ML15112A911
| ML15112A911 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 02/22/1980 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML15112A912 | List: |
| References | |
| NUDOCS 8003070061 | |
| Download: ML15112A911 (15) | |
Text
t REG N0A UNITED STATES' NULEAR REGULATORY COMMISSION WASHINGTON, 0. C.20555 DUKE POWER COMPANY DOCKET NO. 50,269 OCONEE NUCLEAR STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 80 License No. DPR-38
- 1. The Nuclear Regulatory Comission (the Commission) has found that:
A. The application for amendment by Duke Power Company (the licensee) dated November 30, 1976, as revised June 21, 1977, January 23, 1979, October 16, 1979, and February 6, 1980, 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; 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.
8OO3O7o (
- 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-38 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. 80 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 Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: February 22, 1980
UNITED STATES NL EAR REGULATORY COMMISSION WASHINGTON, D. C. 20655 DUKE POWER COMPANY DOCKET NO.
50-270 OCONEE NUCLEAR STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.80 License No. DPR-47
- 1. The Nuclear Regulatory Commission (the Coomission) has found that:
A. The application for amendment by Duke Power Company (the licensee) dated November 30, 1976, as revised June 21, 1977, January 23, 1979, October 16, 1979, and February 6, 1980, 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 Commissidn '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.B Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.80 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 Robert W. Reid, Chief Operating Reactors Branch F4 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of.Issuance:
February 22, 1980
- seUNITED STATES NcLEAR REGULATORY COMMISSION WASHINGTON, D. CM 20555 PUKE POWER COMPANY OCKE 5
NO. 087 OCONEE NUCLEAR STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 77 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 November 30, 1976, as revised June 21, 1977, January 23, 1979, October 16, 1979, and February 6, 1980, 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 Comnissidn'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
- 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. 77 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 ert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 22, 1980
ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 80 TO DPR-38 AMENDMENT NO. 80 TO DPR-47 AMENDMENT NO. 77.TO DPR-55 DOCKETS NOS. 50-269, 50-270 AND 50-287 Revise Appendix A as follows:
Remove Page Insert Page iv iv vi vi 4.17-1 through 4.17-6 The new pages and changes on the revised pages are indicated by marginal lines.
Section Pae 4.1.1 Containment Leakage Tests 4.4-1 4.4.2 Structural Integrity 4.4-6 4.4.3 Hydrogen Purge System 4.4-10 4.5 EMERGENCY CORE COOLING SYSTEMS AND REACTOR 4.5-1 BUILDING COOLING.SYSTEMS PERIODIC TESTING 4.5.1 Emergency Core Cooling Systems 4.5-1 4.5.2 Reactor Building Cooling Systems 4.5-6 4.5.3 Penetration Room Ventilation System 4.5-10 4.5.4 Low Pressure Injection System Leakage 4.5-12 4.6 EMERGENCY POWER PERIODIC TESTING 4.6-1 4.7 REACTOR CONTROL ROD SYSTEM TESTS 4.7-1 4.7.1 Control Rod Trip Insertion Time 4.7-1 4.7.2 Control Rod Program Verification 4.7-2 4.8 MAIN STEAM STOP VALVES 4.8-1 4.9 EMERGENCY FEEDWATER PUMP PERIODIC TESTING 4.9-1 4.10 REACTIVITY ANOMALIES 4.10-1 4.11 ENVIRONMENTAL SURVEILLANCE 4.11-1 4.12 CONTROL ROOM FILTERING SYSTEM 4.12-1 (INTENTIONALLY BLANK) 4.13-1 4.14 REACTOR BUILDING PURGE FILTERS AND THE SPENT 4.14-1 FUEL POOL VENTILATION SYSTEM 4.15 IODINE RADIATION MONITORING FILTERS 4.15-1 4.16 RADIOACTIVE MATERIALS SOURCES 4.16-1 4.17 STEAM GENERATOR TUBING SURVEILLANCE 4.17-1 4.18 HYDRAULIC SHOCK SUPPRESSORS (SNUBBERS) 4.18-1 4.19 FIRE PROTECTION AND DETECTION SYSTEM 4.19-1) 4.20 REACTOR VESSEL INTERNALS VENT VALVES 4.20-1 Amendments Nos. 80, 80 & 77 iv
0 0
LIST OF TABLES Table No.
Page 2.3-1A Reactor Protective System Trip Setting Limits -
Unit 1 2.3-11 2.3-18 Reactor Protective System Trip Setting Limits -
Unit 2 2.3-12 2.3-1C Reactor Protective System Trip Setting Limits -
Unit 3 2.3-13 3.5-1-1 Instrument Operating Conditions 3.5-3 3.5-1 Quadrant Power Tilt Limits 3.5-14 3.17-1 Fire Protection & Detection Systems 3.17-3 4.1-1 Instrument Surveillance Requirements 4.1-3 4.1-2 Minimum Equipment Check Frequency 4.1-9 4.1-3 Minimum Sampling Frequency 4.1-10 4.2-1 Oconee Nuclear Station Capsule Assembly Withdrawal Schedule 4.2-4 at Crystal River Unit No. 3 4.11-1 Oconee Environmental Radioactivity Monitoring Program 4.11-3 4.11-2 Offsite Radiological Monitoring Program 4.11-4 4.11-3 Analytical Sensitivity 4.11-5 4.17-1 Steam Generator Tube Inspection 4.17-5 4.18-1 Safety Related Shock Suppressors (Snubbers) 4.18-3 6.1-1 Minimum Operatinq Shift Requirements with Fuel in Three 6.1-6 Reactor Vessels 6.6-1 Report of Radioactive Effluents 6,6.8 Amendments Nos. 80, 80 & 77 vi
4.17 STEAM GENERATOR TUBING SURVEILLANCE Applicability Applies to the surveillance of tubing of each steam generator.
Obiective 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 inspec tion equipment shall provide a sensitivity that will detect defects with a pene tration of 20 percent or more of the minimum allowable as-manufactured tube wall thickness.
4.17.2 Acceptance Criteria The.steam generator shall be considered operable after completion of the speci fied actions. All tubes examined exceeding the plugging limit shall be 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 nouplugged tubes that previously had detectable wall pene trations (>20%).
- 2. At least 50% of the tubes inspected shall be in those areas where experience has indicated potential problems.
- 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.
Amendments Nos. 80, 80 & 77 4.17-1
(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 tube sheet array where tubes with imperfections were previously found.
- 2. The inspections include those portions of the tubes where imper fections were previously found.
The results of each sample inspection shall be classified into one of the following three categories:
Category Inspection Results C-].
Less than 5% of the total tubes inspected are degraded tubes and none of the inspected tubes are defective.
C-2 Ond 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 deter mining the Inspection Results Category for the general steam generator inspection, unless the mechanism of degradation is random in nature.
4.17.4 Inspection Intervais The above required inservice inspections of steam generator tubes shall be per formed 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 consecu tive inspections demonstrate that previously observed degradation 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 Amendments Nos. 80, 80 & 77 4.17-2
than 10 months nor more than one fuel cycle after the previous inspec tion. The increase in inspection frequency shall apply until a subse quent inspection meets the conditions specified.Ln 4.17.4.a and the interval can be extended to a maximum of 40 months.
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 Specifica tion 3.1.6, additional inspections 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 will be inspected.
- 2. If the leaking tube is not in a Group as defined in 4.17.4.d.1, then an additional inspection will be performed on the affected steam generator in accordance withTable 4.17-1.(i.e., a minimum of S 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 wall thick ness, 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.
- c.
Degraded Tube means a tube containing imperfections >20% of the nominal wall thickness caused by degradation.
- d.
% Degradation means the percentage of the tube wall thickness affected or removed by degradation.
- e.
Defect means an imperfection of such severity that it exceeds the plugging limit. A tube containing a defect is defective.
- f.
Plugging Limit means the imperfection depth beyond which the tube shall be removed from service because it may become unserviceable prior to the next inspection; it is equal to 40% of the nominal tube wall thickness.
- g.
Unserviceable describes the condition of a tube if it leaks or contains Amendments Nos. 80, 80 & 77 4.17-3
a defect Large enough to affect its structural integrity in the event of an Operating 3asis Earthquake, a l.s-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 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 procedure.
- b.
The results of the steam generator tube inservice inspection shall be reported to the NRC within 3 months following completion of the inspec tion. This report shall include:
- 1. Number 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.
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 inves tigations.conducted to determine cause of the tube degradation and correc tive 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 inspec tion of steam generator tubing also provides a means of characterizing the nature and cause of any tube degradation so that corrective measures may be taken.
Removal from service will be required for any tube with service-induced metal loss in excess of 40% of the tube nominal wall thickness or with a through wall crack. Additional corrective actions may be required to stabilize a circum ferentially 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 gen erators is inspected. The results of the latter inspection dictate the extent of further examinations.
Amendments Nos. 80, 80 & 77 4.17-4
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 inspec 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 removed from service. NRC concurrence in this determination is required prior to completion of the inspection.
This inspection plad 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.
Amendments Nos.
80 80, &77 4.17-5
TABLE 4.1 /-1 STEAM GENERATOR TUBE INSPECTIoN (D
IST SAMPLE INSPECTION 2ND SAMPLE INSPECTION 3RD SAMPLE INSPECTION CD Sample Size Result Action Required Result Action Result Action Cd, A minimum of C-1 None N/A N/A N/A N/A S Tubes per 0
S.G.
(1)
C-2 Plug defective tubes C-I None N/A 00 and inspect additional C
2S tubes in this S.C.
2 Plug defective tubes & Inspect C-N/A additional 4S tubes in this S.C.
OO C-2 Plug defective tubes C
o2.0C-3 Plug defective tubes and perform action for C-3 result of lst Sample C-3 Plug defective tubes and perform N/A N/A actions for C-3 result of let Sample C-3 Inspect 6S tubes in this C-I N/A N/A N/A S.G., plug defective tubes & Inspect 2S tubes C-2 N/A N/A N/A in the other S.C.
Per form follow-on inspec lions in the other S.C.
in accordance with re stilts of the above inspec-C-3 (a) If defects can be localized C-1 N/A tion as applied to Table (2) to an affected area, inspect 4.17-1.
all tubes In affected area C-2 N/A and plug defective tubes.
Prompt notification to NRC pursuant to specifi-(b) If defects cannot be local-C-3 N/A cation 6.6.2.1.a ized to an affected area, inspect all tubes in this S.G. and plug defective tubes Notes:
(1)
S = 3 NZ Where N Is the number of steam generators in the unit, aind n is the number of steam generators Inspected during an n
inspect Ion.
(2) Affected and unaffected areas shall be 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.