ML20095L354
| ML20095L354 | |
| Person / Time | |
|---|---|
| Site: | Hatch |
| Issue date: | 08/22/1984 |
| 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 | |
| ML19276C458 | List: |
| References | |
| TAC 55555, NPF-05-A-040 NUDOCS 8408300217 | |
| Download: ML20095L354 (7) | |
Text
._.
j(
UNITED STATES a
g NUCLEAR REGULATORY COMMISSION 3
- j wasmNGTON. D. C. 20555
%,...../
GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET NG. 50-366 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 40 License No. NPF-5 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Georgia Power Company, et al.,
(the licensee) dated August 6,1984, as supplemented August 10, 14, and 16, 1984, 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 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 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 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. NPF-5 is hereby amended to read as follows:
8408300217 840822 PDR ADOC" 05000 P
me
.. ~ _.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 40, are hereby incorporated in the license. The. licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION I
oh PF. Stolz, Chief Op ating Reactors Brakh #4 D ision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 22, 1984 e
h-W-
..h-edwh++-e a.-
gag ne664.ga,ep.c hm D w
,,,_mm
ATTACHMENT TO LICENSE AMENDMENT NO. 40 FACILITY OPERATING LICENSE NO. NPF,
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 nunter and contain a vertical line indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.
Remove Insert 3/4 6-18 3/4 6-18 3/4 6-22 3/4 6-22 e
m.s.s
.r.
TABLE 3.6.3-1 PRIMARY CONTAIPMENT ISOLATION VALVES
. E VALVE FUNCTION AND NUMBER VALVE GROUP (a)
(Seconds)
ISOLATION TIME h
A.
Automatic Isolation Valves j
1.
M,in Steam Isolation Valves 2821-F022 A, B. C and D 1
3<t<5
- 2B21-F028 A, 8, C and D 1
3<t<5 2.
Main Steam Drain Isolation Valves 2821-Ful6 1
15 2821-F019 1
15 3.
Reactor Water Sample Line Isolation Valves I
R 2B31-F019 1
5
[
5 G
4.
Drywell Equipment Drain Sump Discharge Isolation Valves 2G11-F019 2
20 2G11-F020 2
20 5.
Drywell Floor Drain Sump Discharge Isolation Valves
't 2G11-7003 2
20 2G11-F004 2
20 (a)See Specification 3.3.2, TabJe 3.3.2-1, for isolation signals that operate each valve group.
\\
3.
c
\\
-.s 1seur 3.6.3-1 (continued) 1 PRD92Y ODNmil4ENP ISOERr10DI VALVES MINE FtRCTEM NB RSEER Isaurnose ramt i
VAIRE G40Up(a)
(secords)
A.
autmatic isolation valms tomtimed) a i
s.
n=+=iment spray 1=iation m1=es s
2B11-7016 A(b) and B(b) 2E11-7028 A(b) and B(b) 10 24 1.
Est Ibat Iboch Jujer Drain Isolation Wims I
2B11-F011 A and B 2E11-5026 A and B 20 I
20 S.
Drywell-to4brus Differar*Ial Pressure i
System i=1ntian Wises w1 Y
~5 2N8-F210 12 5
12 2048-F211 5
12 2N S-F212 5
12 5
i 9.
HPCI Steam Line Isolation valves 2B41-7002 2E41-9003 3
50 3
50 Y
a (b)peay be opened on an intermittent basis under vinirdstrative controltalsee specifica
- Closes upon actuation of tie IACI mode of mR via a high drywell presaire signal (see itaa 2 a of
.E Table 3.3.3-1) oc a rm Im Im (Iawel 1) signal fram 2B21-ia691A,B,C,D laee itcma 2.b of Table 3 3 3-1 i
I
TABLE 3.6.3-1 (Continued)
PRIMARY CONTAINMENT ISOLATION VALVES ISOLATION TIME VALVE FUNCTION ANO NUMBER VALVE GROUP (a)
(Seconds) iiig A.
Automatic Isolation Valves (Continued)
- c
- 17. Torus Cleanup Vacuum Orag Isolation Valves Eq 2G51-F011 7
15 m
15 4
15 2E41-F104 8
15 l
9 15 1
15
- 20. H0 Sampling System Isolation Valves 22 2P33-F004 10 5
2P33-F012 10 5
2P33-F002 10 5
2P33-F010 10 5
2P33-F006 10 5
2P33-F007 10 5
2P33-F014 10 5
2P33-F015 10 5
2P33-F003 10 5
2P33-F011 10 5
2P13-F005 10
.5 2P33-F013 10 5
I*I See Specification 3.3.2, Table 3.3.2.1, for isolation signals that operate each valve group.
,f
,f
\\
0
s TRBIR 3.6.3-1 (Omtirued) ll ll IRIMMtr oawmIwerr m0 EAT 10N VAWES Isamson vine varyg ytacrIan Jes) tageER WFu,VE CHOUP(a)
(Seonnds)
A.
Jiutomatic Isolation W13es ((butirased)
- 22. Sappoession I001 Wat and Rarge System Isolation M1=es 2r4&P338 10 5
2T88-F339 10 5
2r48-F318 10 5
2Tt8-F326 10 5
23..
MIR Shatdows O=1ing aaction Isolation Wises i
U 2 Ell-5008 11 24 l
- 24. REV Ibad Spray Isolation Wlve 2B11-P023
~
11 20 i
E s
ta3See 5:psw tri<-ation 3.3.2, Table 3.3.2-1, for imlation signals tivat operate each val.ve group
(
or'1asma upon actuation of Cbre Spray via a high drywell presaare signal (see itesa 1.b of Dble 3.3 3-])
g oc a Imu Inw tow (Emel 1) signal from 2B21-N691A,B,C,D (see itema 1.a of hhle 3.3.3-1).
)
P L
g-6 e
r i\\
- \\.
\\'