ML20078E686

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Amend 81 to License DPR-62,changing Tech Specs Re Instrumentation Used to Maintain Water Level in Suppression Chamber of Primary Containment Sys
ML20078E686
Person / Time
Site: Brunswick Duke Energy icon.png
Issue date: 09/22/1983
From: Mackay S
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20078E689 List:
References
NUDOCS 8310060043
Download: ML20078E686 (5)


Text

.____

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8 'k*,", )'. o NUCLEAR REGULATORY COMMISSION

'i WASm NGTON. D. C. 20555 t 9 /p/

CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-324 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 2 4

_A_MENDMENT TO FACILITY OPERATING LICENSE 1

Amendment No. 81 License No. DPR-62 1

The Nuclear Reguatory Commissica (the Commission) has found that:

A.

The application for amendment by Carolina Power & Light Company dated June 16, 1932 and July 22, 1983, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 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'c regulations; 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 regulations and all applicable requirements l

have been satisfied.

1 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:

8310060043 830922 PDR ADOCK 05000324 P

PDR

' (2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 81, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of issuance.

FOR THE NUCLEAR REG'JLATORY COMMISSION J

MpM Domenic B. Vassa11c, Chief Operating Reactors Branch #2 Division of Licensing

Attachment:

Changes to the Technical 3pecifications Date of Issuance:

September 22, 1983

_=..

ATTACHMENT TO LICENSE AMENDMENT NO. 81 FACILITY OPERATING LICENSE NO. DPR-62 DOCKET NO. 50-324 Remove the following pages and replace with identically numbered pages:

3/4 3-51 and 3/4 3-52 h

i h

i l

' TABLE 3.3.5.3-1 POST-ACCIDENT MONITORINC INSTRUMENTATION MINIMUM NO.

0F OPERABLE INSTRUMENT INSTRUMENT AND INSTRUMENT NUMBER CHANNELS 1.

Reactor V.essel Pressure 2

(B21-PI-R004 A,B; C32-LPR-R608; and C32-PT-N005A,B) 2.

Reactor Vessel Water Level 2

(B21-LITS-N026A,B; B21-LR-R615; B21-LI-R604A,B; B21-LT-NO37; and B21-LT:(-NO37-1) 3.

Suppression Chamber Water Level 2

(CAC-LT-2601; CAC-LI-2601-1)

(CAC-LT-2602; CAC-LR-2602) 4.

Suppression Chamber Water Temperature 2

(CAC-TR-1258-14, 21; and C91-P602) 5.

Suppression Chamber Ataosphe're Temperature 2

(CAC-TR-1258-17 thru 20; and C91-P602) 6.

Drywell Pressure 2

(CAC-PI-4176; CAC-PT-4176; CAC-PR-1257-1; and CAC-PT-4175) 7.

Drywell Temperature 2

(CAC-TR-1258-1 thru 13, 22, 23, 24; and C91-P602) 8.

Drywell Radiation 2

(CAC-AR-1260; CAC-AQH-1260-1, 2, 3; CAC-AR-1261; CAC-AQH-1261-1, 2, 3; CAC-AR-1262; and CAC-AQH-1262-1, 2, 3) 9.

Drywell Oxygen 2

(CAC-AT-1259-2; CAC-AR-1259; CAC-AT-1263-2; and CAC-AR-1263) 10.

Drywell Hydrogen 2

(CAC-AT-1259-1; CAC-AR-1259; CAC-AT-1263-1; and CAC-AR-1263) 11.

Safety Relief Valve Position Indication:

1/ valve a.

Primary - Sonic (B21-FY-4157 thru 4167) b.

Secondary - Temp. (B21-TR-R614, points 1-11)

BRUNSWICK - UNIT 2 3/4 3-51 Amendment No. 81

~

5 TABLE 4.3.5.3-1 c

f POST-ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL E

INSTRUMENT AND INSTRUMENT NUMBER CllECK CALIBRATION

1 w

1.

Reactor Vessel Pressure M

R

( 821-PI-R004 A, B; C32-LPR-R608; and C32-PT-N005A,B) 2.

Reactor Vessel Water Level M

R

( B21-LITS-N026 A, B; B21-LR-R615; B21-LI-R604A,B; B21-LT-NO37; and B21-LTM-NO37-1) 3.

Suppression Chamber Water Level M

R (CAC-LT-2601; CAC-LI-2601-1; CAC-LT-2602; CAC-LR-2602) 4.

Suppression Chamber Water Temperature M

R (CAC-TR-1258-14, 21; and C91-P602) 5.

Suppression Chamber Atmosphere Temperature M

R (CAC-TR-1258-17 thru 20; and C91-P602)

O 6.

Drywell Pressure M

R (CAC-PI-4176; CAC-PT-4176; CAC-PR-1257-1; end CAC-PT-4175) 7.

Drywell. Temperature M

R (CAC-TR-1258-1 thru 13, 22, 23, 24; and C91-P602) 8.

Drywell Radiation M'

R (CAC-AR-1260; CAC-AQll-1260-1,2,3; CAC-AR-1261; CAC-AQ11-1261-1,2,3; CAC-AR-1262; and CAC-AQll-1262-1,2,3) 9.

Drywell Oxygen Concentration M

R (CAC-AT-1259-2; CAC-AR-1259; CAC-AT-1263-2; and CAC-AR-1263) k 10.

Drywell liydrogen Concentration M

R g

(CAC-AT-1259-1; CAC-AR-1259; CAC-AT-1263-1; and CAC-AR-1263) a g

11.

Safety Relief Valve Position Indication Primary - Sonic (B21-FY-4157 thru 4167)

M R

n a.

g b.

Secondary - Temp. (B21-TR-R614, points 1-11)

M R

3

.