ML18005B110
| ML18005B110 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 10/18/1989 |
| From: | Lainas G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML18005B111 | List: |
| References | |
| NPF-63-A-014 NUDOCS 8910240034 | |
| Download: ML18005B110 (6) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 0+**k CAROLINA POWER
& LIGHT COMPANY et al.
DOCKET NO. 50-400 SHEARON HARRIS NOCLEAR POWER PLANT UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.14 License No.
NPF-63 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Carolina Power 5 L>ght Company (the licensee),
dated February 22,
- 1989, as supplemented June 7, 1989, August 22, '1989 and October 11, 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 forth in 10 CFR Chapter I; B.
The facility wi 11 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 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 requirements 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.
NPF-63 is hereby amended to read as follows:
89i0240034 89i0i8 PDR ADGCK 05000400 PDC
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(2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, and the Environmental Protection Plan contained in Appendix B, both of which are attached
- hereto, as revised through Amendment No. 14, are hereby incorporated into this license.
Carolina Power 8 Light Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance.
'OR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications David B. Matthews/for Gus C. Lainas, Assistant Director for Region II Reactors Division of Reactor Projects I/II Office of Nuclear Reactor Regulation Date of Issuance:
October 18, 1989
- See previous concurrence C:L NAME.
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ATTACHMENT TO LICENSE AMENDMENT NO.
14 FACILITY OPERATING LICENSE NO. HPF-63 DOCKET NO. 50-400 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.
The revised areas are indicated by marginal lines.
Remove Pa es 3/4 9-10 8 3/4 9-2 Insert Pa es 3/4 9-10 B 3/4 9-2
REFUELING OPERATIONS LOW WATER LEVEL LIMITING CONDITION FOR OPERATION 3.9.8.2 Two independent residual heat removal (RHR) loops shall be
APPLICABILITY:
MODE 6, with irradiated fuel in the vessel when the water level above the top of the reactor vessel flange is less than 23 feet.
ACTION:
a.
With less than the required RHR loops OPERABLE, immediately initiate corrective action to return the required RHR loops to OPERABLE status or to establish greater than or equal to 23 feet of water above the reactor vessel flange as soon as possible.
b.
With no RHR loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required RHR loop to operation.
Close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />'URVEILLANCE RE UIREMENTS 4.9.8.2.1 At least one RHR loop shall be verified in operation and circulating reactor coolant at a flow rate of greater than or equal to 2500 gpm at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> whenever the water level is at or above the reactor vessel flange.
4.9.8.2.2 At least one RHR loop shall be verified in operation and circulating reactor coolant at a flow rate of greater than or equal to 900 gpm at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> whenever the water level is below the reactor vessel flange.
- The operating RHR loop may be removed from operation for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 2-hour period during the performance of CORE ALTERATIONS and core loading verification in the vicinity of the reactor vessel hot legs.
SHEARON HARRIS - UNIT 1 3/4 9-10 Amendment No.
14
REFUELING OPERATIONS BASES 3/4'.6 REFUELING MACHINE The OPERABILITY requirements for the refueling machine ensure that: (1) refuel-ing machine will be used for movement of drive rods and fuel assemblies, (2) each crane has sufficient load capacity to lift a drive rod or fuel
- assembly, and (3) the core internals and reactor vessel are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations.
3/4'.7 CRANE TRAVEL - FUEL HANDLING BUILDING The restriction on movement of loads in excess of the nominal weight of a fuel and control rod assembly and associated handling tool over other fuel assemblies in the storage pool ensures that in the event this load is dropped:
(1) the activity release will be limited to that contained in a single fuel assembly, and (2) any possible distortion of fuel in the storage racks will not result in a critical array.
This assumption is consistent with the activity release assumed in the safety analyses.
3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION The requirement that at least one residual heat removal (RHR) loop be in opera-tion ensures that:
(1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor vessel below 140'F as required during the REFUELING MODE, and (2) sufficient coolant circulation is maintained through the core to minimize the effect of a boron dilution incident and prevent boron stratification.
The requirement to have two RHR loops OPERABLE when there is less than 23 feet of water above the reactor vessel flange ensures that a single failure of the operating RHR loop will not result in a complete loss of residual heat removal capability.
With the reactor vessel head removed and at least 23 feet of water above the reactor pressure vessel
- flange, a large heat sink is available for core cooling.
Thus, in the event of a failure of the operating RHR loop, adequate time is provided to initiate emergency procedures to cool the core.
The minimum RHR flow requirement is reduced to 900 gpm when the reactor water level is below the reactor vessel flange.
The 900 gpm limit reduces the possibility of cavitation during operation of the RHR pumps and ensures sufficient mixing in the event of a MODE 6 boron dilution incident.
3/4.9.9 CONTAINMENT VENTILATION ISOLATION SYSTEM The OPERABILITY of this system ensures that the containment purge makeup and exhaust penetrations will be automatically isolated upon detection of high radiation levels within the containment.
The OPERABILITY of this system is required to restrict the release of radioactive material from the containment atmosphere to the environment.
SHEARON HARRIS - UNIT 1 B 3/4 9-2 Amendment No.
14