ML20034G585
| ML20034G585 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 03/01/1993 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20034G586 | List: |
| References | |
| NUDOCS 9303100168 | |
| Download: ML20034G585 (7) | |
Text
'
'/
'o UNITED STATES
~.,,
l '~
NUCLEAR REGULATORY COMMISSION p,
E WASHINGTON. D. C. 20555 o
'S, liLORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON. GEORJ M DOCKET NO. 50-321 EDWIN 1. HATCH NUCLEAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 184 License No. DPR-57 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Edwin 1. Hatch Nuclear Plant, Unit 1 (the facility) Facility Operating License No. DPR-57 filed by the Georgia Power Company, acting for itself, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the licensees), dated December 21, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as 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 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 set forth in 10 CFR Chapter I; 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.
i 9303100168 930301 PDR ADOCK 0500 1
P
- 2.
Accordingly, the license is hereby amended by page 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-57 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 184, 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 David B. M tthews, Director Project Directorate 11-3 Division of Reactor Prnjects - 1/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance:
March 1, 1993 o
-y
l l
ATTACHMENT TO LICENSE AMENDMENT NO. 1 84 FACILITY OPERATING LICENSE NO. DPR-57
}
DOCKET NO. 50-321 i
i; Replace the following pages of the Appendix "A" Technical Specifications with I
the enclosed pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.
i i
i Remove Paaes Insert Paaes 3.2-26 3.2-26 3.7-18 3.7-18 i
P 3.7-22 3.7-22 3.7-23 3.7-23 s
3 t
i 4
l
-i
~
i t
~f t
!i f
[
Notes for Table 4.21 (Cont'd)
--4 S'
from other BWR's for which the some design instrument operates in en environment eimeter to that of I
HNP-1. The feiture rete date sewat be reviewed and approved by the AEC prior to any change in the Z
+
once-e-month frequency.
~
e.
TNe instrumentation is enempted from the Instrument functional teet defmition. TNs instrument functional test will consist of injecting e simulated electrical signalinto the measurement channels.
f.
Stenderd current source used which providee en instrument chonnel elegnment. Celebretion using a redestion source shell be made once per operating cycle.
w Logic tvetem functionet teste end esmuteted automatic ectuation ohell be performed once each opereimg cycle r4 e
',9 for the fo#owing:
1.
Main Steam Line leoietion Velvee 8.
Reactor Water Cleanup leoletion 2.
Mein Steam Line Drain Velvee 9,
Drywellisoletron Velves 3.
Reactor Weter Sample Velves 10.
TlP Withdrewal 4
RHR - leoletion Velve Control 11.
Atmospheric Control Velvee 5.
Shutdown Cooling Velves 12 Sump Deem Valves 6.
Deleted 13.
Standby Gee Treatment -
l g
7.
Drywell Equipment Sump Descharge to Redweste 14 Reector Bueldmg le9 stion 1
ad The logic system functional toets shallinclude e cet6tetson of time deley releys and timere necessary
'u
- B O:s for proper functiorung of the inp systems.
2 O.
3 J
- n a
t v4
..--....~.i 4w
.w..- -. e
,O.
-m
-~~~-~.m.-.-
.-.,.--. ~....U.E.. < - -,.... -.. ~. -. -..
--w.-.
r.-.,-r.-
..+ w
.--.~.m.my
-... ~ ~ ~ -
3w.
--v --
....-.-.-..---w.,
.w
l I
I l
TABLE 3.7-1 (Cont'd)
--0 i
f O
PRIMARY CONTAINMENT ISOLATION VALVES WHICH RECEIVE A PRIMARY CONTAINMENT ISOLATIO;4 SIGNAL C5
-4 isolation Number of Power Maximum Normal Action on
~
I Group Operated Velves Operatira Position Irdtleting (b)
Vefve kfentification !d)
Inside Outside Time (sect tal Sianal fe}_
6 RHR reactor shutdown cooling i
1 24 C
SC suction loupply)
(E11-FOO8, E11-F009) i 3
HPCI - turtane steem i
1 50 0
GC (E41 FOO2, E41-F003) 4 RCIC - turbine steem 1
1 20 0
GC iE51 FOO7. E51-FOO8) 5 Reector water efeenup from 1
1 30 0
GC g
recirculation loop
.y (G31 F001. G31 FOO4) 2 Post-accident sampling system supply 2
5 C
SC (B21-Fi11, B21-F1121 2
Post-acckient osmpting system return 2
5 C
SC (E41-F122, E41-F121) 30 M
2 Core sprey test line to suppressiort I na-h 57 C
SC S
pool Ene g
(E21 F015A,B)
=>
r4 2
O.
M m
+ - - -
i Table 3.7-3 Testable Penetrations with Testable Bellows Penetration Number Penetration Descrintion Egin X-1A Primary Steamline ' A' (1) (2) (4) (6)
X-78 Primary Steamline 'B' (1) (2) (4) (6)
X-7C Primary Steamline 'C' (1) (2) (4) (6)
X-7D Primary Steamline 'D' (1) (2) (4) (6)
X-8 Steamline Condensate Drain (1) (2) (4) (6)
X-9A Feedwater Line 'A' (1) (2) (4) (6)
X-9B Feedwater Line 'B' (1) (2) (4) (6)
X-10 Steam to RCIC Turbine (1) (2) (4) (6)
X-Il Steam Line to HPCI Turbine (1) (2) (4) (6)
X-12 RHR5 Shutdown Cooling Suction (1) (2) (4) (6)
X-13A RHR LPCI to Reactor (1) (2) (4) (6)
(
X-13B RHR LPCI to Reactor (1) (2) (4) (6)
X-14 Reac+or Water Cleanup Line (1) (2) (4) (6)
X-16A Core Spray to Reactor (1) (2) (4)~(6)
X-16B Core Spray to Reactor (1) (2) (4) (6)
X-17 Spare (1) (2) (4) (6) l X-201A through Drywell Suppression Chamber (1) (2) (4) (6)
X-20lH to Vent Line i
HATCH - UNIT 1 3.7-22 Amendment No.184 i
I t
L__________---------___________________-._____________________--__________.
I Table 3.7-4 l
Primary Containment Testable Isolation Valves 1
Penetration Number Valve Desionatien Egin X-7A B21-F022A & F02BA Main Steam Isolation Valves (1) (2) (3) (5) (9)
X-7B B21-F022B & F02BB Main Steam Isolation Valves (1) (2) (3) (5) (9)
X-7C B21-F022C & F02BC Main Steam Isolation Valves (1) (2) (3) (5) (9)
{
r X-7D B21-F022D & F02BD Main Steam isolation Valves (1) (2) (3) (5) (9)
X-8 B21-F016 & F019 (1) (2) (4) (5) (9)
X-9A B21-F0108 (1) (2) (3) (5) (10)
X-9A B21-F0328 (1) (2) (3) (5) (10) s X-9A E41-F006 (1) (2) (4) (5) (9)
X-9A G31-F203 (1) (2) (4) (5) (10)
X-9B B21-F010A (1) (2) (3) (5) (10)
X-9B B21-F032A (1) (2) (3) (5) (10)
X-9B E51-F013 (1) (2) (4) (5) (9)
X-9B G31-F039 (1) (2) (4) (5) (10)
X-10 E51-F007, F008 (1) (2) (4) (5) (9)
~
X-11 E41-F002 & F003 (1) (2) (4) (5) (9)
X-12 Ell-F008 & F009 (1) (2) (4) (5) (9)
X-13A E11-F015A (1) (2) (4) (5) (9) i X-13B Ell-F015B (1) (2) (4) (5) (9)
X-14 G31-F001 & F004 (1) (2) (4) (5) (9)
X-LEA E21-F005A (1) (2) (4) (5) (9)
X-16B E21-F005B (1) (2) (4) (5) (9)
I 9
HATCH - UNIT 1 3.7-23 Amendment No.184 i