ML17037B644

Letter Regarding a Review of Technical Specifications and a Determination That They Do Not Provide Adequate Surveillance Requirements to Assure Safety-Valve Operability and a Request to Submit Proposed Tech Spec. Changes ..

ML17037B644
Person / Time
Site:	Nine Mile Point
Issue date:	01/03/1977
From:	Lear G Office of Nuclear Reactor Regulation
To:	Rhode G Niagara Mohawk Power Corp
References
Download: ML17037B644 (4)

Text

1977 JAH S Docket, No.60-220 I

Niagara t/ohawk Power Corporation ATTN: tlr. Gerald K. Rhode Vice'President - Engineei ing 300 Erie Boulevard West Syracuse, Hest York 13202 Gentlemen:

RE: NIKE NILE POINT NUCLEAR STATION UNIT HO. 1 We have noted a potential deficiency in the nethod being used to confirm valve operability during periodic testing of Boiling Ilater Reactor (AWR) safety-relief valves. This deficiency concerns the use of the safety-relief valve temperature indication as a positive method of confirmation that a safety-relief valve is open when manually actuated during surveillance testing.

We have found that an increased temperature'ndication may be obtained at the safety-relief valve exit with the safety-relief valve closed. This- indicated temperature increase is the result of steam vented through the valve actuation mechanisn during the surveillance test. In view of this finding, Me have concluded that a temperature increase at the valve exit, by itself do s not provide a positive means of verification that the safety-relief valve has opened.

We have reviewed vour Technical Specifications and have determined that they do not provide adequate surveillance requirements to assure safety-relief valve operability. Therefore, we require that you eliminate this potential deficiency in your surveillance -testing program. You should propose a change to your technical specifications that provides a positive means of verification that the safety-relief valve opens when tested as part of the Automatic Oepressurization System.

An example of an acceptable method would involve the manual actuation of each individual safety-relikf valve at one or more specified pressures and observing a specified minimum compensating turbine bypass or throttle valve closure or change in measured steam f]ow rate.

jorr<cc~

SURNAME~

OATR~

NRC FORM 518 (9-76) NRCM 0240 A Ul so oovRRNMRNT PRINTlffo orrlcEl loTb 440 oc3

T Pf

Niaqara tfohavik Power Corporation - 2-Please submit your proposed Technical Specification changes within 60 days of your'eceipt of this letter. Your submittal should include the basis for your proposal,and in particular should address the adequacy of the method proposed to positively assess the opening of safety-rel ief valves.

Sincere'Jy, George'Lear, CI>ief Operating Reactors Branch ¹3 IDivisiOn of Operating Reactors cc: Arvin E. Upton, Esquire LeBoeuf, Lamb, Leiby 5 HacRae 1757 N Street, N. M. DI STRI BUT ION:

Washington, D. C. 20036 Anthony Z. Roisman, Esquire Local PDR Roisman, Kessler and Cashdan 1025 15th'Street, fl, ll.

5th Floor GLear

'llashington, D. G. 20005 ttr. Eugene G. Saloga, APPlicant CoordinatN'cGough Nine nile, Po~nt Enerqy Infor ation CenterOELD P ~ 0. Box 81 OIgE (3)

LycoQing. New York 13093 DElsenhut TBAbernathy JRBuchanan ACRS (16)

File iOPRICS~ 00 TSG ORB¹3 ORB¹3 BURHAMSW H G SNowick GLear fA/

CATS~ 1/ /7 1/ 5 /77 1/ /77 NRC PORM 318 (9-76) NRCM 0240 A UI 8, OOVSRHMSHT PRIHTlt(O OIIFICSI IOTS BRIMS'

/

t

'h V t

,k',ll~

Eg 3(

h

~ C-0 l

lI jq, tq H

4 t

'()y) I r '4 f

~f'- 'j t h'

(

I ")

I 4

,p,'.,Wt >z . '< = "f 4 + y X',>ptt ! ~:9 W~'~a~~'v .' i i ~ B(>~ "4A