ML20148K730
| ML20148K730 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 06/13/1997 |
| 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 | |
| ML20148K734 | List: |
| References | |
| DPR-70-A-195, DPR-75-A-178 NUDOCS 9706180339 | |
| Download: ML20148K730 (10) | |
Text
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%g UNITED STATES B
NUCLEAR RE2ULATORY COMMISSION N
f WASHINGTON, D.C. 20566 4001
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PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. P Jll SALEM NUCLEAR GENERATING STATION. UNIT NO. 1 AMENDMENT TO FACILEY OPERATING LICENSE Amendment No.195 l
License No. DPR-70 1.
The Nuclear Regulatory Commission (the Commissior, 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 i
Company and Atlantic City Electric Company (the lics:. ;es) dated 1
January 31, Ir% complies with the standards and requirements of the Atomic Energy An of 1954, as amended (the Act), and the Commission's rules and regu'ations 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 withoui 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 sect.rity 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 lic.ase amendment, tnd paragraph 2.C.(2) of Facility Operating License No. DPR-70 is hereby amended to read as follows:
9706190339 970613 PDR ADOCK 05000272 P
PDR l
I j !
(2) Technical Specifications and Environmental Protection Plan i
The Technical Specifications contained in Appendices A and B, as revised through Amendment No.195, 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 and shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
$14 ?
o n F. Stolz, Direc or P oject Directorate I-2 Division of Reactor Projccts - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes'to the Technical Specifications l
Date of Issuance:
June 13, 1997 i
4 i
iiI ATTACHMENT TO LICENSE AMENDMENT N0.195 FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 Revise Appendix A as follows:
Remove Paaes Insert Paaes 3/4 6-7 3/4 6-7 6 3/4 6-2 B 3/4 6-2 e
1 l
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CONTAINMENT SYSTEMS AIR TEMPERATURE LIMITING CONDITION FOR OPERATION
.......................................=......................................
3.6.1.5 Primary containment average air temperature shall not exceed 120*F.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
With the containment average air temperature > 120*F, reduce the average air temperature to within the limit within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, or be in at least HOT STANDBY trithin 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 />.
SURVEILLANCE REQUIREMENTS
...u..................
4.6.1.5 Verify the '..ontainment Average Air Temperature is within limit at least once per twenty four hours.
-.LEM - UNIT 1 3/4 6-7 Amendment No.19 5
- ~ - _.. _.
CONTAINMENT SYSTEMS BASES
==================================================================
3/4.6.1.4 INTERNAL PRESSURE The limitations on containment internal pressure ensure that:
- 1) the containment structure is prevented from exceeding its design negative pressure differential with respect to the outside atmosphere of 3.5 psig and 2) the containment peak pressure does not exceed the design pressure of 47 psig during the limiting pipe break conditions. The pipe breaks considered are LOCA and steam line breaks.
The limit of 0.3 psig for initial positive containment pressure ir consistent with the accident analyses initial conditions.
The maximum peak pressure expected to be obtained from a LOCA or steam line break event is s 47 psig.
3/4.C.1.5 AIR TEMPERATURE The limitations on containment average air temperature ensure that the overall containment average air temperature does not exceed the initial temperature condition assumed in the accident analysis for a LOCA or steam line break.
In order to determine the containment average air temperature, an average is calculated using measurements taken at locations within containment selected to provide a representative sample of the overall containment atmosphere.
3/4.6.1.6 CONTAINMENT STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the containment will be maintained comparable to the original design standards for the life of the facility.
Structural integrity is required to ensure that the containment will withstand the design pressure.
The visual inspections of the concrete and liner and the Type A leakage test are sufficient to demonstrate this capability.
SALEM - UNIT 1 B 3/4 6-2 Amendment No.195
f UNITED STATES l
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20666 4001 l
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PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHJA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET N0. 50-311 SALEM NUCLEAR GENERATING STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.178 License No. DPR-75 1.
The Nuclear Regulatory Commission (the Cmission 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 January 31, 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; 8.
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 withrut 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-75 is hereby amended to read as follows:
l (2) Technical Soecifications and Envircnmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No.178, are hereby incorporated in the t
. license. The licensee shall operate the facility in accordance with i
the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION C
Jo'
. Stolz, Direct Pr ect Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: June 13, 1997 1
l l
ATTACHMENT TO LICENSE AMENDMENT NO. 178 FACILITY OPERATING LICENSE N0. DPR-75 1
DOCKET NO. 50-311 Revise Appendix A as follows:
Remove Paaes Insert Paggi 3/4 6-7 3/4 6-7 i
B 3/4 6-2 B 3/4 6-2 i
l e
i I
CONTAINMENT SYSTEMS AIR TEMPERATURE LIMITING CONDITION FOR OPERATION 1
3.6.1.5 Primary containment average air temperature shall not exceed 120*F.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
With the containment average air temperature greater than 120*F, reduce the 3
average air temperature to within the limit within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 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 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 />.
SdRVEILLANCE REQUIREMENTS
....................................=........................................
4.6.1.5 Verify containment average air temperature is within limit at least once per twenty four hours.
SALEM - UNIT 2 3/4 6-7 Amendment No.178
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CONTAINMENT SYSTEMS BASES
=============================================_====================
3/4.6.1.4 INTERNAL PRESSURE The limitations on containment internal pressure ensure that:
- 1) the
~
containment structure is prevented from exceeding its design negative pressure differential with respect to the outside atmosphere of 3.5 psig, and 2) the i
containment peak pressure does not exceed the design pressure of 4i psig during the limiting pipe break conditions.
The pipe breaks considered are l
LOCA and steam line breaks.
The limit of 0.3 psig for initisl positive containment pressure is consistent with the accident analyses initial conditions.
The maximum peak pressure expected to be obtained from a LOCA or steam line break event is s 47 psig.
3/4.6.1.5 AIR TEMPERATURE The limitations on containment average air temperature ensure that the overall containment average air temperature does not exceed the initial temperature condition assumed in the accident analysis for a LOCA or steam line break.
In order to determine the containment average air temperature, an average is calculated using measurements taken at locations within containment selected to provide a representative sample of the overall containment atmosphere.
3/4.6.1.6 CONTAINMENT STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the containment will be maintained comparable to the original design standr.rds for the life of the facility.
Structural integrity is required to ensure that the containment will withstand the design pressure. The visual inspections of the concrete and liner and the Type A leakage test are sufficient to demonstrate this capability.
3/4.6.1.7 CONTAINMENT VENTILATION SYSTEM The containment purge supply and exhaust isolation valves are required to be closed during plant operation since these valves have not been demonstrated capable of closing during a LOCA.
Maintaining *.hese valves closed during plant operations ensures that excessive quantities of radioactive materials will not be released via the centainment purge system.
SALEM - UNIT 2 B 3/4 6-2 Amendment No. 178