ML20076K633
| ML20076K633 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 06/23/1983 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Georgia Power Co, Oglethorpe Power Corp, Municipal Electric Authority of Georgia, City of Dalton, GA |
| Shared Package | |
| ML19268D925 | List: |
| References | |
| TAC 51851, NPF-05-A-032 NUDOCS 8307180041 | |
| Download: ML20076K633 (7) | |
Text
..
p eer,
u
- [h* 3 va g
UNITED STATES y
q NUCLEAR REGULATORY COMMISSION
{
i.;.c. 3 l WASHINGTON, D. C. 20555
, e-f GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET NO. 50-366 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 32 License No. NPF-5 4
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Georgia Power Company, et al, (the licensee) telecopied June 20, 1983, as supplemented June 21,1983, 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 a 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 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 amend-ment and paragraph 2.C.(2) of Facility Operating License No. NPF-5 is hereby amended to read as follows:
8307180041 830623 PDR AD'~:K 05000366 P
1 i
Technical Speci fications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 32, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This amendment became effective on June 21, 1983.
FOR THE N LEAR REGULATORY COMMISSION John F. Stolz, Chief Operating Reactors Branch #4 Division of Licensing I
Attachment:
Changes to the Technical Specifications i
Date of Issuance: June 23,1983 a
(
4.
i
ATTACHMENT TO LICENSE AMENDMENT NO. 32 FACILITY OPERATING LICENSE NO. NPF-5 DOCKET NO. 50-366 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain a vertical line indicating the area of changes. The corresponding overleaf pages are also provided to maintain document compl eteness.
Remove Insert 3/4 3-14 3/4 3-14 3/4 3-18 3/4 3-18 e
]
i JAllLE 3.3.2-1 (Continue 1),
1 ISOLAT10ft ACIUAT10tl lilSTRUMElilATION VALVE GROUPS HINIMUH fiUH8ER APPLICAlli E M
OPEHATED BY OPERABLE CilANNELS OPERATIONAL x
IRIP futitl10ft S IGriAl.(a )
PER TRIP SYSTEH(b)(c) 00fiDil10ti AC110t 4.
tilGil PRESSURE COOLAtti filJECTI0tl SYSTEH ISOLATI0tl a.
110C1 Steam Line flow -liigh##
3 1
1,2,3 26 l
,o (2E41-tiOO4 and 2E41-11005) b.
IIPCI Steam Supply Pressure -
Low (2E41-N001 A,ll, C, D) 3, 8 2
1, 2, 3 Pt.
c.
IIPCI Iurbine Exhaust Diaphragm Pressure - liigh (2E41-fl012 A,B,C,D) 3 2
1, 2, 1
. e.
d.
IIPCI Equipment Itoom Temperature - liigh (2E41-N610 A, B) 3 1
1, 2, 3 5
Suppression Pool Area Ambient e.
Temperature-liigh (2ESl-N.603 C, D) 3 1
1, 2, 3
/.
f.
Suppression Pool Area A Temp.-liigh (2E51-N604 C, D) 3 1
1, 2, 3 26 9
Suppres'slon Pool Area Temperature 3gg) 1 1,2,3 26 limer Relays (2E41-H603 A, 8) 2 M
h.
Emergency Area Cooler Temperature-9h liigh (2E41-ti602 A, 0) 3 1
1, 2, 3 16 E
in E
I.
Drywell Pressure-Illgh
.y (2E11-11011 C, 0) 0 1
1, 2, 3 26 j.
Logic Power Honitor (2E41-Kl)
NA 1
1, 2, 3 27
j IABLE 3.3.2-1 (Continued)
ISOLATION ACTUATIDH INSTRUMENTATION VALVE GROUPS HINIMUN NUMBER APPL.lCABLE p;
OPERAIED BY OPERABLE CilANNELS OPERATIONAL l
g TRIP FUNCTION SIGNAL (a)
PER TRIP SYSTEM (b)(c)
CONDITION ACTION c
5.
REACTOR CORE. ISOLATION g
~C6DEING SYSilH itDEATION a.
RCIC Stearn Line Flow-liigh 4
1 1, 2, 3 26(
l
-i (2E51-N017,2E51-N018) b.
RCIC Steans Suplily Pressure. -
Low (2E51-H019 A, B, C, D) 4, 9 2
g 1,, 2, 3 26 c.
RCIC Turbine Exliaust Diaphragm Pressure - liirjh 4
2 1, 2, 3 26 (2E51-N012 A, B, C, D) d.
Emergency Area Cooler Temperature -
liigh (2E51-H602 A, 8) 4 1
1,2.3 26 e.
Suppression Pool Area Ambient iTemperature-liigh 4
1 1, 2, 3 26 (2E51-N603 A, B) m h
f.
Suppression Pool Area a T-iligh 4
1 1,2,3 26 (2E51-N604 A, B) g.
Suppression Pool Area Temperature Timer Relays (2ESI-H6d2 A, B) 4g,)
1 1, 2, 3 26 l
h.
Drywell Pressure - liigh F
(2 Ell-H0ll A, B) 9 1
1,2,3 26 1.
Logic Power Monitor (2E51-KI)
NA(b}
l 1, 2, 3 2'7 m
A 6.
SilVTDOWN COOLING SYSTEM ISOLATION E
a.
Reactor vessel Water Level-Lown 2, 5, 6, 10, 11, 2
3, 4, 5 26 (2B21-Nol7A,B,C,0) 12 b.
Reactor Steam Dome Pressure-liigh 11 1
1, 2, 3 28 (2831-N018 A, 0) 4 If Not required OPERABLE during feedwster braclet repair commencing on June 21, 1983.
t
$h
TABLE 3.3.2-2 (Continued)
ISOLATION ACTUATION INSTRUMENTATION SETP0lNTS ALLOWABLE s
TRIP SElPOINT_
VALUE y
TRIP FUNCTION
(.
3.
REACTOR WATER CLEANUP SYSTEM ISOLATION E
M a.
A Flow - liigh 1 79 gpm 1 79 gpm
< 130*F
< 130*F b.
Area Temperature-liigli Area Ventilation a Temperature - liigh
< 75*F
< 75'F c.
d.
SLCS Initiation NA NA e.
Reactor Vessel Water Level-Low
> 12.5 inches *
> 12.5 inches
- 4.
HIGil PRESSURE COOLANT INJECTION SYSTEM ISOLATION L,
< 300% of rated flow
< 300% of rated flow E
a.
IIPCI Steam Line flow-liigh
~> 100 psig
[100psig b.
IIPCI Steam Supply Pressure - Low Y
c.
IlPCI Turbine Exhaust Diaphragm C
Pressure-liigh 1 10 psig 1 10 ps19 d.
IIPCI Equipnent Room Temperature-
< 175*F
< 17S*F liigh Suppression Pool Area Ambient
< 175"F e.
< 175'F Teniperature-liigli f.
Suppression Pool Area AT - liigh 7 50*F**
7 50*F**
g.
Suppression Pool Area Temperature Tiner Relays NA NA h.
Energency Area Cooler Temperature -
< 175*F
< 17S*F liigh
- i. Drywell Pressure - liigh i2psig
[2psig
- j. Logic Power Bus Monitors NA NA
- See Bases Figure B 3/4 3-1.
- Initial setpoint. Firial setpoint to be determined durjng startup testing.
l
TABLE 3.3.2-2 (Continued)
ISOLATION ACTUATION INSTRUMENTATION SETPOINTS 5
ALLOWABLE
[n TRIP FUNCTION TRIP SETPOINT VALUE 5.
REACTOR CORE ISOLATI0l1 E
~TDOEING SYSTEM 1SOEXT10N
~
a.
RCIC Steam Line Flow - liigh 1 300% of rated flow 1 300% of rated flow
[
b.
RCIC Steam Supply Pressure - Low
> 50 psig
> 50 psig c.
RCIC Turbine Exhaust Olaphragm Pressure-1 i 0 psig liigh 1 10 psig d.-
Emergency Area Cooler Temperature-liigh
< 175*F
< 175*F Suppression Pool Area Ambient Temperature e.
< 175*F
< 175*F liigh f.
Suppression Pool Area AT - liigh
< 50*F**
< 50*F**
9 Suppression Pool Area Temperature Timer Itelays NA NA m
w h.
Drywell Pressure - liigh 1 2 psig 1 2 psig 3
5 1.
Logic Power Monitor NA NA I
k 6.
SituTDOWN COOLING SYSlEM ISOLAT10t{
o Reactor Vessel Water Level - Lowff
> 12.5 inches *
> 12.5 inches
- l a.
b.
Iteactor Steani Dome Pressure - liigh 5135psig i135psig 2
- See Bases l'igure B 3/4 3-1.
- Initial setpoint.. Final setpoint to be detennined during startup testing.
- Not required OPEltABLE during feedwater sparger bracket repair conunencing on June 21, 1983.
This involves only Group 11.
g
.