ML20148B994
| ML20148B994 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 03/10/1988 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20148B997 | List: |
| References | |
| NUDOCS 8803220228 | |
| Download: ML20148B994 (10) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION e
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PHILADELPHIA ELECTRIC COMPANY DOCKET NO. 50-3 9 LIMERICK GENERATING STATION, UNIT 1 PENDMENTTOFACILITYOPERATINGLICENSE Amendment No. 8 License No. NPF-39 1.
The Nuclear Regulatory Comission (the Comission) has 'ound that A.
The application for amendment by Philadelphia Electric Company (tha licensee) dated March P3, 1987, complies with the standards and requirements of the Atomic Energy Act of 1054, as amended (the Act),
and the Comission's rules and regulations set forth in 10 CFR Chapter !;
B.
The facility will ooerate 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 P.mendment 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; 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 Corraission's regulations and all applicable requirements have been satisfied.
2 Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(?)
of Facility Operating License No. NPF-39 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 8 are hereby inccrporated into this license.
Philadelphia Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
8803220228 080310 DR ADOCK 05000352 PDR
. 3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGillATORY 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: March 10, 1988 f'f PDI-2/
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3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
'47!
t Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II
Attachment:
Changes to the Technical Specifications Date of Issuance: March 10, 1988
ATTACHMENT TO LICENSE AMENDMENT NO. 8 FACILITY OPERATING LICENSE NO. NPF-39 DOCKET NO. 50-35?
Replace the following pages of the Appendix A Technical Specifications with the attached pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Overleaf page is provided to maintain document completeness.*
Remove Insert xxi xxi xxii
- xxii
- 3/4 6-45*
3/4 6-45*
3/4 6-46 3/4 6-46 8 3/4 6-5*
B 3/4 6-5*
B 3/4 6-Sa B 3/4 6-6 i
4 INDEX BASES SECTION PAGE CONTAINMENT SYSTEMS (Continued) 3/4.6.3 PRIMARY CONTAINMENT ISOLATION VALVES...............
B 3/4 6-4 3/4.6.4 YACVUM RELIEF......................................
B 3/4 6-4 3/4.6.5 SECONDARY CONTAINMENT..............................
B 3/4 6-5 3/4.6.6 PRIMARY CONTAINMENT ATMOSPHERE CONTROL.............
B 3/4 6-6 l 3/4.7 PLANT SYSTEMS 3/4.7.1 SERVICE WATER SYSTEMS..............................
B 3/4 7-1 3/4.7.2 CONTROL ROOM EMERGENCY FRESH AIR SUPPLY SYSTEM.....
B 3/4 7-1 3/4.7.3 REACTOR CORE ISOLATION COOLING SYSTEM..............
B 3/4 7-1 3/4.7.4 SNUBBERS.................,.........................
B 3/4 7-2 3/4.7.5 SEALED SOURCE CONTAMINATION........................
B 3/4 7-3 3 '4. 7. 6 FIRE SUPPRESSION SYSTEMS........................
B 3/4 7-4 1/4.7.7 FIRE RATED ASSEMBLIES..............................
B 3/4 7-4 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1, 3/4.8.2, and 3/4.8.3 A.C. SOURCES, D.C. SOURCES, and ONSITE POWER DISTRIBUTION SYSTEMS...............................
B 3/4 8-1 3/4.8.4 ELECTRICAL EQU1PMENT PROTECTIVE DEVICES............
B 3/4 8-3 3/4.9 REFUELING OPERATIONS 3/4.9.1 REACTOR MODE SWITCH................................
B 3/4 9-1 3/4.9.2 INSTRUMENTATION....................................
B 3/4 9-1 3/4.9.3 CONTROL ROD P0SITION...............................
B 3/4 9-1 3/4.9.4 DECAY TIME.........................................
B 3/4 9-1 3/4.9.5 COMMUNICATIONS.....................................
B 3/4 9-1 LIMERICK - UNIT 1 xxi Amendment No. 8 l
INDEX BASES SECTION PAGE REFUELING OPERATIONS (Continued) 3/4.9.6 REFUELING PLATF0RM................................
B 3/4 9-2 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE P00L............
B 3/4 9-2 3/4.9.8 and 3/4.9.9 WATER LEVEL - REACTOR VESSEL and WATER LEVEL - SPENT FUEL STORAGE P00L.........
B 3/4 9-2 3/4.9.10 CONTROL R00 REMOVAL.,...........................
B 3/4 9-2 3/4.9.11 RESIOUAL HEAT REMOVAL AND COOLANT CIRCULATION.....
B 3/4 9-2 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 PRIMARY CONTAINHENT INTEGRITY.....................
B 3/4 10-1 3/4.10.2 R00 SEQUENCE CONTROL SYSTEM.......................
B 3/4 10-1 3/4.10.3 SHUT 00WN MARGIN DEMONSTRATIONS...................
B 3/4 10-1 3/4.10.4 RECIRCULATION LOOPS............................
B 3/4 10-1 3/4.10.5 OXYGEN CONCENTRATION...........................
B 3/4 10-1 3/4.10.6 TRAINING STARTUPS...............................
B 3/4 10-1 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS Concentration........................
B 3/4 11-1 0ose..............................................
B 3/4 11-1 Liquid Radwaste Treatment System..................
B 3/4 11-2 Liquid Holdup Tanks...............................
B 3/4 11-2 3/4.11.2 GASEOUS EFFLUENTS Dose Rate.........................................
B 3/4 11-2 Dose - Noble Gases...............................
B 3/4 11-3 Oose - Iodine-131 Iodine-133, Tritium, and Radionuclides in Particulate Form.................
B 3/4 11-3 Ventilation Exhaust Treatment System..............
B 3/4 11-4 LIMERICK - UNIT 1 xxii
I CONTAINMENT SYSTFMS SURVEILLANCE REQUIREMENTS 4.6.4.1 Each suppression chamber - drywell vacuum breaker shall be:
a.
Verified closed at least once per 7 days.-
b.
Demonstrated OPERABLE:
1.
At least once per 31 d; and within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> after any discharge of steam to the supprt? on chamber from the safety / relief valves, by cycling each vicuum breaker through at least one complete cycle of full tsavel.
2.
At Itast once per 31 days by verifying both position indicators OPERABLE by observing expected valve movement during the cycling test.
3.
At least once per 18 months by; a)
Verifying each valve's opening setpoint, from the closed position, to be 0.5 psict 2 5%, and b}
Verifying both position indicators OPERABLE by performance of a CHANNEL CALIBRATION, c)
\\erifying that each outboard valve's position indicatrr is capable of detecting disk displacement 10.050" and each inboard valve's position indicator" is capable.f detecting disk displacement 10.120".
LIMERICK - UNIT 1 3/4 6-45
CONTAINMENT SYSTEMS i'
3/4.6.5 SECONDARY CONTAINMENT REACTOR ENCLOSURE SECONDARY CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.5.1.1 REACTOR ENCLOSURE SECONDARY CONTAINMENT INTEGRITY shall be maintained.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.
ACTION:
Without REACTOR ENCLOSURE SECONDARY CONTAINMENT INTEGRITY, restore REACTOR ENCLOSURE SECONDARY CONTAINMENT INTEGRITY within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least 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 /> and in COLD SHUTOOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.5.1.1 REACTOR ENCLOSURE SECONDARY CONTAINMENT INTEGRITY shall be demon-strated by:
Verifying at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> that the pressure within the a.
reactor enclosure secondary containment is greater than or equal to 0.25 inch of vacuum water gauge, b.
Verifying at least once per 31 days that:
1.
All reactor enclosure secondary containment equipment hatches and blowout panels are closed and sealed.
2.
At least one door in each access to the reactor enclosure secondary containment is closed.
3.
All reactor enclosure secondary containment penetrations not capable of being closed by OPERABLE secondary containment auto-matic isolation dampers / valves and required to be closed during accident conditions are closed by valves, blind flanges, slide gate dampers or deactivated automatic dampers / valves secured in
- positica, c.
At least once per 18 monthr.
1.
Verifying that one scandby gas treatment subsystem will draw down the reactor enclosure secondary containment to greater than or equal to 0.25 inch of vacuum water gauge in less than or equal to 121 seconds with the reactor enclosure recirc system in operation, and 2.
Operating one standby gas treatment subsystem for one hour and maintaining greater than or equal to 0.25 inch of vacuum water gauge in the reactor enclosure secondary containment at a flow rate not exceeding 1250 cfm with wind speeds of < 7.0 mph as measured on the wind instrument on Tower 1 elevation 30' or, if that instrument is unavailable, Tower 2, elevation 159'.
LIHERICK - UNIT 1 3/4 6-46 Amendment No. s
CONTAINMENT SYSTEMS BASE $
3/4.6.5 SECONDARY CONTAINMENT Secondary containment is designed to minimize acy ground level release of radioactive material which may result from an accident The Reactor Enclosure and associated structures provide secondary containment during normal operation when the drywell is sealed and in service. At other times the drywell may be open and, when required, secondary containment integrity is specified.
Establishing and maintaining a vacuum in the reactor enclosure secondarj containment with the standby gas treatment system once per 13 months, along with the surveillance of the doors, hatches, dampers and valves, is adequate to ensure that there tre no violations of the integrity of the secondary containment.
The OPERABILITY of the reactor enclosure recirculation system and the standby gas treatment systems ensures that sufficient iodine removal capability will be available in the event of a LOCA or refueling accident (SGTS only).
The reduction in contcinment iodine inventory reduces the resulting SITE SOUNDARY radiation doses associated with containment leaxage.
The operation uf this systrm and resultant iodine removal capacity are consistent with the assumptions used in the LOCA and refueling accident analyses.
Provisions have been made to continuously purge the filter plenums with instrument air when the filters are not in use to orevent buildup of coisture on the adsorbers and the WEPA 'ilters Although the safety analyses assumes that the reactor enclosure secondary containment draw down time will take 135 seconds, these surveillance require-ments specify a draw down time of 121 seconds. This 14 second difference is due to the diesel generator starting and sequence loading delays which is not part of this surveillance recyirement.
The reactor enclosure secondary containment draw down time analyses assumes a starting point of 0.25 inch of vacuum water gauge and worst case SGTS dirty filter flow rate of 2800 cfm.
The surveillance requirements satisfy this as-sumption by starting the drawdown from ambient conditicns and connecting the adjacent reactor enclosure and refueling area to the SGTS to split the exhaust flow between the three zones and verifying a minimum flow rate of 2800 cfm from the test zone.
Tnis simulates the worst case flow alignment and verifies ade-quate flow is available to drawdown the test zone within the required time.
The Technical Specification Surveillance Requirement 4.6.5.3.b.3 is intended to be a multi-zone air balance verification without isolating any test zone.
The SGTS fans are sized for three zones and therefore, when aligned to a i
single zone or two zones, will nave excess capacity to more quickly drawdewn l
the affected zones.
Inere is no maximum flow limit to individual zones or pairs of zones and the air balance and drawdown time are verified when all three zones are connected to the SGTS.
The three zone air balance verification and drawdown test will be done prior to initial criticality of Unit 2 or after any major systeu citeration, which is any modification which will have an effect on the SGTS flowrate such that the ability of the SGTS to drawdown the reactor enclosure to greater than or equal to 0.25 inch of vacuum water gage in less than or equal to 121 seconds could be affected.
LIMERICK - UNIT 1 8 3/4 6-5 Amendment Iso. 6 JULS G87
CONTAINHENT SYSTEMS BASES 4
3/4.6.5 SECONDARY CONTAINMENT (Continued)
The field tests for bypass leakage t. cross the SGTS charcoal adsorber and HEPA filter banks are performed at a flow rate of 3000 t 10% cfm.
This flow rate correspor.ds to the maximum overall three zone inleakage rate of 3264 cfm.
The SCTS filter train pressure drop is a function of air flow rate and filter conditions.
Surveillance testing is performed using either the SCTS or drywell purge fans to provide operating convenience.
Each reactor enclo:;ure secondary containment tone and refueling area secondary containment Zone is tested independently to verify the design leak tightness. A design leak tightness of 1250 cfm or less for each reactor enclosure and 764 cfm or less.for the refueling area at a 0.25 inch of vacuum water gage will ensure that containment integrity is maintained at an acceptable level if all zones are connected to the SGTS at the same time.
The post-LOCA offsite dose analysis assumes a reactor enclosure secondary containment post-draw down leakage rate of 1250 cfm and certain post-accident X/Q values.
While the post-accident X/Q values represent a statistical inter-pretation of historical meteorological data, the highest ground level wind speed which can be associated with these values is 7 mph (Pasquill-Gifford stability Class G for a ground level release).
Therefore, the surveillance requirement assures that tha reactor enclosure secondary containment is verified under meteorological conditions consistent with the assumptions utilized in the design basis analysis. Reactor Enclosure Secondary Containment leakage tests that are successfully performeri at wind speeds in excess of 7 mph would also satisfy the leak rate surveillance requirements, since it shows compliance with more conservative test conditions.
3/4.6.6 PRIMARY C0HTAIUMENT ATMOSPHERE CONTROL The OPERABILITY of the systems required for the detection and control of hydrogen combustible mixtures of hydrogen and oxygen ensures that these systems will be available to maintain the hydrogen concentration within the primary containment below the lower flammability limit during post-LOCA conditions.
The primary contair. ment hydrogen recombiner is provided to maintain the oxygen concentration be hw the lower flammability limit. The combustible gas analyzer is provided to continuously monitor, both during normal operations and post-LOCA, the hydrogen and oxygen concentrations in the primary containment.
The primary containment atmospheric mixing system is provided to ensure adequate mixing of the containment atmosphere to prevent Mcalized accumulations of hydrogen and oxygen from exceeding the lower flammability limit. The hydrogen control system is consistent with the recommendations of Regulatory Guide 1.7, "Control of Combustible Gas Concentrations in Containment Following a LOCA," March 1971.
l LIMERICK - UNIT 1 B 3/4 6-6 Amendment No. 8
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