ML20092C298
| ML20092C298 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 01/30/1992 |
| From: | Larkins J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20092C301 | List: |
| References | |
| NUDOCS 9202110401 | |
| Download: ML20092C298 (7) | |
Text
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[gD8 080go, UNITED STATES 8 ' 3 #,, i NUCL EAR REGULATORY COMMISSION e
wasHINotoN. o c. 20bM s
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p fllL(RGY OPERATIONS. INC.
SYSTEM ENERGY RES0QRCES. ItJC.
SOUTH tilSSISSipPI ELECTRIC POWER ASSO(1ATION
[i S$1551PPI P_QWER AND llGHT COMPANJ ROCKET N0. 50-411 GRAND GU! F NUCLEAR STATION. UNIT 1 AMENDMENT TO FAClllTY OPERATING LICENSE Amendment No. 83 License No. NPf-29 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the licensee) dated September 25, 1991, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's rules t.nd 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 the public, and (ii) that such activities will be 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.
.e issuance of this amendment is in accordance with 10 CFR Part 51 of the Commi>sion's regulations and all applicable requirements have been satisfied, 9202110401 820130 r
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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 fio. NPF-29 is hereby amended to read as follows:
(2) Jechnical Specificpilgni The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 88, are hereby incorporated into this license.
Entergy Operations, Inc. shall operate the facility in accordance with the Tecnnical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATOR ( COMMISSION
- f.
- John T. Larkins, Director Project Directorate IV-1 Division of Reactor Projects 111, IV, and V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical.
Specifications Date of Issuance: January 30, 1992 o
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i ATTACHt4Ef4T TO llCENSE AMENDMENT NO. 88 i
FAClllTY OPERATit4G tl W [SL NO, NPF-29 QQCKET NO. 50-415 l
Replace the following pages of the Appendix A Technical Specifications with F
l the attached pages.
The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
The corresponding overleaf pages are also provided to maintain document completeness.
r REMOVE 1ASU If15ERT PAGU 3/_4 9-8 3/4 9-8 8 3/4 9-1 8 3/4 9--I
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REFUELING OPERA?!0NS 3/4.9.5 COMMUNICATIONS i
LIMITING CONDITION FOR OPiRATION i
- 3. 9. 5 Direct communication shall be maintained between the control room and refueling platform personnel.
APPLICAB!!!TY:
OPERATIONAL CONDITION S, during CORE ALTERATIONS."
ACTION:
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When direct communicatien between the control room and refueling platform personnel cannot be maintained, immediately suspend CORE ALTERAi10NS."
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SURVEILLANCE RtQUIREMENTS 4.9.5-Direct communication between the control room and refueling platform personnel shall be demonstrated within one hour prior to the start of-and 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.*
i "Except movement of control rods with their normal drive system.
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l GRAND-GULF-UNIT 1 3/4 9 7 Amendment No. 35l h-
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REFUELING OPERATIONS 3/4.9.6 REFUELING EQUIPMENT REFUELING PLATF0,RJ LIMITINGCONDITIONFOROPERAl10N 3.9.6.1 TherefuelingplatformshallbeOPERABLEandonlythema[nhoist using the following shall be used for handling fuel essemblies:
a.
NF-500 mast, or b.
NF-400 mast APPLICABILITY:
During handling of fuel assemblies or control rods in the primary confainment with the refueling platform.
ACTION:
With the requirements for refueling platform OPEkABILITY not satisfied suspenduseofanyinoperablerefuelingplatforeequipmentfromoperatIons involving the handling of fuel assemblies or control rods af ter placing tht load in a safe condition.
SURVEILLANCE REQUIREMENTS 4.9.6.1 Each refueling platform hoist to be used for handling fuel assemblies or control rods shall be demonstrated OPERABLE within 7 days prior to the handling of fuel assemblies or control rods:
a.
In the containment fuel pool, reactor cavity or reactor pressure vessel by:
1.
Demonstrating operation of the black cable cutoff on the main hoist when the total cable load is 50110 pounds.
2.
Demonstrating operation of the-grapple engaged loaded interlock on the main hoist hefore the total cable load exceeds 750(535)*
I pounds.
3.
Demonstrating operation of the jam cutoff on the main hoist before the total cable load exceeds 1430(1250)* pounds.
l 4.
Demonstrating operation of prime.ry and redundant overload cutoff on the auxiliary hoists before the load exceeds 550 pounds.
5.
In or over the reactor pressJre vessel by:
1.
Demonstrating operation of the downtravel cutoff on the main-hoist when the bottom of the grapple is L 1.0 inch above the top guide.
2.
Demonstrating operation of the primary and redundant fuel load r
interlocks on the main toist before the total cable load exceeds 750(600)* pounds.
- When the NF-400 mast is in use, setpsints in () apply for these surveil 1ance requirements.
GRAND CULF-UNIT 1 3/4 2-8 Amendment No.
55, 8
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3/4.9 REFUELING OPERATIONS E.ASES 3/4.9.1 REACTOR MODE SWITCH Locking the OPERABLE reactor mode switch in the Shutdown or Refuel position, as specified, ensures that the restrictions on control rod withdrawal and refueling platform movement curing the refueling operations are properly activated. These cond1tions reinforce the refueling procedures and reduce the probability of inadvertent criticality, 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 rance monitors ensures that redundant monitoring capability is available to detect changes in the reactivity condition of the core.
3/4.9.3 CONTROL ROD POSITION The requirement that all control rods be inserted during other CORE ALTERATIONS ensures that fuel will not be loaded into a cell without a control roa.
3/4.9.4 DECAY TIME The minimum requirement for reactor subcriticality prior to fuel movement ensures that sufficient time has elapsed to allow the radioactive decay of the short lived fission products.
This decay time is consistent with the assump-tions used in the accident analyses.
3/4.9.5 COMMUNICATIONS The requirement for conrrunications capability ensures that refueling station personnel can be promptly informed of significant changes in the facility status or core reactivity condition during movement of fuel within the reactor pressure vessel.
3/4.9.6 REFUELINGEQUIPMENJ The OPERABILITY requirements ensure that (1) only the main hoist of the refueling platform or the main hoist of the fuel handling platform will be used for handling fuel assemblies within the reactor pressure vessel, (2) pistform hoists have suf ficient load capacity for handling fuel assemblies and/or control rods (3) the core internals and pressure vessel are protected from excessive
. lifting force in the event they are inadvertently engaged during lifting operations, and (4) a fuel bundle is protected from excessive lifting force in the event it becomes stuck during lifting operations.
GRAND GULF-UNIT 1 B 3/4 9 1 Amendment No. 88
REFUEL 1NC R ERATIONS BASES 3/4.9.7 CRANE TRAVEL - SPENT FUEL AND UPPER LONTAINMENT FUEL STORAGE P_00LS The restriction on novement of loads in excess of the nominal weight of a fuel 6ssembly over otner fuel ast 3mblies in the storage pools ensures that in the event this load is dropped (1) the activity release will be limited to that contained in a single fuel assembly, Und (2) any possible distortion of fuel in the str' age racks will not re;.'t h t critical array.
This assumption is cor.sistent with the activity rP s,e assumed in the safety caalyses.
3/4.9.8 and 3/4.9.9 WATER LEVEL REACTOR VESSEL and WATER LEVEL - SPENT FUEL ANDUPPERCONTAINWNTFUELSTORAGEP00Q The restrictions on minimum water level ensure that sufficient water depth is available to remove 99% of the assumed 10% iodine gap activity releaseri from the rupture of an irradiated fuel assembly.
This minimum water depth is consistent with the assumptions of the accident analysis.
3/4.9.10 CONTR0'. ROD REMOV3 These specifications ensure that maintenance or repair of control rods or control rod drives will be performed under conditions that limit the probability of inadvertent criticality.
The requirements for simultaneous removal of more than one control rod are m.
e stringent since the SHUTDOWN MARGIN specification provides for the core to remain subtfitical with only one control rod fully withdrawn, 3/4.9.11 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION An OPERABLE residual heat removal (RHR) system shutdown cooling mode train consists of at least one OPERABLE RHR pump and one OPERABLE RHR heat exchanger train.
The requirement that at least one residual hest removal loop be OPERABLE and in operation er that an alternate method capable of decay heat removal be demonstrated and uat an alternate method of coolant mixing be in operation ensures that (1) sufficient cooling capacity is available to remove decay heat E"
and reintain the water in the reactor pressure vessel below 140'F as required durin, REFUELING, and (2) sufficient coolant circulaticn would be available through the reactor core to assure accurate temperature indication and to distribute and prevent stratification of the poison in the event it becomes necessary to actuate the standby liquid control syt. tem.
The requirement to have two shutdown cooling mode loops OPERABLE when there is less than 22 feet 8 inches of water above the reactor vessel flange ensure) that a single failure of the operating loop will not result in a complete losa of residual heat removal capability, With the reactor vessel head removed and 22 feet 8 inches of water above the reactor vessel flange, a large heat sink is available for core cooling.
Thus, in the event a failure of the operating RHR loop, adequate time is provided to initiate citernate methods capable of decay heat removal er emergency procedures to cool the core.
GRAND GULF-UNIT 1 B 3/4 9-2 Amendment No. 2D R