ML20033A258
| ML20033A258 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 11/13/1981 |
| 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 | |
| ML20033A259 | List: |
| References | |
| TAC 47092, DPR-57-A-087 NUDOCS 8111250043 | |
| Download: ML20033A258 (9) | |
Text
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UNITED STATES g
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NUCLEAR REGULATORY COMMISSION
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e, WASHINGTON, D. C. 20555
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GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL' ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET NO. 50-321 EDWIN I. HATCH NUCLEAR PLANT, UMIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 87 License No. DPR-57 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Georgia Power Company, et 31.,
(the licensee) dated October 27, 1981, 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; 3.
The facility will operate in confomity 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; 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 tnis amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
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2.
Accordingly, the license is amended by changes to the Technical Spec-j g
. ~ ~
ifications as indicated in the attachment to this license amendment
~. o and paragrach 2.C.(2) of Facility Operating License Nc. OPR-57 is m8 hereby amended to reac as follows:
n
.h (2) Technical Scecifications 80 0
$4 The Technical Specifications contained in Appendices A and
- -x B, as revised through Amendment No. 87, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
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2-
- 3..This license amendment is effective as of the date of its issuance.
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'FOR THE NUCLEAR REGULATORY COMMISSION J hn
. Stolz,. Chief 0
ting Reactors. Branch #4 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
tiovember 13, 1981 i
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ATTACHMENT TO LICENSE AMENDMENT NO. 87 FACILITY OPERATING LICENSE NO. DPR-57 DOCKET NO. 50-321 Replace the*following pages of the Appendix "A" Technical Specifications
~
with the enclosed pages. The revised pages'are identified by Amendment s
number and contain a vertical line indicating the area of chance.
'r Remove Insert i
3.2-16 3.2 3.11-1 3.11-1 Fig. 3.11-1 (Sheet 3)(New)
Fi g. 3.11.4 Fig. 3.11.4
' Fig. 3.11.5 Fig. 3.11.5 Fi g. 3.11.6 Fig. 3.11.6 I
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37 Table 3.2-7 (Coatinued)
$a Po Required 3
Operable Ref.
Trip Channels w
?
No.
Condition per Trip )
(a)
Instrument Nonencla ture System (b Trip Setting Remarks 4
3 APRii Downscale 2(e)
> 3/125 of full scale Not required while performing low power physics test as atmospheric pressure during or after refueling at power levels not to exceed u
5 Mit.
12% Flux 2(e)
$ 12/125 of full scale This function is bypassed when the Mode Switch is placed in the RUN position.
liigh Flux 2(e)
~< 0.66W + 42%
W is the loop recirculation flow rate in percent of rated. Trip level setting is in percent of rated power. Not required while perfonning low power physics tests at atmospheric pressure during or
?'
after refueling at power levels 5;
not to exceed 5ftlt.
4 part inoperative 1(e)(f)
Not applicable Inoperative trip produced by switch (g)(h) not in operate, circuit boards not
-in circuit, fails to null, less than required nunber of LPRM inputs for rod selected.
Downscale 1(e)(f)
~> 3/125 of full scale (g)(h) liigh Flux 1(e)(f) 5 0.6611 + 41%
W is the loop recirculation flow rate in percent of rated. Trip level setting is in percent of rated thennal power.
3 ASIS FOR LIMIT!NG CCNDITIONS FOR' OPERATION AND SURVEILL\\NCE REOUIREME?iTS
'4.11 FUEL RODS 3.11 FUEL ROOS Aeolicability Aeolicability The Li= iring Conditions for Operation The Surveillance Requirements apply associated with the fuel rods apply to to the parameters which monitoc the those parameters which =enitor the fuel rod operating conditions.
fuel red operating conditions.
Chiective Chiective The Objective o'f the L1=iting Condi-The Objective of the Surveillance tions for Operatien is to assure the Require =ents is to specify the type perfor=ance of the fuel reds.
and frequency of surveillance to be applied to the fuel rods.
Seecifications Soecificatiens A. Averaee Pianar Linear Heat Genera-A. Averate Planar Linear Heat Genera-
-tien Rate (APEGR) tion Rate ( APGGR)
During pe'ver operation, the APGGR The A?LEGR fc: each type of fuel as for each type of fuel as a fune:1on a function of average planar of average planar exposure shall exposure shall be de:er=ined hily not exceed the li=iting value shown during reacter operatien a: > 25%
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[ in Figure 3.11-1, sheets 1, 2 and 3.
rated ther=al power.
If at any ti=e during operati'en it is deter =ined by nornal surveillance tha: the li=iting value for APGGR is being exceeded, actica shall be initiated within 15 =inu:es to re-st:re c;eratien :: within the pre-scribed li=i.s.
If :he /2 00R is
- re:: ned :: within the pre-
-d s within tvc (2) hcurs,
scribed
- hen reduce res:::: pcuer to less than 25% of rated thernal pcver with-in the nex: f:ur (I.) hours.
If the li=i:ing cendi:icn fe: Opera:1:n is restored pric: :o expiration of the specified time in:erva', then further progressi:n :: less than 25% of ra:ed
- he =al pcuer is ac: required.
- 3. Linear Hee: Generation Rate (GGR)
- 3. Linear Heat Generatien Rate (GGR)
During power operatica, :he GGR as The GGR as function of core a fune:Lon of core height shall not height shall be checked daily dur-exceed the lici:ing value shown in ing reae:c operation a: > 25 yigure 3.11-2 for 7 x 7 fuel' c: the rated ther=al power.
11=1:ing value of ~ 3.4 'c.r/f: for S x 8/
3 x SR fuel.
If at any time during operati:n 1: is deter =ined by ner:al I
surveillance tha: the lini:ing value f
for *. EOR is being exceeded, ac:1on shall i
be ini:12:ed within 15 =ihu:es to res:cre Opera:ica :: vi:hin the prescribed 11:1:3.
If the 3 11-1 Amendrent No. if, 32, $s, 87 b
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Fuel Type P8DRB284 L121t.a.f_coer_ation f a.r
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- a.000 23.000 30.000 25.000 4,000.~
65.000
. 1000 _
P!.ANAR ALTRAC IX70$'.1l1 09i d/t)
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YPT CR193 Limit.of operstlos car I3" Oycle 53 x
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.cc u.ca F*.Amat AVERAG IIPOSLTE (Mi e/t) knendnent No. 87 Figure 3.11-1 (sheet 3)
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l 1,31 1.30 1.29 1.23 a._
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.. = -
1,37
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E 1.25 a
CC 1.25 w
1.24 1.23 1.22 0.0 x
1.0 MCPR LIMIT FOR 8X8R FUEL FIGURE 3.11.4 Amendment No. 36, 87
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1.31 1.30 1.20 1.28
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1.27 c
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1.26 -
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1.25 l.24
- 1. 2'3 1.22 1.0 0.0 x
MCPR LIMIT FOR PSX8R FUEL FIGURE 3.11.5 Amendment fio. E, 87
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1.31 1.30
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1.29
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1.23
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1.27 E 1.25 a
F
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1.2 1.23 1.22 0.0
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MCPR LIMIT FOR 7X7 FUEL FIGURE 3.11.6 Arendment I'o. 2I, 87 i
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