ML15112A863
| ML15112A863 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 06/19/1979 |
| From: | Grimes B Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML15112A864 | List: |
| References | |
| NUDOCS 7907250595 | |
| Download: ML15112A863 (11) | |
Text
O 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.72 License No. DPR-38
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Duke Power Company (the licensee) dated February 2, 1979, as supplemented April 20 and May 2, 1979, 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 (1) 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.
790725
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- 2. Accordingly, the license is amended by chanqes 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:
3.8 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 72 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 T NUCLEAR REGULA ORY COMMISSION
- Brian K. Grimes, Assistant Director for Engineering & Projects Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: June 19, 1979
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO. 50-270 OCONEE NUCLEAR STATION, UNIT NO.2 AMENDMENT TO FACILITY OPERATING LICENSE.
Amendment No.72 License No. DPR-47
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Duke Power Company (the licensee) dated February 2, 1979, as supplemented April 20 and May 2, 1979, 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 (1) 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 3.B of Facility Operating License No.
DPR-47 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. 72 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 OMMISSION ian K. Grimes, Assistant Director for Engineering & Projects Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: June 19, 1979
0,A RE cUNITED 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 Aendment No. 69 License No. DPR-55
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Duke Power Company (the licensee) dated February 2, 1979, as supplemented April 20 and May 2, 1979, 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, dnd the rules and regulations of the Commission; C. There is reasonable assurance (1) 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.
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- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 3.3 of Facility Operating License No.
DPR-55is hereby amended to read as follows:
3.3 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 69 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 lan K. Grimes, Assistant Director for Engineering & Projects Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: June 19, 1979
ATTACHMENTS TO LICENSE AMENDMLNTS AMENDMENT NO. 72 TO DPR-38 AMENDMENT NO. 72 TO DPR-47 AMENDMENT NO. 69 TO DPR-55 DOCKETS NOS. 50-269, 50-270, AND 50-287 Revise Appendix A as follows:
Remove Pages Insert Pages 3.8-1 thru 3.8-3 3.8-1 thru 3.8-3 5.4-1 5.4-1 5.4-la 5.4-2 Changes on the revised pages are indicated by marginal lines.
3.8 FUEL LOADING AND REFUELING A:volicability Applies to fuel loading and refueling operations.
Obiective To assure that fuel loading and refueling operations are performed in a responsible manner.
Specification 3.8.1 Radiation levels in the reactor building refueling are3 shall be monitored by RlA-2 and RIA-3.
Radiation levels in the spent fuel storage area shall be monitored by RIA-6.
If any of these instruments becomes inoperable, portable survey instrumentation, having tha appropriate ranges and sensitivity to fully protect individuals involved in refueling oper3tion, shall be used until the permanent instrumentation is returned to service.
3.8.2 Core subcritical neutron flux shall be continuously monitored by at least two neutron flux monitors, each with continuous indication available, whenever core geometry is being changed.
When core geometry is not being changed, at least one neutron flux monitor shall be in service.
3.8.3 At least one low pressure injection pump and
- Oler shall be operable.
3.8.4 During reactor vessel head removal and while loading and unloading fuel from the reactor, the boron concentration shall be maintained at not less than that required to shutdown the core to a k
<099 if all control rods were removed.
ofths 3.8.5 Direct copounications between the control room and the refueling personnel in the reactor building shall exist whenever changes in core geometry are taking place.
3.S.6 During the handling of irr3diated fuel in the reactor buildingat least one door o the personnel and emergency hatches shall be closed.
The equipment hatch cover shall be in place with a minimum of four bolts securing the cover to the sealing surfaces.
3.8.7 Both isolation valves in lines containing automatinc containment isolation valves shall be operable, or at least one shallbe closed 3.8.
When two irradiated fuel assemblies are being handled simultaneously within the fuea tronsfer canal, aminunm of 0 fee-separation shall be maintained between the assemblies at all tiMes.
Irradiated hnel assemblies may be handled with the aruiliarv oist provided no other irradiated fuel assembly is bei d simled in th e fuel transfer canal.
Amendments Nos. 72
, 72
, &69 3.3-1
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 he1crease 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.
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 28 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, spentfuel 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 Thz shall be transported over spent fuel stored in either spent fuel pool.
3.8.15 No fuel which has an enrichment greater than 3.5 weight percent U235 (46 grams of U235 per axial centimeter of fuel assembly) will be stored in eitler spent fuel pool.
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 9.7 of the FSAR incorporating built-in iterlocks 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 :L core geometry, one flux nonitor is sufficient.
This permits maintenance on the instrumentation.
Amendments Nos.
72,
72, & 69 3.8-2
Continuous monitoring of radiation levels and neutron flux provides i-m mediate 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 1,8000 ppm.
Although this concentration is sufficient to maintain the core keff 1 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 replacement. The keff with all rods in the core and with re fueling boron concentration is approximately 0.9. 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 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 />.Q)
The off-site doses for the fuel handling accident are within the guidelines of 10CFIR100; however, to further reduce the doses resulting from thisac cident, 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 deayed 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 (l) TSAR, Section 9.7 (2) FSAR, Section 14.2.2.1 (3) FSAR, Section 14.2.2.1.2 3.8-3 Amendments Nos. 72, 72 & 69
5.4 NE' AND SPENT FEL 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 13.75 inches in both directions. This spacing is sufficient to maintain a K (0.95 when flooded with unborated water,,based on fuel with an inrichment of 3.5 weight percent U235.
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 adja 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
<0.95 when flooded with unborated water based on fuel 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 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.
5.4.1.4 New fuel of enrichment not exceeding 2.9 weight percent U23 5 or the equivalent may be placed in dry storage in Unit 3 fuel storage racks in a checkerboard pattern, with fuel assemblies occupying only diagonally adjacent storage locations.
Unused storage loca tions in a fuel storage module shall be covered by inserting a metal plate in the lead-in to prevent incorrect placement of.
fuel assemblies. This configuration is sufficient to assure a K eff0.9 at 3ll times' 5.4.2 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.
72,
- 72. &69 5.41