ML17279A903

Application for Amend to License NPF-21,revising Tech Specs to Reflect Rev of Dc Sys Battery Calculations.Fee Paid

ML17279A903
Person / Time
Site:	Columbia
Issue date:	03/18/1988
From:	Sorensen G WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML17279A904	List: ML17279A903 ML17279A905
References
GO2-88-065, GO2-88-65, TAC-67620, NUDOCS 8803250310
Download: ML17279A903 (7)

Text

ACCELERATED %IBUTION DEMONSRaION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:8803250310 DOC.DATE: 88/03/18 NOTARIZED- YES DOCKET g FACIL:50-3%7 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH. KAME AUTHOR AFFILIATION SORENSEN,G.C. Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Application for amend to License NPF-21,revising Tech Specs .

to reflect rev of DC sys battery calculations. R DISTRIBUTION CODE: AOOID COPIES RECEIVED:LTR [ ENCL I SIZE: 5 +9 TITLE: OR Submittal: General Distribution NOTES RECIPIENT COPIES RECIPIENT COPIES ID PD5 LA CODE/NAME SAMWORTH,R LTTR ENCL 1

1 0

1 ID PD5 PD CODE/NAME LTTR ENCL 5 5 j A

INTERNAL: ARM/DAF/LFMB 1 0 NRR/DEST/ADS7E4 1 1 NRR/DEST/CEB8H7 1 1 NRR/DEST/ESB 8D 1 1 NRR/DEST/MTB 9H 1 1 NRR/DEST/RSB 8E 1 1 NRR/DOEA/TSB11F 1 1 N ~5AS/ILRB12 1 1 OGC 15-B-18 1 0 EG FI 01 1 1 j RES/DE/EIB 1 1 8

EXTERNAL: LPDR 1 1 NRC PDR 1 1 NSIC 1 1 R

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'A TOTAL NUMBER OF COPIES REQUIRED: LTTR 21 ENCL '8

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Washington Public Power Supply System 3000 George Washington Way P.O. Box 968 Richland, Washington 99352-0968 (509)372-5000 March 18, 1988 G02-88-065 Docket No. 50-397 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Gentlemen;

Subject:

NUCLEAR PLANT NO. 2 OPERATING LICENSE NPF-21 RE/VEST FOR AMENDMENT TO TECHNICAL SPECIFICATION 3/4.8.2, DC SOURCES Refer ence: 1) Letter, JB Mar tin (NRC RV) to GC Sorensen (SS), "NRC Inspection at WNP-2", dated December 8, 1987 (NRC Inspection Report 50-397/87-19)

2) Letter, G02-88-025, GC Sorensen (SS) to NRC, "NRC Inspection Report 87-19", dated 1/29/88 In accordance >lith the Code of Federal Regulations, Title 10, Parts 50.90 and 2.101, the Supply System hereby submits a request for amendment to the WNP-2 Technical Specifications. Specifically, the Supply System is request-ing that the battery duty cycles (load profiles) for the Division 1, 2 and 3-125 Volt DC Power Systems, and the Division 1-250 Volt DC Power System, be revised per the attached page (3/4 8-13). This is being done to reflect the results of our recent revision of the DC system battery calculations.

During the period August 3 through August 28, 1987 the NRC conducted a special team Safety System Functional Inspection (SSFI) to assess the opera-tional readiness of selected safety systems at WNP-2. As a result of that inspection, Unresolved Item No. 87-19-01, Class 1E Battery Sizing was iden-tified. The issue dealt with specific instances of incorrectly translating the design basis for certain batteries into plant documents (Battery Calculations). The recalculation effort has now been successfully completed, and has resulted in this request for amendment to Technical Specification 3/4.8.2. Specifically, the battery load profiles contained on page 3/4 8-13 are being modified to reflect the results of the calculation revision.

8803250310 880318 PDR ADOCK 05000397,'CD

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Page Two REQUEST FOR AMENDMENT TO TS 3/4.8.2, DC SOURCES The calculations revised are No. 2.05.01, Battery and Battery Charger Calculation (250VDC, 125VDC, and 24VDC Systems) and E/I-02-85-02 (Hi gh Pressure Core Spray DC System). The r evisions utilized the calculation methodology described in IEEE Standard 485-1983 and the manufacturer's performance data for the installed cells. The load profile for each battery was redefined eliminating the inconsistencies between the one line drawing (E505), inverter loads and efficiencies, and starting currents for valve and pump motors identified during the SSFI. Additionally, factors for temperatut e correction (to account for t)e Technical Specification allowable minimum electrolyte temperature of 60 F), aging and design margin were included in the sizing calculations. All loads were reevaluated and accounted for.

The calculation revisions reconfirmed that the installed battery systems are capable of withstanding the in-rush values without exceeding the batteries'ne minute ratings and are capable of meeting their respective duty cycles as well as fulfilling the operability requirements of 4.8.2.1.

The Supply System has reviewed the revision to the load profiles for the subject batteries per 10CFR50.59 and concluded that it does not involve an unreviewed safety question. The Supply System has also evaluated this request per 10CFR50.92 and provides the following in support of a finding for no significant hazards consideration. This change does not:

1) Involve a significant increase in the probability or consequences of an accident, previously evaluated because no new loads are being placed on the batteries that they wer en't capable of handling prior to the recal-culations, nor are the revised Technical Specification duty cycles beyond the ability of the equipment.

2) Create the possibility of a new or different kind of accident from any previously evaluated because the batteries themselves are not being changed, nor are any changes being made to the way they were being utilized or asked to perform. The additional loads that were added from a calculation standpoint did not result in any changes to the batteries themselves, as they were still capable of fulfilling the licensing bases requirements.

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Page Thr ee RE/VEST FOR AMENDMENT TO TS 3/4.8.2, DC SOURCES

3) Involve a significant reduction in a margin of safety because even after adding additional conser vatism to the calculations, the require-ment that the battery capacity be at least 80% of the manufacturer's rating when subjected to a performance discharge test remains unchanged, as do the other requirements of 4.8.2.1. The effect of the increased duty cycle is to potentially shorten the lifetime of the battery.

As discussed above, the Supply System considers that this change does not involve a significant hazards consideration, nor is there a potential for significant change in the types or significant increase in the amount of any effluents that may be released offsite, nor does it involve a significant increase in individual or cumulative occupational radiation exposure.

Accordingly, the proposed change meets the eligibility criteria for cate-gorical exclusion set forth in 10CFR 51.22(c)(9) and ther efore, per 10CFR 51.22(b), an environmental assessment of the change is not required.

if It should be noted that the proposed change is not approved prior to the next scheduled confirmation of load profiles, the test will be performed using the summation of the most conservative requirements.

This Technical Specification change has'een reviewed and approved by the WNP-2 Plant Operations Committee (POC) and the Supply System Corporate Nuclear Safety Review Board (CNSRB).

In accordance with. 10CFR170.21, an application fee of One hundred fifty dollars ($ 150.00) accompanies this request. In accordance with 10CFR 50.91, the State of Washington has been provided a copy of this letter.

Should you have any questions, please contact Mr. P. L. Powell, Manager, HNP-2 Licensing.

Very truly yours, G. C. Sorensen, Manager Regulatory Programs HLA/bk Attachments cc: C Eschels - EFSEC JB Martin - NRC RV NS Reynolds - BCP8R RB Samworth - NRC DL klilliams - BPA/399 NRC Site Inspector - 901A