ML20006E806
| ML20006E806 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 02/15/1990 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20006E807 | List: |
| References | |
| NUDOCS 9002260367 | |
| Download: ML20006E806 (6) | |
Text
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-W e nan UNITED STATES -
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NUCLEAR REGULATORY COMMISSION g
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5 E-W ASHING TON, D. C. 20555
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CUKE POWER COMPANY
!!0RTH CAROL:NA ELECTRIC MEMBERSHIP CORPORATION CALUDA RIVER ELECTRIC CCCPERATIVE, INC.
DOCKET NO. 50-413 CATAWBA NUCLEAR STATION, UNIT 1 AMENDMENT T0_ FACILITY OPERATING LICENSE Amtridment No. 70 License No. NPF-35 1.
The !!uclear Regulatory Comission (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 Company, acting for itself, North Carolina Electric Menbership) Corporation anc Saluda River Electric Coo)erative, Inc.(licensees, d requirenents of the Atomic Energy Act of 1954, as anended (the Act),
and the Corsission's rules and regulations as set forth in 10 CFR Chap.ter 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 (i) that the activities authorized by this amenoment can be conducted without endangering the health and shfety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulaticns 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 tbc 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.
9002260367 900215 ADOCK 0 % 3 DR i
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Accordingly, the license is hereby a:: ended by page 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-35 is hereby enended to read as follows:
Technical Specifications The. Technical Specifications contained in Appendix A, as revised through Amendrent No. 70, 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 C0lHIS$10ft
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r 99 David B. Matthews, Director Project Directorate II-3 Division of Reactor Projects.1/II Office of t!uclear Reactor Regulation Attachmer.t:
Technical Specification Changes Date of Issuance: February 15, 1990 l
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NOCLEAR REGULATORY COMMISSION I
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CUXE POWER COMPANY l
NORTH CAROLINA ML'HICIPAL POWER AGENCY NO.1 PIEDMONT MUNICIPAL FCWER AGENCY DOCKET NO. 50-414 CATEPA NUCLEAR STATION. UN!T 2 AMENDPENT TO FACILITY OPERATING LICENSE Asaeconent No. 64 License No. NPF-52 1.
The Nuclear Regulatory Comission (the rommission) has found that:
A.
1he application for ameneent to the Catawba Nuclear Station, Unit 2 -
(the facility), facility Cperating License No, hPF-52 filed by the Duke Power Company, acting for itself, fbrth Carolina Municipal Power Agency No.1 and Pieomont Municipal Power Agency (licensees), dated i
February 5,1990, coglies with the standards ano 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; L
C.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; L
l-C.
There is reasonable assurance (i) that the-activities authorized by L
this amendment can be conducted without endangering the health and l<
safety of the public, and (ii) that such activities will be conducted in cogliance with the Comission's regulations set forth in 10 CFR Chapter I; 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 amentent is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have teen satisfied.-
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' Accordingly. the license is hereby arended by page changes to the Technical Specifications as indicated in the attactrnent to this license amentent, and Paragraph 2.C.(2) of Facility Operating License Ho, liPF-52 is hereby amended to read as follows:
Technical Specifica_tions
.The Technical Specifications contained in Appendix A, as revised.
through Arendment ho. 64 are hereby incorporated into the license.
The licensee shall operute the facility in accoroance with the Technical Specifications and the Environ 9 ental Protection Plan.
3.
This licerise amencent is effective as of its date of issuance.
FOR THE t:UCLEAR REGULATORY COMMISSION bd Wu' David B. Matthews, Director Project Directorate 11-3 Divisicn of Reactor Projects-1/II Office of Nuclear Peactor Regulation Attachtrent:
Technical Specification Changes Cate of Issuance: February 15, 1990
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- ATTACHMENT TO LICENSE AMENDMENT NO. 70 c.
- u FACILITY CFERATIhG LICENSE NO. NPF-35
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CCCKET NO. 50-413 AND TO LICENSE AMEllDt1ENT NO. 64 FACILITY OPERATIIG LICENSE NO. NPF-52 DOCKET NO. 50-414 Replaca the.following page of the Appendix "A" Technical Specifications with
- the. enclosed page'.. The. revised page is identified by Amendment number and~
contains vertical lines indicating the areas.of change.
Amended Page 3/4 7-3 I
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? TABLE 3.7-2 2
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' STEAM LINE SAFETY VALVES PER LOOP z
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-LIFTSET.'ING*({-1.S%)**
.( '1%)
ORIFICE SIZE-e-1 VALVE NUMBER 25 IN Loop A Loop B Loop C Loop'D 1.
SV-20 SV-14 SV-8 SV-2 1175 psig 14.18 in.2 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 4 '.
SV-23
-SV-17 SV-11 SV-5' 1220 psig 14.18 in.2 5.
SV-24 SV-18 SV 'SV-6 1230 psig 14.18 in.2 7
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- The lift: setting pressure shall correspond to ambient conditions of the valve at' nominal operating temperature;and pressure.
- Change applies to Unit 2 only. Change only applies until first forced outage, reactor trip,.or refueling outage.
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