ML17037C420

Amendment to Operating License/Change to Appendix a Technical Specification Concerning Request for Change Regarding the Lowering of the Reactor Vessel Water Level

ML17037C420
Person / Time
Site:	Nine Mile Point
Issue date:	05/06/1977
From:	D'Angelo W Niagara Mohawk Power Corp
To:	Nowicki S Office of Nuclear Reactor Regulation
References
Download: ML17037C420 (14)

Text

@D t4RC FOR'M 'I95 I2 10)

U.S. NUCLEAR REGULATORV COMMISSIO OCK T NUMBFR b-2 M.

TO:

Mr.

ST Nowicki FROM:

Niagara Mohawk Power Corp.

Syracuse, New York Wi Ri D'Angelo I

NRC DISTRIBuTION FoR PART 50 DOCKET MATERIAL FILE NUMBER DATE OF DOCUMENT 5/6/77 DATE RECEIVED 5/12/77 e-'TTE R c A)RIGINAl Ocor v ONOTORIZED NC LASS IF I E D PX PROP INPUT FORM ENCLOSURE NUMBER OF COPIES RECEIVED I

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INo letter of transmittal received:

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'rjCKWOWLEDG<D lt.I I

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PLANT NAME:

Nine Mile Point Unit No 1

g)O RJL, 'OP Qg)Q (6-P) ga Amdto to OL/cfiange to Appendix A tech:.

specs'otorized 5/6/T7. ~ cqncerns request.

for change r'egarding the Qwering of'~he ctor essel at 1 vel+.

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I SAFETY ASSIGNED AD:

FOR ACTION/INFORMATION NQ 0 EC MANA E

-LIC-ASST CL k l PROJECT'ANAGER.

LIC ASST INTERNALDISTRIBUTION HR~I)R I &E OELD GOSSICK & STAFF MIPC CASE HARLESS PROJECT MANAGEMENT BOYD P

COLLINS HOUSTON PETERSON MELTZ HELTEMES SKOVHOLT LPDR 5,

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SCHROEDER ENGINEERING MACAI'~Y BOSNlau SIHWEIL PAWLICK REACTOR SAFE ROSS NOVAK ROSZTOCZY CHECK AT& I SALTZHAN RUTBERG EXTERNALDISTRIBUTION NAT LAB REG V IE LA PDR CONSULTANTS:

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IPPOLITO OPERATING REACTORS STELLO OPERATING TECH EISENHUT BUTLE ULR KSON OR SITE SAFE E

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COLLINS KREGER CONTROL NUMBER 330025

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Nuclear Repute.@t:ozy Commission,,

Msgare Nohazic Peace Cox'-

yoxation, hoX,dex of. Feci3.$,ty Opex'etang Licenei Ho. BPR-63, hex'aby requests tbnt Seccioee R,.X.X, and 3.X..6 oZ the Techn9.ca%, Specifications and Bases set forth in ApyeocKv A

@o that. License be amended.

This px'oposed change bee been coacuxxed wS.th by the Si.t:e Operations Revtew Comndtgee end Safety Reviepz and. Audit: Beoz4.

Tke pxopoee8 Technical. Sgocif9.cat:ion. change is set forth in Attachment A cp thin applkeatioA.

8'uppox'tixlg XnÃoxmacS.oa,

+M,cb demonstrates Chac t:he proposed change does not imroIve. a QigoiHcoot 4aw'ard8 ooneMex'et.'J.on, 9e set forth kn Attachment S.

'Axe propoeek change mcn~X8 not:

authorise. any change in the types: oe pay increaee 9n the amounts of off'keone9. or any change in the euthaxizocX p~er

%eve% of the facfliey.

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QHEREPORE, hppl,$.can x'aepecg&alky gequegt6 thee Appendix A to Pec9.lity Opexatinp License No. DPI,>>63 be amended h the farm eteaat>ed hex'eto ae Ateacbmen A,.

NXACARA MOHAWK PONE@ COBPQRMXOH Cma'Ld K, ~Rhode.

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HXACARA. MOHAWK POMER COBPQBATXQN Lk.cense No.

QPR-63'ocket No. 50-220 Pxoposed.

Changes to Technical Speci&.ca@9.oas Aeeached are revisions Co Pages 6 and 53a of Appendix. A to DPR-63.

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The neutron flux shall not exceed its scram setting for longer than 1.5 seconds as indicated by the process

computer,

>lhen the process ccmputer is out of service, a saf'eg limit riolation shall be assmed if the neutron flux exc efs the scram setting and control rod scram does noi occur.

To ensure thai the Safety Limi. established in Specifications 2.l.la and 2.1.]b is not

exceeded, each required scram shall be initiated by

'.s expec.H scram signal.

The Safe.y limit shall be assumed to be exc~ded

~hen scrm~ is accom-plished by a means other than the ~aspect%

scram signai.

Nenever the. reactor is in the shutdee condition xi@ irradiated gael in the reactor

vessel, the eater level shall not be more than 7 feet ll inches (127.1 inches indicator scale} below minimmi normal eater level (Elevation 302'9"),

"c pt as specified in "e" helen For the purpose of performing major mainienanc8 (not to exceed 12 xe Rs in duration) on the rector

vessel, the reactor water level Nay be leered 9'elm the annum nodal water level (Elevation 302'9").

'Nenever the reactor pater level is Xo be lowered helen '.he lm-i~low level set point redundant instrumentation will be provided Zo monitor the reactor eater level.

d, The reactor mter lm level scram trip.

setting shall be no lawe than 12 inches (53 inches indicator scale) relative tq the minimum novi ~ater level (X2'9"),

e.

The reactor mter lm1mr level setting for cor spray initiation shall be no less than -5 feet (5 inches indicator scale) relative to the minimum normal water level glevation 308'9"}.

f.

The Row biased APHR rod block trip settings shall be less than or equal to that shee in Figure 2.1,].

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3URVHLutcK"RKPUBEÃNT For the purpose of perfoWng major maintenance (not to exceed 12 meks in duration) on the reactor

vessel, the. reactor water level my be leered to g'elow the minimum normal water level {elevation 30K'9").

Mhenever the reactor water level is to be lerei 4 beiaw the le-law-law level set, point redundant instrumntation will be provided to monitor the reactor water level and written pro-c dures will be developed and folletad whenever the reactor water level is lawered below the low-lm level set point.

The-procedures will define tne valves that all be used to lover the vessel eater level. Nl other valves, that have the poteniial of lowerin the vessel water level mll be identified by val ve number in the procedures and Nese-valves sill be red tagged to preclude their operation dur',ng the major mintenance with the wa er level belcw the law-.law level set point.

During the period of major maintenance requiring lowering the water level to mre than 7 fe 4 ll inches helm minirm normal eater level (127,1 inches indicator sca)e), either boih Core Spray 5ys.ems must be operable or, if one Core Spray Sys~ is inoporab'le because of the maintananc

, all of the rdundani c~i nenes of the other Cor Spray System must be operable.

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NXAQABA Y>OHAHK POW08. CORPORA'EXON Lf.conic No.

QPK'63 Docket Bo.

50-RRO Su oaten lnfoxmation Our submittal of Nay 9, 1977 requested e change which would allow 3.owerinp of the reactor vessel miter Revel belch the low-low-low level set: point.

Thi.s mes required so that maintenance could be performed an the feedeater spax'gers nnd noaalee.

The maintenance work on the spaxsers and oozzles has been slowex than anti.cf.pated.

Also, nrJditional woxk has been found to be necessary an the control roC dr;Lve hydraulic return line, Therefoxe, a chan8e in the dura-tion from 6 to 1R wrecks is necesonry.

Since the core decay heat peneretion. is constantly decreasing, the consequences of a LOCA, whi3.e in the shutdown condition w3.13. continue to be less sever@.

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