ML100490752

Submittal of Inservice Inspection Program Third Interval, Second Period, Refueling Outage 17 Owner'S Activity Report

ML100490752
Person / Time
Site:	Wolf Creek
Issue date:	02/09/2010
From:	Flannigan R Wolf Creek
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RA 10-0013
Download: ML100490752 (6)

Text

WSLF CREEK '1NUCLEAR OPERATING CORPORATION Richard D. Flannigan February 9, 2010 Manager Regulatory Affairs RA 10-0013 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

Subject:

Docket No. 50-482: Inservice Inspection Program Third Interval, Second Period, Refueling Outage 17 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-P2-RF17) for inservice inspections performed prior to and during Wolf Creek Generating Station's (WCGS) seventeenth refueling outage (RF17) that concluded on November 21, 2009. RF17 was the first outage of the second 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 and ASME Code Case N-532-4.

There are no commitments contained within this letter.

If you have any questions concerning this matter, please contact me at (620) 364-4117 or Ms. Diane Hooper at (620) 364-4041.

Sincerely, Richard D. Flannigan RDF/rlt Enclosure cc: E. E. Collins (NRC), w/e G. B. Miller (NRC), w/e B. K. Singal (NRC), w/e Senior Resident Inspector (NRC), w/e A-04-7 P.O. Box 411 / Burlington, KS 66839 / Phone: (620) 364-8831 An Equal Opportunity Employer M/F/HCNET

FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number WCRE-16, 13-P2-RF17 Plant Wolf Creek Generatina Station, 1550 Oxen Lane Northeast, Burlington, Kansas 66839 Unit No. 1 Commercial service date 9-3-1985 Refueling outage no. RF-17 (Vappcaie)

Current Inspection interval 3rd (i3t.2nd. 3(d.4th, olW Current inspection period 2st (1t. 2nd. 3W)

Edition and Addenda of Section Xl applicable to the inspection plans 1998 Edition through 2000 Addenda Date and revision of inspection plans WCRE-16 Rev. 5. dated 10-5-2009 Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans same Code Cases used: See Attachment I (Ifapp..atie)

CERTIFICATE OF CONFORMANCE I certify that (a) the statements made in this report are correct (b) the examinations and tests meet the Inspection Plan as required by the ASME Code, Section Xl; and (c) the repair/replacement activities and evaluations supporting the completion of RF-17 (reftsaft outdae n-ubO conform to the requirements of Section XI.

Signed . d rr"T,:;O-" rXg:

wesDeatgnee Tfe Obro

', Date 211,41 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 Co. of Connecticut of Hartford.CT have inspected the items described in this Owner's Activity Report 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, conceming the repair/

replacement activities and evaluation 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.

A** f i Commissions NB 13573 ANI KS 857 Natioal Boaald, State, PMOvlM, and Endorsements InsnpetoV Data I AAL 20mn OAR-I 13-P2-RF-)7 Page I of 5

TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination Item Description Evaluation Description Category and Item Number D-B, D2. 10 Essential Service Water (ESW) A through wall leak was piping line EF138HBC-30 identified in an area with reduced thickness in this 30" pipe. Two other areas were also identified as having thickness below minimum wall. The character of the flaws in these areas was indicative of internal pitting. An evaluation was performed in accordance with Code Case N-513-2. The evaluation determined that structural integrity was intact and that the piping could remain in operation in the current condition until the next refueling outage. Reference SWOs 09-318203-002 and 09-318203-009.

Repairs were performed on this piping per R/R plan 2009-051 listed in Table 2.

D-B, D2.10 ESW piping line EFI50HBC-18 A through wall leak was identified in an area with reduced thickness in this 18" pipe. Another area was also identified as having thickness below minimum wall. Both flaws were characterized as being pit-like. An evaluation was performed in accordance with Code Case N-513-2. The evaluation determined that structural integrity was intact and that the piping could remain in operation in the current condition until the next refueling outage. Reference SWO 09-318982-001. Repairs were performed on this piping per R/R plan 2009-054 listed in Table 2.

D-B, D2.10 ESW piping line EF049HBC-8 A through wall leak was identified in an area with reduced thickness in this 8" pipe.

Another area was also identified OAR-i 13-P2-RF-I7 Page 2 of 5

as having thickness below minimum wall. Both flaws were indicative of internal pitting. An evaluation was performed in accordance with Code Case N-513-2. The evaluation determined that structural integrity was intact and that the piping could remain in operation in the current condition until the next refuieling outage. Reference SWO 09-319429-001. Repairs were performed on this piping per R/R plans 2009-061 and 2009-062 listed in Table 2.

OAR-I 13-P2-RF-17 Page3 of 5

TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Code Item Description of Work Date Repair/Replacement Plan Class Description Completed Number 3 ESW piping line Installed three pressure boundary modification 10/01/2009 2009-051 EFI38HBC-30" (encapsulations), one over a leaking area and the other two over areas with below minimum wall thickness.

2 Crosby Relief Reworked BG8119, which failed set pressure test 12/14/2009 2009-053 Valve in CVCS due to excessive seat leakage, by replacing nozzle System and disc insert.

3 ESW piping line Cut out and replaced 18" pipe section containing 12/28/2009 2009-054 EFI50HBC-18" the through wall leak and area of below minimum wall thickness with like material.

3 ESW piping line Repaired leak on ESW line by installing a pressure 10/01/2009 2009-061 EF049HBC-8" boundary modification (encapsulation) over the leaking area.

3 ESW piping line Repaired ESW line by installing a pressure 12/21/2009 2009-062 EF049HBC-8" boundary modification (encapsulation) over the area that was below minimum pipe wall thickness.

1 Reactor Vessel Installed a canopy seal clamp assembly on active 12/29/2009 2009-084 Penetration # 17 Penetration # 17 to stop leakage through seal Canopy Seal Weld welded joint.

2 Pressurizer Replaced a section of 2" stainless steel piping due 12/14/2009 2009-088 Auxiliary Spray to defects indicative of OD initiated SCC.

Line BG-026-BCB-2" 2 Pressurizer Replaced a section of 2" stainless steel piping due 12/14/2009 2009-094 Auxiliary Spray to defects indicative of OD initiated SCC.

Line BG-026-BCB-2" 3 Containment Due to through wall leakage, removed two cooling 12/15/2009 2009-107 Cooler SGNO IC coils from service due to leakage by cutting off the Cooling Coil nozzles and installed blind flanges on the manifold connections.

OAR-i 13-P2-RF-17 Page 4 of 5

ATTACHMENT I Code Cases used:

N-460 N-513-2 N-532-4 N-533-1 N-552 N-566-2 N-616 N-623 N-624 N-639 N-652 N-658 N-685 N-695 N-700 OAR-i 13-P2-RF-17 Page J of 5