ML17252A721

Forwards NRC Evaluation of SEP Topic VII-3.A Re Station Battery Capacity Test Requirements & Recommendations to Modify Tech Specs.Need to Implement Changes Will Be Determined During Integrated Plant Safety Assessment

ML17252A721
Person / Time
Site:	Dresden
Issue date:	07/07/1981
From:	Crutchfield D Office of Nuclear Reactor Regulation
To:	Abel J COMMONWEALTH EDISON CO.
References
TASK-08-03.A, TASK-8-3.A, TASK-RR LSO5-81-07-009, LSO5-81-7-9, NUDOCS 8107130385
Download: ML17252A721 (3)

Text

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Docket No.

50~237 LS05 07-009 Mr. J

• S. Abe 1 Director of Nuclear Licensing Commonwealth Edison Company Post Office Box 767 Chicago, Illinois 60690

Dear Mr. Abel:

July 7, 1981

SUBJECT:

SEP TOPIC VIII-3.A, STATION BATTERY CAPACITY TEST REQUIREMENTS, SAFETY EVALUATION FOR DRESDEN 2 The enclosed* s~aff safety evaluation is.based on a contractor's document that has been made available to you previously., This document supports the findings of the staff safety evaluation on Topic VIIl-3.A and recom-mends modifications to the Technical Specifications.

The need to ae:tually implement these changes w111 be determined during the integrated plant safety assessment. This topic assessment may be revised in the future if your facility design is changed or if NRC criteria relating to this topic are modified before the integrated assessment is completed.

Enclosure:

As stated cc w/enclosure:

See next page Sincerely, Dennis M. Crutchfield, Chief Operating Reactors Branch #5 Division of Licensing

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NRC FORM 3181101801 NRCM 02<40

• OFFICIAL RECORD COPY

• USGPO: 1980-329-824:

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TOPIC:

VI H-3.A STATION BATTERY CAPACIT.Y TEST.REQµ,IR~~1ENTS I.

• INTRODUCTIOK*

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• To assure that the onsite Cl ass 1 E battery tap9ci.ty;; is adequate to * *

. supply de. PO\\\\ler to a 11 safety rel at.e,c:Wloads. requfre1d by the accident analyses.:ci'nd *is,,\\terified on a perioaic;basis, we *r.eviewed the Tech-.

nical Specifications, including the test program,- wTth regard to the.

. requirement for periodic sur~llance testing of onsite Class lE bat-teries and the extent to whi~h the te~t meets Sectfon.5.3.6 of IEEE St. 308~ 1~71, to :determine* battery capacity.

This effort is needed to ensure that*the test to determine battery capacity includes (1) an ai::.ceptance.test of. ba.ttery capacity.perform-ed in accordance.with Section 4.1 of.IEEE Std. 450-1975, (2). a per-formance discharge test listed in Table 2i6f IEEE Std. 308-1971, performed according to Sections 4.2 and 5.4 of.IEEE Std. 450-1975; and (3) a battery service'.test described in Section. 5.6 of IEEE Std..

450~1972, to be performed during ea.ch refueling operation.

II.

REVIEH CRITERIA The review criteria are presented in ~G&G_Report 1314F, "Battery Capacity Tests.. "

III.

RELAiED SAFETY TOPICS AND INTERFACES None IV.

REVIEW GUIDELINES See Introduction.

V.

EVALUATION The Dresden *unit 2 battery surveillance 'requirements are.included in Section 4.9 of the station Technical Specifications.

There are no periodic battery service tests required.

Furthermore, the load discharge test does not appear to verify the require.cl 80%

- capacity.

Therefore, the Dresden 2 does not comply with the

• current licensing requirements for station battery capacity_ tests.

VI.

CONCLUSION The staff proposes that the testing of the batteries be in accor-

. dance with IEEE Standard 450-1975, IEEE Standard_ 308-1974, BTP EICSB 6,.and the "Standard Technical Specific;ations for.General; Electric Boiling Water Reactors 11 (NUREG-0123).

The proposed,tests are as follows:

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At least once per. 18.month~, *during sh_utdown,.a battery.service test s'houl d.be performed to verify that the battery capacity is*

adequate to supply and maintain** in operable, status all of the..

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. actual emergency,loads* f o.r two* hours.

,.2.. At. least one~ per 60 months~. during, shutdown, a battery discharge

• *.. test should Qe per:formed to verifY.* that the battery capac~ty is atleast 80%.o'f.the manufac~urer:'s rating;*.... *.. *~-

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