ML20069Q481

Amends 181 & 151 to Licenses DPR-62 & DPR-71,respectively, Authorizing Removal of RHR Head Spray Flow Transmitters

ML20069Q481
Person / Time
Site:	Brunswick
Issue date:	01/09/1991
From:	Adensam E Office of Nuclear Reactor Regulation
To:
Shared Package
ML20069Q483	List: ML20069Q481 ML20069Q508
References
NUDOCS 9101160082
Download: ML20069Q481 (10)

Text

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UNITED STATES

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g NUCLEAR REGULATORY COMMIS$10N WA BHINGTON, D, C. freebe CAROLINA POWER & LIGHT COMPANY. et al.

DOCKET NO. 50-325 BRUNSWICK STEAM ELECTRIC PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 161 License No. DPR 71 1.

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

A.

The application for amendment filed by Carolina Power & Light Company (thelicensee),datedMay 22, 1990, and supplemented dated December 27, 1990, complies with the standards and re Energy Act of 1954, as amended (the Act)quirements of the Atomic

, and the Comission's rules and regulations 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; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of public; and i

E.

The issuance of this amendment is in accordance with 10 CFR Part 51 i

of the Commission's regulations and all applicable requirements l

have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications, as indicoted in the attachment to this license amendments and paragraph 2.C.(2) of Facility Operating License No. DPR-71 is hereby amended to read as follows:

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.2 (2) Technical Specifications The Technical Specifications contained in Appendices A and B. as revised through Amendment No.151 are hereby incorporated in the license.

Carolinh Power & Light Company shall operate the facility in accordance with the Technical Specifications, j

3.

This license anendment is effective as of the date of its issuance and shall be implemented within 60 days of issuance.

FOR 1HL huCLLAR REGULATORY ColNISSION l

Ronnie Lo/for Elinor G. Adensam, Director

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Project Directorate II.1 Division of Reactor Projects. I/11 Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications 3

i Date of Issuance: January 9, 1991 N

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m' ATTACHMENT _T0__ LICENSE AMENDMENT N_0._151 FACILITY _ OPERATING L_ICENSE_NO _DPR_-71 2

DOCKET NO.__50-325 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.

The revised areas are indicated by marginal lines.

Remove Pages Insert _Pages 3/4 3 57 3/4 3-L7 3/4 3-58 3/4 3-f8

3j TABLE 3.3.5.2-1 REMOTE SHUTDOWN MONITORING INSTRUMENTATION MINIMUM READOUT CHANNELS FUNCTIONAL UNIT LOCATION OPERABLE

1. Reactor Vessel Pressure RSP(a) 3

2. Reactor Vessel Water Level RSP(a) g

3. Suppression Chamber Water Level RSP(a) g

4. Suppression Chamber Water Temperature RSP(a) g

5. Dr ywell Pres sure RSP(a) g

6. Drywell Temperature RSP(a) g

7. Residual Heat Removal System Flow RSP(a) g (a) Remote Shutdown Panel, Reactor Building 20' Elevation BRUNSWICK - UNIT 1 3/4 3-57 Amendment No. 22, J20, 120, 225, 151

q TABLE 4.3.5.2-1 REMOTE SHUTDOWN HONITORINC INSTRUMENTATION SURVE!LLANCE REQUIREMENTS CHANNEL CHANNEL FUNCTIONAL UNIT CHECK CALIBRATION

1. Reactor Vessel Pressure H

Q

2. Reactor Vessel Water Level N017 inst rument Loop NA Q

Remaining Instruments!

H Q

3. Suppression Chamber Water Level M

R

4. Suppression Chamber Water Temperature H

R

5. Drywell Pressure M

Q

6. Drywell Temperat ure H

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7. Residual Heat kemoval System Flow H

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i BRUNSWICK - UNIT 1 3/4 3-58 Amendment No.//,JJp, 130. 135, 151

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DOCKETNO.50-32 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.181 License No. DPR-62 1.

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

A.

The application for amendment filed by Carolina Power & Light Company (thelicensee),datedMay 22, 1990, and supplement dated December 27, 1990, complies with the standards and re Energy Act of 1954, as amended (the Act)quirements of the Atomic and the Comission's rules and regulations set forth in 10 CFR Chapter I; D.

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:

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 amended by changes to the Technical Specifications as indicated in the attachment to this license amendment; and paragraph 2.C.(2) of Facility Operating License No. DPR-62 is hereby amer.ded to read as follows:

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(?) Ttchnical Specifications The Technical Specifications contained in Appendices A end B, as revised through Arnendinent No.181, are hereby inenrportted in the license.

Caroline Power I. Light Company shell operete the facility in accordance with the Technical Specifications, j

3.

This license einendment is effective as of the date of its issuance end shall be implemented within f 0 days of istuance.

FOR THE HUCLEAR REGULATORY COMMIS$10H Ronnie Lo/for Elinor G. Adensarn, Director Project Directorate !!.1 Division of Reactor Projects 1/11 Office of llucicar Reactor Regulation Attachnient:

Changes to the Technical Specifications Date of Issuance: :l muery 9,1991 i

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4 ATTACHMENT TO LICENSE AMENDMENT NO.181 FACILITY OPERATING LICENSE NO. DPR-71 DOCKET NO. 50-325 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.

Remove Pages insert Pages 3/4 3 57 3/4 3-57 3/4 3-58 3/4 3-58 1

' ?.3 TABLE 3.3.5.2-1 REMOTE SHUTDOWN MONITORINC INSTRUMENTATION MIN 1WUM READOUT CHANNELS FUNCTIONAL UNIT LOCATION OPERABLE

1. Recetcr Vessel Pressure RSP(a) 3

2. Reactor Ve:=el Water Level RSP(a) g

3. Suppression Chamber Water Level RSP(a) g

4. Suppression Chamber Water Tempcrature RSP(a) g

5. Drywell Pressure RSP(a) g

6. Drywell Temperature RSP(a) 1

7. Residual Heat Removal System Flow RSP(a) g (8) Remote Shutdown Panel, Reactor Building 20' Elevation BRUNSWICK - UNIT 2 3/4 3-57 Amendment No. f$,Jf),

160, 165, 181

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TABLE 4.3.$.2-1 REMOTE SHUTDOWN MONITORINC INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNCL PUNCTIONAL UNIT CHECK CALIBRATION

1. Reactor Vessel Pressure H

Q

2. Reactor Vessel Water Level N017 Instrument Loopt NA Q

Remaining Instruments!

H Q

3. Suppression Chamber Water Level H

R

4. Suppression Chamber Water Temperature H

R

5. Drywell Pressure H

Q

6. Drywell Temperature H

R

7. Residual Heat Removal System Flow H

Q BRUNSWICK - UNIT 2 3/4 3-58 Amendment No. 46,145, 160 JEE, 181