ML20154Q681
| ML20154Q681 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 03/13/1986 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | Carolina Power & Light Co |
| Shared Package | |
| ML20154Q685 | List: |
| References | |
| DPR-62-A-120, DPR-71-A-095 NUDOCS 8603210255 | |
| Download: ML20154Q681 (14) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION j
g WASHINGTON, D. C. 20555
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CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-325 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 95 License No. DPR-71 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Carolina Power & Light Company (the licensee) dated August 20, 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 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 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.
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 j
hereby amended to read as follows:
)
i I
l 8603210255 860313 PDR ADOCK 05000324 P
PDR i
' (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 95, 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 NUCLEAR REGULATORY COMMISSION
)
AV Daniel R. Muller, Director BWR Project Directorate #2 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: March 13,1986 9
x r
ATTACHMENT TO LICENSE AMENDMENT NO. 95 FACILITY OPERATING LICENSE NO. DPR-71 DOCKET N0. 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 3-31 i
3/4 3-32 3/4 3-32a 3/4 3-33
(BSEP-1-65) g TABLE 3.3.3-1
&g EMERCENCY CORE COOLINC SYSTEM ACTUATION INSTRUMENTATION M
Pt MINIMUM NUMBER APPLICABLE OPERABLE CHANNE OPERATIONAL g
TRIP FUNCTION AND INSTRUMENT NUMBER PER TRIP SYSTEM CONDITIONS ACTION 4
1.
CORE SPRAY SYSTEM a.
Reactor Vessel Water Level - Low, Level 3 2
1,2,3,4,5 30 (B21-LT-NO31A,B,C,D)
(B21-LTS-NO31A-4,B-4,C-4,D-4) b.
Reactor Steam Dome Pressure - Low (Injection Permissive)
,2 1,2,3,4,5 31 (B21-PT-N021A,B,C,D)
(B21-PTS-NO21A-2,B-2,C-2,D-2)
.c.
Drywell Pressure - High 2
1,2,3 30 R
(E11-PT-N011A,B,C,D)
(Ell-PTS-N011A-2,B-2,C-2,D-2) d.
Time Delay Relay 1
1,2,3,4,5 31 (E21-K16A,B)
Id) 1/ bus 1,2,3,4,5 32 e.
Bus Power Monitor (E21-KIA,B) 2.
LOW PRESSURE COOIANT INJECTION MODE OF RHR SYSTEP' a.
Drywell Pressure - High 2
1,2,3 30 (E11-PT-N011A,B,C,D)
(E11-PTM-N011A-1,B-1,C-1,D-1) b.
Reactor Vessel Water Level - Low, Level 3 2
1, 2, 3, 4(b),S 30 ID) g (B21-LT-NO31A,B,C,D) 8.
(B21-LTS-NO31A-4,B-4,C-4,D-4)
' Reactor Vessel Shroud Level (Drywell Spray Permissive) 1 1, 2, 3, 4(b), $(b) 31 c.
(821-LT-NO36 and B21-LT-NO37) f (B21-LTM-NO36-1 and B21-LTM-NO37-1) d.
Reactor Steam Dome Pressure - Low (Injection Permissive)
?
(B21-PT-NO21A,B,C,D)
(B21-PTM-N021A-1,B-1,C-1,D-1)
(B21-PTS-N021A-2,B-2,C-2,D-2) ui 1, 2, 3, 4((b)b), $((b) 1.
RHR Pump Start and LPCI Injection Valve Actuation 2
31 b) 2.
Recirculation Loop Pump Discharge Valve Actuation 2
1,2,3,4
,5 31
(BSEP-1-65) as g
TABLE 3.3.3-1 (Continued) ui EMERCENCY CORE COOLINC SYSTEM ACTUATION INSTRUMENTATION A
HINIEUM NUMBER APPLICABLE OPERABLE CHANNE OPERATIONAL l
g TRIP FUNCTION AND INSTRUMENT NUMBER PER TRIP SYSTEM CONDITIONS ACTION I rH LOW PRESSURE COOLANT INJECTION MODE OF RHR SYSTEM (Contir.ued)
~
l e.
RHR Pump Start - Time Delay Relay 1
1, 2, 3, 4(b), 5(b) 31 (STR-1Al,2 and STR-1B1,2) f.
Bus Power Monitor (d)
,,1/ bus 1, 2, 3, 4(b), $(b) 32 (Ell-K106A,B) 3.
HICH PRESSURE COOLANT INJECTION SYSTEM w
a.
Reactor Vessel Water Level - Low, Level 2 2
1,2,3 30 Y
(B21-LT-NO31A,B,C,D) d (B21-LTS-NO31A-2,B-2,C-2,D-2) b.
Drywell Pressure - High 2
1,2,3 30 (Ell-PT-N0llA,B,C,D)
(Ell-PTS-N0llA-2,B-2,C-2,D-2) l IC) c.
Condensate Storage Tank Level - Low 2
1, 2, 3 33 (E41-LS-N002, E41-LS-N003) d.
Suppression Chamber Water Level - High 2(c) 1, 2, 3 33 l
( E41-LSH-N015 A, B) 4 Bus Power Monitor (d) 1/ bus 1, 2, 3 32 e.
f (E41-K55 and E41-K56) 4.
AUTOMATIC DEPRESSURIZATION SYSTEM N
a.
ADS Inhibit Switch 1
1,2,3 36 g
(B21-CS-S5A,B) b.
Reactor Vessel Water Level - Low, Level 3.
2 1, 2, 3 30 (B21-LT-NO31A,B,C,D) w (B21-LTS-NO31A-3,B-3,C-3,D-3) un
(BSEP-1-65)
TABLE 3.3.3-1 (Continued)
EMERCENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION E
MINIMUM NUMBER APPLICABLE y
OPERABLE CHANNE g OPERATIONAL TRIP FUNCTION AND INSTRUMENT NUMBER PER TRIP SYSTEM CONDITIONS ACTION AUMMATIC DEPRESSURIZATION SYSTEM (Continued)
Ey c.
Reactor Vessel Water Level - Low, Level 1 1
1,2,3 30 (B21-LT-NO42A,B)
(B21-LTM-NO42A-1,B-1) d.
ADS Timer 1
1,2,3 31 (B21-TDPU-K5A,B)
Core Spray Pump Discharge Pressure - High (Permissive) 2 1,2,3 31 e.
(E21-PS-N008A,B and E21-PS-N009A,B) f.
RHR (LPCI MODE) Pump Discharge Pressure - High (Permissive) 2/ pump 1,2,3 31 (E11-PS-N016A,B,C,D and u2 E11-PS-N020A,B,C,D)
Id) 1/ bus 1, 2, 3 32 Y*
g.
Bus Power Monitor M
(B21-K1A,B) na APPLICABLE TOTAL NO.
CHANNELS HINIMUM CHANNELS OPERATIONAL FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE CONDITIONS ACTION 5.
IDSS OF POWER a.
4.16 kv Emergency Bus 1/ bus 1/ bus 1/ bus 1,2,3,4(*),5(*)
34 Undervoltage (Loss of Voltage) Relay Type IAV53K, f
Device Number 27/59E E.
b.
4.16 kv Emergency Bus 3/ bus 2/ bus 2/ bus 1,2,3,4(*),5 *)
35 I
5 Undervoltage (Degraded s
E Voltage) Device Number 27/DV
f (BSEP-1-65)
TABLE 3.3.3-1 (Continued)
EMERCENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION ACTION With the number of OPERABLE channels less than required by the ACTION 30 Minimum OPERABLE Channels per Trip System requirement:
For one trip system, place at least one inoperable channel a.
in the tripped conditton within one hour or declare the associated ECCS inoperable.
b.
For both trip systems, declare the associated ECCS 1
With the number of OPERABLE channels less than required by the ACTION 31 Minimum OPERABLE Channels per Trip System requirement, declare i
the associated: ECCS inoperable.
With the number of OPERABLE channels less than required by the ACTION 32 Minimum OPERABLE Channels per Trip System requirement, verify bus power availability at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or declare the associated ECCS inoperable.
I ACTION 33 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement, place at least one inoperable channel in the tripped condition within one hour or declare the HPCS system inoperable.
ACTION 34 - With the number of OPERABLE channels less than the Total Number of Channels, d-1.are the associated emergency diesel generator 1
inoperable and '.ake the ACTION required by 3pecification 3.8.1.1 or 3.8.1.2, as appropriate.
ACTION 35 - With the number of OPERABLE channels one less than the Total Number of Channels, place the inoperable channel in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />; operation may then continue until 4
performance of the next required CHANNEL FUNCTIONAL TEST.
With the number of OPERABLE channels less than required by the ACTION 36 Minimum OPERABLE Channels per Trip Function requirement, restore i
the inoperable channel 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 declare the associated ECCS inoperable.
i NOTES I
A channel may be placed in an inoperable status for up to two hours for
]
a.
required surveillance without placing the trip system in the tripped l
l conditions, provided at least one OPERABLE channel in the same trip system is monitoring the affected parameter.
b.
Not applicable when two core spray system subsystems are OPERABLE per specification 3.5.3.1.
Provides signal to HPCI pump suction valves only.
c.
d.
Alarm only.
Required when ESF equipment is required to be OPERABLE.
e.
i BRUNSWICK - UNIT 1 3/4 3-33 Amendment No. 87, 95
f* "*\\
UNITED STATES g
k NUCLEAR REGULATORY COMMISSION g
j WASHINGTON, D. C 20555 i
- /
CAROLINA POWER & LIGHT COMPANY DOCKET N0. 50-324 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 120 License No. DPR-62 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Carolina Power & Light Company (the licensee) dated August 20, 1985, 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 j
provisions of the Act, and the rules and regulations of the Commission; 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 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 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-62 is hereby amended to read as follows:
l l
. (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.120, 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 NUCLEAR REGULATORY COMMISSION
~
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~
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Daniel R. Muller, Director BWR Project Directorate #2 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: March 13, 1986 1
O I
i ATTACHMENT TO LICENSE AMENDMENT N0. 120 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.
4 Pages i
3/4 3-31 e
3/4 3-32 3/4 3-32a 3/4 3-33 1
I I
e 4
-,,-r
.n--..-
_._,-..-..n.
(BSEP-2-60) i i
J TABLE 3.3.3-1 Ey EMERCENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION M
M MINIMIM NUMBER APPLICABLE 8
OPERABLE CHANNE OPERATIONAL g
i TRIP FUNCTION AND INSTRUMENT NUMBER PER TRIP SYSTEM CONDITIONS ACTION I
~
1.
CORE SPRAY SYSTEM g
a.
Reactor Vessel Water Level - Low, Level 3 2
1,2,3,4,5 30 (B21-LT-NO31A,B,C,D)
(B21-LTS-NO31A-4,B-4,C-4,D-4) b.
Reactor Steam Dosse Pressure - Low (Injection Permissive) 2 1,2,3,4,5 31 4
)
(B21-PT-NO21A,B,C,D)
(B21-PTS-NO21A-2,B-2,C-2,D-2) c.
Drywell Pressure - High 2
1, 2, 3 30 w)
(Ell-PT-N011A,B,C,D)
(E11-PTS-NOl1A-2,B-2,C-2,D-2) w h
d.
Time Delay Relay 1
1,2,3,4,5 31 (E21-K16A,B)
Bus Power Monitor (d) 1/ bus 1,2,3,4,5 32 l
i e.
I (E21-K1A,B)
I l
2.
IAW PRESSURE COOLANT INJECTION MODE OF RHR SYSTEM a.
Drywell Pressure - HiBh 2
1,2,3 30 (Ell-PT-N0llA,B,C,D) y (Ell-PTM-NOllA-1,B-1,C-1,D-1)
I b.
Reacter Vessel Water Level - Low, Level 3 2
1, 2, 3, 4(b), 5(b) 30
{
(B21-LT-NO31A,B,C,D)
(B21-LTS-NO31A-4,B-4,C-4,D-4) g l
' Reactor Vessel Shroud Level (Drywell Spray Permissive) 1 1, 2, 3, 4(b), 5(b) 3g E,
c.
4 (B21-LT-NO36 and 821-LT-NO37) z (B21-LTM-NO36-1 and B21-LTM-NO37-1)
=
l 7
d.
Reactor Steam Dome Pressure - Low (Injection Permissive)
(B21-PT-NO21A,B,C,D) m
?
y (B21-PTM-NO21A-1,B-1,C-1,D-1) 1 (B21-PTS-NO21A-2,B-2,C-2,D-2) 1, 2, 3, 4((b)b), 5((b) b)
31 1.
RHR Pump Start and LPCI Injection Valve Actuation 2
2.
Recirculation Loop Pump Discharge Valve Actuation 2
1,2,3,4
,5 31
l l
(BSEP-2-60)
=
l TABLE 3.3.3-1 (Continued)
EMERCENCY CORE COOLINC SYSTEM ACTUATION INSTRUMENTATION R
I MINIMUM NUMBER APPLICABLE g
OPERABLE CHANNE OPERATIONAL g
y TRIP FUNCTION AND INSTRUMENT NUMBER PER TRIP SYSTEM CONDITIONS ACTION l
LOW PRESSURE COOLANT INJECTION MODE OF RiiR SYSTEM (Continued) l e.
RHR Pump Start - Time Delay Relay 1
1, 2, 3, 4(b), $(b), 33 (STR-2A1,2 and STR-2B1,2) f.
Bus Power Monitor (d) il/ bus 1, 2, 3, 4(b), $(b) 32 (E11-K106A,B) 3.
HICH PRESSURE COOLANT INJECTION SYSTEM u
N Reactor Vessel Water Level - Low, Level 2 2
1,2,3 30 a.
y (B21-LT-NO31A,B,C,D) g (B21-LTS-NO31A-2,B-2,C-2,D-2) b.
Drywell Pressure - High 2
1,2,3 30 (Ell-PT-N0llA,B,C,D)
(Ell-PTS-NOllA-2,B-2,C-2,D-2) c.
Condensate Storage Tank Level - Low 2(c) 1, 2, 3 33 (E41-LS-N002, E41-LS-N003) d.
Suppression Chamber Water Level - liigh 2(c) 1, 2, 3 33 (E41-LS H-N015 A, B)
Sus Power Monitor (d) 1/ bus 1, 2, 3 32 e.
k (E41-K55 and E41-K56) 4.
AUTOMATIC DEPRESSURIZATION SYSTEM N
Drywell Pressure - High, coincident with 2
1,2,3 30 a.
g (Ell-PT-N010A,B,C,D)
(Ell-PTM-NO10A-1,B-1,C-1,D-1) h,E b.
Reactor Vessel Water Level - Low, Level 3 2
1,2,3 30 (B21-LT-NO31A,B,C,D) f (B21-LTS-NO31A-3,B-3,C-3,D-3).
.D
(BSEP-2-60) g TABLE 3.3.3-1 (Continued)
E m
EMERCENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION N
O MINIHUM NUMBER APPLICABLE 8
OPERABLE CHANNE OPERATIONAL TRIP FUNCTION AND INSTRUMENT NUMBER PER TRIP SYSTEM CONDITIONS ACTION ~
~
- 1 AUTOMATIC DEPRESSURIZATION SYSTEM (Continued) g c.
Reactor Vessel Water Level - Low, Level 1 1
1,2,3 30 (B21-LT-NO42A,B)
(B21-LTM-NO42A-1,B-1) d.
ADS Timer 1
1, 2, 3 31 (B21-TDPU-K5A,B)
Core Spray Pump Discharge Pressure - High (Permissive) 2 1,2,3 31 e.
(E21-PS-N008A,B and E21-PS-N009A,B) w N
f.
RHR (LPCI MODE) Pump Discharge Pressure - High (Permissive) 2/ pump 1, 2, 3 31 y
(E11-PS-N016A,B,C,D and Ell-PS-N020A,B,C,D) l Bus Power Monitor (d) 1/ bus 1, 2, 3 32 g.
(B21-KlA,B)
APPLICABLE TOTAL NO.
CHANNELS MINIMUM CHANNELS OPERATIONAL FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE CONDITIONS ACTION 5.
IASS OF POWER 1,2,3,4 '),5 ")
34 I
I a.
4.16 kv Emergency Bus 1/ bus 1/ bus 1/ bus y
Undervoltage (Loss of Voltage) Relay Type IAV53K, sDevice Number 27/59E g
k b.
4.16 kv Emergency Bus 3/ bus 2/ bus 2/ bus 1,2,3,4(e) $(e) 35 z
Undervoltage (Degraded Voltage) Device Number 27/DV 5?
i O
I O
(BSEP-2-60)
TABLE 3.3.3-1 (Continued)
EMERGENCY CORE C00LINC SYSTEM ACTUATION INSTRUMENTATION ACTION ACTION 30 -
With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirements For one trip system, place at least one inoperable a.
channel in the tripped condition within one hour or declare the associated ECCS inoperable.
b.
For both trip systems, declare the associated ECCS inoperable.
ACTION 31 -
With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement,
.i declare.the associated ECCS inoperable.
ACTION 32 -
With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement, verify' bus power availability at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or declare the associated ECCS inoperable.
ACTION 33 -
With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip, System requirement, place at least one inoperable channel in the tripped condition within one hour or declare the HPCS system inoperable.
i ACTION 34 -
With the number of OPERABLE channels less than the Total Number of Channels, declare the associated emergency diesel
~
generator inoperable and take the ACTION required by Specification 3.8.1.1 or 3.8.1.2, as appropriate.
ACTION 35 -
With the number of OPERABLE channels one less than the Total Number of Channels, place the inoperable channel in the tripped condition wichtn 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />; operation may then continue until performance of the next required CHANNEL FUNCTIONAL TEST.
2 NOTES A channel may be placed in an inoperable status for up to two hours for a.
required surveillance without placing the trip system in the tripped condition, provided at least one OPERABLE channel in the same trip system is monitoring the affected parameter.
b.
Not applicable when two core spray system subsystems are OPERABLE per Specification 3.5.3.1.
i Provides signal to HPCI pump suction valves only.
c.
d.
Alarm only.
Required when ESF equipment is required to be OPERABLE.
e.
l BRUNSWICK - UNIT 2 3/4 3-33 Amendment No. 5/,120
.