ML17285B071

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Application for Amend to License NPF-21,revising Battery Load Profiles in Surveillance Requirement 4.8.2.1.d.2 to Reflect Results of Recent Reviews of Battery Capabilities
ML17285B071
Person / Time
Site: Columbia Energy Northwest icon.png
Issue date: 03/02/1990
From: Sorensen G
WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17285B072 List:
References
GL-89-10, GO2-90-036, GO2-90-36, NUDOCS 9003130404
Download: ML17285B071 (7)


Text

ACCELERATOR) D UTION DEMON TION SYSTEM 4 REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9003130404 DOC.DATE: 90/03/02 NOTARIZED: YES DOCKET g FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH. NAME 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-2l,revising battery load profiles in SR 4.8.2.l.d.2.

DISTRIBUTION CODE: AOOID TITLE: OR COPIES RECEIVED:LTR Submittal: General Distribution Q ENCL ~ SIZE:

NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME ENCL

'TTR PD5 LA 1 1 PD5 PD 1 1 SAMWORTH,R ,5 5' .

INTERNAL: ACRS 6 NRR/DET/ECMB 9H 1 1 NRR/DOEA/OTSB11 1 1 NRR/DST SE2 1 1 NRR/DST/SELB SD 1 1 NRR/DST/SICB 7E 1 1 NRR/DST/SRXB SE 1 1 NUDOCS-ABSTRACT 1 1 OC LFHB 1 0 OGC/HDS2 1 0 ILE Ol 1 1 RES/DSIR/EIB 1 1 EXTERNAL: LPDR 1 1 NRC PDR 1 1 NSIC 1

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, S D-N(KE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTETH CONTACT THE, DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 27 ENCL 25

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WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~ 3000 George Washington Way ~ Richland, Washington 99352 March 2, 1990 G02-90-036 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 REQUEST FOR AMENDMENT TO TECHNICAL SPECIFICATION 3 8 2 1 DC SOURCESi BATTERY LOAD PROFILE In accordance with 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 requesting that the battery load profiles in Surveillance Requirement 4.8.2. I.d.2 be revised as attached to reflect the results of recent reviews of battery capabilities. In summary the reviews were due to 1) an increase in load to battery Bl-1 due to a change in the motor operator for RHR-V-40 2) an increase in the initial current to both battery Bl-l and B1-2 due to a correction of a previously unidentified error, and 3) a review of the listed batteries capacity to identify margin and change the load profiles accordingly. The third review was done so that should a new load be identified, use of the margin will avoid the necessity of submitting a technical specification change request. The present table would not allow this. Any new load additions presently require a technical specifica-tion change prior to implementation.

The recent review of motor operated valves was done as part of the review for Generic Letter 89-10, "Safety Related Motor-Operated Valve Testing and Surveillance". This review identified the motor on RHR-V-40 as being undersized. Accordingly the motor will be replaced with one capable of meeting the criteria of Generic Letter 89-10. However, because of an impact on the battery load profile for 125 VDC battery Bl-1 replacement must be deferred until approval of the attached technical specification change.

ool 5'003i30404 900302 ~l I

PDR ADOCK 05000397 FDC

Page Two RE(VEST FOR AMEND TO TS 3.8.2.1 DC SOURCES, BATTERY LOAD PROFILE In the interim RHR-V-40 has been tagged closed and verified closed by manual handwheel operation. RHR-V-40 is one of two motor operated valves in the discharge of the RHR system to Radwaste. It is normally in the closed position and in the event of an accident receives a closed signal. Operation of the valve to open is not relied on to mitigate the consequences of, or prevent an accident.

RHR-V-40 is the normal letdown path for suppression pool level control and, as stated above, receives a closed signal as an active safety function. Should it be necessary to operate the valve in the interim period, an operator will be sent to the valve to manually operate it. He will also verify the valve closed in the event of an isolation signal or at the end of the operation requiring the valve to be opened. This is the'ame mode'f operation'permitted by Technical Specification 3.6.3 Action a. in which Primary Containment Isolation Valves which are isolated due to inoperability can be reopened on an intermittent basis under administrative control.

The impact of the change in motor size to the technical specifications is in the battery load profile for 125V DC battery Bl-l. The motor operator for RHR-V-40 is powered from this source and the increased size requires a larger motor current. The change to both 125V DC batteries is the result of correcting an error identified by the Supply System's Safety System Functional Inspection of the 125V DC batteries. The previous calculations did not consider that when the 480 volt unit substation breakers are tripped the charging motor automatically runs after the trip. This is opposite to the 4160/6900 volt breaker in which the charging motor is run when the breaker is closed. Therefore the 480 volt breaker motor loads had to be corrected in the initial load profile. This amounted to an additional in-rush load of 50 amps on Bl-I and 60 amps on Bl-2.

Battery load calculations have been performed reconfirming that the batteries can accommodate these increases and meet the operability requirements of the Surveillance Requirements in Section 4.8.2. I of the WNP-2 Technical Specifica-tions. However, the battery load profile specified in surveillance 4.8.2. l.d.2 must be changed, so that the surveillance will continue to verify operability of the battery for the larger load profile.

The Supply System has reviewed the revision per 10CFR 50.92 and provides the following in support of a finding for no significant hazards consideration. This change does not:

I) Involve a significant increase in the probability or consequences of an accident previously evaluated because calculations have been performed demonstrating that the battery can accommodate the increased load and meet all requirements for operability. Hence the operation of the battery under normal and upset conditions is not degraded and this change does not impact the probability or consequences of an accident previously evaluated.

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Page Three REQUEST FOR AMEND TO TS i 3.8.2. 1 DC SOURCES, t

BATTERY LOAD PROFILE

2) Create the possibility of a new or different kind of accident from any previously evaluated because the battery is not being changed, nor are any changes being made to the way it is being utilized or asked to perform.

The additional load being added has been evaluated, by calculation, as not resulting in any changes to the battery capability and confirmed the battery as still capable of fulfilling the l,icensing bases requirements.

Hence no new or different kind of accident is credible due to this change.

3) Involve a significant reduction in a margin of safety because as discussed above calculations have been performed to confirm that the battery will remain 'operable and meet the Surveillance Requirements of Technical Specification 4.8.2. 1. Hence the battery will continue to,fulfill its safety requirements. The impact of an increased load profile is to potentially shorten the life of the battery and dictate battery replace-ment. However in meeting the requirements of the Technical Specification Surveillance Requirements in Section 4.8.2. 1 the required margin of safety is assured.

As discussed above, the Supply System considers that this change does not involve a significant hazards consideration. Further, the change has no 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. According-ly, the proposed change meets the eligibility criteria for categorical exclusion set forth in 10CFR 51.22(c)(9) and therefore, per 10CFR 51.22(b), an environmen-tal assessment of the change is not required.

Please note that battery load profile testing will be conducted during the Spring 1990 outage. Accordingly, this change will be needed to support the outage tentatively scheduled to start April 15, 1990.

This amendment request has been reviewed and approved by the WNP-2 Plant Operating Committee (POC) and the Supply System Corporate Nuclear Safety Review Board (CNSRB). In accordance with 10CFR 50.91, the State of Washington has been provided a copy of this letter.

Very truly yours, G. C. Sorensen, Manager Regulatory Programs PLP/bk cc: JB Martin - NRC Rv NS Reynolds - BCP&R RB Samworth - NRC DL Williams - BPA/399 NRC Site Inspector - 901A C Eschels - EFSEC

STATE OF WASHINGTON) Subject. Request for Amendment to ources, COUNTY OF BENTON ) Battery Load Profile I, G. C. Sorensen, being duly sworn, subscribe to and say that I am the Manager, Regulatory Programs, for the WASHINGTON PUBLIC POWER SUPPLY SYSTEYi, the applicant herein; that I have full authority to execute this oath; that I have reviewed the foregoing; and that to the best of my knowledge, ihformation, and belief the statements made in it are true.

DATE 8 P/ ( . 1990 G. C. Sa ensen, Manager Regulatory Programs On this day personally appeared before me G. C. Sorensen, to me known to be the individual who executed the foregoing instrument, and acknowledged that he signed the same as his free act and deed for the uses and purposes herein mentioned.

GIVEN under my hand and seal this < day of 1990.

~j otary u ic sn a or the STATE OF WASHINGTON

, ~,gyiie'hei(p ~ iq at My commission expires 7 14 91 1<TTA'esiding

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