ML20133B448
| ML20133B448 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 12/12/1996 |
| 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 | |
| ML20133B453 | List: |
| References | |
| DPR-75-A-168 NUDOCS 9701030191 | |
| Download: ML20133B448 (5) | |
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UNITED STATES s
j NUCLEAR REGULATORY COMMISSION t
WASHINGTON, D.C. 20066 4 001
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PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY j
DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-311 SALEM NUCLEAR GENERATING STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPcRATING LICEM1 Amendment No. 168 License No. OPR-75 1.
The Nuclear Regulatory Comission (the Comission or the NRC) has foun<l 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 September 20, 1996, as supplemented September 30, 1996, cormlies 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 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:
9701030191 961212 PDR ADOCK 05000311 P
(2) Technical' Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendt.ent No. 168, 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 30 days.
FOR THE NUCLEAR REGU ATORY COMMISSION Jc/in
. Stolz, Director Project Directorate I-
'Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Ttt.u b unt: Change:, to the Technical Specifications Date of Issuance: December 12, 1996
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i ATTACHMENT TO LICENSE AMENDMENT NO.16fL FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 l
Revise Appendix A as follows:
Remove Paaes Insert Paaes 3/4 7-19 3/4 7-19 B 3/4 7-5 8 3/4 7-5 i
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PLANT SYSTEMS BASES 3 /4. 7. 5 FLOOD PROTECTION The limitation on flood protection ensures that facility protective actions will be taken and operation will be terminated in the event of flood conditions. The limit of elevation 10.5' Mean Sea Level is based on the elevation above which facility flood control measures are required to provide protection to safety-related equipment.
3/4.7.6 CONTROL ROOM EMERGENCY AIR CONDITIO1.. K3 SYSTEM The OPERABILITY of the control room emergency air conditioning system ensures that 1) the ambient air temperature does not exceed the allowable temperature for continuous duty rating for the equipment and instrumentation cooled by this cystem and 2) the control room will remain habitable for operations personnel during and following all credible accident conditions.
The OPERABILITY of this system in conjunction with control room design provisions is based on limiting the radiation exposure to personnel occupying the control room to 5 rem or less whole body, or its equivalent. This limitation is consistent with the requirements of General Design Criterion 19 of Appendix "A", 10 CFR Part 50. ANSI N510-1975 and Generic Letter 83-13 should be used as a procedural guideline for surveillance testing.
3/4.7.7 AUXILIARY BUILDING EXHAUST AIR FILTRATION SYSTEM l
The flowrates specified for surveillance testing correspond to the maximum design flow for the charcoal adsorber. This is the limiting condition for system performance under accident conditions. Testing at this flow assures that the charcoal adsorber removal efficiency, and the system bypass leakage are within the assumed values of the accident analysis. Operation at lower flowrates is conservative with respect to the accident analysis assumptions.
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3 /4. 7. 8 SEALED SOURCE CONTAMINATION The limitations on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10 CFR 70.39 (c) limits for plutonium. This limitation will ensure that leakage from byproduct, source, and special nuclear material sources will not exceed allowable intake values.
Sealed sources are classified into three groups according to their use, with l
surveillance requirements commensurate with the probability of damage to a i
source in that group. Those sources which are frequently handled are required l
to be tested more often than those which are not.
Sealed sources which are continuously enclosed within a shielded mechanism (i.e.,
sealed sources within radiation monitoring or boron measuring devices) are considered to be stored and need not be tested unless they are removed from the shielded mechanism.
l SALEM - UNIT 2 B 3/4 7-5 Amendment No. 168 l
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PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 1.
Verifying that with the system operating at a flow rate of 21,400 cfm i 10 % and exhausting through the HEPA filters and charcoal adsorbers, the total bypass flow'of the ventilation system to the facility vent, including leakage through the ventilation system diverting valves, is less than or equal to it when the system is tested by admitting cold DOP at the system intake.
2.
Verifying that the charcoal adsorbers remove a. 99% of a halogenated hydrocarbon refrigerant test gas and that the HEPA filter banks remove a 99% of the DOP when they are tested in-place using the test procedure guidance of Regulatory Positions C.5.a, C.S.c and C.S.d of Regulatory Guide 1.52, Revision 2, March 1978 (except for the provisions of ANSI N510 Sections 8 and 9,, and the system flow rate is 21,400 cfm i 10%.
3.
Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978.
4.
Verify that the system flowrate does not exceed the design limit of 23,540 cfm (21,400 cfm + 10%) when the HEPA + Charcoal adsorber filter train is aligned to the ECCS equipment areas.
After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation by c.
verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978.
d.
At least once per 18 months by:
1.
Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks of less than 4 inches Water Gauge while operating the system at a flow rate of 21,400 cfm i 10%.
2.
Verifying that the system starts on a Safety Injection Test Signal.
SALEM - UNIT 2 3/4 7-19 Amendment No.168 l