ML16293A739
| ML16293A739 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 09/01/1987 |
| From: | Crocker L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML16138A601 | List: |
| References | |
| NUDOCS 8709090031 | |
| Download: ML16293A739 (13) | |
Text
o, UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO. 50-269 OCONEE NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 161 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 January 16, 1986, as supplemented on April 18, June 27, and September 15, 1986, and April 3, 1987, 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 1; 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 amended by changes to the Technical Specifications as indicated in the attachments to this license amendment, and Paragraph 3.B of Facility Operating License No. DPR738 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. 161, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
8709090031 870901 PDR ADOCK 05000269 P
PDR.
-2
- 3. This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Lawrence P. Crocker, Acting Director Project Directorate 11-3 Division of Reactor Projects -
I/II
Attachment:
Technical Specification Changes Date of Issuance: September 1, 1987 SEE PREVIOUS CONCURRENCES PDII-3/DRP-I/II PDII-3/DRP-I/II OGC-Bethesda PD I-3/DRP-I/II MDuncan/rad
- HPastis
- JScinto LCrocker, Acting PD 09/ /87 07/10/87 07/30/87 09/1 /87
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. 161 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 January 16, 1986, as supplemented on April 18, June 27, and September 15, 1986, and April 3, 1987, 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 1; 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 Comission'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 attachments to this license amendment, and Paragraph 3.8 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. 161, 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 its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Lawrence P. Crocker, Acting Director Project Directorate 11-3 Division of Reactor Projects -
I/II
Attachment:
Technical Specification Changes Date of Issuance:
September 1, 1987 SEE PREVIOUS CONCURRENCES PDII-3/DRP-I/II PDII-3/DRP-I/II OGC-Bethesda PDII-3/DRP-I/II MDuncan/rad
- HPastis
- JScinto LCrocker, Acting PD 09/ /87 07/10/87 07/30/87 09/ / /87
oE(
UNITED STATES 0
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. 158 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 January 16, 1986, as supplemented on April 18, June 27, and September 15, 1986, and April 3, 1987, 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. Ttere 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 1; 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 amended by changes to the Technical Specifications as indicated in the attachments to this license amendment, and Paragraph 3.B 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. 158, 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 its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Lawrence P. Crocker, Acting Director Project Directorate 11-3 Division of Reactor Projects -
I/II
Attachment:
Technical Specification Changes Date of Issuance:
September 1, 1987 SEE PREVIOUS CONCURRENCES PDII-3/DRP-I/II PDII-3/DRP-I/II OGC-Bethesda PDII-3/DRP-I/II MDuncan/rad
- HPastis
'*JScinto LCrocker, Acting PD 09/ /87 07/10/87 07/30/87 09/ I /87
ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 161 TO DPR-38 AMENDMENT NO. 161 TO DPR-47 AMENDMENT NO. 158 TO DPR-55 DOCKET NOS. 50-269, 50-270, AND 50-287 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised page are identified by amendment number and contain vertical lines indicating the areas of change.
Remove Insert Page Page 4.17-1 4.17-1 4.17-2 4.17-2 4.17-3 4.17-3 4.17-4 4.17-4 4.17-5 4.17-5 4.17-6 4.17-6
4.17 STEAM GENERATOR TUBING SURVEILLANCE Applies to the surveillance of tubing of each steam generator.
Objective.
To ensure integrity of the steam generator tubing through a defined inservice surveillance program, and to minimize exposure of personnel to radiation during performance of the surveillance program.
Specification 4.17.1 Examination methods Inservice inspection of steam generator tubing shall include non-destructive examination by eddy-current testing or other equivalent techniques.
The inspection equipment shall provide a sensitivity that will detect defects with a penetration of 20 percent or more of the minimum allowable as-manufactured tube wall thickness.
4.17.2 Acceptance Criteria The steam generator shallube considered operable after completion of the specified actions.
All tubes examined exceeding the repair lim It shall be repaired by sleeving or removed from service (e.g., plugged, stabilized).
4.17.3 Selection and Testing The steam generator tube minimum sample size, inspection result classification, and the corresponding action required shall be as specified in Table 4.17.1.
The inservice inspection of steam generator tubes shall be performed at the frequencies specified in Specification 4.17.4 and the inspected tubes shall be verified acceptable per Specification 4.17.5. The tubes selected for each inservice inspection shall include at least 3% of the total number of tubes in both steam generators, with one or both steam generators being inspected.
The tubes selected for these inspections shall be selected on a random basis except:
- a.
The first sample inspection during each inservice inspection of each steam generator shall include:
- 1.
All tubes that previously had detectable wall penetrations (>20%)
and have not been plugged or sleeve repaired in the affected area.
- 2.
At least 50% of the tubes inspected shall be in those areas where experience has indicated potential problems. i
- 3.
A tube adjacent to any selected tube which does not permit passage of the eddy current probe for tube inspection.
- b.
Tubes in the following Group(s) may be excluded from the first sample if all tubes in a Group in both OTSG are inspected.
No credit will be taken for these tubes in meeting minimum sample size requirements.
4.17-1 Amendment No. 161 (Unit 1)
Amendment No. 161 (Unit 2)
Amendment No. 158 (Unit 3)
00 (1)
Group A-1:
Tubes within one, two, or three rows of the open inspection lane.
- c.
The tubes selected as the second and third samples (if required by Table 4.17.1) during each inservice inspection may be subjected to less than a full tube inspection provided:
- 1.
The tubes selected for these samples include the tubes from those areas of the tubesheet array where tubes with imperfections were previously found.
- 2.
The inspections include those portions of the tubes where imperfections were previously found.
The results of each sample inspection shall be classified into one of the following three categories:
Category Inspection Results C.1 Less than 5% of the total tubes inspected are degraded tubes and none of the inspected tubes are defective.
C.2
-One or more tubes, but not more than 1% of the total tubes inspected are defective, or between 5% and 10% of the total tubes inspected are degraded tubes.
C.3 More than 10% of the total tubes inspected are degraded tubes or more than 1% of the inspected tubes are defective.
NOTES:
(1) In all inspections, previously degraded tubes must exhibit significant (>10%) further wall penetrations to be included in the above percentage calculations.
(2) Where special inspections are performed pursuant to 4.17.3.b, defective or degraded tubes found as a result of the inspection shall be included in determining the Inspection Results Category for that special inspection but need not be included in determining the Inspection Results Category for the general steam generator inspection, unless the mechanism of degradation is random in nature.
4.17.4 Inspection Intervals The above required inservice inspections of steam generator tubes shall be performed at the following frequencies.
- a.
Inservice inspections shall be performed at intervals of not less than 12 nor more than 24 calendar months after the previous inspection. If the results of two consecutive inspections following service under all volatile treatment (AVT) conditions fall into the C-1 category or if two consecutive inspections demonstrate that previously observed degradation 4.17-2 Amendment No. 161 (Unit 1)
Amendment No. 161 (Unit 2)
Amendment No. 158 (Unit 3)
has not continued and no additional degradation has occurred, the inspection interval may be extended to a maximum of 40 months.
- b.
If the results of the inservice inspection of a steam generator performed in accordance with Table 4.17-1 at 40 month intervals fall in Category C.3, subsequent inservice inspections shall be performed at intervals of not less than '10 months nor more than one fuel cycle after the previous inspection. The increase in inspection frequency shall apply until a subsequent inspection meets the conditions specified in 4.17.4.a and the interval can be extended to a maximum of 40 months.
- c.
Additional, unscheduled inservice inspections shall be performed on each steam generator in accordance with the first sample inspection specified in Table 4.17-1 during the shutdown subsequent to any of the following conditions:
- 1.
A seismic occurrence greater than the Operating Basis Earthquake,
- 2.
A loss-of-coolant accident requiring actuation of the engineered safeguards, or
- 3.
A main steam line or feedwater line break.
- d.
After primary to secondary leakage in excess of the limits of Specification 3.1.6, an inspection of the affected steam generator will be performed in accordance with the following criteria:
- 1.
If the leaking tube is in a Group as defined in Section 4.17.3.b, all of the tubes in this Group in this steam generator will be inspected. If the results of this inspection fall into the C-3.
category, additional inspections will be performed in the same Group in the other steam generator.
- 2.
If the leaking tube is not in a Group as defined in 4.17.4.d.1, then an inspection will be performed on the affected steam generator in accordance with Table 4.17-1 with an initial inspection sample size of 6% of the tubes in the affected steam generator.
4.17.5 Definitions As used in this specification:
- a.
Imperfection means an exception to the dimensions, finish or contour of a tube from that required by fabrication drawings or specifications.
Eddy-current testing indications below 20% of the nominal tube or sleeve wall thickness, if detectable, may be considered as imperfections.
- b.
Degradation means a service-induced cracking, wastage, wear or general corrosion occurring on either the inside or outside of a tube or a sleeve.
- c.
Degraded Tube means a tube or a sleeve containing imperfections > 20% of the nominal wall thickness caused by degradation.
4.17-3 Amendment No. 161 (Unit 1)
Amendment No. 161 (Unit 2)
Amendment No. 158 (Unit 3)
__ 0
- d.
i Degradation means the percentage of the tube or sleeve wall thickness affected or removed by degradation.
- e.
Defect means an imperfection of such severity that it exceeds the repair limit.- A tube or sleeve containing a defect is defective.
- f.
Repair Limit means the imperfection depth beyond which the tube shall be either removed from service by plugging or repaired by sleeving because it may become unserviceable prior to the next inspection; it is equal to 40% of the nominal tube or sleeve wall thickness.
The Babcock and Wilcox process (or method) equivalent to the method described in report, BAW-1823P, Revision 1 will be used.
- g.
Unserviceable describes the condition of.a tube if it leaks or contains a defect large enough to affect its structural integrity in the event of an Operating Basis Earthquake, a loss-of coolant accident, or a steam line or feedwater line break as specified in Specification 4.17.4.
- h.
Tube Inspection means an inspection of the steam generator tube from the point of entry completely to the point of exit.
4.17.6 Reports
- a.
The number of tubes plugged or repaired in each steam generator shall be reported to the Director, Office of Inspection and Enforcement, Region II, within 30 days following the completion of the plugging or repair procedure.
- b.
The results of the steam generator tube inservice inspection shall be reported to the NRC within 3 months following completion of the inspection. This report shall include:
- 1. JNumber and extent of tubes inspected.
- 2.
Location and percent of wall-thickness penetration for each indication of a degraded tube.
- 3.
Identification of tubes plugged or repaired.
- c.
Results of steam generator tube inspections which fall into Category C-3 and require prompt notification of the NRC shall be reported pursuant to Specification 6.6.2.1.a prior to resumption of plant operation. The written followup of this report shall provide a description of investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence.
Bases The program of periodic inservice inspection of steam generators provides the means to monitor the integrity of the tubing and to maintain surveillance in the event there is evidence of mechanical damage or progressive deterioration due to design, manufacturing errors, or operating conditions. Inservice inspection of the steam generator tubing also provides a means of characterizing the nature and cause of any tube degradation so that corrective measures may be taken.
4.17-4 Amendment No. 161 (Unit 1)
Amendment No. 161 (Unit 2)
Amendment No. 158 (Unit 3)
Repair or removal from service will be required for any tube with service induced metal loss in excess of 40% of the tube or sleeve nominal wall thickness or with a through wall crack. Additional corrective actions may be required to stabilize a circumferentially cracked tube.
The initial sample of tubes inspected in a steam generator includes tubes from three groups.
First, lane tubes are inspected to assure their integrity.
Second, all other inservice tubes with degradation, inspected in previous inspections, are inspected to assure tube integrity and determine degradation growth, if any. Third, a random sample of 3% of the total number of tubes in both steam generators is inspected. The results of the latter inspection dictate the extent of further examinations.
An objective of this Specification is to provide an inspection plan which will insure, with a high degree of confidence, that no more than 30 defective tubes will remain in a steam generator after an initial C-3 category inspection.
Following an 18% random inspection (C-3 category inspection) an unaffected area is identified. The unaffected area will be logically and consistently defined based on generator design, defect location and characteristics. The criteria for accepting an area as unaffected depend on the number of defects found in the sample inspected in that area and are established such that there is a 0.05 or smaller probability of accepting the area as unaffected if it contains 30 or more defective tubes.
Experience with Babcock and Wilcox steam generators has indicated that tubes near the open inspection lane are susceptible to forms of degradation unique to that area. Therefore, tubes within one, two, or three rows of the insp'ec tion lane have been defined as a special group. If all of these tubes are inspected in both steam generators, no credit will be taken for them in meeting minimum sample size requirements and the results of their inspection will not be used in classifying the results of the general inspection into C-1, C-2 or C-3 categories, unless the mechanism of tube degradation is random in nature. Random degradation mechanisms are those which based on location, steam generator design and operation, and operating experience cannot logi cally and consistently be shown as limited to a local area.
The affected area will be 100% inspected to assure all defective tubes therein are identified and either removed from service or repaired by sleeving. NRC concurrence in this determination is required prior to completion of the inspection.
Degraded steam generator tubes can be repaired by the installation of sleeves which span the area of degradation and serve as a replacement pressure boundary for the degraded portion of the tube, thus permitting the tube to remain in service.
This inspection plan enables exposures to be maintained as low as reasonably achievable to the personnel involved in the inspection and assures that generator areas with significant numbers of degraded tubes are adequately inspected.
4.17-5 Amendment No. 161 (Unit 1)
Amendment No. 161 (Unit 2)
Amendment No. 158(Unit 3)
TABLE 4.17-1 STEAM GENERATOR TUBE INSPECTION Ist SAMPLE INSPECTION 2nd SAMPLE INSPECTION 3rd SAMPLE INSPECTION SAMPLE SIZE RESULT ACTION REQUIRED RESULT ACTION RESULT ACTION A minimum of C-1 None N/A N/A N/A N/A S Tubes per S.G. (1)
C-2 Plug or repair defective C-1 None N/A tubes and inspect additional 2S tubes in C-2 Plug or repair defective C-1 N/A tubes and inspect additional 4S tubes in this S.G.
C-2 Plug or repair defective tubes C-3 Plug or repair defective tubes and perform action for C-3 result of Ist Sample C-3 Plug or repair defective N/A N/A tubes and perform actions for C-3 results of Ist Sample C-3 Inspect 6S tubes in this C-1 N/A N/A N/A S.C., plug or repair defective tubes and C-2 N/A N/A N/A inspect 2S tubes in the other S.G. Perform follow-on inspections in the other S.G. in accordance with results C-3 (a) if defects can be C-1 N/A of the above inspection (2) localized to an affected as applied to Table 4.17.1 area, inspect all tubes C-2 N/A in affected area and Prompt notification to NRC plug or repair defective C-3 N/A pursuant to specification tubes.
6.6.2.1.a (b) If defects cannot be localized to an affected area, inspect all tubes in this S.G. and plug or repair defectives tubes.
Notes:
(1) S 3(N/n)% Where N is the number of steam generators in the unit, and n is the number of steam generators inspected during an inspection (2) Affected and unaffected areas shall he determined in the manner described in the Bases of this specification.
The definition of these areas will be reported to the NRC when they are determined.
4.17-6 Amendment No. 161 (Unit 1)
Amendment No. 161 (Unit 2)
Amendment No. 158 (Unit 3)