ML20082V268
| ML20082V268 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 09/12/1991 |
| From: | Black S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20082V271 | List: |
| References | |
| NUDOCS 9109230188 | |
| Download: ML20082V268 (9) | |
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UNITED STATES
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WOLF CREEK NUCLEAR OPERATIN r0RPORATION WOLF CREEK GENERATING STATION DOCKET NO. 50-482 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 49 License No. NPF-42 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Wolf Creek Generating Station (the facility) Facility Operating License No. NPF-42 filed by the Wolf Creek Nuclear Operating Corporation (the Corporation), dated March 5, 1991, and supplemented on July 24, 1991, 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, as amended, 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 Conmission's regulations; D.
The issuance of this license amendment will not be inimical to the common defense and security or to the health and sa'ety'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.
9109230188 910912 DR ADOCK 050 B2
. l 2.
Accordingly, the license is amended by changes to the Technical Specifi-l cations as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of facility Operating License No. NPF-42 is hereby amended to read as follows:
2.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 49, and tne Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated in the license.
The Corporation shall operate the facility in accordance with the Technical Specifications and the Environmertal Protection Plan.
3.
The license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION ghwL N
Suzanne)C. Black, Director Project Directorate IV-2 Division of Reactor Projects - !!I/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
September 12, 1991 C
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1 ATTACHMENT 101.] CENSE AMENDMENT NO. 49 FACIL]iY OPERATING LICENSE NO. NPF-42 DOCKET NO. 50-482 Revise Appendix A lechnical specificationL by removing the pages identified be ow and inserting the enclosed pages.
The revised pages are identified by amendment number and contain marginal lines indicating the area of change.
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The corresponding overleaf popes are also provided to maintain document completeness.
REMOVE INSERT 3/4 4-35 3/4 4-35 3/4 b-4 3/4 5-4 B 3/4 4 13 8 3/4 4-13 L
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I SURVEILLANCE REQUIREMENTS 4.4.9.3.1 Each PORV shall be demonstrated OPERABLE by:
Performance of an ANALOG CHANNEL OPERATIONA a.
actuation channel, but excluding valve operation, within 31 da e PORV prior to entering a condition in which the PORV is required O and at leatt once per 31 days thereafter when the PORV is requ s
OPERABLE:
E red b.
at least once per 18 months; andPerformance of a CHANNE n channel when the PORV is being used it.. o.arpressure p c.
er 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 4.4.9.3.2 the RHR suction reitet valves are being used for coldEach RH as follows:
when uverpressute protection Far RHR suction relief valve 8708B:
a.
tion Valves (RRSIVs) 87018 and 8702B are openBy n Isola-b.
For RHR suction relief valve 8708A:
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By verifying at least once M r 72 hovs that RRSIVs 8701A are open, and 8702A Testing pursuant to Spccification 4.0.5.
c.
4.4.9.3.3 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
- when the vent (s) is being used for overpressureT e
protection. per
- Except when the vent pathway is provided with a valve or otherwise secured in the open position, then verify thesewhich is locked, scal least once per 31 days.
valves open at WOLF CREEK - UNIT 1 3/4 4-35 Amendment No. 49
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FIGURE 3.4-4 MAXIMUM Au0WED PORV SETPOINT FOR THE COLD OVERPRESSURE MITIGATION SYSTEM Amendment No. 40 3/4 4-36 WOLF CREEK - UNIT 1
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EMERGENCY CORE COOLING SYSTEMS 3/4.5.2 ECCS SUBSYSTEMS - Tavg 1 350 F
. LIMITING CONDITION FOR OPERATION 3.5.2 OPERABLE with each subsystem comprised of:Two independent Emergency a.
One OPERAP'c centrifcgal charging pump, b.
One OPERABL Safety injection pump, One OPERABLE RHR heat exchangct, c.
d.
One OPERABLE RHR pump, and An OPERABLE flow path capable of taking suction from the refueling e.
waterstoragetankonaSafetyinjectionsignalandautomatically transferring suction to the containment sump during the recirculation phase of opetation.
,APPLICAEILITY: MODES 1, 2, and 3.*
ACTI0tj:
With one ECCS subsystem inoperable, restore the inoperable subsystem a.
to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least H01 STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, b.
Coolant System, a Special Report shall be prepared and the Comraission pursuant to Specification 6.9.2 within 90 days describ-irig the circumstances of the actuation and the total accupulated attuation cycles to date.
The current value of the usage factor Special Report whenever its value exceeds 0.70.for each effected khe provisions of Specifications 3.0.4 and 4.0.4 are not applica declared inoperable pursuant to Specification 4.5.3into MODE 3 for th charging pumps and the Safety Injer. tion pumps are re.2 provided the centrifugal within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or prior to the temperature of one or more of the RCS cold legs stored to OPERABLE status exceeding 375 F, whichever comes first.
WOLF CREEK - UNIT 1 3/4 5-3
EMERGENCYCORECOOLINGSYSTEM SURVElllANCE REQUIREMENTS Each ECCS subsystem shall be demonstrated OPERABLE:
4.5.2 At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the following valves are in the indicated positions with power to the valve operators a.
removed:
Valve Number Valve %nction Valve Position BN-HV-8813 Safet frijection to Open RWST aclation Viv EM-HV-8802A(B) 51 Pump Discharge Closed Hot leg Iso Vivs EM-HV-8835 Safety injection Open Cold leg iso Valve EJ-HV-8840 RHK/51 Hot leg Closed Recirc Iso Valve EJ-HV-6809A RHR to Accum inj Open Loops 1 & 2 1so Viv EJ-HV-88098 RHR to Accum inj Open loops 3 & 4 Iso Viv b.
At least once per 31 days by:
Verifying that the ECCS piping is full of water by venting the 1)
ECCS pump casings and accessible discharge piping high points, and Verifying that each valve (ranual, power-operated, or automatic) 2)
in the flow path that is not locked, sealed, or otherwise secured in position, is in its corrett position.
By a visual inspection which verifies that no loose debris (rags, trash, clothing, etc.) is present in the containment which could be c.
trans,rted to the containment sump and cause restrictio1 sf the This visual inspection shall pump suctions during LOCA conditions.
be performed:
For all accessible areas of the containment prior ta 1) establishing CONTAINMENT INTEGRITY, and Of the areas affected within containment at the completion of 2) each containment entry when CONTAINMENT INTEGRITY is established.
d.
At least once per 18 months by:
Verifying automatic interlock action of the RHR System from the 1)
Reactor Coolant System by ensuring that with a simulated or ac+ual Reactor Coolant System pressure signal greater than or equal to 425 psig, the interlocks prevent the valves from being opened.
Amendment No. 49 3/4 5-4 WOLF CREEK - UNIT 3
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REACTOR COOLANT SYSTEM BASES I
i PRESSURE / TEMPERATURE LIMITS (Continued) i t
Following the generation of pressure-temperature curves for both the steady-state and finite heatup rate situations, the final limit curves are produced as follows.
A composite curve is constructed based on a point-by-point comparison of the-steady-state and finite heatup rate data.
At any given temperature, the allowable pressure is taken to be the lesser of the three values taken from the curves under consideration.
The use of the composite curve is necessary to set conservative heatup limitations ber.ause it is possible for conditions to exist such that over the course of the heatup ramp the controlling condition switches from the inside to the outside and the pressure limit must at all times be based on analysis-of the most critical criterion.
Although the pressurizer operates in temperature ranges above those for which there is reason for concern of nonductile failure, operating limits are provided to assure compatibility of operation with the fatigue analysis performed in accordance with the ASME Code-requirements.
The OPERABILITY of two PORVs, or two RHR suction relief valves, or an RCS vent opening of at least 2 square inches ensures that the RCS will be protected from' pressure transients which could exceed the limits of Appendix G to 10 CFR Part 50 when one or more of the RCS cold legs are less than or equal to 368'f.
Either PORV or either RHR suction relief _ valve has adequate relieving capability to protect the RCS from overpressurization when the transient is limited to either: (1) the start of an idle RCP with the secondary water temperature of the steam generator less than or equal to 50 F above the RCS cold leg tempera-tures, or (2) the start of a centrifugal charging pump and its injection-into a water solid RCS.
I In addition to opening RCS vents to meet the requirement of Specifica-tion 3.4.9.3c., it is acceptable to remove a pressurizer Code safety valve, open a PORV block valve and remove power from the valve operator in conjunction with disassembly of a PORV and removal of its internals, or otherwise open the RCS.
WOLF CREEK - UNIT 1 B 3/4 4-13 Amendment No. AB, 4 9 T
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REACTOR COOLANT SYSTEM SASES l
COLD OVERPRESSURE The Maximum Allowed PORV Setpoint for the Cold Overpressure Mitigation System (COMS) is derived by analysis which models the performance of the COM5
-assuming various mass input and heat input transients.
Operation with a PORV Setpoint less than or equal to the maximum Setpoint ensures that Appendix G criteria will not be vicisted with consideration for: (1) process and instru-mentation uncertainties; and (2) single failure.
To ensure mass and heat input transients more severe than those assumed cannot occur, Technical Specifications require lockout of both Safety Injection pumps and all but one centrifugal charging pump while in MODES 4, 5, and 6 with the reactor vessel head installed and disallow start of an RCP i' secondary coolant temperature is more than 50 F above reactor coolant temperature.
Exceptions to these requirements are accept-able as described below.
Operation above 350 F but less than 375 F with only one centrifugal charging pump OPERABLE and no Safety Injection pumps OPERABLE 1s allowed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
As shown by analysis LOCAs occurring at low temperature, low pressure conditions can be successfully mitigated by the operation of a single centrifugal charging pump and a single RHR pump with no credit for accumulator injection.
Given the short time duration and the condition of having only one centrifugal charging pump OPERABLE is allowed and the probability of a LOCA occurring during this time, the failure of the single centrifugal charging pump is not assumed.
Operation below 350 F but greater than 325 F with all centrifugal charging and Safety Injection. pumps OPERABLE is allowed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
During low pressure, low temperature operation all automatic Safety Injection actuation signals except Containment Pressure - High are blocked.
In normal conditions a-single failure of the ESF actuation circuitry will result in the starting of at most one train of Safety lnjection (one centrifugal charging pump, and one Safety injectionpump).
For temperatures above 325 F, an overpressure event occurring as a result of starting two pumps can be successfully mitigated by operation of both PORVs without exceeding Appendix G limit.
Given the short time duration that this condition is allowed and the low probability of a single failure causing an overpressure event during this time, the single failure of a PORV is not assumed.
Initiation of both trains of Safety Injection during this 4-hour time frame due to operator error or a single failure occurring during testing of a redundant channel are not considered to be credible accidents.
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Although COMS is required to be OPERABLE when RCS temperature is less than 368'F, operation with all centrifugal charging pumps and both Safety Injection pumps OPERABLE is acceptable when RCS temperature is greater than 350'F.
Should an inadvertent Safety Injection occur above 350'F, a single PORV has sufficient capacity to relieve the combined flow rate of all pumps.
Above 350 F two RCPs and all pressure safety valves are required to be OPERABLE.
Operation of an WOLF CREEK - UNIT 1 B 3/4 4-14 Amendment No. 40 l
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