L-12-331, Technical Specification 5.6.6.1 - Steam Generator Inspection Report
| ML12299A088 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 10/24/2012 |
| From: | Harden P FirstEnergy Nuclear Operating Co |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| L-12-331 | |
| Download: ML12299A088 (10) | |
Text
{{#Wiki_filter:FENOG FlrstEnergy Nuclear Operatlng Company Beaver Valley Power Station P.O. Box 4 Shippingport, PA 15077 Paul A, Harden Sife Vice President O c t o b e r 2 4, 2 0 L z L-12-331 724-682-5234 724-643-8069 ATTN: Document Control Desk U.S, Nuclear Regulatory Commission Washington, DC 20555-0001 S U BJ ECT: Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 Technic-al Specification 5.O6, 1 - Steam Generator Inspeqtion.Report ln accordance with Technical Specification 5,6,6.1, FirstEnergy Nuclear Operating Company hereby submits information related to steam generator inspections peformed during the Beaver Valley Power Station, Unit No. 1, spring 2012 refueling outage. The enclosed report includes the required information about the inspections, including tabulations of steam generator examination results for tubes in the A, B, and C steam generators. There are no regulatory commitments contained in this letter. lf there are any questions or if additional information is required, please contact Mr, Thomas A, Lentz, Manager-Fleet Licensing, at (330) 315-6810. Paul A. Harden
Enclosure:
Unit #1 - 1R21 Steam Generator '180 Day Report cc. NRC Region I Administrator NRC Resident Inspector NRC Project Manager Director BRP/DEP Site BRP/DEP Representative
Enclosu re L-12-331 Unit #1 - 1R21 Steam Generator 180 Day Reporl (B Pages Follow)
FIRST ENERGY NUCLEAR OPERATING COMPANY Technical Services Engineering Department Nuclear Engineering Programs Section lssue Date: September 4,2012
Subject:
Unit #1 - 1R21 Steam Generator 180 Day Report Prepared by: Reviewed by: Approved by: /'), i( Carl Battistone Lq^J-Y WTf," Acting Manager, Technical Services Date: qloq ltz Date: Q' 't- ' t-Date: Steam Generator m Owner Acting Supervisor, Nu ar Programs
I nfo rrn ?,t! g n Re q ulled" b,v Tech n f c a l. I p e c lfi c at i o n 5.6. 6, 1 Technical Specification 5.6,6,1 requires roportlng of the followlng information after completion of an inspoction performed in accordance with Speclfication 5,5,5.1, "Unit 1 Stearn Generator Program", lnformation requlred by TS 5.6.6,1 ls provided below for activities performed durlng the spring2012 refueling outage (1R21), Refer to the Definitions of Abbreviations,
- Codes, and Reporting Termlnology section of this repoft for abbreviations, codes and other terrns used lhroughout this report, a) Scope of inspections performed on each stearn generator:
Prirnary Slde: 50 percenl full length bobbin probe examinatlon (Rows 3 and up) 50 percent bobbin examlnallon of hot and cold leg stralght sectlons in Rows 1 and 2 50 percent Plus Point probe (magnetically biased) inspection of all Row 1 and 2 U-bends 100 percent Plus Point probe inspectlon of tubesheet dlametrlcal over-expansions and bulges reported from the pre-serulce examination at 10.0 inches or hlgher referenced frorn the hot leg tube end, on tubes in the 50 percent bobbln coil inspectlon program Hot and cold leg top of lubosheet Plus Point probe inspection 360 degrees around the tube bundle periphery and tube lano region (two to three tubes deop Into tube bundle) 100 percent Plus Point probe inspection of bobbin coil slgnals reported as an "l-code" Plus Polnt probe testing of any speclal interest tubes/locations, as required Visual oxamlnations were pefformed of the divider plate to channelhead wefd, the tubesheet to stub runner weld and stub runner to divider plate weld. These examinatlons were performed in response to Westlnghouse Nuclear Safety Advisory Letter NSAL-12-1, "Steam Generator Channel Head Degradation," January 2A12 and NRC Information Notice lN 2010-07, "Weldlng Defects in Replacement SGs," April 2010, No anornalies were noted, Visual examination and accountabllity of tube plugs (as-found and as-left condltlon). This is performed as part of the routlne steam generator inspectlon process each tirne the prlmary slde is opened, During 1R21, the examinatlons verifled that the correct number of tube plugs were present and In the proper tube locations. No anomalies w6re reported. Secondary Slde: A vlsual inspection of the secondary side tubesheot face, annulus, and tube lane was perforrned durlng 1R21 ln all three steam generators. Forelgn object search and retrieval (FOSAR) was also performed. Of the slxty-eight obJects identifled during the FOSAR inspectlon, all but eight objects werCI retrleved, Foreign rnaterlaf that was not removed frorn the secondary side of the steam generators wa$ evaluated and documented in Westinghouse Letter FENOC 12-74, "Transmittal of Evaluatlon of Secondary Side Loose Parts - 1R21 Refueling Outage." Based on this evafuatlon, the foreign materlal that remalned in the secondary side of the steam generator was determined to be acceptable for contlnued operatlon (1,e., tube integrity would be maintained for at least three more operating cycles). Table 1 contains a list of the material not retrievod from the secondary side of the stoam generators and provides (a) a descriptlon of the foreign material left in each steam generator, (b) the location of the foreign
- materlal, and (c) the final evaluation of the forelgn material.
For those tube locations where potential loose part indications were reported from the 1R21 eddy current examinatlons (e.9., bobbln coll or Plus Polnt probes) and no visual inspection was performed at lhose particular tube locations, the Plus Polnt probe was used to vorlfy that no degradation or tube wall wear was present. Thoso tubes remained In service, a a a c
b) Actlve(1) degradation mechanlsrns found; The followlng existing degradatlon mechanlsms were observed during 1R21: . Wear at tube support plate locations . Wear at antl-vlbratlon bar locations c) Nondestructlve examlnatlon techniques utif lzed for each degradation mechanism: For the degradatfon mechanlsrns observed during 1R21, bobbln coll probe$ were used as the prlmary method of detection except at or below TTS, low row U-bends where bobbln probes are not quallfied. In these areasr Plus Point probes were employed, Plus Polnt probes were also used to re-examine any amblguous bobbin coll slgnals that were reported, The 1R21 examination technlques were qualified, for detectlon and slzing (as applfcable) of the existing and potential degradation mechanisrns llsted in the 1R21 degradation assessment, In accordance with Appendices H and lof the EPRl, "Steam Generator Management Program: Pressurized Water Reactor $team Generator Examinatlon Guidelines, Revision 7," (2) - The EPRI Examlnatlon Technlque Speclficatlon Sheet (ETSS) is llsted for reference only. Stte-speclflc ETSSs are developed prlor to each steam generator lnspection for each existlng and potential degradation mechanism identlfled in the 1R21 degradation assessmont, The site-specific ETSSs are developed in accordance with Appendlces H and I of lhe EPRI, "Steam Generator Managernent Program: Pressurized Water Reactor Steam Generator Examination Guidellnes, Revision 7." The examination technlques utilized during 1R21 are considered "$ite Validated" as dofined ln the EPRI, "Steam Gonerator Management Prograrn: Pressurized Water Reactor Steam Generator Examination Guldellnes, Revision 7," fot oach existing and potential degradatlon mechanfsm llsted In the 1R21 degradation assessment, (1) - Per the EPRI, "Steam Gonerator Managoment Program: Steam Goneralor Integrlty Assossment Guldellnes," Rovlslon 3, lhe word "exl$llng" ls now used In lieu of the word "actlve" whon descrlblng dogradatlon lhat has boen prevlously and/or currently obeervod In the stoam generators, 1R21 Examinatlon Technlques Used for Degradation Detection/Slzlng Degradation Mode Tube Location Probe EPRI ETSS, Freespan Differential Slsnals Freespan Bobbin 128413 Manufacturing Burnish Marks All Locatlons Bobbin 9601 0.1 Absolute Drift Sisnals Freespan Bobbin 96010.1 Tube Wear Anti-Vibration Bar Intersectlons Bobbln 96004,1 Tubo Wear Tube Support Plates lntersections Bobbin 96001,1 Tube Wear Tubesheet Periphery, Tube Lane Bobbln t28413 3 Coil Plus Point 21998.1 Volurnetrlc Signals Entire Tube Length Bobbln t28413 3 Coll Plus Point 21 998.1 PWSCC Tubesheet Region 3 Coil Plus Point 20510,1 20511 ,1 Axial ODSCC Dents at AVBs (> 1 volt), Dents at TSPs (> 2 volts), Dinqs (> 5 volts) 3 Coil Plus Point 22401,1
d) Location, orientation (if linear), and measured slzes (lf avallable) of service Induced indlcationsl The 1R21 stoam generator examlnatlon results are included in the Attachmont and provlde the following information (a) locatlon, (b) orientatlon and (c) measured slzes of servlce-lnduced indlcatlons, Bobbln probe Indlcations reporled as "l-codes" were re-lnspected with the Plus Polnt probe, lf the plus polnt probe Indlcated that no degradation or ffaws were present, the tube would remain In.service, lf the Plus Polnt pronjinOicated that degradation or flaws were present, the tube would be rernoved from servlce vla plugglng, New AVB indica6ons reported from the bobbin probe listed as PCT were re-inspected with.the plus point probe, lf the plus Point probe indlcaied no crack-llke flaws were present within the wear scar, a wear call (WAR) would be asslgned to the Plus Point report, Number of tubes plugged durlng the Inspectlon outage for each active degradation rnechanism: No tubes were plugged during 1R21. Totat number and percentage of tubes plugged to date: The total nurnber of tubes plugged as of ihe end of 1R21 ls ono (0.01 percent)' The results of condition monitorlng, includlng the results of tube pulls and In'sltu testing: During the 1R21 stoam generator lube inspections, no lndications were observed that exceeded the struit[rat tntegiity itmit*Tor etther axlal or ilrcumferential degradation (burst Integrity greater than three times normhl operating primary to secondary pressuredifferential). No tubes contained lndications that coutci poteniially chailenge the tube'lntegrity recommsndations of NEI 97'06, Revision 3, "Sleam Generator Program Guidellnes." Based on the Indlcations obserued at 1R21 , lhe steam generator tublng is expected to meet all operational structural and leakage Integrlty requirem"nts at end-of-cycle 24 which is the next outage wh"n primary side inspectlons ire scn6OriteO. None of the Indlcatlons rep_orted during 1R21 represented'a leakagd potential at postulated maln steam line break conditions. The effective plugglng percentage for all plugglng In each SG: The folowing table lists the plugging percentages for each steam generator as of the end of 1R21' $G Total Tubes Plugged Percent Plugged RC.E.1A 0 0,00 RC-E.18 0 0.00 RC.E-1C 1 0,03 1) 2) e) s) h)
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D.efiqitigns of Ahbrevlaljorls,
- GoCeq, and Repgrtinq Ter,minolqsy 3 Letter Code Definitlons Addltlonal Deflnltions Term Bobbln Goil Probe DSI Distorted Tube Support Plate Slqnal with Possible Indlcation PCT Percent Throush Wall Term Plus Polnt Probe SVI Sinqle Volumetric Indication WAR Wear Term Definitlon AVB Anti-Vlbration Bar EPRI Electrlc Power Research Instltute FOSAR Foreign Object Search and Retrieval ODSCC Oulside Diameter Stress Corrosion Crackins PLP Posslble Loose Part PWR Pressurized Water Reactor PWSCC Prlmary Water Stress Corrosion Crackinq SG Steam Generator TSC Tubesheet
" Cold Leq (Secondarv Face) TSH Tubesheet - Hot Loq (Secondary Face) TSP Tubo Sunporl Plate TTS Top of Tubesheet
1R21 Steam Generator Exarnination Results The Attachment provides the steam generator oxamination results for tubes with service-induced indications, Refer to the following tables for a description of the terms used in the Attachment. Description of Column Headlngs and Data Abbreviatlons Used in Stearn Generator Examlnation Results Report Header Definitions Examinatlon Extent Definltlons (FROM - TO) Defin itlon ROW/COL Row & Column of tube location Tvpe of indicatlon Locatlon of noarest support structure Indlcation distance from nearest support structure Field measured percont throuqh wall of indlcatlon LENGTH Field measured lenqth of indicatlon Field measured phase a le of indlcation Field measured voltaqe amplitude of indlcation Fiefd rneasured anqular rolation of indlcatlon channel of indicatfon Startinq point of examination End point of examlnation Term Deflnition TEH Tube End - Hot Leq TSH Hot Leq Tubesheet (Secondarv Face) TEC Tube End - Cold Leq TSC Cold Leo Tubesheet (Secondary Face) 01H First Tube Support Plate on Hot Les Slde 01c First Tube Support Plate on Cold Leq Side AVBl First Antl-Vibratlon Bar (Numbered hot leq to cold leq)
$G A A A ROW COL IND LOC INCH 6 eB DSt 01C 0.54 6 98 SVt 01C 0.54 6 98 PCT 01C 0.54 ATTACHMENT Beaver Valley Power
- Station, Unit No 1 1 R21 Examlnation Results (TUBES WrTH SERVTCE TNDUCED TNDICATTONS)
RC.E.1A %TW LENGTH ANGLE 17 VOLTS PHASE CHAN FROM TO 0.16 41 P1 TEC TEH 0,09 267 P4 01C 01C 0.09 84 P4 01C 01C SG B B B ROW COL IND 38 78 DSI 3B 7B SVI 38 78 PCT RC-E.18 %TW LENGTH ANGLE 1 9 LOC INCH 02H 0,46 02H 0,48 02H 0,47 VOLTS PHA$E CHAN FROM TO AJ4 97 P1 TEC TEH 0.1 1 135 P4 02H 02H 0.11 135 P4 02H 02H SG c C c c RC-E-1Q %TW LENGTH ANGLE PHASE CHAN 61 P1 127 P4 274 P4 134 P4 90 P4 ROW COL IND 1 20 DSt 1 20 SVI 1 20 SVI 1 20 PcT 1 20 PCT LOC INCH 03c 0.34 03c 0,38 03c 0.42 03c 0.46 03c 0.48 1 5 1 6 VOLTS 0.13 0,08 0.08 0.08 0,09 FROM TO O7C TEC 03c 03c 03c 03c 03c 03c 03c 03c}}