ML20155G517
| ML20155G517 | |
| Person / Time | |
|---|---|
| Issue date: | 11/03/1998 |
| From: | Wen P NRC (Affiliation Not Assigned) |
| To: | Essig T NRC (Affiliation Not Assigned) |
| References | |
| PROJECT-694 NUDOCS 9811090074 | |
| Download: ML20155G517 (26) | |
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UNITED STATES s
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NUCLEAR REGULATORY COMMISSION f
WASHINGTON, D.C. 20666-0001
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November 3, 1998 MEMORANDUM FOR: Thomas H. Essig, Acting Chief Generic Issues and Environmental Projects Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation Peter C. Wen, Project Manager feb C, M FROM:
Generic issues and Environmental Projects Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation
SUBJECT:
SUMMARY
OF THE SEMIANNUAL NRR/ WESTINGHOUSE OWNERS GROUP SENIOR MANAGEMENT MEETING ON OCTOBER 27,1998 l
The subject meeting was held at the NRC offices in Rockville, Maryland, on October 27,1998, between representatives of the Westinghouse Owners Group (WOG) and the staff of the Office j
of Nuclear Reactor Regulation (NRR). The purpose of the semiannual senior management meeting is to encourage communication between NRR management and the WOG, discuss emerging issues or concerns, and present the status of NRR and WOG activities. is a list of attendees, and Attachment 2 is the WOG presentation material.
Samuel Collins, Director of NRR, gave the opening remarks in which he stressed the importance of the senior management meeting between the WOG and NRC.
The WOG began its presentation by introducing the Steering Committee members and j
discussing the formation of the WOG Executive Management Group. This group provides executive oversight and strategic planning for the WOG's activities. The WOG also described the organization of the various WOG subcommittees and the WOG's interactions with industry groups such as EPRI, NEl, INPO, and so on.
Although the WOG works on a large number of issues at any one time, it specifically addressed 10 topics at the meeting: (1) the risk informed anticipated transients without scram (ATWS) model, (2) the risk-informed policy for prior submittals, (3) the use of leak before break (LBB) for containment sump issues, (4) break opening time, (5) the status of the baffle barrel botting (BBB) program (6) the elimination of the post-accident sampling system (PASS), (7) the master g
curve, (8) the reactivity manipulation per 10 CFR 55.31(a)(5), (9) severe accident management
\\j guidelines, and (10) Year 2000 issues. These topics are discussed briefly herein, f
Risk-Informed ATWS Model: The WOG has a perception that the utaff may have changed its position on the use of the related topical report (WCAP-11992," Joint Westinghouse Owners 9lM Group / Westinghouse Program: Anticipated Transient Without Scram (ATWS) Rule Administration Process") to the application of positive moderator temperature coefficient (MTC) core. However, in a letter from Marylee M. Slosson (NRC) to Vance D. VanderBurg (WOG),
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-2 November 3, 1998 l
dated July 1,1997, the staff did not accept WOG's submittal of WCAP-11992 for licensing application. One example of the staff's concerns was that WCAP-11992 did not establish an explicit link between MTC and risk. WOG is developing e new WCAP, which is based on a risk-informed model and will address the staff's concerns as de;ineated in the previous correspondence to WOG. The revised WCAP would be a new basis for use in the positive MTC core.
The staff agreed that this issue should be reviewed expeditiously since many new fuel designs are at stake. The staff will support a meeting to be held in December 1998 to review WOG's methodology and application.
Risk-informed Policy for Prior Submittals: Recently, the staff issued the risk-informed guidelines for regulatory applications, and the WOG has used these guidelines for its recent submittal, WCAP-15059, " Risk-informed Evaluation of an Extension to Accumulator Completion Time." However, some of WOG's submittals were submitted before the issuance of the risk-informed guidelines. WOG asked the NRC staff to clarify that this new trend in applying risk-informed information should have no effect on its previous submittals. That is, its previous submittals should not have to be revised or reworked on the basis of the risk information. The staff generally agrees with this view unless a risk evaluation can add value to the report, as in' the planned new ATWS WCAP previously discussed.
Use of LBB for Containment Sumo Issues: The concern of the WOG is the generation of debris after a loss-of-coolant accident (LOCA), which has the potential of clogging the containment sump screen. The WOG discussed the position of the PWR Owners Groups on the use of LBB in connection with this issue. The WOG believes that by using LBF,, the General Design Criterion (GDC) 4 would allow WOG to exclude dynamic effects atsociated with postulated pipe ruptures in evaluating the generation of debris. The staff replied thtt it is still working on this issue, including evaluating the need for rule change, and has not forrned its position yet. The staff also informed the WOG that it is conducting a study on the potential for clogging of the containment sump screen. The study needs detailed system information on individual plant sump, ECCS, and containment designs.
The staff is currentiv wor king with NEl on these containment sump related issues.
Break Ooening Tinle.; The staff issued the Safety Evaluation Report (SER) for WCAP-14748,
" Justification for increasing Postulated Break Opening Times in Westinghouse PWRs," on October 1,1998. However, the staff limited the SER's application to the BBB program only.
The WOG requests that WCAP-14748 be reviewed for other uses, such as the determination of the many forcing functions needed in transient analyses. The staff is willing to support the WOG's request. However, the staff indicated that because of resource constraints, it could not place this item on an accelerated schedule as was done for the BBB program review. To help the staff to assign a priority for this issue, the staff requested the WOG to supply a cost-benefit analysis. Both sides agreed to have a conference call to further discuss the schedule.
1 November 3, 1998 T. Essig _
3-Status of the Baffle Barrel Boltino Procram: The WOG discussed the inspections and replacement activities on the lead 2-and 3-loop plants (Point Beach and Farley), which were closely followed up by the staff. To continue this program, the WOG requested the staff to review the topical report WCAP-15029 " Methodology for Evaluating the Acceptability of Baffle Former Bolting Distributions Under Faulted Load Conditions." The staff replied that its technical review is nearly complete.
The staff requested the WOG to provide the staff with the inspection results after WOG completes its inspections of the lead plants' activities. WOG indicated that this request can be accomplished through a technical meeting, which was projected for January 1999.
Elimination of the PASS: The requirement for the PASS in operating reactors was introduced after the TMI accident. Its purpose was to provide the operators with information on the degree of core degradation and the radioactivity release, as well as the general condition of the plant.
j The PASS was designed by various manufacturers for different licensees, but all designs had to meet the NRC requirements specified in NUREG-0737," Clarification of TMl Action Plan Requirements." The WOG indicated that it is submitting WCAP-14986, Rev.1, "WOG Post-Accident Sampling System Requirements: A Technical Basis," for staff review. The WOG is hoping that some of the PASS requirements can be eliminated on the basis of the analyses presented in the WCAP. The staff replied that it is also working on a generic letter to relax some of the PASS requirements. A conference call will be scheduled to further discuss this issue.
Master Curve: The master curve is a new approach to evaluating the fracture resistance of reactor pressure vessel steels. The industry's perception is that this technique will provice a more accurate assessment of the material's fracture resistance and remove conservatism believed to exist in the current methodology. The WOG advised NRC that it is supporting industry efforts through the Material Reliability Project (MRP). The staff replied that it is unclear how the master curve fits into the current regulatory framework because the lead plant, Kewaunee, does not need the master curve to meet the pressure thermal shock requirements.
A suggestion was made that ASME should take action on the code case to determine how to apply data acquired through master curve testing.
Reactivity Manioulation oer 10 CFR 55.31(a)(5): The regulations in 10 CFR 55.31(a)(5) require that the operator license applicant perform five significant control manipulations that affect reactivity on the actual plant. The WOG informed the staff that it is working through NEl on this issue to propose a rule change to permit reactivity manipulation on a simulator. The staff replied that the rulemaking in this area is proceeding well. The draft rule has been completed and will go through the normal rulemaking process, including seeking public comments and obtaining the Commission's approval. The staff also informed the WOG that if any licensee experiences hardship because of this requirement, the staffis welling to evaluate exemption requests.-
1 T, Essig 4
November 3, 1998 Severe Accident Manaoement Guidelines: The WOG stated that many WOG plants have developed and implemented plant-specific severe accident management guidelines (SAMGs) as part of the voluntary industry initiative on accident management. The WOG expressed the desire to close the severe accident issue as expeditiously as possible, citing the heavy consumption of resources and their little use in dealing with actual plant safety.
The question of the SAMG audit was discussed during the meeting. The staff has proposed to perform audits to ensure that licensee's voluntary program has been properly implemented.
The staff is currently evaluating Owners Groups' comments to the staff's proposed audit plan which will be discussed in the near future with NEl and Owners Groups.
Year 2000 Status: The WOG gave the staff an update of the Year 2000 (Y2K) issues and informed the staff that it has formed a Y2K Subgroup. The staff discussed its recent audit activities and noted that Seabrook has an excellent program in this area.
Next, the current and future planned lists of WOG submittals were reviewed. The staff agreed to supply an update of the projected completion schedule. Regarding the specific topic reports, the following have been agreed upon:
WCAP-14358 (Risk-Based Methods for Check Valve IST) and WCAP-14571 (Risk-Based Methods for Pump IST): The staff plans to close the TAC number associated with these topical reviews because both reports have been on hold since 1996. The WOG will notify the staff by letter regarding whether it wants the staff to continue the reviews.
The progress and schedule for the five license renewal submittals will be discussed in the next WOG/NRR Senior Management Meeting.
WCAP-10541 (RCP Seal Performance Following Loss of All AC Power): Currently, no review is being conducted on this topical report because the staff is still working on the resolution of Generic Safety issue 'GSI) 23. The staff will update this issue at the next j
WOG/NRR Senior Management Meeting.
WCAP-12476 (Evaluation of LOCA during Modes 3 & 4): The WOG will inform the staff regarding whether this topical report needs to be reviewed.
At the conclusion of the Senior Management Meeting, Mr. Collins described the staff's efforts, under the direction of the NRC Chairman, to improve the regulatory process based on the inputs of the stakeholder meetings. He indicated that the staff will utilize four standards to j
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tackle any issues. These standards are maintaining safety, improving effectiveness, reducing l
unnecessary burden on stakeholders, and increasing confidence of the stakeholders. Finally, a senior WOG representative commended the staff's recent positive changes in this area. He
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indicated that he observed that the replies from the staff are more responsive and the l
completion of SERs is more timely.
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- Project No. 694 l
i Attachments: As stated cc w/atts: See next page -
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T,- Essig November 3, 1998 tackle any issues. These standards are maintaining safety, improving affectiveness, reducing unnecessary burden on stakeholders, and increasing confidence of the stakeholders. Finally, a senior WOG representative commended the staffs recent positive changes in this area. He indicated that he observed that the replies from the staff are more responsive and the completion of SERs is more timely.
Project No. 694 Attachments: As stated cc w/atts: See next page DISTRIBUTION: See attached page f
DOCUMENT NAME: G:\\pxw\\ni:um1027,wog SC:PGEB jfg OFFICE PGEB NAME PWen:swRW FAkstuhI
'I DATE 11/3/98 11/3 /98 I
4 DISTRIBUTION: Summary of October 27,1998, masting with WOG dit d November 3,1998
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Central Files
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E-Mail SCollins/FMiraglia l
RZimmerman l'
BSheron l
JRoe/DMatthews GHolahan/SNewberry l.
GLainas/JStrosnider CGrimes RElliott l
RLobel CBerlinger TCollins TAttard LSpessard l
JWermiel RGallo l
DWessman TSullivan l
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Kmanoly l-SLong i
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WOG/NRR SENIOR MANAGEMENT MEETING LIST OF ATTENDEES OCTOBER 27,1998 l
Name Oraanization l
Sam Collins NRR 1
Gus Lainas NRR/DE Dick Wessman NRR/DE/EMEB Kamal Manoly NRR/DE/EMEB Ted Sullivan NRR/DE/EMCB Keith Wichman NRR/DE/EMCB Scott Newberry NRR/DSSA '
Carl Berlinger NRR/DSSA/SCSB Richard Lobel NRR/DSSA/SCSB Rob Elliott NRR/DSSA/SCSB Steve Long NRR/DSSA/SPSB Tony Attard NRR/DSSA/SRXB Jared Wermiel NRR/DRCH/HICB Bob Gallo NRR/DRCH/HOLB Peter Wen NRR/DRPM/PGEB Michael Marshall RES/DRA/GSIB Brew Barron Duke Energy (McGuire)
Jack Bailey TVA Lou Liberatori Consolidated Edison Larry Walsh Northeast Utilities Andrew Drake Westinghouse /WOG Project Office Sam Binger Westinghouse /WOG Project Office Roger Newton.
WEPCo Michele DeWitt Westinghouse /NSD Charles Sawyer Duke Energy Bob Bryan TVA Karl Jacobs New York Power Authority Jack Stringfellow SNC Keiichi Kugimiya Mitsubishi Heavy In.
Lynn Conner DOC-Search Leslie Collins ABB-CE 1
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WESTINGHOUSE OWNERS GROUP / NRC SENIOR MANAGEMENT MEETING One White Flint North - Room O-6B11 Rockville, MD l
October 27,1998 l
9:00 AM-11:00 AM Agenda 9:00 AM. L INTRODUCTION l
Meetmg Purpose Jack Bailey, WOG EAC Cluitman l
l Tennessee Valley Authority Agenda Review Lou Liberatori, WOG Chairman e
1998 WOG Steering Committee Consolidated Edison e
l 9:10 AM IL WOG PRESENTATIONS Lou Liberatori e WOG Ornaintin=1/ Potential Issues Commumcations Risk Informed ATWS Model e
Risk-Informed Policy for Prior Submittals e
Use of LBB for Contamment Sump Issues e
Break Openmg Time e
BafDe Barrel Bolting Program Status e
PASS Elimination e
. Master Curve Reactivity Manipulations per 10 CFR 55.31(a)(5)
Severe Accident Management Guidelines e
Year 2000 Status e
10:10 AM IIL REVIEWWOG NRC SUBMITTALS Lou Liberatori Priority of WOG Submittals e
Future Planned WCAP Submittals e
10:20 AM IV. NRC ITEMS NRC Open Discussion e
10:50 AM V. CLOSING COMMENTS Lou Liberatori Comments / Suggestion l
e Action Item Review e
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WESTINGHOUSE OWNERS GROUP WOG / NRC SENIOR MANAGEMENT MEETING OCTOBER 27,1998 WESTINGHOUSE OWNERS GROUPS WOG / NRC SENIOR MANAGEMENT MEETING OCTOBER 27,1998
- 1. INTRODUCTION Meeting Purpose
- WOO /NRC Information Meetings Implen,ented in 1992
- Conducted on a Biannual Basis
- Last Meeting March 31,1998
- Interface Meetings Maintain & enhance communication channels a
Allow for candid discusion of open issues / concerns Provide major progrsm activity update Review NRC status of WOO submittals Solicit NRC input to WOO program planning A priontization process a
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WESTINGHOUSE OWNERS GROUPS WOG / NRC SENIOR MANAGEMENT MEETING OCTOBER 27,1998 j
I. INIRODUCTION --
Response to 3/31/98 Meeting Action Items
- Fuel Rod Internal Pressure, affected plants to notify NRC via separate letter l
- Staff / WOO to continue work on SAM
- Staff to provide BBB review schedule at 4/8/98 meeting
- WOO to advise Staff of number of potential RI ISI applications
- WOO Project Oflice to advise Staff of attendance at W Y2K Workshop
- Staff to provide most current SER dates l
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WESTINGHOUSE OWNERS GROUPS WOG / NRC SENIOR MANAGEMENT MEETING OCTOBER 27,1998 I. IN 1RODUCTION Agenda Review 1998 WOG Steering Committee
- Orgaruzational Chart l
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WESTINGHOUSE OWNERS GROUP WOG / NRC SENIOR MANAGEMENT MEETING OCTOBER 27,1998 IL WOG PRESENTATIONS WOG Organmtional / Potential Issues Communications
- WOO Regulatory Response Group
+ Operates under its own cL.rter, ard is a WOO, industry. sponsored, quick.
response organization intended to provide the NRC/NRR with a basis for logical and reasoned regulatory response to potential, near-term, generie safety significant events and concerns
- The Issues Review Group (IRO)
- Complements the RRO and has the responsibility of providing direction for the disposition of WOO and industry issuce requiring expedient resolutions not meeting the RRO criteria
- WOO PotentialIssues Communications Pro 6 ram Is a communication process which is designed to enhance potentialissue a
definition, communication and resolution by drawing upon the collective knowledge of both Westinghouse and WOO utility members.
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WESTINGHOUSE OWNERS GROUPS WOG / NRC SENIOR MANAGEMENT MEETING OCTOBER 27,1998 II, WOG PRESENTATIONS --
Risk Informed ATWS Model a
- New WOO ATWS Program Objectives:
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- Develop Risk-Inforneed ATWS model
- Address NRC concerns with WCAP-11992
- Demonstrate the approach in pilot application leis 98 IDf1NT-tm l.
t WESTINGHOUSE OWNERS GROUPS WOG / NRC SENIOR MANAGEMENT MEETING OCTOBER 27,1998 II. WOG PRESENTATIONS --
+ Risk Informed ATWS Model--
- Requested NRC Support Meet with W/ WOO to establish acceptability of approach a
- Information package provided 2 weeks before the meeting
- Review preliminary risk-informed results Discuas NRC's expectations of risk-informed A1WS model and receptiveness to its use relative to PMTC Targeting meeting for early December,1998 l
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WESTINGHOUSE OWNERS GROUP WOG / NRC SENIOR MANAGEMENT MEETING OCTOBER 27,1998 II. WOG PRESENTATIONS --
Risk Informed Policy for Prior Submittals
- Recent WOO pilot programs use current risk-informed applications
- Previous submittals prior to issuance of current draft NRC RI-Guidelines
- Should not need to revise / rework (" Grandfathered")
- NRC feedback w
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l WESTINGHOUSE OWNERS GROUPS WOG / NRC INFORMATION MEETING OCTOBER 27,1998 II.WOG PRESENTATIONS -
Use of Leak Before Break (LBB) for Containment Sump
- Letter requesting LBB application to containment sump issues has been submitted to the NRC by all 003:
. WOO - 11/97
+ BAWOO - 4S8
- CEOO 6S8
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- Allows exclusion ofdynamic effccts of pipe rupture loads for applicable lines as debris generation sources or containment coatings removal mechanism
- Submergence and washdown effects will be considered as primary cause for I
debris generation l
- Position consistent with NRC information published in 52 FR 41288 dated l
10/27/87 Revised GDC 4 l
- Request concurrence on this position for utility response to regulatory issues
- Application of LBB is independent of other risk-informed initiatives that may be developed for this issue l
- All PWR OGs request opportunity to interact with the Staff prior to NRC Tmal l
determination wms.
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WESTINGHOUSE OWNERS GROUPS WOG / NRC SENIOR MANAGEMENT MEETING OCTOBER 27,1998 II. WOG PRESENTATIONS--
Break Opening Time (BOT)
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WCAP-14748," Justification for Increasing Postulated Break Opening Times in Westinghouac PWRs", submitted to NRC for generic review January 1997
- Responded to StafiRAls June,1998
+ Including further justification for generic application / review
- Staff SER issued October 1,1998
- WCAP.14748 limited to application to the BBB program Other applications necd to be reviewed and approved by the staff on a a
case-by-case basis in
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n WESTINGHOUSE OWNERS GROUPS WOG / NRC SENIOR MANAGEMENT MEETING OCTOBER 27,1998 II. WOG PRESENTATION 1--
Break Opening Time --
- Reqwst that the WCAP-14748 be reviewed for Generie Application
. Continue originally requested review while the material is still current in everyone's mind
+ Consistent with BOTs already approved for oder NSSS applications
- Example Benefits
- Subcompartment presourization analysis
- Pipe whipjetimpingement' piping supportloada
. Steam generator loads
- Credit for inercased RCCA insertability during LOCA l
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WESTINGHOUSE OWNERS GROUP WOG / NRC INFORMATION MEETING OCTOBER 27,1998 l
II. WOG PRESENTATIONS -
l Baffle Banel Bolting (BBB) Program l
- Last WOG/NRC technical exchange meeting conducted 6/25/98
- WOO withdrew requests for NRC SERs on 2 loop bolt distnbution report as well as Multi 0ex ? 4:Jed 6/19/98
- committed to 10( 9 6 39 licensing strategy
- WOO inspection /replaw.ent program being implemented via l
10CFR50.59 at the lead plants
- Inspection / replacement campaign being conducted during current outage at Farley 1
- Point Beach 2 inspection / replacement scheduled to commence December 1998
- NRC participated as observer at both Westinghouac (Farley) and FTI (Point Beach) tooling demonstrations i.=
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WESTINGHOUSE OWNERS GROUP WOG / NRC INFORMATION MEETING OCTOBER 27,1998 II. WOG PRESENTATIONS --
- Baffle Barrel Bolting (BBB) Program --
- WOO provided submittst to NRC in support of utilizing irradiated bolt material properties in the ooit distribution analyses 8/26/98
- NRC issued SER on Break Opening Time increase with applicability limited to BBB program 10/1/98
- WOO still requesting NRC SER on generic bolt distribution analysis methodology topical report by the end of 1998 (WCAP-15029 submitted l
2/27/98) i
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WESTINGIIOUSE OWNERS GROUPS WOG / NRC SENIOR MANAGEMENT MEETING OCTOBER 27,1998 II. WOG PRESENTATIONS --
PASS Flimimf mn
- SAMO climinated the need for some PASS requirements
- Revised CDAO eliminated tis wed for PASS in making core damage amenments to support offsite emergency response recommendations
- New NEI scheme for classifying emergency conditions does not rely on the results of analysis of samples of plant fluids
- PASS requirements to be maintained:
- Containment hydrogen
. Containment sump pH (plant speciGe) in..
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u WESTINGIIOUSE OWNERS GROUP WOG / NRC SENIOR MANAGEMENT MEETING OCTOBER 27,1998 II. WOG PRESENTATIONS.-
PASS Elimmation
- WCAP 146%, Core Damage Assessrnent Guidance submitted Nov.1996
- WCAP-14986, Post Accident Sampling System Requirements: A Technical Basis, recently submitted to NRC for review
- WCAP-14986 utilizes WCAP 146% for its technical basis
- Wolf Creek is the lead plant for both Topical Reports
- NRC/WOG/ Wolf Creek meeting requested after lead plant subenittal
- Significant industry interest.BWROO,CEOO, B& WOO and NEI 1erlege as4FFT Em t.
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9 WESTINGHOUSE OWNERS GROUP WOG / NRC SENIOR MANAGEMENT MEETING OCTOBER 27,1998 II. WOG PRESENTATIONS.-
Master Curve
- WOO is supporting industry activities for the incorporation of Master Curve toughness method into Codes and Standards as an alternate method ofdefining RT a for reactor vessel steels including welds
- Kewsunce is the WOO lead plant application (weld )
- Beaver Valley to be the next WOO application (plate)
- With the formation of the industry Materials Reliability Project (MRP)
Master Curve will be utilized as past of a broad RV inwgrity margin assessment am.
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WESTINGHOUSE OWNERS GROUP WOG / NRC SENIOR MANAGEMENT MEETYNG OCTOBER 27,1998 II. WOG PRESENTATIONS.-
Reactivity Manipulations per 10 CFR 55.31(a)(5)
- Cunent requirements of 10CFR5531 not consistendy implemented (refer to IN-97 67 Failure to Satisfy Requirements for Significant Manipulations of the Controls for Power Reactor Operating Licensing)
- Recent plant experiences demonstrate that performing all manipulations on an operating plant is impractical from an economic point of view and may increase tic probability of plant transients / trips
- ANSI certified Simulators not available when rule was written.
- Owners Groups / NB will pursue a rule change to allow up to 3 of 5 required reactivity manipulations to be done on the simulator
- NE is currently collecting supporting information and examples i.w am. u t is 5
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WOG / NRC SENIOR MANAGEMENT MEETING OCTOBER 27,1998 II. WOO PRESENTATIONS. continued Severe Aceident Management a
- For over 50% of the WOO plants, enhanced severe accident management i
capabilities according to NE! 91-04, Rev. I is a reality; the remaining WOO P ants are still committed to the end of 1998.
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- With the competition for resources at both utilities and NRC,it is incumbent upon both organizations to find a way to cloac the severe accident issue as expeditiously as possible.
1 14/1e90 93G7Ff. Ess L 19 WESTINGIIOUSE OWNERS GROUPS WOG / NRC SENIOR MANAGEMENT MEETING OCTOBER 27,1998 II. %vG PRESENTATIONS.
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Year 2000 Issues
- Interfacing with NEI Task Force on this issue
- Westinghouse Workshop conducted April,1998 NRC attended Workshop W initial screening identified potential Y2K implications a
- Y2K Subgroup Formed May,1998 Nineteen WOO Utility hkmbers
- Currently assessing hardware / software applications laind ge4FFT. Rae 1 30 1
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WESTINGHOUSE OWNERS GROUPS WOG / NRC SENIOR MANAGEMENT MEETING OCTOBER 27,1998 III. REVIEW WOG NRC SUBMITTALS Priority of WOG Submittals
- Future Planned WCAP Submittals i.w
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m WESTINGHOUSE OWNERS GROUPS WOG / NRC SENIOR MANAGEMENT MEETING OCTOBER 27,1998 IV. NRC TENE Open Discussion
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l WOG / NRC SENIOR MANAGEMENT MEETING l
OCTOBER 27,1998 V. CLOSING COMhENTS Comments / Suggestions Action Item Review i
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Teble 1: WOG WCAP Subniitte.ls to NRC WCAP #
Woc Title OG letter lead Plant Estimated Actions / Comments Priority SER Date 15029/15030 1
W Methodology for Evaluating the OG-98-030 Generic 12/98 Based on June 25 meeting
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Acwptability of Baffle-Former Bolting February 27,1998 Distnbutions Under Faulted lead Conditions OG-98-043 March 25,1998 14572 Rev 1/
2 WOG Application of Risk Based Methods to Submitted by NEI j Cu-ry 2 12/98 RAls and open items responded 14572 Rev 1 Piping inservice in.,pection October,1937 to 9/30/98 via OG-98-103 Supp1 14986 Rev i 3
WOG Post Accident Sampling System OG-98-108
'# Creek 4/99 Wolf Creek submittal expected 9 '*"
14987 Rev 1 October 26,1998 D #8-146 %
3 Core Damage A-e-t Guidance - Class 3 OG-96-098 WolfCreek 4/99 Review started but waiting on non-prop.
November 22,1996 lead plant submittal. WCNOC subnuttal expected by 10/98 14748/14749 4
Justification for increasing Postulated Break OG-97-006 Generic issued 10/1/98 Limited applicability to BBB Opening Times in Westinghouse Pressurized January 31,1997 program. To:-request approval '
Water Reactors for generic application.
15049-NP 5
Risk-Informed Evaluation of an Extension to OG-98-093 WolfCreek 3/99 Wolf Creek submittal pending Accumulator Completion Times - Class 3 non-August 20,1998 pmp.
14483 6
Generic Methodology for ed Core OG-95-093 -
TBD 3/31/99 RAIs received 9/98 Operating Limits Report - C 3 non-prop.
12/1/95 13877 7
Reliability Meac-t of Westinghouse Type TVA LAR Watts Bar TBD WCAP rev i submitted which AR Relays Used as SSPS Slave Relays February 28,19%
responded to all RAls. Under CRGR rniew for" waiver" and SE being dropped.
14358 / 14358 8
WOG Application ofRisk-Based Methods to OG-96-078 -
TBD On IIold Until TBD Supplement Check Valve IST-Class 3 non-prop.
9/5/96 1999 14571 9
WOG Application of Risk-Based Methods to OG-96-077 -
TBD Oniloid Until
'IBD Pump IST-Class 3 non-prop.
9/5/96 1999 14750 /
10 RCS Flow Verification Using Elbow Taps at Submitted by Farley 12/98 Irptial" partial" RAls reviewed Westinghouse 3-Loop PWRs Southern Nuclear 4 quarter 1997, awaiting 14754 November 26, balance ofquestions from initial 19%.
RAls.
10541,Rev.2 11 Reactor Coolant Pump Seal Performance OG-84-122 Generic OnIfold WCAP not actively being FollowinglessofAll ACPower May 3,1984 rniewed because final generic 06-86-206 (Rev. 2) resolution ofissue is being December 10,1986 ntluated 12476 12 Evaluation of LOCA During Mode 3 and OG-91-61 Generic Onliold No review currently ongoing, Mode 4 Operation for Westinghouse NSSS -
November 27,1991 issue will eventually be resolved Class 3 non-prop.
through the Maintenance Rule.
Note: Estimated SER dates are provided by NRC.
WCAP Tatste Itension 6 - Oaol.w 23. t 998
Tcbla 1: WOG WCAP S:bmittals to NRC WCAP #
WOG Title OG Ietter lead Plant
. Estiaisted Actions /C-==ts Priority SER Date
!1$126%@p g?pfNY > schaical Assessaseet of the Past length wegy
,WOGPLC4153?5 flenericifyj M $1RN/AW%
for Musenden M
iSf 6 18888 k
i
$$ k k 6
"" ' I-3 Y"~?
1Ristitaskiing W9sr p 00y7127434% famands'
'W MM#nN 6FW ~ ~
2 4 g
I I
.[@pe%g~ v l
l;~.
i
~~
- ProteNIlselliRisti inftneRPS'andiW@$ lOG45616M$M,Olema
.A F 1
PM Pg*hh kNb%we9 h $b k
b iL h
e
.,.a pf~my @:.Rasposse.DasTest? W~g&gMA'r. e Jammasy&&27/1995(gak'S i
nuassalan^afPeristio Prosection Channet % OG96405BW9W Weise:1 sg*!#MnemagMg :#M$$$n F*3%iks$$
- 440 j; *4s.
- iW id t. :
wpg ifdg =Ml99 +% $W' %gyGy*;1.<qw&.,
W904 t
kenewKawanw. n tw Wev wm inuut ni yG y
q e
$A ". MHot ~ Recircuistionmiminasicalief$! !:04960$4Bs@$Ni ;N/ ANT 4
- 344ggilh;g$q enmems.
pH
$$2 N/NRh Mdulunen33GCMS W
_ygf$a%.
Ma e
y
, empm'and 4 Loop. Design NSSS(a lM' M N N %, 4glf $se*g M
canceicd#ssisN ??..
is#996 g
M 1
ti. mum mi a s
mwwwg cm x
h,
- 36,Rn 3 si a
<Piegramah Thennal
~
'13!1998c l?RE R
(97' i
E+"
WF M?N'd$
d
- widulmanatis'OG98074 hff4 48tnususal W ii 38% J dEd JgE 2"
W1979818$ p a @$fdk Ikjk
>Beala RMbiFf$ ' MM@@$D M'3?I998N$F $$b
^[ L... mjg$$D$ M$$$dWer$$nWmic m
wJ E$
A Mi i DeisiiinGranC" ~
Base BametM@ i@4048f ~ M,Otatrii " * ]::
'150M7Ms J @d
$pp ~
?ggh:N
%N/AR*%
WOG Requemiti'iesisik.3
- ' M Bottingine;Tsotoop.
iagh== Dd] 5 Adasch3 11998 withdrawavia0095474
.g, T Y. PM A$,
.Plaass' MM..E%# 6 Mi h s Nw% n(@
. m Ml#Mje#eEM * *UsFMS mmh 6 sM
.M $
- @B&J
- 19/98 h & M W a @ gl y '
&W
- Anril 24?i9981?*P 'WMA
.MN WW JW#:
- menWMhMEEdm l
Note: Estimated SER dates are provided by NRC.
1 1
I weer.u.a.m..a w n.im m_
A._.
Table 1: WOG WCAP Submittnis to NRC License Renewal Submittals Woc Estimated WCAP #
Priority Title OG Ixtter Ixad Plant SER Date Actions /Ceanaments 14422, Rev. 2 1
License RenewalEvaluation: Agt'ng OG-97424 Genenc nakanwn /
WOG responded to several sets M====ement for Reactor Coolant Supports March 4,1997 TBD of RAls. Rev 2 includes RAls.
Awaiting SER from NRC.
14575 2
License Renewal Evaluation: Aging OG-96-071 Generic unknown /
WOG has responded to RAls. No Management for Class 1 Piping August 28,19%
TBD additional RAls WM 14574 3
License Renewal Evaluation: Aging OG-96-052 Generic unknown /
[
Management for Pressunzer July 3,1996 TBD additional RAls eWM 14756 4
License Renewal Evaluation : Aging OG-96-103 Generic unknown /
WOG provided response to RAIs Management for Pressunzed Water Reactor December 11,1996 IBD received 2/19/98. No NRC Contamment Structure fmthark to date.
14577 5
License Renewal Evaluation:
'ng OG-97488 Generic unknown /
No action by Staffyet.
Management for Reactor V Internals September 2,1997 TBD i
Note:
E=timata_i SER dates are provided by NRC.
t ASIC Subgroup Program Comments woc Estimated WCAP #
Priority Title OG Ixtter Lead Plant SER Date XXXXX ASICS Based Pentvement Modules for Use in OG-97-069 South Texas 3/99 Chapters 1,2,3, & 7 submitted Analog Pmcess dontrol and Protection Applications July 10,1997 Chapters 4,5,6,8 & 9 scheduled.
for subauttal 12/98.
WOG-ASIC-98-002 June 5,1998 Anticipated WOG WCAP Submittals to NRC h l*
Comments WCAP #
woc Estimated Priority Submittal Date d
RT & ESF Logic and Rx Trip AOT and S'Il 2 Quarter,1999 XXXXX l
i WCAP Table Reviam 6 - atuta 23,1998 l
-.. - - ~.. -..-
~S Westinghouse Owners' Group.
- Project No. 694 cc:-
Mr. Nicholas Liparulo, Manager Equipment Design and Regulatory Engineering l -
. Westinghouse Electric Corporation l-
.' Mail Stop ECE 4-15 i
.' P.O. Box 355
~ Pittsburghi PA 15230-0355 Mr. Andrew Drake, Project Managet L
Westinghouse Owners Group '
l
- Westinghouse Electric Corporation
. Mail Stop ECE 5-16
. P.O. Box 355 L.
Pittsburgh, PA -'15230-0355 Mr. Jack Bastin, Director Regulatory Affairs.
Westinghouse Electric Corporation
.11921 Rockville Pike Suite 107 Rockville, MD 20852 V
Mr. Hank Sepp, Manager Regulatory and Licensing Engineering Westinghouse Electric Corporation
~ PO Box 355 Pittsburgh, PA 15230-0355 I
l' i ;-ll
{.
.-_~ -.
....m.
Westinghouse Owners Group cc:
Mr. Nicholas Liparuto Westinghouse Electric Corporation Mail Stop ECE.4-15 P.O. Box 355 Pittsburgh, Pennsylvania 15320-0355 Mr. Hank Sepp
. Westinghouse Electric Corporation Mail Stop ECE 4-07A P.O. Box 355 l.
Pittsburgh, Pennsylvania 15320-0355 Mr. Andrew Drake
. Westinghouse Owners Group f
- Westinghouse Electric Corporation l,
Mail Stop ECE 5-16 P.O. Box 355
~ Pittsburgh, Pennsylvania 15320-0355 i
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