ML20043H780
| ML20043H780 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 06/14/1990 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20043H781 | List: |
| References | |
| NUDOCS 9006260437 | |
| Download: ML20043H780 (8) | |
Text
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UNITED ST ATES
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DUKE POWER COMPANY NORTH CAROLINA ELECTRIC MEMBERSillP CORPORATION I
SALUDA RIVER' ELECTRIC CDOPERATIVE; INC.
DOCKET NO. 50-413 CATAWBA NUCLEAR STATION, UNIT 1 l
AMENDMENT TO FACILITY OPERATING LICENSE l
Amendment No. 75-License No. NPF-35 t
1.
The Nuclear Regulatory Consission '(the Consission) 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.,
l (licensees) dated April 23, 1990, as supplenented May 17 and June 4,.
1990, complies with the standards and requirenents of the Atomic Energy Act of 1954, as amended (the Act), and the Commission'st rules and regulations us set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Connission; i
C.
Thereisreasonableassurance(1)thatthea'ctivitiesauthorizedby this anendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Consuission's regulations set forth in 10 CFR Chapter I; D.
The issuunce of this 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 Comission's regulations and all applicable requirements have been satisfied.
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2.
Accordingly, the -license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment,.
l and Paragraph 2.C.(2) of Facility Operating License No. NPF-35 is hereby.
amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A, as revised-through 75 are hereby incorporated-into the license. Thi iicensee-i Amendment No.
shalloperatethefacility.in.accordancewiththeTechnicalSpecifications and the Environmental-Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION-
.) i %L David B. Matthews, Director Project Directorate'll-3 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation +
Attachment:
Technical Specification Changes Date of Issuance: June 14, 1990 I O t t k n <a e e -~,os-m
.~ -) a . [ gpOQiCp/I4 UNITED sT ATEs ' ^' ? k." ', d</ [f NUCLEAR REGULATORY COMMISSION-r WASWNOTON,0 C. 206% -] k. / ...+ l-DUKE POWER COMPANY ] l l NORTH CAROLIhA huHICIPAL POWER AGENCY N0. l' l PIEDMONT MUNICIPAL POWER AGENCY DOCKET NO. 50-414 i CATAWBA NUCLEAR STATION, UNIT ? AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 69 License No. NPF-52 1. The Nuclear Regulatory Connission (the Connission)'has found that: A. The application for amendment to the Catawba Nucleer Station, Unit 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) datedt April 23, 1990, as supplemented May 17 and June 4,1990, complies 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; B. The facility will operate in conformity with.the application, 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 anendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in con.pliance with the Connission's regulations set forth in 10 CFR Chapter I; D. The issuance of this emendment 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 Consnission's regulations and all applicable requirements have l been satisfied.
.?.
- 2.. Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to.this license amendment, and Faragraph F.C.(2) of Facility Operating License No. NPF-52 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A, as revised through. Amendeent No. 69 . are hereby incorporated.into the license. The licensee shall operate the facility in accordance with the Technical Specifications-and the Environmental Protection Plan. 3. This license anendment-is effective as of its date of issuance. FOR THE NUCLEAR REGULATORY COMMISSION e n /I q.f. David D. P.atthews, Director Project Directorate 11-3 Division of Reactor Projects-1/11 Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of issuance: June 14, 1990 }
j ATTACHMEleT TO LICENSE AMENDMENT NO. 75 FACILITY OPERATING L10ENSE NO. NPF-35" DOCKET NO. 50-413 a TO LICENSE AMEN 0 MENT NO. so 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 identifico by Amendraent number duc contain vertical lines indicating the areas of change. Reniove Pages Insert Pages 3/4 9-15 3/4 9-15 3/4 9-16 B 3/4 9-3 8 3/4 9-3 -i l' ~. . - - ~..
4,- s-w- --e a .a REFUELING OPERATIONS j i SURVEILLANCE REQUIREMENTS (Continued) 2) Verifying, within 31 days after removal, that a laboratory analysis of a representative activated carbon sample obtained~ in accordance with Re Guide 1.52, Revision hulatory Positions C.6.b of Regulatory , March 1978, meets the laboratory testing criteria of Regulatory Position C 6.a of Regulatory Guide 1.52, Revision 2 Method "A"4, March 1978, as supplemented by ASTM D3803-86, Testfo and i 3) Verifying a system flow rate of 16,565 cfm i 10% during system operation when tested in accordance with ANSI N510-1980. i c. After every 720 hours of activated carbon adsorber operation in any train by verifying, within 31 days after removal, that a laboratory analysis of a representative activated carbon sample obtained in-4 accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, i Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision'2, March 1978, as supplemented by ASTM D3803-86, Test Method "A"*, for a methyl iodide penetration of less than 0.71% d. At least once per 18 months for each train by: i 1) Verifying that the pressure drop across the combined HEPA filters, activated carbon adsorber banks, and moisture separators is less than 8 inches Water Gauge while. operating the system at a flow-rate of 16,565 cfm i 10%. 2) Verifying that the system maintains the spent fuel storage pool area at a negative pressure of greater than or equal to 4 inch l Water Gauge relative to the outside amosphere during system operation, i 3) Verifying that the filter cooling bypass valves can be manually. opened, and 4) Verifying that the heaters dissipate 80 + 8 kW/-17.3 kW.** l l
- Use of ASTM D3803-86, Test Method "A" as a supplement applies until August 26, 1991.
Thereafter, the surveillance requirement shall read, "... meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978, for a methyl iodide j penetration of less than 1%." l l
- 80 + 8 kW/-17.3 kW applies until August 26, 1991.
Thereafter, the j surveillance requirement shall read " Verifying that the heaters dissipate j 80 1 8 kW." - CATAWBA - UNITS 1 & 2 3/4 9-15 Amendment No. 75 (Unit 1) i - Amendment No. 69 (Unit 2) l ,.-~
. REFUELING OPERATIONS / SURVEILLANCE REQUIREMENTS (Continued) e. After each complete or partial replacement of a HEPA filter bank in' any train, 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 DOP test aerosol while operating the system at a: flow rate of 16,565 cfm i 10%; and. f. After each complete or partial replacement of an activated carbon adsorber bank in any train, by verifying that the cleanup system: satisfies the in-place penetration and bypass leakaga testing accept-ance 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 16,565 cfni i 10%. CATAWBA - UNITS 1 & 2 3/4 9-16 Amendment No. 75 (Unit-1) Amendment No. 69 (Unit 2)
RE' FUELING OPERATIONS BASES 3/4.9.9 and 3/4.9.10 WATER LEVEL - REAC10R 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. 3/4.9.11 FUEL HANDLING VENTILATION EXHAUST SYSTEM The limitations on the Fuel Handling Ventilation Exhaust System ensure that all radioactive material released from.an irradiated fuel assembly will be filtered through the HEPA filters and activated carbon adsorber prior to discharge to the atmosphere. Operation of the system with the heaters operat-ing 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.and the result-ing iodine removal capacity are consistent with the assumptions of.the safety. analyses. ANSI N510-1980 will be,used as a procedural guide for surveillance testing. ASTM D3803-86, Test Method "A" will be used for surveillance testing (laboratory test) for methyl iodide penetration in lieu of the laboratory test specified in Regulatory Guide 1.52, Rev. 2, March 1978, Regulatory Position C,6.a. The ASTM D3803-86 test method uses a' relative humidity of 95% at 30 C. The use of this test and the acceptance criterion of a methyl iodide penetration of less than 0.71% are. consistent with assumed decontamination efficiencies of 95%, This change resulted from the lower system heater-capacity during degraded voltage conditions. The use of ASTM D3803-86 will apply until August 26, 1991. This date corresponds to the next-due date'for the 18-month surveillance on Unit 2. The Unit 2 date is used for both units because the next 18 month inspection date for Unit 1, December 13,-1990, will not allow for sufficient time to evaluate ASTM D3803-89. 4 CATAWBA - UNITS 1 & 2 B 3/4 9-3 Amendment No. 75 (Unit 1) i Amendment No. 69 (Unit 2) _}}