ML20151D514

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Amend 148 to License DPR-62,revising Instrument Tag Numbers B21-LI-R604AX & B21-LT-N026A to B21-LI-R604BX & B21-LT-N026B,respectively,in Tech Specs 3.3.5.2-1 & 4.3.5.2-1
ML20151D514
Person / Time
Site: Brunswick 
Issue date: 04/07/1988
From: Adensam E
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20151D516 List:
References
NUDOCS 8804140290
Download: ML20151D514 (5)


Text

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g UNITED STATES NUCLEAR REGULATORY COMMISSION o

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g WASHINGTON, D. C. 20655 A...../

CAROLINA F0WER & LIGHT COMPANY, et al.

DOCKET NO. 50-324 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.143 License No. DPR-62 1.

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

A.

The cpp11 cation for amendment by Carolina Power & Light Company (the licensee), dated December 10, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), 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 Commission; C.

There is rea*3nable 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 'he Comission's regulations; D.

The issuance of this amencment 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 amendmant is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requireirents hai e 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 amended to read as follows:

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, (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.148, are hereby incorporated in the license. Carolina Power & Light Company shall operate the fa:ility in accordance with the Technical Specifications.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION Elinor G. Adensam, Director

".roject Directorate 11-1 Division of Reactor Projects I/II

Attachment:

Changes to the Technical Specifications Date of Issuance:

April 7, 1988

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4 ATTACHMENT TO LICENSE AMENDMENT NO.

FACILITY ~0PERATING LICENSE NO. OPR-62 DOCKET NO. 50-324 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 3-48 3/4 3-48 i

3/4 3-49 3/4 3-49 I

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4 4

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  • dy TABLE 3.3.5.2-1

'd

'A REMOTE SillITDOWN HONITORINC INSTRilHENTATTON e

HINTHIM G

READOUT CllANNELS fj FUNCTIONAL UNIT AND INSTRifMENT NIMRER LOCATION OPERAHLE

1. Reactor Vessel Pressure -

RSP*

1 (C32-PI-3332 and C32-PT-3332)

2. Reactor Vessel Water Level RSP*

1 (821-LT-NO!7D-3, B21-LSit-NOl7D-3)

(821-LI-3331, 821-LI-R604BX, B21-LT-3331, g

821-LT-N0268) l 2

3. Fuppression Chamber Water Level RSP*

1 (CAC-LI-3342 and CAC-LT-3342;

'a '-

4. Suppression Chamber Water Temperatore RSP*

1 g

(CAC-TR-778-7) ca

5. Drywell Pressure RSP*

1 (CAC-PI-3341 and CAC-PT-3341) t I

6. Dryvell Temperature RSP*

1 (CAC-TR-778-1,3,4)

7. Residual Heat Removal Head Spray RSP*

1 Flow (El1-FT-3339 and El1-FI-3339) l

8. Residual Heat Removal System Flow RSP*

I h

(Ell-FT-3338, Ell-FI-3338, end Ell-FY-3338)

9. Residual liest Removal Service Water RSP*

1 f,

Discharge Differential Pressure (Ell-PDT-NOO2BX and Ell-PDI-3344) i; h

SResnote Shutdoun Panel, Reactor Building 2D' Elevation

.S

=

i

ce h

TABl.E 4.3.5.2-1 is REMOTE SHUTDOWN HONITORINC INSTRIIMENTATION SifRVEITJ.ANCE REQlIIREMENTS H

O CllANNEL CilANNEL CllECK CAI.IRRATION C3 FilNCTIONAL UNIT AND INSTRilHENT NIMRER 5~1 M

q 1.

Reactor Vessel Pressure (C32-PI-3332 and C32-PT-3332) f 2.

Reactor Vessel Water Level-'

NA Q

(R21-LT-H017D-3, B21-LSH-N017D-3)

(821-LI-3331, d21-LI-R604BX, B21-LT-3331, M

q 821-LT-NO268)

R M

3.

Suppression Chamber Water Level

-(CAC-LI-3342 and CAC-LT-3342)

H R

{

4.

Suppression Chamber Water Temperature (CAC-TR-778-7) 4' N

Q 5.

D h ll Pressure (CAC-PI-3341 and CAC-PT-3341)

M R

6.

Drywell Temperature (CAC-TR-778-1,3,4) 7.

Residual Heat Removal llend Spray Flow (E11-FT-3339 and Ell-FI-3339)

H q

8.

Residual Heat Removal System Flow M

q

. Ell-FT-3338, Ell-FI-3338, and Ell-FY-3338)

(

I' 9.

Residual Heat Removal Service Water Discharge H

Q Differential Pressure (Ell-PDT-NOO2HX

'and Ell-PDI-33/.4)

IN

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