ML20214J562
| ML20214J562 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 11/20/1986 |
| From: | Jabbour K Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20214J563 | List: |
| References | |
| NUDOCS 8612010351 | |
| Download: ML20214J562 (7) | |
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DOCKET N0. 50-413 CATAWBA NUCLEAR S1ATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 20 License No. NPF-35 1.
The Nuclear Regulatory Commission (the Commission) 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 Corapany acting for itself, North Carolina Electric Membership Corporation, and Saluda River Electric Cooperative, Inc.,
(licensees) dated October 27, 1986, and supplemented November 13, 1986, complies with the standards and re Eneray Act of 1954, as amended (the Act)quirements of the Atomic and the Commission's regulations as 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 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 Conmission's reaulatiers and all applicable requirements have been satisfied.
8612010351 861120 PDR ADOCK 05000413 p
- 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:
(2)TechnicalSpecifications
'The Technical Specifications contained in Appendix A, as revised through Amendment No. 20 and the Environmental Protection Plan contained in Appendix 8, both of which are attached hereto, are hereby incorporated into the 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 November 13, 1986.
FOR THE NUCLEAR REGULATORY COMMISSION x5\\-
Kahtan Jabbour, Project f4 nager PWR Project Directorate #4 Division of PWR Licensing-A
Attachment:
Technical Specification Changes Date of Issuance: November 20, 1986 1
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DUKE POWER COMPANY NORTH CAROLINA MUNICIPAL POWER AGENCY NO. 1 PIEDMONT MUNICIPAL POWER AGENCY DOCKET NO. 50-414 CATAk'BA NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 10 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 Comoany acting for itself, North Carolina Municipal Power Agency No.1, and Piedmont Municipal Power Agency, (licensees) dated October 27, 1986, and supplemented November 13, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulations as set forth in i
10 CFR Chapter I; B.
The facility will operate in confonnity with the application, as amended, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) 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 common defense and security or to the health and safety of the public; ard I
E.
The issuance of this amendment is in accordance with 10 CFR Part 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:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.10 and the Environnental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into the license. Duke Power Conipany shall operate the facility in accordance with the Technical Specifications and the Environmental' Protection Plan.
3.
This license amendment is effective as of Novensber 13, 1986.
FOR THE NUCLEAR REGULATORY COMMISSION Kahtan Jabbour, Project Manager PWR Project Directorate #4 Division of PWR Licensing-A
Attachment:
Technical Specificatien Changes Date of Issuance: November 20, 1986 DJ If h
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ATTACHMENT TO LICENSE AMENDMENT NO. 20 FACILITY OPERATING LICENSE NO. NPF-35 DOCKET NO. 50-413 j
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TO LICENSE AMENDffEtJT fl0.10 F/C' LIM OPERATING LICENSE tiG. NPF-5P POCKET NO. 50-414 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised page is identified by Amendment number and contains vertical lines indicating the areas of change. The corresponding over haf page is also provided to maintain document completeness.
Amended Overleaf Page Page 3/4 7-4 3/4 7-3
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l TABLE 3.7-2 52-j STEAM LINE SAFETY VALVES PER LOOP Es VALVE NUMBER LIFT SETTING (I 1%)*
ORIFICE SIZE C
'E toop A Loop B Loop C Loop D d
1.
SV-20 SV-14 SV-8 SV-2' 1175 psig 14.18 in.2 e.
n3 2.
SV-21 SV-15 SV-9 SV-3 1190 psig 14.18 in.2 3.
SV-22 SV-16 SV-10 SV-4 1205 psig 14.18 in.2
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4.
SV-23 SV-17 SV-11 SV-5 1220 psig 14.18 in.2 5.
SV-24 SV-18 SV-12 SV-6 1230 psig 14.18 in.2 i
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bb "The lif t setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.
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PLANT SYSTEMS AUXILIARY FEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.1.2 At least three independent steam generator auxiliary feedwater pumps and associated flow paths shall be OPERABLE with:
Two motor-driven auxiliary feedwater pumps, each capable of being a.
powered from separate emergency busses, and b.
One steam turbine-driven auxiliary feedwater pump capable of being powered from an OPERABLE steam supply system.
APPLICABILITY:
MODES 1, 2, and 3.
ACTION:
With one auxiliary feedwater pump inoperable, restore the required a.
auxiliary feedwater pumps to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.*
b.
With two auxiliary feedwater pumps inoperable, be in at least HOT STANDBY witin 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6
- hours, With three auxiliary feedwater pumps inoperable, immediately initiate c.
corrective action to restore at least one auxiliary feedwater pump to OPERABLE status as soon as possible.
SURVEILLANCE REQUIREMENTS 4.7.1.2.1 Each auxiliary feedwater pump shall be demonstrated OPERABLE:
At least once per 31 days on a STAGGERED TEST BASIS by:
a.
1)
Verifying that each motor-driven pump develops a total dynamic head of greater than or equal to 3470 feet at a flow of greater than or equal to 400 gpm; i
2)
Verifying that the steam turbine-driven pump develops a total dy-namic head of greater than or equal to 3550 feet at a flow of grea-ter than or equal to 400 gpm when the secondary steam supply pres-sure is greater than 600 psig and the auxiliary feedwater pump tur-bine is operating at less than or equal to 3800 rpm.
The provisions of Specification 4.0.4 are not applicable for entry into MODE 3;
- Until 1845 hours0.0214 days <br />0.513 hours <br />0.00305 weeks <br />7.020225e-4 months <br /> on November 16, 1986, for Unit 1 and 0305 hours0.00353 days <br />0.0847 hours <br />5.042989e-4 weeks <br />1.160525e-4 months <br /> on November 17, 1986, for Unit 2, operation in Mode 3 is permitted with the Auxiliary Feedwater turbine-driven pump inoperable.
CATAWBA - UNITS 1 & 2 3/4 7-4 Amendment No.20 (Unit 1)
Amendment No.10 (Unit 2)