ML20150F837
| ML20150F837 | |
| Person / Time | |
|---|---|
| Site: | Millstone  (DPR-065) |
| Issue date: | 07/07/1988 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Northeast Nuclear Energy Co (NNECO), Connecticut Light & Power Co, Western Massachusetts Electric Co |
| Shared Package | |
| ML20150F840 | List: |
| References | |
| DPR-65-A-130 NUDOCS 8807190081 | |
| Download: ML20150F837 (5) | |
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'%,i UNITED STATES NUCLEAR REGULATORY COMMISSION j
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NORTHEAST NUCLEAR EN QGY COMPAN(
THE CONNECTICUT LIGHT AND POWER COMPANY THE WESTERN MASSACHUSETTS ELECTRIC COMPANY DOCKET NO. 50-336 MILLSTONE fjuCLEAR POWER STATION, UNIT N0. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.130 License No. DPR.65 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Northeast Nuclear Energy Company, et al. (the licensee), dated April 25, 1988, 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 Comission; C.
There is reasonable assurance (1) 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; D.
The issuance of this amendment will not be inimical to the comon 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.
8807190081 880707 PDR ADOCK 0500 6
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2-2.
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. OPR-65 is hereby amended to read as follows:
(2) Technica] gcifications The Technical Specifications contained in Appendix A, as revised through Amendment No.130, 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 issuance.
FOR THE NUCL EGU TORY COMMISSION
/
oh F. Stolz, Directo ject Directorate I-4 Division of Reactor Projects I/I!
Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: July 7, 1988 t
ATTACHMENT TO LICENSE Af1ENDMENT NO.130 FACILITY OPERATING LICENSE N0. OPR-65 DOCKET NO. 50-336 Replace the following page of the Apoendix A Technical Specifications with the enclosed page. The revised page is identified by amendment number and contains vertical lines indicating the areas of change.
The corresponding overleaf page is provided to maintain document completeness.
Remove Insert 3/4 4 4 3/4 4-4 1
REACTOR COOLANT SYSTEM RELIEF VALVES LIMITING CONDITION FOR OPERATION 3.4.3 Two power operated relief valves (PORVs) and their associated block valves shall be OPERABLE.
APPLICABILITY: MODES 1, 2 and 3.
ACTION:
a.
With one or more PORV(s) inoperable, within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> either restore the PORV(s) to OPERABLE status or close the associated block valve (s) and remove power from the block valve (s); otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD.tHUT00WN 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 one or more block valve (s) inoperable, within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> either restore the block valve (s) to OPERABLE status or close the block valve (s) and remove power from the block valve (s); otherwise, be in at least HOT STANDBY within the next 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 />.
The provisions of Specification 3.0.4 are not applicable.
c.
l SURVEILLANCE REQUIREMENTS
- 4. 4. 3.1 Each PORY shall be demonstrated OPERABLE:
a.
Once per 31 days by performance of a CHANNEL FUNCTIONAL TEST, excluding valve operation, and b.
Once per 18 months by performance of a CHANNEL CALIBRATION.
i 4.4.3.2 Each block valve shall be demonstrated OPEP'BLE once per 92 days by operating the valve through one complete cycle of f. il travel, This demonstration is not required if a PORY block valve is closed and power removed to meet Specification 3.4.3 a or b.
i MILLSTONE - UNIT 2 3/4 4-3 Amendment No. H M 68
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REACTOR COOLANT SYSTEM PRELSURIZER
, LIMITING CONDITION FOR OPERATION 3.4.4 The pressurizer shall be OPERABLE with:
a.
A water volume greater than or equal to 525 cubic feet (35%) but less than or equal to 1050 cubic feet (70%), and b.
At lett two groups of pressurizer heaters each having a capacity of at least 130 kW capable of being supplied by emergency power.
APPLICABILITY: MODES 1, 2 and 3.
ACTION:
a.
With only one group of pressurizer heaters OPERABLE, restore at least two groups 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 at least HOT STANDBY within the next 6
hours and in HOT SHUTDOWN within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
b.
With the pressurizer otherwise inoperable, be in at least HOT STANDBY with the reactor trip breakers open within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE REQUIREMENT 4.4.4 The pressurizer water volume shall be determined to be within its limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
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1 MILLSTONE - UNIT 2 3/4 4-4 Amendment No. #, 7f, y', 130
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