ML15112B118
| ML15112B118 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 09/29/1983 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Duke Power Co |
| Shared Package | |
| ML15112B119 | List: |
| References | |
| DPR-38-A-123, DPR-47-A-123, DPR-55-A-120 NUDOCS 8310110561 | |
| Download: ML15112B118 (11) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION
- E WASHINGTON, 0. C. 20555 DUKE POWER COMPANY DOCKET NO.' 50-269 OCONEE NUCLEAR STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.123 License No.
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by the Duke Power Company (the licensee) dated March 10, 1983, as supplemented June 24 and 30, 1983, July 14, 1983, and August 8, 1983, complies with the standards and require ments of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10-CFR Chaoter 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 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 Specifications as indicated in the attachment to this license amendment and paragraph 3.B of FAcility Operating License No. DPR-3 8 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. 123 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
8310110561 830929 PDR ADOCK 05000269 P
9e
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- 3. This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Jo n F. Stolz, Chief Oerating Reactors Branch #4 ivision of Licensing
Attachment:
Changes to the Technical Specifications I
Date of Issuance: September 29, 1983
+ Q %t 4UNITED STATES C
.NUCLEAR REGULATORY COMMISSION o
E WASHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO. 50-270 OCONEE NUCLEAR STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.123 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 March 10, 1983, as supplemented June 24 and 30, 1983, July 14, 1983, and August 8, 1983, complies wioth the standards and require ments 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 Cominssion'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 Specifications as indicated in the attachment to this license amendment and paragraph 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.123 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.'
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- 3. This -1i-cens-e-amendment--s-effective -as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION h
F. Stolz, Chief ting Reactors Branch #4 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: September 29, 1983
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O.C. 20555 DUKE POWER COMPANY DOCKET NO. 50-287 OCONEE NUCLEAR STATION, UNIT NO.3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 120 License No. DPR-55
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by the Duke Power Company (the licensee) dated March 10, 1983, as supplemented June 24 and 30, 1983, July 14, 1983, and August 8, 1983,.complies wioth the standards and require ments 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 willinot 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 Specifications as indicated in the attachment to this license amendment and paragraph 3.8 of Facility Operating License No. DPR-55 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. 120are 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 oh F. Stolz, Chief 0
rating Reactors Branch 04 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
Septeuiber 29, 1983
ATTACHMENTS TO'LICENSE AMENDMENTS AMENDMENT NO. 123TO DPR-38 AMENDMENT NO.
123TO DPR-47 AMENDMENT NO. 120TO DPR-55 DOCKETS NOS.
50-269, 50-270 AND 50-287 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages.
The revised pages are identified by amendment numbers and contain vertical lines indicating the area of change.
Remove Pages insert Pages 3.8-2 3.8-2 3.8-3
.3.8-3 5.4-1 5.4-1 5.4-2 5.4-2
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 in crease the reactivity of the core shall be made.
3.8.10 The reactor building purge system, including the radiation monitor, RIA-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 yentilation 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.
- c.
This specification does not apply during reracking operations with no fuel in the spent fuel pool.
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 31 rows of the pool closest to the spent fuel cask handling area shall be decayed a minimum of 70 days.
3.8.14 No suspended loads of more than 3000 lb shall be transported over spent fuel stored in either'spent fuel pool.
3.8.15
- a.
No fuel which has an enrichment greater than 4.0 weight percent U235 (53 grams of U2 35 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 Uz3 5 (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.
3.8-2 Amendments Nos. 123, 123, & 120
ae These procedures, the above specificatiods, and the design of the fuel hand ling equipment as described in Section 9.1.4 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.
Continuous monitoring of radiation levels and neutron flux provides immediate indication of an unsafe condition. The low pressure injection pump is used to maintain a uniform boron concentration. (1) The shutdown margin indicated in Specification 3.8.4 will keep the core subcritical, even with all control rods withdrawn from the core. (2) The boron concentration will be maintained above.1835 ppm. Although this concentration is sUfficient to maintain the core K
<0.99 if all the control rods were removed from the core, only a few eff control rods will be removed at any one time during fuel shuffling and replace ment. The Keff with all rods in the core and with refueling boron concentra tion is approximately 0.90. Specification 3.8.5 allows the control room opera tor to inform the reactor.building personnel of any impending unsafe condition detected from the main control board indicators during fuel movement.
The specification requiring testing of the Reactor Building purge isolation is to verify that these components will function as required should a fuel handling accident occur which resulted in the release of significant fission products.
Specification 3.8.11 is required, as the safety analysis for the fuel handling accident was based on the assumption that the reactor had been shutdown for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.(3)
The off-site dodes for the fuel handling accident are within the guidelines of 10 CFR 100; however, to further reduce the doses resulting from this acci dent, it is required that the spent fuel pool ventilation system be operable whenever the possibility of a fuel handling accident could exist.
Specification 3.8.13 is required as the safety analysis for a postulated cask handling accident was based on the assumptions that spent fuel stored as in dicated has decayed for the amount of time specified for each spent fuel pool.
Specification 3.8.14 is required to prohibit transport of loads greater than a fuel assembly with a control rod and the associated fuel handling tool(s).
REFERENCES (1) FSAR, Section 9.1.4 (2) FSAR, Section 15.11.1 (3) FSAR,.Section 15.11.2.1 Amendments Nos. 123, 123, & 120 3.8-3
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 1 and 2, the fuel assemblies are stored in racks in parallel rows, having a nominal center-to center distance of 10.65 inches in both directions. This spacing is sufficient to maintain K
<0.95 when flooded with unborated ieff water, based on fuel with an enrichment of 4.3 weight percent U235 In the spent fuel pool serving Unit 3, the fuel assemblies are stored in racks in parallel rows, having a nominal center-to-center distance of 10.60 inches in both directions. This spacing is sufficient to maintain a K
<0.95 when flooded with unborated eff water, based 'on fuel with an enrichment of 4.0 weight percent U235 5.4.1.2 New fuel may also be stored in the fuel transfer canal. 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.
5.4.2 Spent Fuel Storage 5.4.2.1 Irradiated fuel assemblies will be stored, prior to off-site ship ment, in a stainless steel lined spent fuel pool.
The spent fuel pool serving Units 1 and 2 is sized to accommodate a full core of irradiated fuel assemblies in addition to the con current storage of the largest quantity of new and spent fuel assemblies predicted by the fuel management program.
Provisions are made in the Units 1, 2 spent fuel pool to accommo date up to 1312 fuel assemblies and in the Unit 3 spent fuel pool up to 825 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.
5.4.3 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.
mendments Nos. 123, 123 &
120
- 5.
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9I 5.4.4 The spent fuel pool and fuel transfer canal racks are designed for an earthquake force of O.1g ground motion.
REFERENCES FSAR, Section 9.1.
Amendments Nos. 123, 123 & 120 5.4-2