ML17037C416

Application for Amendment to Operating License and Proposed Change to Technical Specification Concerning the Emergency Cooling System

ML17037C416
Person / Time
Site:	Nine Mile Point
Issue date:	07/14/1977
From:	Rhode G Niagara Mohawk Power Corp
To:	Office of Nuclear Reactor Regulation
References
Download: ML17037C416 (12)

Text

U.S. NUCLEAR REGULATORY MISSION DOCKET NUMBER

'NRC FORM+195 (2-76)

C FILE NUMBER NRC DISTRIBUTION FQR PART 60 DOCKET MATERIAL FROM: DATE OF DOCUMENT TO:

I Niagara Mohowk Power Corp, not dated No Ro Co Syracuse, New York DATE REf Gerald Ki Rhode )IMP QkNOTO R I Z E D PROP INPUT FORM NUMBER OF COPIES RECEIVED P5 ETTER

%ORIGINAL CI COPY JRUNCLASSIFIED s t aeHu ENCLOSURE po +g op l~msmr7/wZ lID0ÃOT REMOVE License No. DPR-63 'Appl for Amend: tech specs proposed change concerning the

/Imtfggg~@ Emergency Cooling Systemi ~ inotorized 7/14/77 ~ ~ ~ ~ ~

(5-P).

. PLANT NAME: Nine Mile Point Unit No, 1 RJL 7/18/77 FOR ACTION/INFORMATION ENVIRHNMENTAL ASSIGNED AD: V MOORE LTR BRANCH CHIEF:

ECT MANAGER: PROJECT MANAGER:

CENSING ASSXSTANT: LICENSING ASSISTANT:

Bi HARLESS INTERNAL DISTRIBUTION

~TFMS SAFETY PLANT SYSTEMS SITE SAFETY &

HEIN&IAN TEDESCO ENVIRON ANALYSIS EDER BENAROYA DENTON Bi MULLER ENGINEERING IPPOLITO ENVIRO TECH ERNST OPERATING REACTORS BALLARD 0 G BLOOD BAER BUTLER GAMMILL 2 Z )CZY .GRIME CHECK SITE ANALYSIS VOLQIER AT I BUNCH ALTZMAN Ji COLLINS TBERG KREGER EXTERNAL DISTRIBUTION CONTROL NUMBER TIC iVSIC REG IV J HANCHETT 77i9902O8, 16 CYS ACRS SENT CAT GO NRC FORM 196 (2.76)

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of )

)

)

NIAGARA MOHAWK POWER CORPORATION ) Docket No. 50-220 (Nine Mile Point Nuclear Station )

Unit No. 1) )

.Re ato QQX~ ~o&~

APPLICATION FOR AMENDMENT TO C ~

OPERATING LICENSE Pursuant to Section 50.90 of the regulations of the Nuclear Regulatory Commission, Niagara Mohawk Power Cor-poration, holder of Faci,lity Operating License No. DPR-63, hereby requests that Secti.ons 3.1.3 and 4.1.3 of the Technic'al Specifications set forth in Appendix A to that License be amended. Thes'e 'proposed changes have been concurred with by the.'Site Operations Review Committee and the Safety Revi.ew and Audi,t Board.

The proposed Techni,cal Specification changes are set forth in Attachment A to this appli,cation. Supporting Information, which 'demonstrates that the proposed changes do not involve a significant hazards consideration, is set forth in Attachment B. The proposed changes would not authorize any change in the types or any increase in the amounts of effluents or any change i.n the authorized power level of the f"cility.

771990208

I 4 WHEREFORE, Applicant respectfully requests Facility that'ppendix A to Operating License No. DPR-63 be amended in the form attached hereto as Attachment A.

NIAGARA MOHAWK POWER CORPORATION By Gexald K. Rhode Vice President Engineering Subscribed apd sworn to befoxe me this /4N~ day of July, 1977.

CPi NOTARY PUBLTC t'llYLLIS D. VQYTKO tery Public ln the Qt ~ te of New Yorg

.uetitied in Onon, Co, No, 34 548553+~

'4v Cnmmieetnrr Evotree t4erch 30, 19~

~5 ATTACHMENT A Niagara Mohawk Power Corporation License No. DPR-63 Docket No. 50-220

~Pro osed Chan 'e'o'echn'ica1 S e'cification Attached are revised Pages 47 and 48.

~4 LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT EMiERGENCY COOLING SYSTEM 4.1.3 EMERGENCY COOLING SYSTEM

~iii i iii: i iiiii App1 i es to the operating status of the Applies to periodic testing requirements emergency cooling system. for the emergency cooling system.

Ob ective: Ob ective:

To assure the capability, of the emergency To assure he capability of the emergency cooling system to cool the reactor coolant cooling system for cooling of the reactor in the event the normal reactor heat sink coolant.

is not available.

S ecification: S ecification:

a. During power operating conditions and The emergency cooling system surveillance whenever the reactor coolant temperature shall be performed as indicated. below:

is greater than 212F, both emergency cooling systems shall be operable a ~ At least once ever five vears-except as specified in 3. 1.3.b and c.

The system heat removal capability

b. During Cycle 5, with one emergency shall be determined.

cooling system inoperable, Specification 3.1.3.a shall be con- b. At least once dail sidered fulfilled, provided the additional surveillance required is The shell side water level and mak performed. tank plater level. shall be checked.

c~ During Cycle 6 and subsequent cycles'f C. At 1 east once r month-one emergency cooling system becomes inoperable, Specification 3.1.3.a shall The makeup tank level control valv be considered fulfilled, pr'ovided that shall be manually opened and close the inoperable system is returned to an operable condition within 7 days and the additional surveillance required is performed.

47

LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT Makeup water shall be available from the two gravity feed makeup water tanks.

If Specifications 3.1.3a, b, c or d d. At least once each shift-are not met, a normal orderly shutdown shall be initiated within one hour The area temperature shall be checked.

and the reactor shall be in the cold shutdown condition within ten hours. e. During each major refuelin outa e-Automatic actuation and functional system testing shall be performed during each major refueling outage and whenever major repairs are completed on the system.

Surveillance with an Ino erable S stem During Cycle 5 with one of the emergency cooling systems inoperable, the level control valve and the motor-operated isolation valve in the operable system shall be demonstrated to be operable immediately and weekly thereafter.

During Cycle 6 and subsequent cycles,

<shen one of the emergency cooling systems is inoperable, the level control valve and the motor-operated isolation valve in the operable system shall be demonstrated to be operable immediately and daily thereafter.

48

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