ML17324B258
| ML17324B258 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 02/28/1987 |
| From: | Wigginton D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17324B259 | List: |
| References | |
| NUDOCS 8703060264 | |
| Download: ML17324B258 (10) | |
Text
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+ ))*y 4 UNITEDSTATES NUCLEAR REGULATORY COMMISSION 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. >o>
License No.
DPR-58 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Indiana and Michigan Electric Company (the licensee) dated January 9,
1987 and January 13, 1987, 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 Comission; 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 fnimical 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.
DPR-58 is hereby amended to read as follows:
8703060264 870228 PDR ADOCK 05000315 P
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 1o$ are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Speci ficati ons.
3.
The Technical Specification changes are to become effective within 45 days of receipt of this amendment.
4.
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 28, 1987 Dave L. Wigginton, Project Manager PWR Project Directorate k'4 Division of PWR Licensing-A r
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PWR / PWR-A DWigginton/rad 02/ Li /87 P)<Rg / PWR-A MDuHca 02//I /87
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P0 UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON. D. C. 20555 INDIANA AND MICHIGAN ELECTRIC COMPANY DOCKET NO. 50-316 DONALD C.
COOK NUCLEAR'LANT UNIT NO.
2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
License 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 January 9,
1987 and January 13, 1987, 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 Comission; 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.
DPR-74 is hereby amended to read as follows:
3.
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 8>, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
The Technical Specification changes are to become effective within 45 days of receipt of this amendment.
4.
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 28, 1987 Dave L. Wigginton, Project Manager PWR Project Directorate ¹4 Division of PWR Licensing-A PWR¹4/DPWR-A DWigginton/rad 02/Q /87 PW 4
PWR-A 02/Ij /87 PWR PWR-A BJY
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ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT N0.101 FACILITY OPERATING LICENSE NO.
DPR-58 AMENDMENT NO.
87 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 9-8 Insert Pa es 3/4 9-8 Unit 2 3/4 9-7 3/4 9-7
REFUELING OPERATIONS CR"NE TRDA~cL - SPENT FUEL STORAGE POOL BUILDING LIHITING CONDITION 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.
APPLICABILITY: With fuel assemblies in the storage pool.
ACT'0!I:
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.
S"RVEILLANCE RE'3L'IRE".ENTS 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 c 24,240 in.-lbs. prior to moving each load over racksontaining fuel.
eShared system vith D. C. Cook Unit 2
- This does not include the main load block, vhich veighs approximately F 25 tons.
Whenever the load block is moved over the pool, the main hoi~'~t be deenergised and be carrying no load.
D. C.
COOK - UNIT 1 3/4 9-8 A~ndment ho.
101
REFUELING OPERATIONS CRANE TRAVEL - SPENT FUEL STORAGE POOL BUILDING~
l LIMITING CONDITION FOR OPERATIOH 3.9.7 Loads in excess of 2,500 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 containing 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.
APPLICABILITY: Nth 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 REOUI RE.".ENTS 4.4.7.1 Crane interlocks and physical stops which prevent crane travel with.
loads in excess of 2,500 pounds over fuel assemblies shall be demonstrated OPEVBLE 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 c 24,240 in.-lbs. prior to moving each load over racks containing fuel.
I.IIM. IT\\
- This does not include the main load block, which veighs approximately 4.25 tons.
Whenever the load block is moved over the pool, the main hoist must be deenergized and be carrying no load.
D. C.
COOV - UNIT 2 3/4 9-7 hmendment No.
87