ML20196E295
| ML20196E295 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 12/05/1988 |
| From: | Calvo J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20196E299 | List: |
| References | |
| NUDOCS 8812090309 | |
| Download: ML20196E295 (13) | |
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UNITED STATES
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g NUCLEAR REGULATORY COMMISSION j
W ASHINGTON, D. C. 20655 Fe k.....,/
KANSAS GAS & ELECTRIC C0ftPANY KANSAS CITY POWER AND LIGHT COMPANY KANSAS ELECTRIC POWER COOPERATIVE. INC.
WOLF CREEK GENERATING STATION DOCKET NO. 50-482 Af1ENDMENT TO FACILITY OPERATING LICENSE Amendment No. 22 License flo. NPF-42 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the Wolf Creek Generating Station (the f acility) Facility Operating License No. NPF-42 filed by the Wolf Creek Nuclear Operating Corporation. dated February 26, 1988 and as supplemented on October 31, 1988 complies with the standards and requirements of the Atcmic Energy Act of 1954, as amended (the Act), and the Comission'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 Comission; C.
There is reasonable assurance:
(i)thattheactivitiesauthorized 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 Cumission's regulations; D.
The issuance of this license amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
"he issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
G812090309 891205 PDR ADOCK 050004S2 P
2.
Accordingly, the license is amended by changes to the Technical Specifi-cations 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. 22, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated in the license. The Operating Corporation shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
m 3.
The license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION (i,
[< C'W Jose A. Calvo, Director Project Directorate - IV Division of Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: December 5,1988
ATTACHMENT TO LICENSE AMENDMENT NO. 22 FACILITY OPERATING LICENSE NO. NPF-42 DOCKET NO. 50-482 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by amendment number and contain marginal lines indicating the area of change.
The corresponding overleaf pages are also provided to maintain document completeness.
i REMOVE PAGES INSERT PAGES 3/4 7-15 3/4 7-15 3/4 7-16 3/4 7-16 3/4 7-17 3/4 7-17 3/4 7-18 3/4 7-18 3/4 9-17 3/4 9-17 3/4 9-18 3/4 9-18 4
3/4 9-18a B 3/4 7-4 8 3/4 7-4 j
B 3/4 9-3 8 3/4 9-3 l
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PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) c.
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:
1)
Verifying that the Control Room Emergency Ventilation System satisfies the in place penetration and bypass leakage testing acceptance criteria; of less than 1% for HEPA filters and 0.05%
for charcoal adsorbers and uses the test procedure guidance in Regulatory Positiont C.5.a. C.S.c. and C.5.d of Regulatory Guide 1.52, Revision 2, March 1978, and the system flow rate is 2000 cfm 110% for the Filtration System and 2200 cfm 110% for the Pressurization System with 750 cfm 110% going through the Pressurization System filter adsorber unit; I
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, for a methyl iodide penetration of less than 1%; and 3)
Verifying system flow rate of 2000 cfm t10% at greater than or equal to 6.6 inches W.G. (dirty filter) for the Filtration System and 2200 cfm 110% at greater than or equal to 3.6 l
inches W.G. (dirty filter) for the Pressurization System with 750 cfm 110% going through the Pressurization System filter l
adsorber unit during system operation when tested in accordance with ANSI N510-1980.
d.
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 verifying within 31 days after removal, that a laboratory analysis of a represen-tative 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, for a methyl iodide penetration of less than 1%;
e.
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 6.6 inches Water Gauge while operating the system at a flow rate of 2000 cfm 110% for the Filtration System and less than 3.6 inches Water Gauge while operating the system at a flow rate of 750 cfm 110%
for the Pressurization System filter adsorber unit, 2)
Verifying that on a Control Room Ventilation Isolation or High Gaseous Radioactivity test signal, the system automatically switches into a recirculation mode of operation with flow through the HEPA filters and charcoal adsorber banks,
)
WOLF CREEK - UNIT 1 3/4 7-15 Amendment No. 22
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 3)
Verifyir that the system maintains the control room at a positiv. pressure of greater than or equal to 1/4 inch Water Gauge relative to the outside atmosphere during system operation, 4)
Verifying that the Pressurization System filter adsorber unit heaters dissipate 15 i 2 kW in the Pressurization System when tested in accordance with ANSI N510-1975, and 5)
Verifying that on a High Chlorine test signal, the system auto-matica11y switches into a recirculation mode of operation with flow through the HEPA filters and charcoal adsorber banks within 15 seconds.
f.
After each complete or partial replacement of a HEPA filter bank, by verifying that the cleanup system satisfies the in place penetration and bypass leakage testing criteria of less than 1% in accordance with ANSI N510-1975 (however Pterequisite Testing, Sections 8 and 9 shall be in accordance with ANSI N510-1980) for a DOP test aerosol while operating the system at a flow rate of 2000 cfm 110% for the Filtra-tion System and 750 cfm 110% for the Pressurization System filter l
adsorber unit; and g.
After each complete or partial replacement of a charcoal adsorber bank, by verifying that the cleanup system satisfies the in place penetration and bypass leakage testing criteria of less than 0.05% in accordance with ANSI N510-1975 (however Prerequisite Testing, Sections 8 and 9 shall be in accordance with ANSI N510-1980) for a halogenated hydrocarbon refrigerant test gas while operating the system at a flow rate of 2000 cfm 110% for the Filtration System' and 750 cfm *10% for the Pressurization System filter adsorber unit.
l WOLF CREEK - UNIT 1 3/4 7-16 Amendment No. 22
PLANT SYSTEMS 3/4.7.7 EMERGENCY EXHAUST SYSTEM - AUXILIARY BUILDING l
LIMITING CONDITION FOR OPERATION 3.7.7 Two independent Emergency Exhaust Systems shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTION:
With one Emergency Exhaust System inoperable, restore the inoperable Emergency Exhaust System 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 COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.7.7 Each Emergency Exhaust System shall be demonstrated OPERABLE:
By performing surveillance requirements 4.9.13.a through 4.9.13.f.
a.
- and, b.
At least once per 18 months by:
1)
Verifying that the system maintains the Auxiliary Building at a negative pressure of greater than or equal to % inch Water Gauge relative to the outside atmosphere during system operation, 2)
Verifying that the system starts on a Safety Injection test
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i WOLF CREEK - UNIT 1 3/4 7-17 Amendment No. 22 Next text on page 3/4 7-19
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WOLF CREEK - UNIT 1 3/4 7-18 Amendment No. 22
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REFUELING OPERATIONS 3/4.9.13 EMERGENCY EXHAUST SYSTEM - FUEL BUILDING LIMITING CONDITION FOR OPERATION 3.9.13 Two independent Emergency Exhaust Systems shall be OPERABLE.
APPLICABILITY: Whenever irradiated fuel is in the spent fuel pool.
ACTION:
a.
With one Emergency Exhaust System inoperable, fuel movement within the fuel storage areas or crane operation with loads over the fuel storage areas may proceed provided the OPERABLE Emergency Exhaust System is in operation and discharging through at least one train of HEPA filters and charcoal adsorbers.
b.
With no Emergency Exnaust System OPERABLE suspend all operations involvingmovementoffuelwithinthefuelstorageareasorcrane operation with loads over the fuel storage areas until at least one Emergency Exhaust System is restored to OPERABLE status.
c.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.9.13 The above required Emergency Exhaust Systems shall be demonstrated OPERABLE:
a.
At least once per 31 days on a STAGGERED TEST BASIS by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the system operates for at least 10 continuous hours with the heaters operating; b.
At least once per 18 months, or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housingsorchemica!.eleaseinan or painting, fire,ith the system, by:
zone communicating w 1)
Verifying that the Emergency Exhaust System satisfies the in place penetration and by) ass leakage testing % for charcoal adsorbers and acceptance criteria of less than 1% for HEPA filters and 0.05 uses the test procedure guidance in Regulatory Positions C.5.a.
C.S.c, and C.5.d of Regulatory Guide 1.52, Revision 2, March 1978, and the system flow rate is 6500 cfm 110%.
l WOLF CREEK - UNIT 1 3/4 9-17 Amendment No.22
RETSELING OPERATIONS SURVEILLANCE REQUIREMENTS (Continued) 2)
Verifying, within 31 days after removal, that a laboratory analy-sis of a resresentative carbon sample obtained in accordance with Regulatory )osition C.6.b of Regulatory Guide 1.52, Revision 2, March 1978,6.a of Regulatory Guide 1.52, Revisison 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.
for a methyl iodide penetration of less than 1%; and 3)
Verif ing a system flow rate of 6500 cfm *Wi ot > 4.7 inches l
W.G. y(dirty filter) during system operatien wher. Yested in accordance with ANSI N510-1980.
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 verifying, c.
within 31 days after removal that a laboratory anal sis of a repre-sentativecarbonsampleobtaInedinaccordancewith egulatory Posi-I tion C.6.b of Regulatory Guide 1.52 Revision 2 March 1978, meets the
(
laboratorytestingcriteriaofRegulatoryPositIonC.6.aofRegulatory Guide 1.52 Revision 2, March 1978, for a methyl iodide penetration of lessthan1%;
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 4.7 inches kater Gauge while operating the system at a flow rate of 6500 cfm 110%.
2)
Verifying that the heaters dissipate 37 3 kW when tested in accordance with ANSI N510-1975.
After each complete or partial replacement of a HEPA filter bank, ion e.
by verifying that the cleanup system satisfies the in place penetrat I
and bypass leakage testing acceptance criteria of less than 1%
in accordance with ANSI N510-1975 (however Prerequisite Testing, Sections 8 and 9 shall be in accordance with ANSI N510-1980) for a 00P test aerosol while operating the system at a flow rate of 6500 cfm 110%; and
[
f.
After each com lete or partial replacement of a charcoal adsorber bank, by verif ing that the cleanup system satisfies the in place penetration an bypass leakage testing acceptance criteria of less than 0.05% in accordance with ANSI H510-1975 (however Prerequisite l
Testing, Sections 8 and 9 shall be in accordance with ANSI H510-1980) for a halogenated hydrocarbon refrigerant test gas while operating the system at a flow rate of 6500 cfm 110%.
g.
At least once per 18 months by:
1)
Verifying that on a Fuel Building Exhaust Gaseous Radioactivity-High test signal the system automatically starts (unless already operating)anddIrectsitsexhaustflowthroughtheHEPAfilters and charcoal adsorber banks and isolates the normal fuel building exhaust flow to the auxiliary / fuel building exhaust fan; WOLF CREEK - UNIT 1 3/4 9-18 Amendment Nn. 22 1
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REFUELING OPERATIONS SURVEILLANCE REQUIREMENTS (Continued) 2)
Verifying that the system maintains the Fuel Building at a nega-tive pressure of greater than or equal to 1/4 inches Water Gauge relative to the outside atmosphere during system operation.
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WOLF CREEK - UNIT 1 3/4 9-18a Amendment No. 22 I
l PLANT SYSTEMS BASES 3/4.7.1.5 MAIN STEAM LINE ISOLATION VALVES The OPERABILITY of the main steam line isolation valves ensarts that no more than one steam generator will blowdown in the event of a steam line rupture.
This restriction is required to: (1) minimize the positive reactivity effects of the Reactor Coolant System cooldown associated with the blowdown, and (2) limit the pressure rise within containment in the event the steam line rupture occurs within containment. The OPERABILITY of the main steam isolation valves within the closure times of the Surveillance Requiremehts are consistent with the assumptions used in the safety analyses.
3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION The limitation on steam generator pressure and temperature ensures that the pressure-induced stresses in the stsam generators do not exceed the maxit,tum allowable fracture toughness stress limits.
The limitations of 70'F and 200 psig are based on a steam generator RT of 60'F and are sufficient NDT to prevent brittle fracture.
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3/4.7.3 COMPONENT COOLING WATER SYSTEM 9
The OPERABILITY of the Component Cooling Water System ensures that sufficient cooling capacity is available for continued operation of safety-related equipment during normal and accident conditions.
The redundant cooling capacity of this system, assuming a single failure, is consistent with the assumptions used in the safety analyses.
Each independent CCW loop contains two 100% capacity pumps and, therefore, the failure of one pump does not affect the OPERABILITY of that loop.
3/4.7.4 ESSENT.'AL SERVICE WATER SYSTEM The OPERABli.ITY of the Essential Service Water System ensures that sufficient cooling capacity is available for continued operation of safety-related equipment during normal and accident conditions.
The redundant cooling capacity of this aystem, assuminq a single failure, is consistent with the assumptions used in the safety analysis.
3/4.7.5 ULTIMATE HEAT $1NK The limitations on the ultimate heat sink level and temperature ensure that sufficient cooling capacity is available either to: (1) provide normal cooldown of the facility or (2) mitigate the effects of accident condition; within acceptable limits.
WOLF CREEK - UNIT 1 B 3/4 7-3
PLANT 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)theambientairtemperaturedoesnotexceedtheallowabletemperature for continuous-dut this system, and (y) the control room will remain habitable for orating for the equipment an
~
2 personnel during and following all credible accident conditions. perations 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 Design Criterion 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,
l fications for Wolf Creek Unit 1, including applicable parts of ANSI N509-1976.
3/4.7.7 EMERGENCY EXHAUST SYSTEM - AUXILIARY BUILDING l
The OPERABILITY of the Emergency Exhaut,t System cnsures that radioactive materials leaking from the ECCS equipment within the Auxiliary Building following l
a LOCA tre filtered prior to reaching the environment.
Operation of the system l
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 chdtcoal adsorbers and HEPA filters.
The opeia-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.
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WOLF CREEK - UNIT 1 B 3/4 7-4 Amendment No. 22 1
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BASES 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.
1 3/4.9.12 SPENT FUEL ASSFMBLY 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 dircharge to the atmosphere.
Operation of the system with the heaters operating to maintain low humidity with automatic control for at least 10 continucus cours 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 gut ies for surveillance testing.
WOLF CREEK - UNIT 1 B 3/4 9-3 Amendment No. 22