ML20004C318
| ML20004C318 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 05/26/1981 |
| 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 | |
| ML20004C319 | List: |
| References | |
| TAC 43822, TAC 43823, DPR-57-A-085 NUDOCS 8106030061 | |
| Download: ML20004C318 (6) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION E
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. \\ *....f GEORGIA POWER COMPANY OGLETh0RPE POWER CORPORATION MUNICTPAE ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET NO. 50-321 EDWIN -I. HATCH NUCLEAR PLANT. UNIT"NO.1 AMENDfENT TO FACILITY OPERATING LICENSE Amendment No. 85 License No. DPR-57 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Georgia Power Company, et al.,
(the licensee) dated May 4',1981, complies with the s+andards and requirements of the Atomic Energy Act of 1954, at amended (the Act) and the Commission'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 Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of tSe public, and (ii) that such activities will bu 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 this amendment is in accordance with 10 CFR Part 51 of the Ccmmission's regulations and all applicable requirements have been satisfied.
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e 2.
Accordingly, the license is amended by changes to the Technical Spec-ifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. OPR-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. 85, are hereby incorporated in the license. The licensee shall operate the facility in l
accordance with the Technical Specifications.
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- 3. - This -amandment is'~ effective as of the date of i'ssuance.
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FOR THE NUCLEAR REGULATORY COMMISSION
^ uf J ihn F.. Stolz,- Ch f perating-Reactors-Branch #4-
- Division of Licensing.-
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Attachment:
Changes to the Technical
. Speci fications '
Date of_ Issuance: May. 26,1981-t 4
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x4. Li A1TACHMENT TO LICENSE"AMENDMENI NO.
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~ FACILITY OPERATING LICENSE NO. OPR-57 :
DOCKET NO.150-321 Repl' ace the following pages of.the A'ppendix "A". Technical. Specifications with the enclosed pages. The revised pages are' identified by Amendment number and contain vertical lines indicating the area of change.
Remove Insert-
- 3.6-9a
- 3.6-9a 3.7-26 3.7-26 3.7-27 '
3.7-27 o
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.l LIMITDIG CC?QITIO;iS FOR OPEPATION SURVEILIANCE R2QUIRL'fENTS 4.6.H.
Relief / Safety Valves (Continued) 5.
Operability of Tail Pipe Pressure
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Switches a.
Functional Test:
- 2. At each scheduled outage greater than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> during which entry is made into the pri=ary containment, if not perfor=ed within the previous-31 days.
b.
Calibration and verify.ing the setpoint to be 30 j; 5 psis at l
least once per 18 conths.
.I.
Jet Pu=es I. Jet Pu=es Whenever the reactor is in the Whenever both recirculating pu=ps Start & Eat Standby or Run Mode are operating with the reactor in
-vith both recirculating pu=ps the Start & Ect Standby or Run ikde, operating, all jet pu=ps shall be jet pu=p operability shall be checked operable.
If it is determined that daily by verifying that the folleving a fet pu=p is inoperable, an orderly conditiens do not occur si=ultaneously.
shutdown shall be initiated and the reactor shall be in the Cold Shut-
- 1. The two recirculation loops have down Condition with 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
a flow i= balance of 15% or' nore when the pu=ps are operated at the sa=a speed.
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Amendment No. 77, 85 3.6-9a
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. Table 3.7-4
-(Concluded)
Primary Cont'airment' Testable Isolation Valves Penetration M;mber
. Valve Designation Notes X-220
-P33-F006 & F014 (1) (2) (4)-(5) (9)-
~X-220
.T48-F318 & F326 X-220 T48-F332A & F333A
'X-220-T48-F3329 & F3338 X-220 T48-F338 & F339 X-218A
-G51-F002 (1) (2) (4) (5) (10)
~X-218A G51-0001 (1) (2) (4)-(5) (13)
X-218A G51-F0,16 (1) (2) (4) (5) (14)
X-218A G51-0004-(1) (2) (4) (5) (13) a
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Amendment.No. 53, 85 3.7-26
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Notes For Tables 3.7-2 throuch 3.7-4 (1).
-Test duration for all valves and penetrations listed will generally exceed one hour.
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(2)-
Test pressures are 'at least' 59 psig for all valves and penetrations except MSIV's which are tested at 28 psig.
- (3)~
MSIV acceptable, leakage limit is 11.5 scfh/ valve of air.
(4)-
The total acceptable ' leakage for all; valves and penetrations other than the l'SIV's is 0.6 La-(5)-
Local leak tests on all. testable isolation' valves shall be performed each major refueling shutdcwn but in no -case at intervals greater than 2 years.
(6)
' Local leak tests on all testable penetrations shall be p'erformed each major refueling shutdown but in no case at intervals greater
-- than 2 years.
(7).
The perscnnel air lock shall.be tested at intervals not to exceed 6 months.
(8)
The oersonnel air lock dcor seals are tested at 10 psig after each opening.
(9)
Identi'les isolation valves that are tested by applying pressure
' betweer the inboard and outbcard isolation valves.
Inboard valve is not tested in the direction required for isolation but will have equivalint or more conservative leakage results.
(10) identiff es isolation valves that are tested %y applying pressure between the isolation valve and a manually coerated valve such that the is,lation valve is tested in' the direction required for isolat!cn.
(11)
Identi 'ies isolation valves that are. tested by acolying pressure betwer :) the isolation valves and other system valves.
Isolation valves not tested in the direction required for isolation will have equivalent or more conservative results.
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(12)
The r+R system remains water filled post-LCCA.
Isolatien valves are tasted with water.
(13)
Identifies blind flange that is tested by applying pressure between the fiange and a manually operated valve such that the flange is tested in the directicn recaired for isolation.
(14)
Identifies an isolation valve that is tested by applying pressure between the manually ocerated isolation valve and a blind flange.
The isolaticn valve is not tested in the direction required for isolation but will have equivalent or more ccnservative results.
Amendment No. M, 35-3.7-27 i
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