ML20127P653
| ML20127P653 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 11/27/1992 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20127P657 | List: |
| References | |
| NUDOCS 9212030052 | |
| Download: ML20127P653 (10) | |
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UNITED STATES n
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~i NUCLEAR f1EGULATORY COMMISSION I
WASHINGTON. D C. 2(0A os....*/
CARulINA POWER & LIGHT COMPANY. et ab.
DOCKET NO. 50-321 ERVNSWICK STEAM ELECTRIC PLANT. UNIT 1 AMENDMENT TO FACIllTY OPERATING LlCENSE Amendment No.158 License No. DPR-71 1.
The Nuclear Regulatory Commission (the Commission) has found that:
The application for amendment filed by Carolina Power & Light Company (the licensee), dated February 21, 1992, as supplemented August 24, 1992, September 4,1992, and October 28, 1992, 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 l
provisions of the Act, and the rules and regulations of the l
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.
Tha ist.1ce of this amendment is in accordance with 10 CFR Part 51 l
of the Ormission's regulations and all applicable requirements have l
been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications, as indicated in the attachment to this license amendment; l
and paragraph 2.C.(2) of Facility Operating License No. OPR-71 is hereby amendad to read as follows:
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Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.158, are hereby incorporated in the license. Carolina Power & Light Company shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/W linor G. Adensam, Director Project Directorate 11-1 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specificationr.
Date of Issuance: November 27, 1992 3
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9 ATTACHMENT TO LICENSE AMENDMENT NO.158 FACIlllY OPERATING LICENSE NO, OPR-71 DOCKET NO. 50-325 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Remove Paqgi insert Paae-,
3/4 9-8 3/4 9-8 B 3/4 9-2 B 3/4 9-2
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I REFUELING OPERATIONS t
3/4.9.6 CPANE AND HOIST OPEPABILIr(
LIMITING CONDITION FOR OPERATION j
3,9.6 All cranes and hoists used for handling fuel assemblies or control rods within the reactor pressure vessel shall be OPERABLE.
APPLICABILITY:
During movement of fuel assemblies oc control rods within the reactor pressure vessel.
ACTION:
With the requirements for crane or hoist OPERABILITY not satlafted, suspend use of any traoerable crane or hoist from operations involving the movement of control rods and fuel assemblies after placing the load in a safe location.
The provisions of Specification 3.0.3 are not applicable.
SURVEILIANCE REOUIREMENTS 4.9.6 Each crane or hoist used for movement of control rods or fuel assemblies within the reactor pressurc vessel shall be demonstrated OPERABLE within 7 days prior to the start of such operations with that crane oc hoist by:
a.
Demonstrating operation of the overload cutoff when the load exceeds 1600 pounds for the mast fuel gripper and s 1050 pounds l
for all other cranes and hoists.
b.
Demonstrating operation of the loaded interlock when the load exceeds 750 pounds for the mast fuel gripper and s 350 pounds for l
all other cranes and hoists.
Demonstrating operation of the uptravel stop for all cranes and c.
hoists other than the mast fuel gripper when uptravel would bring the top of the acti.ve fuel to 7 feet below the normal spent fuel pool water level, d.
Demonstrating operation of the slack cable cutoff when the load is less than 50 25 pounds fc. the mast fuel gripper.
Performing a load test of at least 1000 pounds.
e.
BRUNSVICK - UNIT 1 3/4 9 8 Amendment No.158
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PEFUELING OPEP.ATIONS BASES J/4 96 CRANE AND HOIST OPE / ABILITY The OPERABILITY requirements of the cranes and hoists used for movement of fuel assemblies ensures that:
- 1) each has sufficient load capac.;y to lift a fuel element, and 2) the core internals and pressure vessel are protected from excessive lifting force in the event they are inadvertently engaged l
during lifting operations.*
l-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 th6 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 VATER LEVEL REACTOR VESSEL AND SPENT FUEL STOKACk POOL The restrictions on minimum water level ensure that sufficient water depth is available to remove 98% of the assumed 10t
- 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 ermures that maintenance or repair on control rods or control rod drin es 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.
The fuel grappis hoist overload cutoff demonstration load of 1600 pounds is based on the submerged fuel bundle loads of 650 pounds,- the highest -
unloaded heist cable supported 1 cad of approximately 660 pounds. and a-tolerance for fuel bundle friction and load spikes of 290 pounds.
The fuel grapple hoist loaded interlock demonstration load of 750 pounds is based on the hi hest uniorded hoist cable supported load of approximately 660 pounda plus a toleranc6 for load spikes of 90 pounds as sections are raised and lowered.
d BRUNSVICA UNIT 1 D 3/4 9 2 Amendment No.158 1
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.I NUCLEAR REGULATOR *' COMMISSION WASHINGTON. D t..T666 o,s,*..**/
CAROLINA POWER &,_11GHT COMPANY. ets a_L, DOCKET No. 50-324 fl@fi.SWICK STEAM ELECTRIC PLANT. UNIT 2 At!ENDMENT TO FACILITY OPERATING LICENSE Amendment No. 189 License No. DPR-62 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by Carolina Power & Light Company (the licensee), dated February 21, 1992, as supplemented August 24, 1992, September 4, 1992, and October 28, 1992, 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 rhapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulattut.s of the Commission; P
C.
There is reasonable as:.rance (i) that the activities authotized by this amendment can be ccnducted 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.iot be inimical to the common defense and security or to the health and s fety 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 Licensst No. DPR-62 is hereby amended to read as follows:
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(2)
Technical Specifications The Technical Specifications contained in Appedices A and B, as revised through Ameadment No.189, are hereby incorporated in the license. Carolina Power & Light Company shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date cf its issuance and shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/
1 Adensam, Director Project Directorate 11-1 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation -
At
.iment:
Changes to the Technical Specifications.
Date of issuance: November 27, 1992 4
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ATTACHMENT TO LICENSE AMENDMENT NO.189.
FACILITY OLERATING LICENSE NO. DPR-62 QQCKET NO. S E}21 l
Replace the following pages of the Appendix A Technical Specifications with the enci m d pages.
The revised areas are indicated by marginal lines.
Pemove Paaes Insert Paaes 3/4 9-8 3/4 9-8 8 3/4 9-2 8 3/4 9-2 i
t 1
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i REFUELING OPERATIONS M.9.6 CRANE AND HOIST OPERABILITY LIMITING CONDITION FOP, SPERATION 3.9.6 All cranes and hoists used for handling fuel assemblies or control rods within the reactor pressure vessel shall be OPERABIE.
APPLICASILITY:
During movement of fuel assembifas or control rods within the reactor pressure vessel.
ACTION:
Vith the requirerents for crane or hoist OPERABILITY not satisfied, suspend use of any inoperable crane or hoist from operatians ' involving the movement of control rods and fuel assemblies af ter placing t'.no load in a safe location.
The provisions of Specification 3.0.3 are not applicable.
SURVEILIANCE REOUIREMENTS 4.9.6 Each crane or hoist used for movement of control rods or fuel assemblies within the reactor pressure vessel shall be demonstrated OPERA 3LE within 7 days prior to the start of such operations with that crane or hoist by:
a.
Demonstrating operation of the overload cutoff when the load exceeds 1600 pounds for the mast fuel gripper and s 1050 pounds for all other cranes and holses.
b.
Demonstratin5 operation of the loaded interlock when the load exceeds 750 pounds for the mast fuel gripper and s 350 pounds for j
all other cranes and hoists.
c.
Demonstrating operation of the uptravel stop for all cranes and hoists other than the mast fuel gripper when uptravel would bring the top of the active fuel to 7 feet below the normal spent fuci pool water level, d.
Demonstrating operation of the slack cable cutoff whan the load is less than 50 25 pounds for the mast fuel gripper.
e.
"trfornir3 a load east of at least 1000 rounds.
BRUN$VICK - UNIT 2 3/4 9 8 Ameniment No. 189
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REFUELING OPEP.ATIONS LMES.
1/ J.
9 6 CPANE /3D HOIST OPEPABILI'Y The OPERA 31LITY requirements of the cranes and hoists used for movement of fuel.ssemb18 9s ensures that:
- 1) each has sufficient load capacity to life a fuel element, and 2) the core internals and pressure vessel are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations.*
l 3/4.9.7 CPANE TFAVEL SJENT WEL STOPACE POOL The restriction on movement of loads in excess of the weight specified providas some assurance that with the failure of the lifting device the fuel pool would not be damaged to such a degros that the irradi.tcod fuel would he subjected to a loss of coolant.
3/4.9.8 and 3 M L VATER LEVEL REAGI M SSEL AND SPENT W EL STORACE POOL The restrictiont on minimum water level ensers that sufficient water depth is available to remove 984 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 analyois.
J/4.9.10 CONTROL ROD REMOVAL This specification ensures that maintenance or repair on control rods or control rod drives will be performad under conditions that limit the probability of inr.dvertent criticality.
The requirements for simultaneous removal of more than one control rod are more stringent since the SKUTDOWN KARG1N specification providas for the core to remain suberitical with only one control tod fully withdrawn.
E The fuel grapple hoist overload cutofi demonstration load of 1600 pounds is based on time submerged fuel bundle loads of 650 pounds. the highest unloaded heist cable supported load of approximately 660 pounds, and a tolerance for fua) bundle friction and load spikes of 290 pounds.
The fuel grapple hoist loadad interlock demonstration load of 750 pounds is based on tk highest unloaded hoist cable-supported. load of approximately 660 pounds.plus a tolerance for load spikes of 90 pounds as sections are raised and lowered.
I BRUNSWICK UNIT 2 5 3/4 9 2 Ahendmer<c No.189
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