ML20206R821

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Amends 174 & 166 to Licenses NPF-35 & NPF-52,respectively, Revising SRs 3.6.11.6 & 3.6.11.7,re Containment Pressure Control Sys,Of Units Joint TSs
ML20206R821
Person / Time
Site: Catawba  Duke Energy icon.png
Issue date: 01/14/1999
From: Berkow H
NRC (Affiliation Not Assigned)
To:
Shared Package
ML20206R825 List:
References
NUDOCS 9901200277
Download: ML20206R821 (7)


Text

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UNITED STATES g

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DUKE ENERGY CORPORATION l

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.174 License No. NPF-35 i

1.

The Nuclear Regulatory Commission (the Commission) has found that:

l A.

The application for amendment to the Catawba Nuclear Statim, Unit 1 (the facility) Facility Operating License No. NPF-35 filed by the Duke Energy Corporation, acting for itself, North Carolina Electric Membership Corporation and Saluda River Electric Cooperative, Inc. (licensees), dated November 11, l

1998, complies with the standards and requirements of the Atomic Energy Act of l

1954, as amended (the Act), and the Commission's rules and regulations as set l

forth in 10 CFR Chapter I;

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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 (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 Commission's regulations set forth in 10 CFR Chapter I; i

D.

The issuance of this amendment will not be inimical to the common defense and I

security or to the health and safety of the public; and 1

E.

The issuance of this amendment is in accordance with 10 C 9 Part 51 of the l

Commission's regulations and all applicable requirements hasa been satisfied.

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9901200277 990114 PDR ADOCK 05000413 P

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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, and paragraph 2.C.(2) of Facility Operating Ucense No. NPF-35 is hereby amended to read as follows:

4 (2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 174, which are enached hereto, are I

hereby incorporated into this license. Duke Energy Corporation j

shall operate the facility in accordance with the Tcchnical Specifications.

l 3.

This license amendment is effective as of its date of issuance, to be implemented concurrently with implementation of Amendment No.173.

l FOR THE NUCLEAR REGULATORY COMMISSION t

v y rbert N. Berkow, Director Ifroject Directorate ll-2 1

Division of Reactor Projects - l/ll Office of Nuclear Reactor Regulation

Attachment:

Technical Specification Changes Date of Issuance:

January 14, 1999 l

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UNITED STATES e*

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NUCLEAR REGULATORY COMMISSION

't WASHINGTON, D.c. 2055W1

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DUKE ENERGY CORPORATION 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.166 License No. NPF-52 1.

The Nuclear Regulatory Commission (the Commission) has icond 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 Energy Corporation, acting for itself, North Carolina Municipal Power Agency No.1 and Piedmont Municipal Power Agency (licensees), dated November 11,1998, 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 (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 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 reculations 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 attachment 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.166, which are attached hereto, are hereby incorporated into this license. Duke Energy Corporation shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance, to be implemented concurrently with implementation of Amendment No.165.

FOR THE NUCLEAR REGULATORY COMMISSION hp Her rt N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects - l/II Office of Nuclear Reactor Regulation

Attachment:

Technical Specification Changes Date of issuance: January 14, 1999

ATTACHMENT TO LICENSE AMENDMENT NOS.174 AND 166 FACILITY OPERATING LICENSE NOS NPF-35 AND NPF-52 DOCKET NOS. 50 413 AND 50-414 Replace the following page of the joint Technical Specifications (Appendix A of the Operating Licenses) with the enclosed page. The revised page is identified by amendment number and contains vertical lines indicating the areas of change.

Remove Insert 3.6.11-2 3.6.11-2 l

Replace the following page of the Technical Specifications Bases with the enclosed page. The l

revised page is identified by amendment number and contains vertical lines indicating the areas of change.

Remove Insert B 3.6.11-5 B 3.6.11-5 i

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i ARS 3.6.11 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY I

SR 3.6.11.2 Verify, with the ARS air return fan damper closed and 92 days with the bypass dampers open, each ARS fan motor current is s 59.0 amps when the fan speed is 2 174 rpm 1

l and s 1200 rpm.

SR 3.6.11.3 Verify, with the ARS fan not operating, each ARS motor 92 days operated damper opens automatically on an actual or simulated actuation signal after a delay of 2 9 seconds and s 11 seconds.

1 SR 3.6.11.4 Verify the check damper is open with the ARS fan 92 days operating.

i SR 3.6.11.5 Verify the check damper is closed with the ARS fan not 92 days operating.

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l SR 3.6.11.6 Verify that each ARS fan is de-energized or is prevented 18 months from starting upon receipt of a terminate signal from the Containment Pressure Control System (CPCS) and is l

allowed to start upon receipt of a start permissive from t

the CPCS.

SR 3.6.11.7 Verify that each ARS fan motor-operated damper is 18 months prevented from opening in the absence of a start permissive from the Containment Pressure Control System (CPCS) and is allowed to open upon receipt of a start permissive from the CPCS.

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Catawba Units 1 and 2 3.6.11-2 Amendment No.174 (Unit 1)

Amendment No.166 (Unit 2)

ARS B 3.6.11 BASES SURVEILLANCE REQUIREMENTS (continued)

SR 3.6.11.3 Verifying the OPERABILITY of the return air damper provides assurance that the proper flow path will exist when the fan is started. This Surveillance also tests the circuitry, including time delays to ensure the system operates properly. The Frequency of 92 days was developed considering the importance of the dampers, their location, physical l

environment, and probability of failure. Operating experience has also l

shown this Frequency to be acceptable.

SR 3.6.11.4 and SR 3.6.11.5 Verifying the OPERABILITY of the check damper in the air return fan discharge line to the containment lower compartment provides assurance that the proper flow path will exist when the fan is started and that l

reverse flow can not occur when the fan is not operating. The Frequency of 92 days was developed considering the importance of the dampers, their location, physical environment, and probability of failure. Operating experience has also shown this Frequency to be acceptable.

SR 3.6.11.6 and SR 3.6.11.7 These SRs require verification that each ARS motor operated damper is i

allowed to open or is prevented from opening and each ARS fan is I

allowed to start or is de-energized or prevented from starting based on the presence or absence of Containment Pressure Control System start permissive and terminate signals. The CPCS is described in the Bases for LCO 3.3.2, "ESFAS." The 18 month Frequency is based on operating experience which has shown it to be acceptable.

REFERENCES 1.

UFSAR, Section 6.2.

2.

10 CFR 50, Appendix K.

3.

10 CFR 50.36, Technical Specifications, (c)(2)(ii).

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i Catawba Units 1 and 2 B 3.6.11-5 Revision No. I t

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