ML20207N874
| ML20207N874 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 01/07/1987 |
| From: | Mckenna E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20207N857 | List: |
| References | |
| NUDOCS 8701140470 | |
| Download: ML20207N874 (5) | |
Text
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UNITED STATES o,,
8" NUCLEAR REGULATORY COMMISSION g
WASHWGTON, D. C. 20555
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YANKEE ATOMIC ELECTRIC COMPANY YANKEE NUCLEAR POWER STATION DOCKET NO.50-029 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.102 License No. DPR-3 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Yankee Atomic Electric Company (the licensee) dated October 15, 1985 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and 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 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 Comission'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. DPR-3 is hereby amended to read as follows:
Q1140470870107 ADOCK 05000029 p
. (2)
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No.102, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION bL Q,
Eileen M. McKenna, Project Manager Project Directorate #1 Division of PWR Licensing-A
Attachment:
Changes to the Technical Specifications Date of Issuance: January 7, 1987 k
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ATTACHMENT TO LICENSE AMENDMENT NO.102 FACILITY OPERATING LICENSE P'O. DPR-3 DOCKET NO.50-029 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
1 REMOVE INSERT 3/4 4-39 3/4 4-39 B 3/4 4-13 8 3/4 4-13 t
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MAIN COOLANT SYSTEN MAIN COOLANT SYSTEM N LIMITING CONDITIONS FOR OPERATION 3.4.11 At least one main coolant system vent' path consisting of at least two valves in series powered from emergency buses shall be OPERABLE and closed with power removed from the valve actuator at each of the, following locations:
a.
Reactor vessel head (VD-MOV-559 and 541) b.
pressuriser steam space (FR-MOV-558 and 560)
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._PLICARILITY: WODES 1, 2, 3, and-4.
AhTION:
s.
With one of the above main coolant system went valves inoperable, STARTUP and/or POWER OPERATION may continue provided the inoperable j
valve is maintained closed with power removed from the valve actuator of the inoperable valve; restore the inoperable went valve to OPERABLE status within 30 days, or, be in NOT STANDBY within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
b.
With both main coolant systems vent paths inoperable; maintain the inoperable went paths closed with power removed from the valve l
actuators of the inoperable valves, and restore at least one of the went paths 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 be in NOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
l SURVEfffAMCE REOUIe N MTS 4.4.11.1 At least once per 31 days verify that the supply breakers at the ENCC for each of the following valves is locked open:
a.
VD-MOV-559 and 561 b.
PR-MOV-558 and 560 4.4.11.2 Each main coolant system went path shall be demonstrated OPERABLE st least once per 18 months by:
Verifying all manual isolation valves in each went path are locked a.
in the open position.
b.
Cycling each motor-operated valve in the went path through at least one complete cycle at full teevel from the Control Room during COLD SHUTDOWN or REFUEL 15C.
a.
Verifying flow through the main coolant went system went paths during wanting during COLD SHUTDOWN OR REFUELINC.
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MAIN COOLANT $YSTEN Y3f&
i Whenever the results of any steam generator tubing inservice inspection fall into Category C-3, these results will be promptly reported to the Cossalssion pursyant to Specification 6.9.4 prior to resumption of plant operation. Such cases will be considered by the Commission on a case-by-cese basis and may result in a requirement for analysis, laboratory examinations, tests.
additional eddy-current inspection, and revision of the Technical Specifications, if necessary.
3/4.4.11 Main Coolant System Vents Main coolant system vents are provided to exhaust noncondensable gases and/or steam from the primary system that could inhibit natural circulation core cooling. The OPERABILITY of at least one main coolant system vent path from
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the reactor vessel head or the pressuriser steam space ensures the capability exists to perform this function.
The redundancy of the main coolant system vent paths, the normally closed valves and the open valve circuit breakers serve to minimise the probability of inadvertant irreversible actuation while ensuring that a single failure of a vent valve, power supply, or control system does not prevent isolation of the vent path.
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The function, capabilities, and testing requirements of the main coolant l
system vent systems are consistent with the requirements of Item II.B.1 of NUREG-0737, " Clarification of THI Action plan Requirements " November 1980.
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Amendment g, % [ 102 YANKEE ROWE 33/4 4-13
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