ML15112A981
| ML15112A981 | |
| Person / Time | |
|---|---|
| Site: | Oconee, Surry, Vermont Yankee  |
| Issue date: | 12/24/1980 |
| From: | Novak T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML15112A982 | List: |
| References | |
| NUDOCS 8101100448 | |
| Download: ML15112A981 (10) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO.
50-269 OCONEE NUCLEAR STATION, UNIT NO.. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 90 License *No. DPR-38
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A-The application for amendment by the Duke Power Company (the licensee) dated July 25, 1980, as supplemented July 1, August 7 and 14, October 15 and 31, and November 3 and December 12, 1980, 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 pro visions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authoriied 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 satis fied.
- 2. Accordingly, the license is amended by changes to the Technical Specifi cations as indicated in the attachment to this license amendment and 'para graph 3.B of Facility Operating License No. DPR-38 is hereby amended to read as follows:
3.3 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 90 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
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- 3. This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION omas M ak, Assistant Director for Operating Reactors Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 24, 1980
UNITED STATES NUCLEAR REGULATORY COMMISSION S.
WASHINGTON. D. C. 20555 DUKE POWER COMPANY DOCKET NO. 50- 270 OCONEE NUCLEAR STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 90 License No. DPR-47
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A* The application for amendment by the Duke Power Company (the licensee) dated July 25, 1980, as supplemented July 1, August 7 and 14, October 15 and 31, and November 3 and December 12, 1980, 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 pro visions 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; D. The issuance of this amendment will not be inimical to the conon 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 satis fied.
- 2. Accordingly, the license is amended by changes to the Technical Specifi cations as indicated in the attachment to this license amendment and para graph 3.B of Facility Operating License No. DPR-47 is hereby amended to read as follows:
3.B Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 90 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
-2
- 3. This license amendment is effective as of the date of its issuance.
'FOR THE NUCLEAR REGULATORY COMMISSION Thomas M. Novak, Assistant Director for Operating Reactors Division of Licensing
Attachment:
Changes to the Technical
-Specifications Date of Issuance: December'24, 1980
0 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON. D. C. 20555 DUKE POWER COMPANY DOCKET NO. 50-287 OCONEE NUCLEAR STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
87 License No. DPR-5
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
- The application for amendment by the Duke Power Company (the licensee) dated July 25, 1980, as supplemented July 1, August 7 and 14, October 15 and 31, and November 3 and December 14 1980, 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 pro visions of the Act, and the rules and regulations of the Corission; 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 satis fied.
- 2. Accordingly, the license is amended by changes to the Technical Specifi cations as indicated in the attachment to this license amendment and 'para
,graph 3.B of Facility Operating License No. DPR-55is hereby amended to read as follows:
3.B Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 87 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
-2
- 3. This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Thomas M. Novak, Assistant Director for Operating Reactors Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 24, 1980
ATTACHMFNT TO ITCFNSF AIFNDMFNTS AMENDMENT NO.
90 TO DPR-38 AMENDMENT NO.
90 TO DPR-47 AMENDMENT NO.
87 TO DPR-55 DOCKETS NOS. 50-269, 50-270 AND 50-287 Revise Appendix A as follows:
Remove Pages Insert Pages 3.8-2 3.8-2 5.4-1 5.4-1 5.4-2 5.4-2 Changes on the revised pages are indicated by marginal lines.
3.8.9 If any of the above specified limiting conditions for fuel loading and refueling are not met, movement of fuel into the reactor core shall cease; action shall be initiated to correct the conditions so that the specified limits are met, and no operations which may increase the reactivity of the core shall be made.
3.8.10 The reactor building purge system, including thje rqdiapioq monitor, RIRA-45, which initiates purge isolation, shall be tested and verified to be operable immediately prior to refueling operations.
3.8.11 Irradiated fuel shall not be moved from.the reactor until the unit has been subcritical for at least 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
3.8.12 Two trains of spent fuel pool ventilation shall be operable with the following exceptions:
- a. With one train of spent fuel pool ventilation inoperable, fuel movement within the storage pool or crane operation with loads over the storage pool may proceed provided the operable spent fuel pool ventilation train is in operation and discharging through the Reactor Building purge filters.
- b. With no spent fuel pool ventilation.filter operable, suspend all operations involving movement of fuel within the storage pool or crane operations with loads over the storage-pool until at least one train of spent fuel pool ventilation is restored to operable status.
3.8.13
- a. Prior to spent fuel cask movement in the Unit 1 and 2 spent fuel pool, spent fuel stored in the first 36 rows of the pool closest to the spent fuel cask handling area shall be decayed a minimum of 55 days.
- b. Prior to spent fuel cask movement in the Unit 3 spent fuel pool, spent fuel stored in the first 20 rows of the pool closest to the spent fuel cask handling area shall be decayed a minimum of 43 days.
3.8.14 No suspended loads of more than 3000 lbm shall be transported over spent fuel stored in either spent fuel pool.
3.8.15
- a. N ?3 uel which has an enrichment greater than 3.5 weight percent U
(46 grams of U2 3 5 per axial centimeter of fuel assembly) will be stored in the spent fuel pool for Unit 3.
- b. No fuel which has an enrichment greater than 4.3 weight percent U235 (57 grams of U235 per axial centimeter of fuel assembly) will be stored in the spent fuel pool for Units 1 and 2.
Bases Detailed written procedures will be available for use by refueling personnel.
These procedures, the above specifications, and the design of the fuel hand ling equipment as described in Section 9.7 of the FSAR incorporating built-in interlocks and safety features, provide assurance that no incident could occur during the refueling operations that would result in a hazard to public health and safety.
If no change is being made in core geometry, one flux monitor is sufficient. This permits maintenance on the instrumentation.
Amendments Nos.. 90, 90, & 87 3.8-2
5.4 NEW AND SPENT FUEL STORAGE FACILITIES Specification 5.4.1 New Fuel Storage 5.4.1.1 New fuel will normally be stored in the spent fuel pool serving the respective unit.
In the spent fuel pool serving Units I and 2, the fuel assemblies arestored in racks in parallel rows, having a nominal centor-to center distance of 10.65 inches in both directions. This sparing is sufficient to maintain a K
<0.95 when flooded with unberated eff.
water, based on fuel with an enrichment of 4.3 weight percent U23.
In the spent fuel pool serving Unit 3, the fuel assemblies are stored in racks consisting of stainless steel cavities which main tain a minimum edge-to-edge spacing of 3.95 inches between.sija cent fuel assemblies. The neutron poisoning effect of the storage cavity material combined with the minimum 3.95 inches edge-to-edge spacing between adjacent fuel assemblies is sufficient to main tain a K 50.95 when flooded with unborated water based on fuel eff with an enrichment of 3.5 weight percent U235 or the equivalent.
5.4.1.2 New fuel may also be stored in the fuel Lransfer canai.
The fuel assemblies are stored in five racks in a row having a nominal center-to-center distance of 2' 1-3/4".
One rack is oversized to receive a failed fuel assembly container.
The other four racks are normal size and are capable of receiving new fuel assemblies.
5.4.1.3 New fuel may also be stored in shipping containers.
5.4.1.4-New fuel of enrichment not exceeding 2.9 weight percent U2."
or the equivalent may be placed in dry storage in Unit 3 fuel stLcr.g_.
racks in a checkerboard pattern, with fuel assemblies occupying only diagonally adjacent storaee locations.
Unused storage ioca tions in a fuel storage module shall be covered! by.inserting a metal plate in the lead-in to prevent incorrect placement of mel assemblies.
This configuration is sufficient to assure a X 50.9 at all times.
eft S.4.2 Spent Fuel Storage 5.4.2.1 Irradiated fuel assemblies will be stored, prior to offsite ship ment, in a stainless steel lined spent fuel pool.
Amendments Nos. 90, 90, & 87 5.4-1
The spent fuel pool serving Units 1 and 2 is sized to accommodate a full core of irradiated fuel assemblies in addition ;o the concur rent storage of the largest quantity of new and spent fuel assemblies predicted by the fuel management program.
Provisions are made in the Unit 1, 2 spent fuel pool to accommodate up to 1312 fuel assemblies and in the Unit 3 spent fuel pool up to 474 fuel assemblies.
5.4.2.2 Spent fuel may also be stored in storage racks in the fuel transfer canal when the canal is at refueling level.
5.6.
Except as provided in Specification 5.4.1.4, whenever there is fuel in the pool, the spent fuel pool is filled with water borated to the concentration that is used in the reactor cavity and fuel transfer canal during refueling operations.
5.4.4 The spent fuel pool and fuel transfer canal racks are designed for an earthquake force.of 0.Ig ground motion.
REFERENCES FSAR, Section 9.7 Amendments Nos.
90, 90, & 87 5.4-2