ML20112F747
| ML20112F747 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 03/19/1985 |
| From: | GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20112F735 | List: |
| References | |
| TAC-57308, NUDOCS 8503270533 | |
| Download: ML20112F747 (5) | |
Text
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ENCLOSURE 2 PEC DOCKET 50-366 OPERATING LICENSE PPF-5 EDWIN I. HATCH NUCLEAR PLANT UNIT 2 REQUEST TO AMEPO TECFNICAL SPECIFICATIONS The proposed change to. the Technical Specifications (Appendix A to Operating License ffF-5) would be incorporated as follows:
Remove Page Insert Page 3/4 3 3/4 3-27 3/4 3-29 3/4 3-29 3/4 3-32 3/4 3-32 8503270533 850319ADOCK 05000366 PDR PDR i
P l
'mBLE 3.3.3-1 (Contimed)
- @~
~
DMGENCY CORE C00 LIM 3 SYS'11!M ACNRTIN INSTRLMiNMTION
- 3::
c 5%.
MINIMM NLDEER
. APPLICABLE 8
OPERABLE OIAIM!:IS OPERATIOIRL
'w
'IRIP FUICTICE PER TRIP SYS11!M (DNDITIOl69
- 3. HIGH PRESSURE CDOLANT ItUfCfl0N SYSTEM i
Reactor Vessel Water Ievel - Iow Iow (Ietel 2) 2-1, 2, 3 a.
(2B21-N692 A,B,C,D) b.
Drywell Presaire - High (2 Ell-N694 A,B,C,D) 2 1,2,3 c.
Condensate Storage Tank Ietel-Iow (2E41-N002, 2E41-N003) 2(b) (c) 1, 2, 3 j
d.
Suppression Gamber Water Ietel-High' (2E41-N662B,D) 2(b) (c) 1, 2, 3 e.
Iogic Power Monitor (2E41-Kl) l(a) 1, 2, 3 f.
Reactor Vessel Water Ietel-High (Ievel 8)- (2B21-N693 B,D) 2 1,2,3-l
- 4. Alf10MATIC DEPRESSURIZATION SYSTEM i
l a.
Drywell Presaire - High (Permissive) (2 Ell-N694A,B,C,D) 2-1,2,3 i
w b.
Reactor Vessel Water Ietel - Iow Iow Low (Ietel 1)
)
(2B21-N691 A,B,C,D) 2 1,2,3 c.
ADS Timer (2B21-K5A,B) 1 1,2,3 Y
d.
ADS Iow Water Ievel Act11ation Timer (2B21-K754A,B; 2B21-K756A,B) 2 1,2,3 l
i l
e.
Reactor Vessel Water level-Low (Level 3) (Permissive) 1 1,'2, 3 1
(2B21-N695A,B) l f.
Core Spray Rig Discharge Presaire - High (Permissite) i (2E21-N655A,B; 2E21-N652A,B) 2 1,2,3 l
g.
RHR (LPCI M)DE) Rag Discharge Presaire - High (Permissite)
(2 Ell-N655A,B,C,D; 2 Ell-N656A,B,C,D) 2/ loop (a) 1,2,3 i
h.
Control Power Monitor. (2B21-KIA,B) 1/ bas 1, 2, 3
- 5. ION ION SETT S/RV SYSTEM i
I a.
Reactor Steam Dome Presaire - High (Permissite)
}
(2B21-N620A,B,C,D) 2 1,2,3 l
(a)
Alarm only. When inoperable,. verify power availability to the his 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 system inoperable.
2 l
(b)
Provides signal to HPCI pug alction valtes only.
(c)
When either channel of the altamatic transfer logic is inoperable, align HPCI pay alction to t
the alppression pool.
l I
HPCI and ADS are not req 11 red to be OPERABLE with reactor steam dome presaire -f 150 psig.
i
TABLE 3 3 3
- M EMERGENCY 00RE CI)OLING SYSTEM ACIUATION INS'IMMNTATION SETPOIlfrS 2
?c-AImRBLE N
'IRIP FUFCTION
'IRIP SETPOIlfr VALUE A
N 3.
HIGH PRESSURE 000LANT IRTECTION SYSTEM
- a. Reactor Vessel Water Ievel - Iow Iow (Level 2) 2 -55 inches
- 2 -55 inches *
- b. Drywell Presaire-High 5 1.85 psig S 1.85 psig.
- c. Condensate Storage Tank Ievel - Iow 2 0 inches **
1 0 inches **
- d. Suppression Chamber Water Level - High 5 33.2 inches S 33.2 inches
- e. Iogic Power Monitor NA.
NA
- f. Reactor Vessel Water Ietel-High (Ievel 8)
- 5 56.5 inches S 56.5 inches 4.
AUIOMATIC DEPRESSURIZATION SYSTEM
- a. Drywell Presaire-High S 1.85 psig S 1.85 psig
- b. Reactor Vessel Water Ievel - Iow Iow Iow (Ietel 1) 2.-121.5 inches
- 2 -121.5 inches *
- c. ADS Timer.
S 120 seconds S 120 seconds
(
- d. ADS Iow Water Ievel Actuation Timer S 13 mimtes S 13 mimtes l
A
- e. Reactor Vessel Water Ievel'- Iow (Ietel 3)
.E 8.5 inches *
.2 8.5 inches *
- f. Core Spray Rinp Discharge Presaire - High S 130 psig S 130 psig w
h
- h. Control Power Monitor NA NA 5.
IDW IDW SET S/RV SYSTEM
- a. Reactor Steam Dome Presaire - High S 1054 psig i 1054 psig
- See Bases Ficy. Ire B 3/4 3-1.
- Eka11 valent to 10,000 gallons of water in the CET.
R i
TABLE 4.3.3-1 (Contimed)'
4 3
~ :x:
ENERGEMN CI)RE COOLING SYSTEM ACTUATION INSTRLBENIRTICN SURVEILIANCE RBQUIRIM!NIS E:
z CHnuNEL oeERATIoNAL 8
OIANNEL FUICTIONAL CHANIEL CONDITIONS IN MIICH TRIP MRCTION CHBCX TEST CALIBRATION SUR')EILLABCE RBQUIRED#
w
.I 3.
HIGI PRESSURE C00DNP IMIECTION SYSTEM i
5
- a. Reactor Vessel Water Ietel -
l Iow Iow (Letel 2)
S M
R 1,2,3
- b. Drywell Presaire-High S
M R
.1, 2, 3
- c. Condensate Storage Tank Letel -
l Iow NA M
Q 1,2,3 i
- d. Suppression Chamber Water Ievel - High S
M
.R 1,2,3
- e. Logic Power Pt>nitor NA R
NA 1,2,3 1
l
- f. Reactor Vessel Water Ietel - High S
M R
1,2,3 i
(Ievel 8) 5 a
4.
AUIOMATIC DEPRESSURIZATION SYSTEM u
e
- a. Drywell Presaire - High S
M R
1, 2,.3 d
- b. Reactor Vessel Water Ietel -
1 Iow Iow Iow (Ietel 1)
S M.
R 1, 2, 3
- c. ADS Timer NA NA R-1, 2, 3 -
- d. ADS Iow Water Ievel Act11ation Timer NA NA R
1,2,3 l
- e. Reactor Vessel Water Ievel - Iow S
M R.
1,2,3 (Level 3)
- f. Core Spray Rinp Discharge Presaire - High S
M R
1,2,3
M R
1,2,3
- h. Control Power Monitor NA R
NA 1,2,3 5.
IDW IDW SET S/RV SYSTEM
- a. Reactor Steam Dame Presaire -
High S
M R
1,2,3
c:
5*-
ENCLOSURE 3 tEC DOCKET 50-366 OPERATING LICENSE IPF-5 EDWIN I. HATCH NUCLEAR PLANT UNIT 2 REQUEST TO AMEPO TECHNICAL SPECIFICATIONS Pursuant to 10 CFR 50.92, Georgia Power Company has evaluated the attached proposed amendment and has determined that its adoption would not involve _ a significant hazard.
The. basis for this determination is as follows: _
a.
PROPOSED CHANGE Add. timers 2B21-K754A, B and 2821-K756A, B to the list of Emergency COIe Cooling System actuation instrumentation.
Specify allowable setpoints and impose surveillance requirements.
i BASIS This change constitutes an additional control _not.previously included in the Technical Specifications.
This. change does not affect the probability.or consequences of an accident or malfunction analyzed in the FSAR. This change does not create the possibility of an accident or malfunction of a different type than analyzed in the FSAR.
The maIgin of safety as defined in the basis for any Technical Specification is not affected.
The effect of this change is therefore within the acceptance criteria and the change is consistent with Item (ii) of the " Examples of Amendments That Are Considered Not Likely to Involve Significant Hazards Considerations"' listed on page 14870 of the April -6,1983 issue of the Federal Register.
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