GO2-17-153, Inservice Inspection Summary Report for the Twenty-Third Refueling Outage (R23)

Inservice Inspection Summary Report for the Twenty-Third Refueling Outage (R23)

ML17255A955
Person / Time
Site:	Columbia
Issue date:	09/12/2017
From:	Javorik A Energy Northwest
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
GO2-17-153
Download: ML17255A955 (5)

Text

Alex L. Javorik Columbia Generating Station P.O. Box 968, PE04 Richland, WA 99352-0968 Ph. 509.377.8555 l F. 509.377.4150 aljavorik@energy-northwest.com September 12, 2017 GO2-17-153 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-THIRD REFUELING OUTAGE (R23)

Dear Sir or Madam:

Article IWA-6000 of Section XI of the 2007 Edition with the 2008 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 at the completion of each refueling outage for the examinations, tests, and repair replacement activities conducted since the preceding summary report.

This report is to be submitted within 90 calendar days of the completion of the refueling outage. In this case, the report is for R23 for Columbia Generating Station (Columbia).

The outage was completed on June 19, 2017.

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 U.S. Nuclear Regulatory Commission (NRC) approval to implement this code case is not required.

The enclosure to this letter is herewith being submitted, which includes the completed OAR-1 form 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 23 up to and including refueling outage R23.

G02-17-153 Page 2 of 2 There are no commitments being made to the NRC by this letter. By means of this submittal, the reporting requirement of IWA-6000 is fulfilled for the R23 Outage. Should you have any questions or require additional information, please contact Ms. LL. Williams at (509) 377-8148.

Executed on this L2t-4 day of Sepfer1Je/

1 io11.

A. L. Javo; Vice President, Engineering

Enclosure:

Form OAR-1, Owner's Activity Report for Columbia Generating Station Cycle R23 cc: NRC Region IV Administrator NRC NRA Project Manager NRC Senior Resident lnspector/988C CD Sonoda - BPA/1399 WA Horin - Winston & Strawn L Williamson - WA Department of L&I

FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number ISl-SR-R23 Plant Columbia Generating Station, 76 North Power Plant Loop, Richland, WA 99354 Unit No. ---"'"-N_A_ __ Commercial service date _ _ _1_2_/1_3_/_19_8_4_ __ Refueling outage no. _ _ _ _ R_2_3_ __

(if applicable)

Current inspection interval _ _ _ _ _ _ _ _ _ _ _ _ 4_

1 h~(_12_/_1_3_/2_0_1_5_-_1_2_/_12/_2_0_25

_)~-----------

(1", 2"", 3'", 4", other)

Current inspection period _ _ _ _ _ _ _ _ _ _ _ _1_s1_,(._1_2_/1_3_/2_0_1_5_-_12_/_1_2/_2_0_1_9,_)- - - - - - - - - - - -

(1", 2"". 3"')

Edition and Addenda of Section XI applicable to the inspection plans 2007 Edition with 2008 Addenda Oate I revision of inspection plans April 2017, Revision 2 Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection p l a n s - - - - - -

None Code Cases used for inspection and evaluation: _ _ _ _ _ _ _N_-_50_8_-_4"'",_N_-_5_3_2_-5_,_,_N_-_6_1_3_*1~,_N_-_6_6_3~,_N_-7_0_2 _ _ _ _ _ __

(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, meet the Inspection Plan as required by the ASME Code,Section XI; and (c) the repair/replacement activities and evaluations supporting the completion of R23 nts of Section XI. ' l l (refueling outage number)

Si.~fli!c.~ ~C.,~- S..fe.so" R;c..~ i~r per 1e fl'OI\ *

' OAme~ Dcrw:" Cf-&*- 17 Date 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 The Hartford Steam Boiler Inspection and Insurance Company of Hartford, Connecticut 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, 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.

Commission (Inspector's Signature) mber and Endorsement)

Date _ _,__~___..,,.._6/0_'/,7_ __

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TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination Category and Item Item Description Evaluation Description Number F*A/F1.10C Loose jam nut. Evaluated under Spring Support: RFW-175 Report # 4-003.

Cold set point found out of tolerance.

F-A/F1.10C Spring Support: RHR-431 Evaluated under CAP Condition Report #366255 Apparent misalignment under cold F-A/F1.10C Spring Can Support: RCIC-940N conditions due to thermal expansion.

Evaluated under CAP Condition Report #366440 Page 2 of 3

TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Code Class Item Description Description of Date Completed Repair/Replacement Work Plan Number HPCS-R0-5: High Pressure 2 Core Spray minimum flow Replaced fasteners 12/20/16 2-2938 line restriction orifice.

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 19, 2017.

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