ML20072E867
| ML20072E867 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 06/20/1983 |
| From: | GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20072E857 | List: |
| References | |
| TAC-51851, NUDOCS 8306270175 | |
| Download: ML20072E867 (4) | |
Text
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ATTACIDENT 1 NHC DOCKET 50-366 OPERATING LICENSE NPF-5 EININ I. HAICH NUCIEAR PIANT UNIT 2 PROPOSAL FOR TECHNICAL SPECIFICATION CHANGE FEEDWATER SPARGER REPAIR The proposed change to the Technical Specifications (Appendix A to the Operatire License) muld be incorporated as follows:
Remove Page Insert Page 3/4 3-14 3/4 3-14 3/4 3-18 3/4 3-18 J
l 8306270175 830620 PDR ADOCK 05000366 P
- /
TABLE 3.3.2-1 (Continued)
ISOLATION ACTUATION INSTRtFENTATION VALVE GROUPS MINIMtN NL)eER APPLICABLE OPERATED BY OPERABLE CHANNELS OPERATIONAL 5!
TRIP FUNCTION SIGN *L (a)
PER TRIP SYSTEM (b)(c)
CONDITION ACTION N*
5.
REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION 4
a.
RCIC Steam Line Flow-High 4
1 1.2,3 26 (2E51-N017, 2E51-N018) m b.
RCIC Steam Supply Pressure -
Low (2E51-N019 A, B, C, D) 4, 9 2
1,2,3 26 c.
RCIC Turbine Exhaust Diaphregm Pressure - High 4
2 1,2,3 26 (2E51-N012 A, B, C, D) d.
Emergency Area Cooler Temperature -
High (2E51-N602 A, B) 4 1
1,2,3 26 w3 u
e.
Suppression Pool Area Ambient
,L Temperature-High 4
1 1,2,3 26 (2E51-N603 A, B) f.
Suppression Pool Area A T-High 4
1 1,2,3 26 s
(2E51-N604 A, B) g.
Suppression Pool Area Temperature Timer Relays (2E51-M602 A, B) 4(1) 1 1,2,3 26 h.
Drywell Pressure - High (2 Ell-N0ll A, 8) 9 1
1,2,3 26 i
Logic Power Monitor (2E51-Kl)
NA(h) 1 1,2,3 27 6.
SHUTDOWN COOLING SYSTEM ISOLATION Reactor Vessel Water Level-Low ##
2, 5, 6, 10, 11 2
3, 4, 5 26 l
a.
(2B21-N017 A, B, C, D) 12 b.
Reactor Steam Dome Pressure-High 11 1
1,2,3 28 (2831-N018 A, B)
.## ot required OPERABLE during feedwater sparger bracket repair commencing on June 20, 1983.'~
N
1 TABLE 3.3.2-2 (Continued) i g
ISOLATION ACTUATION INSTRUMENTATION SETPOINTS h
ALLOWABLE URIP FUNCTION TRIP SETPOINT VALUE h
5.
REACTOR CORE ISOLATION H
COOLING SYSTEM ISOLATION w
a.
RCIC Steam Line flow - High 1300% of rated flow 1300% of rated flow b.
RCIC Steam Supply Pressure - Low 2,50 psig 1 50 psig c.
RCIC Turbine Exhaust Diaphragm Pressure-Hi@l 1 10 psig 1 10 psig u
D d.
Emergency Area Cooler Temperaturt-High
< 1750F
< 1750F w'
e.
Suppression Pool Area Ambient Temperature High 1 1750F 1 1750F f.
Suppression Pool Area AT - High 1 500F**
1 500F**
g.
Suppression Pool Area Temperature Timer Relays NA NA h.
Drywell Pressure - High 1 2 psig i 2 psig 1.
Logic Power Monitors NA NA 6.
SHJTDOWN COOLING SYSTEM ISOLATION a.
Reactor Vessel Water Level - Low ##
1 12.5 inches
- 1 12.5 inches
- g D
b.
Reactor Steam Dome Pressure - High 1 135 psig 1 135 psig
- See Bases Figure B 3/4 3-1.
- Initial setpoint. Final setpoint to be determined during startup testing.
- ot required OPERABEE during feedsster spargerTrTcket rep ~ air commencing on ~ June 20, 1983.
N This involves only Group 11.
A'ITAC19ENT 2 NBC DOCKET 50-366 OPERATING-LICENSE NPF-5 EIMIN I. HA'IGI N(I' LEAR PLANP UNIT 2 PROPOSAL' EOR TECHNICAL SPECIFICATION CHANGE FEEDWATER SPARGER REPAIR Pursuant to 10 CFR _170.12 (c),. Georgia Power conpany has evaluated the attached proposed amendment to operating license NPF-5 and has determined that:
a.
The proposed amendment does not require the evaluation of a new Safety Analysis Report or rewrite of the facility license;
- b. -
The proposed amendment does not contain several complex issues, does not involve ACRS review, and does not require an environmental inpact statement; c.
The proposed anendment does not involve a complex issue or more than one environmental or safety issue; d.
The proposed amendment does involve a single safety issue, namely, removing the requirement to have shitdown cooling system isolation at a level of 12.5 inches in the reactor vessel during the feedwater sparger repair.
4 e.
The proposed amendment is therefore a Class III amendment.
,