ML20011E047
| ML20011E047 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 01/30/1990 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20011E048 | List: |
| References | |
| NUDOCS 9002070129 | |
| Download: ML20011E047 (9) | |
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3 PUBLIC SERVICE ELECTRIC & GAS _ COMPANY PHILADELPHIA ELECTRIC COMPANY
.DELMAPVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-311 SALEM GENERATING STATION. UNIT NO. 2-AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 88 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 Lig Company and Atlantic City Electric Company thelicensees) dated September 25, 1989 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 Comission; C.
There is reasonable assurance:-(i) that the activities authorized by this arendment 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 emendment 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:
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(2) Technical Specifications and Environ #nental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 88, 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 the date of issuance; FOR THE NUCLEAR REGULATORY COMMISSION
/s/
Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II
Attachment:
Changes to the Technical Specifications Date of Issuance: Jr.nuary 30, 1990 l
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b 'i (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained-in Appendices-A and B, as revised through Amendment No. 88, 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 the date of issuance, i
FOR THE MUCLEAR REGULATORY COMMISSION i
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Walter R. Butler, Director Project Directorate 1-2 Division of Reactor Projects 1/11 i
Attachment:
Changes to the Technical Specifications l
Date of Issuance: January 30, 1990 l
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19 1 ATTACHMENT TO LICENSE AMENDMENT NO. nn w-
.fACILITYOPERATINGLICENSENO.DPR-75 I
DOCr.ET N0. 50-311 Revise Appendix A as follows:-
Remove Pages Insert Paces 3/4 7-16 3/4 7-16 3/4 7 3/4 7-19 3/4 9-14 3/4 9-14 8 3/4 7-5 B 3/4 7-5 B 3/4.9-3 B 3/4 9-3 r
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7 PIANT' SYSTEMS
'r SURVEll. LANCE REQUfREMENTS (Continued) y 1
t At least once per 31 days by initiating i' low through the HEPA a.
filter and charcoal'adsorber train and verifying that _the train operates for at least one hour and maintains the control room air 1
temperature less than or equal to 120'F with each fan operating for at least 15 minutes, b.
At least once per 18 months or (1)'after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2)-
following painting, fire or chemical release in any ventilation zone communicating with the system, by:
i 1.
Verifying that the charcoal.adsorbe_rs remove 2 99% of a halogenated hydrocarbon refrigerant test gas and that the HEPA filter banks remove 2 99% of the DOP when they are tested-in place using the test procedure guidance of Regulatory Positions C.S.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 7410 cfm i 104, 2.
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.
3.
Verifying a system flow rate of 7410 cfm i 10% during-system operation.
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.
SALEM UNIT 2 3/4 7-16 Amendment No. 88
.i PIANT SYSTEMS -
b SURVEILI.ANCE REQUIREMENTS'(Continued) 1.
Verifying that with the system operating at a flow rato 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 2 99% of a F
halogenated hydrocarbon refrigerant test gas and that the HEPA filter banks remove 2 99% of the DOP when they are tested in place using the test procedure guidance of Regulatory Positions C.5.a., C.5,c and C,5,d of Regulatory Guide 1,52, Revision 2, March 1978 (except for the provisions'of ANSI N510 Sections 8 and 9), and th' system flow rate is R1, ann ifm 1 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.
Verifying a system flow rate of 21,400 cfm t 10% during f
system operation.
. Af ter 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 af ter 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, 3
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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 Cauge 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. 88
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ib REFUELING ' OPERATIONS -
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[': F SURVEILLANCE REQUIREMENTS (Continued)'
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Verifying _that the charcoal.adsorbers remove 2 99% of a halogenated hydrocarbon refrigerant test gas and'that the HEPA-filter banks remove 2 99% of the DOP when they are tested in place using the test procedure guidance of Regulatory
-Positions C.5.a. C.5.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 f1'ow rate is 19,490 cfm i 10%.
3.
Verifying within 31 days after removal that a laboratory r -
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 Verifying a system flow rate of 19,490 cfm i 10%
during system operation,
~Af ter 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 is less than or equal to 4 inches Water Cauge while operating the system 7
at a flow rate of 19,490 cfm i 104.
2.
Vorifying that on a high radiation test signal, the system automatically starts (unless already operating) and_ directs its exhaust flow through the HEPA filters and charcoal adsorber banks.
3.
Verifying that the system maintains the spent fuel storage pool area at a negative pressure of greater than K
or equal to 1/8 inches Water Gauge relative to the outside atmosphere during system operation.
SALEM UNIT 2 3/4 9-14 Amendment No. 88 l
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PL NT SYSTEMS A. "
BASES -
L 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 EMERCENCY AIR CONDITIONING 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 system 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 1
should be usted as procedural guidelines for surveillance testing.
3/4.7.7 AUXILI ARY BUILDING EXHAUST AIR FILTRATION SYSTEM The OPERABILITY of the auxiliary building exhaust air filtration system ensures that radioactive materials leaking from the ECCS equipment following a LOCA are filtered prior to reaching the environment. The operation of this system and the resultant effect on offsite dosage calculations was assumed in the accident analyses, ANSI N510-1975 and Generic Letter 83 13 should be used as procedural guidelines for surveillance testing.
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 surveillance requirements commensurate with the probability of damage to a source in that group.
Those sources which are frequently handled are required 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.'
SALEM UNIT 2 B 3/4 7-5 Amendment No. 88 1
REFUELING OPERATIONS
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3/4.9.9 CONTAINMENT PURGE AND PRESSURE VACUUM RELIEF ISOLATION SYSTEM The OPERABILITY of'this-system ensures that the containment vent and.
purge penetrations will be automatically isolated upon detection of high radiation levels within the containment. The OPERABILITY of this system is required'to restrict the release of radioactive material from the containment atmosphere to the environment.
3 /4. 9.10 and 3 /4 /9 /11 VATER LEVEL REACTOR VESSEL AND STORAGE POOL f
The restrictions on minimum water level ensure that sufficient water depth is available to remove 99% of the assumed 10% iodine gap activity.
released from the rupture of an irradiated fuel assembly. The minimum water depth is consistent with the assumptions of the accident analysis, i
3/4.9.12 FUEL HANDLING AREA VENTILATION SYSTEM The limitations on the fuel handling area ventilation system ensure that all radioactive material released from an irradiated fuel assembly will be filtered through'the HEPA filters and charcoal adsorber prior to discharge to the atmosphere, The OPERABILITY of this system and the resulting iodine.
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removal capacity are consistent with the assumptions of the accident analyses.
ANSI N510 1975'and Generic Letter 83 13 should be used as procedural guidelines for. surveillance testing.
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SALEM - UNIT 2 B 3/4 9 3 Amendment No. 88
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