ML20135A721
| ML20135A721 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 09/03/1985 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Carolina Power & Light Co |
| Shared Package | |
| ML20135A725 | List: |
| References | |
| DPR-62-A-115, DPR-71-A-090 NUDOCS 8509100247 | |
| Download: ML20135A721 (12) | |
Text
.
UNITED STATES g
't NUCLEAR REGULATORY COMMISSION
- ,1 y
WASHINGTON, D. C. 20555 e
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CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-325 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 1
AMENDMENT TO FACILITY OPERATING LICENSE
.anndment No. 90 License No. OPR-71 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Carolina Power & Light Company (the licensee) dated June 18, 1985, 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 Comission; 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 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.
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-71 is hereby amended to read as follows:
8509100247 850903 PDR ADOCK 05000324
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. 4 (2) Technical Specifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No. 90, are hereby incorporated in the 4
license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: September 3,1985 l
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ATTACHMENT TO LICENSE AMENDMENT NO. 90 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.
Pages 3/4 3-63 3/4 3-65
}
3/4 3-66 i
i
(BSEP-1-55)
TABLE 3.3.5.8-1
&g RADIOACTIVE LIQUID EFFLUENT HONITORINC INSTRUMENTATION r
-l INSTRUMENT ")
APPLICABILITY ACTION I
i g
1.
Li' quid Radwaste Radio:ctivity Effluent Monitor y
(Providing alarm and automatic termination of release) 110 111 2.
Liquid Radwaste Effluent Flow Heasurement Device 112 3.
Main, Service Water Ef fluent Radioactivity Monitor 113 4.
Stabilization Pond Effluent Composite Sampler 5.
Stabilization Pond Ef fluent Flow Measurement Device 114
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115 6.
Condensate Storage Tank Level Indicating Device 3
7.
Service Water Effluent from Augmented Off gas
[
Precooler Radioactivity Monitor 112 m
.-s s
aa an C3
1 i
J 1
I (BSEP-1-55) i TABLE 3.3.5.8-1 (Continued)
RADIOACTIVE LIQUID EFFLUENT MONITORINC INSTRUMENTATION NOTES At all times At all times other than when the line is valved out and locked.
At all times while the AOC system precooler is in operation once this monitor is installed and after the AOC system becomes operationali however, if the AOC system becomes operational prior to the monitor being installed, then action statement 112 will be implemented.
[ NOTE: This monitor is to be installed].
(a)
Refer to Appendix E of the OFFSITE DOSE CALCULATION MANUAL for specific instrumentation identification numbers.
. BRUNSWICK - UNIT 1 3/4 3-65 Amendment No. 90
_ _. ~ _. _ _
(BSEP-1-55)
TABLE 4.3.5.8-1 g
E RADIOACTIVE LIQUID EFFLUENT HONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS y
E CHANNEL P:
CilANNEL SOURCE CHANNEL FUNCTIONAL I
INSTRUMENT (a)
CllECK CilECK CALIBRATION TEST g
4 1.
Liquid Radwaste Radioactivity Effluent Monitor R(b) q(c)
D M
(Providing alarm and automatic termination of release)
D *)
NA R
Q I
Device 2.
Liquid Radwaste Effluent Flow Measurement R(b) g(d)
D M
'3.
Main Service Water Effluent Radioactivity Monitor D
NA R
Q
~_
4.
Stabilization Pcnd Effluent Composite Sampler D
NA R
Q
.5.
Stabilization Pond Ef fluent Flow Measuremcat Device D-( f)
NA R
Q 6.
Condensate Storage Tank Level Indicating Device mk o'
7.
Service Water Effluent.from Augmented Off-Cas R(b) q D
N Preccoler Radioactivity Monitor t'
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UNITED STATES NUCLEAR REGULATORY COMMISSION o
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,E WASMNGTON, D. C. 20555
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t CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-324 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.115 License No. DPR-62
- 1.. The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Carolina Power & Light Company (the licensee) dated June 18, 1985, complies with the standards and i
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; j.
B.
The facility will operate in confomity with the application, the provisions of the Act, and the rules and regulations of the Connission; f.
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 l
conducted in compliance with the Comission's regulations;-
i i
D.
The issuance of this amendment will not be inimical to the i
comon defense and security or to the health and safety of the public; and i
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 amended to read as follows:
. (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 115, 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 its issuance.
FOR THE NUC EAR REGULATORY COMMISSION Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: September 3, 1985
._=
i l
i i
d i
ATTACHMENT TO LICENSE AMENDMENT NO.115 FACILITY OPERATING LICENSE NO. DPR-62 DOCKET NO. 50-374 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Pages 3/4 3-63 3/4 3-65 3/4 3-66 l
1 1
(BSEP-2-50)
E TABLE 3.3.5.8-1 Ey
.RADI0 ACTIVE LIQUID EFFLUENT NONITORINC INSTRUMENTATION INSTRUMENT (a)
APPLICA8II.ITY ACTION O
g 1.
Liquid Radwaste Radioactivity Effluent Monitor y
(Providing alarm and automatic termination of release) 110 u
2.
Liquid Radwaste Effluent Flow Measurement Device
'111 3.
Main Service Water Effluent Radioactivity Monitor 112 4.
Stabilization Pond Effluent Composite Sampler 113 5.
Stabilization Pond Ef fluent Flow Measurement Device 114 6.
Condensate Storage Tank Level Indicating Device 115
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7.
Service Water Effluent from Augmented Off gas Preccoler Radioactivity Monitor 112 Y
u an
.C a.
o
e, s.
(BSEP-2-50)
TABLE 3.3.5.8-1 (Continued)
RADIOACTIVE LIQUID EFFLUENT MONITORINC INSTRUMENTATION NOTES At all times At all times other than when the line is valved out and locked.
At all times while the AOC sys'em precooler is in operation once this i
monitor is installed and after the AOC system becomes operational; however, if the AOC system becomes operational prior to the monitor being installed, then action statement 112 will be implemented.
[ NOTE: This monitor is to be installed).
l (a)
Refer to Appendix E of the OFFSITE DOSE CALCULATION MANUAL for specific instrumentation identification numbers.
i BRUNSWICK - UNIT 2 3/4 3-65 Amendment No. 116 L -
__o
(RSEP-2-50)
~
- w TABLE 4.3.5.8-1 Ey RADIOACTIVE LIQUID EFFLUENT MONITORINC INSTRLMENTATION SURVEILLANCE RE@IREMENTS h
E CHANNEL e
I CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT *)
e CHECK CilECK CALIBRATION TEST d"
1.
Liquid Radwaste Radioactivity Effluent Monitor (Providing alarm and automatic termination of release)
D M
R(b) q(c)
I D *)
NA R
q 2.
Liquid Radvaste Effluent Flow Measurement Device 3.
Main Service Water Effluent Radioactivity Monitor D
M R(b) q(d) 4.
Stabilization Pond Effluent Composite Sampler D
WA R
Q 5.
Stabilization Pond Ef fluent Flow Measurement Device D
NA R
Q S
If) 6.
Condensate Storage Tank Level Indicating Device D
NA R
Q m
S e
7.
Service Water Effluent from Augmented Off-Cas Precooler Radioactivity Monitor D
M RID)
Q c.
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