ML20006B934
| ML20006B934 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 01/23/1990 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20006B935 | List: |
| References | |
| NUDOCS 9002060107 | |
| Download: ML20006B934 (9) | |
Text
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g NUCLEAR REGULATORY COMMISSION 3
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DUKE POWER COMPANY i
l NORTH CAROLINA ELECTRIC MEMBERSHIP' CORPORATION SttUDA RIVER ELECTRIC COOPERATIVE. INC.
DOCKET NO. 50-411 CATAWBA NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE 1
Amendment No. 69 License No. NPF-35 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the Catawba Nuclear Station, Unit 1 (the facility) Facility Operating License No. NPF-35 filed by the 4
Duke Power Company acting for itself, North Carolina Electric Membership) Corporation and Saluda River Electric Cooperative, Inc.,
(licensees dated April 6, 1989, as supplemented September 6, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regula-tions as set forth in 10 CFR Chapter I; P.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; I
L C.
There is reasonable assurance (i) that the activities authorized by I
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 Comission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the comon.
defense and security or to the health and safety of the public; and
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E.
The. issuance of this amendment is in accordance with 10 CFR Part 51-of the Comission's regulations and all applicable requirements have been satisfied.
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E.
Accordingly, the license is hereby anenoea hy page 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-35 is herehy amended to read as follows:
)
Technical Specifications The Technical Specifications contait,od in Appendix A, as revised through Amendment No. 69
, are hereby incorporated into the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environnental Protection Plan.
3.
This license amendment is effective as of its date of issuance.-
FOR THE NUCLEAR REGULATORY COMMISSION f n h k. N.
l' David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance: January 23, 1990 i
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UNITED STATES p,
NUCLEAR REGULATORY COMMISSION 7.
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CUKE POWER COMPANY NORTH CAROLINA K'NICIPAL POWER AGENCY NO. I l
PIEDMONT MUNICIPAL POWER AGENCY
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DOCKET NO. 50-414 CATAWBA NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATit'G LICENSE
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Amendment No. 63 License No. NPF-52
-l 1.
The Nuclear Regulatory Commission (the Connission) has found that:
A.
The application for amendment to the Catawba huclear Station, Unit 2 (the facility) Facility Operating License No. NPF-52 filed by the Duke Power Company acting for itself, North Carolina Municipal Power Agency No.1 and Piedmont Municipal Power Agancy (licensees) dated April 6,1989, as supplemented Septenber 6,1989, conplies with the standards and requirements of the Atomic' Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; 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 Commissio6's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amenchent will not be inimical to the connon 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.
.1
~2-2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachent to this license amendment, and Paragraph 2.C.-(2) of Facility Operating License No. NPF-52 is hereby amended to read as follows:
Technical Specifica tions The-Technical Specifications contained in Appendix A, as revised through Amendment No. 63
, are hereby incorporated into the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amenoment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION b b A- '/
David B. liatthews, Director Project Directorate II-3 Division of Reactor Projects-I/II-Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance: January 23, 1990 i
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ATTACHMENT TO LICENSE AMENDMENT NO. 69 FACILITY OPERATING LICENSE NO. NPF-35 DOCKET NO. 50-413 AND TO LICENSE AMENDMENT NO. 63 FACILITY OPERATING LICENSE NO. NPF-52 DOCKET NO. 50-414 i
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 areas of change. The corresponding over-leaf page is also provided to maintain document completeness.
Amended Page Overleaf Page 3/4 9-10 3/4 9-11 3/4 9-12 i
B 3/4 9-2 1.
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1
i' 3/4.9,8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION F
HIGN WATER LEVEL LIMITING CONDITION FOR OPERATION 3.9.8.1 At least one residual heat removal loop shall be OPERABLE and in operation.*
APPLICABILITY: MODE 6, when the water level above the top of the reactor i
vessel flange is greater than or equal to 23 feet.
ACTION:
With no residual heat removal loop OPERABLE and in operation, suspend all operations involving an increase in the reactor decay heat load or a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required residual heat removal loop to OPERABLE and operating status as soon as possible.
Close all containment penetrations providing direct access from the containment atmosphere to the outside atmos-phere within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
SURVEILLANCE RE0VIREMENTS 4.9.8.1 At least once per twelve hours one residual heat removal-loop shall be verified in opera: ion and circulating reactor coolant at a flow rate:
a) greater than or equal to 1000 gpm, and b) sufficient to maintain the RCS temperature at less than or equal to 140'F.
- The residual heat removal loop may be removed from operation for up to I hour per 8-hour period during the performance of CORE ALTERATIONS in the vicinity of the reactor vessel hot legs.
CATAWBA - UNITS 1 & 2 3/4 9-10 Amendment No.69 Unit 1 Amendment No.63 Unit 2
REFUELING OPERATIONS
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. LOW WATER LEVEL LIMITING CONDITION FOR OPERATION 4
3.9.8.2 Two independent residual ~ heat removal loops shall be OPERABLE, and at least one residual heat removal loop shall be in operation.*
APPLICABILITY: MODE 6, when-the water level above the top of the reactor vessel flange is less than 23 feet.
ACTION:
a.
With less than the required residual heat removal loops OPERABLE, immediately initiate corrective action to return the required resi-dual heat removal loops to OPERABLE status, or establish greater than or equal to 23 feet of water above the reactor vessel flange, i
as soon as possible, b.
With no residual heat removal-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
'ual heat removal loop to' operation.
Close all containment ations providing direct access from the containment atmosphere
..;e outside atmosphere within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
SURVEILLANCE REQUIREMENTS I
L 4.9.8.2 At least once per twelve hours one residual heat removal loop shall be verified in operation and circulating reactor coolant at a flow rate:
a) greater than or equal to 1000 gpm, and I
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b) sufficient to maintain the RCS temperature at less than or equal to 140 F.
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- Prior to initial criticality, the residual heat removal 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 8-hour period during the performance of 1
CORE ALTERATIONS in the vicinity of the reactor vessel hot legs.
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CATAWBA - UNITS 1 & 2 3/4 9-11 Amendment No. 69 (Unit 1)
Amendment No. 63 (Unit 2)-
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f, REFUELING OPERATIONS 3/4.9.9 WATER LEVEL - REACTOR VESSEL LIMITING CONDITION FOR 0;ERATION
. 9. 9 At least 23 feet of water shall be maintained over the top of the reactor vessel flange.
APPLICABILITY:
During movement of fuel assemblies or control rods within the' containment when either the fuel assemblies being moved or the fuel assemblies seated within the reactor vessel are-irradiated while in MODE 6.
ACTION:
With the requirements.of the above specification not satisfied, suspend all operations involving movement of fuel assemblies or control rods within the reactor vessel.
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SURVEILLANCE REQUIREMENTS 4.9.9 The water level shall be determined to.be at least its minimum required depth within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> prict to the start of and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereaf ter during movement of' fuel assemblies or control rods.
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i CATAWBA - UNITS 1 & 2 3/4 9-12
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REFUELING OPERATIONS BASES 3/4.9.5 COMMUNICATIONS The requirement for communications capability ensures that refueling station personnel can be promptly informed of significant changes in the facility status or core reactivity conditions during CORE ALTERATIONS.
3/4.9.6 MANIPULATOR CRANE The OPERABILITY requirements for the manipulator cranes ensure that:
(1) manipulator cranes will be used for movement of control rods and fuel assemblies, (2) each crane has sufficient load capacity to lift a control 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.
3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE POOL 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 loop be 4 operation 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 residual heat removal' loops OPERABLE when there is less than 23 feet of water above the reactor vessel flange ensures that a single failure of the operating residual heat removal 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 1
vessel flange, a large heat. sink is available for core cooling. Thus, in the event of a failure of the operating residual heat removal loop, adequate time is provided to initiate emergency procedures'to cool the core.
To prevent vortexing in the suction of the residual heat removal pumps, the flow rate requirements for the residual heat removal system were lowered from 3000 gpm to 1000 gpm. A specific surveillance has been added to ensure the flow remains high enough.to ensure the reactor coolant system temperature remains below 140*F. The problems associated with vortexing and mid-loop operations are provided in Generic Letter 88-17, Loss of Decay Heat Removal.
i CATA4BA - UNITS 1 & 2 B 3/4 9-2 Amendment No. 69 (Unit 1)
Amendment No. 63 (Unit 2)