B17046, Application for Amend to License NPF-49,clarifying Administrative Controls for RHR Isolation Valves When RHR Sys Is in Svc for Core Cooling

Application for Amend to License NPF-49,clarifying Administrative Controls for RHR Isolation Valves When RHR Sys Is in Svc for Core Cooling

ML20236W012
Person / Time
Site:	Millstone
Issue date:	07/30/1998
From:	Bowling M NORTHEAST NUCLEAR ENERGY CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20236W014	List: B17046, Application for Amend to License NPF-49,clarifying Administrative Controls for RHR Isolation Valves When RHR Sys Is in Svc for Core Cooling ML20236W020
References
B17046, NUDOCS 9808050027
Download: ML20236W012 (4)

Text

. ._ .__. __ _- __-____- _-____ _ ___ _ _____ _ - _. _ _ .- -__

i R ne Ferry Rd. (Route 156), hterford, CF 06385 N e st .

Nuclear Energy winsiooe Noaear Power station Northeast Nudear Energy Company

, J. P.O. Box 128 l< ~ ., ..

Waterford, CT 06385-0128

[. (860) 447-1791 l Fax (860) 444-4277 The Northeast Utilities Systern 1

l Jll 3 01998 Docket No. 50-43 y B17046 Re: 10 CFR 50.59

-U.S. Nuclear Regulatory Commission Attention: Document Control Desk

. Washington, DC 20555 Millstone Nuclear Power Statu Unit No. 3 thanae to Technical Specification Bases SQa) yf 6.1.1 I PTSCR 3-3-98)

Northeast Nuclear Energy Company (NNECO) is providing the NRC Staff with a change to Technical-Specification Bases Section 3/4.6.1.1 for information only. This ,

change was reviewed and approved by the Millstone Unit No. 3 Plant Operating Review 1 Committee on July 10,1998, in accordance with the provisions of 10CFR50.59.

Description of Chance The change to Technical Specification Basis 3/4.6.1.1 clarifies the administrative  ;

controls for the RHR isolation valves when the RHR system is in service for cora cooling. The bases is being modified to explicitly state that the control room operators are credited for providing the administrative controls and a separate dedicated operator  ;

is not needed. ,

Suoolemental information Placing RHR:in' service is necessary for providing core cooling in Mode 4. This requires opening the RHR isolation valves. However, since these valves are also ,

containment isolation valves, and they do not receive an automatic close signal, the Technical Specifications requires the establishment of administrative controls. These .

- administrative controls specified in~ the bases of Specification 3/4.6.1.1 include the o following: (1) st&tioning an operator, who is in constant communication with the control room, at the valve controls, (2) instructing the operator to close the valves in an

~

j

,4.o oo 7 o -

l PDR ADOCK 05000423 4D P PDR1

_ e_ .au.. __ _m ._ __. __ _ __ _ _ _ _ _ . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ - . _ _ _ _ ______-_-mm_____ -

__ __ _--. J

l

. . U.S. Nucl=r R:guintory Commission l B17046\Page 2 accident. situation, and (3) assuring that environmental conditions will not preclude access to close the valves and that this action will prevent the release of radioactivity outside the containment.

The control room operators meet the requirements for administrative controls for opening the RHR isolation valves as:

1. The controls for the RHR isolation valves are located in the control room and closing the valves when necessary will be performed by one of the two control room operators.

2. The mitigation of accidents is specified by Millstone Unit No. 3 AOPs and EOPs.

These procedures specify when the RHR isola %n valves are to be closed. The j RHR valves would not be closed for every aident scenario, because RHR may be the only available means for decay heat renioval.

3. The control room is a mild environment for postelated scenarios where containment isolation is required.

Therefore, the control room operators meet the requirements for administrative controls necessary wher: RHR isolation valves are open.

Additionally, the above is consistent with the NR.C approval on December 18,1997, of a revision to Millstone Unit No. 2 Technical Specification for the SDC isolation valves.

!f you have any questions, please contact Mr. D. A. Smith at (860) '37-5840. j Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY Martin i.. Bowling, Jr. V Recovery Officer - Technica) uervices l i

Attachments cc: H. J. Miller, Region l Administrator l J. W. Andersen, NRC Project Manager, Millstone Unit No. 3

} A. C. Cerne, Senior Resident inspector, Millstone Unit No. 3 W. D. Travers, Ph.D.., Director, Special Projects Office

\

L_ _ ____ _ _. __ _ _

4 Docket No. 50-423 B17046 1

i l

Attachment 1 Millstone Nuclear Power Station,' Unit No. 3 l

Commitments ,

1 July 1998 t

t I

, ' U.S. Nuclear Regulatory Commission B17046%ttachment 1\Page 1

, Enclosure List of Regulatory Commitments The following table identifies those actions committed to by NNECO in this document. Please notify the Manager - Regulatory Compliance at the Millstone Nuclear Power Station Unit No. 3 of any questions regarding this document or l

any associated regulatory commitments.

Commitment Committed Date or Outage NONE N/A u_ - - _____