ML20136H012
| ML20136H012 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 12/23/1985 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | City of Dalton, GA, Georgia Power Co, Municipal Electric Authority of Georgia, Oglethorpe Power Corp |
| Shared Package | |
| ML20136H014 | List: |
| References | |
| DPR-57-A-119, TAC 59334 NUDOCS 8601090109 | |
| Download: ML20136H012 (10) | |
Text
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g NUCLEAR RE2ULATORY COMMISSION E
WASHINGTON, C. C. 20565
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GEORGTA POWER COMPANY OGLETHORPE POWER COP.P0 RATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGTA CITY OF DALTON, GEORGTA DOCKET NO. 50-321 EDWIN 1. HATCH NUCLEAR PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 119 License No. DPR-57 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Georgia Power Company, et al.,
(the licensee) dated August 1, 1985, 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; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; 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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications 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:
8601090109 851223 PDR ADOCK 05000321 P
PDR w
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.119, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMI STON f
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Daniel R. Muller, Director project Directorate #2 Division of BWR Licensing
Attachment:
Chances to the Technical Specifications Date of Issuance: December 23, 1985 i
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ATTACHMENT TO LICENSE AMEN 0 MENT NO.119 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 number and contain vertical lines indicating the area of change.
Remove Insert iv iv ix ix 3.6-9b 3.6-9b 3.6-10 3.6-10 3.6-11 3.6-11 through 3.6-14 (blank page) 3.6-12 3.6-13 3.6-14 3.6-23 3.6-23 3.6-24 3.6-24 through 3.6-30 (blank page) 3.6-25 3.6-26 3.6-27 3.6-28 3.6-29 3.6-30
Section Section Page LIMITDC CCCITIONS FCR OFSATICE SLRVEILIMG PFCliturlNIS 3.6 PRDiAFY SYSTDi BOUhTJRY 4.6 PRIMARY SYSID: BOCNP#Y 3.6-1 A.
Reactor Coolant Beatup A.
Reactor Coolant Beetup 3.6-1 i
and Cool h n and Cooldown t
B.
Reactor Vessel Tutperature 2.
Reactor vessel I4mperature 3.6-1 i
and Pressure and Pressure C.
Reactor Vessel Head Stud C.
Reactor Vessel Head Stud 3'6-2 Tensioning
'1%nsioning D.
Idle Recirculation Icop D.
Idle Recirculation Icop 3.6-2 Startup Startup E.
Recirculation Putp Start E.
Recirculation P ep Start 3.6-3 F.
Reactor Coolant Chenistry F.
Reactor Coolant Chenistry 3.6-4 G.
Reactor Coolant I4ekage G.
Reactor Coolant Leekage 3.6-7 H.
Safety and Relief Valves H.
Safety and Palief Valves 3.6-9 I.
Jet Pxps I.
Jet P mps 3.6-9 J.
Recirculation Pop Speeds J.
Recirculation Pop Speeds 3.6-10 K.
Structural Integrity K.
Structural Integrity 3.6-10 L.
Snubbers L.
Snubbers 3.6-10a 3.7 CCtCADEI2;T SYSUMS 4.7 CDUADMENT SYSUMS 3.7-1 A.
Prima:y Contaiment A.
P-imary Contaiment 3.7-1 B.
Starxity Gas Treat 2nent Systen B.
Standby Gas Treatment,Systen 3.7-10 C.
Secondary Contalment C.
Secondary Contaiment 3.7 -
D.
Primary Contaiment D.
Primary Chntaiment 3.7-13 Isolation Valves Isolation Valves 3.6 RADIO >CTIVE MA'!DlAIS 4.8 RADICACTIVE MATDIAIS 3.6-1
- A.
Miacellaneous Radioactive A.
W h 11 mous Radioactive 3.8-1 Meterials Sources Materials Sources 3.9 AUXILIARY E12CIRICAL SYSHMS 4.9 AUXILIARY II2CIRICAL SYSHMS 3.9-1 A.
Rm;uirements for Reactor
- A.
Auxiliary Electrical 3.9-1 Startup Systens Bluipment iv Amenthnent No. 37, yt,119 l
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LIST OF TABLES (Continued)
Table Title Paea 3.7-1 Primary Containmetnt Isolation Valves 3.7-16 3.7-2 Testable Penetrations with Double 0-Ring Seals 3.7-21 3.7-3 Testable Penetrations with Testable Bellows 3.7-22 3.7-4 Primary Containment Testable Isolation Valves 3.7-23 3.13-1 Fire Detectors 3.13-2 3.13-2 Fire Hose Stations 3.13-9 3.14.1-1 Radioactive Liquid Effluent Monitoring 3.14-2 Instrumentation 3.14.2-1 Radioactive caseous Effluent Monitoring 3'.14-7 Instrumentation 4.14.1-1 Radioactive Liquid Effluent Monitoring 3.14-4 Instr *tmentation Surveillance Requirements i
4.14.2-1 Radioactive Gaseous Effluent Monitoring 3.14-l'1 Instrumentation Surveillance Requirements 4.15.1-1 Radioactive Liquid Effluent Sampling and 3.15-2 Analysis Program 4.15.2-1 Radioactive Gaseous Waste Sampling and i 3.15-10 Analysis Program l
3.16.1-1 Radiological Environmental Monitoring Program 3.16-4 3.16.1-2 Reporting Levels for Radioactivity concentra-3.16-7
, tions in Environmental Samples j
4.16.1-1 Lower Limit of Detection 3.16-8 l
6.2.2-1 Minimum Shift Crew Composition 6-4 6.9.1.7-1 Environmental Radiological Monitoring Program 6-18 Susunary 6.9.2-1 Special Reporting Requirements 6-19 A
AmendmentsNos.$5.97.779.1)f.Il9 gg s
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and/or the low low s;t function of more than one of the above required rcacttr coolant system rolief/ safety valves inop;rablo, be in at least HOT SPUTDOWN with-in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and.in COLD SHUTDOWN within the next'24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3.6.I Jet Pumos 4,6 I.
Jet Pumps Whenever the reactor is in the Whenever both recirculating pumps Start & Hot Standby or Run Mode are operating with the reactor in with both recirculating pumps the Start & Hot Standby or Run operating, all jet pumps shall be Mode, jet pump operability shall operable. If it is determined that be checked daily by verifying that a jet pump is inoperable, an orderly the following conditions do not shutdown shall be initiated and the occur simultaneously.
reactor shall be in the Cold Shut-down Condition within 24 hows.
1.
The two recirculation loops have a flow imbalance of 15%
or more when the pumps are operated at the same speed.
- 2. The indicated value of core flow rate varies frcm the value derived fran Icep ficw measuraments by more than lot.
~
- 3. The diffuser to 1ower plenun differential pressure reading on an individual jet pump vary from the mean of all jet punp differential pressures by more than lot.
3.5.J.
Recirculatien Puno Seceds 4.6.J.
jiecirculation Pcum Sceeds
- 1. Cbre thermal power shall not exceed Recirculatica punp speeds shall be it of rated thermal power without recorded at least once per day.
forced recirculation.
- 2. Operation with a single recirculation pep is permitted for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless the recirculatien pump is smner made crerable. With one recirculatien e
p mp not_in operation, initiate action within 15 minutes or continue
(
acticm to reduce reactor power to or below the ifmit specifiaa in Figure 3.6-5 within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. If the m cannot be made operable or the limit of Figure 3.6-5 cannot be met within the required time, the reactor shall be in cold shutcown within 24 leurs.
- 3. Fellowing one Izzp operation the discharge valve of the low speed pu:p
, may not be opened unless the speed of the faster pump is less than 50% of
(,its rated speed.
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LIMITING CONDITIONS EDR OPERATION SURVEILIAN3 REQUIRENENIS 3.6.K STICAM. INTEGRITY 4.6.K S'IRUCIURAL INTEGRITY
- 1. Normal Condition Surveillance Req 11rements for in-service inspection and testing of ASME Cbde The structural integrity of ASME Class 1, 2, and 3 (eo2ivalent) conponents Code Class 1, 2, and 3 (eg2iva-shall be applicable alt follows:
lent) conponents shall be maintained in accordance with the
- 1. In-service inspection of ASME Surveillance Req 2irements of Code Class 1, 2, and 3 (ensivalent)
Specification 4.6.K.
components and in-service testing of ASME (bde Class 1, 2, and 3
- 2. Off-Normal Conditions (eolivalent) punps arx! valves shall be performed in accordance with a.
With the structural Section XI of the ASME Boiler and integrity of any ASME Code Press 2re Vessel Oxle and applicable Class 1 couponent not Addenda as reasired by 10CFR50, conforming to the above Section 50.55a(g), except where reo2irements, restore the specific relief has been structural integrity of granted by the Cbmission p2rsuant the affected ccaponent(s) to 10CFR50, Section 50.55a(g) to within its limit or (6) (1).
isolate the affected component (s) prior to increasing the Reactor
- 2. Performance of the above in-service Cbolant System tenperature inspection and testing activities more than 50oF above the shall be in addition to other mininum tenperature req 2 ired specified Surveillance by NDI' considerations.
Recuirements.
b.
With the structural integrity
- 3. Nothing in the ASME Boiler and of any ASME Code Class 2 Pressare Vessel (bde shall be cenponent(s) not conforming construed to aspersede the to the above ren2irements, req 2irements of any Technical restore the structural Specification.
integrity of the affected couponent(s) to within its limit or isolate the affected cocponent(s) prior to increasirg the Reactor Coolant System temperature above 2120F, c.
With the structural integrity of any ASME Code Class 3 component (s) not conforming to the above recuirements, restore the structural l
integrity of the affected conponent(s) to within its limit or isolate the affected component (s) from service.
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Amendment Nd. 77, H, Jpp, 119 g
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These pages have been left blank.
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Anendment No. pp,119 3.6-11 through 3.6-14 l
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BASES FOR LIMITING CDNDITIONS FOR OPERATION AND SURVEILIANCE REQUIRDENIS 3.6.K STRUCIURlb INITGRITY
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In-servide inspection of ASME Code Class 1, 2, and 3 (ecuivalent) cortponents and in-service testing of ASME Cbde Class 1, 2, and 3 (e<uivalent) punps and valves s%11 be performed in accordance with a periodically updated version of Section kI of the ASME Boiler and Pressare Vessel Code and Addenda as recuired by 10CE750.55a(g). This objective will maintain the structural integrity of safety-related certponents, punps, and valves which are necessary to safely slut down the plant or mitigate the consecuences of an accident.
Amendment NO.119 3.6-23
These pages have been left blank.
l Amendment No. 119 3.6-24 thrcugh 3.6-30 l