ML20147E869

Summary of 970206 Meeting W/Bwrog in Rockville,Md to Discuss Status of Current BWROG Topics.List of Attendees & Affiliations & Copy of Handouts Used by BWROG Encl

ML20147E869
Person / Time
Issue date:	03/17/1997
From:	Joshua Wilson NRC (Affiliation Not Assigned)
To:	Matthews D NRC (Affiliation Not Assigned)
References
PROJECT-691 NUDOCS 9703190259
Download: ML20147E869 (36)

Text

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sP 'lity f' [ t UNITED STATES

.g j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 3066H001 o,

s*****/ March 17, 1997 MEMORANDUM TO: David B. Matthews, Chief Generic Issues and Environmental Projects Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation FROM: James H. Wilson, Senior Project Manage Generic Issues and Environmental pd%

Projects Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation 1

SUMMARY

OF MANAGEMENT MEETING HELD ON FEBRUARY 6, 1997, WITH l THE BOILING WATER REACTOR OWNERS' GROUP (BWROG) TO DISCUSS  !

l STATUS OF CURRENT BWR0G TOPICS On February 6,1997, the staff held a public meeting with the BWROG at NRC headquarters in Rockville, Maryland to discuss a number of topics. For each topic, the BWROG provirled an overview describing the status of the owners' group activities and indicated where significant interactions with the staff l would be beneficial in resolving ~the issue. A list of attendees and their l affiliations is provided as Attachment 1. A copy of the handouts used by the l BWROG in its presentations is provided as Attachment 2. I BWROG members summarized the status of action items from the previous meeting held on October 23, 1996. Each of the agenda items was then discussed, as summarized below.

ECCS Suction Strainer Performance The staff has issued Bulletin 96-03 and Reg. Guide 1.82, Rev. 2 to address ,

this issue. The staff has received the BWR0G's submittal of the Utility Resolution Guidance (URG) document and has provided the BWROG with its comments. The BWROG provided the staff with its response to the staff comments on January 30, 1997. The BWROG response is currently under review and some open issues remain. l Since open issues remain, plants having Fall 1997 refueling outages who cannot proceed to resolution under 10 CFR Part 50.59 will be asked to submit plant A specific responses for staff review in order to avoid delays in U implementation. Many plants are taking a conservative approach to resolution which the staff believes will allow expeditious review of their response. A meeting will be held within the next couple of weeks to provide guidance to the utilities on submittal requirements.

97031" M 7 770317 6 PDR 97 O ggHECBHE Ey

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! D. Matthews March 17, 1997 The staff is proceeding with granting implementation deferrals to plants 4

having refueling outages in the Spring of 1997; however, it was made clear

, that the staff expected these utilities to complete implementation prior to j December 31, 1998. This maintains the overall schedule for implementation of i the NRCB 96-03's requested actions, and may require a mid-cycle outage by the j utility.

MSIV Leakaae 1 The BWROG strategy for resolution of this issue has been to significantly i increase the allowable main steam isolation valve (MSIV) leakage rates, take credit for the turbine cycle pathway, and eliminate requirements for the MSIV leakage control system (LCS). This has been accomplished through specific license change requests and supporting radiological dose calculations. The staff has approved technical specification changes from 8 plants to relax l limits or eliminate the leakage control system.

l

, The BWROG submitted a topical report in 1993, providing the proposed generic methodology for increasing MSIV leakage and elimination of the leakage control systems. Staff concerns remain regarding the use of earthquake' experience

data. On January 9, 1997, the BWROG submitted a response to staff questions i posed in May 1996. (The staff's questions of May 1996 were raised because the BWROG RAI responses dated February 19, 1996 did not adequately address the issue.) ,

i The BWROG reported that 12 plants have completed seismic verification work and

. are awaiting completion of the staff's review of the BWROG topical report i before making submittals seeking the elimination of the MSIV-LCS. The staff j is evaluating the most recent material provided by the BWROG, will determine l its schedule for issuance of the topical safety evaluation, will and advise  ;

the BWROG. '

The staff has assigned Ms. Tilde Liu as the new project manager for i coordination of activities involving the MSIV-LCS. ~

Feedwater Nozzle Insoection The BWROG submitted a generic report in a letter in October 1995, requesting i alternative inspections and schedules to those specified in NUREG-0619. The

! staff issued requests for additional information on December 18, 1996. The BWROG is developing a proposed schedule for its draft approach and response to the RAls. The BWROG will notify the staff of its proposed response schedule.

The staff encouraged the BWROG to interact closely with the staff through 4 face-to-face meetings in order to expeditiously resolve the key issues involved and avoid additional requests for information.

CRD Scram Solenoid Pilot Valves GE submitted its Scram Solenoid Pilot Valve Delayed Response Time Evaluation (NEDC-32646P) to the staff for informal review in January 1997. The staff reviewed the report and agreed with the GE methodology used to determine that

1 i

'e D. Matthews March 17, 1997

{

1 i

! the root cause of the slow response times was due to volatile components l l 1eaching out of the Viton elastomer diaphragm and forming a wetting adhesion l l with the brass valve seat of the scram solenoid pilot valve. The staff had l some questions on the plant data used to support the claim that the delay in )

the 5% scram response time leveled off or decreased over a period of 6 to 12  !

l months after installation. The staff would also like to see the testing i carried on for a longer period of time to ensure that the delayed response l times have indeed leveled off.

i The BWROG stated that more data on delayed scram times would be difficult to

obtain and would only be of academic interest because plants have either i changed out the affected diaphrages or implemented the improved standard 3

technical specifications that allow 5% scram insertion times of 0.440 seconds,

! which is substantially above the amount of delay caused by the suspect diaphragms. The BWROG will request that its members voluntarily submit letters to the staff when they stop performing the BWROG-recommended enhanced response time testing and provide the individual plant resolution of the problem (replacement of the diaphrages, adoption of improved TS, etc).

The staff requested that the BWROG provide a more detailed status of utility actions and position on testing at the next management meeting.

Resnonse Time Testina The BWROG has been trying to simplify technical specification requirements for response time testing. The staff and the BWROG have scheduled a meeting for March 12, 1997 to address the results of the supplemental response time l testing work being done by the owners' group to address instrument loops with shorter response time requirements than were previously addressed in the earlier BWROG program.

Taraet Rock SRVs j Target Rock 2-stage safety relief valves (SRVs) have had a history of setpoint 4 drift patterns. Resolution involves installation of a catalyst (platinum disc) or installation of pressure actuation switches. The staff and the BWROG discussed the valla design changes involving platinum alloys designed to alleviate the bonding between the pilot seat and the pilot disc that contributes to the setpoint drift. Preliminary data indicate that, in most instances, the performance of the platinum alloy disc is acceptable. The data also indicate that pilot valve seat leakage decreases the effectiveness of the platinum discs. Improved maintenance is being implemented to reduce pilot leakage. Two facilities (Hatch and Millstone) have installed pressure switches. Currently, 7 out of the 10 plants with 2-stage Target Rock SRVs are on the BWROG committee. However, the other three plants are believed to be taking actions to address the SRV problem.

The BWROG stated that it would report on status and industry intentions at the next management meeting - after the April 1997 industry meeting.

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a D. Matthews March 17, 1997 Intearated Risk-Based Reaulation The BWROG's Integrated Risk-Based Regulation Committee described the BWROG PSA certification process. The staff pointed out that the revised Standard Review 1 l

Plan (SRP) and Regulatory Guides (RGs) are scheduled for issuance in 1997, including the areas addressing PSA. The SRP and RGs will be issued for public comment and will contain a framework for how to do risk-informed licensing changes. Although the target for final issuance is the end of the year, more time may be required to resolve comments. The staff encouraged the BWROG to work through the public comment process to ensure that their concerns are met.

Reactivity Controls Review Committee The Reactivity Controls Review Committee summarized its recent activities and accomplishments.

Reload Analysis and Core Manaaement Committee The BWROG Reload Analysis and Core Report Committee shared information and described experience on reactivity-related issues to inform the staff of activities accomplished by the committee since 1989.

Future Manaaement Meetina The next BWROG/NRC management meeting is tentatively scheduled for May 1997.

One additional item on the agenda for that meeting will be discussion of how licensees address Information Notices. Licensees should be prepared to describe their screening process and how they determine the appropriate level of response. '

l Project No. 691 Attachments: As stated i

.- . - - - .-_. _ . _ _ . - . - - _ - - . . -. _ ~ - - _ - .

D. Matthews '

.l March 17, 1997 i d

Intearated Risk-Based Reaulation The.BWROG's Integrated Risk-Based Regulation Comittee described the BWROG PSA certification process. The staff pointed out that the revised Standard Review h1 (SRP) and Regulatory Guides (RGs) are scheduled for issuance in 1997, including the areas addressing PSA. The SRP and RGs will be issued for public  :

comment and will contain a framework for how to do risk-informed licensing J changes. Although the target for final issuance is -the end of the year, more l

time may be required to resolve comments. The staff encouraged the BWROG to l

, work through the public coment process to ensure that their concerns are met. 1 Reactivity Controls Review Committee I

The Reactivity Controls Review Comittee sumarized its recent activities and accomplishments.

i Reload Analysis and Core Manaaement Committee I The BWROG Reload Analysis and Core Report Committee shared information and described experience on reactivity-related issues to inform the staff of

activities accomplished by the committee since 1989.

i i Future Manaaement Meetina The next BWR0G/NRC management meeting is tentatively scheduled for May 1997.

One additional item on the agenda for that meeting will be discussion of how licensees address Information Notices. Licensees should be prepared to describe their screening process and how they determine the appropriate level of response.

8 Project No..,691< 1 Attachments: As stated DISTRIBUTION: See next page Document Name: MEETSUM.206 , t 0FC PGES y SC:PGEB ff y'C:PGEhk i NAME JHWit.un:sw RArchitzel DMatthDs\

, DATE 3//4/97 3/ d 97

/ 3/ k/97 0FFIC.lAL RECORD COPY

]

Ap1

LIST OF ATTENDEES AT MEETING WITH BWROG HELD IN ROCKVILLE, MARYLAND ON FEBRUARY 6, 1997 NatiE AFFILIATION B. Sheron NRC l j B. Boger NRC  !

C. Berlinger NRC i R. Jones NRC J. Lyons NRC e 'R. Wessman NRC i J. Strohsnider NRC l D. Terao NRC i R. Lobel NRC l i.. Phillips NRC K. Kavanagh NRC D. Skeen NRC J. Petrosino NRC R. Elliott NRC D. Naujock NRC l M. Chatterton NRC J. H. Wilson NRC K. Donovan Centerior C. Terry Niagra Mohawk D. Fetters PECO Energy i G. Krueger PECO Energy i T. Rausch Comed K. Sedney GE ,

P. Negus GE R. Sgarro PP&L G. Ottman NY Power Attachment 1

. . . _ . . . _ . _ _ _ . _ . . _ . . . . _ = . _ _ _ . . _ - . . _ _ _ _ . _ . _ _ _ _ _ . . - __ _

• l

NRCIBWROG MANAGEMENT MEETING ,

l FEBRUARY 8,1997 l l 9:00 a.m. - 12 Noon i

Agenda l i +

1 9:00 am introduction ECCS Suction Strainer Performance MSIV Leakage

Feedwater Nozzle Inspection (NUREG 0619) j CRD Scram Solenoid Pilot Valves l Response Time Testing

)'

Target Rock SRVs f Integrated Risk Based Regulation Reactivity Controls Review Reload Analysis and Core Management Status on Action itemt from October 23,1996 Meeting j Open Discussion i 12 Noon Adjoum i l i

i l

oG2103501 Attachment 2

I ECCS SUCTION STRAINER PERFORMANCE I

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i NRC/BWROG MANAGEMENT MEETING l

FEBRUARY 6,1997 ROCKVILLE, MD

9 l- ECCS SUCTION STRAINER l i  :

l l (BWROG/NRC Management Meeting) >

Background:

. Formally established in September, I 1993 l

! . Current funding authorized:

l $6.0M to date j Key support:

i > General Electric Nuclear

! Energy i > Continuum Dynamics, Inc.

l > Sequoia Consulting, Inc.

> Electric Power Research Institute

> Teledyne Brown, Inc.  ;

> Bechtel Power i

4

. Interface with International Task l l Group l

TAG 97-20 February 6.1997

l..

l- ECCS SUCTION STRAINER i

j (BWROG/NRC Management Meeting) i l Activities Summary (Continued):

l l . Document in Utility Resolution Guidance (URG) the calculational methodology employed to justify

! acceptability of alternate strainers

! > Zone of destruction Computational Fluid Dynamics (CFD) rnodeling l

j -

% destruction within zone j -

Airjet testing of typicalinsulation materials l > Drywell transport Break flow l

Washdown flow l

Scale model testing i > Strainer head loss I -

Fibrous insulation debris, iron oxide sludge, RMI, other materials Small scale testing in " gravitational" head loss facility Full scale testing at EPRI

%,'L'.397

i I- ECCS SUCTION STRAINER l

, (BWROG/NRC Management Meeting) l i

l US NRC Bulletin 96-03 Implementation:

l J

l . Alternate passive strainers is preferred resolution option

! I i

. Plant specific critical path Final strainer sizing calculation Structural analysis / hydrodynamics loads Final design, fabrication, & delivery

. Potential NRC approval requirements New generic design criteria, eg:

> URG Plant specific requests

> Bulletin response (s)

> Resolution of Unresolved Safety Questions (USQ) [if applicable]

> Approval of olant soecific strainer test data (vendor data) and design methodology

> Plant specific issues not covered by URG

> Potential changes to technical specifications

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ECCS SUCTION STRAINER i

(BWROG/NRC Management Meeting)

Recent Actions: (Continued)

E

. Meeting with NRC on December 17,1996 i (Continued) i j -

Other pending NRC generic communications i > LaSalle and NMP-2 events 1

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> NPSH issues i

i i > Containment coating concerns l l

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i TAG 97 20 February 6,1997

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l MSIV LEAKAGE CLOSURE i

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! NRC/BWROG MANAGEMENT MEETING

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l. FEBRUARY 6,1997

ROCKVILLE, MD 4

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MSIV LEAKAGE CLOSURE j (NRC/BWROG Management Meeting)

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Background:

. Alternate treatment equipment (main

stearn piping and condenser) for MSIV leakage demonstrated to be highly l

l reliable ,

! )

1

. Lead BWROG License Change l

Requests have been approved i - Hatch 2 March '94 l - Limerick 1,2 February '95

- Duane Arnold . February '95

)

! - Susquehanna 1,2 August '95

- LaSalle 1,2 April '96 l i

l . Several plants have completed

( seismic verifications:

1

- Hope Creek Perry l

2 -

Nine Mile Point 2

( - Hatch 1

- Nine Mile Point 2

- Oyster Creek

- Peach Bottom 2,3 WNP-2 Browns Ferry 2,3 Brunswick 1 TAG 97 22

MSIV LEAKAGE CLOSURE l

(NRC/BWROG Management Meeting) l 1

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Actions:

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• BWROG believes that SER in early 1997 is now l possible

• NRC management attention required to close this issue ,

Identify new project manager l l

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l TAG 97 22

. FEEDWATER NOZZLE INSPECTION Committee . Obtain NRC approval of BWROG Objective recommendations for feedwater nozzle inspections intended as an alternative to NUREG-0619 Presentation . Discuss NRC Request for Additional Objective Information. l l

1 l

4 FWNOZZ

FEEDWATER NOZZLE INSPECTION

/ssues

. Generic BWROG Report (alternative

inspection requirements) submitted for i

NRC review October 1995 1

- Would eliminate PT exams and

increase penod between UT exams l l

. NRC issued letter (5/28/96):

i Review of BWROG submittal will be

! complete before Fall 1996 outages  !

- In the interim, NRC will approve deferral of PT exam for one '

operating cycle on a plant-specific basis 4

. Proposed UT frequency still under j review

. Extensive NRC RAls issued 12/18/96.  !

. Notified staff verbally that due to l extensive comments, response in 30 l days not possible - staff agreed to

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schedule  ;

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t j SSPV COMMITTEE Committee e Gather and evaluate information l Objective related to the observed scram l delay l

4

) e Monitor GE evaluation of the root l

cause and development of

! replacement SSPV diaphragms i

j . Provide recommendations for

! efficient and timely resolution of j the SSPV issue i

i l Presentation . Review committee activities Objective:

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. . Inform NRC of committee i

conclusions and i

recommendations I I

i e Obtain NRC acceptance of l recommendations for resolution

! of the SSPV issue l

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i SSPV COMMITTEE l Background . Plant data supports the predicted j (continued): bounded nature of the delay l - Delay approaches maximum i value in 6 to 12 months

! - Observed delay less than j approximately 50 msec l

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-. Scram delay increase occurs

! relatively slowly compared to 60 l day augmented test i

! recommended by RRG (i.e.,

i augmented testing can be l

stopped if margin exists) l 1 1

. Replacement Buna-N and Viton '

l diaphragms developed by GE

! - Buna-N Qualified for 10 years l - Viton qualified for 15 years i

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! - Stable scram performance

! demonstrated i

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l SSPV COMMITTEE 1

i Actions:

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• BWROG proposed resolution approach reviewed )

! with NRC l

! - NRC stated that approach seems " reasonable" l

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! - GE root cause report & information on plant data

! requested l

l - No issues have been identified by NRC review to i date i

. With regard to diaphragm performance the BWROG assessment concludes

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1) The GE root cause evaluation correctly l identifies the cause of the scram delay l

i l 2) Plant data shows the expected stabilization in ,

diaphragm performance, and suggests that l average delay will not exceed approximately i 50 msec j .

3) If adequate margin exists (e.g., ~50 msec),

j normal testing at 120 day intervals is adequate j to ensure that unexpected delays of greater

than 50 msec will be detected I

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) RESPONSE TIME TESTING i

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! NRC/BWROG MANAGEMENT MEETING 1

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.i FEBRUARY 6,1997 ROCKVILLE, MD j

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i~- RESPONSE TIME TESTING  !

l (NRC/BWROG Management Meeting) l l l l

1 l /ssues . Evaluation for majority of selected l

components complete

! - Identify failure modes affecting i

response time

- Identify how detected

! - Review component supplier i requirements

- Review failure experience

1 i

l Actions e issue draft addendum to '

l NEDO-32291 A for Committee l review - February 1997 3

. Meet with NRC to review i preliminary results - March 12,1997 e issue final addendum - April 1997

! . NRC review -last half 1997

)

i TAG 97-21 February 6,1997

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I l TARGET ROCK SRVs I

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l NRC/BWROG MANAGEMENT MEETING i

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i . SRV l Feb NRC l

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Backaround:

l l . Catalyst Option l -Install Alloy Discs (All members have discs j installed)

! - Evaluate Disc Performance j + Total Fix, or

! + Add Catalyst Plating, or

+ Install Pressure Switch fix l

l Preliminary Data Indicates Pt Alloy Discs have l excellent results for  ;

leaktight pilots l

J;SRV-NRCdoc

ll-i-

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SRV Feb NRC l 5 l Summary of SRV Performance: i l . Number of Discs- u l - 36 Pt-Stellite i

! - 34 Stellite  !

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l . Average Drift:

l - Pt-Stellite: 2.7%

! - Stellite: 4.9%

SRV Pilot Leakaae Concerns:

4

! . Limerick event indicates l l extended gross leakage of pilot  !

! can result in SRV blowdown due f

! to mechanical failure ofinternal

components l

\

l . Leakage decreases

! effectiveness of Pt Alloy disc

. Committee pursuing elimination j of stroking SRVs during plant startup J;SRV-NRCdoc i

j.~

l-j*. SRV Feb NRC l

7 s

Conclusions:

I l

. Implementation of Pt Alloy disc to l l fix setpoint drift is progressing l

with full Committee participation

[ . Final decision on effectiveness of i Pt Alloy discs will be made mid-i 1997 l

} . Efforts to improve pilot leakage l are in progress.

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INTEGRATED RISK BASED REGULATION d

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4 NRC/BWROG MANAGEMENT MEETING 4

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FEBRUARY 6,1997 l ROCKVILLE, MD l

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Integrated Risk Based Regulation Committee 4

Backgroundt . Major Accomplishments l

l - Completed Risk Management l of On-Line Maintenance report

- Completed the " Approved"

! version of the MOV l implementation topical report

! - Monitoring of NEl and ASME l lST/ISI projects l - Participation in the NEl Risk Based Application Task Force

- Completed Graded QA report

- Completed report on risk l management l

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! Integrated Risk Based Regulation Committee l /ssues . The committee will provide l comments on NRC Regulatory l Guide and Standard Review I Plans for implementation of PSA l in the regulatory process 1

j e The committee wil0 support NEl j and provide comments on

! NUREG 1560, a comparison of IPEs

! - Industry believes PSAs are I j suitable for certain applications now j - BWROG PSA Certification

! process assures quality

! (Pilot plant report sent to NRC l for Information)

- NRC holding an industry workshopin April 1997

- BWROG IRBR Committee will provide initial commente, prior to workshop and will present at the workshop l

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REACTIVITY CONTROLS REVIEW COMMITTEE l Committee . Share information and experience l Objective l on reactivity related issues 1

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. Be prepared to respond quickly to 1

reactivity related events 1

!. . Identify best methods for j reactivity control based on peer l

experience I

l Presentation . .

inform NRC of this committee j Objective; activity b l i

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j HCP:RCR

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! REACTIVITY CONTROLS REVIEW COMMITTEE i

l /ssues: . Committee addressing i operational issues raised by l lNPO and NRC, e.g.:

i i - NRC Core Performance l Workshop i

j - INPO SOER on design and j operation of reactor cores i

• Fuel reliability practices

! . Operational review of stability l long term solution

! implementation 4

Actions:

l

! = Four or five committee meetings are planned in

! 1997 to address issues and provide guidelines I

l HCP:RCR

l :-

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l RELOAD ANALYSIS & CORE MANAGEMENT

! COMMITTEE l

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! Committee e Provide information sharing forum

! Objectivet between utilities and fuel vendors i on reload analysis and core j management issues 1 I I e Identify, prioritize, and recommend l resolution to technical issues i

. Support fuel audits by NUPIC l . Facilitate resolution of issues i

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l Presentation .

Inform NRC of this new committee I

\

Objectivet activity i

i Background; e Committee authorized at January l BWROG General Meeting (1/22/97) l l

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HCP.RACM

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^

Project No. 691

, Boiling Water Reactor Owners Group

, cc: K. P. Donovan, Chairman i Boiling Water Reactor Owners' Group Centerior Energy Perry Power Plant MC A210

! P. O. Box 97 i Perry, OH 44081

! C. D. Terry Vice President, Nuclear Engineering

Niagara Mohawk Power Corporation

! Nine Mile Point-2 1

PO Box 63 Lycoming, NY 13093 D. B. Fetters PECO Energy Nuclear Group Headquarters

MC 62C-3

] 965 Chesterbrook Blvd.

Wayne, PA 19087 l

2 L. A. England i Entergy Operations Inc.

PO Box 31995

Jackson, MS 39286 K. K. Sedney 4

GE Nuclear Energy 175 Curtner Ave, M/C 182

San Jose, CA 95125 T. J. Rausch s

Commonwealth Edison Company Nuclear Fuel Services 1400 Opus Place, 4th Floor ETWIII Downers Grove, IL 60515 a

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DISTRIBUTION w/ attachment: Mtg. Sumary/BWROG Dated uy, c w 17 199, liard Cooy Central File

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