ML20217B222
| ML20217B222 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 09/11/1997 |
| 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 | |
| ML20217B228 | List: |
| References | |
| DPR-70-A-200, DPR-75-A-184 NUDOCS 9709230273 | |
| Download: ML20217B222 (8) | |
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WASHINGTON, D.C. - =t 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.200 License No. DPR-70 1.
The Nuclear Regulatory Commission (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 Conpany (the licensees) dated April 25, 1997, as supplemented on June 6, 1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission'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: (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 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 Commission'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:
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(2) Technical Snecifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and 8 as revised through Amendment No. 200, are hereby incorporated In the license. The licensee shall o the Technical Specifications. perate the facility in accordance with I
3.
This license amendment is effective as of its date of issuance and shall be implemented within 60 days of issuance.
1 FOR THE NUCLEAR REGULATORY COMISSION
. hn T. Stolz, Direct i
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0 vision of Reactor Projects. 1/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: September 11, 1997 r
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ATTACHMENT TO LICENSE AMENDMENT NO. 200 FACILITY OPERATING LICENSE No. DPR-70 1
1 LOCKET NO. 50-272 1
Revise Appendix A as follows:
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EMERGENCY CORE COOLING SYSTEMS ECCS SUBSYSTEMS - 7,y _ a 350'r LIMITING CONDITION roR OPERATION 3.5.2 Two independent ECCS subsystens shall be OPERABLE with each subsystem comprised of the following injection systems a.
One OPERABLE centrifugal charging pump and associated flow path capable of taking suction from the refueling water storage tank and transferring suction to the residual heat removal pump discharge piping ands 1.
Discharging into each Reactor Coolant System (RCS) cold leg.
b.
One OPERABLE safety injection pump and associated flow path capable of taking suction from the refueling water storage tank and transferring suction to the residual heat removal pump discharge piping and; 1.
Discharging into each RCS cold leg, ands upon nanual initiation, 2.
Discharging into its two associated RCS hot legs.
c.
One OPERABLE residual heat removal pump and associated residual heat removal heat exchanger and flow path capable of taking suction from the refueling water storage tank on a safety injection signal and transferring suction to the containment sump during the recirculation phase of operation ands 1.
Discharging into each RCS cold leg.
APPLICABILITY: MODES 1, 2 and 3.
ACTION:
a.
With one ECCS subsystem inoperable, restore the inoperable subsystem 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 HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
b.
In the event the ECCS is actuated and injects water into the Reactor Coolant System, a special Report shall be prepared and submitted to the Conadssion pursuant to specification 6.9.2 within 30 days describing the circumstances of the actuation and the total accumulated actuation cycles to date.
c.
With both ECCS subsystens inoperable for surveillance testing /
restore at least one subsystem to OPERABLE status within I hour 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 at least 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 /> and at least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SALEM - UNIT 1 3/4 5-3 Amendment No. 200 l
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/g WASHINGTON, D.C. asseHoot PUBLIC SERVICE ELECTRIC & 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 OPERATING LICF,NSI Amendment No.184 License No. DPR-75 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 Corpany and Atlantic City Electric Company (the licensees) dated April 25, 1997, as supplemented on June 6, 1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission'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:
!) that the activities authorized by this amendment can be conducted (without endangering the health and safety of the public, and (ii) ion's regulations set forth in 10 CFR that such activities will be conducted in compliance with the Commiss 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 Commission'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:
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(2) Technical Snecifications and Environmental Protection Plan The Technical Specifications contained in Apsendices A and B, as revised through Amendment No.184, are here)y incorporated in the license.
The licensee shall o the Technical Specifications. perate the facility in accordance with 3.
This license amendment is effective as of its date of issuance and shall be implemented within 60 days of issuance.
FOR THE NUCl. EAR REGULATORY COMMISSION ojectDirectorate(L-2F. Stolz, Direc pr o
Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: September 11, 1997 4
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ATTACHMENT TO LICENSE AMENDMENT NO. 184 FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 Revise Appendix A as follows:
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EMERGENCY EORE COOLING SYSTD4S ECCS SUBSYSTEMS - T,.
2 350*F iiXITING CONDITION FOR OPERATION
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3.5.2 Two independent ECCS subsystems shall be OPERABLE with each subsystem comprised of the following injection systems:
One OPERABLE centrifugal charging pump and associated flow path a.
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capable of taking suction from the refueJis.3 water storage tank and a-transferring suction to the residual heat removal pump discharge piping and; 1.
Discharging into each Reactor Coolant System (RCS) cold leg.
b.
One OPERABLE safety injection pump and associated flow path capable of taking suction from the refueling water storage tank and transferring suction to the residual heat removtl pump discharge piping and; 1.
Discharging into each RCS cold leg, and; upon manual initiation, 2.
Discharging into l's twe associated RCS hot legs.
c.
One OPERABLE residual heat removal pump and associated residual heat removal heat exchanger and flow path capable of taking suction from the refueling sater storage tank on a safety injectior signal ar.d
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transferring suction to the containment su,9p during the recirculation phase of operation and;
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Discharging into each RC3 cold leg.
APPLICABILITY: MODES 1, 2 and 3.
ACTION:
hith one ECCS subsystem inoperable, restore the inoperable subsystem a.
l 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 HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
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b.
In the event the ECCS is actuated and in,4kats water into the Reactor Coolant 3ystem, a Special Report shall be prepared and submitted to L
the Corudssion pursuant to Specification 6.9.2 within 90 days describing the circumstances of the actuation and the total accumulated actuation cycles to date. The current value of the ue: ge factor for each affected safety injection norrio shall be orovided in this Special Report whenever its value excesds 0.70.
SALEM - UNIT 2 3/4 5-3 Amendment No. 184 l
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