ML20134B633

Summary of 961023 Meeting W/Util in Rockville,Md Re Status of Various Technical Topics.List of Attendees Encl

ML20134B633
Person / Time
Issue date:	01/24/1997
From:	Architzel R NRC (Affiliation Not Assigned)
To:	Matthews D NRC (Affiliation Not Assigned)
References
PROJECT-691 NUDOCS 9701300251
Download: ML20134B633 (61)

Text

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e' t UNITED STATES

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o 's NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 4 001

\..... January 24, 1997 MEMORANDUM T0: David B. Matthews, Chief Generic Issues and Environmental l Projects Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation FROM: Ralph E. Architzel, Section Chie ".

Generic Issues and Environmental Projects Branch -

. - [f' U Office of Nuclear Reactor Regula ion Division of Reactor Program Management

SUBJECT:

SU'tMARY OF MANAGEMENT MEETING HELD BETWEEN THE BOILING WATER REACTOR OWNERS' GROUP (BWR0G) AND THE NRC STAFF On October 23, 1996, the staff held a public meeting with the BWROG at NRC headquarters in Rockville, Maryland. The purpose was to discuss the status of various technical topics listed below. For each topic, the BWROG provided an overview describing the status of the owners' group activities and indicated where interactions with the staff would be beneficial in resolving the issue.

A list of attendees and their affiliations is provided as Attachment 1. A copy of the handouts used by the BWROG in its presentation is provided as Attachment 2.

E.CCS Suction Strainer Performance Regarding Bulletin 96-03 implementation, the BWROG noted that six plants with spring 97 outages were working towards resolution, but would be requesting deferrals. Some of the difficulty included the delay in obtaining generic approval, and the need to bring the analyses up-to-date basis following generic approval. The NRC indicated that the priority should remain on the Utility Resolution Guidance document, rather than plant-specific reviews. The NRC agreed to provide feedback on whether the interim actions were acceptable Severe Accident Manaaement Regarding the water level strategies for an ATWS, the BWROG was raquested to provide their rationale by the end of CY 1996. The NRC noted thai, their contractor, ORNL, was reviewing Revision 0 of the emergency procedure and severe accident guidelines (EP/ SAG) and would be available to meet with the BWROG at the conclusion of the review. The staff indicated that they would 5p like the BWROG work concerning EP/ SAG implementation timeline for a typical sequence to be moved up to allow completion of the contractor work.

MSIV Leakaae

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The BWR0G presented a status of closure of this technical issue. They noted g that the revised RAI response was targeted for December 1, 1996. The NRC requested that where verifications are being done, that other plants follow

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D. Matthews -2 ?

January 24, 1997 ,

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the lessons learned from the approved license change requests so that approval of the other plants would easily follow approval of the Topical Report.

Feedwater Nozzle Inspection

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i The BWROG discussed the status of this issue as outlined in the attached i

} handout material.

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l CRD Scram Solenoid Pilot Valves  !

The status of this issue was discussed. The BWROG noted that the root cause L

i report would be submitted oy the end of October. The staff requested that I qualification data be submitted for the solenoid valves. . Regarding fee l recovery, the NRC indicated that they would look into whether or not this

' review was fee recoverable. (Following the meeting the NRC determined that fees were not being charged for this review).  ;

, Calibration Interval Extension

} Regarding this issue, the BWROG indicated that they wanted to meet with the

staff to go over their concerns. The staff acknowledged that a meeting was

, needed. The BWROG stated that they would follow through on the actions to

{ resolve this issue identified in the handouts, including setting up a meeting

! with the staff, r

Response Time Testina  !

! This issue arose as a result of the WNP-2 actions to eliminate response time  ;

j testing under IC CFR 50.59. It was clarified that the response time testing was being eliminated. The staff agreed that equipment degradation identified j by response tiae testing is also detectable during other routine periodic testing. The staff did not agree with the characterization of response time .

testing in the handouts, and pointed out the need for amendments to the technical specification:: when implementing revisions to response time testing.

l The BWROG agreed with the staff that the topical report approval eliminated

!: specific technical specification required response time testing for selected j equipment.

Status on Action Items and Open Discussion 1

. The participants went over the status'of previous open items as reflected in the BWROG handout material and as noted above for the current issues. The NRC requested that the actions being taken by the BWROG for Target Rock Relief Safety relief valves should t>e on the agenda for the next management meeting.

The BWROG discussed the summary of refueling shutdown risk, including Hope l

Creek lessons learned that had been communicated to the BWROG utilities.

~

! The staff,requesthd'the BWROG to' discuss the status of several recent sump debris issues. The BWROG went'over their understanding of the situation at-l that time.at Nine' Mile Unit;2 (construction debris in the downcomers including

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f D. Matthews' i several hard hats, other floating debris, and some plastic caps on the downcomers and Lasalle (several large pieces of debris found in drywell,

' including a large gasket and a nylc, bag). t Project No. 691 Attachments: As stated  !

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D. Matthews January 24, 1997 i

several hard hats, other floating debris, and some plastic caps on the  ;

downcomers and Lasalle (several large pieces of debris found in drywell, '

including a large gasket and a nylon bag).

Project No. 691 i.

4 i Attachments: As stated

, cc w/atts: See next page i

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Boiling,Wa,ter Reactor 0wners' Group l

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C. D. Terry .

'Vice President, Nuclear Engineering Niagara ~ Mohawk Power, Corporation  ;

Nine Mile Point-2 '

PO Box 63 -

Lycoming, NY' 13093

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D..B. Fetters, 4

-PEC0! Energy '

r. ~ Nuclear Group Headquarters , + 1

. 'MC 62C-3 .

965-Chesterbrook Blvd. l

Wayne,.PA.'19087 R. A. Pinelli I GPU Nuclear MCC Building E-One Upper Pond Road i Parsippany, NJ 07054 '

i S. J. Stark i GE Nuclear Energy 175 Curtner Ave, M/C 165 San Jose, CA 95125 T. J. Rausch Commonwealth Edison Company Nuclear Fuel Services 1400 Opus Place, 4th Floor ETWIII Downers Grove, IL 60515

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LIST OF ' ATTENDEES AT MANAGEMENT MEETING WITH BWROG HELD IN WASHINGTON, DC ON 0CTOBER 23, 1996 a

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NatiE . AFFILIATION B. Sheron .NRC/ADT

?..* R . Wessman' NRC/DE

! "M. Virgilio . NRC/DSSA l "R. 'Architzel. i NRC/DRPM J.. Strosnider: -

' ' ' NRC/DE '

3 G. ' Jones , ,

~PP&L/VP-Nuc. Ops R., Sgarro.. . .. 'a PP&L D. ' Fetters > PECO Energy T. Rausch' -

Commonwealth Edison S. Stark '

General Electric K. Donovan ' Centerior C. Terry NMPC C. Brinkman ABB-CE l J. Wermiel NRC/DRCH  !

K. Noonan Framatome F. Burke Framatome S. Peterson NRC/ADT R. Palla NRC/DSSA K. Kavanagh NRC/DSSA D. Naujock NRC/DE P. Negus General Electric.

R. Rybak Commonwealth Edison '

L. Spessard NRC/DRCH D. Powell PSE&G l

Attachement 1 t

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NRC/BWROG MANAGEMENT MEETING j OCTOBER 23,1996 i 1

30 p.m. - 4: 30 p.m.

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Aaenda 4

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l 1:30 pm introduction l l

i ECCS Suction Strainer Performance l

' Severe Accident Management 1

MSIV Leakage '

Feedwater Nozzle inspection (NUREG 0619)

CRD Scram Solenoid Pilot Valves l Calibration Interval Extension Response Time Testing Status on Actiori Items from June 13,1996 Meeting Open Discssion 4:30 pm Adjourn OG20: AGENDA 10/23/96 Attachment 2

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l lNTRODUCTION i

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NRC/BWROG MANAGEMENT MEETING OCTOBER 23,1996 ROCKVILLE, MD

INTRODUCTION l

l Significant Progress Being Made by BWROG & NRC j l

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. Draft ECCS Suction Strainer Utility Resolution l Guidance (URG) submitted to Staff October 7,1996 Met with NRC October 16 for preliminary l review i l j e Stability hardware documentation nearing closure l 4 ,

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Option 1 A SERs issued 4 -

Option 1 A Solution Closure LTR

(Supplement 5) submitted l l

Option 1A calculation procedure l l successfully audited l Option Ill Plant Specific Implementation Data based on Detect & Suppress Methodology  :

4 transmitted to utilities and NRC

. Emergency Procedure Guidelines / Severe Accident Guidelines submitted to NRC OG2W4TRO

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INTRODUCTION - continued - l

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e NRC issued SER for Near Term Operating License SRV Performance Reporting l I i

. Dual ASCO Scram Solenoid Pilot Valve Root 4

Cause Report being submitted to NRC i

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OG20:lNTRO 10/23/96 i

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l ECCS SUCTION STRAINER PERFORMANCE 4

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2 NRC/BWROG MANAGEMENT MEETING 1

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i l OCTOBER 23,1996 ROCKVILLE, MD i

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.. ECCS SUCTION STRAINER i

Committee . Resolve the ECCS Suction Strainer j Objective

Issue for BWRs 4

l - Ensure interim safe operation

! - Ensure final resolution meets l regulatory requirements

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- Resolve within key constraints j > Containment analytical envelope

> Drywell dose, temperature

! considerations

> Minimize costs 3

l Presentation . Update NRC Management l Objective:

J TAG 96-86

i ECCS SUCTION STRAINER

Background:

. Formally established in September, a 1993

e Current funding authorized

l $5.5M to date l Key support:

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> General Electric Nuclear i

Energy i > Continuum Dynamics, Inc.

> Sequoia Consulting, Inc.

i > Electric Power Research j Institute j > Teledyne Brown, Inc.

j > Bechtel Power i

. Interface with International Task Group l

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L ECCS SUCTION STRAINER j.

Activities Summary:

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• Safety Assessment i l

. 1 e Development of Unique Altemate Strainer Designs l

l > Self-cleaning strainer l

Scoping tests j -

Full scale design, fabrication, and test Reliability issues

> 60 point star and stacked disk strainers Scoping tests Full scale tests Scaling of strainer designs for plant specific j application

> Evaluated effect of Reflective Metal Insulation ]

(RMI) and other miscellaneous debris on alternate strainer performance l

> Other key information developed l Suppression pool sludge particle size distribution Suppression pool slu@2 generation rates Containment coatings performance '

TAG 96-86

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ECCS SUCTION STRAINER l i

Activities Summary (Continued): '

. Document in Utility Resolution Guidance (URG) the '

calculational methodology employed to justify acceptability of alternate strainers

> Zone of destruction '

Computational Fluid Dynamics (CFD) modeling

% destruction within zone Airjet testing of typicalinsulation materials

> Drywell transport Break flow Washdown flow Scale model testing l

> Strainer head loss Fibrous insulation debris, iron oxide sludge, RMI, :

l other materials Small scale testing in " gravitational" head loss l facility ,

l Full scale testing at EPRI r

TAG 96-86 1

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ECCS SUCTION STRAINER .

US NRC Regulatory Status:

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. Bulletin 96-03 published on May 6,1996 l i  :

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Large enough strainers to handle bounding scenario l l

Self-cleaning strainer i j -

Strainer backflush l 3

Other industry selected resolutions

) . Requires issue resolution first refueling outage l beginning after January 1,1997 i

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l . Associated Regulatory Guide 1.82 Revision 2 issued

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l TAG 96-86 i

ECCS SUCTION STRAINER  !

US NRC Bulletin 96-03 Implementation:

e Alternate passive strainers is preferred resolution option 1

i . Plant specific critical path 3

Final strainer sizing calculation i

> Requires NRC approval of Utility Resolution Guidance (URG) document Structural analysis / hydrodynamics loads Final design fabrication & delivery

. NRC approval requirements New generic design criteria, eg:

! > URG

> Supporting technical reports Plant specific requests

> Bulletin response (s) l l > Plant specific issues not covered by URG

> Potential changes to technical specifications l

TAG 96-86

., ECCS SUCTION STRAINER 1

Recent Actions:

. Nine (9) utilities with spring '97 RFOs met with A.

Thadani (NRC) on August 8 to discuss difficulties with respect to resolving issue in the spring, and to investigate deferral potential NRC is expecting compensatory actions if deferral is requested

. Most utilities with spring '97 RFOs have requested deferrals l TAG 96-86

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ECCS SUCTION STRAINER l i Recent Actions: '

i l All BWROG testing to support URG positions complete l l

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Airjet impact testing of 26 typical insulation design i

configurations - l RMI head loss testing l

Jet deflector / downcomer transport testing )

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Draft URG along with technical support documentation provided to NRC and full Committee in early October '

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October 16th NRC meeting i -

Formal transmittal in mid-November l -

Need SER from NRC in January '97 to support fall

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TAG 96-86

!,' ECCS SUCTION STRAINER 1

l Utility Resolution Guidance (URG) for ECCS Suction Strainer Blockage

! BWROG supporting technicaplocyments:

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! (1) Testing of alternate strainers with insulation fiber and other debris l (2) Zone of influence as defined by computational fluid j dynamics

! (3) Insulation transport through downcomers/ vents into

! the wetwell i (4) Air jet impact testing ofjbrous and reflective metal  ;

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insulation l (5) BWR drywell floor flow modeling following pipe break

loss-of-coolant accident (6) Performance of containment coatings during a loss- i of-coolant accident (7) Evaluation of the effects of debris on ECCS performance (8) Suppression pool sludge particle size distribution (9) Suppression pool sludge generation rate data (10) Evaluation for existence of blast waves following licensing basis double-ended guillotine pipe breaks (11) Total pressure topography and zone of destruction for steam and mixture discharge from ruptured pipes (12) Effect of temperature on Net Positive Suction Head (NPSH) including strainer head loss  ;

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ECCS Suction Strainer Project Schedule -

1996 ID Task Name Jun Jul Aug Sep l l Oct Nov 1 Draft GG and Tech Support Doc. to NRC*

l l l l Dec Jan l Feb l Mar l Apr 2 Meeting with NitC Regarding Draft URG

$ 10/16 3 Draft URG Transport Section to NRC

$ 10/25 4 Formal URG Submittal

$ 11/22 S NRC Approval of URG

$ 1/31 6

7 "without transport section Task Summary Rolled Up Progress N Project-Date: 10/2/96 Progress - Rolled Up Task Milestor:a $ Rotted Up Milestone Q Page 1

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SEVERE ACCIDENT MANAGEMENT i

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NRC/BWROG MANAGEMENT MEETING i

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j OCTOBER 23,1996

! ROCKVILLE, MD 1

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i EPC-Il and AMWG i

i Committee . To support the Severe Accident j Objective Emergency Procedure Guidelines 4

(EPG/ SAG) j . To address EPG/ SAG  ;

t implementation issues l

. To assist utilities as they l implement their plant specific programs by information

exchange.

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Presentation . Provide a status of committee

!; Objective: work 1

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. Announce the merging of Emergency Procedures Committee (EPC) and Accident j Management Working Group (AMWG)

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i EPC-Il and AMWG i I l Background! . The Emergency Procedures i Committee (EPC) is responsible '

l for developing and maintaining j the Emergency Procedure '

Guidelines

. The AMWG has been responsible

for developing Accident l Management Guidelines j consisting of

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- The Overview Document j

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- Flexible assignment criteria

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- Technical support guidelines

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l - Training guidelines l . With the completion of the

! EPG/ SAG the AMWG has j completed its function.

i, j = Any remaining implementatiun

{ issues will be the scope of the i EPC i

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EPC-Il and AMWG

! /ssues: . ATWS water level  :

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) - NRC requested BWROG to i provide consensus rationale i of why they will retain lower i water level control l procedures for ATWS i

- BWROG documenting l rationale for NRC; will be '

l provided by the end of1996 1 i

. The NRC has provided AMG j scenarios for BWROG to provide j information i

! - The BWROG is targeting

, early 1997 for its response i

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!~ EPC-Il and AMWG l

Actions:

. Respond to NRC regarding the ATWS water level

. Respond to the NRC regarding AMG scenarios

Participants:

All21 utilities

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93 1994 1995 1996 1997 1998 . .

ID Task N m3 Otr 3 Otr1 l Otr 3 Otr 1 l Otr3 Otr 1 l Otr 3 Otr 1 l Otr3 Otr 1 l Otr 3 1 Final EPG Chinges Packages V V l

2 Contractors Drafts t 3 AMWG Review 4 EPC Approval

'gg i 5 Infortnal NRC Submittal g 6 NRC Comments _

7 Tech Basis Document p _.

8 Final Package to Utilities g_

9 Training Materials _ . _ . _ _ _ . _ _ _ _ _ _ _ . . _ _ . . _ _ _ _ . ,

l 10 Final Criteria 11 INPO Input Reviewed \

12 Integrate (w) EPGs/TSGs 13 Provide Draft Materials 14 Final Training Materials 15 Overview Document i I

16 Complete Draft l i

17 Review Draft 18 Complete Changes g i 19 AMWG Approvat .

20 Prim Rep Approval 21 NRC Submittal 2 9 j 22 NRC Comment 23 Final to Utilities 24 EPG/ SAG p l j

Task .

Milestone $ Rolled Up Milestone $ f P%ect. Task Progress m Summary Rolled Up Progress -

Date: 10/23/96 Critical Task f/////////////////j Rolled Up Task .

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! MSIV LEAKAGE i

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i l NRC/BWROG MANAGEMENT MEETING l

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OCTOBER 23,1996 ROCKVILLE, MD

.. MSIV LEAKAGE CLOSURE i

Committee . Obtain technical specification '

l Objective relaxation to significantly increase l allowable MSIV Leakage rates and 1 l to eliminate requirements for MSIV

Leakage control systems 1

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. Support plant specific license change requests with respect to radiological dose calculations I

Presentation Update NRC Management Objective:

TAG 95-67

{' MSIV LEAKAGE CLOSURE i

! Background; e Alternate treatment equipment l (main steam piping and condenser) j for MSIV leakage demonstrated to be highly reliable i

j . Lead BWROG License Change l Requests have been approved j - Hatch 2 March '94 l - Limerick 1,2 February '95

- Duane Arnold February '95

- Susquehanna 1,2 August '95

- LaSalle 1,2 April '96

. Others have completed seismic verifications:

- Hope Creek

- Perry

- Hatch 1

- Nine Mile Point 2

- Oyster Creek I

- Peach Bottom 2,3

- Brunswick 1

- WN P-2

- Browns Ferry 2,3 4 TAG 95-67

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MSIV LEAKAGE CLOSURE i

l Background; e Alternate treatment equipment i (main steam piping and condenser)

! for MSIV leakage demonstrated to l be highly reliable j '

l . Lead BWROG License Change l Requests have been approved

! - Hatch 2 March '94 l - Limerick 1,2 February '95 l - Duane Arnold February '95 l

} - Susquehanna 1,2 August '95 l l - LaSalle 1,2 April '96 i

j e Others have completed seismic i

verifications:

- Hope Creek

- Perry

- Hatch 1

- Nine Mile Point 2

- Oyster Creek

- Peach Bottom 2,3

- Brunswick 1

- WNP-2

- Browns Ferry 2,3 TAG 95-67 I

!..' MSIV LEAKAGE CLOSURE i

i Issues: \

! . Generic approval of NEDC-31858P Revision 2 l (Submitted by BWROG in September 1993) i - RAIissued March 29,1995 l - BWROG response transmitted February 19,1996 l - Conference call held on May 9,1996 to discuss

! BWROG response along with newNRC questions

! > Reliability of the alternate pathway, include l boundary valves in plant ISI program [new]

l > Seismic adequacy of condenser structural members in addition to anchorage [new]

> NRC will review results of Conservative Deterministic Failure Margins (CDFM) methodology on plant specific basis (RAI #8)

> For seismic database, clarify method used to estimate distance between the facility and the fault rupture (RAI #11)

Actions:

. BWROG to revise RAI response

- Target resubmittal December 1,1996 TAG 95-85

MSIV LEAKAGE CLOSURE i

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l Current

Participants:

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. CP&L NMPC

! Centerior NSP l l Comed PECC Energy

! DECO PP&L

Entergy Operations TVA Southern Nuclear Supply System l

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

MSIV LEAKAGE CLOSURE 1991 1992 1993 1994 1995 1996 1 ID Task Name 1 l2 l3 l4 1 l2 l3 l4 1 l2 l3 l4 1 l2 l3 l4 1 l2 l3 l4 1 l2 l3 l4 1 l2 1 BWROG Submittals 2 NEDC-31858P Rev 1 '

10/1 3 NEDC-31858P Rev 2 4 gj 4 Response to3/29/95 RAI k 2/19  ;

G Revise response to RAI i

6 NRC Review '

7 NEDC-31858P i

8 RAl/NEDC-31858P

$ 3/29 9 Hatch 2 ,

i 10 Limerick 1,2 .

11 Duane Amold 12 Susquehanna 13 LaSalle 1

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f Task _

Summary Rolled Up Progress -

Project BWROG Date: 10/2/96 Progress -

Rolled Up Task Milestone $ Rolled Up Milestone h Page1

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I l 4 FEEDWATER NOZZLE INSPECTION  !

l (NUREG 0619)  ;

i i i j NRC/BWROG MANAGEMENT MEETING 3

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i OCTOBER 23,1996 ROCKVILLE, MD

FEEDWATER NOZZLE INSPECTION Committee Objective . Obtain NRC approval of BWROG recommendations for feedwater nozzle inspections intended as an alternative to NUREG-0619 Presentation Objectives: . Obtain status of NRC review

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i 1 FEEDWATER NOZZLE INSPECTION i

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Background:

• NUREG-0619 issued in 1980 as a

! result of feedwater nozzle l cracking i

, . Due to lack of con 0dence in UT at the time, periodic liquid penetrant testing and frequent UT exams required l

. Improvements in UT and installation of new nozzle designs allow changes to inspection type  !

and frequency l

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.. o L. FEEDWATER NOZZLE INSPECTION i

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i. /ssues . Generic BWROG Report l (alternative inspection require-i ments) submitted for NRC review i October 1995 Would eliminate PT exams and

increase period between UT

exams l

. NRC issued letter (5/28/96)

l review of BWROG submittal will l be complete before Fall 1996 l outages {

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In the interim, NRC will approve i I

deferral of PT exam for one j operating cycle on a plant-i specific basis I . Proposed UT frequency still under

! review i

e i Actions

• NRC to complete review of l BWROG submittal addressing l.

PT and UT frequency issues l

a:nrefwn. doc

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FEEDWATER NOZZLE INSPECTION i

i l

i l Participating i Utilities; i

4 i

SNC DECO NYPA PP&L l CP&L Entergy NMPC PSE&G l Centerior GPU-N NSP TVA

! Comed IES Utilities PECO Energy WPPSS i

4 a:nrefwn. doc

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l CRD SCRAM SOLENOID PILOT VALVES i

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l

. . l

! NRC/BWROG MANAGEMENT MEETING i

l i

i 1

i 4

t I

f OCTOBER 23,1996 ROCKVILLE, MD l

i'~ SSPV COMMITTEE 4

I j Committee .

Work with GE and NRC to resolve  !

i Objective; SSPV issue I

- Monitor GE development of j replacement SSPV diaphragms 4

- Assess process root cause and l apply lessons learned to current l program 1

l - Evaluate alternative valves for SSPV application  !

! l

! - Develop recommendations for i resolution and obtain NRC  !

l acceptance Presentation

. Review status of BWROG SSPV Objective; program

. Discuss actions needed to resolve issue

SSPV COMMITTEE Background . Qualification of dual type SSPV with extended life elastomers (Viton) completed early 1994 e increase in 5% insertion scram time observed at some utilities in late 1995 (after approximately 6 months operation)

. Augmented testing recommended by RRG being performed by utilities

. GE Phenomenological root l cause report completed and i' provided for NRC review at the GE WDC offices 1

. GE qualification of replacement diaphragms complete

- Buna N (10 years)

- Viton (15 or more years)

{..

i e i

SSPV COMMITTEE

Background . Plant data suggests that j (continued) performance of existing Viton i diaphragms may be acceptable if l adequate margin exists j - Delay is small and does not i continue to increase '

i i

1

- Performance consistent with i 1

j root cause conclusions l . Proposed resolution discussed I l

with NRC with positive feedback j - Install new qualified l diaphragms and return to i, normal test schedule i

- Continue use of existing Viton j diaphragms supported by augmented testing as i

)

appropriate  !

i l - Use ITS basis and DART test j as appropriate i

j 4

4

SSPV COMMITTEE

/ssues: . NRC requires submittal of the GE root cause report on the BWROG docket as a condition for closure

! . NRC requested review of plant  ;

data demonstrating Viton delay characteristics

. NRC requested review of SSPV Committee recommendations

- Information only (approval will not be requested) r

- NRC feedback will be addressed ,

- NRC endorsementwill smooth implementation ,

. Delivery of new Viton diaphragms delayed due to production low yield rate

SSPV COMMITTEE Actions:

. SSPV Committee recommendations reviewed by BWROG with agreement to provioe to NRC for information

. BWROG reviewing GE root cause report for submittal to NRC (approval anticipated by 10/25)

- Submitta, being made for NRC information j - BWROG not anticipating NRC questions or review fees 1

. Plant data discussions with NRC are in progress l . GE working to improve producibility of Viton i

diaphragms d

i l

i

1 CRD/SSRV Committee 1996 1997  ;

ID Task Name Apr l May l Jun l Jul l Aug l Sep l Oct l Nov l Dec Jan l Feb l Mar l Apr l_May l Jun l Jul l Aug l Sep l Od l Nov l Dec 1 PhenomenoyicalRoot Cause (GE) g ,, j 2 Process Root Cause

$ 10/30 AR. Valve Evaluation 3

$ 1 011 4 AL Testing RecommeMations g 7fg7 5 Tech. Spec. Recommendations

$ 10130 8 Qualified Buna Diaphragms Available (GE)

$ 6117 7 Qualified Viton Diaphragm AvaBable (GE)

$ S/15 8 Submit GE Root Cause Report to NRC l $ 10130 9 Discuss Plant Data with NRC

$ 10/30 10 issue Recommendations for Resolution l $ 11115 11 Respond to NRC Questions 12 Coordinate Resolution M

Task Summary Rolled Up Progress N 0/10/96 ,

Milestone $ Rolled Up Milestone O Page1

1 i

i i

I l

1 CAllBRATION INTERVAL EXTENSION i

NRC/BWROG MANAGEMENT MEETING OCTOBER 23,1996 ROCKVILLE, MD

l i -

2 .

i CAllBRATION INTERVAL EXTENSION i

i i

i

! Committee . Develop methodology to extend  !

! Objective; instrumentation calibration l j interval to 45 months (36 months l plus 25%)

l

! . Obtain NRC approval of the j methodology and application l

i l Presentation . Review status of calibration

! Objective interval extension program

/i

. Express BWROG concern with NRC response to CIE submittals l

. Discuss actions needed to resolve

'ssueS I

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

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I~ CAllBRATION INTERVAL EXTENSION 4

i l Background . Calibration interval extension

offers efficient use of utility i resources in addition to providing j safety benefits

- Reduces false safety system j trips

! - Reduces radiation exposure J

i j - Increases safety system l availability i

l . Licensing Topical Report NEDC-32160P submitted January 1993 l . Discussed issues and approach at

!. meeting with the NRC in

November 1994 (agreed on

overall approach) i 1

j CAllBRATION INTERVAL EXTENSION i i

Background . Responses to NRC requestfor ,

(continued); additionalinformation (RAl) provided

- First round responses submitted Jan.1994

- Second/ third round responses plus Tech. Spec. & LTR '

revisions submitted Nov.1995 4

- Significant technical effort expended

. BWROG did not anticipate major issues because:

- Agreement reached with NRC on approach

- NRC approved basic methodology as part of Setpoint Methodology review ,

l l

6 CAllBRATION INTERVAL EXTENSION

/ssues;

• CIE approval anticipated in June 1996 time frame (supported by a i meeting to address remaining issues)

. Instead, NRC issued " status report" on technical evaluation on June 13,1996

- Identified major new issues which will require substantial BWROG resources to address

- rtot consistent with previously agreed upon approach

4 .

I i

CAllBRATION INTERVAL EXTENSION l i l i i I

4 1

Actions:

l Proposed actions to reconcile issue:

l . BWROG define concerns with NRC June 1996 l Status Report l

l . Obtain NRC staff and management input on j appropriate methodology uad basis for calibration 1 l Interval Extension Program  !

. BWROG meet with NRC staff to reconcile j remaining issues with BWROG submittals and l 1 obtain approval i

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~- ~

6 RESPONSE TIME TESTING 1

NRC/BWROG MANAGEMENT MEETING l

1 i

l OCTOBER 23,1996 ROCKVILLE, MD l

l l

l l

l l

, - . ~ .

j.. .

i +

! Response Time Testing

! . Replaced

• selected Response Time Testing (RTT) as

defined in Tech Specs with demonstration that changes l in response times beyond acceptable limits are i detectable during other routine periodic testing i

i > " Mini" FMEAs used to show that failures affecting response time would be detected via calibrations, functional tests, and/or channel checks

>

• Confirmation of response times not eliminated, alternate means provided

> Technician awareness methods employed to supplement FMEA results

. NRC approved BWROG Generic Licensing Report in December 1994

. BWROG now developing technical basis for replacement of additional selected RTTs not covered in NRC approved Licensing Report l

l 1

TAG 96-88  !

)

1 t

4 i

4 STATUS ON ACTION ITEMS i

FROM JUNE 13,1996 MEETING  :

i

l l l i

i

, NRC/BWROG MANAGEMENT MEETING i i

i l

1  !

OCTOBER 23,1996 ROCKVILLE, MD

i .-

ACTION ITEMS from JUNE 13,1996

, NRC/BWROG Management Meeting i 1 l 1. Utilities individually close Near Term Operating j License SRV Surveillance reporting on their i dockets i

! > BWROG has reminded utilities of this action l

l 2. BWROG provide NRC with the consensus rationale of why they will retain lower water level control procedure for ATWS l;

j > BWROG documenting rationale for NRC

3. BWROG summarize for NRC Hope Creek Shutdown event lessons learned communicated to BWROG utilities

> Summary available

4. BWROG hold meeting or conference call with NRC to review progress towards closure on the Dual ASCO Scram Solenoid Pilot Valve delayed . scram

> Conference call held

%EL"

9 t

i BWR UTILITY BRIEFING ON REFUELING SHUTDOWN RISK (including Hope Creek Lessons Leamed)*

i I

1 4

. Lessons learned from recent shutdown events and experience l e Good practices that utilities have found to minimize shutdown

risk

. Examples:

j > Identify and highlight defense in depth systems and their j safety function on the master outage schedule (level 1) '

and/or on the daily outage status / summary report

> If a full core offload has been accomplished, evaluate and communicate the time to boil of the fuel pool 1

> Consider maintaining all RHR shutdown cooling paths I

available until cavity is flooded-up and refueling gates are

removed

> Consider adopting a procedure or process that avoids a shutdown cooling bypass due to opening of recirculation pump suction and discharge valves at the same time

(SIL 069)*

TAG 96-89

)

j

,{

• BWR UTILITY BRIEFING ON REFUELING SHUTDOWN RISK (including Hope Creek Lessons Learned)*

(Continued)

> Results confirm that RHR heat exchanger temperatures correlate well with bulk coolant and core exit temperatures *

> Results confirm significant margin exists when water level is maintained above the turraround point if shutdown cooling is lost for short time periods *

> Schedule fuel pool cooling work as much as possible on-line and late in the operating cycle i

J 1

1 d

I 1

TAG 96-89 1