ML20216E504
| ML20216E504 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 04/10/1998 |
| From: | William Reckley NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20216E509 | List: |
| References | |
| NUDOCS 9804160230 | |
| Download: ML20216E504 (5) | |
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4 UNITED STATES g
.g NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 20665 4001 49.....,o ENTERGY OPERATIONS INC.
DOCKET NO. 50-313 ARKANSAS NUCLE / R ONE. UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.191 License No. DPR-51 l
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the licensee) dated April 1,1998, as supplemented by letter dated April 8,1998, complies with the i
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 tne rules and regulations of the Commission; C.
There is reasonable assurance: (l) 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 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 I
Commission's regulations and all applicable requirements have been satisfied.
9804160230 980410 PDR ADOCK 05000313 P
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2 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. DPR-51 is hereby amended to read as follows:
2.
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.191, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The license amendment is effective as of its date of issuance.
j FOR THE NUCLEAR REGULATORY COMMISSION l
William Reckley, Project Manager Project Directorate IV-1 Division of Reactor Projects Ill/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: April 10, 1998
ATTACHMENT TO LICENSE AMENDMENT NO.191 FACILITY OPERATING LICENSE NO. DPR-51 DOCKET NO. 50-313 Replace the following page of the Appendix "A" Technical Specifications with the attached page.
The revised page is identified by Amendment number and contain vertical lines indicating the l
area of change.
REMOVE PAGE INSERT PAGE 110m1 110m1 110n 110n l
1 i
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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 4.18.4.c.
9.
Tube insoection r%ans an inspection of the steam generator tube from the point of entry completely to the point of exit. For tubes that have been repaired by the reroll process within the upper tubesheet, that portion of the tube above the new roll can be excluded from future periodic inspection requirements because it is no longer part of the pressure boundary once the repair roll is installed.
b.
The steam generator shall be determined operable after completing the corresponding actions (plug, reroll, or sleeve all tubes exceeding the plugging limit and all tubes containing through-wall cracks) required by Table 4.18-2 with the following exception:
Tubes with outer diameter intergranular attack indications within the upper tubesheet with potential of through-wall depths greater than the plugging limit, located by eddy current between 2.75 inches above the secondary face and below the roll transition, may remain in service for Cycle 15 contingent upon the following conditions:
1.
One hundred percent of the unsleeved tubes are examined by bobbin coil eddy current in the upper tubesheet region during the fourteenth refueling outage, 2.
Bobbin coil indications in the upper tubesheet region are examined by rotating pancake coil eddy current and confirmed to be volumetric, 3.
A comparison shall be made between the bobbin coil voltage measured during the thirteenth refueling outage for the confirmed indications and the bobbin coil voltage for the same indications measured during the fourteenth refueling outage.
The comparison shall confirm essentially no increase in voltage on average, 4.
Tubes containing indications with bobbin coil voltage amplitudes > 0.7 volt and having growth > 0.3 volt since the last inspection shall be plugged or repaired, and 5.
In-situ pressure testing in the "A" steam generator during the fourteenth refueling l'
outage confirms, at a 95% confidence level, that the bounding accident leakage due to volumetric ODIGA flaws within the upper twesheet region will be less than 0.5 gallon per minute due to a main steam line break.
4.18.6 Reoorts Following each inservice inspection of steam generator tubes, the complete results of the inspection shall be reported to the NRC. This report, to be submitted within 45 days of inspection completion, shall
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include:
a.
Number and extent of tubes inspected; b.
Location and percent of wall-thickness penetration for each indication of an imperfection; l
c.
Identification of tubes plugged and tubes sleeved; and Amendment No. 24,41,00,100,134, 110m1 469690,191
d.
Number of tubes repaired by rerolling and number ofindications detected in the new roll area of the repaired tubes.
This report shall be in addition to a Special Report (per Specification 6.12.5.d) required for the results of steam generator tube inspections which fall into Category C-3 as denoted in Table 4.18-2. The Commission shall be notified of the results of steam generator tube inspections which fallinto Category C-3 prior to resumption of plant operation. The written Special Report shall provide a description of I
investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence.
Bases l
The surveillance requirements for inspection of the steam generator tubes ensure that the structural integrity of this portion of the RCS will be maintained. The program for inservice inspection of steam generator tubes is based on a modification of Regulatory Guide 1.83, Revision 1. Inservice inspection of steam generator tubing is essential in order to maintain surveillance of the conditions of the tubes in the event that there is evidence of mechanical damage or progressive degradation due to design, manufacturing errors, or inservice conditions that lead to corrosion. Inservice inspection of steam generator tubing also provides a means of characterizing the nature and cause of any tube degradation so that corrective measures can be taken.
Steam generator tubes that are degraded beyond the repair limit can either be plugged, sleeved, or rerolled. The steam generator tubes that are plugged are removed from service by the installation of plugs at both ends of the associated tube and thus completely removing the tube from service.
Degraded steam generator tubes can also 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.
Degraded steam generator tubes can also be repaired by the rerolling of the tube in the upper tubesheet to create a new roll area and pressure boundary for the tube. The rerolling methodology establishes a new pressure boundary below the degradation, thus permitting the tube to remain in service. The degraded tube above the new roll area can be excluded from future periodic inspection requirements because it is no longer part of the pressure boundary once the repair roll is installed in the upper tubesheet. The reroiling repair process will only be used to repair defects in the upper tubesheet in accordance with BAW-10232P, Revision 00.
All tubes which have been repaired using the reroll process will have the new roll area inspected during future inservice inspections. Defective or degraded tube indications found in the new roll and any indications found in the original roll need not be included in determining the inspection Results Category for the generator inspection.
The reroll repair process will only be used tc repair tubes with defects in the upper tubesheet area. The reroll repair process will be performed only once per steam generator tube using a 1 inch roll length.
Thus, multiple applications of the reroll process to any individual tube is not acceptable. The new roll area must be free of detectable degradation in order for the repair to be considered acceptable. After the new roll area is initially deemed acceptable, future degradation in the new roll area will be analyzed to determine if the tube is defective and needs to be removed from service. The reroll repair process is described in the topical report, BAW-10232P, Revision 00.
Amendment No. N A1,00,l'91' 06,+Hh 110n 172,100,
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