Wang E NRC (Affiliation Not Assigned) |
| To: | Matthews D NRC (Affiliation Not Assigned) |
| References | |
| NUDOCS 9611190019 | |
| Download: ML20149L832 (46) | |
Text
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UNITED STATES
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.j NUCLEAR REGULATORY COMMISSION ~
2 WASHINGTON, D.C. 20666 0001 November 6, 1996 MEMORANDUM TO:
David B. Matthews, Chief i
i Generic Issues and Environmental
}
Projects Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation i
FROM:
Egan Y. Wang, Reactor System Engineer -
Generic Issues and Environmental
([
i Projects Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation
SUBJECT:
MEETING SUPMARY OF OCTOBER 24, 1996, WESTINGHOUSE OWNERS i
GROUP AND NRC INTERFACE MEETING i
On October 24,.1996, representatives of the Westinghouse Owners Group (WOG) met with representatives of the Nuclear Regulatory Commission (NRC). The purpose of this interface meeting was to provide opportunity for:
maintaining and improving communication channels, discussion of open issues, e
major pt-ogram activity updates, e
review NRC status of WOG submittals, input to WOG program planning and prioritization process, and
- ~
discussion of issues and concerns.
e
.Mr. T. Green made an introduction'and reviewed the meeting agenda.
Mr. V. VanderBurg discussed the incomplete rod insertion issue. He requested NRC require either rod drop testing or drag testing and review and accept proposed Bulletin 96-01 testing relaxations to limit the fuel population to be tested. 'The proposal would exclude:
- 1) Westinghouse fuel with intermediate flow mixing (IFM) & Non-Westinghouse fuel with IFNs which are shown to provide additional fuel assembly stiffness, and 2) 12 foot fuel with burnup less than
'40,000 MWO/MTU. He indicated that the slides at the recent water reactor safety meeting presented by NRC staff conflict with the preliminary Westinghouse root cause conclusions of incomplete rod insertions.
Mr. VanderBurg also discussed the expanded core operating limits-report (COLR)
. issue. Feedback from NRC/ Westinghouse meeting. held on June 13, 1996 was that NRC was placing "new initiatives" "on hold" until'a lessons learned occurs for
/ /
Millstone and Maine Yankee. He indicated that the WOG is awaiting NRC review and approval'of WCAP-14483 topical report. Until then, utilities will continue to submit cycle-specific Technical Specification changes.
$3 On the issue of anticipated transient without scram (ATWS), Mr. VanderBurg A -t 4 UA%)e y j /f 4 NCTifA ) @L 9611190019 961106 PDR TOPRP E Sy 1
o stated that the WOG has submitted topical reports for NRC's review and responded to staff's request for additional information (RAI).
He requested a meeting be arranged between NRC staff and WOG representatives to discuss the review findings and to establish appropriate actions needed to resolve open items and obtain NRC approval.
Mr. J. Stringfellow briefly discussed the boron credit in spent fuel pool issue. He requested NRC expedite issuance of the safety evaluation report (SER). The staff indicated that the Committee To Review Generic Requirements' (CRGR) comments have been incorporated, and the SER is near completion.
Mr. R. Cockrel discussed probabilistic risk analysis applications. Specific topics that were discussed in the presentation include: Risk-Informed Inservice Testing, Risk-Informed Inservice Inspection, and Technical Specification Instrumentation Chapter Optimization Program.
Mr. R. Newton discussed the Westinghouse DB and DS series circuit breaker failures issue. Most discussion on this topic was concentrated on the DS breakers since the DS breakers are more susceptible to failure than the DB breakers. To address the concern, the WOG has initiated a member utilities survey which is to be completed in the next few weeks. Mr. Newton indicated that the WOG is going to look at the effectiveness of licensees' maintenance program. Staff raised concerns that since these types of breakers are not l
tested in 31-day surveillance testing, perhaps, procedures need to be revised to include these breakers in a 31-day surveillance testing. The staff mentioned that DS/DB breakers used in both safety-related and non-safety-related applications should also be inspected to better understand the full scope of the breakers failures. The staff raised a concern that after several NRC Information Notices, the industry is still experiencing problems with these breakers. Mr. Newton indicated that crafts' skills may impact failures i
of the breakers. The WOG will followup with NEI to check if NEI has any initiatives with regard to the breakers.
l Mr. Newton also discussed the life cycle management and license renewal program. The basic objectives of the life cycle management and license renewal program are to develop a cost-effective approach to license renewal, assist plants with life cycle management, and recognize and utilize t
maintenance rule activities which are similar to license renewal rule requirements. He also discussed current WOG activities in the life cycle management and license renewal program areas. The WOG is in the process of developing generic technical reports (GTRs) to aid in identifying what is
" acceptable and sufficient," and to provide a reference for individual utilitics for their license renewal applications as a basis for acceptable t
There was a brief discussion about missile shield removal issue. Staff indicated that a topical report is needed before the staff can begin the review.
Licensees can refer to the SER written for other licensees, after the SER has been approved by the NRC.
A discussion of the priority list for WOG topical reports submitted to NRC for review was held. The staff indicated that NRC is working on an integrated priority list including reports from other vendors and owners groups. The staff requested the WOG reprioritize the list since 11 of 15 submitted reports
l were ranked high priority. The WOG requested NRC to provide more detailed guidance as how to prioritize the reports. NRC staff indicated that other considerations may include safety impact, number of utilities, and economical benefits.
The staff discussed the status of severe accident management issue. The staff indicated that generic guidelines are issued. The Temporary Instruction (TI) is not ready for release; the long term plan is using TI as a guideline for inspection of individual plants.
At the end of the meeting, NRC staff reviewed the action items resulted from this management meeting. They are listed as follows:
NRC is to arrange a meeting between the staff and WOG representatives on the issue of incomplete rod insertion. The objectives of this meeting are to resolve the disagreement between staff and WOG representatives and ensure understanding between the parties.
NRC is to arrange telephone conference with WOG representatives followed by meeting on the subject of ATWS. The objective is to resolve any differences in opinions on the subject and establish appropriate actions to resolve open items.
NRC is to provide the WOG with more guidance on the topical report priority list.
The WOG is to resubmit the list (with more detailed ranking information) after re-prioritization. After receiving the revised priority list from the WOG, NRC will begin to work out an integrated priority list that includes topical reports from other vendors and owners groups.
The WOG is to complete the survey on DS and DB series breakers.
Telephone conference will be set up to discuss the findings from the survey. provides a list of meeting attendees. Attachment 2 is the presentation material.
Attachments: As stated cc w/att:
see next page t
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were ranked high priority. The WOG requested NRC to provide more detailed guidance as how to prioritize the reports.
NRC staff indicated that other
~
considerations may include safety impact, number of utilities, and economical benefits.
The staff discussed the status of severe accident management issue. The staff indicated that generic guidelines are issued. The Temporary Instruction (TI) is not ready for release; the long term plan is using TI as a guideline for 1
inspection of individual plants.
i At the end of the meeting, NRC staff reviewed the action items resulted from i
this management meeting. They are listed as follows:
NRC is to arrange a meeting between the staff and WOG representatives on the issue of incomplete rod insertion. The objectives of this meeting j
are to resolve the disagreement between staff and WOG representatives and ensure understanding between the parties.
NRC is to arrange telephone conference with WOG representatives followed by meeting on the subject of ATWS. The objective is to resolve any differences in opinions on the subject and establish appropriate actions to resolve open items.
i NRC is to provide the WOG with more guidance on the topical report priority list. The WOG is to resubmit the list (with more detailed ranking information) after re-prioritization. After receiving the revised priority list from the W0G, NRC will begin to work out an integrated priority list that includes topical reports from other vendors and owners groups.
The WOG is to complete the survey on DS and DB series breakers.
Telephone conference will be set up to discuss the findings from the survey. provides a list of meeting attendees. Attachment 2 is the presentation material.
Attachments: As stated cc w/att:
see next page Document name: 102496MT. SUM
//
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DATE 11/ 4-/96 11/ /96 11/(//96 11/h/96 11/b/96 OFFICIAL RECORD COPY
cc:
Mr. Nicholas Liparulo Wastinghouse Electric Corporation PO Box 355 Pittsburgh, PA 15230-0355
~ Mr. Hank Sepp Westinghouse Electric Corporation PO Box 355 Pittsburgh, PA 15230-0355 Mr. Andrew Drake, WOG Project Manager Westinghouse Electric Corporation PO Box 355 Pittsburgh, PA 15230-0355 i
f
l NRC/WOG INTERFACE MEETING LIST OF ATTENDEES Oct 24, 1996 18t!E ORGANIZATION Thadani, Ashok NRC/NRR Virgilio, Martin NRC/NRR/DSSA Sheron, Brian NRC/ADT Lainas, Gus NRC/NRR/DE Wessman, Richard NRC/NRR/DE Drake, Andrew WOG Cockrel, Bob TU Electric Newton, Roger WEPC0 VanderBurg, Vance WOG Liberatori, Louis WOG Green, Tom OG i
Couture, Robert WOG i
Stringfellow, Jack WOG Mathews, Larry WOG Jacobs, Karl NYPA Binger, Sam WOG Liparulo, Nick WOG Flack, John NRC/NRR/DSSA Matthews, David NRC/NRR/DRPM Architzel, Ralph NRC/NRR/DRPM Gill, Paul NRC/NRR/DE Pal, Amar NiiC/NRR/DE Palla, Bob FRC/NRR/DSSA Wang, Egan NRC I
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DISTRIBUTION: Mtg. Summary of October 24 Meeting with Westinghouse Owners Group Dated November 6. 1996 HARD COPY Centra 12 File.
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R. Cooper, RI E. Merschoff, RII W. Alexion,'RIII J. Dyer, RIV C. Craig E. Wang OGC ACRS E-MAIL F. Miraglia A.-Thadani R. Zimmerman i
B. Sheron T. Martin G. Lainas M. Virgilio E. Jordan D. Matthews R. Wessman F. Akstulewicz R. Architzel P. Gill J. Flack A. Pal R. Palla 1
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Westinghouse Owners Group i
i WOG/NRC Information Meeting i
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1 October 24,1996 i
i Rockville, MD i
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s WESTINGHOUSE OWNERS GROUP
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WOG/NRC INFORMATION MEETING October 24,1996 1.
INTRODUCTION l
O Meeting Purpose 7
WOG/NRC Information Meetings Implemented in 1992 Interface Meetings Provide o
Maintained and improved communication channels
- t o
Discussion of open issues o
Major program activity updates i
o Discussion of issues / concerns o
Review NRC status of WOG submittals o
Input to WOG program planning and prioritization process l
4 O
Agenda Review l
O 1996 WOG Steering Committee 4
e i
REV.O w
WESTINGHOUSE OWNERS GROUP WOG/NRC INFORMATION MEETING AGENDA October 24,19% : 1:00 PM - 4:00 PM Agenda 1:00 PM 1.
INTRODUCTION T. Green, WOG Chairman Georgia Power Company o Meeting Purpose o Agenda Review o 1996 WOG Steering Committee 1:15 AM - 11. WOG PRESENTATIONS o Incomplete RCCA Insertion -
V. VanderBurg, Analysis S/C Chairman American Electric Power o COLR Enhancements o ATWS o Boron Credit in Spent Fuel Pool J. Stringfellow, Licensing S/C Chairman Southern Nuclear o PRA Applications R. Cockrel, Systems & Equipment Engineering S/C Chairman TU Electric o DB/DS Breaker issue R. Newton, RRG/lRG Chairman Wisconsin Electric Power o Life Cycle Management / License Renewal Programs R. Newton, LCM /LR W/G Chairman 2:45 PM - 111.
DISCUSSION T. Greene o NRC Feedback on SAM Guideline implementation NRC
. 3:30 PM IV.
REVIEW WOG NRC SUBMITTALS T. Greene o Priority of WOG Submittals o Future Planned WCAP Submittals.
4:00 PM V.NLC NRC o Action item Review o Comments / Suggestion 4:30 PM VI.
. CLOSING COMMENTS T. Greene waan.ww
Westinghouse Owners Group Steering Committee - 1996 CHAIRMAN EAC CHAIRMAN Tom Greene Ted McMeekin GEORGIA POWER COMPANY DUKE POWER (205) 992-7103 (704) 875-4800 EAC VICE CHAIRMAN RRG/lRG UHAlilMAN ~
VICE CHAIRMAN Ted Cloninger Lou Uberatori ilOUSTOtt LIGilittlG & POWER Roger Newton COtlSOLIDATED EDISOrg (512) 972-8787 WISCOt4 SIN ELECTRIC POWER RRG/lRG Vice Cterman (914) 734-5676 (414) 221-2002 SW W M I#'#I433-1416
~
PROJECT MANAUEIl Ucense RenewalW/G Andrew Drake Cl{ AIRMAN WESTil1Gif 0VSE Roger tiewton (WEP)
I' (414) 221-2002 MATERIALS S/C SYSTEMS & EQUIPMENT ANALYSIS S/C OPERATIONS S/C UCENSING S/C CHAIRMAN ENGINEERING S/C CHAIRMAN CilAIRMAN CHAIRMAN CHAIRMAN Larry Mathews (SNC)
Dob Cockrel(TU E)
Vance VanderBurg (AEP)
Robert Couture (NEU)
Jack Stringfellow (SNC)
(205) 992-7729 (817) 897-6246 (616) 697-5142 (603) 474-9521 13389 (205) 992-1037 Vice Chairman Vice Chairman Vice Chairman Vice Chairman Vice Chairman T.R. Satyan-Sharma KarlJacobs Rick Kohrt (WEP)
Charles Sawyer (Duke)
TDB (616) 697-5143 (914) 681-626; (414) 22 t-3964 (704) 382-3331 Risk Based W/G I&C W/G Training W/G Shutdown issues W/G CHAIRMAN CHAIRMAN CHAIRMAN CHAIRMAN Duncan Brewer (Duke)
MAe Murray (HL&P)
Frank Maciuska (RG&E)
Mike Millen (WEP)
(704) 382-7409 (512) 972-8164 (716) 771-6651 (414) 221-3372 STR_ORG2.DRW Pesse i It) 96 l
WESTINGHOUSE OWNERS GROUP WOG/NRC INFORMATION MEETING October 24,1996 ll.
WOG PRESENTATIONS O
Incomplete RCCA Insertion WOG Activities o
Monitor Results Of Individual Licensee Bulletin 96-01 Test Results W/WOG/NRC May 15,1996 Meeting o
Coordinate WOG Requests For Bulletin 96-01 Testing Relaxations NRC/WOG August 13,1996 Meeting WOG Letter OG-96-069 To NRC WOG Letter OG-96-090 To NRC i
WOG Letter On IFM Fuel - Forecast 11/22 i
o Monitor The Westinghouse Root Cause Efforts Attendance At W/NRC Meetings Participation in Weekly NRC/W Telecons o
RPI Operational Issues
WESTINGHOUSE OWNERS GROUP WOG/NRC INFORMATION MEETING October 24,1996 l
O Incomplete RCCA Insertion continued l
WOG Request Of NRC o
Review And Acceptance Of Bulletin 96-01 Testing Relaxations Limit The Fuel Population To Be Tested To Exclude I
o Westinghouse Fuel With IFMs &
Non-Westinghouse Fuel With IFMs Which Are Shown To Provide Additional Fuel Assembly Stiffness l
o 12 Foot Fuel With Burnup Less Than 40,000 MWD /MTU Require Either Rod Drop Testing Or Drag Testing
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WESTINGHOUSE OWNERS GROUP WOG/NRC INFORMATION MEETING October 24,1996 0
Incomplete RCCA Insertion continued WOG Request of NRC O
Root Cause Efforts 7
Review And Consider Conclusions From Westinghouse Root Cause Determination Efforts o
IFM Plants Not Effected o
Non-IFM 12 Foot Plants With T Core Hot <615F -
Not Effected o
Non-IFM 12 Foot Plants With T Core Hot > 615F -
Need To Consider Other Criteria Power History Burnup
{
Recent Slide Presented At WRSM-On Monday Presented i
NRC " Thoughts" That Are in Conflict With The Preliminary Westinghouse Root Cause Conclusions l
l
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WESTINGHOUSE OWNERS GROUP WOG/NRC INFORMATION MEETING i
October 24,1996 i
i O
Incomplete RCCA Insertion continued Recent NRC Responses To Individual Licensee Requests j
~ For Bulletin 96-01 Testing Relaxations o
Point Beach
^
Drag Test Fuel Assemblies With Burnup Between 20,000 MWD /MTU and 40,000 MWD /MTU l'
o Vogtle Drag Test Fuel Assemblies i
o First Cycle Fuel Assemblies With Burnup Greater Than 29,500 MWD /MTU o
Second Cycle Fuel Assemblies With Burnup
.Between 43,000 And 49,000 MWD /MTU l
o Callaway EOC Rod Drop Testing o
Recoil Data Not Required i
Drag Testing i
o Rodded Assemblies in Cycle 8 Which Will Be Rodded in Cycle 9 l-o Fuel Assemblies With Burnups Exceeding
]
30,000 MWD /MTU
i WESTINGHOUSE OWNERS GROUP WOG/NRC INFORMATION MEETING October 24,1996 O
Expanded COLR / Expanded COLR.WCAP' Review Objectives:
1 o
To justify moving selected Tech Specs that are j
dependent upon the full power RCS operating i
conditions to th' Core Operating Limits Report j
e (COLR) thereby eliminating / minimizing NRC reviews due to cycle-specific changes in steam generator tube plugging, FAH, Tavg, etc.
Selected Tech Specs:
o WCAP-14483 justifies moving those Tech Specs that j
are dependent on the full power RCS operating conditions to the Core Operating Limits Report.
DNB Parameter Tech Spec (3.2.5 -0452)
OTDT/OPDT numerical Tech-Specs Replace Reactor Core Safety Limits (Figure 2.1 0452) o Each of the above items has been approved on'a plant specific basis by the NRC
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i WESTINGHOUSE OWNERS GROUP i
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WOG/NRC INFORMATION MEETING October 24,1996 i
O Expanded COLR / Expanded COLR WCAP Review continueo Status o
WOG met with the NRC (Larry Phillips, Chris Grimes, etc.) April 7,1995 and September 27,1995 to j
discuss concept. Feedback was favorable.
o WCAP-14483 submitted to the NRC for review and approval December 1,1995 o
Wisconsin Electric submitted Tech Spec
)
changes for the Point Beach units referencing WCAP-14483 on Dec 13,1995 requesting approval by March and then June of 1996.
o Feedback from NRC/ Westinghouse meeting held June 13,1996 was that the NRC was placing "new initiatives" "on-hold" until a lessons learned occurs for Millstone and Maine Yankee.
2 i
o WOG awaiting NRC review and approval of WCAP-14483. Until then, utilities will continue to submit cycle-specific Tech Spec changes.
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J
l WESTINGHOUSE OWNERS GROUP I
WOG/NRC INFORMATION MEETING October 24,1996 O
ATWS Rule - 10CFR50.62 Benefits of ATWS Rule Administration Process for W PWRs o
Provides a structured basis for assessing compliance with a prescriptive rule for the non-design basis ATWS events i
i o
Provides a method of assessing changes in plant conditions important to the consequences of an ATWS event using a deterministic safety analyses basis combined with PRA o
Maintains conservatism of ATWS Rule basis equating the_RCS pressure limit of 3200 psig with core damage i
o
'Provides a method for demonstrating ~ continued i
compliance with basis for ATWS Rule for plants l
currently licensed with part-power PMTC o
Eliminates ambiguous probabilistic arguments imbedded in deterministic analysis basis for ATWS j
rule (e.g., basis for arbitrary 5% of cycle unfavorable MTC) while ensuring that.the overall objective of-ATWS Rule is maintained.
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WOG/NRC INFORMATION MEETING i
October 24,1996 i
O ATWS Rule - 10CFR50.62 continued NRC Review of WCAP-11992 i
o W/WOG ATWS Rule Administration' Process (WCAP-11992) used in 1988 " Assessment of Compliance c
with ATWS Rule Basis for W PWRs" (WCAP-11993) f o
The W/WOG program was presented to the ACRS on l
l two separate occasions l
Feb.19,1988 Subcommittee meeting on Core
[
Performance & Scram System Reliability
'h April 21,1989 Instrumentation- & Control Systems Subcommittee on ATWS Rule Implementation o
25 copies of WCAP-11993 were~provided to NRC for information purposes on March 1,1989 o.
WCAP-11992 ATWS Rule Administration Process PRA model used and referenced in numerous plant IPEs in response to GL 88-20 o
WCAP-11992 formally submitted to NRC for review and approval by WOG on May 2,1995, after being informed by NRC that process was not recognized when referenced in response to plant specific LAR for PMTC (Byron /Br'aidwood units)
WESTINGHOUSE OWNERS. GROUP WOG/NRC INFORMATION MEETING October 24,1996 0
-ATWS Rule - 10CFR50.62 continuee NRC Review of WCAP-11992 (continued) o W/WOG formally responded to NRC RAls in Nov.
1995 and again in March 1996 o
NRC Technical Review and internal NRC management briefings complete o
informal indications from NRC reviewers indicate that while PRA model looks reasonable, policy issues exist o
Need to schedule meeting with NRC and W/WOG to discuss review findings and policy concerns and establish appropriate actions needed to resolve open items and obtain NRC approval 6
0 9
I l
9 WESTINGHOUSE OWNERS GROUP 4-l' WOG/NRC INFORMATION MEETING October 24,1996 4
0-Boron Credit in Spent Fuel Pool Received comments from CRGR on criticality anaylis methodology topical l
Responded to those comments by OG letters dated, October 18 & 23, 1996.
Request NRC expedite issuance of SER
WESTINGHOUSE OWNERS GROUP WOG/NRC INFORMATION MEETING October 24,1996 O
PRA Applications Risk-informed Inservice Testing o
Two WOG WCAPs submitted for NRC review in September 96 WCAP-14358, Supplement 1, " Westinghouse Owners Group Application of Risk-based Methods to Check Valve Inservice Testing Condition Monitoring Program Topical Report,"
and WCAP-14358, " Application of Risk-based Methods to Check Valve Inservice Testing Demonstration Project" WCAP-14571, " Westinghouse Owners Group Application of Risk-based Methods to Pump Inservice Testing Demonstration Project" o
Process includes:
Risk-ranking of components (including expert panel and incorporation of deterministic insights) and extension of test intervals based on performance A process to identify the predominant component failure modes and causes and to evaluate the effectiveness of test methods and test intervals at identifying conditions that are precursors to failure
l-l WESTINGHOUSE OWNERS GROUP l'
WOG/NRC INFORMATION MEETING i
October 24,1996 i
O PRA - Applications continued Risk-informed Inservice Testing continued i
j j
o Consistent with the Electric Power Research Institute (EPRI) PSA Applications Guide, ASME Research 1
report on risk-based IST and NEl Risk-informed IST draft Guideline
}
Supports the NRC in the development of the o
regulatory guide'and standard review plan on risk-informed inservice testing, particularly with regard to l
effective test strategies for high safety-significant i
components Risk-informed Inservice Inspection l
o WOG WCAP submitted for NRC review in April 96 via NEl WCAP-14572, " Westinghouse Owners Group Application of Risk-based Methods to Piping Inservice Inspection Topical Report"
[
o Process includes:
c Risk-ranking of piping segments based on PSA insights, structural reliability insights, operational experience and engineering I
judgement 4
1-Methods to perform expert panel review I
incorporating deterministic insights 4
Guidance provided on selection of inspection locations and methods m
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WESTINGHOUSE OWNERS GROUP WOG/NRC INFORMATION MEETING October 24,1996 O
PRA Applications continued Risk-informed Inservice inspection continued o
Currently performing study at Surry Unit 1 Gaining additional insights and process enhancements as part of program Working with ASME Research in benchmarking efforts with NRC o
Supports the NRC in the development of the i
regulatory guide and standard review plan on risk-informed inservice inspection o
Awaiting NRC RAls on WCAP Technical Specification Instrumentation Chapter Optimization Program o
WCAP-14333-P submitted for NRC review on June 20,1995 (Ginna lead plant) o RAls provided to RG&E on June 28,1996 l
I
WESTINGHOUSE OWNERS GROUP WOG/NRC INFORMATION MEETING October 24,1996 O
PRA Applications continuee Technical Specification Instrumentation Chapter Optimization Program continued o
RAI #18 addresses NRC's use of the three tiered approach in reviewing Tech Spec modifications. RAI
- 18b requests:
Explain how you are going to address the issue of configuration and control, consistent with the Maintenance Rule, i.e., evaluate the impact of maintenance activities on plant configurations.
Please discuss the programs for configuration management in.W__ plants to address assessment of risk impacts prior to entry into the RPS and ESFAS bypass time or AOT, being proposed for extension.
o issue:
l Based on Oct.15 discussions with NRC staff, WOG understands that NRC desires some form of risk informed decision making with respect to configuration control.
WOG position is that risk informed evaluations to meet the Maintenance Rule requirements are acceptable o
CEOG Responses - Perform proceduralized risk in'ormed evaluation of plant configuration by either PRA derived risk matrices or on-line risk calculations.
WESTINGHOUSE OWNERS GROUP WOG/NRC INFORMATION MEETING October 24,1996 O
PRA Applications continued Other WOG Risk-Based Programs of Interest to the NRC o
Accumulator Outage Time Relaxation Program Develop approach for justifying changes to AOTs Accumulator initial application Depending on results, additional applications in the future Discussed at the NRC/WOG Licensing S/C Risk-Based Program Initiatives Meeting (10/15/96) o Tech Spec RT and ESF Logic and Reactor Trip-Breaker AOT and STI Relaxations Provide justification for extending STis for logic cabinets, master relays, and reactor trip breakers, and AOTs for reactor trip breakers Follow-on program for WCAP-10271 and WCAP-14333
4 IU WESTINGHOUSE OWNERS GROUP i
WOG/NRC INFORMATION MEETING i
October 24,1996 i
O PRA Applications continueo 1
4 5
Other WOG Risk-Based Programs of Interest to the NRC -
continued I
o Tech Spec RT and ESF Logic and Reactor Trip Breaker AOT and STI Relaxations Discussed at the NRC/WOG Licensing S/C Risk-Based Program Initiatives Meeting (10/15/96) i-o PSA Model Methods and Results Comparison Program Detailed examination and comparison of the most recent plant specific PSA models and results for Westinghouse plants Developing electronic database Discussion within WOG concerning sharing of information with the NRC
WESTINGHOUSE OWNERS GROUP e
WOG/NRC INFORMATION MEETING October 24,1996 O
DS Breaker issue l
Background
o NRC IN 96-44 " Failure of Reactor Trip Breaker from Cracking of Phenolic Material in Secondary Contact Assembly" o
Description of issue:
Cracking or chipping of secondary contact assembly may impact operation of breaker Postulated root cause: mishandling or overtorquing i
NRC Request to the WOG o
Assist in assessing scope of problem by collecting information o
Respond to specific questions regarding torque valuer, testing and inspection, failures WOG Program o
Survey member utilities l
o Reduce data from survey on inspections and failures o
Develop responses to specific questions o
Participate in Telecon with NRC
~'
WESTINGHOUSE OWNERS GROUP WOG/NRC INFORMATION MEETING October 24,1996 O
DS Breaker issue continued Current Status o
DS Breaker Survey issued to membership October 4, 1996 (Requested procedure info for DB breakers also) o Responses to date: 20 sites (34 plants)
Preliminary Results o
All plants responding have formal procedures in use for both DS and DB Series Breakers o
Twenty (20) contact blocks have been replaced during the last 10 years for DS Breakers o
All broken / chipped blocks found during maintenance inspection or a direct result of handling o
Root Cause (when determined): handling or i
overtorquing o
Breakers in service: ~ 9000 Action o
Complete Su.*,ey o
Telecon with NRC (Respond to six questions)
t WESTINGHOUSE OWNERS GROUP c.
WOG/NRC INFORMATiON MEETING October 24,1996 O
Life Cycle Management / License Renewal Program Endorsed by WOG Executive Advisory Committee (January,1993)
Program Authorized at the WOG - February 1993 General Session
$8,225K Program (revised down from an original
$8,740K) 5 Year Duration (1993-1997)
Basic Objectives:
o Develop a Cost-effective Approach to License Renewal o
Assist Plants with Life Cycle Management i
o Recognize and Utilize Maintenance Rule Activities which are Similar to License Renewal Rule Requirements
WESTINGHOUSE OWNERS GROUP WOG/NRC INFORMATION MEETING October 24,1996 O
Life Cycle Management / License Renewal Program continued 4
Currently Six Major Areas of Activity l
1.
Generic Technical Reports (GTRs) i i
Template: Standard Organization and Review Criteria j
i Aging Management Program " Attributes" Expert Panel Review (where needed)
Submittal to NRC, RAI response and meetings 2.
WOG Expectations for Generic Technical Reports Purpose of GTR Intended Utility Use Encourage NRC Review of Generic Topical Reports Expected Outcomes from NRC Review 3.
Program Key Issues Open Technical Issues from Industry Reports for LR SECY-96-080 - ASME Sections XI, IWE, IWL Review Fee Waiver Request
WESTINGHOUSE OWNERS GROUP n
WOG/NRC INFORMATION MEETING October 24,1996 O
Life Cycle Management / License Renewal Program continueo
. Currently Six Major Areas of Activity continued 4.
Life Cycle Management Structural Monitoring and Buried Commodities; implementation and Field Guides issued to WOG Systems Engineer Walkdown Manual being developed Cable and Connectors next topic 5.
Generic LR Implementation Plan Support for NEl implementation guideline development j
Generic procedures being developed for WOG based on NEl guideline 6.
Support for Implementing Plant Efforts Plant Life Assessment Program Subgroup Phase 1 complete Phase 2 in progress
o WESTINGHOUSE OWNERS GROUP WOG/NRC INFORMATION MEETING October 24,1996 O
Life Cycle Management / License Renewal Program continued WOG Expectations for Generic Technical Reports o
Purpose of GTR LR Rule issued, but review criteria unknown.
GTRs will help identified what is " acceptable and sufficient" o
Intended Utility Use Individual utilities will reference GTRs within th' air LR Applications as a basis for acceptable Aging Management Programs which
' demonstrate the effects of aging are being managed o
Encourage NRC Review of Generic Topical Reports NRC review of generic topical reports are essential to establish a standard for acceptance NRC review of GENERIC topical reports provide for economical implementation of LR Rule for both the industry and NRC
WESTINGHOUSE OWNERS GROUP
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WOG/NRC INFORMATION MEETING October 24,1996 O
Life Cycle Management / License Renewal Program continuee WOG Expectations for Generic Technical Reports continued o
Expected Outcomes from NRC Review Agree with GTR Scope Agree with identified aging effects, TLAAs and the evaluation of them o
Aging effects needing management o
Aging effects NOT needing management Approve the aging management program attributes within the GTRs j
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0 WESTINGHOUSE OWNERS GROUP WOG/NRC INFORMATION MEETING October 24,1996 LIFE CYCLE MANAGEMENT / LICENSE RENEWAL GENERIC TECHNICAL REPORTS (GTRs) 5 GTRs have been completed, 6 GTRs are in final draft form, & 4 additional GTRs scheduled to begin 10/96 (15 GTRs total)
NRC GIB Comoletion SUBMITTAL Groun 1 Heat Exchanger 3/95 N/A RHR System 3/95 N/A RCS Supports, Rev 1 3/95 3/96 Grouo 2.
Pressurizer 7/96 7/96 Class 1 Piping 8/96 8/96 Containments 10/96 10/96-RV Internals 11/96 11/96 Rx Vessel 10/96 N/S Grouc 3 Class 1 Structures 10/96 TBD Steam Generator 10/96 TBD Valve Bodies / Piping 10/96 N/S Groun 4 Electrical Distrib & Structures 5/97*
TBD Cables & Connectors 5/97*
TBD Pressure Vessels 5/97*
TBD Seismic / Safety Supports 5/97*
- = Estimate N/S = Not Submit
l WESTINGHOUSE OWNERS GROUP s
WOG/NRC INFORMATION MEETING October 24,1996 O
Life Cycle Management / License Renewal continued 1
Program Key Issues o
Open technical issues from the Industry Reports - EPRI efforts in progress to establish industry positions for:
Fatigue Thermal Aging of Cast Austenitic Stainless Steel Alloy 600 Irradiation Assisted Stress Corrosion Cracking Stress Relaxation Neutron irradiation Embrittlement of Reactor Vessel ISE requirements for Containment Structures Class 1 small bore piping o
SECY-96-080, Incorporation of ASME Section XI, IWE /
IWL Class MC/CC Structures ISE Requirements in 10 CFR 50.55a issued 5/3/96 50.55A incorporation of IWE / IWL effective September 9,1996 Industry review meeting held 9/10/96 Containment GTR under revision o
Review Fee Waiver Request Submitted 8/28/96 WOG program benefits industry and NRC
I e
d WESTINGHOUSE OWNERS GROUP
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WOG/NRC INFORMATION MEETING October 24,1996 O
Life Cycle Management / License Renewal Program continued Life Cycle Management o
4-Level Model Developed to Describe LCM Implementation Component System Plant Corporate o
Specific Topics identified Where Guidance Needed Initial list contained 14 items Structural Monitoring and Buried Commodities were top priority Ad Hoc Committee established to pursue LCM o
Guidance Materials Developed to Support Plant Implementation Implementation Guide Field Guide Workshops Videos o
System Engineer Walkdown Manual is current Topic Under Development o
Cable and Connectors is next LCM topic for i
Development
WESTINGHOUSE OWNERS GROUP WOG/NRC INFORMATION MEETING October 24,1996 O
Life Cycle Management / License Renewal Program continueo Generic License Renewal Implementation Plan o
Intended to Provide Guidance for All WOG Members o
Active WOG Support Provided for NEl Implementation Guideline, NEl 95-10 o
More Detailed "WOG Generic" Guidelines Developed:
Based on NEl Guideline Utilize information on plant-specific activities /
processes j
Basis for plant-specific procedures 4 Guidelines developed o
Scoping o
Screening o
Performing Aging Management Review o
Evaluating TLAAs and Exemptions
8 WESTINGHOUSE OWNERS GROUP WOG/NRC INFORMATION MEETING October 24,1996 O
Life Cycle Management / License Renewal Program continued Plant Life Assessment Program (PLAP) Subgroup o
Phase 1 Program Completed, November 1995 o
Phase 1 Subgroup Included 13 Utilities and Westinghouse o
Phase 1 Deliverables Were Distributed to all WOG members:
Considerations for Plant Life Extension (Corporate, Technical, non-Technical, Economic, Licensing, Major Equipment Costs)
Plant Life Assessment Pr. gram Phase 1 Questionnaire Similarities in Systems Structures and Components (based on questionnaire results; these are the basis for sharing evaluations) l Integrated Plan for Plant Life Assessment Program - Phase 2 o
Phase 2 Project Authorization and Charter Approved by WOG Subgroup members in January 1996 o
Phase 2 Subgroup Includes 11 Utilities and Westinghouse l
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s WESTINGHOUSE OWNERS GROUP i
WOG/NRC INFORMATION MEETING October 24,1996 O
Life Cycle Management / License Renewal Program continuee Plant Life Assessment Program (PLAP) Subgroup continued o
Phase 2 Initiation - January 1996 For the first 9 months of 1996, Phase 2 will support the NEl Demonstration Program for the License Renewal implementation Guideline, NEl 95-10
)
o Phase 2 Completion is scheduled for December 1997 1
1
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WESTINGHOUSE OWNERS GROUP WOG/NRC INFORMATION MEETING October 24,1996 li i
4 l
Ill.
DISCUSSION i
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NRC Feedback on SAM Guideline implementation e
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s WESTINGHOUSE OWNERS GROUP i
WOG/NRC INFORMATION MEETING October 24,1996 IV.
REVIEW WOG NRC SUBMITTALS O
Priority of WOG Submittals WOG Programs Undergo Rigorous Review Process Prior To Being Approved Programs Provide Benefits To Both WOG And NRC By:
o Addressing / Resolving Issues For Large Number Of Plants o
Generic Review Provides The Most Cost Effective Approach For Both The WOG And NRC Review Of WOG Programs Should Receive High Priority By NRC As It Allows For The Most Cost Effective Use Of Limited Resources And Impacts A Large Population Of Plants O
Future Planned WCAP Submittals i
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Table 1: WOG WCAPs Submitted to NRC Estimated WCAP #
Priority Title OG Letter Lead Plant SERDau Actions / Comments 11992' liigh -
Joint Westinghouse /WOG Program: ATWS Rule OG-95-4 i Byron 1st qtr,1996*
Administration Process hiay 2,1995 14333-P liigh Probabilistic Risk Analysis of the RPS and OG-95-51 Ginna June Will respond to RAls by cud of 14334-NP ESFAS Test Times and Completion Times June 20,1995 1996*
November,1996 14416-P fligh Westinghouse Spent Fuct Rack Criticality OG-95-62 Prairic Island 9/96*
Responded to CRGR 14417-NP Analysis hiethodology July 28,1995 comments October,1996.
144M3 liigh Generic hiethodology for Expanded Core OG-95-093 Point Beach h1 arch,1996 WOG requested SER date of Operating Limits Report December I,1995 h1 arch,1996 14535 liigh Topical Report on RCP Fly Wheci inspection Submitted by DLCo Beaver Valley Sept,1996 Received SER October,1996 Elimination on January 24,1996 liigh Reliability Assessment of Westinghouse Type TVA LAR Watts Bar Under Resiew, RAls recciscd 13877
- AR Relays Used as SSPS Slave Relays February 28,1996 September 3,1996 14422, Rev.
Iligh License Renewal Evaluation: Aging OG-96-027 Generic WCAP resubmitted h1 arch, I
h1anagement for Reactor Coolant Supports h1 arch 22,1996 1996, Responded to 2 sets of RAls 14574 High License Renewal Evaluation. Aging OG-96-052 Generic hianagement for Pressurizer July 3,1996 14486 liigh ECCS Hot Leg Recirculation Elimination for OG-96-054 Comanche Peak Westinghouse 3 and 4 Loop Design NSSS July 18,1996 14575 High License Renewal Evaluation: Aging OG-96-071 Generic hianagement for Class 1 Piping-August 28,1996
[
14358 and liigh WOG Application of Risk-Based hiethods to OG-96-078 Vogtic Vogtle submittal expected by 14358 Check Vahr IST - Class 3 non-prop.
September 5,1996 end of January,1997 Supplement 10541, Rev.
hiedium Reactor Coolant Pump Seal Performance OG-84-122 Generic No estimated WCAP not activelv being 2
Following Loss of All AC Power hiay 3,1984 SER datc resicued because final generic OG-86-206 (Rev 2) resolution ofissue is bemg December 10,1986 evahrated 14571 hiedium WOG Application of Risk-Based hiethods to OG-96-077 Shcaron liarris Lead plant submittal date TBD Pump IST - Class 3 non-prop.
September 5,1996 14181 Low Evaluation of the Potential for Diluting PWR OG-95-076 Prairie Island 2nd Qtr, NRC informed WOG on Spent Fuel Pools September 21,1995 19 %
8/27/96 they would not resiew WCAP
+ Estimated SER dates provided by NRC WCAP TBLDOCtt)
Itemedissued. October M 1996
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' Table 1: WOG WCAPs Submitted to NRC Estimated WCAP #
Priority Title OG Letter Lead Plant SER Date Actions / Comments 12476 low
' Evaluation of LOCA During Mide 3 and Mode OG-91-61 Generic No review currently ongoing, 4 Operation for Westinghouse NSSS November 27,1991 issue will eventually he resolved through the shutdown rulemaking.
+ Estimated SER dates provided by NRC
- 3 "#* *' " '
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1 Table 2: Anticipated WOG WCAP Submittals to NRC Est. Submittal Date Lead Plant Title WCAP #
Priority 11/96 Gencric 14577 liigh License Renewal Evaluation: Aging hianagement for Reactor Vessel Internals 4th quaner,1996 D.C. Cook 14696 liigh Westinghouse Owners Group Core Damage Assessment Guidance 14036 liigh Elimination of Periodic Protection Channel Response Time Tests ist quarter,1997 Farley 10/96 Generic License Renemil Evahiation: Aging Management for PWR Containment 14579 liigh Structures ist quarter,1997 TBD XXXXX liigh Relaxation of PASS Requirements (NUREG-0737) ist quarter,1997 South Texas XXXXX liigh ASICS Development Program
(
Justification for increasing Postulated Break Opening Times in Westinghouse 4th quarter,1996 Generic 14748 liigh Pressurized Water Reactors 2nd quarter,1997 TBD XXXXX liigh Accumulator AOT 3rd Quarter 1997 TBD XXXXX liigh RT & ESF Logic and Rx Trip AOT and STI I
+ Estimated SER dates provided by NRC Revoe.11somd Octolm 24. l996 WCAP_2L WPF (3)
- =.. --
WESTINGHOUSE OWNERS GROUP t
WOG/NRC INFORMATION MEETING A
October 24,1996
'V.
NRC O
Action item Review O
Comments / Suggestions 4
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3 4
1 1
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!TT WESTINGHOUSE OWNERS GROUP s:'
WOG/NRC INFORMATION MEETING I
October 24,1996 VI.
CLOSING COMMENTS I
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