ML20205F751
| ML20205F751 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 03/24/1987 |
| From: | Jabbour K Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20205F755 | List: |
| References | |
| NUDOCS 8703310279 | |
| Download: ML20205F751 (9) | |
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= UNITED STATES i - 7 NUCLEAR REGULATORY COMMISSION o
WASHmGTON, D. C. 20555 I
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DUKE POWER COMPANY NORTH CAROLINA ELECTRIC MEMBERS 4IP CORPORATION SALUDA RIVER ELECTRIC COOPERATIVE, INC.
DOCKET NO. 50-413 CATAWBA NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 23 License No. NPF-35 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The' application for amendment to the Catawba Nuclear Station, Unit 1 (the facility) Facility Operating License No. NPF-35 filed by the Duke Power Company acting for itself, North Carolina Electric Membership Corporation and Saluda River Electric Cooperative, Inc.,- (licensees) dated April 9,1986, and supplemented February 13, 1987, comolies with the standards and requirements of the Atomic Energy Act of 1954, as.
amended (the Act) and the Commission's rules and regulations as set forth in 10 CFR Chapter I;
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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 set forth in 10 CFR Chapter I; l
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; E.
The issuance of this amenoment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
l-2.
Accordingly, the license is hereby amended by page changes to the Technical i
Specifications as indicated in the attachments to this license amendment and l
Paragraph 2.C.(2) of Facility Operating License No. NPF-35 is hereby amended to read as follows:
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,. (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 23, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. Duke Power Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This ifcense amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION p\\
Kahtan Jabbour, Project Manager PWR Project Directorate No. 4
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Division of PWR Licensing-A
Attachment:
Technical Specification Changes Date of Issuance: March 24, 1987 b
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UNITED STATES E'!
NUCLEAR REGULATORY COMMISSION n
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DUKE POWER COMPANY NORTH CAROLINA MUNICIPAL POWER AGENCY NO. 1 PIEDMONT MUNICIPAL POWER AGENCY DOCKET NO. 50-414 CATAWBA NUCLEAR STATION, UNIT 2 AMENDriENT TO FACILITY OPERATING LICENSE Amendment No. 13 License No. NPF-52 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The applicition for amendment to the Catawba Nuclear Station, Ur.it 2 (the facility) Facility Operating License No. NPF-52 filed by the Duke Power Company acting for itself, North Carolina Municipal Power Agency No. I and Piedmont Municipal Power Agency (licensees) dated April 9, 1986, and supplemented February 13, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the apolication, 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 conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I; 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; 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.
2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachments to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. NPF-52 is hereby amended to read as follows:
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. (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 13, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. Duke Power Company shall operate the-facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3..This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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Kahtan Jabbour, Project Manager PWR Project Directorate No. 4 Division of PWR Licensing-A
Attachment:
Technical Specification Changes Date of Issuance: March 24, 1987 M
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r ATTACHMENT TO LICENSE AMENDMENT NO. 23 FACILITY OPERATING LICENSE NO. NPF-35 DOCKET NO. 50-413 AND TO LICENSE AMENDMENT NO. 13 FACILITY OPERATING LICENSE NO. NPF-52 DOCKET NO. 50-414 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical ljnes indicating the areas of change. The corresponding overleaf pages are also provided to naintain document completeness.
Amended Overleaf Page Page 3/4 7-17 3/4 7-18
~B 3/4 7 4 B3/4 7-3 s
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PLANT SYSTEMS l=
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3/4.7.7 AUXILIARY BUILDING FILTERED EXHAUST SYSTEM i
LIMITING CONDITION FOR OPERATION 3.7.7 Two independent trains of the Auxiliary Building Filtered Exhaust System l
shall be OPERABLE.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
With one train of the Auxiliary Building Filtered Exhaust System inoperable, restore the inoperable train 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 RE0UIREMENTS 4.7.7 Each train of the Auxiliary Building Filtered Exhaust System shall be demonstrated OPERABLE:
a.
At least once per 31 days by initiating, frem the control room, fibw through the HEPA filters and charcoal adsorbers. and verifying that the system operates for at least 10 continuous hours with the heaters Q
operating;
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b.
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 same by:
1)
Verifying that the cleanup system satisfies the in place penetration and bypass leakage testing acceptance criteria of less than 1% (Unit 1), 0.05% (Unit 2) and uses the test proce-dure guidance in Regulatory Positions C.S.a C.5.c, and C.S.d*
of Regulatory Guide 1.52, Revision 2, March 1978, and the system-flow rate is 30,000 cfm i 10%;
2)
Verifying, within 31 days after removal, that a laboratory analysis of a representative carbon sample obtained in accor-dance 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, Revi-sion 2, March 1978, for a methyl iodide penetration of less than 1%; anu
- The requirement for reducing refrigerant concentration to 0.01 ppm may be satisfied by operating the system for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> with heaters on and operating.
CATAWBA - UNITS 1 & 2 3/4 7-17 Amendment No. 23 (Unit 1)
Amendment No. 13 (Unit 2)
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PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) t 3)
Verifying a system flow rate of 30,000 cfm i 10% during system operation when tested in accordani:e with ANSI H510-2980.
c.
After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of carbon 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 Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978, for a methyl iodide penetration of less than 1%;
d.
At.least once per 18 months by:
1)
Verifying that the pressure drop across the combined HEPA filters, charcoal adsorber banks, and moisture separators of less than B inches Water Gauge while operating the system at a flow rate of 30,000 cfm i 10%,
2)
Verifying that the system starts on a Safety Injection test signal, and directs its exhaust flow through the HEPA filters and charcoal adsorbers,"*
3)
Verifying that the system maintains the ECCS pump room at a T
negative pressure relative to adjacent areas, j
4)
Verifying that the filter cooling bypass valves can be manually opened, and 0,
5)
Verifying that the heaters dissipate 40 1 4 kW.
After each complete or partial replacement of a HEPA filter bank, e.
by verifying that the cleanup system satisfies the in place pene-tration and bypass leakage testing acceptance criteria of less than 1% (Unit 1), 0.05% (Unit 2) in accordance with ANSI N510-1980 for a DOP test aerosol while opera. ting the system at a flow rate of 30,000 cfm i 10%; and f.
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 acceptance criteria of less than 1% (Unit 1), 0.05% (Unit 2) in accordance with ANSI N510-1980 for a halogenated hydrocarbon refrigerant test gas while operating the system at a flow rate of 30,000 cfm i 10%.
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- This surveillance need not be performed until prior to entering HOT SHUTDOWN following the Unit 1 first refueling.
CATAWBA - UNITS 1 & 2 3/4 7-18
PLANT SYSTEMS BASES 3/4.7.3 COMPONENT COOLING WATER SYSTEM.
The OPERABILITY of the Component Cooling Water System ensures that suf-ficient-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.
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3/4.7.4 NUCLEAR SERVICE WATER SYSTEM The OPERABILITY of the Nuclear Service Water System ensures that sufficient -
cooling capacity is available for continued operation of safety-related equip-ment 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 analysis.
3/4.7.5 STANDBY NUCLEAR SERVICE WATER POND-The limitations on the standby nuclear service water pond level and temperature ensure that sufficient cooling capacity is available to either:
(1) provide normal cooldown of the facility, or (2) mitigate the effects of
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accident conditions within acceptable limits.
The limitations on minimum water level and maximum temperature are bcsed on providing a 30-day cooling water supply to safety-related equipment without
,2 exceeding its design basis temperature and is consistent with the recommend-g i
ations of Regulatory Guide 1.27, " Ultimate Heat Sink for Nuclear Plants,"
March 1974.
3/4.7.6 CONTROL ROOM AREA VENTILATION SYSTEM The OPERABILITY of the Control Room Area 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 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 con-sistent with the requirements of General Design Criterion 19 of Appendix A, 10 CFR Part 50. ANSI N510-1980 will be used as a procedural guide for surveil-lance testing.
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1! ANT -SYSTEMS j
ti BASES 3/4.7.7 AUXILIARY BUILDING FILTERED EXHAUST SYSTEM The OPERABILITY of the Auxiliary Building Filtered Exhaust System ensures that radioactive 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 using automatic control for at least 10 continuous hours in a 31-day period is sufficient to reduce the buildup of moisture on the ads;rbers and HEPA filters.
The operation of this system and the resultant effect on offsite dosage calcu-lations was not taken credit for in the safety analyses.
However, the operation of this system and the resultant effect on the NRC staff's offsite dose.calcula-tions was assumed in the staff's SER, NUREG-0954.
ANSI N510-1980 will be used as a procedural guide for surveillance testing.
3/4.7.8 SNUBBERS r
. All snubbers are required OPERABLE to ensure that the structural integrity of the Reactor Coolant System and all other safety-related systems is main-tained during and following a seismic or other event initiating dynamic loads.
Snubbers are classified and grouped by design and manufacturer but not.by size. For example, mechanical snubbers utilizing the same design features of the 2-kip, 10-kip, and 100-kip capacity manufactured by Company "A" are of the i same type. The same design mechanical snubbers manufactured by Company "B"
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for the purposes of this Technical Specification would be of a different type, l
as would hydraulic snubbers from either manufacturer.
A list of individual snubbers with detailed information of snubber locatio'n and size and of system affected shall be available at the plant in accordance i
with Section 50.71(c) of 10 CFR Part 50.
The accessibility of each snubber shall be determined and approved by the Catawba Safety Review Group.
The determination shall be based upon the existing radiation levels and the expected time to per-form a visual inspection in each snubber location as well as other factors asso-ciated with accessibility during plant operations (e.g., temperature, atmosphere, location etc.), and the recommendations of Regulatory Guides 8.8 and 8.10.
The addition or deletions of any hydraulic or mechanical snubber shall be made in accordance with Section 50.59 of 10 CFR Part 50.
CATAWBA - UNITS 1 & 2 B 3/4 7-4 Amendment No. 23 (Unit 1)
Amendment No.13 (Unit 2)