ML20236S326

Provides Position on Staff Guidance Identified in Generic Ltr 87-02, Verification on Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Usi A-46. Generic Implementing Procedure Will Be Completed in 1988

ML20236S326
Person / Time
Site:	Point Beach, Cooper
Issue date:	10/09/1987
From:	Smith N SEISMIC QUALIFICATION UTILITY GROUP
To:	Murley T Office of Nuclear Reactor Regulation
Shared Package
ML20236S283	List: ML20236S281 ML20236S326
References
REF-GTECI-A-46, REF-GTECI-SC, TASK-A-46, TASK-OR GL-87-02, GL-87-2, TAC-64912, NUDOCS 8711250062
Download: ML20236S326 (12)

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- 9,51987.

October y,

oDr.' Thomas E.;Murley,7 Director

. Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission A

Washington, D.C.

20555

Subject:

' -Seismic Qualification Utility Group Response to Generic Letter 87 Recolution of USI A-46 Dearsorg Murleys g b;.h y.g 13 qg. A; e g gay 43 qy,

.On February 19, 1987, the NRC issued Generic Letter 87-02, i

• Verification of:Seicmic Adequacy of Mechanical and Electrical

' " ^

? Equipment in Operating-Reactors, Unresolved Safety Issue (USI) n*

'A-46."

TheLGeneric Letter provided guidance for resolution of USI 7"

1A-46'and requested that licensees submit a schedule within sixty

, days for final resolution of'the issue using that guidance.

In a

= letter to the NRC's Office ' of Nuclear Reactor Regulation (NRR)

' dated g ril'10, 1987, the Seismic Qualification Utility Group

.i

-(SQUG)-

(1). requested an extension.of the generic letter's sixty-day-response period until final implementation guidance had Jbeen provided to industry,>and (2)' stated its intention to provide 5z comments on-the'. Generic' Letter's guidance.

The Staff's response,

. dated April' 28,.1987, extended the sixty-day reporting period with

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.an'end date of December 1, 1987.

The purposes of this letter are 1

(1) to provide.SQUG's positions on Staff guidance identified in

Generic Letter 87-02 and (2) to. provide the SQUG generic program

~ schedule.

i, SQUG.is currently developing the " Generic Implementation

?

, Procedure for Verification of Seismic Adequacy of. Nuclear Plant Equipment" (GIP) for use by its members.

This Procedure will be in.three parts.

Part 1 provides SQUG's positions relative to l

. Generic' Letter 87-02.

A copy of Part 1 is attached (Attachment 1)

.to this letter for your review and comment.

Part 2 is a detailed

' technical document containing criteria and associated guidance for L

l' 1

1/l SQUG is currently composed of 38 member utilities who are each holders of one or more operating licenses.

The Group has worked closely with EPRI over the past several years to provide information to the Staff to assist in resolution of USI A-46.

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.1The. initial draft of Part 2 was issued for 05

.USI~A-46' resolution.

NRC Staff; review in April, 1987; a revision based on preliminary f

SQUG' member,.NRC Staff-and Senior Seismic Review and Advisory comments was~ issued for Staff revieu on September 2, L Panel' (SSRAP)

(including a relay evaluation procedure, but excluding

1987, seismiciverification procedures for cable tray and conduit, heat exchangers,:and tankc,'which are still under development).

Part 3 T

willyconsist of:a' series of training ceminare to be eponsored by

Initial: training l materials will be provided to the Staff in J

SQUG.

-November;1987.

The.first trial. training seminar will be conducted in'DecemberL1987.

,We' request.the Staff have representatives f.

Lattend this seminar.

1

~"

l

'Itfis-expected that the Staff'will review and provide com-J J

Iments cnr the' GIP and its revisions as lessons are learned through Following' review of all three parts of the final GIP, trial use'.

an NRC-Safety Evaluation Report (SER) is' expected.

Based on our

~

' currentCs'tatus andethef schedules, present9d to;the Staff in June j

and; August, 1987, we expect'a: GIP addressing the^ initial scope of

However, USI A-46 to be'available by the.second quarter of 1988.

.a complete GIP' addressing the.' detailed requirements of the Generic LetterLregarding seismic verification of_ cable trays and conduit,

-heat exchangers and tanks and relays is not expected to be available until the Jend-of 1988.

l

'It'is our beliefithat the schedule provided is responsive to

.thefinterest of the NRC Staff. summarizes the major tasks / activities:and associated milestones.

Please note that

" timely NRC-reviews.of the draft reports and procedures.are a requirement'in order to meet this schedule.

Sixty days following receipt'of the NRClSER'on the complete GIP is a feasible schedule r

forLSQUG' licensees to provide plant-specific schedules for final U

'A-46' resolution.

SQUG intends that this letter satisfy the December 1, 1967 1987 letter for 2 4

. response: requirement imposed by your' April.28,

. licensees participating in the SQUG program to resolve USI A-46.

We would be pleased to answer any questions you may have or to meet with'you regarding the positions taken in this letter.

Sincerely, i

/

Neil P. Smith, Chairman l

Seismic. Qualification Utility Group Encl.

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Attachment I i

. GENERIC IMPLEMENTATION PROCEDURE FOR VERIFICATION k

OF. SEISMIC ADEQUACY OF NUCLEAR PLANT EQUIPMENT

-SQUG Response to Generic Letter 87-02 Part 1:

7

. Introduction, On February. 19, 1987, the NRC Staff issued Generic Letter 87-02, " Verification of Seismic Adequacy of 1:echanical and Elec-trical-Equipment'in Operating Reactors, Unresolved Safety Issue a

The, enclosure to the Generic Letter, entitled

" Seismic Adequacy verification Procedule," contains implementation (USI) A-46,"

guidance for generic and plant. specific resolution of A-46.

SQUG'is' developing the " Generic Implementation Procedure for (GIP)

. Veri,fication of; Seism,1c Adequacy of Nuclear Plant Equipment Part 1 for use by its' member's.

This Procedure.is in three parts.

Part provides SQUG's positions relative to Generic Letter 87-02.2 Part 3 ciated guidance for plant-specific resolution of USI A-46.-

consists of~the series'of training seminars sponsored by SQUG.

At LThe complete GIP'is expected to be reviewed by the NRC Staff.

'the completion of this review an.NRC Safety Evaluation Rep

- (SER) methodology..

. It'is the purpose of this part of the GIP to provide the SOUG SQUG l position with respect to Generic Letter 87-02 guidance. maintain The GIP provides the technical USI~A-46 are reflected in the GIP.

approach, generic procedures and documentation guidance which can be utilized by SQUG licensees to evaluate the seismic adequacy of l

t

. mechanical and electrical equipment needed to bring their p an s to'a safe shutdown condition following a Safe Shutdown Earthquake To the. extent that the GIP and the Generic Letter appear J

inconsistent, SQUG members will be guided by the GIP, which, (SSE).

I previously noted, SER.

GENERAL COMMENT

S It is SQUG's understanding that the Generic Letter is As such, the use of what l'..

intended as a guidance document.

(e.g., "must")

j would appear to be unduly restrictive language is confusing and would be interpreted to reduce the flexibil-f SOUG members will ity to effect resolution of USI A-46.

l continue to interpret the Generic Letter as guidance.

I The Senior Seismic Review and Advisory Panel (SSRAP) was established to provide technical review of SQUG efforts to 2.

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resolvel USI

A-46 by using : experience. data on. equipment in i

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1. ig W 3 industrial 1 facilities which.had been subjected to-strong-b*

motion' seismic..eventst SSRAP's functions'and responsibili-h~

'3" jtiesLwere? defined and? agreed upon mutually by SQUG and the

,e n iM NACLStafflin 1982.

Its tenure was4 envisioned as. coming to an

's "

jsnd;as afgroupLat_the completion of'the development of the SQUG. generic' program..,SQUG does notlintend for SSRAP to d; g,,m-

, participate {in!the: plant-specific implementation of the USI 4

,l?

LA-462 resolution.1 Furthermore,:the specific. tasks which it' P

J

-Liperforms are assigned and reviewed by SQUGfandithe.NRC Staff.

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Tasks'areinever assigned byreither organization without the g

s awareness'ofJthe.other.e The tasks which are assigned require N

La. response?-- be it letter, meeting minutes or a; report.- The 1

U

~ ; task assignments and; responses may warrant, in'some instan-7ces,freview"by both SQUG;and the. Staff,"but'they do not require: concurrence.n 8,y y y w

W]3,

, Licensees-are:.rgquired"under lhp,F.R..SS50.7,2 and 50 73,and Jby MeMinicalliiipecificatioM toi report any plant conditi'en 4 fwhich'would have'a'significant adverse effect on. safety.

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, i:,.,

pm SQUG does'not believe that the Generic Letter imposes any l

Jadditional= reporting requirement.or requires' preparation of a l

6p justification-for continued operation (JCO) unless nece.ssary

)

W lto meet existing' regulatory requirements.

Accordingly,~SQUG j

M'f

. licensees;arefrequiredito report only conditions discovered lduringtheA-46:reviewwhichmeetthereportingthresholdsof

'J theDregulations.or. plant-specific technical specifications, J

(and:will not? provide /JCos unless warranted by~the existing

. reporting. requirements:noted above.

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J4' sTheienclosure-to'the GenericLLetter provides for the submit-

'talfofranLinspection report by each licensee upon the comple-

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a tion.of the, plant'walkdown..SQUG maintains that licensees

'which arel utilizing the GIP.for resolution may satisfy this M.

report provisionTby referencing the GIP and providing a i*

m plant-specific inspection summary report, including a pro-posed; schedule for future' modifications and replacements, l

j-y F,

-where appropriate.

Any reportable conditions discovered y

lduring the walkdown will be treated as discussed under i

M, general > comment 3.

1

'f 5.

TheLiGeneric; Letter provides that in addition to the report I

noted in comment 4 above', licensees should submit a final H,,

. report certifying completion of reviews and completion of lresulting modifications and replacements.

The Generic Letter 7

' suggests that plant-specific SERs will not be issued until

+

this second1 report is submitted by the licensee.

SQUG main-

.tains;that a;second' report providing certification of comple-4 tion.of necessary modifications and replacements is not only lnot warranted,-but also contrary to Staff practice in other Lareas,.i.e.,' licensees do not submit such certifications on

'other-issues of equal safety significance.

Further, SQUG submits.that'an~SER can and should be issued after review of the:. licensee summary report noted in comment 4.

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SQUG. maintains that in the Staff's two-stage backfitting 26.

analysis when a licensee has identified discrepancies in its m

s summary report' (see comment 4, above) and provided justifica-l tion for notfperforming corrective modification or rep ace-ment, the Staff must provide a backfitting analysis before

.c

. ordering corrective. modifications or replacements.

Ssecific Comments Inithe section-by-section analysis.below, specific SQUG

.fpositions are stated corresponding to specific statements in U1 Generic. Letter'87-02.

Some of.the above' general comments are j

t

. restated in. connection with specific language in the-General g.

' Letter.

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