ML17059C440

Amend 85 to License NPF-69,deleting TSs Requirements Associated with Meteorological Monitoring Instrumentation Relocated to Updated Safety Analysis Rept

ML17059C440
Person / Time
Site:	Nine Mile Point
Issue date:	12/22/1998
From:	Bajwa S NRC (Affiliation Not Assigned)
To:
Shared Package
ML17059C441	List: ML17059C440
References
NUDOCS 9812300036
Download: ML17059C440 (18)

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~0 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 NIAGARAMOHAWKPOWER CORPORATION DOCKET NO. 50-410 NINE MILEPOINT NUCLEAR STATION UNIT2 AMENDMENTTO FACILITYOPERATING LICENSE Amendment No. 85 License No. NPF-69

1. The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Niagara Mohawk Power Corporation (the licensee) dated April30, 1997, as supplemented by letter dated November 12, 1998, compli'es with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter 1; B.

The facilitywilloperate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities willbe conducted in compliance with the Commission's regulations; D.

The issuance of this amendment willnot be inimical to the common defense and security'or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-69 is hereby amended to read as follows:

(2)

Technical S ecifications and Environmental Protection Plan The, Technical Specifications contained in Appendix A and the Environmental Protection, Plan contained in Appendix B, both of which are attached hereto, as revised thro'ugh Amendment No.

are hereby incorporated into this license.

Niagara Mohawk Power Corporation shall operate the facilityin accordance with-the Te'chnical Specifications and the Environmental Protection Plan.

98i2300036 98i222 PDR ADOCK 050004l0 P

PDR

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3.

This license amendment is effective as of the date of its issuance to be implemented within 30 days.

FOR THE NUCLEAR REGULATORYCOMMISSION Attachments:

Changes to the Technical Specifications S. Singh Bajwa, Director Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Date of Issuance:

December 22, 1998

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ATTACHMENTTO LICENSE AMENDMENTNO.

If FACILITYOPERATING LICENSE NO. NPF-69 DOCKET NO. 50-410 Replace the following pages of Appendix A Technical Specifications with the attached pages.

The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.

Remove Insert VII xvii 3/4 3-74 3/4 3-75 3/4 3-76 B3/4 3-5 VII XVII 3/4 3-74 3/4 3-75 3/4 3-76 B3/4 3-5

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Table 4.3.4.2-1 End-of-Cycle Recirculation Pump Trip System Surveillance Requlrements 0

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~ 3/4 3-53 3/4.3.5 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION.......................... ~.......

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~. 3/4 3-54 Table 3.3.5-1 Reactor Core Isolation Cooling System Actuation Instrumentatlon.........................................

3/4 3-55.

Table 3.3.5-2 Reactor Core Isolation Cooling System Actuation Instrumentation S etpOlnts oo

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~ iooi 3/4 3-57 Table 4.3.5.1-1 Reactor Core Isolation Cooling System Actuation Instrumentation Surveillance Requirements.................................

3/4 3-58 3/4.3.6 CONTROL ROD BLOCK INSTRUMENTATION....................

3/4 3-59 Table 3.3.6-1 Control Rod Block Instrumentation.............'..............

3/43-60 Table 3.3.6-2 Control Rod Block Instrumentation Setpoints....................

3/4 3-62 Table 4.3.6-1 Control Rod Block Instrumentation Surveillance Requirements........

3/4 3-64 3/4.3.7 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation 3/4 3-67 Table 3.3.7.1-1 Radiation Monitoring Instrumentation........................

3/4 3-68 Table 4.3.7.1-1 Radiation Monitoring Instrumentation Surveillance Requirements

.;.. 3/4 3-70 Seismic Monitoring Instrumentation 3/4 3-71 Tably 3.3.7.2-1 Seismic Monitoring Instrumentation.........................

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Table 4.3.7.2-1 Seismic Monitoring Instrumentation Surveillance Requlrements..........................................

3/4 3-73 ELETED

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D Table 3'.3.7.3-1 DELETED..........................................

Tabl,", 4.3.7.3-1 DELETED.............................:..............

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NINE MILE POINT - UNIT 2 VII AMENDMENTNO.S"

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4 (Continued) 3/4.3.7 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation Seismic Monitoring Instrumentation '........................

B3/4 3-4a

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B3/4 3 5 Remote Shutdown Monitoring Instrumentation...................

B3/4 3-5 Accident-Monitoring Instrumentation..........................

B3/4 3-5 Source Range Monitors...................................

B3/43-6 Traversing ln-Core Probe System............................

B3/4 3-6 Loose-Part Detection System.................'..............

B3/4 3-7 Radioactive Liquid Effluent Monitoring Instrumentation............. B3/4 3-7 Radioactive Gaseous Effluent Monitoring Instrumentation...........

B3/4 3-7 3/4.3.8 3/4.3.9 ELETED

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.. B3/4 3-7 PLANT SYSTEMS ACTUATIONINSTRUMENTATION..............

B3/4 3-8 Bases Figure B3/4.3-1 Reactor Vessel Water Level......................

B3/4 3-9 LA Y

3/4.4.1 3/4.4.2 3/4.4.3 RECIRCULATION SYSTEM.................................

B3/4 4-1 SAFETY/RELIEF VALVES............... *...................

B3/4 4-3 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems '-.........................'.......

B3/4 4-3 0perational Leakage.....................................

B3/4 4-3 3/4.4.4 HEMISTRY..................................'.........

B3/444 C

3/4.4.5 SPECIFIC ACTIVITY.............................,........

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NINE MILE POINT - UNIT2 Xvll AMENDMENTNO. g$, if) 8

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THIS PAGE IS NOT USED NINE MILE POINT - UNIT 2 3/4 3-74 AMENDMENTNO.85

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THIS PAGE IS NOT USED NINE IVIILE POINT - UNIT 2 3/4 3-75 AMENDMENTNO. 8

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THIS PAGE IS NOT USED NINE MILE POINT - UNIT 2 3/4 3-76 AMENDMENTNO.S!

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ME T I

I N T The OPERABILITYof the seismic monitoring instrumentation ensures that sufficient capability is available to promptly determine the ground motion effects of a seismic event and evaluate the response of those features.imp'ortant't'o safety.'his capability is required to permit comparison of the measured response to that used in the design basis for the unit. This instrumentation is consistent with the recommendations of Regulatory Guide (RG) 1.12, "Instrumentation for Earthquakes," April 1974.

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I E TAT The OPERABILITYof the remote shutdown monitoring instrumentation ensures that sufficient capability is available'to"permit,shutdown

'and maintenance. of HOT SHUTDOWN of the unit from locations outside of the control room. This capability is required in the event control room habitability is lost and consistent with GDC 19 and 10 CFR 50.

I The OPERABILITYof the remote shutdown system controls ensures that a fire willnot preclude achieving safe shutdow'n.. The'remote shutd'own system instrumentation, controls and power circuits and transfer switches necessary to eliminate effects, of a fire and allow operation of instrumentation, c'ontrol'and power circuits required to achieve and maintain a safe shutdown condition'are independent 'of areas in which a fire*could damage systems normally used to shut down the reactor.

This capability is consistent with GDC 3 and Appendix R to 10 CFR 50.

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IN IN TR M

T The OPERABILITYof the accident-monitoring instrumentation ensures that sufficient information is available on selected. plant parameters to monitor and assess important variables following an accident.

This capability ia consistent, with the recommendations of RG 1.97, "Instrumentation for Light Water, Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident," December 1980; and NUREG-0737, "Clarification of TMI Action Plan Requirements,"

November 1980.

NINE MILE POINT - UNIT 2 B3/4 3-5 AMENDMENTNOSE

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