ML17058A674
| ML17058A674 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 03/12/1991 |
| From: | Brinkman D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17058A675 | List: |
| References | |
| TAC-79137, NUDOCS 9103220328 | |
| Download: ML17058A674 (12) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 MZ4GARA MOHAWK-POl4ER-GORPORA740N.
DOCKET"40 4N NINE-NGE-POINT--NUCLEAR-STAIN¹ -QlRT-2 AMNDMENT-TO"FACILITY-OPERATING-LICENSE.
Amendment No.
28 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 November 20, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comnission's rules and regulations set forth in 10 CFR Chapter 1;
B.
The facility will operate 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 will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not 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:
9103220328 910312 PDR ADOCK 05000410 P
1 4t
W (2)
Teehnieak-S ecifications-and-Environmental-Protection-Nan.
'h The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, both of which are attached
- hereto, as revised through Amendment No.
are hereby incorporated into this license.
Niagara Mohawk Power Corporation shall operate the facility in accordance with the Technical Specifications and the Env'ironmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance to be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications R MMcL Robert A. Capra, Director Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Date of Issuance:
March 12, 1991
I
ATTACHMENT-TO-ACETOSE-ANENfNENV.
ANENQHENT&O~ 28--70-FACILITY-OPERAT/NG-LTCENE NO,.
NRF.-69.
POCKET-NOi.-60-4KO.
Revise Appendix A as fol1ows:
iv 3/4 0-2 3/4 0-4 8 3/4 0-4 iv 3/4 0-2 W
B 3/4 0-4
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INDEX SAFETY LIHITS (Continued?
Reactor Coolant System Pressure Reactor Vessel Hater Level PAGE
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2.2 LIMITING SAFETY SYSTEM SETTINGS Reactor Protection System Instrumentation Setpoints............
82-6 4
M T N
F N
A A
3/4. 0 APPLICABILITY...........
3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEHS 3/4.1.1 SKUTDOWN MARGIN.
3/4.1.2 REACTIVITY ANOMALIES..
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3/4 1
1 3/4 1-2 3/4.1.3 CONTROL RODS Control Rod Operability...................................
3/4 1-3'ontrol Rod Maximum Scram Insertion Times,..............,.
3/4 1-6 Control Rod Average Scram Insertion Times.................
3/4 1-7 Four Control Rod Group Scram Insertion Times Control Rod Scram Accumulators.............;..............
Control Rod Drive Coupling.............,..................
3/4 1-8 3/4 1-9 3/4 1-11 Control Rod Position Indication...........................
3/4 1-13 Control Rod Drive Kousing Support.........................
3/4.1.4 CONTROL ROD PROGRAH CONTROl.S Rod North Minimizer....................................
Rod Sequence Control System...............................
Rod Block Honitor......
3/4 1-15 3/4 1-16 3/4 1-11 3/4 1-18 NINE MILE POINT - UNIT 2 Amendment No. lg, 28
SURVEILLANCE RE UIREMENTS 4.0.1 Surveillance Requirements shall be met du~ing the OPERATIONAL CONDITIONS or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement.
4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with a maximum allowable extension'ot to exceed 25K of the surveillance interval.
4.0.3 Failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by Specification 4.0.2, shall constitute noncompliance with the OPERABILITY requirements for a Limiting Condition for Operation.
The time limits of the ACTION requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed.
The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to permit the completion of the surveillance when the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Surveillance Requirements do not have to be performed on inoperable equipment.
4.0.4 Entry into an OPERATIONAL CONDITION or other specified applicable condition shall not be made unless the Surveillance Requirement(s) associated with the Limiting Condition for Operation have. been performed within the applicable surveillance interval or as otherwise specified.
This provision shall not prevent passage through or to OPERATIONAL CONDITIONS as required to comply with ACTION requirements.
4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2, and 3 components shall be applicable as follows:
a.
Inservice inspection of ASME Code Class 1, 2, and 3 components and inservice testing of ASME Code Class 1, 2, and 3 pumps and valves shall be performed in accordance with Section XI of the ASME."Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50.55a(g),
except where specific written relief has been granted by the Commission pursuant to 10 CFR 50.55a(g)(6)(i).
b.
~ Surveillance intervals specified in Section XI of the ASME Boiler and
'Pressure Vessel Code and applicable addenda for the inservice inspection and testing activities required by the ASME Boiler and Pressure Vessel Code and applicable addenda shall be applicable as follows in these Technical Specifications:
NIME MILE POINT - UNIT 2 3/4 0-2 Amendment No.
XH 27, 28
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- APPLICABILITY BASES "Surveillance requirements are requirements relating to test, calibration, or inspection to ensure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions of operation will be met."
S ecification 4. 0. 1 establishes the requitement that surveillances must be per ormed during the OPERATIONAL CONDITIONS or other conditions for which the requirements of the Limiting Conditions for Operation apply unless otherwise stated in an individual Surveillance Requirement.
The purpose of this specifi-cation is to ensure that survei llances are performed to verify the operational status of systems and components and that parameters are within specified limits to ensure safe operation of the facility when the plant is in an OPERATIONAL CONDITION or other specified condition for which the individual Limiting Condi-tions for Operation are applicable.
Surveillance Requirements do not have to be performed when the facility is in an OPERATIONAL CONDITION for which the requirements of the associated Limiting Condition for Operation do not apply unless otherwise specified.
The Surveillance Requirements associated with a Special Test Exception are only applicable when the Special Test Exception is used as an allowable exception to the requirements of a specification.
4.0.2 Specification 4.0.2 establishes the limit for which the specified time interval for Surveillance Requirements may be extended.
It permits an allow-'ble extension of the normal surveillance interval to facilitate surveillance scheduling and consideration of plant operating conditions that may not be suitable for conducting the surveillance; e.g., transient conditions or other ongoing surveillance or maintenance activities.
It also provides flexibility to accommodate the length of a fuel cycle for surveillances that are performed at each refueling outage and are specified with an 18 month surveillance interval.
It is not intended that this provision be used repeatedly as a convenience to extend surveillance intervals beyond that specified for surveillances that are not performed during refueling outages.
The limitation of Specification 4.0.2 is based on engineering judgement and the recognition that the most probable result of any particular surveillance being performed is the verification of conformance with the Surveillance Requirements.
This provision is sufficient to ensure that the reliability ensured through surveillance activities is not significantly degraded beyond that obtained from the specified surveillance interval.
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4.0.3 blah h fbi p f S
F11 Rqi ment wlthln the allowed surveillance interval, defined by the provisions of Specification 4.0.2, as a condition that constitutes a failure to meet the OPERABILITY requirements for a Limiting Condition for Operation.
Under the provisions of this specification, systems and components are assumed to be OPERABLE when Surveillance Requirements have been satisfactorily performed within the specified time interval.
However, nothing in this provision is to be construed as implying that systems or components are OPERABLE when they are found or known to be inoperable although still meeting the Surveillance Requirements.
This specification also clarifies that the ACTION requirements are applicable when Surveillance Requirements have not been completed within the allowed surveillance interval and that the time limits of the ACTION requirements apply from the point in time it is identified that a surveillance has not been performed and not at the time that the allowed surveillance inter-val was exceeded.
Completion of the Surveillance Requirement within the allow-able outage time limits of the ACTION requirements restores compliance with NINE MILE POINT-UNIT 2 B3/4 0-4 Amendment No. 2,'1',
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