ML20128E614
| ML20128E614 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 02/03/1993 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20128E617 | List: |
| References | |
| NUDOCS 9302100525 | |
| Download: ML20128E614 (10) | |
Text
. _ _ _ _ _ _ _ _ _ _ _ _ _ - - - -
e
,#' p2 Moog'g UNITED STATES
["
g NUCLEAR REGULATORY COMMISSION E
WASHINGTON, D. C. 20555
'g.....
CAROLINA POWER & LIGliT..CDMPAflY. tL3L DOCKET NO. 50-3&5 BRUNSWIC", STEAM ELECTRIC PLANT. UNIT 1 AMENDMENT 10 f ACILITY OPERATlRG LICENSE Amendment No. 160 License No. OPR-71 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by Carolina Power & Light Company (the licensee), dated November 16, 1992, as supplemented January 25, 1993, 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; D.
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.
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:
jgg21SDoh P
o e
2 (2) Jechnical Specific 111pn1 The Technical Specifications contained in Appendices A and B, as revised through Amendment No.160, are hereby incorporated in the license.
Carolina Power & Light Company 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 30 days of issuance, FOR THE NUCLEAR REGULATORY COMMISSION
'f : ^ ='
Elinor G. Adensam, Director Project Directorate 11-1 Division of Reactor Projects - 1/11-Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 3, 1993
ATTACHMENT T0 llCENSE AMENDMENT NO.160 FACILITY OPERATING LICENSE NO. OPR-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.
Remote Pages Insert Pages 3/4 3-34 3/4 3-34 3/4 3-38 3/4 3-38 4
3 I
i
{
~
zn
'b E
M n
E TABLE 3.3.3-1 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION MINIMUM NLHBER APPLICABLE OPERABLE CHANNELS OPERATIONAL PER TRIP SYSTEM" CONDITIONS ACTION l
TRIP FUNCTION
- 1. CORE SPRAY SYSTEM Reactor Vessel Water level - Low, level 3 2
1,2,3,4,5 30 a.
b.
Reactor Steam Dome Pressure - Low (Injection Permissive) 2" 1,2,3,4,5 31 2
1, 2, 3 30
[
Drywell Pressure - High c.
1 1,2,3,4,5 31 d.
Time Delay Relay e.
Bus Power Monitor" 1/ bus 1, 2,.3, 4, 5 32
- 2. LC14 ?RESSURE COOLANT INJECTION MODE OF RHR' SYSTEM 2
1, 2, 3 30 a.
Drywell Pressure - High b.
Reactor Vessel Water Level - Low, level 3 2
1, 2, 3, 4", 5" 30 Reactor Vessel Shroud Level (Drywell Spray Permissive) 1-1, 2, 3, 4", 5" 31 c.
d.
Reactor Steam Dome Pressure - Low (Injection Permissive)
F 1.
RHR Pump Start and-LPCI Injection Valve Actuation 2
1, 2, 3, 4", 5" 31-8
[
2.
Recirculation Loop Pump Discharge Valve Actuation 2'
1, 2, 3, 4", 5" 31 1
I, 2, 3, 4", 5" 31 RHR Pump Start - Time Delay Relay e.
Y f.
Bus Power Monitor" 1/ bus 1, 2,-3, 4", 5"
-32 c.%
3
4 TABLE 3,3.3-1 (Continued)
EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION WOTES (a) A channel may be placed in an inoperable st:tus for up to two hours for required surveillance without placing the tiip 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.
1 (c) Provides signal to HPCI pump suction valves only.
(d) Alarm only.
(e) Required when E5F equipment is required to be OPERABLE.
(f) On a one-time basis, prior to start-up from the outage that began on April 21, 1992, the Minimum Number OPERABLE Channels per Trip System for une reactor steam dome pressure hw (injection permissive) trip function may be reduced, for no longer than 7 days, from two (2) channels to one (1) channel without declaring the associated ECCS inoperable in accordance with ACTION 31.
This will be done on one occasion for Unit 1 and two occasions for Unit 2.
During these periods, the following actions shall be implemented:
(1)
The inoperable channel shall be placed in the condition that will satisfy the logic for allowing injection by the associated ECCS with the reactor steam dnme pressure below 410 psig 15 psig.
(2)
Both channels in the other trip system shall be maintained OPERABLE.
(3)
The reactor vessel head vent shall be maintained in the open position.
i BRbHSWICK - UNIT 1 3/4 3-38 Amendment No. H, IM 150
4;wc-j#*f
-T LJNITED STATES :
{
- f NUCLEAR REGULATORY COMMISSION -
- W ASHINGTON, D. C. 20555 -
p
-g-CAROLINA POWER & LIGHT COMPANY. et al.
DOCKET NO. 50-324:
a, BRUNSWICK STEAM ELECTRIC PLANT. UNIT 2 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment'Noi 191 License No.uDPR-62~
1.
The Nucle'ar Regulatory Commission (the Commission) has found. that:
A. ~The application for amendment. filed by Carolina Power & Light--
Company-(the licensee), dated November 16, 1992,- as supplemented-January 25,'1993, complies with the: standards and: requirements'.of-;
the Atomic Energy Act of 1954, as amended (the Act) aud-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 thet Commission:
C.
There is reasonabl_e assurance _(i) that tho' activities authorized-by:_
this-amendment can be conducted without endangering the:he'althiand safety of the public, and (ii) that such activities-'will-be?
conducted in compliance with'the Commission's regulations;t 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;-andi E.
The issuance of this amendment is in-accordance with'10 CFR:Part 51
' of the Commission's regulations and ~all Lapplicable requirements have been satisfied.
2.
Accordingly, the license is amended _by changes'to the Technical-Specifications as l indicated in the attachment to -this license amendment;.
-and paragraph 2.C.(2) of Facility Operating Ljcense No. DPR-62 is:hereby.
amended to read as follows:
g.
=
.2..
J
. (2) Technical Specifications
]
The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 191, are hereby incorporated in the l
license.
Carolina Power & Light Company 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 irnplemented within 30 days of issuance.
FOR THE NUCLEAR RECUtATORY COMMISSION Elinor G. Adensam, Director Project Directorate !!-l Division of Reactor Projects - I/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: February 3, 1993
- r a,;
ATTACHMENT TO LICENSE AMENDMENT NO.191 FACIllTY OPERATING LICENSE N0, 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.
Remove Paoes insert Paoes 3/4 3-34 3/4 3-34 3/4 3-38 3/4 3-38 Z
- . 0.
'm m
m
L.
TABLE 3.3.3-1 (Continued)
EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION IN.IU (a) A channel may be placed in an inoperable status for up to two hours for 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.
(c) Provides signal to HPCI pump suction valves only.
(d) Alarm only.
(e) Required when ESF equipment is required to be OPERABLE.
(f) On a one-time basis, prior to start-up from the outage that began on April 21, 1992, the Minimum Number OPERABLE Channels per Trip System for one reactor steam dome pressure - low (injection permissive) trip function may be reduced, for no-longer than 7 days, from two (2) channels to one (1) channel without declaring the associated ECCS inoperable in accordance with ACTION 31. This will be done on one occasion for Unit 1 and two occasions for Unit 2.
During these periods, the following actions shall i
be implemented:
(1)
The inoperable channel shall be placed in the condition that will satisfy the logic for allowing injection by the associated ECCS with the reactor steam dome pressure below 410 psig 15 psig.
(2)
Both channels in the other trip system shall be maintained OPERABLE.
(3)
The reactor vessel head vent shall be maintained in the open position.
4 1
I i
BRUNSWICK - UNIT 2 3/4 3-38 Amendment No. 56, 60, 78,4 97, 150, 191 !
~
~
g'
~
I rr k'
3
- z -
r 7:t 1
,...x-TABLE 3.3~3-1 h'
EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION p?
1N.
MINIMUM NUMBER APPLICABLE OPERABLE CHANNELS OPERATIONAL
. TRIP FbHCTION
.PER TRIP SYSTEM" CONDITIONS-ACTION
-[
- 1. CORE SPRAY SYSTEM j'
a.
Reactor Vessel Water Level - Low, Level'3' 2
1,2,3,4,5 30-w b.
Reactor Steam Dome Pressure - Low (Injection Permissive) 2" 1,2,3,4,5 31.
1
- c. - 'Drywell Pressure.- High-2 1, 2,.3 30 d.
Time Delay Relay 1
1, 2 3,'.4, 5
- 31 e.
Bus: Power Mar.itor" 1/ bus.
1,2,3,4,5 32 2.: LOW PRESSURE COOLAMT INJECTIGN MODE OF RHR SYSTEM a.
Drywell' Pressure - High.
2 1, 2, 3
'30-t
~b.
Reactor. Vessel Water L9 vel'- Low, Level-3 2
1, 2,-3, 4", 5"
[30
- Reactor Vessel' Shroud Level -(Drywell Spray Pernissive) 1 1,.2, 3,L4", 5"'
. 31 -
c.
- . d.
Reactor. Steam Dome Pressure 1-Low (Injection.Pemisst_ve).
f
!=. :RHR Pump' Start and LPCI Injection Valve. Actuation:
2"
- .1, 2,.' 3, L 4",. 5" l31 z-
=l 42.
Recirculation Loop Pump Discharge' Valv'e' Actuation 2
- 1, 2, 3,'.4",
5",
' 31' 8
.g<
i e.
I-RHR Pump. Start - Time Delay. Relay :
1.
1, 2,.3. 4", 5" y31 p
l t g[
f.
Bus Power Monitor".
1/ bus-1,2,3,t.4",(5"'
32'
.m l
b, =
g..
...