GO2-15-136, In-Service Inspection Summary Report for the Twenty-Second Refueling Outage (R22)

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In-Service Inspection Summary Report for the Twenty-Second Refueling Outage (R22)
ML15266A453
Person / Time
Site: Columbia Energy Northwest icon.png
Issue date: 09/22/2015
From: Javorik A
Energy Northwest
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
GO2-15-136
Download: ML15266A453 (6)


Text

Alex L. Javorik Columbia Generating Station P.O. Box 968, PE04 Richland, WA 99352-0968 Ph. 509-377-8555 l F. 509-377-2354 aljavorik@energy-northwest.com September 22, 2015 GO2-15-136 10 CFR 50.55a U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001

Subject:

COLUMBIA GENERATING STATION, DOCKET NO. 50-397 IN-SERVICE INSPECTION

SUMMARY

REPORT FOR THE TWENTY-SECOND REFUELING OUTAGE (R22)

Dear Sir or Madam:

Article IWA-6000 of Section XI of the 2001 Edition with the 2003 Addenda of the American Society of Mechanical Engineers (ASME) Code requires an In-Service Inspection summary report be submitted to regulatory and enforcement authorities having jurisdiction at the plant site.

This report is to be prepared at the completion of a refueling outage and submitted within 90 calendar days of the completion of the refueling outage. In this case, the report is for the twenty-second refueling outage (R22) for Columbia Generating Station (Columbia). The outage was completed on June 28, 2015.

Code Case N-532 allows Energy Northwest to prepare an Owners Activity Report Form OAR-1 in place of the Code required NIS-1 and NIS-2 forms for the summary report.

The latest revision of this code case, N-532-5, is listed in Regulatory Guide 1.147, Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1, Revision 17, Table 1, Acceptable Section XI Code Cases. Therefore, prior NRC approval to implement this code case is not required.

The enclosure to this letter, Inservice Inspection Summary Report for Third Inspection Interval Third Inspection Period Refueling Outage R22, is herewith being submitted, which includes the completed Form OAR-1 for Columbia. Included with the form are tables listing the Items with Flaws or Relevant Conditions that Required Evaluation for Continued Service and Abstract of Repair/Replacement Activities Required for Continued Service in accordance with Code Case N-532-5. The results that are contained in this completed form are for activities performed during cycle 22 up to and including refueling outage R22.

IN-SERVICE INSPECTION

SUMMARY

REPORT FOR THE TWENTY-SECOND REFUELING OUTAGE (R22)

Page 2 of 2 There are no commitments being made to the NRC by this letter. By means of this submittal, the reporting requirements of IWA-6000 are fulfilled for the R22 Outage.

Should you have any questions or require additional information pertaining to this report, please contact JR Trautvetter at (509) 377-4337.

Executed on 'j'eptJ_><</:Jev C2_) Z &>/$

I Respectfully,

-1~/~

Vice President, Engineering

Enclosure:

lnservice Inspection Summary Report for Third Inspection Interval Third Inspection Period Refueling Outage R22 cc: NRC Region IV Administrator NRC NRR Project Manager NRC Sr. Resident Inspector - 988C CD Sonoda - BPA/1399 WA Horin -Winston & Strawn L Williamson - WA Department of Labor and Industries

IsI

SUMMARY

REPORT R22 INSERVICE INSPECTION

SUMMARY

REPORT FOR THIRD INSPECTION INTERVAL THIRD INSPECTION PERIOD REFUELING OUTAGE R22 OWNER: Energy Northwest P0 Box 968 Richiand, Washington 99352 PLANT: Columbia Generating Station 76 North Power Plant Loop Richland, Washington 99354 COMMERCIAL SERVICE DATE: December 13, 1984 CAPACITY: 3486 Megawatts Thermal REACTOR PRESSURE VESSEL: Manufacturer: CBIN Serial Number: T-45 National Board No. : CBIN-8 Prepared By: SK RichY ISI-Enineer Date JE Dorwin  ?

ASME Progr Lead Engineer Date Reviewed By: N Labella f/il1 NDE Lead Date Approved By: .

151 Engineer s Supervisor ate Concurrence: FA Aflqaier Authorized Nuclear Inservice Vspector Date Page 1 of 4

ISi

SUMMARY

REPORT R22

SUMMARY

Columbia Generating Station has completed American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME)Section XI examinations and repair/replacement activities for the twenty-second (22"d) refueling outage.

This report summarizes the ASME Section XI in-service inspection (ISi) activities and repair/replacement activities performed at Columbia Generating Station during its 22"d operating cycle up to and including Refueling Outage 22 (R22). The cycle began June 25, 2013 and ended June 28, 2015. General Electric (GE) and Energy Northwest personnel performed the ISi examinations. The twenty-second refueling outage is the fifth refueling outage of the third ten year inspection interval. This report is submitted in accordance with ASME Code Case N-532-5 and contains:

  • Form OAR-1, Owner's Activity Report,
  • Table 1, Items With Flaws or Relevant Conditions That Required Evaluation For Continued Service, and
  • Table 2, Abstract of Repair/Replacement Activities Required for Continued Service.

Documentation supporting this summary report is located in the Columbia Generatiqg Station files (DIC 1100 and 1830).

Page 2 of 4

1 FORM OAR-i OWNERS ACTIVITY REPORT Report Number ISI-SR-R22 Plant Columbia Generating Station, 76 North Power Plant Loop, Richiand, WA 99354 Unit No. NA CommercaI service date 1 2/1 3/1 984 Refueling outage no. R22 (if applicable) 3rd Currentinspection interval (12/13/2005 - 12/12/2015)

(1St 2d 3a 4th other) 3rd Current inspection period (1 2/1 3/201 2 - 12/12/2015)

(1st 2nd 3(d)

Edition and Addenda of Section Xl applicable to the inspection plans 2001 Edition with 2003 Addenda Date I revision of inspection plans May 201 5, Revision 7 Edition and Addenda of Section Xl applicable to repair/replacement activities, if different than the inspection plans None Code Cases used for inspection and evaluation: N-460, N-508-4, N-532-4, N-532-5, N-61 3-1 N-663, N-700, N-702 ,

(if applicable, including cases modified by Case N-532 and later revisions)

CERTIFICATE OF CONFORMANCE I certify that (a) the statements made in this report are correct; (b) the examinations and tests, meetthe Inspection Plan as required by the ASME Code,Section XI; and (c) th epair/replacement activities and evaluations supporting the completion of R22 Conform to th quire e t Section Xl. (refueling outage number)

Signed Z1E Dtrt4ri Date 9/14/15 CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspector and employed by HSB Global Standards of Hartford, Connecticut 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 employee 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 (Inspectors Signare)

Commission I 332 A (Nation BoarNumber and Endorsement)

Date 5,Io tS Page 3 of 4

ISI

SUMMARY

REPORT R22 TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination Category and Item Item Description Evaluation Description Number Misalignment due to*thermal F-AIF1.10A Rigid Strut Support: RFW-164 expansion. Evaluated under CAP Condition Report # 328829.

Misalignment due to thermal F-AIF1.10C Spring Can Support: MS-HA-2 expansion. Evaluated under CAP Condition Report #329488 Component not in alignment per drawing information. Evaluated under F-AIF1.10C Spring Can Support: RRC-12 CAP Condition Report #329966. The drawina was in error and corrected.

Missing lug pin and cap screws.

Evaluated under CAP Condition E-AIE1 .11 Wetwell Hatch Report # 329946. The missing parts do not impact pressure boundary components.

Damaged stud threads during disassembly. Nuts replaced under ASME Plan 2-2795. Studs remained B-G-2/B7.70 Valve Bolting: RHR-V-50B with spacers to cover damaged threads. Evaluated under CAP Condition Report #330022.

TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Code Class Item Description Description of Date Completed Repair/Replacement Work Plan Number Replaced Degraded RWCU-HX-1C/2A 3 Piping Identified by 9/3/15 2-2861 Piping FAC Replaced Degraded RWCU-HX-1B/1C 3 Piping Identified by 7/27/15 2-2855 Piping FAC Snubber Support Replaced Deformed 1 7/13/15 2-2851 MS-48 Snubber Pin Replaced MSRV due 1 MS-RV-4C 8/24/15 2-2834 to IST Failure Replaced MSRV due 1 MS-RV-1A 8/24/15 2-2832 to IST Failure RCIC Spray Piping Machined Damaged 1 7/23/15 2-2817 Flange Flange Face Replaced Damaged Bonnet Bolting 1 RHR-V-50B 8/18/15 2-2795 Materials (ISi Exam Relects)

Replaced Damaged Bonnet Bolting 1 MS-V-28A 9/1/15 2-2717 Materials (ISi Exam Rejects)

Replaced Damaged Bonnet Bolting 1 RCIC-V-66 8/25/15 2-2675 Materials (ISi Exam Rejects)

Date Completed refers to the date of the completed NIS-2 or NIS-2A form. The physical repair/replacement work was performed prior to June 28, 2015.

Page 4 of 4