ML20063G930
| ML20063G930 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 08/17/1982 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20063G932 | List: |
| References | |
| DPR-62-A-073 NUDOCS 8209010249 | |
| Download: ML20063G930 (7) | |
Text
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.. _.mu2 p**%['t, UNITED STATES y
NUCLEAR REGULATORY COMMISSION I
..,fg WASHINGTON, D. C. 2,0555 2
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CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-324 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE I
Amendment No. 73 License No. DPR-62 1.
The Nuclear Regulatory Commission (the Commi:sfon) has found that:
A.
The application for amendment by Carolina Power & Light Company dated June 16, 1982, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations sat 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.
l 2.
Accordingly, the license is amended by changes to the Technical Spec-ifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. DPR-62 is here-by amended to read as follows:
l (2) Technical Specifications The Technical Specifications contained in Nppendices A and B, as revised through Amendment No. 73, are hereby incorporated in the license. The licensee shall operate the facility.in accordance with the Technical Specifications.
O DR DR
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This license amendment is effective as of the date of issuance.
j FORTHENUCLE)RREGULATORYCOMMISSION
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Domenic B. Vassallo, Chief 4
Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical I
j Specifications f
Date of Issuance: August 17, 1982 I
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ATTACHMENT TO LICENSE AMENDMENT NO. 73 FACILITY OPERATING LICENSE-NO. DPR-62 P
DOCKET NO. 50-324 5
Remove the following pages and replace with identically numbered pages.
3/4 3-3 3/4 3-6 3/4 3-8 3/4 7-12
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TABLE 3.3.1-1 (Continued) es S'8 REACTOR PROTECTION SYSTEM INSTRUMENTATION N
m APPLICABLE MINIMUM NUMBER Q
OPERATIONAL OPERABLE CilANNELS FUNCTIONAL UNIT AND INSTRUMENT NUMBE9 CONDITIONS PER TRIP SYSTEM (a)(b)
ACTION h
7.
Drywell Pressure - High 1, 2(*)
2 6
H (C72-PS-N002 A,B,C,D) r w
8.
Scram Discharge Volume Water level -
High (Cl2-LSil-N013 A,B,C,D) 1, 2, 5(f) 2 5
l (C12-LSH-4516A,B,C,D) l
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1(E) 4 8
9.
Turbine Stop Valve - Closure (EHC-SVOS-1X,2X,3X,4X)
R Control Oil Pressure - Low 1
2 8
I e
(EHC-PSL-1756,1757,1758,1759) i Y
l W
- 11. Reactor Mode Switch in Shutdown l
l Position (C72A-SI) 1,2,3,4,5 1
9
.I
- 12. Manual Scram (C72A-S3A,B)
I, 2, 3,'4, 5 1
10 '
l N
E I
- = =-
TABLE 3.3.1-2
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b REACTOR PROTECTION RESPONSE TIMES
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g FUNCTIONAL UNIT AND INSTRUMENT NUMBER RESPONSE TIME j
7 (Seconds) l.
Intermediate Range Monitors (C51-IRM-K601 A,B,C,D,E,F,G,II):
f h
a.
Neutron Flux - liigh*
NA s
i H
b.
Inoperative NA r.
w 2.
Average Power Range Monitor * (C51-APRM-Cll. A,B,C,D,E,F):
f a.
Neutron Flux - liigh, 15%
< 0.09 l
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b.
Flow-Biased Neutron Flux - High NA c.
Neutron Flux - High, 120%
d.
Inoperative
~< 0.09 NA 6
e.
Downscale NA l
f.
LPRM NA N
3.
Reactor Vessel Steam Dome Pressure - High (B21-PS-N023 A,B,C,D)
~< 0.55
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4.
Reactor Vessel Water Level - Level #1 (B21-LIS-N017 A,B,C,D)
< 1.05 k
b 5.
Main Steam Line Isolation Valve-Closure (B21-F022 A,B,C,D and B21-F028 A,B.C.D)
< 0.06 b
i 6.
Main Steam Line Radiation - High (D12-RM-K603 A,B,C,D)
NA 7.
Drywell Pressure - High (C72-PS-N002 A,B,C,D)
NA L
8.
Scram Discharge Volume Water level - liigh (Cl2-LSH-N013 A,B,C D)
NA (Cl2-LSH-4516A,B,C,D) l 9.
Turbine Stop Valve - Closure (EHC-SVOS-IX,2X,3X,4X)
< 0.06
- 10. Turbine Control Valve Fast Closure, Control Oil Pressure - low (EHC-PSL-1756,1757,1758,1759)
< 0.08 h
I g
- 11. Reactor Mode Switch in Shutdown Position (C72A-SI)
NA i
I g
- 12. Manual Scram (C72A-S3 A,B)
NA re g
- Neutron detectors are exempt from response time testing. Response time shall be measured from detector output or input of first electronic component in channel.
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}j TABLE 4.3.1-1 (Continu:d)
REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS
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i E
j y2 CHANNEL OPERATIONAL g
FUNCTIONAL UNIT CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH I
o AND INSTRUMENT NUNBER CHECK TEST CALIBRATION SURVEILLANCE REQUIRED M
- 8. Scram Discharge Volume Water f
Level-- High NA Q
R 1, 2, 5 H
(Cl2-LSH-N013 A,B,C,D)
(Cl2-LSH-4516A,B,C,D) f j
w
- 9. Turbine Stop Valve - Closure NA M
R(h) g (EHC-SVOS-IX,2X,3X,4X) s h
- 10. Turbine Control Valve Fast
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Closure, Control Oil Pressure -
Low (EHC-PSI.-1756,1757,1758,1759)
NA M
R 1
- 11. Reactor Mode Switch in Shutdown NA R
NA
. --1, 2, 3, 4, 5
]
g Position (C72A-SI) li 4
y
- 12. Manual Scram NA Q
NA 1,2,3,4,5
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Ii (C72A-S3A,B) co l]
a.
Neutron detectors may be excluded from CHANNEL CALIBRATION.
j b.
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to start-up, if nc-t performed within thh previous 7 days.
d The IRM channels shall be compared to the APRM channels and the SRM instruments for overlap during each c.
start-up, if not performed within the previous 7 days.
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d.
When changing from CONDITION 1 to CONDITION 2, perform the required surveil' lance within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> i
af ter entering CONDITION 2.
e.
This calibration shall consist of the adjustment of the APRM readout to conform to the power values calculated by a heat balance during CONDITION 1 when THERMAL POWER _> 25% of RATED THERMAL POWER.
to conform to a 1
f
. This calibration shall consist of the adjustment of the APRM flow-blased setpoint f
r:
calibrated flow signal.
,j g
g.
The LPRMs shc11 be calibrated at least once per effective full power month (EFPM) using the TIP system.
l g
h.
This calibration shall consist of a physical inspection and actuation of these position switches.
d g
1.
Instrument alignment using a standard current source.
j
- j. Calibration using a standard radiation source.
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A TABLE 3.7.5-1 (Cor.tinutd)
(
SAFETY-RELATED flYDRAULIC SNUBBERS *
- o h
SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT NO.
ON, IDCATION AND ELEVATION INACCESSIBLE ZONE **
TO REMOVE O
Reactor Water Cleanup System r
I 2G31-ISS3 Drywell 54' A
No No E
.N Condensate Drains System N
2821-51SS103 Drywell 29' I
No No
[
SISS105 26' I
No No SISS106 18' I
No No 51SS109 31' I
No No SISSill 28' I
No No i
SISSil3 23' I
No No 51SSil5 24'
\\
I No No 51SS118 24' I
No No liigh Pressure Coolant Injection System l
t2 2E41-4SS44 Drywell 40' I
No No 4SS45 35' I
No i
No y
4SS47 40' I
No No i
G 4SS49 37' I
No No 4SS50 40' I
No No 4SS51 30' I
No No i
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