ML20115C465
| ML20115C465 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 10/08/1992 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20115C466 | List: |
| References | |
| NUDOCS 9210190389 | |
| Download: ML20115C465 (6) | |
Text
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UNITED STATES 8'
NUCLEAR REGULATORY COMMISSION n
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LOUTHERN NUCLEAR OPERATING COMPANY. INC.
DOCKET NO. 50-348 JOSEPH 4. FARLEY NUCLEAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No-95 License No. NPF-2 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Southern Nuclear Operating Company, Inc. (Southern Nuclear), dated August 24, 1992, as supplemented on September 29, 1992, 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 license amendment will not be inimical to the ommon 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 2.c.(2) of Facility Operating License No. NPF-2 is hereby amended to read as follows:
9210190389 921008 PDR ADOCK 05000348 P
1 (2)
Technical Specificatiqn_s The Technical Specifications contained in Appendices A and 8, as revised through Amendment No.
95
, are hereby incorporated into the license.
Southern Nuclear shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its datc of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION W
Elinor G. Adensam, Director Project Directorate II-l Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: October 8, 1992
s 9
4 ATTACHMENT TO't.lCENSE AMENDMENT N0. 95 FACillTY OPERATING LICENSE NO, NPF-2 DOCKET NO. 50-348 Replace the following pages,of the Appendix A Technical Specifications with the enclosed pages-as indicated.
The revised areas are indicated by marginal lines.
Remove Paaes Insert Paaes 3/4 4-12 3/4 4-12 3/4 4-12a B 3/4 4-3 B 3/4 4-3
REACTOR COOLANT. SYSTEM SVRVEILLANCE REQUIREMENTS (Continued) 4.4.6.4 Acceptance Criteria a.
As used in this Specification:
1.
Imoerfection means an exception to the di w nsions, finish or contour of a tube or sleeve from that required b3 'abrication drawings or specifications.
Eddy-current testing indications below 20% of the nominal wall thickness, if detectable, may be considered as imperfections.
2.
Dearadation means a service-induced cracking,
wastage, wear or general corrosion occurring on either inside or outside of a tube or sleeve.
3.
Daaraded Tube means a tube, including the sleeve if the tube has been repaired, that contains imperfections greater than or equal to 20% of the nominal wall thickness caused by degradation.
4.
% Dearadation means the percentage of the tube or sleeve wall thickness affected or removed by degradation.
5.
Dif.rl means an imperfection of such severity that it exceeds the plugging or repair limit. A tube or sleeve containing ; defect is defec'ive.
6.
Pluaaina or Rooair Limit means the imperfection depth at or beyond which the tube shall be repaired (i.e., sleeved) or removed from service by plugging and is greater than or eJal to 40% of the nominal tube wall thickness.
For a tube that has been sleeved with a mechanical joint sleeve, through wall penetration of greater than or equal to 31% of sleeve nominal wall thickness in the sleeve requires the tube to be removed from service by plugging.
For a tube that has been sleeved with a welded joint sleeve, through wall penetration greater than or equal to 37% of sleeve nominal wall thickness in the c.leeve between the weld joints requires the tube to be removed from service by plugging. At tube support' plate intersections, the repair limit for the Twelfth Operating Cycle is based on maintaining steam generator tube serviceability as described below; a.
An eddy current examination using a bobbin probe of 100% of the hot and cold leg steam ge_nerator tube support plate intersections will be perforced for tubes in service.
b.
Degradation attributed to outside diameter stress corrosion cracking within the bounds of the tube support plate with bobbin voltage less than or equal to 1.0 volt will be allowed to remain in service.
c.
Degradation attributed to outside diameter stress corrosion cracking within the bounds of the tube support plate with a bobbin voltage greater than 1.0 volt will be repaired or plugged except as noted in 4.4.6.4.a.6.d below.
I FARLEY-UNIT 1 3/4 4-12 AMENDMENT N0.
26,77, 85, 95
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SURVEILLANCt: REQUIREKSP'6 (Continued)L d _ Indications of potential: degradation attributed to'outside diameter stress corrosion cracking within the bounds of the tube support' plate with'a bobbin voltage greater than 1.0 volt-but less than or equal to 3.6 volts may remain in service if a rotating-pancake coil probe (RPC)1 inspection does-not' detect degradation.
Indications of-outside diameter stress corrosion cracking-degradation with a bobbin. voltage greater than 3.6 volts willL be; plugged or repaired.
7.
Unserviceable describes the condition of a tube or sleeve if it leaksi 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 4.4.6.3.c,'above.
8.
Tube Inspection means an inspection of-the steam generat'or tubeLfrom the point of entry (hot leg side) completely around the-U-bendito the top support of the cold leg.
For-a tube sat has been repaired by sleeving, the tube inspection should 'oclude the sleeved portion of-the tube.
9.
Tube Repair refers to mechanical sleeving, as described by-Westinghouse. report WCAP-lll78, Rev.1, or laser welded sleeving, as described by Westinghouse report WCAP-12672, which is used to maintain, a tube in service or return a tube'to service.
This includes the removal of plugs that were installed-as a corrective or preventive measure.
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I
'FARLEY-UNIT 1 3/4 4-12a AMENDMENT NO. 95 V
. ~ -
REACTOR C00 TANT SYSTEM BASES 3/4.4.6 STEAM GENERATORS 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 terors, 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.
The plant is expected to be operated in a manner such that the secondary coolant will be maintained within those enemistry limits found to result in negligible corrosion of the steam generator tubes.
If the secondary coolant chemistry is not maintained within these limits, localized corrosion may likely result in stress corrosion cracking.
The extent of cracking during plant operation would be limited by the limitation of steam generator tube leakage between the primary coolant system and the secondary coolant system (primary 4.o-se ondary leakage - 140 gallons per day per steam generator).
Cracks having a p;1ma: 3 -to-secondary leakage less than this limit during operation will have an adequate margin of safety to withstand the loads imposed during normal operation and by postulated accidents. Operational leakage of this magnitude can be readily detected by existing Farley Unit I radiation monitors.
Leakage in excess of this limit will require plant shutdown and an unscheduled inspection, during which the leaking tubes will be located and plugged or repaired.
For the Twelfth Operating Cycle only, the repair limit for tubes with flaw indications contained witnin the bounds of a tube support plate has been provided to the NRC in Southern Nuclear Operating Company letter dated August 24, 1992.
The repair limit is based on the analysis contained in WCAP-12871, Revision 2, "J. M. Farley Units 1 and 2 SG Tube Plugging Criteria for ODSCC at Tuba 'upport Plates." The application of this criteria is based on limiting primary-tr
.ondary leakage during a steam line break to less than 1 gallon per minute.
Wastage-type defects are unlikely with proper chemistry treatment of the secondary coolant.
However, even if a defect should develop in service, it will be found during scheduled inservice steam generator tube examinations.
Plugging or repair will be required for all tubes with imperfections exceeding 40% of the tube nominal wall thickness.
If a sleeved tube is found to have through wall penetration of greater than or equal to 31% for the mechanical sleeve and 37% for the laser welded sleeve of sleeve nominal wall thickness in the sleeve, it must be plugged. The 31% and 37%
limits are derived from R.G.1.121 calculations with 20% added for conservatism.
The portion of the tube and the sleeve for which indications of wall degradation must be evaluated can be summarized as follows:
a.
Mechanical 1.
Indications of degradation in the entire length of the sleeve must be evaluated against the sleeve plugging limit.
2.
Indication of tube degradation of ary type including a complete guillotine break in the tube between the bottom of the upper joint and the top of the lower roll expansion does not require that the tube be removed from service, i,
FARLEY-UNIT 1 B3/4 4-3 AMENDMENT N0. S7, 72, a%