ML19318A874
| ML19318A874 | |
| Person / Time | |
|---|---|
| Site: | Salem  (DPR-75-A-001, DPR-75-A-1) |
| Issue date: | 06/11/1980 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19318A875 | List: |
| References | |
| NUDOCS 8006240310 | |
| Download: ML19318A874 (5) | |
Text
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PUBLIC SERVICE ELECTRIC AND GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-311 SALEM NUCLEAR GENERATING STATION, UNIT NO. 2 AMENDMENT TO FACILITY'0PERATING LICENSE bPR-75 cen e o 1.
The Nuclear. Regulatory Commission (the Comission) has found that:
i A.
The application for amendment by Public Service Electric and Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated 1
June 6, 1980 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 fort.h 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 (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.
6006240$(0
. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amend-ment, and paragraph 2.C.(2) of Facility Operating License No. DPR-75 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.1, are hereby incorporated in the license.
The licensee shall operate the facility in accord-ance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION h/tto /AU A. Schwencer, Acting Chief j
Licer:ing Branch No. 3
)
Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 11, 1980 l
L
nelACHMENT TO LICENSE AMENDPENT NO. 1 FACILITY OPERATING LICENSE N0'. DPR-75 DOCKET N0. 50-311 Revise Appendix A as follows:
Remove Pages Insert Pages 3/4 10-4 3/4 10-4 3/4 10-5 3/4 10-5 4
SPECIAL TEST EXCEPTIONS NO FLOW TESTS LIMITING CON 0! TION FOR OPERATION 3.10.4 The limitations of Specification 3.4.1.1 may be suspended during the performance of startup and PHYSICS TESTS, provided:
4 The THERMAL POWER does not exceed the P-7 Interlock Setpoint, and a.
b.
The Reactor Trip Setpoints on the OPERA 8LE Intermediate and Power Range Channels are set less than or equal to 25% of RATED THERMAL t
POWER APPLICA8ILITY:
During operation below the P-7 Interlock Setpoint.
ACTION:
l With the THERMAL POWER greater than the P-7 Interlock Setpoint, immediately open the reactor trip breakers.
SURVEILLANCE REQUTREMENTS
}
I 4.10.4.1 The THERMAL POWER shall be determined to be less than P-7 Interlock l
Setpoint at least once per hour during startup and PHYSICS TESTS.
4.10.4.2 Each Intermediate, Power Range Channel and P-7 Interlock shall be subjected to a CHANNEL FUNCTIONAL TEST within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> prior to initiating startup or PHYSICS TESTS.
i
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SALEM - UNIT.2 3/4 10-4
SPECIAL TEST EXCEPTIONS POSITION INDICATION SYSTEM - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.10.5 The limitations of Specification 3.1.3.2.2 may be suspended during the performance of individual full length (shutdown and control) rod testing and during rod position indication system calibration provided:
a.
Only one shutdown or control bank is withdrawn from the fully inserted position at a time, and b.
Either 1.
The rod position indicator is OPERABLE during the with-drawal of the rods, or 2.
k-effective is maintained less than or equal to 0.95.
APPLICABILITY:
MODES 3, 4 and 5 during performance of rod testing and during rod position indication system calibration.
ACTION:
If either condition a or condition b above are not met, immediately open the reactor trip breakers.
SURVEILLANCE REQUIREMENTS 4.10.5 The above required rod position indication systems shall be determined to be OPERABLE within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the start of and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter during rod drop time measure-ments by verifying the demand position indication system and the rod position indication systems agree:
a.
Within 12 steps when the rods are stationary, and b.
Within 24 steps during rod. motion.
I SALEM - UNIT 2 3/4 10-5
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