ML20236E024
| ML20236E024 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 02/26/1982 |
| 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 | |
| ML20236E028 | List: |
| References | |
| TAC 47893, NPF-05-A-026 NUDOCS 8710290030 | |
| Download: ML20236E024 (7) | |
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GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTH'ORITY OF GEORGI A CITY OF DALTON, GEORGIA-DOCXET NO. 50-366 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No, 26 License No. NPF-5 1.
The Nuclear Regulatory Commission (the Commission) has found that:
s A.
The application for amendment by Georgia Power Company, et al.,
(the licensee) dated January 22, 1982, 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; B.
The facility will operate in confonnity 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; i
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 Commission's regulations and all applicable requirements have been satisfied.
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. NPF-5 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and
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B, as revised through Amendment No. 26, are hereby incorporated
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in the license. The licensee shall operate the facility in I
accordance with the Technical Specifications.
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' 3..This amendment is. effective as of the date of issuance.
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FOR THE NUCLEAR' REG LATORY COMMISSION
. JInF.Stolz, Chief
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Attachment:
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. Changes:to the. Technical H
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Date-of Issuance: February 26, 1982
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. ATTACHMENT TO LICENSE AMEN 0 MENT NO. 26 l-
FACILITY OPERATING LICENSE NO. NPF DOCKET NO. 50-366 3
Replace the' following pages of the' Appendix "A" Technical, Specifications i
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.with the enclosed pages. The revised pages are' identified by Amendment number and contain vertical lines indicating the area of change. T he -
overleaf pages are provided to maintsin. document completeness.
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3/4 9-4 3/4 9 4 s
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REFUELING OPERATIONS _
3/4.A 2_ INSTRUMENTAL 10N LIMITING CONDITION FOR OPERATION At least 2 source range monitor * (SRM) channels shall be OPERABLE 3.9.2 and inserted to the normal operating level:
Each with continuous visual indication in the control room, a.
At least one with an audible alarm in the control room, b.
One of the SRM detectors located in the quadrant where CORE c.
ALTERATIONS are being performed and the other SRM detector located in an adjacent quadrant, and The " shorting links" removed from the RPS circuity during CORE d.
ALTERATIONS and shutdown margin demonstrations.
APPLICABILITY: CONDITION 5.
ACTION:
With tne requirements of the above specification not satisfied, imediately suspend all operations involving CORE ALTERATIONS ** or positive reactivity changes and actuate the manual scram.
The provisions of Specification 3.0.3 are not applicable.
1 SURVEILLANCE REQUIREMENTS 4.9.2 Each of the above required SRM channels shall be demonstrated OPERABLE by:
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a.
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />; l
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Performance of a CHANNEL CHErK, 2.
Verifying the detectors are inserted to the normal operating level, 3.
During CORE ALTERATIONS, verifying that the detector of an OPERABLE SRM channel is located in the core quadrant where CORE ALTERATIONS are being performed and one is located in the adjacent quadrant.
- The use of special movable detectors during CORE ALTERATIONS in place of the normal SRM nuclear detectors is permissible as long as these special detectors are connected to the normal SRM circuits.
- Except movement of SRM or special movable detectors.
HATCH - UNIT 2 3/4 9-3 l
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1 INSTRIJENTATION -
SURVEILLANCE REQUIREMENTS CONTINUED b.
Performance of a CHANtEL FUNCTIONAL TEST:
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the start of CORE ALTERATIONS, and 1.
i 2.
At least.once per 7 days.
Vei; Tying that the channel count rate is at least 3 cps at least'
' once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during CORE ALTERATIONS,'. and at least once per 24 c.
hours, except:
1.
The 3 cps is not. required during core alterations involving only fuel unloading provided the SRMs were confirmedito read at least 3 eps initially and. were checked for neutron response.
2.
The. 3 cps is not required - initially on a full core reload.
Prior to the reload, two diagonally adjacent fuel assemblies will be leaded into their previous core positions next to each of the 4 SRMs to obtain.the required count rate.
Verifying that the RPS circuitry " shorting-links" have been removed d.
and that the RPS circuitry is in a non-coincidence trip mode within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to starting-CORE ALTERATIONS or shutdown margin demonstrations.
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3/4 M Menhed M.
M HATCH - UNIT 2
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3/4'.9 RERJELING (PERATIONS
'8ASES 3/4.9.1 REACTOR MODE SWITCH Locking.the OPERABLE reactor hode switch in the refuel' position ensures that the restrictions on rod withdrawal and refueling ~ platform movement during the refueling operations are properly activated.. These' conditions reinforce
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' the refueling procedures and reduce the probability of inadvertent criticality, l
damage'. to reactor internals or fuel assemblies, and exposure of personnel to excessive radioactivity.-
3/4.9.2 INSTRUMENTATION _'
The OPERABILITY' of at least two source range monitors. ensures that
' redundant monitoring. capability is available to detect-changes in the During the unloading, it is not necessary to' reactivity condition of the core.lterations will involve only reactivity removar
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zmaintain 3 eps because core a The loading of diagonally adjacent bundles 1
and.will not result. in criticality.
around the SRMs before attaining the 3 cps is permissible because these bundles were. in'succritical. configuration when they were removed and therefore will remain subcritical when placed back in the previous positions.
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'3/4.9.3 CONTROL ROO POSITION The requirement 'that ' all control rods be inserted during CORE ALTERATIONS fuel will not be loaded' into' a ec11 without a control rod and ensures that prevents two positive reactivity changes from occurring simultaneously.
3/4.9.4 DECAY TIME ~
i The minimum requirement for reactor suberiticality prior to fuel movement short lived fission products.
This decay time is consistent with the ensures that sufficient time has elapsed to allow the radioactive. decay of the assumptions used in the accident analyses.
3/4.9.5 SECONDARY CONTAI*ENT i
Secondary containment is designed to minimize any ground level release of y
The reactor building radioactive material which may result from an accident.during normal operation wh l
containment provides secondary sealed and in service, when the reractor is shutdown or during refueling, the be open and the reactor building then becomes the primary drywell may The refueling floor is maintained under the secondary containment containment.
integrity of Hatch-Unit 1.
Establishing and maintaining a vacuum in the building with the standby gas treatment system once per 18 months, along with the surveillance of the doors, hatches and dampers, is adequate to ensure that there are no violaticns of the integrity of the secondary containraent.
Only one closed damper in each penetration line is required to maintain the integrity of the secondary y
containment.
B 3/4 9-1 Amendment No. 26 HATCH - UNIT 2
1 REFUELING OPERATIONS _
i BASES 3/4.9.6 COPNUNICATIONS_
The requirement for communications capability ens res inat refueling station personnel can be promptly infonned of significant changes in the facility status or core reactivity condition during movement of fuel within the reactor pressure vessel.
l 3/4.9.7 CRANE AND HOIST OPERABILITY The OPERABILITY requirements of the. cranes and hoists used for movement (1) each has sufficient load capacity to of fuel assemblies ensures that:
lift a fuel element, and (2) the core internals and pressure vessel are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations.
3/4.9.8 CRANE TRAVEL-SPENT FUEL STORAGE POOL The restriction on movement of loads in excess of the nominal weight of a fuel element over irradiated fuel assemblies ensures that no more than the contents of one fuel assembly will be ruptured in the event of This assumption is consistent with the activity a fuel handling accident.
release assumed in the accident analyses.
WATER LEVEL-REACTOR VESSEL AND WATER LEVEL-SPENT 3/4.9.9 and 3/4.9.10 STORAGE POOL The restrictions on minimum water level ensure that sufficient water depth is available to remove 99% of the assumed 10% iodine gap activity This minimum released from the rupture of an irradiated fuel assembly.
i water depth is consistent with the assumptions of the accident analysis, f
3/4.9.11 CONTROL R00 REMOVAL This specification ensures that maintenance or repair of control rods or control rod drives will be performed under conditions that limit the The requirements for simultaneous probability of inadvertent criticality. removal of more than one centrol r MARGIN specification provides for the core to remain subcritical with only one control rod fully withdrawn.
HATCH - UNIT 2 B 3/4 9-2
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