RA-07-0012, Inservice Inspection Program Third Interval, First Period, Refueling Outage 15 Owner'S Activity Report

Inservice Inspection Program Third Interval, First Period, Refueling Outage 15 Owner'S Activity Report

ML070430458
Person / Time
Site:	Wolf Creek
Issue date:	01/31/2007
From:	Moles K Wolf Creek
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RA-07-0012
Download: ML070430458 (9)

Text

WQLF. CREEK UCLEARoPERATING CORPORATION January 31, 2007 Kevin J. Moles Manager Regulatory Affairs RA 07-0012 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

Subject:

Docket no. 50-482: Inservice Inspection Program Third Interval, First Period, Refueling Outage 15 Owner's Activity Report Gentlemen:

Enclosed is Wolf Creek Nuclear Operating Corporation's (WCNOC's) Owner's Activity Report (Form OAR-i, Report Number WCRE-16, 13-P1-RF-15) for inservice inspections performed prior to and during Wolf Creek Generating Station's (WCGS) fifteenth refueling outage (RF15) that concluded on November 10, 2006. RF15 was the first outage of the first period of the third interval of the WCNOC Inservice Inspection Program. The enclosed report is submitted pursuant to the requirements of paragraph IWA-6240 of the 1998 Edition through 2000 Addenda of Section Xl of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code.

There are no commitments contained within this letter.

If you have any questions concerning this matter, please contact me at (620) 364-4126 or Ms. Diane Hooper at (620) 364-4041.

Very truly yours, KJ M/rlt P.O. Box 411 / Burlington, KS 66839 / Phone: (620) 364-8831 1oL77 An Equal Opportunity Employer M/F/HCNVET

.0 RA 07-0012 Page 2 of 2 Enclosure cc: J. N. Donohew (NRC), w/e V. G. Gaddy (NRC) wMe B. S. Mallett (NRC), wMe Senior Resident Inspector (NRC), wMe

F'ORM OAR-I OWNER'S ACTIVITY REPORT Report Number -WCRE-16, 13-PI-RF-15 Owner Wolf Creek Nuclear Operating Corporation, 1550 Oxen Lane Northeast, Burlington, Kansas 66839 (Name and Address of Owner)

Plant Wolf Creek Generating Station, 1550 Oxen Lane Northeast, Burlington, Kansas 66839 (Name and Address of Plant)

Unit No. I Commercial service date 9-3-85 Refueling outage no. IS (If applicable)

Current inspection interval 3rd 2nd. 3rd. 4th. other)

(lst.

Current inspection period Ist (1 st. 2nd. 3rd)

Edition and Addenda of Section X' applicable to the inspection plan 1998 edition through 2000 addenda Date and revision of inspection plan WCRE- 16 Rev. I, dated 9-29-2006 Edition and Addenda of Section XI applicable to repairs and replacements, if different than the inspection plan same CERTIFICATE OF CONFORMANCE I certify that the statements made in this Owner's Activity Report are correct, and that the examinations, tests, repairs, replacements, evaluations, and corrective measures represented by this report conform to the requirements of Section XI.

Certificate of Authorization No. N/A Expiration Date N/A (If anolicable)

Signed Dennis E. TougaWnro w i Engineer Date January 25, 2007 70&+ner or Ownr'sge'signee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Kansas and employed by The Hartford Steam Boiler Inspection and Insurance Company of Connecticut of Hartford, Connecticut have inspected the items described in this Owner's Activity Report, during the period September 3, 2005 to November 10, 2006 , and state that

• to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requirements of Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations, tests, repairs, replacements, evaluations and corrective measures described in this report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Commissions KS#594 A, N, I

~e~tor's Signature National Board. State. Province, and Endorsements 4... r Signature Date This form (EOO 127) may be obtained from the Order Dept., ASME, 22 Law Drive, Box 2300, Fairfield, NJ 07007-2300 OAR-I 13-PI-RF-15 Page 1 of 7

TABLE 1 ABSTRACT OF EXAMINATIONS AND TESTS Completion ofRF-15 (1-3, P-i)

I

<'Total Total:, 'TotaIl1 ,:Total Exarin latioii%

Examhinations Exam inations 'Ex ,aiiinations Examinationi Required For* Credited for This Credited (%): for - Dat-eI' rhe Category,, ~Per-io~d*, 4

>ThePer~iod~*,ý,

4~ . .-..

Remarks B-A*

24 0 0 0 13-13 B-B 1 20 5 20 B-D 36 0 0 0 B-F Note 1 Note I Note I Note I Note I B-G-I 219 0 0 0 B-G-2 15 0 0 0 Note 2 B-J Note I 0 Note Note I Note I Note 1 B-K 0 0 0 B-L-2 0 0" 0 Note 3 B-M-2 7 14 14 Note 4 B-N-I 3 0 0 0 B-N-2 6 0 0 0 B-N-3 1 0 0 0 B-O 4 0 0 0 B-P 6 1 17 17 Note 5 B-Q Note 6 Note 6 Note 6 Note 6 Note 6 C-A 11 0 0 0 C-B 5 0 0 0 C-C 21 2 9 9 C-D 1 0 0 0 C-F-I Note I Note 1 Note I Note 1 Note 1 C-F-2 Note I Note 1 Note 1 Note 1 Note 1 C-G 5 0 0" 0 C-H 114 12 11 Note 7 D-A 44 1 2 2 D-B 96 5 5 5 Note 8 F-A. 279 22 8 8 R-A 132 10 8 8 Note 9 L J J This column is interpretedto representthe cumulative number of exams performed to.date in this period

• • This column is interpretedto representthe cumulativepercentage of scheduled exams for the interval which have completed in this period to date.

OAR-I 13-PI-RF-15 Page 2 of 7

Note I: Categories B-F, B-J, C-F-I, and C-F-2 welds are now examined underthe RI-ISI program. These welds are listed under Category R-A.

Note 2: For pumps and valves, examinations are limited to components selected for examination under Examination Categories B-L-2 and B-M-2.

Note 3: Examination is required only when a pump is disassembled for maintenance, repair or examination.

Note 4: Examination is required only when a valve is disassembled for maintenance, repair or examination.

Note 5: All Category B-P components receive a visual examination (VT-2) each refueling outage.

Note 6: Steam Generator tubing results are reported in accordance with Plant Technical Specifications. See Attachment I for a summary of the Steam Generator tubing results'.

Note 7: All Category C-H components receive a visual examination (VT-2) each period.

Note 8: All Category D-B components receive a visual examination (VT-2) each period.

Note 9: The RI-ISI program is implemented by 10 CFR 50.55(a) request 13R-01. As of this date, NRC approval of this request has not been received. These examinations are not to be considered final until NRC approval of this request is received.

OAR-I 13-PI-RF-15 Page 3 of 7

TABLE 2 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE

- Flaw Flaw or Relevant Condition Found Examination Item Item Description Characterization During ScheduledeSection XI CategoryExamination or Test (Yes or No)

There were no components containing flaws or relevant conditions that required an evaluation to determine acceptability for continued service.,

OAR-I 13-PI-RF-15 Page 4 of 7

TABLE 3 ABSTRACT OF REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES REQUIRED FOR CONTINUED SERVICE Flaw or Relevant Condition Found Repair, During Scheduled Repair/

Replacement, Section XI . Replacement Code or Corrective Item Description Examination or Date Plan Class Measure Description of Work Test (Yes/No) Complete Number 3 Repair/ EDG "A" Crankcase Eductor Duct Fabricate and install a missing support No 01/26/2006 2004-003 Replacement Angle Support Bracket, (Dwg/Part# bracket (Dwg/Part# 11874049) for the 118704049), KKJO1A Crankcase Vacuum Ejector for KKJO1A.

3 Repair/ EDG "B" Crankcase Eductor Duct Fabricate and install a missing support No 08/29/2006 2004-004 Replacement Angle Support Bracket, (Dwg/Part# bracket (Dwg/Part# 11874049) for the 118704049), KKJOIB Crankcase Vacuum Ejector for KKJO IB.

3 Repair/ Carrier Type 28NW Room Cooler Remove H-Bends to allow installing jumper No 01/03/2007 2006-008 Replacement Coil, SGL09A from Row 48 Tube 2 to Row 44 Tube 4 to remove tube at Row 47 Tube 3 from service.

Replace tube nut at Row 37 Tube 2.

3 Repair/ Carrier Type 28NW Room Cooler Remove H-Bends to allow installing a No 05/04/2006. 2006-023 Replacement Coil, SGL12A jumper from Row 64 Tube 2 to Row 62 Tube 3 to remove Row 64 Tube 3 from service.

Cut tubes at header for Row 55 Tube I and Row 48 Tube 4 and install caps to remove the entire circuit containing Row 55 Tube 1 from service.

3 Repair/ Daniel International, Bergen- During implementation of DCP# 10355 for No 12/15/2006 2006-031 Replacement Paterson, Pacific Scientific Snubber Snubber Reduction, one snubber removed Pipe Support, EG07-R014/132 from EG07R014132 failed to pass the hand stroke test when removed and required an evaluation which was documented on CCP 12241.

Repair/ Pressurizer Vertical Tank, TBB03 Performed full structural repair weld overlays Yes See Note A 2006-043 Replacement on TBB03 Nozzle To Safe End Dissimilar Metal Welds on Surge, Relief, And "C" Safety Nozzles in accordance with CCP 11977.

3 Repair/ Containment Air Cooler, SGNO IB Remove one leaking cooling coil, S/N# No 12/08/2006 2006-064 Replacement 906897-A5, from service by cutting off nozzles and blind flanging the supply and return header connections per DCP 07111.

OAR-I I3-P1-RF-15 Page 5 of 7

a Note A - Although all work and reviews have been completed, certification of this repair/replacement activity is not complete. Certification is not complete because WCNOC has not yet received the NRC Safety Evaluation for Relief Request 13R-05. NRC verbal approval of the Relief Request was received by WCNOC on October 6, 2006.

OAR-I 13-PI-RF-15 Page 6 of 7

ATTACHMENT 1

SUMMARY

OF RF15 STEAM GENERATOR TUBING (CATEGORY B-Q) RESULTS Eddy Current Inspections were performed on S/Gs A and D. The following inspection programs were completed:

1) A Full Length Bobbin probe inspection of 100% of the tubes in both S/G A and S/G D was performed except for the U-bend portion of the rows 1-4.

2) A 55% Rotating Pancake Coil (RPC) Hot Leg Top of Tubesheet inspection (+ and - 3") in S/G's A and D was performed. This inspection included the peripheral tubes to inspect for possible loose parts.

3) A 100% RPC Cold Leg Top of Tubesheet Peripheral (2 rows deep) inspection (+ and - 3") in S/G's A and D was performed to inspect for possible loose parts.

4) A 50% RPC of tubesheet expansion zone bulges and over expansion in S/G's A & D Tubesheet (+3" and -17") was performed.

This sample was concentrated in the upper tubsheet region (+3" to -10").

5) A Special Interest RPC program included all bobbin "I" codes (signals that were new or changed after history review). The inspection of 5.00 volts or greater dents on the hot leg side including the u-bend in the current 90 EFPM inspection cycle was completed. A 5% sample of the total population of bobbin indications that have not changed since the prior inspection ("H" and "S"codes) was inspected by RPC. The sample was performed on the hot leg only.

As a result of the inspection, four tubes in S/G A and seventeen tubes in S/G D were plugged due to wear at Anti-Vibration Bar locations. Two tubes in S/G A with geometry signals at the tubesheet transition were preventively plugged.

No cracklike indications were found during the inspection.

The inspection results are reported to the Nuclear Regulatory Commission in accordance with Technical Specification 5.6.10.

OAR-I 13-P1-RF-15 Page 7 of 7