ML20125C591
| ML20125C591 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 05/23/1985 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Carolina Power & Light Co |
| Shared Package | |
| ML20125C594 | List: |
| References | |
| DPR-62-A-109, DPR-71-A-082 NUDOCS 8506120091 | |
| Download: ML20125C591 (12) | |
Text
__
[per og UNITED STATES E
.g NUCLEAR REGULATORY COMMISSION D
j WASHING TON, D. C. 20555
~s...../
CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-325 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 82 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 July 29, 1982, as supplemented August 30, 1984 and January 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 (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 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 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:
B30 $
i
.. 2.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 82, 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 Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 23,1985
.a p.
ATTACHMENT TO LICENSE AMENDMENT NO. 82 FACILITY OPERATING LICENSE NO. DPR-71 DOCKET No. 50-325 Revise the Appendix A Technical Specifications as follows:
Remove Insert 3/4 3-32a 3/4 3-32a 3/4 3-35a 3/4 3-35a 3/4 3-38b 3/4 3-38b
l (BSEP-1-61)
TABLE 3.3 3-1 (Continued) 3 EMERCENCY CORE COOLINC SYSTEM AC11JATION INSTRUENTATION Eg MINIMLBt NtBfBER APPLICABLE ca OPERABLE CHANNELS OPERATIONAL k
TRIP FUNCTION AND INSTRUMENT NIBfBER PER TRIP SYSTEM CONDITIONS ACTION n
e AUTOMATIC DEPRESSURIZATION SYSTEM (Continued)
Ey c.
Reactor Vessel Water Level - Iow, Level 1 1
1,2,3 30 (B21-LT-NO42A,5)
(B21-LTM-NO42A-1,B-1) d.
ADS Timer 1
1,2,3 31 (821-TDPU-K5A,5)
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 E11-PS-N020A,B,C,D) w g.
Bus Power Monitori 1/ bus 1, 2, 3 32 2,
(B21-K1A,B)
L"s APPLICABLE TOTAL NO.
CHANNELS MINIMIM CHAIAIELS 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, Device Number 27/59E k
b.
4.16 kv Emergency Bus 3/ bus 2/ bus 2/ bus 1,2,3,4##,58#
35 E.
Undervoltage (Degraded R
Voltage) Device Number 27/DV E
z
- Not applicable when two core spray system subsystems are OPERABLE per Specification 3.5.3.1.
- Provides signal to HPCI pump suction valves only.
m N
- Alarm only.
1
)
(BSEP-1-61)
TABLE 4.3.3-1 (Continued)
EMERCENCY CORE COOLING SYSTEM ACTUATIOIf INSTRtMENTATION SIRVEILLAIICE REQUIREMENTS es 58 CHAINIEL OPERATICIIAL h
CHANIIEL FUISCTIONAL CHAINIEL COIIDITIONS IN WHICH TRIP FUISCTION AND INSTRUMENT NtMBER CHECK TEST CALIBRATIOIl SURVEILLABICE REQUIRED R
5.
ID3S OF POWER c:
5 a.
4.16 kv Emergency Bus NA NA R
1, 2, 3, 4*, 5*
H Undervoltage (Loss of
~
Voltage) Relay Type IAV53K, Device Number 27/59E b.
4.16 kv Emergency Bus NA M
R 1, 2, 3, 4*, 5*
i Undervoltage (Degraded Voltage)
Device Number 27/DV U
Y (a) The transmitter channel check is satisfied by the trip unit channel check.
A separate transmitter check is not required.
(b) Transmitters are exempted from the monthly channel calibration.
N a,
%.9
TABIE 3-3.3-2 (Continued)
EMERCENCY CORE C00LINC SYSTDI ACTUATION INSTRIBGENTATION SETPOINTS as E
ALLOWABLE TRIP FUNCTION.JD INSTRUMENT N13fBER TRIP SETPOINT VALUE N
7:
AUTOMATIC DEPRESSURIZATION SYSTEM (Continued) e g
e.
Core Spray Pump Discharge Pressure - High 3 100 psig 3 100 psig g
(E21-PS-N008A,8 and E21-PS-N009A,5) f.
RHR (LPCI MODE) Pump Discharge Pressure - High 3 100 psig 3 100 psig (E11-PS-N016A,B,C,D and E11-PS-N020A,B,C,D) g.
Bus Power Monitor NA NA (B21-KIA,B) 5.
LOSS OF POWER wy a.
4.16 kv Emergency Bus Undervoltage a.
4.16 kv Basis - 3430 1 172 volts (Loss of Voltage)# Relay Type IAV53K, b.
120 v Basis - 98 1 4.9 volts i
w 4,
Device Number 27/59E c.
< 1.575 sec. at 0 volts i
E b.
4.16 kv Emergency Bus Undervoltage a.
4.16 kv Basis - 3727 i 9 volts 3727 1 21 volts (Degraded Voltage) b.
120 v Basis - 106.5 i 0.25 volts 106.5 i 0.60 volts Device Number 27/DV c.
10 1 0.5 se:. time delay 10 i 1.0 sec. time delay l
N k
i This is an inverse time delay voltage relay. The relay will not trip for voltages greater than the trip setpoint.
I 5
For voltages less than the trip setpoint allowable values are determined by the inverse time characteristic.
l E
- Vessel water levels refer to REFERENCE LEVEL ZERO.
- Suppression chamber water level zero is the torus centerline minus 1 inch.
z r
pa a%,,
h UNITED STATES
_8, t
'k NUCLEAR REGULATORY COMMISSION o
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. 109 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)datedJuly 29, 1982, as supplemented August 30, 1984 and January 18, 1985, complies with the standards and requirements of the Atomic Energy Act cf 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 (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 Comission's regulations and all applicabie 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.109, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Soecifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 4:'.^
Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 23, 1985 l
l l
6 I
ATTACHMENT TO LICENSE AMENDMENT NO. 109 FACILITY OPERATING LICENSE NO. DPR-62 DOCKET NO. 50-324 l
Revise the Appendix A Technical Specifications as follows:
Remove Insert 3/4 3-32 3/4 3-32 3/4 3-35a 3/4 3-35a i
3/4 3-38a 3/4 3-38a l
l l
l l
l I
L-
(BSEP-2-56) g TAB M 3.3.3-1 (Continued)
Ey EMERCENCY CORE COOLING SYSTEM ACTUATION INSTRUIN3fTATION E
M MINIMtM NLBIBER APPLICABLE OPERABM CHARAIELS OPERATIONAL g
TRIP FIRfCTION AND INSTRUIENT NLMBER PER TRIP SYSTEM CONDITIOIIS ACTION 4
AUTOMATIC DEPRESSURIZATION SYSTEM (Continued) y c.
Reactor Vessel Water Level - Iow, 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-KSA,B)
Core Spray Pump Discharge Pressure - High (Permissive) 2 1,2,3 31 e.
(E21-PS-N008A,8 and E21-PS-N009A,B) f.
RHR (LPCI MODE) Pump Discharge Pressure - High (Permissive) 2epump 1, 2, 3 31 (E11-PS-N016A,B,C,D and m
E11-PS-N020A,B,C,D) g.
Bus Power Monitori 1/ bus 1, 2, 3 32 (B21-K1A,B)
APPLICABLE TOTAL NO.
CHAIBIELS MINIMIM CHAINIELS OPERATICIIAL FUNCTICIfAL UNIT OF CHANNELS TO TRIP OPERABLE CONDITIOIfS ACTION 5.
IDSS OF POWER a.
4.16 kv Emergency Bus 1/ bus 1/ bus 1/ bus 1,2,3,4##,5#
34 g
Undervoltage (Loss of
'y Voltage) Relay Type IAV53K, i
Device Number 27/59E k
b.
4.16 kv Emergency Bus 3/ bus 2/ bus 2/ bus 1,2,3,4##,5##
35 Undervoltage (Degraded z
Voltage) Device Number 27/DV U
e
- Not applicable when two core spray system subsystems are OPERABLE per Specification 3.5.3.1.
- Provides signal to HPCI pump suction valves only.
- Alarm only.
j
c t
l (BSEP-2-56)
I es TABLE 3.3.3-2 (Continued)
- =
C E
EMBCENCY CORE (DOLINC SYSTEM ACTUATION INSTRISIENTATIM SETPOINTS S
o 7:
ALIDIABLE e
TRIP FUNCTION AND INSTEUM NT NtBIBER TRIP SETPOINT VALUE c3 AUTOMATIC DEPRESSURIZATION SYSTEM (Continued) 4 Core Spray Pump Discharge Pressure - High 3 100 psig 3 100 psig e.
(E21-PS-N008A,5 and E21-PS-N009A,5) f.
RHR (LPCI MODE) Pump Discharge Pressure - High 3 100 psig 3 100 psig (E11-PS-N016A,8,C,D and E11-PS-N020A,B,C,D) 3 Bus Power Monitor NA NA (B21-KIA,B)
~s-5.
LOSS OF POWER 0
4.16 kv Emergency Bus Undervoltage a.
4.16 kw Basis - 3430 1 172 volts y
a.
(Imss of Voltage)# Relay Type IAV53K, b.
120 v Basis - 98 i 4.9 volts Device Number 27/59E c.
5 1.575 sec. at 0 volts i
b.
4.16 kv Emergency Bus Undervoltage a.
4.16 kv Basis - 3727 i 9 volts 3727 i 21 volts (Degraded Voltage) b.
120 v Basis - 106.5 1 0.25 volts 106.5 i 0.60 volts l
Device Number 27/DV c.
10 1 0.5 sec. time delay 101 1.0 sec. time delay I l
D l
e i
a" t
- This is an inverse time delay voltage relay. The relay will not trip for voltages greater than the trip setpoint.
z
?
For voltages less than the trip setpoint, allowable values are determined by the inverse time characteristic.
l l
- Vessel water levels refer to REFERENCE LEVEL ZEBO.
S
- Suppression chamber water level zero is the torus centerline minus 1 inch.
l
(BSEP-2-56) g TABLE 4.3.3-1 (Coatimmed)
Eg EMERCENCY CORE ODOLING SYSTEM ACTUATION INSTRIMENTATION SERVEILIANCE Mm3IREMENTS E
M CHANNEL OPERATIONAL 8
CHAINfEL FUNCTIONAL ruassMFL COMITIONS IN 1ARICH g
TRIP FUNCTION AND INSTRUtENT MIMRER CHECK TEST CALIBRATICII SURVEILLAllCE REQUIRED G
5.
IDSS OF POWER y
a.
4.16 kv Emergency Bus NA NA R
1, 2, 3, 4*, 5*
Undervoltage (Loss of Voltage) Relay Type IAV53K, Device Number 27/59E b.
4.16 kv Emergency Bus NA M
R 1, 2, 3, 4*, 5*
l Undervoltage (Degraded Voltage)
,g Device Number 27/DV Yu er
(a) The transmitter charnel check is satisfied by the trip unit channel check.
A separate transmitter check is not required.
(b) Transmitters are exempted from the monthly channel calibration.
l
.E
.