ML15112A887
| ML15112A887 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 07/16/1979 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML15112A888 | List: |
| References | |
| NUDOCS 7908080348 | |
| Download: ML15112A887 (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, 76 License No. DPR-38
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The applications for amendment by Duke Power Company (the licensee) dated October 1, 1976, and June 12, 1978, comply 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 CPR Chapter I; B. The facility will operate-in conformity with the applications, 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.
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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-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. 76 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 a ert 4. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors
Attachment:
Changes 'to the Technical Specifications Date of Issuance. July 16, 1979
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1 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, 0. C. 20555 DUKE POWER COMPANY DOCKET NO. 50-270 OCONEE NUCLEAR STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Anendment No, 76 License No. DPR-47
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The applications for amendment by Duke Power Company (the licensee) dated October 1, 1976, and June 12, 1978, comply 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 CPR Chapter I; B. The facility will operate-in conformity with the applications, 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 cons;on 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.
S.- 2
- 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:
3.8 Technical Specifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No. 76 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 ober Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: July 16, 1979
a paWcS UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, 0. C. 20555 DUKE POWER COMPANY DOCKET NO. 50-2871 OCONEE NUCLEAR STATION, UNIT NO.3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 73 License No. DPR-55
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The applications for amendment by Duke Power Company (the licensee) dated October 1, 1976, and June 12, 1978, comply 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 CRR Chapter I; B. The facility will operate-in conformity with the applications, 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 comion 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.B of Facility Operating License No.
- DPR-55 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. 73 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 isuance.
FOR THE NUCLEAR REGULATORY COMMISSION Robert.W.
Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: July 16, 1979
ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 76 TO DPR-38 AMENDMENT NO. 76 TO DPR-47 AMENDMENT NO. 73 TO DPR-55 DOCKETS NOS. 50-269, 50-270 AND 50-287 Revise Appendix A as follows:
Remove Pages Insert Pages 4.4 4.4-9 4.4 4.4-8 Changes on the revised pages are indicated by marginal lines.
Page-4.4-5 is unchanged and is included for convenience only.
liner, because of conformance of the complete containment to a 0.25 percent leakage rate at 59 psig during preoperational testing and the absence of any significant stresses in the liner during reactor operation. Second is the more frequent testing, at design pressure, of those portions of the contain ment envelope that are most likely to develop leaks during reactor operation (penetrations and isolation valves) and the low value (0.125 percent) of leakage that is specified as acceptable from penetrations and isolation valves.
Third is the tendon stress surveillance program which provides assurance that an important part of the structural integrity of the containment is maintained.
Leakage to the penetration room, which is permitted to be up to 50 percent of the total allowable containment leakage, is discharged through high efficiency particulate air (HEPA) and charcoal filters to the unit vent. The filters are conservatively said to be 90 percent efficient for iodine removal.
More frequent testing of various penetrations is specified as these locations are more susceptible to leakage than the Reactor Building liner due to the mechanical closure involved. Particular attention is given to testing those penetrations with resilient sealing materials, penetrations that vent directly to the reactor building atmosphere, and penetrations that connect to the Reactor Coolant System pressure boundary. The basis for specifying a maximum leak rate of 0.125 percent from penetrations and isolation valves is that one-half of the actual integrated leak rate is expected from those sources.
Valve operability tests are specified to assure proper closure or opening of
-the Reactor Building isolation valves to provide for isolation of functioning of Engineered Safety Features systems. Valves will be stroked to the position required to fulfill their safety function unless it is established that such testing is not practical during operation. Valves that cannot be full-stroke tested will be part-stroke tested during operation and full-stroke tested during each normal refueling shutdown.
REFERENCES (1) FSAR, Sections 5 and 13 4.-5
4.4.2 Structural Integrity Applicability Applies to the structural integrity of the Reactor Building.
Objective To define the inservice surveillance program for the Reactor Building.
Specification 4.4.2.1 Tendon Surveillance For the initial surveillance program, covering the first five years of operation, nine tendons shall be selected for periodic inspection for symptoms of material deterioration or force reduction.. The surveillance o
tendons shall consist of three horizontal tendons, one in each of three 120 sectors of the containment; three vertical tendons located at approximately 1200 apart; and three dome tendons located approximately 1200 apart.
The following nine tendons have been selected as the surveillance tendonsi Dome 1028 2D28 (Units 1 & 3) 3D28 Horizontal 13H9 51H9 53H10 Vertical 23V14 45V16 61V16 4.4.2.1.1 Lift-Off Lift-off readings shall be taken for all nine surveillance tendons.
4.4.2.1.2 Wire Inspection and Testing One surveillance tendon of each directional group shall be relaxed and one wire from each relaxed tendon shall be removed as a sample and visually in spected for corrosion or pitting. Tensile tests shall also be performed on a minimum of three specimens taken from the ends and middle of each of the three wires.
The specimens shall be the maximum length acceptable for the test apparatus to be used and shall include areas representative of Sig nificant corrosion or pitting.
After the wire removal, the tendons shall be retensioned to the stress level measured at the lift-off reading and then checked by a final lift-off reading.
Amendments Nos.
4.4-6
Should the inspection of one of the wires reveal any significant corrosion (pitting or loss of area), further inspection of the other two sets in that directional group will be made to determine the extent of the corrosion and its significance to the load-carrying capability of the structure.
The sheathing filler will be sampled and inspected for changes in physical appearance.
Wire samples shall be selected ih such a manner that with the third in spection, wires from all nine surveillance tendons shall have been inspected and tested.
4.4.2.2 Inspection Intervals and Reports For Unit 1, the initial inspection shall be within 18 months of the initial Reactor Building Structural Integrity Test.
The inspection intervals, measured from the date of the initial inspection, shall be two years, four years and every five years thereafter or as modified based on experience.
For Units 2 and 3 the inspection intervals measured from the date of the initial structural test shall be one year, three years and every five years thereafter or as modified based on experience.
Tendon surveillance may be conducted during reactor operation provided design conditions regarding loss of adjacent tendons are satisfied at all times.
A quantitative analytical report covering results of each inspection shall be submitted to the Commission within 90 days of completion, and shall especially address the following conditions, should they develop.
- a.
Broken wires.
- b. The force-time trend line for any tendon, when extrapolated, that extends beyond either the upper or lower bounds of the predicted dosign band.
- c. 'Unexpected changes in corrosion conditions or sheathing filler properties.
Bases Provisions have been made for an in-service surveillance program, covering the first several years of the life of the unit4 intended to provide suf ficient evidence to maintain confidence that the integrity of the Reactor Building is being preserved. This program consists of tendon, tendon anchorage and liner plate surveillance.
The first year tendon anchorage and liner plate saiveillance programs have been successfully completed.
To accomplish these programs, the following representative tendon groups have been selected for surveillance:
Horizontal -
Three 1200 tendons comprising one complete hoop system below grade Vertical Three tendons spaced approximately 1200 apart.
O Dome Three tendons spaced approximately 120 apart.
Amendments Nos.
.4-7
The inspection during this initial period of at least one wire from each of the nine surveillance tendons (one wire per group per inspection) is con sidered sufficient representation to detect the presence of any wide spread tendon corrosion or pitting conditions in the structure. This program will be subject to review and revision as warranted based on studies and on results obtained for this and other prestressed concrete reactor buildings during this period of time.
4.4-8 Amendments NoIS.?~,
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