ML20126L268

Amend 86 to License DPR-57,revising Tech Specs to Enable Plant Operation After Cycle 5 Reload,At Licensed Power

ML20126L268
Person / Time
Site:	Hatch
Issue date:	05/28/1981
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
ML20126L270	List: ML20126L268 ML20126L272 ML20126L277
References
TAC 43589, DPR-57-A-086 NUDOCS 8106020167
Download: ML20126L268 (9)

Text

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[pnea [o UNITED STATES g

NUCLEAR REGULATORY COMMISSION y b c(l/

g WASHINGTON, O. C. 20555 5 1 %3.b5tl;:: 5 E

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' GEORGIA POWER COMPANY OGLETITORPE POWER CORPORATION MUNICTPAL ELECTRIC AUTHORITY OF GEORGI A CITY OF DALTON, GEORGIA 00CXET NO. 50-321 EDWIN I. HATCH NUCLEAR" PLANT, UNIT NO.1 i

AMENOMENT TO FACILITY OPERATING LICENSE Amendment No. 86 License No OPR-57 1.

The Nuclear Regulatory Commission (the Commission) has fcund that:

A.

The application for amendment by Georgia Powe'r Company, et al.,

(the licensee) dated March 6,1981, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; S.

The facility will operate in confomity with the application, the provisions of the Act, and the rules and regulations of the Commission; There is reasonable assurance (i) that the activities authorized C.

by this amencment 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; l

The issuance of this amendment will not be inimical to the common D.

defense and security or to the health and safety of the public; and The issuance of this amendment is in accordance with 10 CFR Part E.

51 of the Commission's regulations and all applicable requirements have been satisfied.

Accordingly, the license is amended by changes to the Technical Spec-2.

ifications 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:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 86, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical. Specifications.

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Thislicenseamendmentiseffectiveasofthedateofitsfssuance.

FOR THE fiUCLEAR REGULATORY COMMISS10ti

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Johp F. Stolz, Chief Opgrating Reactors Branch #4 vision of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: May 28, 1981 5

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i ATTACHME.'iT 0 LICENSE AtiENDf!Eili fi0. 86 l

FACILITY OPERATIt'G LICENSE NO. OPR-57 l

DOCKET No.30-321 Replace the following pages of the Appendix "A" Technical Specifications with the enciesed pages.

The revised pages are identified by Amendment numoer and contain a vertical line indicating the area of change.

Insert

_R_emo ve 3..;-2 3.11-2 3.il-2a(new) 3.11-6 3.:1-6 Fi g. 3.11-4 (new)

Fig. 3.11-5 (new',

Fi g. 3.11-6 :'nea) l i

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-3.11.3 ' Linear Heat Generation Rate'(LHGR)-

- (Con ti nuec )

LHGR is.not' returned. to within the s

prescribed limits within two (2)-

hodrs, then reduce reactor power to less than 25t of rated thermal power

'within tre nex four (4) hours. If the l_imiting condition for operation is res cre, pricr to.expiraticn or.

the specified-time interval, then fur:her :recression':c less than 25%

of. rated thermal. pc*.er is not re-quireo.

1 C. Minimum Critical Power Ratio (MCPR) 4.11.C.1 Minimum Critical Power Ratio D'.CPRI The minimum crit'ical aower ratio MCPR shall be deter:1tnedtobb (MCFR) as.a function of scram time equal to or creater -han the and core flew, shall be ecual to or appif c,acie limit, daily during greater than shown in Figures 3.11.4, reactor power cperation a > 25%

3.11.5, or 3.11.5 mul:ipiied by the rated t..ermal pcwer and rolicwing K-shown in Ficure 3.11.3, where:

any enange in cower.le.m or dis-t tribution that would :ause opera-tion with a limiting cen:rci red i

= 0 or r'

• VS..,.

1 pattern as described in the. base:

0 A.T3;', whichever is for Specification 3.3.F.

T grea ter l

.=0.90 sec (Scecifications 3.3.C.2.a d.11.C.2 kinimumCriticalPowerRatioLimit

^ scram :ime-limi: to 20% insertica trem ru ty w,.thdrawn)

The MCPR iimit at rated flow shall

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be determined for each fuel type,

. N, " j 'u SX3R, F3XGP,, 7X7 from ficures (0.053)(Raf.101 3.11.j,3.11.5,and3.115re-

3=0.710+1.55(3

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r Nj spectiveiy using:

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a. ::1.0 prior to initial scram n

time measuremen:s for the J [y,..

cycle, performed in accordance l '1 i

' ave with spe:ifica:ior.s 4.3.C.2.a n.

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Nj or I

i=1

b. : as defined in specification 3.11.C.

n = n ' "~ = ' of surva411anca~ tasts m'qs t.- - r"'i ~- a - "n c #wi th;;n

' "' a l i "i '*

Tha +$

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performed to da e in cycle

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N = number of ac:ive control rods I

measured in :he ith surveillance or the :enclusion of each scram

.ime surveillance tes: required

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by specification 4.3.C.2.

i= Averace scram time.to 20", in-I sertion tr0m rully withdrawn of all rods measured in the i th surveillance tes t, and, N = total number of active rods 3

measured in 4.3.C.2.a.

f If at any time durir.g operation it is determined by normal surveillance that the limiting value for MCPR is being exceeded, action shall be Aaendment No. E, F, 57, X, 86 3.11-2

LIMITIhG,CONDlil0N5 FOR OPERATICM SURVEILLANCE REQUIREMENTS

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3.11.C Minimum Critical Power Ratio (MCPR)

(Continued) initiated within 15 minutes to restore operation to within the prescribed limits. If the steady s tate MCPR is not returned to within the prescribed limits within two (2) hours, then reduce reactor power to less than 25% of rated thermal pcwer within the next four (4) hours. If.

the Limiting Condi tion for Operation is res tored prior to expiration of the specified time interval, then further progression to less than 25% of rated thermal power is not required.

D. Recortina Recuirements If any of the limiting values iden-tified in Scecifica tions 3.11. A.,

S., or C. are exceeded, a Resor:able Occurrence report shall be submitted.

If the corrective action is taken, as described, a thirty-day written report will meet the requirements of this specification.

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Amendment No. 86 3.11-2a

IS FOR OPERATION N;D SURVEILLNiCE REOUIRE.SNTS l

BASES FOR LDtITI!!G C0!:DITIO:

l 3.11.E. References

1. General E1cetric Coepany Analytical Model for loss-of-Coolant Analysis I

in Accordance with 10 CFR 50, Appendix K, NEDE-20566-P, November,1975.

1 1

to SAFE Code

2. General Electric Refill Reflood Cal,culation (Supplement trans=itted to USAEC by letter, G. L. Cyorey to V. Stello, Description)

Jr., dated Dece=ber 20, 1974.

3. Edwin'I. Hatch Nuclear Plant Unit 1 Emergency Core Cooling System Analysis - Appendix K Require ent With Modified Low Pressure Coolant Injection System, NEDO-21137, Supplement 1, April, 1976.

4. " Fuel Densification Ef fects on Cencral Electric 3 oiling 'n'acer Reactor 1973.

Fuel", Supplements 6, 7, and 8, lfEDM-10735, August,

5. Supple =ent 1 to Technical Report on Densification of Cencral Electric Reactor Fuels, December 16,1974 (USA Regulatory Staf f).

7. A. Moore to I. S. Mitchell, " Modified CE Model for

6. Cc==unication:

Fuel Densificatien", Docket 50-321, >Mrch 27,1974

7. "Edwin I. Hatch Nuclear Plant Unit 1 Channel Inspection and Safety Analysis with 3ypass Flow Coles ? lugged", liEDO-21124-1, July,1976.

8. R. 3. Linf ord, Analytical Methods of Plant Transient Evaluations for 1the GE 3'ia, Tetruary,1973 (:TELO-10802).

9. Ceceral Electric 3 oiling

• tater Reactor Reload No.1 Licensing A=andment for the_Edwin I. Hatch Nuclear Plant tait 1 Full Core Drilled Conditions, NEDO-215 SO, Feb rua ry, 1977,

10. Letter from R. H. Buchholz (G. E.) to P. S. Check (NRC), " Response to for information on ODYN computer model", September 5,1980.

liRC request l

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