ML20095K381
| ML20095K381 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 12/20/1995 |
| From: | Thomas K NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20095K383 | List: |
| References | |
| NUDOCS 9512280307 | |
| Download: ML20095K381 (6) | |
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UNITED STATES p
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NUCLEAR REGULATORY COMMISSION WASHINGTON D.C. 3000H001 i
UNION ELECTRIC CONPANY i
CALLAWAY PLANT. UNIT NO. 1 i
DOCKET NO. 50-483 ANENDNENT TO FACILITY OPERATING LICENSE i
I Amendment No.106 License No. NPF-30 l
1.
The Nuclear Regulat'ory Comission (the Comission) has found that:
f A.
The application for amendment to the Callaway Plant, Unit 1 (the j
facility) Facility Operating License No. NPF-30 filed by the Union Electric Company (the licensee), dated April 26, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; l
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:
(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 l
conducted in compliance with the Comission's regulations; D.,
The issuance of this license amendment will not be inimical to the i
comon defense and security or to the health and safety of the i
public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have l
been satisfied.
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9512280307 951220 PDR ADOCK 05000403 p
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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-30 is hereby amended to read as follows:
2.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.106, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated in the license. UE shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
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3.
The license amendment is effective as of its date of issuance to be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Me MTMm Kristine M. Thomas, Project Manager Project Directorate IV-2 i
Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation i
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 20, 1995 l
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ATTACHMENT TO LICENSE AMENDMENT NO.106 FACILITY OPERATING LICENSE NO. NPF-30 DOCKET NO. 50-483 Replace the following pages of the Appendix A Technical Specifications with l
the attached pages. The revised pages are identified by Amendment number and contain marginal lines indicating the areas of change.
BEMYf 111121 3/4 7-15 3/4 7-15 3/4 7-16 3/4 7-16 B 3/4 7-4 8 3/4 7-4 i
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PLANT SYSTEMS i
SURVEILLANCE REQUIREMENTS (Continued) i J
c.
At least once per 18 months, or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following i
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 j
acceptance criteria of less than 1% and uses the test procedure guidance in Regulatory Positions C.5.a. C.5.c, and C.5.d of Regulatory Guide 1.52, Revision 2, March 1978, and the system flow rate is 2000 cfm [ $ for the Filtration System and I
$forthePressurizationSystemwith500cfm h0 2200 cfm 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 i
accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of ASTM D-3803-1989 when tested at 30*L and 70%
relative humidity for a methyl iodide penetration of less than j
2%; and 3)
Verifying a system flow rate of 2000 cfm
$forthe l
Filtration System and 2200 cfm hforthePressurization Systemwith500cfm[h0 going through the Pressurization l
System filter adsorber unit during system operation when tested in accordance with ANSI N510-1975.
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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 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 ASTM D-3803-1989 when tested at 30*C and 70% relative humidity for a methyl iodide penetration of less than 2%;
e.
At least once per 18 months by:
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Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is less than 5.4 inches Water Gauge while operating the system at a flow rate of 2000cfm[
for the Filtration System and 500 cfm h0 l
for the Pressurization System filter adsorber unit; CALLAWAY - UNIT 1 3/4 7-15 Amendment No. 47,106
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PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 3 i
2)
Verifying that on a Control Room Ventilation Isolation or High j
Gaseous Radioactivity test signal, the system automatically switches into a recirculation mode of operation with flow through the HEPA filters and charcoal adsorber banks; 3)
Verifying that the system maintains the control room at a positive pressure of greater than or equal to 1/8 inch Water i
Gauge relative to the outside atmosphere during system operation; and i
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.
f.
After each complete or partial replacement of a HEPA filter bank, by j
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 for a DOP test aerosol while operating the system at a flow rate of 2000 cfm [
for the Filtration System h0 for the Pressurization System filter adsorber and 500 cfm unit; and g.
After ench 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 1% in accordance with ANSI N510-1975 for a halogenated hydrocarbon refrigerant test gas while operating the system at a flow rate of f
2000cfm[
fortheFiltrationSystemand500cfm[h0 for the Pressurization System filter adsorber unit.
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CALLAWAY - UNIT 1 3/4 7-16 Amendment No. U,106 i
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PLANT SYSTEMS BASES ULTIMATE HEAT SINK (Continued) l The limitations on minimum water level and maximum temperature are based on providing a 30-day cooling water supply to safety-related equipment without exceeding its design basis temperature and are consistent with the recommendations of Regulatory Guide 1.27, " Ultimate Heat Sink for Nuclear Plants," March 1974.
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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 i
temperature for continuous-duty rating for the equipment and instrumentation cooled by this system, and (2) the control room will remain habitable for i
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 i
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 will be used as a procedural guide for in-place surveillance testing. ASTM D-3803-1989 will be used as a procedural guide for the laboratory testing of carbon samples.
l 3/4.7.7 EMERGENCY EXHAUST SYSTEM i
The OPERABILITY of the Emergency Exhaust System assures that radioactive materials leaking from the ECCS equipment within the pump room following a LOCA are filtered prior to reaching the environment. Operation of the system with the heaters operating to maintain low humidity using automatic control i
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 operation of this system and the resultant effect on offsite dosage calculations was assumed in the safety analyses. ANSI N510-1975 will be used as a procedural guide for surveillance testing.
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CALLAWAY - UNIT 1 B 3/4 7-4 Amendment No. 106
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