ML20042D268
| ML20042D268 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 12/29/1989 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20042D269 | List: |
| References | |
| NUDOCS 9001080177 | |
| Download: ML20042D268 (6) | |
Text
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. UNITED STATES -
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- NUCLEAR REGULATORY COMMISSION n
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tn WASHINGTON, D C. 20585 '
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G 0RGIA POWER COMPAl#
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'OGLETHORPE POWER CORPORATION i
L MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA d
CITY '0F DALTON, GEORGIA'
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DOCKET NO. 50-366 4
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EDWIN 1. HATCH NUCLEAR PLANT UNIT 'NO.,2,
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c AMENDMENT T0-FACILITY OPERATING LICENSE I
Amendment No.104 License No.-NPF-5
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The Nuclear Regulatory Consission'(the Commission) has found that:
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'A.
The application for amendment to the Edwin.I. Hatch Nuclear Plant, Unit 2 (the facility)L Facility Operating License No..NPF-5 filed l
by Georgia Power Company, acting for itself, Oglethorpe Power i
h Corporation, Municipal Electric Authority of Georgia, and City of Dalton; Georgia (the licensee) dated August 22,.1989,l complies with 1
the' standards-and requirements of the Atomic Energy Act of 1954, as
. amended' (the : Act), and the Commission's rules and regulations set Li e
-forth,in-10 CFR Chapter I;
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B.
The facility will operate in cenformity with the application, the i
. provisions of the Act, and the rules and regulations of the p
Commission; L
C.
There is reasonable assurance (i) that the activities authorized by
- this amendment can be conducted without endangering the health ano H
L safety of the public, and (ii) that such activities will be conducted l
in compliance with the Commission's regulations set forth in 10 CFR "y
Chapter'I; D.
The issuance of this amendment will not be inimical to the common i
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 t
.of the Commission's regulations and all applicable requirements have been satisfieo.
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9001080177 891229 PDR ADOCK 05000366 F
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Mcordingly, the license is amended by changes to the Technical Specifi-c.ations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-5 is hereby r
amended to read as follows:
i Technical Specifications
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The Technical Specifications contained in Appendices A and B, as revised through Amendment No.104, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technfeal' Specifications.
3.
This license anandment is effective as of its date of issuance and shall be iniplemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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U David B. Matthews, D ter Froject Directorate 11-3 Division of Reactor Projects-l/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical
!pecifications Date of Issuancm December 29, 1989 h
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ATTACHMENT TO LICENSE AMENDMENT NO.104 L
FACILITY OPERATING LICENSE NO. NPF-5 DOCKET NO. 50-366 l
Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. 'The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove Pages Intert Pages j
3/4 3-7 3/4 3-7 3/4 3-41 3/4 3-41 3/4 3-42 3/4 3-42*
- 0verleaf page provided to maintain document completeness.
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' TABLE 4.3.1-1
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REACTOR PROTECTIOII SYSTEM litSTRUMENTATION SURVEILLME REQUIREfEllTS e
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C CHA8eISEL OPERATIONAL CHAIINEL FUNCTIONAL CHA88NEL CONDITIONS IN WNICH
-4 FUteCTIONAL UNIT CHECK TEST CALIBRAT IOll ' SURVEILLAM;E REQUIRED 1.
a.
Neutron Flux - High D.
S/U' * * ' ' '
R 2
D W
R 3, 4, 5 b.
Inope ra t ive NA W.
IIA 2,3,4,5 2.
Average Power Range Monitor:
a.
Neutron Flux - Upscale, 15%
S S/U **8, W'
S/U, W'*8 2
8 S
W W
5-b.
Flow Referenced Simulated S
S/U'**, Q.
W',
SA 1
Thermal Power - Upscale c.
Fixed Neutron Flux - Upscale, S
S/U, O W,
SA 1'
118%
d.
Inoperative NA Q
stA 1, 2,.5 e.
Downscale NA W _
NA 1
F.
LPRM D
ssA
~ 1, 2, 5 Y
3.
Reactor Vessel Steam Dome S
Q R
1, 2 Pressure - High w
8 4.
S Q
R 1, 2 -
Low (Level 3) 5.
Main Steam Line Isolation Valve -
Closure itA Q
R 1
l 6.
Main Steam Line Radiation - High D
Q
R 1, 2 7.
Drywell Pressure - High S
Q R-1, 2 8.
Scram Discharge Volume Water 9tA Q
R'*'
' 1, 2, 3 Level - High x~
3o 3
C1 3o 3
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2' O
O 4
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TABLE 4.3.5-1 r>
I CONTROL ROD WITHORAWAL BLOCK INSTRUMENTATICII SURVEILLAME REQUIME9ENTS.
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CHANIBEL OPERATBOIML CHA90NEl.
FUIOCTIDISAL CHAaestCL CONDITIOIBS IN WetiCst 3 TR I P FUNCTION.
~_CHECR TEST CAllBRATf0f0fal SURVEILLANCE REQUIRED
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APRM:
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a.
Flow Referenced Simulated The rma l Powe r-Upsca le NA.
8 S/U *8,Q R
1 b.
I nopera t ive NA S/U Q 16 4 1, 2, 5 c.
Downscale StA S/U'*8,,M R
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d.
Neutron Flux - High, 12%
MA S/U,Q R
2, 5 l
2.
Rod Block Monitor:
a.
Upscale NA S/U'*8, Q R
l'**
f b.
Inopera t ive NA t
S/U *8, Q
NA 1'*8 c.
Downscale NA S/U, Q R
1'*8 3.
Source Range Monitors:
a.
Detector not full in MA S/U'*8,W
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b.
Upscale NA S/U * *, W R
2* 5 8
c.
Inopera t ive NA Sfgtes y gg y
d.
Downscale NA S/U,W R
2,' 5 a
8 Intermediate Range Monitors:
4 sa a.
Detector not full in MA S/U'*8 t
W*8 ggA 2 5 b..
Upscalt 86A S/U,W'**
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R 2* 5 c.
Inopera6sve NA S/U' * *,'W'
- 8 pgA d.
Downscale NA S/U'*8 W**
g 2,' 5 t
5.
Scram Discharge Volume:
4 a.
Water Level-High NA Q
R 1, 2, 5'**
>9 to 3
l QL B
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TABLE 4.3.5 1 (Continued)'
i-C0h""ROL ROO V!':"rORAVAL ILOCK INS'"RLHEWATION $URVIILLANeg 33cy;yggns
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NOTIsr Neutren detectors may be excluded f:ce CRANNEL CAL:1 RAT:0N.
a.
l b.
Within :a heurs p ler to ::artup, if net performed within :he L
previous 7 days.
When changing free OONDITION 1 to 00NDIT:0N 2, perform the c.
required surveillance within 1: heufs'afier entering 00ND:::0N :.
i d.
When 7:-:ERMAL PO'a*IR exceeds the preset pcVer level of the RVM i
and R505.
The addittenal surveillance defined in Specificatien i
4.1.a.3 vill be required when the Liniting Ocndition defined in Specification 3.1.4.3 exists,
e.
Vith any cent::1 : d withdrawn. Nc: applicable to cent::1 : ds removed per Specification 3.9.11.1 cr 3.9.11.2.
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r EA7 E*2 3/' 2*40 Amendment No.'9
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