ML20057D008
| ML20057D008 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 09/23/1993 |
| From: | Bajwa S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20057D009 | List: |
| References | |
| NUDOCS 9309300241 | |
| Download: ML20057D008 (12) | |
Text
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o UNITED STATES g
- ,c g
NUCLEAR REGULATORY COMMISSION y
- E WASHINGTON. D. C. 20555
% * *... v9 CAROLINA POWER & LIGHT COMPANY. et al.
DOCKET NO. 50-325 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 165 License No. DPR-71 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by Carolina Power & Light Company (the licensee), dated December 28, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission'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 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; 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 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-71 is hereby amended to read as follows:
i I
9309300241 930923 PDR ADDCK 05000324 p
. (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.165, are hereby incorporated in the license.
Carolina Power & Light Company shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION S. Singh Bajwa, Acting Director Project Directorate 11-1 l
Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation 1
Attachment:
Changes to the Technical Specifications Date of Issuance: September 23, 1993
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e-
i ATTACHMENT TO LICENSE AMENDMENT NO.165 l
FACH ITY OPERATING LICENSE NO. DPR-71 l
DOCXET NO. 50-325 i
Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Remove Paaes Insert Paaes 3/4 1-18 3/4 1-18 3/4 3-13 3/4 3-13 3/4 3-28 3/4 3-28 i
l 4
1 4
1
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i 1
l 1
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REACTIVITY CONTROL SYSTEMS 3/4.1.5 STANDBY L10VID CONTROL SYSTEM i
l LIMITING CONDITION FOR OPERATION l
3.1.5 The standby liquid control system shall be OPERABLE with:
l l
a.
An OPERABLE flow path from the storage tank to the reactor core, i
containing two pumps and two inline explosive injection valves, b.
The contained solution volume-concentration within the limits of Figure 3.1.5-1, and c.
The solution temperature above the limit of Figure 3.1.5-2.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 l
ACTION:
a.
In OPERATIONAL CONDITION 1 or 2:
l 1.
With one pump and/or one explosive valve inoperable, restore the inoperable pump and/or explosive valve to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
2.
With the standby liquid control system inoperable, restore the system to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
l BRUNSWICK - UNIT 1 3/4 1-18 Amendment No. 22,165
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E lii Ejj TABLE 3.3.2-1 (Continued)
ISOLATION ACTUATION INSTRUMENTATION z
El VALVE GROUPS MINIMUM NUMBER APPLICABLE OPERATED BY OPERABLE CHANNELS OPERATIONAL TRIP FUNCTION SIGNAL (a)
PER TRIP SYSTEM (b)(c) CONDITION ACTION
- 2. SECONDARY CONTAllMENT ISOLATION a.
Reactor Building Exhaust Radiation - High (1) 1 1, 2, 3, 5, and* 23 6
1 1, 2, 3 20 un b.
Drywell Pressure - High (1) 2 1,2,3 23 ls 2, 6 2
1,2,3 20 un d.
c.
Low, Level 2 (1) 2 1, 2, 3 23 3
2 1, 2, 3 24
- 3. REACTOR WATER CLEANUP SYSTEM ISOLATION a.
A Flow - High 3
1 1, 2, 3 24 b.
Area Temperature - High 3
2 1, 2, 3 24 c.
Area Ventilation A Temperature - High 3
2 1, 2, 3 24 l[
d.
SLCS Initiation 3"
NA 1, 2 24 l
s lf e.
g; Low, Level 2 3
2 1, 2, 3 24 af f.
er Flow - High - Time Delay Relay NA 1
1, 2, 3 24 l
O'=
o ynym
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E h
TABLE 4.3.2-1 (Continued)
ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIRENENTS z
~.-e CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED
- 2. SECONDARY CONTAIPMENT ISOLATION a.
Reactor Building Exhaust Radiation - High D
M R
1,2,3,5, and" b.
Drywell Pressure - High Transmitter:
NA" NA R"
1, 2, 3 g
Trip Logic:
D M
M 1, 2, 3 i
y c.
Low, Level 2
~
Transmitter:
NA" NA R"
1, 2, 3 Trip Logic:
D M
M 1, 2, 3
- 3. REACTOR WATER CLEANUP SYSTEM ISOLATION a.
A Flow - High D
M R
1, 2, 3 b.
Area Temperature - High NA M
R 1, 2, 3 c.
Area Ventilation A Temperature - High NA M
R 1, 2, 3
(
d.
SLCS Initiation NA R
NA 1, 2 l
e.
Low, Level 2
=
[
Transmitter:
NA" NA R"
1, 2, 3 Trip Logic:
D M
M 1, 2, 3 o
~
f.
A Flow - High - Time Delay Relay NA M
R 1, 2, 3
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'" i E
UNITED STATES i
NUCLEAR REGULATORY COMMISSION
%, v,/
WASHINGTON, D.C. 2055!M)001 CAROLINA POWER & LIGHT COMPANY. et al.
j DOCKET NO. 50-324 BRUNSWICK STEAM ELECTRIC PLANT. UNIT 2 l
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.196 License No. DPR-62 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment filed by Carolina Power & Light Company (the licensee), dated December 28, 1992, 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 l
provisions of the Act, and the rules and regulations of the i
Comission; j
l l
C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and i
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 l
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 amended to read as follows:
l i
l
4 4
- l l
(2) Technical Specifications The Technical. Specifications contained in Appendices A and B, as revised through Amendment No.196, are hereby incorporated in the license.
Carolina Power & Light Company shall operate the facility in accordance with the Technical Specifications, j
3.
This license amendment is effective as of the date of its issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION fVh
/
S. Singh Bajwa, Acting Director Project Directorate 11-1 l
Division of Reactor Projects'- I/II Office of-Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: September 23, 1993 i
l l-i t
l l
i
ATTACHMENT TO LICENSE AMENDMENT NO.196 FACILITY OPERATING LICENSE NO. DPR-62 DOCKET NO. 50-324 l
Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Remove Paaes Insert Paaes 3/4 1-18 3/4 1-18 3/4 3-13 3/4 3-13 3/4 3-28 3/4 3-28 l
l l
l i
1
?
REACTfVITY CONTROL SYSTEMS l
3/4.1.5 STANDBY LIOUID CONTROL SYSTEM LIMITING CONDITION FOR OPERATION i
i 3.1.5 The standby liquid control system shall be OPERABLE with:
l a.
An OPERABLE flow path from the storage tank to the reactor core, containing two pumps and two inline explosive injection valves, l
l b.
The contained solution volume-concentration within the limits of Figure 3.1.5-1, and l
c.
The solution temperature above the limit of Figure 3.1.5-2.
l APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 l
l ACTION:
a.
In OPERATIONAL CONDITION 1 or 2:
l l
l 1.
With one pump and/or.one explosive valve inoperable,- restore the inoperable pump and/or explosive valve to OPERABLE I
status within 7 days or be in at least HOT SHUTDOWN within i
the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
i 2.
With the standby liquid control system inoperable, restore the system to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
l l
l 4
BRUNSWICK - UNIT 2 3/4 1-18 Amendment No. 46,196 l
I v,
TABLE 3.3.2-1 (Continued) n IS0?.ATION ACTUATION INSTRUMENTATIGN b
VALVE GROUPS MINIMUM NUMBER APPLICABLE OPERATED BY OPERABLE CHANNELS OPERATIONAL TRIP FUNCTION SIGNAL (a)
PER TRIP SYSTEM (b)(c) CONDITION ACTION
- 2. SECONDARY CONTAIPMENT' ISOLATION a.
Reactor Building Exhaust (1) 1 1, 2, 3, S, 23 Radiation - High and
- 6 1
1,2,3 20 b.
Drywell Pressure - High (1) 2 1, 2, 3 23 y
2, 6 2
1, 2, 3 20 Y
c.
(1) 2 1, 2, 3 23 C
Low, Level 2 3
2 1,2,3 24
- 3. REACTOR WATER C_Lf3 0P SYSTEM ISOLATION a.
A Flow - High 3
1 1,2,3 24 b.
Area Temperature - High 3
2 1,2,3 24 c.
Area Ventilation A Temperature - High 3
2 1, 2, 3 24 d.
SLCS Initiation 3m NA 1, 2 24 l
e.
hB.
Low, Level 2 3
2 1, 2, 3 24 4
3 ha f.
A Flow - High - Time Delay Relay NA 1
1, 2, 3 24 sz PR GL my
!B C
h l
TABLE 4.3.2 1 (Continued)
-R ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS c
l i5 CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WilCH TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED
- 2. SECOWARY CONTAlmENT JSOLATION a.
Reactor Building Exhaust Radiation - High D
M R
1.2.3.5, and "'
b.
Dr;mell Pressure - High ransmitter:
NA'd NA R"
- 1. 2. 3 Trip Logic:
D M
M
- 1. 2. 3 w
w c.
a Low. Level 2 Transmitter:
NA'd NA R"
1,2.3 Trip Logic:
D M
M
- 1. 2, 3
- 3. REACTOR WATER CLEANUP SYSTEM ISOLATION a.
A Flow - High D
M R
- 1. 2, 3 b.
Area Temperature - High NA M
R 1, 2. 3 c.
Area Ventilation A Temperature - High NA M
R
- 1. 2, 3 d.
SLCS Initiation NA R
NA 1, 2 l
e.
Low. Level.2 Transmitter:
NA'd NA R*
1, 2. 3 Trip Logic:
D M
M
- 1. 2. 3 g
i f.
A Flow - High - Time Delay Relay NA M
R
- 1. 2, 3
. " ^. "
m.
.