ML20066E917

Application for Amend to License DPR-28,consisting of Proposed Change 163,removing Surveillance Requirement of Indication of LPCI Crosstie Monitor from Tech Specs

ML20066E917
Person / Time
Site:	Vermont Yankee
Issue date:	01/15/1991
From:	Murphy W VERMONT YANKEE NUCLEAR POWER CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20066E919	List: ML20066E917 ML20066E922
References
BVY-91-03, BVY-91-3, NUDOCS 9101220393
Download: ML20066E917 (3)

Text

_ _ _ _ _ _ _

. . VERMONT YANKEE NUCLEAR POWER CORPORATION BVY 91-03

-d'%s Ferry Road, Brattleboro, VT 05301-7002 k'h*

ENGINE ING OFFICE LM M A!N STRE E T DOLTON M A 01740 016 779 6711 Proposed Change 163 January 15, 1991 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

References:

(a) License No. DPR 28, (Docket No. 50-271)

(b) Letter, VYV 89-195 (LER 89 23), VYNPC to USNRC, dated October 11, 1989 (c) Letter, WVY 74 5, VYNPC to USAEC, dated June 25, 1974

Subject:

Surveillance of the Indication of the LPCI Crosstle Monitor (Valve RHR.20):

Proposed Change No.163 Pursuant to Section 50.90 of the Commission's Rules and Regulations, Vermont Yankee hereby proposes the following chances to Appendix A of the operating license Reference (a).

Proposed Chance This proposed change removes the surveillance requirement of the indication of the LPCI crosstle monitor [ Residual Heat Removal (RHR) System Valve RHR 20] from the Vermont Yankee Technical Specificadon9. The proposed change would require replacing Page 51 of the Technical Specifications with the attached Page 51.

Readon for Chance On October it,1989, Vermont Yankee filed a License Event Report (LER) to the NRC

) [ Reference (b)) which addressed noncompliance with Technical Specification 4.2.A as it applies to -the daily surveillance of the valve position of RHR 20.

As uplained in Reference (b), the RHR 20 valve is locked shut with its motor leads disconnected. Therefore, daily surveillance of its valve position Indication is overly conservative and unnecessary and Technical Specification 4.'c A should be changed to remove the surveillance requirement of the RHR 20 vaive.

Basis for Chance Vermont Yankee Technical Specifications require that an instrument check of the indication for the RHR System crosstle valve, RHR 20, be completed once per day. However, 9101220393 910115 g\

[ DR ADOCK0500g1 [ sg

1 VERMONT YANKEE NUCLE AR POWER CORPOR ATION ,

. 1 i

U.S. Nuclear Regulatory Commission January 15, 1991 Page 2 in Reference (c) Technical Specification 4.2.A was revised to reflect the removal of the RHR LPCI Loop selection logic. The loop selection logic was designed to determine which recirculation loop was breached during a LOCA and utilized the LPCI crosstle valve to direct cooling water to the selected loop. The change to the Technical Specification that removed the loop selection logic resulted in:

o RHR 20 being chained and locked shut o RHR 20 motor leads being disconnected o The RHR 20 keylock switch beino defeated and thus the valve cannot be opened without direct manual intervention.

Because the RHR-20 valve is locked shut as described above, daily surveillance is not necessary. Also, current administrative procedures require surveillance for the RHR 20 valve position at a minimum frequency of once per operating cycle. Therefore, current administrative procedures enst's the proper positioning of the velve.

Safety Considerations The proposed change is considered administrative because the RHR-20 valve is locked shut, the motor leads are disconnected, and the keylock switch is defeated. Thus, it cannot be opened without manual intervention. The change has been reviewed by the Plant Operetions/ Review Committee and the Nuclear Safety Audit and Review Committee.

Slonificant Hazards Considerations 10CFR50.92 states that a proposed amendment will not involve a significant hazards consideration if the proposed amendmei,t does not: (i) Involve a significant increase in the probability or consequences of an accident previously evaluated; or (il) create the possibility of a new or different kind of accident from any accident previously evaluated; or (iii) involve a significant reduction in a margin of safety.

The' RHR 20 valve is locked shut, the motor leads are disconnected, and the keylock switch has been defeated. The proposed change refers only to the frequency of surveillance of the RHR 20 valve position Indication, and therefore, can be considered administrative. As such, it does not increase the probability or consequence of any accident previously evaluated, nor does it create the possibility of a new or different kind of accident, nor does it involve any kind of safety margin. herefore, the change does not involve a significant hazards consideration as defined * - .CF A50.92.

T' b T -

VERMONT YANKEE NUCLEAR POWER CORPORAYlON U.S. Nuclear Regulatory Commission January 15,1991 Page 3 Schedule of Chance The revised pages will be tricorporated into the Technical Specifications as soon as possible following receipt of NRC approval.

Very truly yours, ,

Vermont Yankee Nuclear Power Corporation 1

Warren P. Mur , y V Senior Vice President, Operation ec: USNRC Region i Administrator USNRC Resident inspector, VYNPS USNRC Project Manager, VYNPS VT Department of Public Service STATE OF VERMONT )

)ss OF WINDHAM COUNTY )

Then personally appeared before me, Warren P. Murphy, who, being duly sworn, did state that he is Senior Vice President, Operations of Vermont Yankee Nuclear Power Corporation, that he is duly authorized to execute and file the foregoing document in the name and on the behalf of Vermont Yankee Nuclear Power Corporation and tha' the statements therein are true to the best of his knowledge and belief.

<?,

& NNk A44 0, Judith A;/ Hanis Notary Public gggyy g My Com nission Expires February 10, 1991 3$ PUBL; ,,

4 4j Coyyp,/g '