ML20148E011
| ML20148E011 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 05/28/1997 |
| From: | Stone J NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20148E016 | List: |
| References | |
| NUDOCS 9706020229 | |
| Download: ML20148E011 (5) | |
Text
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l UNITED STATES s
j NUCLEAR REGULATORY COMMISSION t
WASHINGTON, D.C. 20665 4)01 4
o 9.....g WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION DOCKET N0. 50-482 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.105 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 1
Wolf Creek Nuclear Operating Corporation (the Corporation), dated March 18, 1997, 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 Commission's regulations; D.
The issuance of this license 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.
9706020229 970528 PDR ADOCK 05000482 p
. 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. NPF-42 is hereby amended to read as follows:
2.
Technical Soecifications Tiie Technical Specifications contained in Appendix A, as revised through Amendment No.105, and the 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 Environmental Protection Plan.
3.
The license amendment is effective as of its date of issuance and shall be implemented within 30 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION w C.
Ja es C. Stone, Senior Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 28, 1997
ATTACHMENT TO LICENSE AMENDMENT NO. 105 FACILITY OPERATING LICENSE NO. NPF-42 DOCKET NO. 50-482 Replace the following page of the Appendix A Technical Specifications with the attached page.
The revised page is. identified by Amendment number and contain marginal lines indicating the areas tif change.
The corresponding overleaf page is also provided to maintain document completeness.
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ATTACHMENT TO LICENSE AMENDMENT N0. 105 FACILITY OPERATING LICENSE N0. NPF-42 DOCKET NO. 50-482 Replace the following page of the Appendix A Technical Specifications with the attached page. The revised page is identified by Amendment number and contain marginal lines indicating the areas 'of change. The corresponding overleaf page is also provided to maintain document completeness.
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_ EMERGENCY CORE COOLING SYSTEMS l
j 3/4.5.2 ECCS SUBSYSTEMS - T,yg > 350*F 19C '.'.ONDITION FOR OPERATION 3.5.2 OPERABLE with each subsystem comprised of:Two independent Emergency One OPERABLE centrifugal charging pump, a.
b.
One OPERABLE Safety Injection pump, One OPERABLE RHR heat exchanger, c,
d.
One OPERABLE RHR pump, and An OPERABLE flow path capable of taking suction from the refueling e.
water storage tank on a Safety Injection signal and automatically transferring suction to the containment sump during the recirculation phase of operation.
APPLICABILITY: MODES 1, 2, and 3.*
ACTION:
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 HOT 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.
In the event the ECCS is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describ-ing the circumstances of the actuation and the total accumulated actuation cycles to date.
The current value of the usage factor for each affected Safety Injection nozzle shall be provided in this Special Report whenever its value exceeds 0.70.
QThe provisions of Specifications 3.0.4 and 4 0 4 are not appli declared inoperable pursuant to Specification 4.5into MODE 3 for the ce charging pumps and the Safety Injection pumps are.3.2 provided the centrifugal restored 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 prior to the temperature of one or more of the RCS cold legs exceeding 375*F, whichever comes first.
WOLF CREEK - UNIT 1 3/4 5-3 J
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EMERGENCY CORE COOLING SYSTEMS 3/4.5.2 ECCS SUBSYSTEMS - T,yg >_ 350*F LIMITING CONDITION FOR OPERATION 3.5.2 Two independent Emergency Core Cooling System (ECCS) subsystems shall be OPERABLE with each subsystem comprised of:
a.
One OPERABLE centrifugal charging pump, b.
One OPERABLE Safety Injection pump, c.
One OPERABLE RHR heat exchanger, d.
An OPERABLE flow path capable of taking suction from the refueling water storage tank on a Safety Injection signal and automatically transferring suction to the containment sump during the recirculation phase of operation.
APPLICABILITY:
MODES 1, 2, and 3.*
2 ACTION:
a.
With one ECCS subsystem inoperable, restore the inoperable subsystem 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 HOT 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.
In the event the ECCS is actuated and injects water into the Reactor Coolant System, a Special Report shc11 be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describ-ing the circumstances of the actuation and the total accumulated actuation cycles to date.
The current value of the usage factor for each affected Safety Injection nozzle shall be provided in this Special Report whenever its value exceeds 0.70.
- The provisions of Specifications 3.0.4 and 4.0.4 are not applicable for entry into MODE 3 for the centrifugal charging pumps and the Safety Injection pumps declared inoperable pursuant to Specification 4.5.3.2 provided the centrifugal charging pumps and the Safety Injection pumps are restored 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 prior to the temperature of one or more of the RCS cold legs exceeding 375 F, whichever comes first.
WOLF CREEK - UNIT 1 3/4 5-3
EMERGENCY CORE COOLING SYSTEMS SVRVEILLANCE RE0VIREMENTS 4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE:
a.
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 witii oower to the valve operators removed:
Valve Number Valve Function Valve Position BN-HV-8813 Safety Injection to Open RWST Isolation V1v EM-HV-8802A(B)
SI Pump Discharge Closed Hot Leg Iso V1vs EM-HV-8835 Safety Injection Open Cold Leg Iso Valve EJ-HV-8840 RHR/SI Hot Leg Closed Recirc Iso Valve EJ-HV-8809A RHR to Accum Inj Open Loops 1 & 2 Iso V1v EJ-HV-8809B RHR to Accum Inj Open Loops 3 & 4 Iso V1v b.
At least once per 31 days by:
1)
Verifying that the ECCS piping is full of water by venting the ECCS pump casings and accessible discharge piping high points, and 2)
Verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.
c.
By a visual inspection which verifies that no loose debris (rags, trash, clothing, etc.) is present in the containment which could be transported to the containment sump and cause restriction of the pump suctions during LOCA conditions.
This visual inspection shall be performed:
1)
For all accessible areas of the containment prior to establishing CONTAINMENT INTEGRITY, and 2)
At least once daily of the areas affected within containment by containment entry and during the final entry when CONTAINMENT INTEGRITY is established.
d.
At least once per 18 months by:
1)
Verifying automatic interlock action of the RHR System from the Reactor Coolant System by ensuring that with a simulated or l
actual Reactor Coolant System pressure signal greater than or equal to 425 psig, the interlocks prevent the valves from being opened.
WOLF CREEK - UNIT 1 3/4 5-4 Amendment No. 49,105