GO2-21-112, Status of License Renewal Commitments

Status of License Renewal Commitments

ML21319A276
Person / Time
Site:	Columbia
Issue date:	11/15/2021
From:	Wolfgramm D Energy Northwest
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
GO2-21-112
Download: ML21319A276 (3)

Text




       

ENERGY Desirée M. Wolfgramm Columbia Generating Station NORTHWEST P.O. Box 968, PE20 Richland, WA 99352-0968 Ph. 509.377.4792 l F. 509.377.4674 dmwolfgramm@energy-northwest.com November 15, 2021 GO2-21-112 10 CFR 54 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

Subject:

COLUMBIA GENERATING STATION, DOCKET NO. 50-397 STATUS OF LICENSE RENEWAL COMMITMENTS

Reference:

NUREG-2123 "Safety Evaluation Report Related to the License Renewal of Columbia Generating Station," dated May 2012

Dear Sir or Madam,

The purpose of this letter is to notify the U.S. Nuclear Regulatory Commission of the completion of certain license renewal commitments (LRC) identified in the reference and as required by Renewed License No. NPF-21 License Condition 2.C.(35) when implementation of these activities is complete.

The table provided in the attachment identifies the LRCs that Energy Northwest is reporting as complete. The remaining commitments are in the process of being completed.

No new commitments are being made by this letter or the attachment. If you have any questions or require additional information, please contact Mr. R. M. Garcia, Licensing Supervisor, at (509) 377-8463.

Respectfully, c=F6::~

~ DocuSigned by:

Desirée M. Wolfgramm Regulatory Affairs Manager

Attachment:

As stated cc: NRC RIV Regional Administrator NRC NRR Project Manager NRC Senior Resident Inspector CD Sonoda - BPA/1399 EFSECutc.wa.gov E Fordham - WDOH R Brice - WDOH L Albin - WDOH




       

GO2-21-112 Attachment Page 1 of 2 Columbia's Completed License Renewal Commitment Table Commitment Summary/Description Status No.

Incorporate FSAR Supplement into the Columbia FSAR as required by 10 55 Completed CFR 54.21(d).

The elements of corrective actions, confirmation process, and administrative controls in the OQAPD (operational quality assurance program description) 56 will be applied to required aging management programs for both safety- Completed related and non-safety related structures and components determined to require aging management during the period of extended operation.

Commitments identified in association with the Columbia license renewal will 57 be tracked within the Columbia Regulatory Commitment Management Completed Program In accordance with the BWR Vessel Internals Program, Columbia will 58 implement the additional inspection requirements of BWRVIP-42-A once Completed those requirements are approved by the NRC staff.

Energy Northwest will submit a licensing basis change request to implement the BWRVIP ISP(E) at least two years prior to the period of extended 59 operation. Columbia will implement the ISP(E) as amended by the BWRVIP Completed letter of January 11, 2005, including the new capsule test schedule in Table 1 of that letter.

BWRVIP-116 The Columbia site procedure was modified to require any capsules removed from the reactor vessel to be stored in a manner that 60 would support future re-insertion of these capsules in the reactor vessel. Completed Columbia will notify the BWRVIP prior to any change in the storage of on-site materials.

61 Boron Carbide Monitoring Program Completed ISI Program: Prepare and submit the ISI Program Plan for the fourth 10-year 65 Completed interval no later than 2015.

Structures Monitoring Program: Perform borescope inspection of containment 67 sand pocket drain lines to confirm the absence of clogged drain lines and that Completed a flow path exists FAC Program: Ensure that the condensate and feedwater systems are 68 Completed screened and evaluated for cavitation prior to entering the PEO.

Re-evaluate the portions of the reactor pressure vessel beltline welds BG and BM for the period of extended operation (54 EFPY), in accordance with 69 the requirements of the ASME Code,Section XI, IWB- 3600 based on the Completed results of 2015 inservice inspection.

Perform a 54 EFPY equivalent margin analysis for the embrittlement (upper 70 shelf energy) of the reactor vessel N12 (instrumentation) nozzle forgings. Completed




       

GO2-21-112 Attachment Page 2 of 2 Commitment Summary/Description Status No.

At least two years prior to the period of extended operation, Columbia will install core plate wedges unless:

1) A site-specific analysis is approved by the NRC that resolves core plate bolt loss of preload due to both stress relaxation and cracking, or

2) An NRC approved method is developed to inspect the core plate bolts for cracking and a site-specific analysis for loss of preload due to stress relaxation of the core plate bolts is approved by the NRC.

71 LC 2.C.(56) Completed To prevent lateral motion of the core plate, the licensee shall install core plate wedges around the periphery of the core plate within the shroud on or before December 20, 2021. Upon completion of the core plate wedge installation, the licensee shall submit a written report to the NRC staff summarizing the results of the installation. The licensee shall also submit a written report regarding any corrective action taken related to core plate rim hold-down bolts or core plate wedges and the results of extent of condition reviews on or before December 20, 2021.