ML17324A668
| ML17324A668 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 02/24/1986 |
| From: | Youngblood B Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17324A669 | List: |
| References | |
| NUDOCS 8603050573 | |
| Download: ML17324A668 (10) | |
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t UNITEDSTATES NUCLEAR REGULATORYCOMMISSION WASHINGTON,D. C. 20555 INDIANA AND MICHIGAN ELECTRIC COMPANY DOCKET NO. 50-315 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 93 License No.
DPR-58 The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Indiana and Michigan Electric Company (the licensee) dated February 14, 1986, 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 Comission'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 2.
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.
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.
DPR-58 is hereby amended to read as follows:
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PDR (2)
Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
93
, 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 TKE NUCLEAR REGULATORY COMMISSION Orfgyral s1gnog by-De Hood
Attachment:
Changes to the Technical Specifications Date of Issuance:
Pebruary 24, 1986
. J.
Youngblood, Director WR Project Directorate ¹4 Division of PWR Licensing-A, NRR PWR
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 INDIANA AND MICHIGAN ELECTRIC COMPANY DOCKET NO. 50-316 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
2 AMENDMENT TO FACILITY OPERATING LICENSE Anendment No.
79
.J.icense No.
DPR-74 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Indiana and Michigan Electric Company (the licensee) dated February 14, 1986, complies with the standards and requirements of the Atomic Energy Act of
- 1954, as amended (the Act) and the Comission'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 Comission's regulations; 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 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.
DPR-74 is hereby amended to read as follows:
(2)
Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
79
, 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 COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
FebrUary 24, 1986 Original signel by:
D. Hool B. J.
Youngblood, Director PWR Project Directorate ¹4 Division of PWR Licensing-A, NRR PWR
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ATTACHMENT TO LICENSE AMENDMENTS 1
AMENDMENT NO.
93 FACILITY OPERATING LICENSE NO.
DPR-58 AMENDMENT NO.
79 FACILITY OPERATING LICENSE NO.
DPR-74 DOCKET NOS. 50-315 AND 50-316 Revise Appendix A as follows:
Remove Pa es Unit 1
3/4 9-7 3/4 9-8 Inssrt Pa es Unit 1
3/4 9-7*
3/4 9-8 Unit 2 3/4 9-7 Unit 2 3/4 9-7
- Included for convenience only.
REFUELING OPERATIONS SURVEILLANCE RE UIRENENTS (Continued)
\\
4.9.6.2 'ach auxiliary hoist and associated load indicator used for movement of control rods within the reactor pressure shall be demonstrated OPERABLE within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the start of such operations by per-forming a load test of at least 700 pounds.
D.
C.
COOK - UNIT 1
3/4 9-7
REFUEL.NG OPERATIONS CRANE TRAVEL - SPENT FUEL STORAGE POOL BUILDING*
LIMITING CONL ITION FOR OPERATION 3.9.7 Loads in excess of 2500 pounds shall be prohibited from travel over fuel assemblies in the storage pool.
Loads carried over the'spent fuel pool and the heights at which they may be carried over racks containinp fuel shall be limited in such a way as to preclude impact energies over 24,240 in.-lbs., if the.loads are dropped from the crane.
APPLICABILfTY: With fuel assemblies in the storage pool.
ACTION:
With the requirements of the above specification not satisfied, place the crane load in a safe condition.
The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE RE'3UIRKMENTS 4.9.7.1 Crane interlocks and physical stops which prevent crane travel with loads in excess of 2500 pounds over fuel assemblies shall be demon-strated OPERABLE within 7 days prior to crane use and at least once per 7
days thereafter during crane operation.
4.9.7.2 The potential impact energy due to dropping the crane's load shall be determined to be
< 24,240 in.-lbs. prior to moving each load over racks containing fuel.
3/4 9-8 Amndmeat No 93
- Shared system with D. C. Cook - Unit 2
- This does not include the main load block, which weighs approximately 4.25 tons.
Whenever the load block is moved over the pool, the main hoist must be deenergized and be carrying no load.
This provision expires February 28 1987.
D. C.
COOK - UNIT 1
3 REFUEL IHG OPERATIONS CRANE TRAVEL - SPENT FUEL STORAGE POOL BUILDING>>
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LIMITING CONDITION FOR OPERATION 3.9,7 Loads fn excess of. 2,500 pounds shall be prohfbfted from travel over fuel assemblies in the storage pool..
Loads carried over the spent fuel pool and the heights at whfch they may be carried over racks containing fuel shall be limited in such a way as to preclude impact ene'rgies over 24,240 fn.-lbs., if the Toads are dropped from the 'crane.
APPLICABILITY: Mfth fuel'ssemblies fn the storage pool.
ACTION:
Nth the requfrements of the above specification not satisfied, place the crane load in a.safe condition.
The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REOUIREMENTS 4.9.7,1 Crane interlocks and physical stops which prevent crane travel wi.l; loads in excess of 2,500 pounds over fuel assemblies shall be demonstrated OPERABLE wfthin 7 days prior to crane use and at least once per 7 days thereafter during crane operation.
4.9.7.2 The potential fmpact energy due to dropping the crane's load shall be determined to be c 24,240 fn.-lbs. prior to moving each load over racks containing fuel.
)
Shared system with D.
C. COOK-
- This does not include the main tons.
Whenever the load block be deenergized and be carrying 1987.
D.
C.
COOK - UNIT 2 3/4 9-7 Amendment No.
79 UNIT 1 load block, which weighs approximately 4.25 is moved over the pool, the main hoist must no load.
This provision expires February 28,