ML20077N189

Application for Amend to License NPF-69 Re Deletion of Certain Instruments Not Classified as Category 1

ML20077N189
Person / Time
Site:	Nine Mile Point
Issue date:	01/06/1995
From:	Sylvia B NIAGARA MOHAWK POWER CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20077N194	List: ML20077N189 ML20077N207
References
NMP2L-1519, NUDOCS 9501170098
Download: ML20077N189 (4)

Text

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gm NIAGARA MOHAWK POWER CORPORATION /NINE MILE POINT, P.O. BOX 63, LYCOMING NY 13093/ TELEPHONE (315) 349-2882 B. Ralph Sylvia Executive Vice President N wlear January 6,1995 NMP2L 1519 U. S. Nuclear Regulatory Commission  ;

Atta: Document Control Desk l

. Washington, DC 20555  !

l RE: Nine Mile Point Unit 2 Docket No. 50-410 NPF-69 Gentlemen:

Niagara Mohawk Power Corporation hereby transmits an Application for Amendment to Nine Mile Point Unit 2 Operating License NPF-69. Also enclosed are the proposed changes to the Technical Specifications set forth in Appendix A of the above mentioned license.

Supporting information and analysis demonstrating that the proposed changes involve no significant hazards considerations pursuant to 10 CFR 50.92 are included as Attachment B.

The proposed TV Acal Specification changes contained herein represent revisions to Specification 3/4..' 9, " Accident Monitoring histrumentation," beluding Tables 3.3.7.5-1,

" Accident Monitoring Instrumentation," and 4.3.7.5-1, " Accident Monitoring Instrumentation Surveillance Requirements," and Specification 3/4.4.2, " Safety / Relief Valves." Specifically, Tables 3.3.7.5-1 and 4.3.7.5-1 are proposed for revision to delete certain instruments not classified as Category 1 (Type A us in,a-Type A), as defined in Regulatory Guide 1.97,

" Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident," and to delete the requirement that accident n .aitoring instrumentation be operable in Operational Condition 3. The ACTIONS of Table 3.3.7.5-1 are also proposed for revision to allow 30 days to restore one inoperable channel and 7 days to restore two inoperable channels. With one inoperable channel, the ACTIONS will require the filing of a Special Report after 30 days and, with two inoperable channels, the ACTIONS will require a plant shutdown after 7 days (except for the Drywell High Range Radiation Monitors, where no shutdown is required). In addition, Limiting Condition for Operation 3.3.7.5 is proposed for revision to add an exception to Spccification 3.0.4 and editorial changes are proposed to Tables 3.3.7.5-1 and 4.3.7.5-1 for consistency and clarity.

Finally, the Limiting Conditions for Operation, ACTIONS and Surveillance Requirements of Specification 3/4.4.2 are proposed for revision to remove requirements related to the i safety / relief valve acoustic monitors, contistent with the changes proposed to Tables 3.3.7.5-1 and 4.3.7.5-1. Note that changes to page 3/4 4-10 have been submitted in our Application for Amendment dated July 22,1993.

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The proposed amendment will reduce unnecessary testing and prevent unwarranted plant shutdowns when post-accident monitoring instrumentation channels are inoperable. The proposed changes are consistent with NUREG-1433, " Improved Standard Technical Specifications," regarding post-accident monitoring. The changes also incorporate certain ;

provisions of Generic Letter 83-36, "NUREG-0737 Technical Specifications," regarding .

post-accident monitoring. In addition, the proposed changes are consistent with changes approved at other plants, including Clinton Power Station (Amendment No. 31) and Sequoyah Nuclear Plant, Unit I and Unit 2 (Amendment Nos.159 and No.149, '

respectively).

Pursuant to 10 CFR 50.91 (b)(1), Niagara Mohawk has provided a copy of this license amendment request and the associated analysis regarding no significant hazards to the  ;

appropriate state representative.

Very truly yours,  !

7 B. Ralph Sylvia  ;

Exec. Vice President - Nuclear  !

JMT/Imc xc: Regional Administrator .

Mr. L. B. Marsh, Director, Project Directorate I-1, NRR Mr. D. S. Brinkman, Senior Project Manager, NRR ,

Mr. B. S. Norris, Senior Resident Inspector j Ms. Donna Ross Division of Policy Analysis New York State Energy Office t Agency Building 2 Empire State Plaza Albany, NY 12223 Records Management 1

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i UNITED STATES NUCLEAR REGULATORY COMMISSION l l

In the matter of )

I  !

NIAGARA MOHAWK POWER CORPORATION ) Docket No. 50-410 -

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Nine Mile Point Nuclear Station Unit No. 2 )

i APPLICATION FOR AMENDMENT

-l TO s OPERATING LICENSE Pursuant to Section 50.90 of the regulations of the Nuclear Regulatory Commission, '

Niagara Mohawk Power Corporation, holder of Facility Operating License No. NPF-69, l hereby requests that Section 3/4.3.7.5, " Accident Monitoring Instrumentation," and .

Section 3/4.4.2, " Safety / Relief Valves," of the Technical Specifications set forth in Appendix A to that License be amended. The proposed changes have been reviewed in '

accordance with Section 6.5 of the Technical Specifications.

The proposed Technical Specification changes contained herein represent revisions to l

Specification 3/4.3.7.5, " Accident Monitoring Instrumentation," including Tables 3.3.7.5-1, " Accident Monitoring Instrumentation," and 4.3.7.5-1, " Accident Monitoring instrumentation Surveillance Requirements," and Specification 3/4.4.2, " Safety / Relief I Valves." Specifically, Tables 3.3.7.5-1 and 4.3.7.5-1 are proposed for revision to delete >

certain instruments not classified as Category 1 (Type A or non-Type A), as defined in Regulatory Guide 1.97, " Instrumentation for Light-Water-Cooled Nuclear Power Plants to  ;

Assess Plant and Environs Conditions During and Following an Accident," and to delete the requirement that accident monitoring instrumentation be operable in Operational i Condition 3. The ACTIONS of Table 3.3.7.51 are also proposed for revision to allow 30 days to restore one inoperable channel and 7 days to restore two inoperable channels, j With one inoperable channel, the ACTIONS will require the filing of a Special Report after .

30 days and, with two inoperable channels, the ACTIONS will require a plant shutdown i after 7 days (except for the Drywell High Range Radiation Monitors, where no shutdown is ,

required). In addition, Limiting Condition for Operation 3.3.7.5 is proposed for revision to  :

add an exception to Specification 3.0.4 and editorial changes are proposed to Tables 3.3.7.5-1 and 4.3.7.5-1 for consistency and clarity. Finally, the Limiting Conditions for i Operation, ACTIONS and Surveillance Requirements of Specification 3/4.4.2 are proposed J for revision to remove requirements related to the safety / relief valve acoustic monitors,  ;

consistent with the changes proposed to Tables 3.3.7.5-1 and 4.3.7.5-1.  !

l The proposed changes would not authorize any change in the types of effluents or in the I authorized power level of the facility. Supporting information and analysis that demonstrate that the proposed changes involve no significant hazards consideration pursuont to 10 CFR 50.92 are included as Attachment B.

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l WHEREFORE, Applicant respectfully requests that Appendix A to Facility Operating License No. NPF 69 be amended in the form attached hereto as Attachment A.

1 NIAGARA MOHAWK POWER CORPORATION 1

By: Na /-

B. Ralph Sylvia /

Exec. Vice President - Nuclear Subscribed and Swor to befors me on this y day of ,1995.

& r &

NOTARY PUEILIC l

BEVERLY W. RIPKA ,

matary Public Stateof New York j yuatin Oswego Co. j h ammission Ero. 4  !