ML16138A679
| ML16138A679 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 11/16/1989 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML16138A680 | List: |
| References | |
| NUDOCS 8911210237 | |
| Download: ML16138A679 (10) | |
Text
UNITED STATES NUCLEAR REGULATORY COMSION WASHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO. 50-269 OCONEE NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 177 License No. DPR-38
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment to the Oconee Nuclear Station, Unit 1 (the facility) Facility Operating License No. DPR-38 filed by the Duke Power Company (the licensee) dated March 31, 1988, 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 Commission's regulations set forth in 10 CFR Chapter I; D. The issuance of this license 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 hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 3.B. of Facility Operating License No. DPR-38 is hereby amended to read as follows:
8911210'237 891116.
PDR ADOCK 05000269 FPDC
-2 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 177, 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 its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
-11 David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance:
November 16, 1989
0-SRREG(,
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO.
50-270 OCONEE NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 177 License No. DPR-47
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment to the Oconee Nuclear Station, Unit 2 (the facility) Facility Operating License No. DPR-47 filed by the Duke Power Company (the-licensee) dated March 31, 1988, 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 Commission's regulations set forth in 10 CFR Chapter I; D. The issuance of this license 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 hereby amended by page 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:
-2 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
177, 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 its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects -
I/Il Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance:
November 16, 1989
0RE UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO. 50-287 OCONEE NUCLEAR STATION, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 174 License No. DPR-55
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment to the Oconee Nuclear Station, Unit 3 (the facility) Facility Operating License No. DPR-55 filed by the Duke Power Company (the licensee) dated March 31, 1988, 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; F. 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 Commission's regulations set forth in 10 CFR Chapter I; D. The issuance of this license 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 hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 3.B. of Facility Operating License No. DPR-55 is hereby amended to read as follows:
-2 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 174, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specificaticns.
- 3. This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION David B. Matthews, Director 7 e Project Directorate 11-3 Division of Reactor Projects -
I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance:
November 16, 1989
ATTACHMENT TO LICENSE AMENDMENT NO. 177 FACILITY OPERATING LICENSE NO. DPR-38 DOCKET NO. 50-269 AND TO LICENSE AMENDMENT NO. 177 FACILITY OPERATING LICENSE NO. DPR-47 DOCKET NO. 50-270 AND TO LICENSE AMENDMENT NO. 174 FACILITY OPERATING LICENSE NO. DPR-55 DOCKET NO. 50-287 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.
Remove Pages Insert Pages 3.8-2 3.8-2 3.8-3 3.8-3 5.4-1 5.4-1
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 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.
- 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 33 rows of the pool closest to the spent fuel cask handling area shall be decayed a minimum of 70 days.
- c.
Prior to dry storage transfer cask movement in the Unit 1 and 2 spent fuel pool, spent fuel stored in the first 64 rows of the pool closest to the cask handling area shall be decayed a minimum of 65 days.
- d.
Prior to dry storage transfer cask movement in the Unit 3 spent fuel pool, all spent fuel stored in that pool shall be decayed a minimum of 57 days.
3.8.14 No suspended loads of more than 3000 lbm shall be transported over spent fuel stored in either spent fuel pool.
OCONEE -
UNITS 1, 2, & 3 3.8-2 Amendment No. 177 (Unit 1)
Amendment No. 177 (Unit 2)
Amendment No. 174 (Unit 3)
3.8.15 No fuel which has an enrichot greater than 4.0 weight percent U2 3 S (53 grams of U23 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 U23 S (57 grams of U23 S 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 handling 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. TEis 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 1950 ppm. Although this concentration is sufficient to maintain the core Keff <0.99 if all the control rods were removed from the core, only a few 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 operator 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 hand ling 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 doses for the fuel handling accident are within the guidelines of 10 CFR 100; however, to further reduce the doses resulting from this accident, 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 indicated 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 OCONEE -
UNITS 1, 2, & 3 3.8-3 Amendment No. 177 (Unit 1)
Amendment No. 177 (Unit 2)
Amendment No. 174 (Unit 3)
(1)1 5.4 NEW A 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 Keff 10.95 *when flooded with unborated water, based on fuel with an enrichment of 4.3 weight percent Uta.
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 Keff (0.95 when flooded with unborated water, based on fuel with an enrichment of 4.0 weight percent Uas.
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.
5.4.2.3 Spent fuel may also be stored in Oconee Nuclear Station Independent Spent Fuel Storage Installation.
5.4.3
'henever 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.
OCONEE -
UNITS 1, 2, & 3 5.4-1 Amendment No.
177 (Unit 1)
Amendment No.
177 (Unit 2)
Amendment No.
174 (Unit 3)