ML20072G091
| ML20072G091 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 08/16/1994 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20072G094 | List: |
| References | |
| NUDOCS 9408240194 | |
| Download: ML20072G091 (10) | |
Text
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NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D.C. 20555 4001 WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION DOCKET NO. 50-482 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 77 License No. NPF-42 1.
The Nuclear Regulatory Commis,sion (the Commission) has found that:
A.
The application for amendment to the Wolf Creek Generating Station (the facility) Facility Operating License No. NPF-42 filed by the Wolf Creek Nuclear Operating Corporation (the Corporation), dated February 24, 1994, 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, as amended, the provisions of the Act, and the rules and regulations of the Commission; 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 Commission's regulations; D.
The issuance of this license 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 Commission's regulations and all applicable requirements have been satisfied.
9408240194 940816 PDR ADOCK 05000482 P
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.(2) of Facility Operating License No. NPF-42 is hereby amended to read as follows:
2.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 77, and the Environmental Protection Plan contained in Appendix B,-both of which are attached hereto, are hereby incorporated in the license. The Corporation shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3, The license amendment is effective as of its date of issuance and shall be implemented within 30 days of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION uN Theodore R. Quay, Director Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: August 16, 1994
i ATTACHMENT TO LICENSE AMEN 0 MENT NO. 77 FACILITY OPERATING LICENSE N0. NPF-42 DOCKET NO. 50-482 Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain marginal lines indicating the areas of change. The corresponding overleaf pages are also provided to maintain document completeness.
REMOVE INSERT 3/4 7-4 3/4 7-4 3/4 7-5 3/4 7-5 B 3/4 7-4 8 3/4 7-4 8 3/4 9-3 B 3/4 9-3
I
\\
l TABLE 3.7-2 STEAM LINE SAFETY VALVES PER LOOP VALVE NUMBER LIFT SETTING * (13%)** ORIFICE SIZE l
Loon 1 Loon 2 Loon 3 Loon 4 V055 V065 V075 V045 1185 psig 16.0 sq. in.
V056 V066 V076 V046 1197 psig 16.0 sq. in.
V057 V067 V077 V047 1210 psig 16.0 sq. in.
V058 V068 V078 V048 1222 psig 16.0 sq. in.
V059 V069 V079 V049 1234 psig 16.0 sq. in.
~
i i
- The lift setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.
- After testing, the valves will be left at 11%.
WOLF CREEK - UNIT 1 3/4 7-3 Amendment No. 61
__ _ _ _ _ __ __j
PLANT SYSTEMS AUXILLARY 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-drilen 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.
SURVElllANCE REQUIREMENTS 4.7.1.2.1 Each auxiliary feedwater pump shall be demonstrated OPERABLE:
a.
At least once per quarter on a STAGGERED TEST BASIS by:
l 1)
Verifying that each motor-driven pump develops a discharge pressure of greater than or equal to 1535 psig on recirculation l
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.c.4 are not applicable for entry into MODE 3;
WOLF CREEK - UNIT 1 3/4 7-4 Amendment No. 77
PLANT SYSTEMS SURVElllANCE REQUIREMENTS (Continued) b.
At least once per 31 days by:
l 4
1)
Verifying that each non-automatic valve in the flow path that l
is not locked, sealed, or otherwise secured in position is in j
i its correct position; and 2)
Verifying that each automatic valve in the flow path is in the l
fully open position whenever the Auxiliary Feedwater System is placed in automatic control or when above 10% RATED THERMAL POWER.
c.
At least once per 18 months during shutdown by:
l 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)
Verifying that each auxiliary feedwater pump starts as designed automatically upon receipt of an Auxiliary Feedwater Actuation test signal, and 3)
Verifying that each auxiliary feedwater motor-operated discharge valve limits the flow to each steam generator from the motor-driven pump to less than or equal to 320 gpm.
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 verifying normal flow to at least two steam generators from one auxiliary feedwater pump, WOLF CREEK - UNIT 1 3/4 7-5 Amendment No. 77
PLANT SYSTEMS CONDENSATE STORAGE TANK LIMITING CONDITION FOR OPERATION 3.7.1.3 The condensate storage tank (CST) shall be OPERABLE with a contained water volume of at least 281,000 gallons.
APPLICABILITY:
MODES 1, 2, and 3.
ACTION:
With the CST inoperable, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either:
a.
Restore the CST to OPERABLE status 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 />, or b.
Demonstrate the OPERABILITY of the Essential Service Water (ESW) Sys-tem as a backup supply to the auxiliary feedwater pumps and restore the CST to OPERABLE status within 7 days 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 />.
SURVEILLANCE REQUIREMENTS 4.7.1.3.1 The CST shall be demonstrated OPERABLE at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying the contained water volume is within its limits when the tank is the supply source for the auxiliary feedwater pumps.
4.7.1.3.2 The ESW System shall be demonstrated OPERABLE at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the ESW System is in operation whenever the ESW System is the supply source for the auxiliary feedwater pumps.
WOLF CREEK - UNIT 1 3/4 7-6
i ELANT SYSTEMS BASES ULTIMATE 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.
3/4.7.6 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 with the heaters operating to maintain low humidity using automatic control for at least 10 continuous hours in a 31-day ~ period is sufficient to reduce the buildup of moisture on the charcoal adsorbers and HEPA filters. 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 rems or less whole body, or its equivalent.
This limitation is consistent with the requirements of General Desige Criterion 19 of Appendix A, 10 CFR Part 50.
ANSI N510-1975 and N510-i980 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 specifications for Wolf Creek Unit 1, including applicable parts of ANSI N509-1976.
When determining compliance with action statement requirements, addition to the RCS of borated water with a concentration greater than or equal to the minimum required RWST concentration shall not be considered to-be a positive reactivity change.
3/4.7.7 EMERGENCY EXHAUST SYSTEM - AUXILIARY BUILDING The OPERABILITY of the Emergency Exhaust System ensures that radioactive l
materials leaking from the ECCS equipment within the Auxiliary Building following a LOCA are filtered prior to reaching the environment. Operation of the system with the heaters operating to maintain low humidity for at least 10 l
continuous hours in a 31-day period is sufficient to reduce the buildup of moisture on the charcoal adsorbers and HEPA filters. The operation of this system and the resultant effect on offsite dosage calculations was assumed in j
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. BB,77
REFUELING OPERATIONS BASES 3/4.9.9 CONTAINMENT VENTILATION SYSTEM The OPERABILITY of this system ensures that the containment 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 WATER LEVEL - REACTOR VESSEL and STORAGE POOL 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 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.
Operation of the system with the heaters operating to maintain low humidity for at least 10 continuous hours in a 31-day period is l
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.
WOLF CREEK - UNIT 1 B 3/4 9-3 Amendment No. 22,77