ML17279A825

Application for Amend to License NPF-21,revising Tech Spec to Clarify That Automatic Isolation Signals Will Be Placed in Svc When Control Returned to Control Room

ML17279A825
Person / Time
Site:	Columbia
Issue date:	02/12/1988
From:	Sorensen G WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML17279A826	List: ML17279A825 ML17279A827 ML17279A828
References
GO2-88-037, GO2-88-37, TAC-66927, NUDOCS 8802220209
Download: ML17279A825 (7)

Text

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>ACCESSION NBR: 880222020'P DOC. DATE: 88/02/12 NOTARIZED: YES DOCKET 0 FACIL~ 50-397 WPPSS Nuclear ProJects Unit 2s Washington Public Poee 05000397 AUTH. NAME AUTHOR AFFILIATION SORENSENs Q. C. Washington Public Power Supply System RECIP. NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Application for amend to License NPF-21I revising Tech Spec to clarify that automatic isolation signals will be placed in svc .chen control returned to control room.

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DISTRIBUTION CODE: *0019 COPIES RECEIVED: LTR J ENCL SIZE:

TITLE: OR Submittal: Qeneral Distribution OTES:

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REC I P ENT COPIES RECIPIENT Co< IES c ID,CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD5 LA 0 PD5 PD 5 5 SAMWORTHs R 1 INTERNAL: ACRS 6 6 ARM/DAF/LFMB 1 0 NRR/DEST/*DS7E4 NRR/DEST/CEBBH7 1 1 NRR/DEST/MTB 'PH 1 1 NRR/DEST/RSB 8E 1 NRR/DOEA/TSB11F 1 1 NRR/ AS/ILRB12 1 OQC 15-B-18 1 0 G FIL 01 1 RES/DE/EIB 1 1 EXTERNAL: LPDR 1 1 NRC PDR NSIC 1 1 4

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Washington Public Power Supply System 3000 George Washington Way P.O. Box 968 Richland, Washington 99352-0968 (509)372-5000 Docket No. 50-397 February 12, 1988 G02-88-037 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 TECHNICAL SPECIFICATION AMENDMENT TABLE 3.3.2-1, ISOLATION ACTUATION INSTRUMENTATION (ADDITIONAL CONTROLS)

Reference:

Letter, G02-88-002, GC Sorensen (SS) to NRC, same subject, dated January 5, 1988 On January 19, 1988, members of our respective organizations met in Bethesda to discuss the Supply System's approach to resolving the RHR-V-8/V-9 issue (see Reference). During that meeting the NRC Staff expressed certain concerns about the possibility of inadvertent opening of RHR-V-8 when it was in the transferred "Emergency" position with the interlocks bypassed. The purpose of this letter is to provide additional actions to be taken by the Supply System to assuage those concerns.

To prevent inadvertent opening of both RHR pump suction valves RHR-V-8 and V-9 resulting from a control room fire the Supply System proposes the fol 1 owi ng:

1. During normal plant operation, (Operational Conditions 1, 2 and 3 when above 135 psig reactor steam dome pressure) the control of RHR valve V-8 will not be available in the main control room. The transfer switch located at the Alternate Remote Shutdown Panel will be placed in the "Emergency" position. With the valve closed and control transferred to the Alternate Remote Shutdown Panel, RHR-V-8 (closed during normal operation) cannot be inadvertently opened due to a fire in the main control room. This assures that the intersystem LOCA cannot occur from such a fire.

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I Page Two REQUEST FOR TS AMENDMENT TABLE 3.3.2-1, ISOLATION ACTUATION INSTRUMENTATION (ADDITIONAL CONTROLS)

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2. With the transfer switch in the transferred "Emergency" position, the automatic isolation signals to RHR-V-8 are bypassed. These automatic isolation signals are: I) reactor pressure above shutdown range permissive, 2) shutdown flow high, and 3) reactor vessel water level low. RHR-V-8 position indication will remain available continuously in the control room during normal operation through the use of the SPDS display. Upon retur n of control of RHR-V-8 to the control room during Shutdown Cooling Mode operation, the automatic isolation signals will be reinstated by returning the Alternate Remote Shutdown transfer switch to the "Normal" position. Refer to attached wiring diagram circled area at drawing zone A-3 for schematic representation.

3. To aid in the prevention of inadvertent operation of the valve from the local shutdown panel, a modification essentially identical to that incorporated by River Bend (approved by the NRC) will be included. The modification consists of the addition of a key-locked, two position (Enable-Disable), maintained contact control switch. A contact from this switch will be wired in series with the Alternate Remote Shutdown Panel RHR-V-8 control switch("Open" control contact). Thus, in order to actuate valve V-8, the key (controlled by Administrative Procedure 1.3.23) must be acquired, the key-locked switch moved from the "Disable" to the "Enable" position, and the valve control switch moved from the "Close" to the "Open" position. Refer to the attached electrical wiring diagram circled area at drawing zone F-6 for a schematic representation.

As a result of the above changes, it will also be necessary for the Supply System to add this new step to the Remote Shutdown Procedures (PPM 4. 12.1.1 and 4.12.1.2) .

The Staff also requested that the proposed changes to the Technical Specifications (see Reference) be revised to clarify that the automatic isolation signals will be placed in service when control is returned to the control room. This has been accomplished by providing some clarification to the previously submitted material (attached).

The Supply System has reviewed the addition of the key-lock switch in conjunction with the previously evaluated transfer of control of RHR-V-8 to the Alternate Remote Shutdown Panel and concludes that it does not involve an unreviewed safety question. The Supply System has evaluated this request per 10 CFR50.92 and provides the following in support of the finding for no significant hazards consideration:

1) The proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated because the installation of the key-lock provides additional assurance that RHR-V-8 will not open inadvertently. The change results in a reduction in the probability of a high/low pressure interface failure as a result of a postulated control room fire concurrent with an inadvertent opening of RHR-V-8.

Page Three REQUEST FOR TS NIENDNENT TABLE 3.3.2-1, ISOLATION ACTUATION INSTRUMENTATION (ADDITIONAL CONTROLS)

2) The proposed change does not create the possibility of a new or different kind of accident from any previously evaluated. A key-lock switch failure -will not prevent returning control of RHR-V-8 to the contr ol room which is in accordance with the original approved design of the plant. The addition of the key-lock is intended to add an additional action, thus further preventing the inadvertent opening of RHR-V-8.

3) The proposed change does not involve a significant reduction in a technical specification margin of safety because the automatic isolation remains in service for the RHR-V-9 valve and equivalent restraints are applied in preventing inadvertent actuation of RHR-V-8.

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 incr ease in the amount of any effluents that may be released offsite, nor does it involve a significant increase in individual or cummulative occupational radiation exposure.

Accordingly. 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 environmental assessment of the change is not required.

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

An application fee is not required as this is a supplemental submittal. In accordance with 10 CFR 50.91, the State of Washington has been provided a copy of this letter.

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

Very tr uly yours, G. C. Sor ensen, Manager Regulatory Programs HLA/bk Attachments cc: C Eschels - EFSEC JB Martin - NRC Reynolds - RV'S BCPSR RB Samworth - NRC DL Williams - BPA/399 NRC Site Inspector - 901A

STATE OF WASHINGTON) Sub~ect: 7'> 7A'C~

COUNTY OF BENTON

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I, G. C. Sorensen, being duly sworn, subscribe to and say that I am the Manager, Regulatory Programs for the WASHINGTON PUBLIC POWER SUPPLY SYSTEM, 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, information and belief the statements made in it are true.

DATE JZ /EH, 1988 G. C. Sor nsen, 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 lg day of 1988.

Notary Public i nd for the STATE OF WASHINGTON qg>rgb~

) Residing at H

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