ML20039E600
| ML20039E600 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 12/18/1981 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20039E601 | List: |
| References | |
| TAC-47390, NUDOCS 8201110069 | |
| Download: ML20039E600 (2) | |
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NUCLEAR REGULATORY COMMISSION gg gy j -
=:=mren. m. e. 2 ens g,j j N..CA f NORTHEAST NUC'. EAR ENERGY CCMPANY THE CONNECTICUT LIGHT AND PC'4ER COMPANY THE HARTFORD ELECTRIC LIGHT CCMPANY THE WESTERN MASSACHUSETTS ELECTRIC COMPANY DOCKET NO. 50-336 MILLSTONE NUCLEAR PC'4ER STATION, UNIT NO. 2 AMENOMENT TO FACILITY OPERATING LICENSE Amendment No. 71 License No. OPR-65 1.
The Nuclear Regulatcry Ccenission (the Ccenission) has found that:
A.
The application for amendment by Northeast Nuclear Energy Company (the licensee) dated Decem5er 2,1981, as supplemented by letter dated Decem5er 18,1931, complies with the standards and require-ments 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; E.
The f acility will ccerate in ecnfermity with the a;plicatien, the previsiens of the Act, and the rules and regulations of the Ccrmissien; C.
There is reasenable assurance (i) that the activities autherized by this amendment can te cenducted without endangering the health and safety of the public, and (ii) that such activities will be cenducted in ccepliance with the Cennissicn's regulatiens; D.
The issuance cf this a:endment will not be inimical to the ccc.cn defense and security er to the health and safety cf the public; and E.
The issuance of this amenc=ent is in acccreance with 10 CFR Part 51 of the Ccenissien's regulatiens and all acplicable recuire=ents have been satisfied.
8201110069 811218 PDR ADOCK 05000336 P
ATTAC'-! MENT 70 LICENSE AMENCMENT NO,71 FACILITY OPERATING LICENSE NO. OPR 00CXET NO. 50-336 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. The corresponding overleaf pages are also provided to maintain document completeness.
Pages 3/4 9-8 3/4 9-8a B 3/4 9-2 9
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-n REFUELING OPERATIONS CRANE TRAVEL - SPENT FUEL STORAGE POOL BUILDING LIMITING CONDITION FOR OPERATION 3.9.7 Loads in excess of 1800 pounds shall be prohibited from travel over irradiated fuel assemblies in the storage pool.
APPLICABILITY: DURING ALL CRANE OPERATION.
ACTION:
With the requirements of the above specification not satisfied, place load in a safe condition.
SURVEILLANCE REOUIREMENTS_,
4.9.7 Crane interlocks and/or physical stops which prevent crane travel with loads in excess of 1800 pounds over irradiated fuel assemblies shall be demonstrated OPERABLE within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior to initiation of irradiated fuel handling cperations and at least once per 7 days during irradiated fuel handling operations.
MILLSTONE - UNIT 2 3/4 9-7
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REFUELING OPERATIONS SHUTDOWN COOLING AND COOLANT CIRCULATION LIMITING CONDITION FOR OPERATION 3.9.8.1 At least one shutdown cooling loop shall be in operation *,
APPLICABILITY: MODE 6 at all reactor water levels.
ACTION:
With less than one shutdown cooling loop in operation, suspend all operations involving an increase in the reactor decay heat load or a reduction in boron concentration of the Reactor Coolant System. Close all containment penetra-
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tions providing direct access from the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
3.9.8.2 Two independent shutdown cooling loops shall be OPERABLE **.
APPLICABILITY: MODE 6, whenever all the foliowing conditions are not satisfied:
a.
reactor vessel water level at or above the vessel flange; and b.
the reactor vessel pit seal installed; and c.
the combined available volume of water in the refuel pool and refueling water storage tank exceeds 370,000 gallons; and d.
(1) one LPSI pump not in shutdown cooling service and aligned to take suction from the RWST and deliver flow to the RCS is OPERABLE,**; or (2) one HPSI pump aligned to take suction from the RWST and deliver flow to the RCS is OPERABLE.**
ACTION:
With let than the required shutdown cooling loops OPERABLE, initiate correc-tive action to return the loop (s) to CPERABLE status within one hour.
The provisions of Specification 3.0.3 are not applicable for 3.9.8.1 and 3.9.8.2.
- The shutdown cooling loop may be removed from operation for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period during the performance of CORE ALTERATIONS in the vicinity of the reactor pressure vessel hot legs.
- The normal or energency power source may be inoperable for each shutdown cooling loop.
' MILLSTONE-UNIT 2 3/4 9-8 Amendment No. 69, 71
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4 REFUELING OPERATIONS SURVEILLANCE REQUIREMENT 3 4.9.3.1 At least one shutdown cooling loop shall b'. verified to be in operation and circulating reactor coolant at a flow rate consistent with l
decay heat requirements at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
4.9.8.2 Once per 7 days, the required shutdown cooling loops, if not in operation, shall be determined OPERABLE by verifying correct breaker align-ments and-indicated power availability for pump and shutdown cooling valves, or:
Verifying that the reactor vessel water level is at or above the vessel flange, the reactor vessel pit seal is installed, and greater than 370,000 gallons of water is available as a heat sink, as indicated by either:
a.
refuel pool level greater than 23 feet above the reactor vessel flange, or b.
the combined volume of the refuel pool and refueling water storage tank exceeds 370,000 gallons and a flow path is available from the refueling water stcrage tank to the refuel pool.
MILLSTONE - UNIT 2 3/4 9-8a Amendment No. 71 g
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3/4.9 REFUELING OPERATIONS BASES 3/4.9.1 BORON CONCENTRATION The limitations on minimum boron concentration ensure that: 1) the reactor will remain subcritical during CORE ALTERATIONS, and 2) a uniform baron concentration is maintained for reactivity control in the water volumes having direct access to the reactor vessel. The limitation on Keff of no greater than 0.90 is sufficient to prevent reactor criticality with all full length rods (shutdown and regulating) fully withdrawn.
3/4.9.2 INSTRUMENTATION Tne OPERABILITY of the source range neutron flux monitors ensures that redundant monitoring capability is available to detect changes in the reactivity condition of the core.
3/4.9.3 DECAY TIME The minimum requirement for reactor subcriticality prior to movement of irradiated fuel ensures that sufficient time has elapsed to allow the radioactive decay of the short lived fission products. This decay time is censistent with the assumptions.used in the accident analyses.
3/4.9.4 CONTAINMENT PENETRATIONS The requirements on containment penetration closure and OPERABILITY ensure that a release of radioactive material within containment will be restricted from leakage to the environment. The OPERABILITY and closure restrictions are sufficient to restrict radioactive material release from a fuel element rupture based upon the lack of containment pressur-ization potential while in the REFUELING MODE.
3/4.9.5 COMMUNICATIONS The requirement for ccmmunications capability ensures that refueling station personnel can be promptly informed of significant changes in the facility status or core reactivity condition during fuel or CEA movement within the reactor pressure vessel.
MILLSTONE - UNIT 2 B 3/4 9-1
REFUELING OPERATIONS BASES 3/4.9.6 CRANE OPERABILITY - CONTAINMENT BUILDING The OPERABILITY requirements of the cranes used for movement of fuel assemblies ensures that: 1) each crane has sufficient load capacity to 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.
3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE BUILDING.
The restriction on movement of loads in excess of the nominal weight of a fuel assembly and CEA over irradiated fuel assemblies ensures that no more than the contents of one fuel assembly will be ruptured in the event of a fuel hand-ling accident. This assumption is consistent with the activity release assumed in the accident analyses.
3/4.9.B SHUTDOWN COOLING AND COOLANT CIRCULATION The requirement that at least one shutdown cooling loop be in operation ensures that (1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel below 140*F as required during the REFUELING MODE, and (2) sufficient coolant circulation is maintained through the reactor core to minimize the effects of a boron dilution incident and prevent boron stratification.
The requirement to have two shutdown cooling loops OPERABLE when the refuel pool is unavailable as a heat sink ensures that a single failure of the operating shutdown cooling loop will not result in a complete loss of decay heat removal capability. With the reactor vessel water level at or' above the vessel flange, the reactor vessel pit seal installed, and a combined available volume of water in the refueling pool and refueling water storage tank in excess of 370,000 gallons, a large heat sink is readily available for core cooling. Adequate time is thus available to initiate emergency procedures to provide core cooling
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in the event of a failure of the operating shutdown cooling loop.
3/4.9.9 and 3/4.9.10 CONTAINMENT RADIATION MONITORING AND CONTAINMENT PURGE VALVE ISOLATION SYSTEM The OPERABILITY of these systems ensures that the containment purge valves will be automatically isolated upon detection of high radiation levels within
- ne containment. The OPERABILITY of these systems is required to restrict the release of radioactive material from the containment atmosphere to the environment.
3/4.9.11 and 3/4.9.12 WATER LEVEL-REACTOR VESSEL AND STORAGE POOL WATER LEVEL The restrictions on minimum water level ensure that sufficient water depth is available to remove 99% of the assumed 10% iodine gap activity released from the rupture of an irradiated fuel assembly. The minimum water depth is consistent with the assumptions of the accident analysis.
MILLSTONE - UNIT 2 B 3/4 9-2 Amendment No. 6), 71
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