ML11263A149: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
Line 2: Line 2:
| number = ML11263A149
| number = ML11263A149
| issue date = 09/13/2011
| issue date = 09/13/2011
| title = Wolf Creek, Containment Inservice Inspection Program Second Interval, First Period, Refueling Outage 18 Owner'S Activity Report
| title = Containment Inservice Inspection Program Second Interval, First Period, Refueling Outage 18 Owner'S Activity Report
| author name = Sen G
| author name = Sen G
| author affiliation = Wolf Creek Nuclear Operating Corp
| author affiliation = Wolf Creek Nuclear Operating Corp

Revision as of 17:08, 12 April 2019

Containment Inservice Inspection Program Second Interval, First Period, Refueling Outage 18 Owner'S Activity Report
ML11263A149
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 09/13/2011
From: Sen G
Wolf Creek
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
RA 11-0180
Download: ML11263A149 (6)


Text

WeLF CREEK r NUCLEAR OPERATING CORPORATION Gautam Sen Manager Regulatory Affairs September 13, 2011 RA 11-0180 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

Subject:

Docket No. 50-482: Containment Inservice Inspection Program Second Interval, First Period, Refueling Outage 18 Owner's Activity Report Gentlemen:

Enclosed is the Wolf Creek Nuclear Operating Corporation (WCNOC) Owner's Activity Report (Form OAR-i, Report Number WCRE-22, 12-P1-RF18) for containment inservice inspections performed prior to, and during, Wolf Creek Generating Station's (WCGS)eighteenth refueling outage (RF18) that concluded on June 24, 2011. RF18 was the second outage of the first period of the second interval of the WCNOC Containment Inservice Inspection Program. The enclosed report is submitted pursuant to the requirements of paragraph IWA-6240 of the 2001 Edition through 2003 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) 364-4175 or Ms. Diane Hooper at (620) 364-4041.Sincerely, 6ic,,~ V, .-Va4-Gautam Sen GS/rlt Enclosure cc: E. E. Collins (NRC), w/e J. R. Hall (NRC), w/e G. B. Miller (NRC), w/e Senior Resident Inspector (NRC), w/e P.O. Box 411 / Burlington, KS 66839 / Phone: (620) 364-8831 An Equal Opportunity Employer M/F/HCNET Enclosure to RA 11-0180 Wolf Creek Nuclear Operating Corporation (WCNOC)Owner's Activity Report (Form OAR-I, Report Number WCRE-22, 12-PI -RFI 8)(4 pages)

FORM OAR-I OWNER'S ACTIVITY REPORT Report Number WCRE-22, 12-P1-RF18 Plant Wolf Creek Generatina Station. 1550 Oxen Lane Northeast.

Burlington, Kansas 66839 Unit No. 1 Coa (if applicable)

Current inspection interval 2rd Current inspection period 1st mmercial service date 9-3-1985 Refueling outage no. RF-18 (1st. 2nd. 3rd. 4th. other)(l t. 2nd. 3rd)Edition and Addenda of Section XI applicable to the inspection plans 2001 Edition through 2003 Addenda Date and revision of inspection plans WCRE-22 Rev. 3. dated 11-11-2010 Attachment 1 Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans same Code Cases used: N-532-4. N-686-1 (if applicable)

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 XI; and (c) the repair/replacement activities and evaluations supporting the completion of RF-18 (refueling outage number)conform to the requirements of Section XI.Signed TP_ .Cv-iiAlee)?

nlatm V /20/Owner or ttWlers uesignee, Tile 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 Insoection and Insurance Co. of Connecticut of Hartford.

CT have inspected the items described in this Owners 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, concerning 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.

Commissions NB 13573 A.N.l KS 657 Inspector's Sigrir ) National Board, State, Province.

and Endorsements Date _/' 2 f01 OAR-I 12-PI-RF-18 Page I of 4 TABLE I ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination Item Description Evaluation Description Category and Item Number E-C, E4.11 Containment Incore Tunnel Pits that measured up to 3/32" Sump Liner deep were identified on the sump liner surface. These pit depths were acceptable per an engineering evaluation.

Reference work order 11-339212-003 and CCP 12959.E-A, E 1. 11 Containment Equipment Hatch The bolt and bolt chair members E-C, E4.11 Surface and Bolting at Location 6 of the containment equipment hatch were found bent. See Note I for more information.

The condition was evaluated as acceptable.

Reference work order 11-339112-004 and CCP 1373 1.L-B, L2.10 Containment Vertical After lift off testing 7 of the Tendon V7 tendon wires were found damaged. See Note 2 for more information.

The condition was evaluated as acceptable.

Reference work order 10-331454-001 and CCP 13427.L-B, L2.10 Containment Vertical After lift off testing 2 of the Tendon V65 tendon wires were found damaged. See Note 2 for more information.

The condition was evaluated as acceptable.

Reference work order 10-331498-001 and CCP 13427.Note 1: This condition was not service induced. The bolt and bolt chair members were bent during the process of removing the hatch cover to support outage activities.

This damage was caused by personnel error. The subject components were determined to be acceptable for continued service by an engineering evaluation.

Note 2: This condition was not service induced. The tendon wires were damaged during the testing process. This damage was caused by an error of the vendor performing the testing. The subject components were determined to be acceptable for continued service by an engineering evaluation.

OAR-]12-P I-RF-18 Page 2 of 4 TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Code Item Description of Work Date Repair/Replacement Class Description Completed Plan Number None OAR-I 12-PI-RF-18 Page 3 of 4 ATTACHMENT 1 As specified in the inspection plan, WCRE-22, this attachment is added to meet the requirements of 10 CFR 50.55a(b)(2)(viii)(E) and 10 CFR 50.55a(b)(2)(ix)(A) 10 CFR 50.55a(b)(2)(viii)(E)

As noted in WCRE-22, there are no inaccessible areas identified that meet the criteria of this section.10 CFR 50.55a(b)(2)(ix)(A)

As noted in WCRE-22, there are no inaccessible areas identified that meet the criteria of this section.OAR-I 12-P I-RF-18 Page 4 of 4