ML20207E610
| ML20207E610 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 12/24/1986 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | Carolina Power & Light Co |
| Shared Package | |
| ML20207E612 | List: |
| References | |
| DPR-62-A-132, DPR-71-A-102 NUDOCS 8701020227 | |
| Download: ML20207E610 (10) | |
Text
\\
y/
J't NUCLEAR REGULATORY COMMISSION UNITED STATES
}.
j WASHINGTON, D. C. 20555 u
e R.....,$
e CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-525 s
BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.102 License No. DPR-71 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Carolina Power & Light Company (thelicensee)datedApril 23,.1986 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 activit'.es 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:
8701020227 861224 PDR ADOCK 05000324 P
e 9
- (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.102, are hereby incorporated in the
- license, lhe licensee 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 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION A
Daniel R. Muller, Director BWR Project Directorate #2 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: December 24, 1986 l
l L
ATTACHMENT TO LICENSE AMENDMENT NO.102 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 3-40 3/4 3-41
(BSEP-1-74)
TABLE 3.3.4-1 CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION z
MINIMUM NUMBER OF APPLICABLE Q
OPERABLE CHANNELS OPERATIONAL i
TRIP FUNCTION AND INSTRUMENT NUMBER PER TRIP SYSTEM (a)
CONDI TIONS c:
1.
APRM (CSI-APRM-CH.A,B,C,D,E,F)
H a.
Upscale (Flow Biased) 2 1
b.
Inoperative 2
1, 2, 5 c.
Downscale 2
1 d.
Upscale (Fixed) 2 2, 5 2.
ROD BLOCK MONITOR (CSI-RBM-CH.A,B) 1((f) a.
Upscale 1
f) b.
Inoperative 1
1(f) c.
Downscale 1
1 g
s~
3.
SOURCE RANCE MONITORS (C51-SRM-K600A,B,C,D) y full in (b) 1 2, 5 a.
Detecto ot b.
Upscale 1
2, 5 Inoperatig()c) 1 2, 5 c.
Downscale
]
d.
1 2, 5 Id)
(C51-IRM-K601A,B,C,D,E,F,C,H) 4.
INTERMEDIATE RANCE MONITORS a.
Detector not full in 2
2, 5 l
b.
Upscale 2
2, 5 j
g m
c.
Inoperabl 2
2, 5 e) h d.
Downscale 2
2, 5 m
5 5.
SCRAM DISCHARGE VOLUME (Cll-LSH-N013E) z a.
Water Level - liigh 1(h) 1, 2, S B) l I
=
O N
(BSEP-1-74)
TABLE 3.3.4-1 (Continued)
CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION NOTE (a) The minimum number of OPERABLE CHANNELS may be reduced by one for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in one of the trip systems for maintenance and/or testing ex:ept for Rod Block Monitor function.
(b) This function is bypassed if detector is reading >100 cps or the IRM channels are on range 3 or higher.
(c) This function is bypassed when the associated IRM channels are on range 8 or higher.
(d) A total of 6 IRM instruments must by OPERABLE.
(e) This function is bypassed when the IRM channels are on range 1.
(f) When THERMAL POWER exceeds the preset power level of the RWM and RSCS.
(g) With any control rod withdrawn.
Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.
(h) This signal is contained in the Channel A logic only.
l l
l I
i l
l BRUNSWICK - UNIT 1 3/4 3-41 Amendment No. E9,102
8 4
UNITED STATES 8
N NUCLEAR REGULATORY COMMISSION t
j WASHINGTON, D. C. 20555
\\...../
CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-324 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.132 License No. DPR-62 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Carolina Power & Light Company (thelicensee)datedApril 23, 1986 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 j
in 10 CFR Chapter I; I
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; 1
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 common defense and security or to the health and safety of the l
public; and l
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 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.132, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
Thislicenseamendmentiseffectiveasof[thedateofitsissuance shall be implemented within 60 days of issuance.
t FOR THE NUCLEAR REGULATORY COMMISSION 4
v Daniel R. Muller, D'irector BWR Project Directorate #2 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: December 24, 1986 f
I e
4 h
t t
i
(
1 k$
[
- o' s',
q t t l
s 3,.
-.---r-----
w w
v,
-r y
4---r,-w-e,
t ATTACHMENT TO LICENSE AMENDMENT NO.132 FACILITY OPERATING LICENSE'NO. DPR-62 DOCKET NO. 50-324 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 3-40 3/4 3-41 l
l l
l l
.~
(BSEP-2-71)
TABLE 3.3.4-1 Eg CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION 18g MIhIMUM NUMBER OF APPLICABLE X
OPERABLE CHANNE OPERATIONAL
)
I TRIP FUNCTION AND INSTRUMENT NUMBER PER T4 P SYSTEM CONDITIONS
$y 1.
APRM (CSI-APRM-CH.A,B,C,D,E,F) w a.
Upscale (Flow Biased) 2 1
b.
Inoperative 2
1,2,5 c.
Downscale 2
1 d.
Upscale (Fixed) 2 2, 5 2.
ROD BLOCK MONITOR (C51-RBM-CH.A,B)
I(I f) a.
Upscale 1
1(f) b.
Inoperative 1
w f}
3 c.
Downscale 1
1 3.
SOURCE RANCE MONITORS (C51-SRM-K600A,B,C,D) full in(b) 1 2, 5 Detectogot a.
b.
Upscale 1
2, 5 Inoperatig()C) 1 2, 5 c.
Downscale d.
1 2, 5 4.
INTERMEDIATE RANTE MONITORS (d)
(C51-IRM-K601A,B,C,D,E,F,C,H) a.
Detector not full in 2
2, 5 l
g b.
Upscale 2
2, 5 c.
Inoperabige) 2 2, 5 d.
Downscale 2
2, 5 5.
SCRAM DISCHARCE VOLUME (C12-LSH-NO13E) v a.
Water Level - High 1(h) 1, 2, S B) l I
N
(BSEP-2-71)
[
TABLE 3.3.4-1 (Continued)
CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION NOTE (a) The minimum number of OPERABLE CHANNELS may be reduced by one for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in one of the trip systems for maintenance and/or testing except for Rod Block Monitor. function.
(b) This function is bypassed if detector is reading >100 cps or the IRM channels are on range 3 or higher.
(c) This function is bypassed when the associated IRM channels are on range 8 or higher.
(d) A total of 6 IRM instruments must be OPERABLE.
(e) This function is bypassed when the IRM channels are on range 1.
(f) When THERMAL POWER exceeds the preset power level of the RWM and RSCS.
(g) With any control rod withdrawn. Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.
s (h) This signal is contained in the Channel A logic only.
BRUNSWICK - UNIT 2 3/4 3-41 Amendment No.83* l02