ML20012E109

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Summary of 900202 Meeting W/Seismic Qualification Util Group Re USI A-46 on Seismic Qualification of Equipment.Issues to Be Resolved Include Use of 3 X Dead Weight as Screening Method for Evaluation of All Cable Trays.Viewgraphs Encl
ML20012E109
Person / Time
Issue date: 03/13/1990
From: Sears P
Office of Nuclear Reactor Regulation
To: Wessman R
Office of Nuclear Reactor Regulation
References
REF-GTECI-A-46, REF-GTECI-SC, TASK-A-46, TASK-OR NUDOCS 9003300079
Download: ML20012E109 (20)


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UNITED STATES l

NUCLEAR REGULATdRY COMMISSION i

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March 13,1990 Docket Hos: See Attached List l

t MEMORANDUM FOR: Richard H. Wessman, Director 4

Project Directorate 1-3 Division of Reactor Projects FROM:

Patrick M. Sears, Lead Project Manager Multi-Plant Action B105 Project Directorate I-3 Division of Reactor Projects

SUBJECT:

SUMMARY

OF MEETING WITH SEISMIC QUALIFICATION UTILITY GROUP (SQUG)CONCERNINGSEISMICQUALIFICATIONOFEQUIPMENTUSIA-46 L

On February 2, 1990, the NRC staff met with representatives of SQUG concerning the current status of the SQUG 3rogram for resolution of USI A-46 and to reach egreement on actions to bring tie program to closure. The main points discussed and agreements reached are summarized as follows:

1.

Status of SOUG program and SQUG's position on open issues.

Mr. N. P. Smith, SQUG Chairman, presented a sumary of the status of the

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SQUG program and SQUG's position on open issues affecting completion of the program. The information presented by Mr. Smith is given in i.

In sumary, Mr. Smith indicated that SQUG has been actively proceeding'with development of technical criteria for resolution of USI L.

A-46, despite the lack of formal acceptance of certain elements of the progran by the NRC in the form of Supplement 1 to their generic Safety E

EvaluationReport(SER). He indicated that SQUG is reluctant to expend L

substantial additional resources in the training program detelopment.and L

implementation without resolution of-(1) the legal challenge to use of GenericEquipmentRuggednessSpectra(GERS)and(2)openlicensingissues, b

Dr. Richardson and Mr. Marsh acknowledged that they understood the SQUG' I-position. They also indicated they wish to make clear the NRC's position on.USI A-46, which is to implement resolution of USI A-46 as soon as possible,' independent of future programs which may impact USI A-46 such astheIndividualPlantExaminationforExternalEvents(IPEEE).

However, they indicated that utilities would be prudent to coordinate any data gathering needed for IPEEE with the USI A-46 walkdowns. They indicated that necessary guidance for the IPEEE data gathering will be

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issued by the NRC in time to support this approach.

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. March 13,1990 2.

Legal challenge by Westinghouse to GERS.

Westinghouse transmitted a letter to the NRC in late 1988 which challenges the use of the SQUG/EPRI Generic Equipment Ruggedness Spectra (GERS) by the NRC. The NRC has not responded officially to the Westinghouse legal i

challenge. The NRC staff representatives indicated that they are presently preparing a negative consent position paper on this issue which will be submitted to the NRC Comissioners in the next few weeks. This position paper is expected to state that the NRC staff does not agree with the Westinghouse challenge of the use of the GERS by the NRC. The negative consent position paper will indicate that if the Comissioners do not disagree, the staff will proceed and allow the use of GERS for equipment verification, Dr. Richardson suggested that the SOUG utilities may wish to explore this matter further with Westinghouse in parallel with the NRC's disposition process. The timing for resolution of this issue is i

j unclear, >ut it is unlikely to be resolved in less than two months.

SQUG representatives advised that the use of the EPRI/SOUG-developed GERS is an essential element of the SQUG generic program, particularly for equipment not included in the experience data base and for equipment L

installed at high elevations in nuclear plants. They also noted that GERS and similar published data mey be needed for planned future seismic evaluations such as the IPEEE.

l 3.

Licensing Issues The ettendees discussed the licensing issues which are considered signifi-cant by SQ'JG for which formal NRC acceptance has not been received. The nainissuesare(1)whethertheUSIA-46rulescanbeusedforseismic verification of new and replacement equipment in A-46 plants, and (2) whether the plant's licensing basis for seismic qualification of ecuipment can be changed to be consistent with the use of A-46 rules.

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tir. Schmidt (P.PR) sumarized the NRC's position on the use of USI A-46 1

rules for new and replacement equipment as presented officially in NRC Generic Letter 87-02 and as given to SQUG by the NRC staff (Mr. Marsh) during several previous SQUG/NRC meetings. This infornetion is summarized in Enclosure 2.

The NRC staff acknowledged the correctness of SQUG's presentation of the NRC's post position on this subject and indicated that the NRC's positions l

on these licensing issues are currently being reevaluated by the NRC staff.

They stated that the NRC positions on ti,ese issues will be promulgated officially in the NRC's SER supplement which should be issued within 60 days. Based on the discussions at this meeting, it was agreed that the HRC SER supplement need not address the SOUG technical criteria since the i -

technical information in Revision 1 of the GIP has been significantly 1-revised.

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, March 13,1990 1

SQUG representatives expressed concern that the NRC has found it necessary to reevaluate their long-standing position on the application of USI A-46 rules to future equipment applications.

SQUG representatives noted that a change in the NRC position would likely result in reevaluation of utility plans for resolution of USI A-46, 4.

Technical Issues

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SQUG representatives advised that essentially all of the open technical issues have been resolved between SQUG, SSRAP and the NRC staff, leaving only two issues on which SQUG and the NRC have chosen to disagree. These two issues are:

o The use of 3 X Dead Weight as a screening method for evaluation of all calde trays; and The use of 7 versus 6 as the generic amplification factor for relays o

installed in switchgear.

The letter issue on use of an amplification factor of six or seven for switchgear is not expected to have a significant impact on the seismic verificction of switchgear.

In the case of the 3 X Dead Height screening criteria for cable trays, SQUG proposed a compromise approach for resolu-tion cf this issue. The compromise is that SQUG could eccept the use of 3 X Dead Weight as_a screening criteria for all cable trays with the under-standing that the alternative lateral load c. heck, described in the E0E cable tray report, would be an acceptable approach for resolving outliers which do not meet this 3 X Dead Weight vertical capacity check. This compronise would retain the cencept that the screening criteria would flag those cable trays which are not consistent with the earthquake experience data base, yet provide reasonable, fWst principlet approach to resolve outliers which would result from this screening check. The NRC staff indicated that the use of alternative lateral load check as an approach for resolvir.g outliers will be reviewed on a case-by-case basis.

5.

Future Course of Action The tiRC management representatives summarized actions which are underway by the NRC staff to resolve the open legal and licensing issues. They are proceeding to 3repare a position paper for submission to the Commissioners on the legal c,allenge to the use of GERS. This position paper will have to be reviewed by appropriate individuals in the NRC staff before submittal to the Commission.

In parallel, the NRC staff will prepare and issue an SER supplement covering t!.e open licensing issues discussed at this meeting.

This SER is projected to be issued within about 60 days.

SQUG representatives indicated that based on the discussions at this meeting, SOUG cannot proceed to cormiit significant resources until the open issues are resolved. This will likely mean that development of the SQUG training program

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4 March 13,1990 t

as well as plant. specific implementation will be delayed on a day-for. day basis until the NRC positions are received and any disagreements are i

resolved.

i includes information concerning the completion of' Generic Develop-

,i-nent Phase of USI A.46 Program. It contains projected schedules for the completion. Enclosure 2 is a brief summary of USl A.46 Application of i

New/ Replacement Equipment. Enclosure 3 is a list of persons attending the

. February 2,1990 neeting.

p Original signed by Patrick M. Sears, Lead Project Manager r

Multi. Plant Action BIOS-t Project Directorate 1 3,-

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. Division of Reactor Projects

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Enclosures:

As stated cc:

M. L. Slosson

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._ P. Y. Chen i- '

P. T. Kuo 1

L' B. Marsh a

-lJ.E. Richardson 1

'L. Shao-f, J. Partlow (4 ',

f F. Maraglia W. Schmidt (MPR Associates Inc.)

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-4 R. Schaffsta11. EPRI

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' Distribution:

_ Docket Files NRC PDR ALPDRs O. Sniczak PDI.3 Reading P. Sears M. Rushbrook OGC E. Jordan ACRS(10)

'J. Johnson, Region 1 J. Dyer, Region I Plants.17G21 R. Borchardt, Region 11 Plants-17G21 J. Clifford, Region III Plants.17G21 c

J. Sharkey, Region IV Plants.17G21

- H.B. Clayton, Region Y Plants.17G21

  • See previous concurrence 0FC: PDI-3*
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List of Docket Nos:

1 50-313 ANO 1 1

50-368 AN0 2 50-334 Beaver Valley 1 l

50-155 Big Rock Point 50-259 Browns Ferry 1 i

50-260 Browns Ferry 2 50-296 Browns Ferry 3 50-324' Brunswick 1 50-325 Brunswick 2 50-317 Calvert Cliffs 1 50-318 Calvert Cliffs 2 50-315 Cook 1 50-316 Cook 2 50-298 Cooper 50-302 Crystal River 3 50-346 Davis Besse 50-237 Dresden 2 50-249 Dresden 3 50-331 Duane Arnold 50-34B Farley 1 50-333 Fitzpatrick 50-285 Fort Calhoun 1 50-244 Ginna 50-313 Haddam Neck 50-321 Hatch 1 50-366 Hatch 2 50-247 Indian Point 2 l

50-286

. Indian Point 3 l

50-305 Kewaunee 50-309 Maine Yankee 50-245 Millstone 1 50-336 Millstone 2 50-263 Monticello 50-220 Nine Mile Point 50-33B North Anna 1 50-339-North Anna 2 50-269 Oconee 1 50-270 Oconee 2 50-287 Oconee 3 50-219 Oyster Creek 50-255-Palisades 50-277/278 Peech Bottom 2/3 50-293 Pilgrim 1 1

50-266 Point Beach 1 50-301 Point Beach 2 50-282 Prairie Island 1 50-306 Prairie Island 2 50-254 Quad Cities 1 50-265 Quad Cities 2 b

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11 50-312 Rancho Seco 50-261 Robinson 2 50-272 Salem 1 50-311 Salem 2 50-206 San Onofre 1 50 280 Surry 1 50-281 Surry 2 50-289 Three Mile Island 1 50-344 Trojan 50-271 Vermont Yankee 50-029 Yankee Rowe 50-295 Zion 1 50-304 Zion 2 F

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l L-COMPLETION OF GENERIC DEVELOPMENT PHASE OF l

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USI A-46 PROGRAM

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SQUG STEERING GROUP PRESENTATION i

To NRC MANAGEMENT 1

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2 AND ITS REFERENCE TECNNICAL I

DOCUMENTS.

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DEVELOPING A TRAINING PROGRan.

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CONDUCTED Two SYSTEMS TRAINING SESSIONS.

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RESOLVING ANCHORAGE AND RELAY EVALUATION ISSUES.

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GERS LEGAL CHALLENGE.

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OVERALL PROGRAM SCHEDULE HAS SLIPPED MORE THAN A YEAR SINCE SQUG UTILITIES SUBMITTED THEIR SCHEDULES IN OCTOBER 1988.

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l SQUG UTILITY IMPLEMENTATION SCHEDULES.WERE KEYED TO l

RECEIVING THE FINAL SER SUPPLEMENT 2 BY MAY 1989.

1 PRESENT SCHEDULE SHowS RECEIPT OF SER SUPPLEMENT 2 BY AUGUST 1990 BASED ON:

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-- RECEIPT OF SER SUPPLEMENT 1 BY FEBRUARY 1990 4

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-- NO SIGNIFICANT OPEN ISSUES IN SER SUPPL. 1 OR 2.

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~ t PURPOSE ~ OF REMAINDER OF MEETING:

Discuss APPROACHES FOR COMPLETING.THE< GENERIC DEVELOPMENT PHASE 0F-THE USI A-46 PROGRAM..

AGREE UPoN ALCouRsE OF' Actron.

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APPLICATION OF USI A-46 TO'NEW/ REPLACEMENT EQUIPMENTi y

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THE A-46 REVIEW AND RESOLUTION WILL IMPACT SEISMIC-QUALIFICATION REQUIREMENTS IN FUTURE ALSO 7

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0 APPLIES TO RkPLACEMENT EQUIPMENT ~IN A-46 SCOPE' "IF A UTILITY REPLACES COMPONENTS FOR ANY REASON', EACH REPLACEMENT r

(ASSEMBLY, SUBASSEMBLY,- DEVICE) MUST BE VERIFIED FOR SEISMIC ADEQUACY EITHER BY USING A-46 CRITERIA'AND METHODS OR, AS AN OPTION, QUALIFYING BY. CURRENT LICENSING' CRITERIA."

GENERIC LETTER 87-02 MARCH 1987 o

WILL-REQUIRE MAINTENANCE OF QUALIFICATION STATUS i

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NRC STAFF POSITION i

USI A-46-CRITERIA (GIP) ACCEPTABLE FOR NEW/ REPLACEMENT PARTS SUBJECT T0:-

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- i EQUIPMENT IS IN ORIGINAL A-46: SCOPE (ON SSEL)

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Ir NOT ON SSEL, EQUIPMENT IS-WALKED DOWN AND HEETS GIP REQUIREMENTS 0-GIP IS MAINTAINED AS A WORKING DOCUMENT, 5

CNANGES. APPROVED BY NRC EXCEPTION:.

L A-46 CRITERIA CANNOT SUPERSEDE / REPLACE ANY PLANT-SPECIFIC COMMITMENTS TO MEET HORE DEFINITIVE REQUIREMENTS (I.E., IEEE)

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i 1 Determination of Seismic Qualfication Requirements:

e Specific Licensing Commitments e USI A-46 Scope -

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Apply' Specific.

Yes There with NRC approval, where require )

Requirements Licensing L

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A-46 Scope Apply Original (on SSEU Recuirements

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Select Candidate Ewipment,

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are Met-ana Seismic is the Capacity is Adecuate.

Are Original Ong.nal Yes Seismic v

Requirements Design Basis 7

Appropnate Clearly Specif y Special gip installation

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Defined Requirements and Checks in

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Installation Specification 1

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Revise FSAR to Perform Verifications, invoke A-46/GlP Prepare Selsmic Qualification-Requirements Documentation, and Sign-Of f OVERALL STEPS IN APPLYING GIP SEISMIC VERIFICATION CRITERIA TO NEW AND REPLACEMENT EQUIPMENT FIGURE 1 i

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