ML20108C381
| ML20108C381 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 10/31/1984 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Northern States Power Co |
| Shared Package | |
| ML20108C383 | List: |
| References | |
| DPR-22-A-027 NUDOCS 8411160543 | |
| Download: ML20108C381 (12) | |
Text
l ft'"**'*v UNITED STATES
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WASHINGTON, D. C. 20555 f-NORTHERN' STATES POWER COMPANY DOCKET N0. 50-263 MONTICELLO NUCLEAR GENERATING PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 27 License No. DPR-22 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Northern States Power Company (the licensee) dated May 29, 1984, as supplemented August 16, 1984, 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.
i 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, l
and paragraph 2.C.2 of Facility Operating License No. DPR-22 is hereby l
amended to read as follows:
2 Technical Specifications l
The Technical Specifications contained in Appendix A as revised through Amendment No. 27, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the
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Technical Specifications.
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8411160543 841031 PDR ADOCK 05000263 i
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This license amendment is effective as of the.date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION j:p
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m Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
October 31, 1984 s
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ATTACHMENT TO LICENSE AMENDMENT NO. 27 FACILITY OPERATING LICENSE NO. DPR-22 DOCKET NO. 50-263 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number ard contain vertical lines indicating the area of change.
Remove Insert 17 17 103 103 104 104 105a 106 106 107 107 114 114 116a 119 119 1
1 6
B_ases Continued:
backed up by the rod worth minimizer. Worth of individual rods is very low in a uniform rod pattern. Thus, of all possihte sources of reactivity input, uniform control red withdrawat is the most probable cause of significant power rise.
Because the flux distribution associated with uniform rod withdrawals does not involve high local peaks, and because several rods must he moved to change power by a significant percentage of rated power, the rate of power rise is very slow.
Generally..the heat flux is in near equilibrium with the fission rate.
In an assumed uniform rod withdrawal approach to the scram level, the rate of power rise is no more than 5% of rated power per minute, and the IRM system would be more than adequate to assure a scram before the power could exceed the safety limit.
The, IRM scram remains active until the mode switch is placed in the run position. This switch occurs when reactor pressure is greater than 850 psig.
The operator will set the APRM neutron flux trip setting no greater than that stated in Specifica-tion 2.3.A.I.
Iloweve r, the actual setpoint can be as much as 3% greater than that stated in Specification 2.3.A.1 for recirculation driving flows less than. 50% of design and 2% greater than that shown for recirculation driving flows greater than 50% of design due to the deviations discussed on page 39.
t B.
APRM Control Rod Block Trips Reactor power level may be varied by moving control rods or by varying the recirculation flow rate.
The APRM system provides a control rod block to prevent rod withdrawal beyond a given point at constant recirculate flow ra te, and thus to protect against the condition of a MCPR less than the Safety Limit (T.S.2.1.A).
This rod block trip setting, whic,h is automatically varied with recirculation loop flow rate, prevents an increase in the reactor power level to excessive values due to control rod withdrawal. The flow variable trip setting provides substantial margin from fuel damage, assuming a steady-state operation at the trip setting, over the entire recirculation flow ranga. The margin to the Safety Limit 1
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2.3 BASES 17 AmendmentNo.[,27
3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEII. LANCE REQllIREMENTS operation is permissible only during diesel generators required for the succeeding seven days ualess at operation of such components (if least one of such systems is sooner no external source of power were made operable, provided that during available) shall be demonstrated such seven days all active components to be operable immediately and of the LPCI mode of RiiR system and the daily thereafter.
diesel generators required for operation of such components (if no external source of power were available) shall be opera-ble.
- 4. Each core spray system shall be capable of delivering 3,020 gpm against a reactor pressure of 130 psig.
If this rate of delivery requirement cannot be met, the system shall be considered inoperable.
- 5. If the requirements of 3.5.A.1-3 cannot be met, an orderly shutdown of the reactor will be initiated and the reactor water temperature shall be reduced to less than 212*F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
1 3.5/4.5 103 Amendment No. 27
3.0 1.lHITING CONulTIONS FOR OPEPATION 4.0 SURVELLLANCE REQUIREMENTS B.
Low Pressure Coolant Injection (LPCI)
B.
Surveillance of the Low Pressure Coolant Subsystem (LPCI Hode of RHR System)
Injection (LPCI) Subsystem (LPCI Mode of RHR System) shall be perforned as follows:
- 1. Except as specified in 3.5.B.2 and I. Testing 3.5.B.3 below, the LPCI shall be operable whenever irradiated fuel Item Frequency is in the reactor vessel and reactor Pump Operability Once/ month coolant tempe ra tu re is greater than 212*F.
Motor operated valve Once/ month operability Cycling of RHR Once/Ouarter Intertie Line Valves Flow rate test Af ter major pump (recirculate to maintenance and torus) every three months Simulated automatic Every refueling actuation test outage
- 2. From and after the date that one of the
- 2. When it is determined that one of the LPCI pumps or admission valves is made LPCI pumps is inoperable, the remaining or found to be Inoperable for any reason, active components of the LPCI and con-reactor operation is permissible only tainment cooling subsystem, both core during the succeeding thirty days unless spray systems and the diesel generators such pump or admission valve is sooner required for operation of such components made operable, provided that durin'g such (if no external source of power were thirty days the remaining active components available) shall be demonstrated to be of the LPCI and containment cooling sub-operable immediately and the operable system and all active components of both LPCI pumps daily thereafter.
core spray systems and the diesel genera-tors required for operation of such com-ponents (if no external source of power were available) shall be operable.
3.5/4.5 104 Amendment flo. 27
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1.0 f.IllITith: CONDITIONS FOR OPERATION 4.0 StIRVEILI.ANCE REQllIREttENTS 6 Hoth RilR Intertie return line isola t ion va lves shal l be operable.
To be considered operable, each valve must be capable of automa tic closure on a 1.PCI initiation signal or he in the closed position.
If one valve is made or found to be Inope rable for any reason, the other return Line isolation valve and the HilR suction line isolation valve shall be closed, otherwise the actions speci fied in 3.5.B.3 shall be taken.
- 7. Plow shall not be established in the RilR intertie line with t'ie reactor in the Run flode.
8.
If the requirements of 3.5.B.1 through 3.5.B.4 cannot be met, an orderly sliutdown of the reactor shall be Initiated and the reactor water temperature shalI be reduced ta less than 212"F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
4 1.5/4.5 105a Amendment No. 27
3.0 LlHITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS Containment Cooling Capability Containment Cooling Capabiitty C. Residual lleat Removal (RilR) Service Water C. Surveillance of the RHR service water System system shall be performed e.s follows:
- 1. Except as specified in 3.5.C.2 and 3.5.C.3 1.
Testing below, both RHR service water system loops shall be operable whenever irradiated fuel Item Frequency is in the reactor vessel and reactor coolant Pump and valve once/3 months temperature is greater than 212*F.
operability Flow rate test After major pump maintenance and every three months
- 2. From and after the date that one of the 2.
When it is determined that one RilR RHR service water system pumps is made or service water pump is inoperable, found to be inoperable for any reason, the redundant components of the reactor operation is permissible only remaining subsystem shall be during the succeeding thirty days unless demonstrated to be operable immedi-such pump is sooner made operable, pro-ately and daily thereafter.
vided that during such thirty days all other active components of the RHR service water system are operable.
3.5/4.5 106 Amendment No. 27
3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMEffrS 3.
From and after the date that one of the
- 3. When one RilR service water system RilR service water systems is made or found becomes inoperable, the operable to be inoperable for any reason, reactor system shall be demonstrated to be operation is permissible only during the operable immediately and daily succeeding seven days unless such system thereafter.
is sooner made operable, provided that during such seven days aLL active compo-nents of the operable RilR service water system shall be demonstrated to be opera-ble at least once each day.
4.
To be considered operable, a RilR service water pump shall be capable of delivering 3500 gpm against a head of 500 feet.
5.
If the requirements of 3.5.C.1-3 cannot be met, an orderly shutdown of the reactor will be initiated and the reactor water temperature shall be reduced to less than 212*F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3.5/4.5 107 Amendment No. 27
9 3.0 I.ltlITIrlG Corl0!TIO!1S FOR OPERATION 4.0 SURVEII.LAtlCE REQUIRE!!EfffS
- 1. Recirculation System I. Recirculation System
- 1. I:eactor operat ion with one loop simil be See Specification 4.6.G.
1imited to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3.5/4.5 114 Amendment No. 27
Bases Continued:
An intertie line.is provided to connect the RilR suction line with the two RilR loop return lines.
This four-inch line is equipped with three isolation valves. The Rl!R. loop return line isolation valves receive a closure signal on LPCI initiation.
In the event of an inoperable return line isolation valve, there is a potential for some of the LPCI flow to be diverted to the broken loop during a loss of coolant accident. Surveillance requirements have been established to periodically cycle the RilR intertie line isolation valves.
In the ever.t of an inoperable s
RilR loop return line isolation valve, the other two isolation valves are closed to prevent diversion of LPCI flow.
The RilR intertie line is not used when the reactor is in the Run }fode to eliminate the need to compensate for the small change in jet pump drive flow or for a potential reduction in core flow during a loss of coolant accident.
L 3.5 BASES Il6a Amendment No. 27
Itases Continued 3.5:
G.
Emergency cooling Avattah111ty The purpose of Specification G is to assure that sufficient core cooling equipment is available at all times.
It is during refueling outages that major matntenance is performed and during such time that all core and containment cooling subsystems may be out of service. Specification 3.5.G.3 allows all core and containment cooling subsystems to be inoperable provided no work is being done which has the potential for draining the reactor vessel. Thus events respairing core cooling are precluded.
Specification 3.5.G.4 recognizes that concurrent with control rod drive maintenance during the refueling outage, it may be necessary to drain the suppression chamber for maintenance or for the inspection re< pit red by Specification 4.7. A. I.
In this situation, a sufficient inventory of water is maintained to assure adequate core cooling in the unlikely event of loss of control rod drive housing or _ instrument thimble seat integrity.
11.
1)eleted I.
Recirculation System 1:xtendtd operation with one reactor recirculation loop inoperable is prohibited until the NRC has completed an evaluation of single loop operation.
't.5 llASES 119 Amendment No. 27
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