ML20133G324
| ML20133G324 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 07/30/1985 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Carolina Power & Light Co |
| Shared Package | |
| ML20133G326 | List: |
| References | |
| DPR-71-A-087 NUDOCS 8508080638 | |
| Download: ML20133G324 (8) | |
Text
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UNITED STATES
[
'i NUCLEAR REGULATORY COMMISSION L
-l W ASHINGTON,0. C. 20555 t
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CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-325 BRUNSWICK STEAM ELECTRIC PLANT, UNIT I AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 87 f
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 March 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; 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 i
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 hereby amended to read as follows:
1 8500080638 850730 i
PDR ADOCK 05000325 P
PDR 4
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2.
Technical Specifications 1
The Technical dpecifications contained in Appendices A and B, as revised through Amendment No. 87, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications, i
j 3.
This license amendment is effective as of the date of its issuance.
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FOR THE NUCLEAR REGULATORY C0tNISSION r
/
Ah Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing i
Attachment:
1 Changes to the Technical 1
Specifications I
Date of Issuance: July 30,1985 l
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i ATTACimENT TO LICENSE AMENDMENT NO. 87 i
FACILITY OPERATING LICENSE NO. DPR-71 l
i DOCKET NO. 50-325 l
1 f
1 Replace the following pages of the Appendix A Technical Specificaitons l
with the enclosed pages. The changed areas are indicated by vertical lines.
j Pages I
j 3/4 3-32 3/4 3-33 l
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3/4 3-35 3/4 3-38a 3/4 3-38b i
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( BSEP-1 -46)
TABl.E 3.3.3-1 (Centinuc<!)
g E}g EHERCENCY CORE COOLING SYSTEM ACTilArturi,If4_STIMiljtirAT10N,
!!Ilif fillti tilfl8ER APPLICABl.E OPERAllt.l? CilAfJfiEl.S OPERA rlorial, I
G TRIP Fl!NCTION AND INSTRiftlENT NUflBER PER TRIP SYSTEM CorlDi r!Of!S ACTION 5
LOW PRESSIIRE C001.Ali{lNJECrl0N 190DE OF RIIR SYSTEM (Continned) e.
RilR Pump Start - Tline Delay Relay 1
1, 2, 3, 4*, 5
- 31 (STR-IAl.2 and S TR-lill,2) f.
Bus Power Monitors 1/ bus 1, 2, 3, 4*, 5*
32
( E l l -K I O 6,\\,5) 3.
IIICil PRES $11RE C001. ANT INJECTION SYSTEM mS Reactor Vessel Water Level - Low, i.evel 2 2
1, 2, 3 30 a.
i Sf (H21-LT-NO31A,B,C,D) g (B21-LTS-NO31A-2,5-2,C-2,D-2) b.
Drywel1 Pressure - liigh 2
1, 2, 3 30 (1s t 1-PS-N0l l A, B,C.D)
( E l l-PTS-tki l l A-2, B-2, C-2,D-2) c.
Condensate Storage Tank Level-, low 2**
1, 2, 3 33 (E 41-I.S-!I002, E41-LS-N003) d.
Suppression Chainber Water level - Iligh 2**
1, 2, 3 33
( E 41-LS:1-N015 A, B) e.
Bus Power Monitor #
1/ bus 1, 2, 3 32 h
(E41-K55 and E41-K56) a 4.
AUT0!!ATIC dei'RESSURI7.ATION SYSTEM a.
' ADS Inhibit Switch 1
1, 2, 3 36
- s" "g
(lill-CS-55 A, B) b.
React..r V. ssel Water level - Iow, level 3 2
1, 2, 3 30 (Is21 -1.1-N011 A, B,C D)
( B21 -LTS-NO31.1-3, B-3, C-3,D-3) 5
( B SEP 46)
T3.BLE 3.3.3-1 (Continued)
EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION ACTION ACTION 30 With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement:
a.
For one trip system, place at least one inoperable 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, declare the associated ECCS inoperable.
ACTION 32 With the number of OPERABLE channels less than required by the
>Rninum 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.
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 within I hour; operation may then continue until performance of the next required CHANNEL FUNCTIONAL TEST.
ACTION 36 With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, restare 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 w.
BRUNS'JICK - UNIT I 3/4 3-33 Amendment No. 87
(llSEP-1 -46)
TABLE 3.3.3-2 (Cont inued) m C;
M EMERGEt!CY CORE COOLING SYSTEtt ACTilATIOff INSTR _I_R_IE_NT.A_T.i n_t_i._ SET _.P_O_IN_T._S_
g s
Al.LOWABl.E l
TRIP FUNCTION AND INSTRiitlENT NUMBER TRIP SMTPOINT V Al.IIE l
c:
N LOW PRE _S_S_U_RE C00_1_.A_NT ItLIECTION tt01)E OF RilR SYSTEM (Continited) g RilR Pump Start - Tline Delay Relay 9<t< 11 seconds 9<t < 11 seconds
~
c.
(STR-1Al.2 ani STR-1Bl.2) f.
Bus Power !!onitor NA
!!A
( E l l-K 10 6A, B) 3.
111011 PRESS 3E C001. ANT INJECTION SYSTEM Reactor Vessel llater Level - Low, Level 2
-->& 112 inches *
'-> + 112 inches
- a.
( H21 -1.TS-NO31 A-2, B-2,C-2, D-2) b.
Drywell Pressure - Iligh
< 2 psig
< 2 psig y
( Ell-P rS-N0 l l A-2,II-2,C-2,D-2) c.
Condensate Storage Tank Level - Low
> 23 feet 4 inches
> 23 feet 4 inches (E41-I.S-N002; E41-LS-N003) d.
Suppression Chamber Water I,evel - liigh
< -2 feet **
< -2 f ec t* *
( C 41 -1. Sit-NO I S A, B) c.
Bus Power !!anitor NA NA (E41-K55 anct E41-K5 6) 4.
AUTortATIC Ill:Pl:ESSilRl/.ATION SYSTEtt 9
a.
ADS Inhibit Switch NA NA y
(H21-CS-SSA,B) 8.
b.
Reactor Vessel Water Level - Low, Level 3
> + 2.5 inches *
> + 2.5 inches
- m
( !!21 -1.TS-NO 31 A-3, B-3, C-3,D-3 )
E Reactor Vessel Water Level - Low, Level I
> + 162. 5 i nches*
> + 162.5 inches
- c.
6
( B 21 -1.T!!-N0 42 A-1, B-1 )
5 d.
ADS Timer O
( 1,21 - rt)PU-K5 A, B)
< 120 e.econds
< 120 seconds
}
(ilSEP-l-46) l en TABLE 4.3.3-1 (Continumi)_ _.
M Et!ERGENCY CORE COOLING SYSTEM ACTilATION INSTRttIE!1TATION SilRVEIII.ANCE REllifil E,ll_I;NTS j
N-Q
- CIIANNEl,
' OPERATIONAL CilANNEL FUNCTIONAI, CIIANNEl.
CONDITIONS IN WilICil TRIP FUNCTION AND INSTRU?!ENT NtPIBER-CilECK TEST CALIllR ATION_ -
S,IIRVEILI.ANCE REQUIRED
- 4. AUT0!!ATIC DEPRESSURIZATION SYSTEM a.
ADS Inhibit Switch D(c)
R NA 1, 2, 3 (B21-CS-SSA,B) b.
Low, I.evel 3
( B21 -LT-NO3 t A, B,C,D)
N A(a)
NA R(b)
I, 2, 3 (B21-LTS-No1IA-3,B-3,C-3,D-3)
D H
H I, 2, 3 c.
w Low, Level I s
( B21 -1.T-N042 A, B)
NA(")
NA R(b) 1, 2, 3 (ll21-LTil-N0 42 A-1, B-1)
D 11 M
1, 2, 3 u
M d.
ADS Timer NA R
R 1, 2, 3 (ll21-TDPil-KS A, B) e.
. Core Spray Pump Discharge Pressure - liigh NA Q
I, 2, 3 (E21-PS-N008A,Il and E21-PS-N009A,15) f.
RilR (LPCI IIODE) Pump Discharge Pressure - liigh NA 11 Q
1, 2, 3 (Ell-PS-Nill 6A,ll,C,D and
,E l 1 -PS-NO 20 A,11,C, D) g.
Bus Power tioni tor NA R
NA 1, 2, 3 (ll21-KI A,11)
Sn
.O I
(BSEP-1-46)
E TABLE 4.3.3-1 (continued)
E h
EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS R
CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH h
TRIP FUNCTION AND INSTRUMENT NUMBER CHECK TEST CALIBRATION SURVEILLANCE REQUIRED e
5.
LOSS OF POWER t
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*
Undervoltage (Degraded Voltage) u 30 Device Number 27/DV Ys
. o.
(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.
(c) The ADS Inhibit Switches shall be maintained in the Automatic position.
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