ML20135E535

Discusses Series of Telcon W/Nrc Concluding 961003 Re CS & RHR Sys Containment Isolation Valves at Vynp.Staff Assessment of Plant Submittals Encl

ML20135E535
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	03/03/1997
From:	Rooney V NRC (Affiliation Not Assigned)
To:	Reid D VERMONT YANKEE NUCLEAR POWER CORP.
Shared Package
ML20135E514	List: ML20135E511 ML20135E535 ML20135E540
References
TAC-M96754, NUDOCS 9703070125
Download: ML20135E535 (3)

Text

. . , _ _ _ . _ _ _ _ _ . _ . _ _ . _ _ _ - _ . . . . _ _ _ . _ . _ _ _ _ . _ - -

Mr. Donald A. Reid March 3, 1997-

, Vice Prasid:nt, Opsratiens Vermont Yankee Nuclear Power Ccrporation Ferry Road

., Brattleboro, VT 05301

SUBJECT:

CORE SPRAY AND RESIDUA l. HEAT REMOVAL SYSTEMS CONTAINMENT ISOLATION VALVES AT VERMONT YANKEE NUCLEAR POWER STATION (TAC NO. M96754)

Dear Mr. Reid:

During a series of, telephone conversations,with the NRC staff concluding on October 3, 1996, representatives of Vermont Yankee Nuclear Power Corporation (VYNPC) described changes it planned to implement in the containment isolation configuration for the Vermont Yankee residual heat removal (RHR) and core spray (CS) systems prior to restart from the fall 1996 refueling outage.

Based on the information discussed during the telephone conversation, the NRC staff understood that VYNPC planned to implement these changes under the provisions of 10 CFR 50.59 because VYNPC had, determined that the changes involve neither a change to the Vermont Yankee; Technical Specifications (TSs) nor an unreviewed safety. question. _During.the 0ctober 3, 1996, telephone conversation, the NRC staff informed ,VYNPC it had concluded, based on the information.. discussed, that- the; planned changes in containment isolation configuration'for,the RHR and CS systems appeared to be acceptable. In addition, the NRC staff found that.VYNPC's concl_usion that these changes did not involve an unreviewed safety-question was; reasonable. However, to document the information' discussed on October 3, 1996, the NRC staff requested VYNPC to submit a summary;of VYNPC's evaluation of these changes. VYNPC submitted the requested information in a letter dated October 15, 1996. A letter dated November 15, 1996 provided VYNPC's 10 CFR 50.59 determination, in response to a verbal request"from the staff.

This letter forwards the NRC staff's assessment of VYNPC's submittals. The enclosed safety assessment confirms the NRC staff's previous conclusions that the CS and RHR containment isolation configuration changes are acceptable and l do not require prior NRC approval. j l

Sincerely, I n L. y enior Project Manager Project Direc M ate I-3 1 Division of Reactor Projects - I/II  ;

Office of Nuclear Reactor Regulation  ;

i

Enclosure:

Safety Assessment Distribution  !

Docket File- ACRS Docket No. 50-271 PUBLIC CHarbuck PDI-3 RF CBerlinger cc: See next page SVarga I JZwolinski i PMilano VRooney p/

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! Mr. Donald A. Reid

Vice President, Operations Vermont Yankee Nuclear Power Corporation Ferry Road j Brattleboro, VT 05301 i

SUBJECT:

CORE SPRAY AND RESIDUAL HEAT REMOVAL SYSTEMS CONTAINMENT ISOLATION

, VALVES AT VERMONT YANKEE NUCLEAR POWER STATION (TAC NO. M96754) 4 l

Dear Mr. Reid:

During a series of telephone conversations with the NRC staff concluding on October 3, 1996, representatives of Vermont Yankee Nuclear Power Corporation

(VYNPC) described changes it planned to implement in the containment isolation l configuration for the Vermont Yankee residual heat removal (RHR) and core

, spray (CS) systems prior to restart from the fall 1996 refueling outage.

2 Based on the information discussed during the telephone conversation, the NRC staff understood that VYNPC planned to implement these changes under the provisions of 10 CFR 50.59 because VYNPC had determined that the changes involve neither a change to the Vermont Yankee Technical Specifications (TSs) nor an unreviewed safety question. During the October 3, 1996, telephone conversation, the NRC staff informed VYNPC it had concluded, based on the information discussed, that the planned changes in containment isolation configuration for the RHR and CS systems appeared to be acceptable. In addition, the NRC staff found that VYNPC's conclusion that these changes did not involve an unreviewed safety question was reasonable. However, to document the information discussed on October 3, 1996, the NRC staff requested VYNPC to submit a summary of VYNPC's evaluation of these changes. VYNPC submitted the requested information in a letter dated October 15, 1996. A letter dated November 15, 1996 provided VYNPC's 10 CFR 50.59 determination, in response to a verbal request from the staff.

This letter forwards the NRC staff's assessment of VYNPC's submittals. The enclosed safety assessment confirms the NRC staff's previous conclusions that the CS and RHR containment isolation configuration changes are acceptable and do not require prior NRC approval.

Sincerely,

'/

/ e-a --

p Verno L. Rooney, Senipr Project Manager Project Directorate I-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Enclosure:

Safety Assessment Docket No. 50-271 cc: See next page

D. Reid Vermont Yankee Nuclear Power Station Vermont Yankee Nuclear Power Corporation cc:

Regional Administrator, Region I G. Dana Bisbee, Esq.

U. S. Nuclear Regulatory Commission Deputy Attorney General 475 Allendale Road 33 Capitol Street i King of Prussia, PA 19406 Concord, NH 03301-6937 '

R. K. Gad, III Resident Inspector Ropes & Gray Vermont Yankee Nuclear Power Station One International Place U.S. Nuclear Regulatory Commission Boston, MA 02110-2624 P.O. Box 176 Vernon, VT 05354 Mr. Richard P. Sedano, Commissioner Vermont Department of Public Service Chief, Safety Unit -

120 State Street, 3rd Floor Office of the Attorney General  !

Montpelier, VT 05602 One Ashburton Place, 19th Floor  ;

Bost on, MA 02108 Public Service Board State of Vermont Mr. David Rodham, Director 120 State Street ATTN: James Muckerheide Montpelier, VT 05602 Massachusetts Civil Defense Agency 400 Worcester Rd.

Chairman, Board of Selectmen P.O. Box 1496 Town of Vernon Framingham, MA 01701-0317 P.O. Box 116 Vernon, VT 05354-0116 Mr. Raymond N. McCandless Vermont Division of Occupational Mr. Richard E. McCullough and Radiological Health Operating Experience Coordinator Administration Building Vermont Yankee Nuclear Power Station- Montpelier, VT 05602 P.O. Box 157 Governor Hunt Road Mr. J. J. Duffy Vernon, VT 05354 Licensing Engineer Vermont Yankee Nuclear Power Corporation 580 Main Street Bolton, MA 01740-1398 Mr. Robert J. Wanczyk, Plant Manager Vermont Yankee Nuclear Power Station P.O. Box 157, Governor Hunt Road >

Vernon, VT 05354 Mr. Ross B. Barkhurst, President Vermont Yankee Nuclear Power Corporation I Ferry Road I Brattleboro, VT 05301 ,

1 J