ML20217Q673
| ML20217Q673 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 08/26/1997 |
| From: | Public Service Enterprise Group |
| To: | |
| Shared Package | |
| ML20217Q667 | List: |
| References | |
| NUDOCS 9709030308 | |
| Download: ML20217Q673 (4) | |
Text
ATTACHMENT 3 LCR-H97-16 LETTER LR-N97523 HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NPF-57 DOCKET NO. 50-354 REVISIONS TO THE TECHNICAL SPECIFICATIONS (TS)
TECHNICAL SPECIFICATION PAGES WITH PROPOSED Clh4GES The following Technical Specifications for Facility Operating License No. NPF-57 are affected by this change request:
Technical Specification Page 4.6.5.3.1.b 3/4 6-51 4.6.5.3.2.b 3/4 6-52a Bases 3/4.6.5 B 3/4 6-5 970903030s 970826 gDR ADOCK'05000354 PDR a
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-CONTA!NMENT $YSTENS
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FRv5 VENTILATION SU$$Y$ TEN I
L!NITING CON 0! TION FOR OPERATION 3.6.5.3.1 Two FRV5 ventilation units shall ee OPERA 8LE.
l APPLICA81LITY:
OPERATIONAL CON 0!TIONS 1, 2, 3 and a, ACTION:
With one of the above required FRVS ventilation units inoperable, a.
restore the inoperable unit to OPERABLE status within 7 days, or:
1.
In OPERATIONAL CONDITION 1, 2 or 3, be in at least H0T SHUT 00WN 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 SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
2.
In Operational Condition suspend he.dling of irradiated fuel in the secondary containment, CORE ALTEtAT!0NS and operations with a potential for draining the reactor vessel.
The provisions of Specification.'.0.3 are not applicable.
Witn both ventilation units inoperable in Operational Condition *,
D.
suspend handling of irradiated fuel in the secondary containment, CORE ALTERATION $-or operations with a potential for draining the reactor vessel.
The provisions of Specification 3.0.3. are not applicable.
SURVE!LLANCE REQUIREMENTS 4.6.5.3.1 Each of the tw ventilation units shall be demonstrated OPERA 8LE:
I At least once per 14 days by verifying that the water seal bucket a.
traps have a water seal and making up any evaporative losses by fil-ling the traps to the overflow, b.
At least once per 31 days by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifyin that tne subsystem operates for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> with the heaters n orcer to reduce the buildup of moisture on the carbon adsorbers nd NEPA filters.- m m q
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"When irradiated fuel is being handled n the secondary containment and during CORE ALTERATIONS and operations with a potential for draining the reactor vessel.
HOPE CREEK 3/4 6-51 Amendment No. 30
._______m__---
CONTAINMErr SYSTEMS 3.6.5.3 FILTRATION. 11 CIRCULATION AND VENTILATION SYSTEM WRVS)
FRVS REC'1RCtflayf aN SUBSYSTEM LIMITING CONDITICH FOR OPERATION 3.6.5.3.2 Six FRVS recirculation units shall be OPERABLE.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, 3 and *.
ACTION:
a.
With one or two of the above required FRVS recirculation units inoperable, restore all the inoperable unit (s) to OPERABLE status within 7 days, or 1.
In CPERATICNAL CONDITION 1, 2, or 3, be in at least HOT SHWDOWN 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 SHWDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
2.
In operational condition *, suspend handling of irradiated fuel in the secondary contairment, CORE ALTERATIONS and operations with a potential for draining the reactor vessel.
The provisions of Specification 3.0.3 are not applicable.
b.
With three or more of the above required FRVS recirculation units inoperable in operational Condition *, suspend handling of irradiated fuel in the secondary containment, CORE ALTERATIONS or operations with a potential for draining the reactor vessel. The provisions of Specification 3.0.3 are not applicable, c.
With three or more of the above required FRVS recirculation units inoperable in OPERATIONAL CONDITION 1, 2, or 3, 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 SHWDOWN 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 4.6.5.1.2 Each of the six FRVS recirculation units uhall be demonstrated OPERABLE:
a.
At least once per 14 days by verifying that the water seal bucket traps have a water seal and making up any evaporative losses by filling the traps to the overflow.
b.
At least once per 31 days by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying,
that the subsystem operates for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> with the heaters (j nh a order to reduce the buildu of.Japis1uga_on,_tb3 ca
'adsorbers and HEPA fib ers, k r u e <-
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- When irradiated fuel is being 7 co containment and ng CORE ALTERATIONS and operations with a potential for draining the reactor vessel.
HOPE CREEK 3/4 6 52a Amendment No. 99
CONTAINMENT SYSTEMS BASES 3/4.6.3 PRIMARY CONTA!NMENT.! SOLATION VALVES The OPERABILITY of the primary containment isolation valves ensures that the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressurization of the containment and is consistent with the requirements of GDC 54 through 57 of Appendix A of 10 CFR 50.
Containment isolation within the time limits specified for those isolation valves designed to close auto-matica11y ensures that the release of radioactive material to the environment will be consistent with the assumptions used in the analyses for a LOCA.
3/4.6.4 VACUUM RELIEF Vacuum relief breakers are provided to equalite the pressure between the suppression chamber and drywell and between the Reactor Building and suppres-sion chamhr.
This system will maintain the structural integrity of the primary containment under conditions of large differential pressures.
The vacuum breakers between the suppression chamber and the drywell must not be inoperable in the open position since this would allow bypassing of the suppression pool in case of an accident.
3/4.6.5 $ECONDARY CONTAINMENT Secondary containment is designed to minimize any ground level release of radioactive material which may result from an accident.
The Reactor Building 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 0.25 inch water gage vacuum in the reactor ouilding with the filtration recirculation and ventilation system (FRVS) once per 18 months, along with the surveillance of the doors, hatches, dampers and valves, is adequate to ensure that there are no v.iolations of the integrity of the secondary containment.
The OPERABILITY of the FRVS ensures that sufficient iodine removal capa-bility will be available in the event of a LOCA.
The reduction in containment iodine inventory reduces the resulting site boundary radiation doses associated with containment leakage.
The operation of this system and resultant iodine removal capacity are consistent with the assumptions used in the LOCA analyses and with the drawdown analysis.
Continuousoperayonofthesystemwiththe heaters and humidity control instruments Oa % c for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> during each 31 day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters.
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