ML20107G361
| ML20107G361 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 10/25/1984 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Carolina Power & Light Co |
| Shared Package | |
| ML20107G363 | List: |
| References | |
| DPR-62-A-104, DPR-71-A-077 NUDOCS 8411070347 | |
| Download: ML20107G361 (10) | |
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' NUCLEAR REGULATORY COMMISSION
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h CAROLINA POWER & LIGHT COMPANY-DOCKET NO. 50-325 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AMENDMENT T0' FACILITY OPERATING LIC'5NSE
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Amendment No. 77 License No. DPR-71 1.
The Nuclear Regulatory Commission (the Commission) has found that:
c A.
The application for amendment by Carolina Power & Light Company (thelicensee)datedJune 13, 1984, 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, 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; l
D.
The issuance of this amendment will not be inimical to the l
common defense and security or to the health and safety of the l
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 i
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. OPR-71 is hereby amended to read as follows:
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a 2.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
77, 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.
FOR THE CLEAR REGULATORY COPMISSION
~
Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: October 25, 1984 4
I ATTACHMENT TO LICENSE AMENDMENT NO. 77 FACILITY OPERATING LICENSE NO.-DPR-71 DOCKET NO. 50-325 Revise the Appendix A Technical Specifications as follows:
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(BSEP-1-27).
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- REFUELING' OPERATION-3/4.9;9 WATER LEVEL - SPENT FUEL' STORAGE POOL LIMITINC CONDITION FOR OPERATION 3.9.9 At -least.20 feet 6 inches of water shall be maintained over the top of the irradiated fuel rods seated =in the spent fuel storage pool racks..
- APPLICABILITY: - Whenever irradiated fuel assemblies 'are in the spent fuel storage pool.
ACTION:
i With the requirements of the above specificacian not sTatisfied, suspend _all movement of fuel assemblies and crane' operations with loads in the spent fuel
' storage pool area after placing the load in a safe location. Restore the water level to within its limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.. The provisions of Specification 3.0.3 are not applicable.
L SURVEILLANCE REQUIREMENTS 4.9.9 The water level in the spent fuel storage pool shall be determined to be et least its minimum required depth at least once per 7 days.
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BRUNSWICK - UNIT 1 3/4 9-11 Amendment No. 77 l
(BSEP-1-27)
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BASES 3/4.9.6 CRANE AND ROIST OPERABILITY Thej0PERABILITY requirements of the cranes and hoists used for moiement of fuel assemblies ensures thatt.1) each has sufficient load capacity to lif t e
a' fuel element, and' 2) the core internals and pressure vessel are protected from excessive lif ting force in the event they are inadvertently engaged during lifting operations.
3/4.9.7 CRANE TRAVEL-SPENT FUEL STORAGE POOL The restriction on movement of loads in excess of the'veight specified provides some assurance that with the failure of the lifting device the fuel pool would not be damaged to such a degree that the irradiated fuel would be subjected to a loss-of-coolant.
y 3/4.9.8 and 3/4.9.9 WATER LEVEL-REACTOR VESSEL AND SPENT FUEL STORAGE P0OL The. restrictions on minimum water level ensure that sufficient water
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depth is available to remove 98% of the assumed 10% iodine gap activity released from the rupture of irradiated fuel assembly. This minimum water.
depth is consistent with the assumptions of the accident analysis.
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3/4.9.10 CONTROL ROD REMOVAL This specification ensures that maintenance or rnpair on control rods or control rod drives will be performed under conditions that limit the probability of inadvertent criticality. The requirements for simultaneous removal of more chari one control rod are more stringent since the SHUTDOWN MARGIN specification provides for the core to remain subcritical with only one control rod fully withdrawn.
i BRUNSWICK - UNIT 1 B 3/4 9-2 Amendment No. 77
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NUCLEAR RECULATIRY COMMISSION 5
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_ CAROLINA POWER'&' LIGHT COMPANY DOCKET NO. 50-324 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 2 AMENDMENTTOFACILITYOPERATINGIICENSE 7
Amendment No.104 License No. OPR-62 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Carolina Power & Light Company (thelicensee)datedJune 13, 1984, 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, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (1) 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 Comission's regulations; D.
The issuance of this amendment will not bt inimical to the commor jefense 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 Comission'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, j
and paragraph 2.C.(2) of Facility Operating License No. OPR-62 is i
.hereby amended to read as follows:
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e 2.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.104, 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.
FOR THE NUCLEAR REGULATORY COMISSION Domenic B. Vassallo. Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: October 25, 1984 i
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ATTACHMENT TO LICENSE AMEN 0 MENT NO.104 FACILITY OPERATING LICENSE NO. DPR-62 DOCKET NO. 50-324 Revise the Appendix A Technical Specifications as follows:
Remove Insert
~
3/4 9-11 3/4 9-11 B3/4 9-2 B3/4 9-2 6
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(BSEP-2-27)
REFUELING OPERATIONS 3/4.9.9 WATER LEVEL - SPENT FUEL STORAGE POOL LIMITING CONDITION FOR OPERATION 3.9.9 At least 20 feet 6 inches of water shall be maintained over the top of the irradiated fuel rods seated in the spent fuel storage pool rdeks.
APPLICABILITY: Whenever irradiated fuel assemblies are in the spent fuel storage pool.
ACTION:
With the requirements of the above specification nbt Katisfied, suspend all movement of fuel assemblies and crane operations with loads in the spent fuel storage pool area af ter placing the lo'ad in a safe location. Restore the water level to within its limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. The provisions of f
Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.9.9 The water level in the spent fuel storage pool shall be determined to be at least its minimum required depth at least once per 7 days.
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BRUNSWICK - UNIT 2 3/4 9-11 Amendment No.104 v.
_. (BSEP-2-27)
REFUELING OPERATIONS
- BASES 3/4.9.6 CRANE AND HOIST _ OPERABILITY The OPERABILITY requirements of the cranes and hoists used for movement of fuel. assemblies ensures that
- 1) each has sufficient load
. capacity to. lift a fuel element, and 2)' the core. internals and pressure vessel are protected from. excessive lif ting force in the event they are inadvertently engaged during lift.ing operations.
-3/4.9.7 CRANE TRAVEL-SPENT FUEL STORAGE POOL The restriction on movement of loads in excess of the weight -
specified provides some assurance that with the failure of the lifting device the fuel-pool ~would not'be damaged to such a degree that the irradiated fuel would be subjected to a-loss-of-coolant.
"3/4.9.8 and 3/4.9.9 WATER LEVEL-REACTOR VESSEL AND SPENT FUEL STORAGE POOL The restrictions on minimum water level ensure that sufficient ' water de th.is available to remove 98% of the assumed 10% iodine gap activity released from the rupture of irradiated fuel assembly.
This minimum water depth is consistent with the assumptions of the accident analysis.
3/4.9.10 CONTROL ROD REMOVAL This specification ensures that maintenance or repair on control rods or control rod drives will be performed under conditions that limit the probability of inadvertent criticality. The requirements for simultaneous removal of more than -one control rod are more stringent since the SHUTDOWN MARGIN specification provides for the core to remain suberitical with only one control rod fully withdrawn.
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BRUNSWICK -- UNIT 2 B 3/4 9-2 Amendment No. 104
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