ML17055E724
| ML17055E724 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 05/16/1989 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17055E725 | List: |
| References | |
| NUDOCS 8905300380 | |
| Download: ML17055E724 (26) | |
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 NIAGARA MOHAWK POl<ER CORPORATION DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. log 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 January 13, 1989, 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 for'th 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 s<ith 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.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable reouirements
'have been satisfied.
2.
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:
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(2)
Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 10', 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 its issuance to be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 16, 1989 Robert A. Capra, Director Project Directorate I-1 Division of Reactor Projects, I/II
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ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. l05 TO FACILITY OPERATING LICENSE NO.
DPR-63 DOCKET NO. 50-220 Pevise Appendix A as follows:
Remove Pa es 51 52 53 53a 54 55 56 160 161 163 164 Insert Pa es 51 52 53 54 55 56 163
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LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.1.4 CORE SPRAY SYSTEM 4.1.4 CORE SPRAY SYSTEM Applies to the operating status of the core spray systems.
O~b'ecti ve:
To assure the capability of the core spray systems to cool. reactor fuel in the event of a loss-of-coolant accident.
Applies to the periodic testing requirements for the core spray systems.
~Ob'ective:
To verify the operability of the core spray systems.
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b.
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Hhenever irradiated fuel is in the reactor vessel and the reactor coolant temperature is greater than 212'F, each of the two core spray systems shall be operable except as specified in Specifications b and c below.
If a redundant component of a core spray system becomes inoperable, that system shall be considered operable provided that the component is returned to an operable condition within 7 days and the additional surveillance required is performed.
If a redundant component in each of the core spray systems becomes inoperable, both systems shall be considered operable provided that the component is returned to an operable condition within 7 days and the additional surveillance required is performed.
The core spray system surveillance shall be performed as indicated below.
a.
At each major refueling outage automatic actuation of each subsystem in each core spray system shall be demonstrated.
b.
At least once per quarter pump operability shall be checked.
c.
At least once per quarter the operability of power-operated valves required for proper system operation shall be checked.
- .0302S 1P5 51
LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT If Specifications a,
b and c are not met, a normal orderly shutdown shall be initiated within one hour and the reactor shall be in the cold shutdown condition within ten hours.
check calibrate test Once/day Once/3 months Once/3 months d.
Core spray header 5 P instrumentation e.
During reactor operation, except during core spray system surveillance testing, core spray isolation valves 40-02 and 40-12 shall be in the open position and the associated valve motor starter circuit breakers for these valves shall be locked in the off position.
In
- addition, redundant valve position indication shall be available in the control room.
e.
Surveillance with Ino erable Com onents Hhen a component becomes inoperable its redundant component or system shall be demonstrated to be operable immediately and daily thereafter.
Hhenever irradiated fuel is in the reactor vessel and the reactor coolant temperature is less than or equal to 212'F, two core spray subsystems shall be operable except as specified in g and h
below.
f.
Hith a core spray subsystem suction from the
- g. If one of the above required subsystems becomes inoperable, restore at least two subsystems to an operable status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or suspend all operations that have a potential for draining the reactor vessel.
g.
At least once per month when the reactor coolant-temperature is greater than 212 F, verify that the piping system between valves 40-03, 13 and 40-01, 09, 10, 11 is filled wi th water.
105 52
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LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT
- h. If both of the above required subsystems become inoperable, suspend core alterations and all operations that have a potential for draining the reactor vessel.
Restore at least one subsystem to operable status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or establish secondary containment integrity within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
i.
Hith the downcomers in the suppression chamber having less than 3 ft.
submergence, two core spray subsystems and the associated raw water pumps shall be operable with the core spray suction from the condensate storage tanks (CST),
and the CST inventory shall not be less than 300,000 gallons.
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BASES FOR 3. 1.4 AND 4. 1.4 CORE SPRAY SYSTEM The core spray system consists of two automatically actuated, independent systems capable of cooling reactor fuel for a range of loss-of-coolant accidents.
Each of the two independent systems consists of 2 subsystems having one pump set of a core spray pump and core spray topping pump.
Both systems (at least one subsystem in each system) are required to operate to limit peak clad temperatures below 2200'F (10 CFR 50 Appendix K
model) for the worst case line break (recirculation line break at the point where the emergency condenser return line connects to the recirculation loop).
When a component/subsystem is in a LCO state, additional surveillance requirements are imposed for the redundant component/subsystem.
Consequently, application of the single failure criteria to. the redundant component/subsystem is not a design requirement during the LCO period.
Allowable outage time is specified to account for-redundant components that become inoperable.
Both core spray systems contain redundant supply pump sets and blocking valves.
Operation of one pump set and blocking valve is sufficient to establish required delivery rate and flow path.
Therefore, even with the loss of one of the redundant components, the system is still capable of performing its intended function. If a redundant component is found to have failed, corrective maintenance will begin promptly.
Nearly all maintenance can be completed within a few days.
Infrequently,
- however, major maintenance might be required, Replacement of principal system components could necessitate outages in excess of those specified.
In spite of the best efforts of the operator to return equipment to service, some maintenance could require up to 6 months.
In determining the operability of a core spray system the required performance capability of its various components shall be considered.
For example:
1.
Periodic tests will demonstrate that adequate core cooling is provided to satisfy the core spray flow
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requirements used in the 10CFR 50 Appendix K analysis.
2.
The pump shall be capable of automatic initiation from a low-low water level signal in the reactor vessel or a high containment pressure signal.
The blocking valves shall be capable of automatically opening from either a low-low water signal or high containment pressure signal simultaneous with low
. reactor pressure permissive signal.
(Section VII)*
- FSAR 105 (Proposed revision 6105G)
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BASES FOR 3.1.4 AND 4.1.4 CORE SPRAY SYSTEM Instrumentation has been installed to monitor the integrity of the core spray piping within the reactor pressure vessel.
t The testing specified for each major refueling outage will demonstrate component response upon automatic system initiation.
For example, pump set starting
( low-low level or high drywell pressure) and valve opening (low-low level or high drywell pressure and low reactor pressure) must function, under simulated conditions, in the same manner as the systems are required to operate under actual conditions.
The only differences will be that demineralized water rather than suppression chamber water will be pumped to the reactor vessel and the reactor will be at atmospheric pressure.
The core spray systems are designed such that demineralized water is available to the suction of one set of pumps in each system.
(Section VII-Figure VII-1)*
The system test interval between operating cycles results in a system failure probability of 1.1 x 10-6 (Fifth Supplement, page 115) and is consistent with practical considerations.
The more frequent component testing results in a more reliable system.
At quarterly intervals, startup of core spray pumps wi 11 demonstrate pump starting and operability.
No flow wi 11 take place to the reactor vessel due to the lack of a low-pressure permissive signal required for opening of the blocking valves.
A flow restricting device has been provided in the test loop which will create a low pressure loss for testing of the system.
In addition, the normally closed power operated blocking valves wi 1 1 be manually opened and re-closed to demonstrate operability.
The intent of Specification 3.1.4i is to allow core spray operability at the time that the suppression chamber is dewatered which wi 1 1 allow normal refueling activities to be performed.
Hi th a core spray pump taking suction from the CST, sufficient time. is available to manually initiate one of the two 'raw water pumps that provide an alternate core spray supply using lake water.
Both raw water pumps shall be operable in the event the suppression chamber was dewatered.
- FSAR (Proposed revision 6105G)
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BASES FOR 3.1.4 AND 4.1.4 CORE SPRAY SYSTEM (cont'd)
Based on the limited time involved in performance of the concurrent refueling maintenance
- tasks, procedural controls to minimize the potential and duration of leakage and available coolant makeup (CST) provides adequate protection against drainage of the vessel while the suppression chamber is drained.
Specification 3.1.4e establishes provisions to eliminate a potential single failure mode of core spray isolation valves 40-02 and 40-12.
These provisions are necessary to ensure that the core spray system safety function is single failure proof.
During system testing, when the isolation valve(s) are required to be in the closed condition, automatic opening signals to the valve(s) are operable if the core spray system safety function is required.
In the. cold shutdown and refuel conditions, the potential for a LOCA due to a line break is much less than during operation.
In addition, the potential consequences of the LOCA on the fuel and containment is less due to the lower reactor coolant temperature and pressures.
Therefore, one subsystem of a core spray system is sufficient to provide adequate cooling for the fuel during the cold s'hutdown or refueling conditions.
Therefore, requiring two core spray subsystems to be operable in the cold shutdown and refuel conditions provides sufficient redundancy.
(Proposed revision - 6105G) 105 56
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BASES FOR 3.3.7 AND 4.3.7 CONTAINMENT SPRAY SYSTEM suppression chamber pool.
Taking into account the reduced steam condensation capability and increased suppression chamber vapor pressure, the raw water cooling would not be required for more than 20 minutes for initial suppression chamber temperatures up to 110F.
This assumes that all core spray systems fail.
Therefore, manual initiation of the raw water system is acceptable.
Nearly all maintenance can be completed within a few days.
Infrequently,
- however, major maintenance might be required.
Replacement of principal system components could necessitate outages of more than 15 days.
In spite of the best efforts of the operator to return equipment to service, some maintenance could require up to 6 months.
In conjunction with containment spray pump operation during each operating cycle, the raw water pumps and associated cooling system performance will be observed.
The containment spray system shall be capable of automatic initiation from simultaneous low-low reactor water level and high containment pressure.
The associated raw water cooling system shall be capable of manual'actuation.
Operation of the containment spray system involves spraying water into the atmosphere of the containment.
Therefore, periodic system tests are not practical.
Instead separate testing of automatic containment spray pump startup will be performed during each operating cycle.
During pump operation, water wi 11 be recycled to the suppression chamber.
Also, air tests to verify that the drywell and torus spray nozzles and associated piping are free from obstructions will be performed each operating cycle.
Design features are discussed in Volume I, Section VII-B.2.0 (page VII-19*).
The valves in the containment spray system are normally open and are not required to operate when the system is called upon to operate.
The test interval between operating cycle results in a system failure probability of 1.1 x 10-6 (Fifth Supplement, page 115*) and is consistent with practical considerations.
Pump operability will be demonstrated on a more frequent basis and wi 11 provide a more reliable system.
- FSAR (Proposed revision
. 6105G) 163
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