ML20118A844
| ML20118A844 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 09/21/1992 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20118A845 | List: |
| References | |
| NUDOCS 9209280278 | |
| Download: ML20118A844 (5) | |
Text
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UNITED STATES 3
/ i NUCLEAR REGULATORY COMMISSION
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GEORGIA POWER COMPA.JH QHLETHORPE POWER CORPORAllI%
MUNICIPAL ELECTRIC AUTHORITY Of GEORGla LITY Of DALTON. GE0E 1A DOCKET NO. 50-321 EDWIN 1. HATCH NUCLEAR PLANT. UNIT 1 BiENDMENT TO FAClllTY OPERATING llCEDJ.
Amendment No.182 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 July 17, 1992, as sunplemented July 30, 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 an.endment 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.
9209280278 920921 PDR ADOCK 0500 1
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~ 2.
Accordingly, the license is hereby amended by page cht.nges to the.
Technical Specifications as indicated in the attachment to this license dmendment, and paragraph 2.C.(2) of facility Operating License No. DPR-57 is hereby amended to read as follows:
lechnical Specifications The Technical Specifications contained in Appendix A and B, as revised through Amendment No.182, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective no later than 60 days from the date of issuance.
FOR THE NtlCLEAR REGULATORY COMMISSION LL ldi David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation attachment:
Technical Specification Changes Date of issuance:
September 21. 1992 i
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ATTACHMENT TO LICENSE AMENDMENT NO.182 LACILITY 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 number and contain vertical lines indicating the areas of change.
Remove Paaes insert Pagel 3.5-10 3.5-10 3.9-5 3.9-5 l'
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LIM 111NG CON 0lfl0NS FOR OPIRAY10N SURyflLLANCE Ft0UlRfMIN15 3.$.G.
Minimum Core and Connainment 4.$.G. Surveillance of Cere and Centain.
Coolina 5vstems avat ability ment Coolino Systers During any period when one of
/sen it is determined that one I
the standby diesel generators of the stanosy diesel generators is inoperable, continued reactor is inoperable. all of the compo-operation is limited to 7*
l nents in the RHR system LPCI days unless operability of the mode and containment cooling t
diesel generator is restored mode connected to the operable within this period. During such dietel generators shall be veri-7* days all of the components l
fled to be operable.
in the RHR system LPCI mode and containment cooling mode mode shall be operable. if this requirement cannot be met, an orderly shutdown shall be initi-ated and the reactor shall be in the Cold shutdown Condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. $pecification 3.9. provides further guidance on electrical system availability.
Any combination of inoperable components in the core and con-tainment cooling systems shall not defeat the capability of the remaining operable components to fulfill the core and contain-ment cooling functions.
When irradiated fuel is in the reactor vessel and the reactor is in the Cold Shutdown Condi-tion, both CS systems and the LPCI and containment cooling subsystems of the RHR system may be inoperable provided that the shutdowq cooling subsystem of the RHR system is operable in accordance with $pecification 3.5.B.I.b and that no work is being done which has the potential for draining the reactor vessel, i
t aihe IB diesel generator may be inoperable for up to 14 days during the Hatch bnit 2 tenth refueling outage to perform preventative maintenance and modification work, HATCH - UNIT 1 3.5-10 Almendment hk). 182
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... LIMlfl E CO O111 25 fGR QPLRAllW 9J'VElllME kluulRI.MNTS 3.9.8.1. QDt_litriuo Auxiliary Transdormet 4.9.B.l. 00t_116tiuo Aalliary Transdomet MC er 10) Inocerable or Ori y One flC or 10) inocerable or km Qffsite Power %irte Available Of fsite Poser Sourte Available g}o kv 1ranwission Line)
(230kVTransmissionLine)
Reactor operation is pemissible Whenitisestablishedthatone I
for seven days frtre the date that startup auxiliary transformer one startup autliary transforwr (IC or ID) is iroperable or in-(1C or 10) is inoperable or in-ccning power is available frta ecntrg powr is available frtn only one 230 kV offsite trans-only one 230 kV offsite trans-mission line, verify cornet mission line provided the in-breaker aligreents and indica-creased Surveillance Ragstre ted power availability within sents as stated in Specification one tour and at least once per 4.9.B i. are iglemented, eight hours thereafter, ard perform Surveillance Paquire-ment 4.9.A.2.a.1 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, j
- 2. One Diesel Generator flA.18.
- 2. Qut.Dittel G e erator flA. I L or IC) Incoerable or IC) Inoc rable Frta and after the date that one When it is establisted that one of the diesel generators is eade dieselgenerator(IA,IB,orIC) or found to to inoperable, continued isinoperable,verifycornet nactor operation is pemist.itle in breaker alignments and indicated accordance with specification 3.6.C.
power availability within one tour for a period not to exceed seven and at least once per eight hours days
- pmvided that two D0 kV off-l thereafter, ard perforn $urveill-sitt transmission lines are avail.
ance Requirenent 4.9.A.2.a.1 withinl
&ble, toth twraining diesel gen.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, anti every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> erators and associated emergency thereafter, buses are operacle, and the in-creased Surveilla.te Ragairirents as stated in $pecification 4.9.B.2.
are trolenented.
- 3. One 125/250 Volu OC Power Systm
- 3. Orc 125/250 Volt DC Power Sysi g (P' ant Battery lA or IB) Inocer-iP ant Batterv 1A or IB) Inocen Frtn and after the date that one When it is established that one of of the two 125/250 volt plant bat-the 125/250 volt DC power systems twies is sade or found to te in-(plant battery 1A or IB) is made operable, continued reactor oper-or found to te inoperable, the ation is pervisilble durire the pilot call voltage and specific succeedingseven(7)dayswithin gravity and the overall battery electrical salaty considerations, voltage of the operable plant bat-provided mpair work is inittaind tery shall be testad daily and de-intnedtately to mturn the failed termined to be satisfactory.
comonent to an operable state, Specification 3.5.G. is satisfied, i e IB diesel generator may te inopernole foc up to 14 daya Th durtrq the Hatch Unit 2 tenth refueling outage to perfom preventative maintenance and codification work.
mTCH - Ltd1 1 3.9-5
/m ndment No. 18?