ML20100C072
| ML20100C072 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 01/24/1996 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Public Service Electric & Gas Co, Philadelphia Electric Co, Delmarva Power & Light Co, Atlantic City Electric Co |
| Shared Package | |
| ML20100C075 | List: |
| References | |
| DPR-70-A-179, DPR-75-A-160 NUDOCS 9601300054 | |
| Download: ML20100C072 (8) | |
Text
._._ ___
..d UNITED STATES P
S NUCLEAR REGULATORY COMMISSION j
WASHINGTON, D.C. 28564 2
% *** /
PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-272 SALEM NUCLEAR GENERATING STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 179 License No. DPR-70 1.
The Nuclear Regulatory Comission (the Comission or the NRC) has found that:
A.
The application for amendment filed by the Public Service Electric &
Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated October 11, 1994, as supplemented December 13, 1994, September 6, 1995, and December 28, 1995, 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 t
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 set forth in 10 CFR Chapter I; 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 Specifica-tions as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-70 is hereby amended to read as follows:
1 9601300054 960124 i
DR ADOCK0500g2 i
j
(2) Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No.179, 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 its date of issuance, to be implemented within 60 days.
FOR THE WUCLEAR REGULATORY COMMISSION J
. Stolz, Direc P
ct Directorate I-2 D ision of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
January 24, 1996
ATTACHMENT TO LICENSE AMENDMENT NO.179 FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 Revise Appendix A as follows:
Remove Paaes Insert Paaes i
3/4 4-6 3/4 4-6 i
I I
_..__.-.m
__. _.. ~.. _ _ _ _ _ _ _. _.
REACTOR COOLANT SYSTEM 3/4.4.4 PRESSURIEER LIMITING CONDITION FOR OPERATION' 3.4.4 The pressuriser shall be OPERABLE with a water volume of less than or equal to 1650 cubic feet (92% indicated level), and at least two groups of pressurizer heaters each having a capacity of a 150 kw and capable of being powered from an emergency power supply.
1 APPLICABILITY: MODES 1, 2, and 3.
ACTION:
With the pressurizer inoperable due to an inoperable emergency power a.
supply to the pressurizer heaters either restore the inoperable emergency power supply 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 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 />.
I 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 />.
I SURVEILLANCE REQUIREMENTS 4.4.4.1 The pressurizer water volume shall be determined to be within its limit at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
4.4.4.2 The capacity of each of the above' required groups of pressurizer heaters shall be verified by measuring circuit current at least once each refueling outage.
t 4.4.4.3 The emergency power supply for the pressurizer heaters shall be demonstrated OPERABLE at least once per 18 months by manually transferring power from the normal to the emergency power supply and energizing the heaters.
i 1
i SALEM - UNIT 1 3/4 4-6 Amendment No.179
./
UNITED STATES P
S NUCLEAR REGULATORY COMMISSION h
j WASHINGTON D.o. 30seH001 i
/
i PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT' COMPANY ATLANTIC CITY ELECTRIC COMPANY l
DOCKET NO. 50-311 SALEM NUCLEAR GENERATING STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.160 License No. DPR-75 1.
The Nuclear Regulatory Comission (the Commission or the NRC) has found that:
A.
The application for amendment filed by the Public Service Electric &
Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated October 11, 1994, as supplemented December 13, 1994, September 6, 1995, and December 28, 1995, 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: (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 set forth in 10 CFR Chapter I; 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.
2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-75 is hereby amended to read as follows:
~
. e (2) Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No.160, 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 its date of issuance, to be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COPf4ISSION Join F. Stolz, Di ctor oject Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
January 24, 1996 i
ATTACHMENT TO LICENSE AMENDMENT NO.160 i
FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 Revise Appendix A as follows:
Remove Paaes Insert Paaes 3/4 4-7 3/4 4_7 i
REACTOR COOLANT SYSTEM 3/4.4.4 PRESSURIEER LIMITING CONDITION'FOR OPERATION 3.4.4 The pressurizer shall be OPERABLE with a water volume of less than or equal to 1650 cubic feet (924 indicated level), and at least two groups of pressurizer heaters each having a capacity of a 150 kw and capable of being powered from an emergency power supply.
APPLICABILITY: MODES 1, 2, and 3.
ACTION:
a.
With the pressurizer inoperable due to an inoperable emergency power supply to.the pressurizer heaters either restore the inoperable emergency power supply 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 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 />.
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. REQUIREMENTS 4.4.4.1 The pressurizer water volume shall be determined to be within its limit at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
4.4.4.2 The capacity of each of the above required groups of pressurizer heaters shall be verified by measuring circuit current at least once each refueling outage.
4.4.4.3 The emergency power supply for the pressurizer heaters shall be demonstrated OPERABLE at least once per 18 months by manually transferring power from the normal to the emergency power supply and energizing the heaters.
SALEM - UNIT 2 3/4 4-7 Amendment No.160