ML17053A839
| ML17053A839 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 06/11/1979 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17053A840 | List: |
| References | |
| NUDOCS 7907240378 | |
| Download: ML17053A839 (16) | |
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, +o UNITEDSTATES NUCLEAR REGULATORYCOMMISSION
'ASHINGTON, D. C. 20555 NIAGARA MOHAWK POWER CORPORATION DOCKET NO. 50 220 NINE MILE POINT NUCLEAR STATION UNIT NO.
1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 32 License No.
DPR-63, 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Niagara Mohawk Power Corporation (the licensee) dated May 29, l979, 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 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 Commiss'ion'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.
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.
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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 No. DPR-63 is hereby amended to read as follows:
(2)
Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 32, 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 the date of i ts issuance.
7i fOR THE NUCLEAR REGULATORY CS1hiISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
June ll, 1979 omas Ippolito, Chief Operating Reactors Branch t3 Division of Operating Reactors
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p ATTACHMENT TO LICENSE AMENDMENT NO. 32 FACILITY OPERATING LICENSE NO.
DPR-63 DOCKET NO. 50-220 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 6
6a 13 64b 70b Insert 6
6a 13 64b 70b
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SAFETY LIHIT LIHITING SAFETY SYSTEH.SETTING C.
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- d. I The neutron flux shall not exceed its scram setting for longer than 1.5 seconds as indicated by the process computer.
When the process computer is out of service, a safety limit violation shall be assumed if the neutron flux exceeds the scram setting and control rod scram does not occur.
To ensure that the Safety Limit established in Specifications 2.l.la and 2.l.lb is not
The Safety Limit shall be assumed to be exceeded when scram is accomplished by a means other than the expected scram signal.
During all operating conditions with irradiated fuel in the reactor vessel, the water level shall not be more than 7 feet ll inches (127.1 inches indicator scale) below minimum normal water level (Elevation 302'9"), except as specified in "e" below.
d.
e.
g.
The reactor water low level scram trip setting shall be no lower than -12 inches (53 inches indicator scale) relative to the minimum normal water level (302'9");
The reactor water low-low level setting for core spray initiation shall be no less than -5 feet (5 inches indicator scale)
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relative to the minimum normal water level (Elevation 302'9").
The reactor low-low-low level setting shall be no less than 7'll" (127.1 inches indicator scale) below minimum normal water level.
The flow biased APRM rod block trip settings shall be less than or equal to that shown in Figure 2. 1.1.
During all operating conditions with irradiated fuel in the reactor vessel, at least two (2) re-circulation loop suction valves and their associated discharge valves will be in the full open position except when the reactor vessel is flooded to a level above the main steam nozzles or when the steam separators and dryers are removed.
For the purpose of performing major maintenance in the shutdown mode only (not to exceed 12 weeks in duration) on the reactor vessel, the reactor water level may be lowered 9'elow the minimum normal water level (Elevation 302'9").
When-ever the reactor water level is to be lowered to more than 7 feet 11 inches below minimum normal water level, redundant
'...strumentation will be provided to monitor the reactor water leva].
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SAFETY LIMIT Written procedures will be developed and followed whenever the reactor water level is lowered below the low-low level set point.
(5 feet below minimum normal water level)
The procedures will define the valves that will be used to lower the vessel water level.
All other valves that have the potential of lowering the vessel water level will be identified by valve number in the procedures and -these valves will be red tagged to preclude their operation during the major maintenance with the water level below the low-low level set point.
In addition to the Facility Staff requirements given in Specification 6.2.2.b, there shall be another control room operator present in the control room with no other dutieS than to monitor the reactor vessel water level.
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. BASES FOR 2.1.1 FUEL CLADDING SAFETY LIMIT The lowest point at which the water level can normally be monitored is approximately 4 feet 8 inches above the top of the active fuel.
This is the low-low-low water level trip point, which is 7 feet ll inches (127.1 inches indicator scale) below minimum normal water level (Elevation 302'9").
The safety limit has been established here to provide a
point which can be monitored and also can provide adequate margin for core heat removal.
During periods when the reactor is shut down, consideration must also be given to water level requirements, due to the effect of decay heat.
If reactor water level should drop below the top of the active fuel during this time, the ability to cool the core is reduced.
This reduction in core cooling capability could lead to elevated cladding temperatures and clad per-foration.
The core will be cooled sufficiently to prevent clad melting should the water level be reduced to two-thirds of the core height.
However, the. performing major maintenance as specified in Specification 2.1.le, redundant instrumentation will be provided for monitoring reactor water level below the,low-low-low water level set point.
(For example, by installing temporary instrument lines and reference pots to redundant level transmitters, so that the reactor water level may be monitored over the required range.)
In addition written procedures, which identify all the valves which have the potential of lowering the water level inadvertently, are established to prevent their operation during the major maintenance which requires the water level to be below the low-low-low level set point.
Also a safety limit on the recirculation loop isolation is provided to ensure adequate maintaining water level.
The thermal power transient resulting when a scram is accomplished other than by the expected scram signal (e.g.,
scram from neutron flux following closure of the-main turbine stop valves) does not necessarily cause fuel damage.
However, for this specification a safety limit violation will be assumed when a scram is only accomplished by means of a backup feature of the plant design.
The concept of not approaching a safety limit provided scram signals are operable is supported by the extensive plant safety analysis.
Amendment No
, 32 13
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LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT If at any time during power operation it is
. determined by normal surveillance that the limiting value for the power/flow relation-ship is being exceeded, action shall be initiated within 15 minutes to restore operation to within the prescribed limits'f the power/flow relationship is not returned to within the prescribed limits within two (2) hours, reactor power reductions shall be initiated at a rate not less than 105 per hour until the power/flow relationship is within the prescribed limits.
Recirculation Loo s During all operating conditions with irradiated fuel in the reactor vessel, at least two (2) recirculation loop suction valves and their associated discharge valves will be in the full open position except when the reactor vessel is flooded to a level above the main steam nozzles or when the steam separators and dryer are removed.
Re ortin Re uirements If any of the limiting values identified. in Specification 3.1.7.a, b,
c and d are
- exceeded, a Reportable Occurrence Report shall be submitted.
If the corrective action is taken, as described, a thirty-day written report will meet the requirements of this Specification.
Amendment No. lC >%~ pl.
S2 64b
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BASES FOR 3.1.7 AND 4.1.7 FUEL RODS Recirculation Loo s Requiring the suction and discharge for at least two (2) recirculation loops to be full open assures. that an adequate flow path exists from the annular region between the pressure vessel wall and the core shroud. to the core region.
This provides for coamunication between those areas thus assuring that reactor water level instrument readings are ~
indicative of the water level in the core region..
When the reactor vessel is flooded to the level of the main steam line nozzle, comnunication between the core region and annulus exists above the core to ensure that indicative water level monitoring in the 'core region exists.
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the steam separators and dryer are removed, safety limit 2..1. ld and e requires water level to be higher than 9 feet ~
below minimum normal water level (Elevation 302'9").
This level is above the core shroud elevation. which would ensure coranunication between the core region and annulus thus ensuring indicative water level monitoring in the core region.
Therefore, maintaining a recirculation loop. in the full open position in these two instances are not necessary to ensure indicative water level monitoring.
Re ortin Re uirements The LCO's associated with monitoring the fuel rod operating conditions are required to be met at all times, i.e.,
there is no allowable time in which the plant can knowingly exceed. the'imiting values of. MAPLHGR. LHGR, NCPR, or Power/Flow Ratio. It is a. requirement, as stated in Specifications 3.1.7a, b, c 8 d that if at. any time during power operation, it is determined that the limiting values'for NAPLHGR, LHGR, NCPR, or Power/Flow Ratio are
- exceeded, action is then initiated to restore opet'ation to within the prescribed limits.
This action is initiated as soon as normal surveillance indicates that an operating limit has been reached.
.Each. event inv'olving operation beyond a specified limit shall be reported as a Reportable Occurrence.
If the specified corrective action described in the LCO's was taken, a thirty-day written report is acceptable.
Amendment No.g, g3, 32 70b
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