ML20246K940
| ML20246K940 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 07/10/1989 |
| From: | Knighton G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20246K944 | List: |
| References | |
| NUDOCS 8907180304 | |
| Download: ML20246K940 (8) | |
Text
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UNITED STATES j
NUCLE AR REGULATORY COMMISSION
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E-WA$HINGTON. D. C. 20555
%,.....f PgIFICGASANDELECTRICCOMPANY DIABLO CANYON NUCLEAR POWER PLANT, UNIT 1 EKET_NO.50-275 D
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 42 License No. DPR-80 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Pacific Gas & Electric Company (the licensee),datedJanuary 22, 1988, as supplemented by letter dated May 15, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the -
Commission's regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Comission; 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 Comission's regulations; s t' D.
The issuance of this amendment will not be inimical to the common S~'
defense and security or to the health and safety of the public; and
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The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
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UNITED STATES
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WASHINGTON. D. C. 20S55
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PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON NUCLEAR POWER PLANT, UNIT 2 DOCKET NO. 50-323 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 41 License No. DPR-82 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Pacific Gas & Electric Company (the licensee), dated January 22, 1988, as supplemented by letter dated May 15, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Commission; C.
Thereisreasonableassurance(1)thattheactivitiesauthorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be l,
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.
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2.
Accordingly,. the -license is amended by changes to 'the Technical.
j Specifications as indicated.in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-82 is hereby 1
amended _to read as follows:
-(2) Technical Specifications The. Technical Specifications contained in Appendix A and the u
Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 41, are hereby incorporated in the license.
Pacific Gas & Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, except where otherwise stated in specific license
-conditions.
3.
This-license amendment becomes effective at the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
& #1.
/rina/k George-W. Knighton, Director Project Directorate V Division of Reactor-Projects - III, IV, V, and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: July 10, 1989
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' ATTACHMENT TO LICENSE AMENDMENT N05.'42 AND 41-FACILITY OPERATING LICENSE N05. DPR-80 and DPR DOCKET N05. 50-275 AND 50-323
. Replace the following pages of the 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 Pa g -
Insert Page 3/4 3-69 3/4 3-69 8 3/4 3-5 B 3/4 3-5 I
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L INSTRUMENTATI0i!
3/4.3.4 TURBINE OVERSPEED PROTECTION LIMITING CONDITION FOR OPERATION
.4 3.3.4.1 At least one Turbine Overspeed Protection. System shall be OPERABLE.
APPLICABILITY: MODES 1, 2 and 3 (during turbine operation).
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ACTION:
a.
With one stop valve or one control valve per high pressure turbine steam line_ inoperable or with one reheat stop valve or one reheat intercept valve per low pressure turbine steam line inoperable, restore the inoperable valve (s) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or isolate the turbine from the steam supply within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
With the above required Turbine Overspeed Protection System otherwise inoperable, within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> isolate the turbine from the steam supply.
SURVEILLANCE REQUIREMENTS 4.3.4.1.1 The provisions of Specification 4.0.4 are not applicable.
4.3.4.1.2 The above required Turbine Overspeed Protection System shall be demonstrated OPERABLE:
a.
At least once per quarter by cycling -and direct observation of the movement of each of the following valves through at least one complete cycle from the running position:
1)
Four high pressure turbine stop valves, 2)
Four high pressure turbine control valves, 3)
Six low pressure turbine reheat stop valves, and 4)
Six low pressure turbine reheat intercept valves.
l b.
At least once per 18 months by performance of a CHANNEL CALIBRATION on the Turbine Overspeed Protection Systems.
c.
At least once per 40 months by disassembling at least one of each of the above valves and performing a visual and surface inspection of valve seats, disks and stems and verifying no unacceptable flaws or corrosion.
3 JUL 10 839 DIABLO CANYON - UNITS 1 & 2 3/4 3-69 Amendment Nos. 42 and 41
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_IN_ST_RUMENTATION BASES 1
l 3/4.3.3.10 _RADI0A_Cy VE GASEOUS EFFLUENT MONITORING INSTRUMENTATION The.-radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. Ti.e Alarm / Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCP to ensure that the a'larm/ trip will occur prior to exceeding the limits of 10 CFR Part 20.
This instrumentation also includes provisions for monitoring (and controlling) the concentrations of potentially explosive gas mixtwes in the GASEOUS-RADWASTE SYSTEM. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.
The sensitivity of any noble gas activity monitors used to show compliance with the gaseous effluent release requirements of Specification 3.11.2.2 shall be such that concentrations as low as 1 x 10-5 mC1/ml are measurable.
1 3/4.3.4 TURBINE OVERSPEED PROTECTION This specification is provided to ensure that the turbine overspeed protection ~ instrumentation and the turbine speed control valves are OPERABLE and will protect the turbine from excessive overspeed. Protection from turbine excessive overspeed is required since excessive overspeed of the turbine could generate potentially damaging missiles which could Spact and damage safety related components, equipment or structures.
The quarterly valve test frequency required by Specification 4.3.4.1.2a, is based on Diablo Canyon operating experience and the results of an evaluation documented in WCAP-11525, "Probabilistic Evaluation of Reduction in Turbine Valve Test Frequency," June 1987. The evaluation shows that for Diablo Canyon the probability of turbine missile generation is within the NRC acceptance criteria (letter from C. E. Rossi, USNRC, to J. A. Martin, Westinghouse, dated February 2,1987) for turbine valve test intervals up to seven months.
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JUL 101989 DIABLO CANYON - UNITS 1&2 B 3/4 3-5 Amendment Nos. 42 and 41 L____-_______-__-_________
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