ML17285A571

Safety Evaluation Supporting Amend 68 to License NPF-21

ML17285A571
Person / Time
Site:	Columbia
Issue date:	06/06/1989
From:	Office of Nuclear Reactor Regulation
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ML17285A569	List: ML17285A568 ML17285A570 ML17285A571 ML17285A572
References
NUDOCS 8906260288
Download: ML17285A571 (6)

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NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION BY THE OFFICE. OF. NUCLEAR-REACTOR-REGULATION SUPPORTING AMENDMENT N0.68 TO FACILITY.OPERATING-LICENSE NO. NPF-21 WASHINGTON PUBLIC POWER SUPPLY-SYSTEM

.NUCLEAR PROJECT.N0.-2 DOCKET-NO. 50-397

1.0 INTRODUCTION

By letter dated March 18, 1989, Washington Public Power Supply System proposed certain changes to thI. Technical Specifications for Nuclear Project No.

2 (WNP-2).

Specifically they would change the battery duty cycles (load profiles) for division 1, 2, and 3 125 volt. DC and division 1 250 volt DC power systems contained in Technical Specification section 4.8.2.1.d.

These changes reflect a revision to the battery calculations related to the resolution of unresolved item No. 87-19-01 resulting from the safety system functional inspection (SSFI) of WNP-2 during the period of August 3 to August 28, 1987.

The SSFI resulted in the iddntification of instances of incorrectly calculating battery loads from the plant design basis.

The licensee subsequently recalculated battery loads and determined the new battery load profiles for inclusion in the technical specifications.

By letter dated April 12, 1989, the licensee identified corrections to Technical Specification sections 4.8.2.l.e and 4.8.2.1.f to account for the fact that the aging factor for the 250 volt battery is different from the factor used for the other batteries, 2.0 EVALUATION In support of the amendment application the licensee provided the following revised calculations for staff review:

Revision 7 to calculation No. 2.05.01 covering 24, 125, and 250 volt batteries and revision 1 to calculation No.

E/I-02-85-02 covering the high pressure core spray (HPCS) 125 volt DC bat-tery.

In each calculation specific load profiles for each battery were developed based on assumed loss of coolant accident (LOCA) with simultaneous loss of offsite power (including loss of AC power to the battery chargers) for two hours.

Accident loads included valve, motor/pump, and breaker actuations as a result of the accident signals and operator actions.

Loads for miscellaneous inverters, relays,

alarms, and indicators were also included in the calculations.

Once the load profiles were developed, the licensee verified the correct sizing of the corresponding batteries utilizing methodology contained in 0

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IEEE Standard 485-1983, "IEEE Recommended Practice for Sizing Large Lead Storage Batteries for Generating Stations and Substations."

Continuous and momentary loads were included in the load profiles.

An aging factor of 25K (corresponding to a battery replacement when its actual capacity drops to 80K of its rated capacity) was used for all battery calculations except for the division 1 250 Vdc batteries.

For these, an aging factor of 20K was used.

A design margin of 10% and a minimum allowable battery voltage of 1.81 volts per cell were used in the calculations for all batteries.

An aging factor of 25K corresponds to replacement of the battery when its actual capacity drops to 80K of its rated capacity.

An aging factor of 20%,

as used in the division 1 250 Vdc calculations, would require that this battery be replaced when measured capacity drops to 83.4X of.rated capacity.

Technical Specification section 4.8.2.l.e previously only addressed verifi-cation based on the 25% aging factor.

The proposed revision includes verification of the capacity of the division 1 250 Vdc battery which uses the lower aging factor.

Since the lower aging factor is more conservative, the staff finds this revision acceptable.

The staff reviewed the battery sizing calculations submitted by the licensee.

Since the sizing methodology as recommended in IEEE Std 485-1983 and the 2-hour scenario are consistent with current staff guidance and requirements, we find that the battery sizing calculations are acceptable to support the load profile/battery capacity verification performed by the licensee.

The staff reviewed=the load profiles developed by the licensee and finds them acceptable based on their consistency with plant conditions and system operations during the assumed two hour scenario.

Since the requested revision to the division 1, 2, and 3 125 Vdc and division 1 250 Vdc battery duty cycles for section 4.8.2.l.d.2 of the Technical Specifications reflects the new load profiles, we find that revision acceptable.

3.0 ENVIRONMENTAL CONSIDERATION

Pursuant to 10 CFR 51.21, 51.32, and 51.35, an envir'onmental assessment and finding of no significant impact have been prepared and published (54 FR 23552) in the Federal

~Re ister on June 1, 1989.

Accordingly, based upon the environmentaT assessment the C,ommission has determined that the issuance of this amendment will not have a significant effect on the quality of the human environment.

4.0 CONTACT WITH STATE OFFICIAL The Commission has issued a Notice of Consideration of Issuance of Amendment to Facility Operating License and Opportunity for Hearing (53 FR 17810, Nay 18, 1988) and consulted with the State of Washington.

No public comments were received, and the State of Washington did not have any comment.

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5.0 CONCLUSION

Lfe have concluded, based on the considerations discussed above, that:

(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed

manner, and (2) such activities will be conducted in compliance with the Commission's regula-tions and (3) the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributor:

Frederick H. Burrows Dated:

June 6, 1989

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