ML20063L694
| ML20063L694 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 02/24/1994 |
| From: | WOLF CREEK NUCLEAR OPERATING CORP. |
| To: | |
| Shared Package | |
| ML20063L692 | List: |
| References | |
| NUDOCS 9403070300 | |
| Download: ML20063L694 (5) | |
Text
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Attachment IV to NA 94-0015 Page 1 of 5 l
ATTACHMENT IV l
PROPOSED TECHNICAL SPEC 1FICATION CHANGES i
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( PDR ADOCK 05000482
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Attachment IV to NA 94-0015 Page 2 of 5 9
PLANT SYSTEMS AUXILIARY FEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION ]
3.7.1.2 At least three independent steam generator auxiliary feedwater -
pumps and associated flow paths shall be OPERABLE with:
- a. Two motor-driven auxiliary feedwater pumps, each capable of being powered from separate emergency busses, and
- b. One steam turbine-driven auxiliary feedwater pump capable of being powered from an OPERABLE steam supply system.
. APPLICABILITY: MODES 1,2, and 3.
ACTION:
- a. With one auxiliary feedwater pump inoperable, restore the required auxiliary feedwater pumps to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
- b. With two auxiliary feedwater pumps inoperable, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
- c. With three auxiliary feedwater pumps inoperable, immediately initiate corrective action to restore at least one auxiliary feedwater pump to OPERABLE status as soon as possible.
SURVEILLANCE REQUIREMENTS 4.7.1.2.1 Each auxiliar dwater pump shall be demonstrated OPERABLE:-
quarter
- a. At least once pe'r(34. days n a STAGGERED TEST BASIS by:
- 1) Verifying that each motor-driven pump develops a discharge pressure of greater than or equal to 1535 psig on recirculation flow when tested pursuant to Specification 4.0.5;
- 2) Verifying that the steam turbine-driven pump develops a discharge pressure of greater than or equal to 1625 psig at a flow of greater than or equal to 120 gpm when the secondary steam supply pressure is greater than 900 psig The provisions of Specification 4.0.4 are not applicable for entry into MODE 3; i 1
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1 l Attachment IV to NA 94-0015 l Page 3 of 5 PLANT SYSTEMS
- SURVEILLANCE REQUIREMENTS Q ntinued) mvw -
- b. At le_ast onceper 31 d
- 1) 3) enfyinglit each non-automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in its correct position; and Verifying that each automatic valve in the flow path is in the fully open position whenever the auxiliary Feedwater System is placed in automatic control or when above 10% RATED THERMAL POWER:
At least once per 18 months during shutdown by:
- 1) Verifying that each automatic valve in the ESW supply to the auxiliary feedwater pumps actuates to its full open position upon receipt of an Auxiliary Feedwater Pump Suction Pressure-Low test signal
- 2) Venfying that each auxiliary feedwater pump starts as designed automatically upon receipt of an Auxiliary Feedwater Actuation test signal, and l
l 3) Venfying that each auxiliary feedwater motor-operated discharge
, valve limits the flow to each steam generator from the motor-l driven pump to less than or equal to 320 gpm.
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4.7.1.2.2 An auxiliary feedwater flow path shall be demonstrated OPERABLE following each COLD SHUTDOWN of greater than 30 days prior to entering MODE 2 by ventying normal flow to at least two steam generators from one auxiliary feedwater pump.
WOLF CREEK - UNIT 1 3/4 7-5
Attachment IV to NA 94-0015 Page 4 of 5 PLANT SYSTEMS BASES ,
I ULTiM ATE HEAT SINK (Continued) :
The limitations on minimum water level and maximum temperature are based on providing a 30-day cooling water supply from the Essential Service Water pumps to safety-related equipment without exceeding its design basis temperature and is consistent with the recommendations of Regulatory Guide 1.27," Ultimate Heat Sink for Nuclear Plants," March 1974.
3/4f7.6 CONTROL ROOM EMERGENCY VENTILATION SYSTEM The OPERABILITY of the Control Room Emergency Ventilation 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. Operation of the system w,th the heaters operating to maintain low humidity using automatic control for at hast 10 continuous hours in a 31-day period is sufficient to reduce the buidup of moisture on the charcoal adsorbers and HEPA filters. The OPERABILiT% 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 rems or less whole body, or its equivalent. This limitation is consistent with the requirements of General Design Cnterion 19 of Appendix A, 10 CFR Part 50. ANSI N510-1975 and N510-1980 will be used as procedural guides for surveillance testing , Surveillance testing provides assurance that system and component performances continue to be in accordance with performance speci-fications for Wolf Creek Unit 1, including applicable parts of ANSI N509-1976.
3/4.7.7 EMERGENCY EXHAUST SYSTEM - AUXlLIARY BUILDING The OPERABILITY of the Emergency Exhaust System ensures that radioactive materials leaking from the ECCS equipment within the Auxiliary Building following a LOCA are f ttered prior to reaching the environme a n of tbe tem Oper_ati with the heaters operating to maintain low humidity us' utomaho4ontro for at least 10 continuous hours .i a 31-day period is su icient to re uce the buildup of moisture on the enarcoal adsorbers and HEPA filters. The opera-tion of this system and the resultant effect on offsite dosage calculations was assumed in the safety analyses. ANSI N510-1975 and N510-1980 will be used as procedural guides for surveillance testing The surveillance requirements associated with the HEPA filters, charcoal adsorbers and heaters are stated in 4.9.13.
WOLF CREEK - UNIT 1 B 3/4 7-4 Amendment No. 22 l
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t Attachment IV to NA 94-0015 Page 5 of 5 BASES 3/4.9.10 and 3/4 9.11 WATER LEVEL - REACTOR VESSEL and STORAGE POOL Ti 3 restrictions on minimum water level ensure that sufficient water depth is avtfable to remove 99% of the assumed 10% iodine gap actn/ity released from the rupture o' an irradiated fuel asumbly. The minimum water depth is consistent with the assumptions of the safety analysis.
3/4 9.12 SPENT FUEL ASSEMBLY STORAGE The restrictions placed on spent fuel assemblies stored in Region 2 of the spent fuel pool ensure inadvertent criticality will not occur.
3/4 9.13 EMERGENCY EXHAUST SYSTEM - FUEL BUILDING The limitations on the Emergency Exhaust 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.
.r in of tile system with the heaters operating to maintain low humidity hauto% tic fedtrb!Jfor at least 10 continuous hours in a 31-day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters.
The OPERABILITY of this system and the resulting iodine removal capacity are consistent with the assumptions of the safety analyses. ANSI N510-1975 and N510-1980 will be used as procedural guides for surveillance testing.
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WOLF CREEK - UNIT 1 B 3/4 9-3 Amendment No. 22
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