ML20245C893
| ML20245C893 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 04/21/1989 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20245C895 | List: |
| References | |
| NUDOCS 8904280009 | |
| Download: ML20245C893 (9) | |
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' n NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20656
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DUKE POWER COMPANY NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION SALUDA RIVER ELECTRIC COOPERATIVE, INC.
DOCKET NO. 50-413 CATAWBA NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 62 License No. NPF-35 1.
The Nuclear Regulatory Commission (the Comissi
- 1 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 October 5, 1988, as supplemented December 30, 1988, and January 27, 1989, 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 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 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; D.
The issuance 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 Commission's regulations and all applicable requirements have been satisfied.
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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-35 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 62, 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 amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Ka L J. JaSL ~ /,
David B. Matthews, Director Project Dire;torate 11-3 Division of Reactor Projects-1/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance: April 21, 1989 i
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-35 is hereby amended to read as follows:
l (2) Technical Specifications-
.The Technical Specifications contained in Appendix A, as revised through Amendment No. 62, are hereby incorporated into the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
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3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY C011 MISSION i/5 David B. Matthews,' Director Project Directorate _II-3 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance:
April 21, 1989 0FFICIAL RECORD COPYL'b C)
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NUCLEAR REGULATORY COMMISSION n
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DUKE POWER CONPANY NORTH CAROLINA MUNICIPAL POWER AGENCY NO. 1 PIEDMONT MUNICIPAL POWER AGENCY DOCKET NO. 50-414 CATAWBA NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 56 License No. NPF-52 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the Catawba Nuclear 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) dated October 5,1988, as supplemented Decenber 30, 1988, and January 27, Energy Act of 1954, as amended (the Act)quirerrents of the Atomic, and the 1989, complies with the standards and re 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 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 amendment will not be inimical to the comon 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.
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:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised i
through Anendment No. 56, 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 amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COP 911SSION KJk J T&&
David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance: April 21, 1989 l
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. 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. IlPF-52 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.
56, 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 amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION David B. fiatthews, Director Project Directorate 11-3 Division of Reactor Projects-1/II Office of Nuclear Reactor Regulation l
Attachnent:
Technical Specification Changes Date of Issuance:
April 21, 1989 i
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0FFICIAL RECORD COPY
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ATTACHMENT TO LICENSE AMENDMENT NO. 62 FACILITY OPERATING ~ LICENSE NO. NPF-35 DOCKET NO. 50-413 AND 56 TO LICENSE AMENDMENT NO.
FACILITY OPERATING LICENSE NO. NPF-52 DOCKET NO. 50-414 Replace the following pages of the Appendix "A" Technical Specifications withf the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of. change.
Amended Page 3/4 8-7 3/4' 8-9
,a 4
ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
- 11) Verifying that the fuel transfer valve transfers fuel from each
. fuel storage tank to the day tank of each diesel via the in-stalled cross-connection lines;
'12) Verifying that the automatic load sequence timer is OPERABLE with the interval between each load block within the tolerances given in Table 4.8-2;
- 13) derifying that the voltage and diesel speed tolerances for the accelerated sequencer permissives are 92.5 i 1% and 98 + 1%,
respectively, with a minimum tiae delay of 2 1 0.2 s;
- 14) Verifying that the following diesel generator lockout features -
prevent diesel generator starting only when required:
a)
Turning gear engaged, or b)
Maintenance mode; and
- 15) Operating at greater than or equal to 5600 KW but less than or i
equal to 5750 KW for one hour or until operating temperature has stabilized. Within 5 minutes after completing this test, perform Specification 4.8.1.1.2g.6)b).
h.
At least once per 10 years or after any modifications which could affect diesel generator interdependence by starting both diesel generators simultaneously, during shutdown, and verifying that both diesel generators accelerate to at least 441 rpm in less than or equal to 11 seconds; and i.
At least once per 10 years by:
1)
Draining each fuel oil storage tank, removing the accumulated sediment and cleaning the tank using a sodium hypochlorite solution or its equivalent, and 1
2)
Performing a pressure test of those portions of the diesel fuel 1
oil system derigned to Section III, subsection ND of the ASME l
Code at a test pressure equal to 110% of the system design pressure.
3)
Performing tank wall thickness measurements.
The resulting data shall be evaluated and any abnormal degradation will be l
justified or corrected.
Any abnormal degradation will be i
documented in a report to the Commission.
4.8.1.1.3 Reports - All diesel generator failures, valid or non-valid, shall be reported in a Special Report to the Commission pursuant to Specification 6.9.2 within 30 days.
Reports of diesel generator failures shall include the informa-tion recommended in Regulatory Position C.3.b of Regulatory Guide 1.108, Revi-sion 1, August 1977.
If the number of failures in the last 100 valid tests of any diese? generator is greater than or equal to 7, the report shall be supplemented to include the additional information recommended in Regulatory Position C 3.b of Regulatory Guide 1.108, Revision 1, August 1977.
1 CATAWBA - UNITS 1 & 2 3/4 8-7 Amendment No.62 (Unit 1)
Amendment No.56 (Unit 2)
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! TABLE 4.8-1 c.
DIESEL GENERATOR TEST SCHECblE NUMBED 0F FAILURES IN NUMBER OF FAILURES IN LAST 20 VALID TESTS
- LAST 100 VALID TESTS
- TEST FREQUENCY 51.
$4 At least once per 31 days
> 2**-
>5 At least once-per 7 days I-
- Criteria for determining number of failures and number of valid tests shall be in accordance with Regulatory Position C.2.e of Regulatory Guide 1.108, but determined on a per diesel generator basis.
For purposes of this schedule, only valid tests conducted after the completion of the preoperational test requirements of Regulatory Guide 1.108, Revision 1, August 1977, shall be included in the computation of.the "last 20/100 valid tests."
Fcr the purposes of determining the required test frequency, the previous test'failurecountmaybereducedtozeroifacompletediegel~ overhaul.to like-new condition is completed, provided that the overhaul, including appro-l priate post-maintenance operation and testing, is specifically approved by the manufacturer and if acceptable reliability has been demonstrated. The reliability criterion shall be the successful completion of 14 consecutive tests in a single series.
Ten of these tests shall be in accordance with the routine. Surveillance Requirement 4.8.1.1.2a.4) and 4.8.1.1.2a.5), four j
tests, in accordance with the 184-day testing requirement of Surveillance Requirements 4.8.1.1.2a.4) and 4.8.1.1.2a.5).
If this criterion is not l
satisfied during the first series of tests, any alternate criterion to be used to transvalue the failure count to zero requires NRC approval.
- The associated test frequency shall be maintained until seven consecutive failure-free demands have been performed and the number of failures in the
-last 20 valid demands has been reduced to less than or equal to one.
- A one-time waiver to the requirement for performance of a complete diesel generator overhaul to like-new condition has been granted in order to rezero four' failures of diesel generator 1A which occurred on April 12, 1988, April 19, 1988, April 25, 1988, and May 5, 1988.
These failures resulted from faulty pressure sensors in the diesel generator pneumatic control system.
CATAWBA - UNITS 1 & 2 3/4 8-9 Amendment No42 (Unit 1)
Amendment No.56 (Unit 2)