ML20082P650
| ML20082P650 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 11/28/1983 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Carolina Power & Light Co |
| Shared Package | |
| ML20082P651 | List: |
| References | |
| DPR-62-A-084, DPR-71-A-058 NUDOCS 8312090123 | |
| Download: ML20082P650 (5) | |
Text
. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _.
_ jntag'e UNITED STATES NUCLEAR REGULATORY COfM5lSSION WASHINGTON, D. C. 20555
.t
.i CAROLINA POWER & LIGHT COMPANY-i DOCKET NO. 50-325 I
BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 D
AMEtiDMENT TO FACILITY OPERATING LICENSE
<y Amendment No. 58 I
License No. DPR-71 l
1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Carolina Power & Light Company (thelicensee-)datedDecember 13, 1982 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; The' facility will operate in conformity'd regulations of the B.
with the application, the provisions of the Act, and the rules ~an Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted.without endangerir.g 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 defens'e and security or to the health and safety of the l
public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 i
of the Comission's regulations and all applicable requirements have been satisfied.
j,
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-71 is hereby amended to read as follows:
o!$$$$j4 PDR
l 2-2.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 58, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Speciff;ations.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUC AR REGU TORY COMMISSION N,
Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of. Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
November 28, 1983 N ewe #
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ATTACHMENT TO LICENSE AMENDMENT NO. 58 FACIl.ITY OPERATING LICENSE NO. OPR-71 DOCKET N0. 50-325' o
Revise the Appendix A Technical Specifications as follows:
Remove Insert 3/4 3-14 3/4 3-14 y
3/4 3-14a 3/4 3-14a s
9 Mwo W e
'd s.
2 a
e n-w
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.w e__
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Y Ihh" TABLE 3.3.2-1 (Continued)
~
g E
ISOLATION ACTUATION INSTRUMENTATION y
MINIMUMNUMl}bR' H
VALVE GROUPS APPLICABLE b
-9 OPERATED BY OPERABLE ClJANNELS OPERATIONAL 8
TRIP FUNCTION AND INSTRUlfENT NUMBER SIGNAL (a)
PER TRIP SYSTEM (b)(c) C0tiDITION ACTION l
0, 4.
CORE STANDBY COOLING SYSTEMS ISOLATION g
w a.
High Pressure Coolant Injection System Isolation
- 1. -
HPCI Steam Line. Flow - Iligh 4
1 1, 2, 3 25 l
(E41-dPIS-N004 and T41-dPIS-N005) 2.
IlPCI Steam Supply Pressure - Low 4 2
1,.2, 3
25 (E41-PSL-N001A,B,C,D) 3 '.
IIPCI Steam Line. Tunnel Temperature - High 4
2 1,2,3 25 t'
(E41-TS-3314; E41-TS-3315; y
E41-TS-3316;,
7 E41-TS-3317;.
E41-TS-3318;-
[
E41-TS-3354;.
3 E41-TS-3488; E41-TS-3489) 4.
Bus Power Monitor NA(h) 1/ bus 1, 2, 3 26 (E41-K55 and E41-K56) 5.
I!PCI Turbine Exhaust Diaphragm Pressure - Iligh 4
2 1,2,3 25 y
(E41-PSil-N012A,B,C, D) m g,.
6.
"IIPCI Steam Line Ambient M
Temperature - liigh 4
1 1,2,3 25 l
E (E51-TS-N6030, D) y 7.
IIPCI Steam Line Area a Temp. -
Illgh 4
1 1,2,3 25 l
g (E51-dTS-N604C,D) 8.
Emergency Area Cooler
~
Temperature - Iligh 4
I 1, 2, 3 25 l
(E41-TS-N602A,B)
-. - ~ _ - -.
'd
(
x
- r TABLE 3.3.2-1 (Continued)
. :o E!
ISOLATION ACTUATION INSTRUMENTATION en2:
E VALVE GROUPS
- HINIMUti NUMBER
' APPLICABLE OPERATED BY OPERABLE Cil/NNELS.
OPEliATIONAL TRIP FUNCTION AND INSTRUtlENT NUMBER.
SIGNAL (a)'
PER TRIP SISTEM(b)(c) CONDITION ACTION E!
E b.
Reactor Core Isolation Codling System Isolation.
~
1.
RCIC Steam Line Flow - liigh 5
1 1,2,3 25 l
(E5.1-dPIS-N017 and E51-dPIS-N018) 2.
RCIC Steam Supply Pressure - Low 5
2 1, 2, 3 -
25 (E51-PS-H019A,B,C,D)
~ 3.
RCIC Steam Line Tunnel Temperature
- liigh 5
2 1,2,3 25 (E51-TS-3319;
~
E51-TS-3320; E51-TS-3321; N
E51-TS-3322; E51-TS-3323; lY E51-TS-3355; I5 E51-TS-3487) l 9
4.
'Btis Power Monitor
\\
NA (h) 1/ bus 1, 2, 3 26 (E51-K42 and E51-K43) 5.
RCIC Turbine Exhaust Diaphragm Pressure - liigh 5
2 1,2,3 25 (E51-PS-N012A,B,C, D) 6.
.RCIC Steam Line Ambient Temp -
liigh 5
1 1,2,3 25 l
[
(E51-TS-N603A,B) j!,
7.
RCIC Steam Line ' Area A Temp - liigh 5
1 1,2,3 25-l g
(E51-dTS-N6044,B) o" 8.
- RCIC Equipment Room Ambient y
Temp - liigh 5
1 1,2,3 25 l
(E51-TS-N602A,B)
<n 9.
RCIC Equipment Room A Temp - liigh 5
1 1
2,3 25 l
(E51-dTS-N601A,B)
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