ML23061A059

Revision of One Procedure That Implements the Radiological Emergency Response Plan (RERP) for Wolf Creek Generating Station (WCGS)

ML23061A059
Person / Time
Site:	Wolf Creek
Issue date:	03/02/2023
From:	Hamman D Wolf Creek
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
RA 23-0015
Download: ML23061A059 (1)

Text

Dustin T. Hamman Director Nuclear and Regulatory Affairs March 2, 2023 RA 23-0015 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

Subject:

Docket No. 50-482: Revision of One Procedure that Implements the Radiological Emergency Response Plan (RERP) for Wolf Creek Generating Station (WCGS)

Commissioners and Staff:

In accordance with 10 CFR 50.54(q)(5), WCGS is submitting a change to the emergency plan.

Specifically, one procedure that implements the WCGS RERP has been revised. The revised document is identified below:

Procedures Effective Dates EPP 06-017, Rev. 5 February 9, 2023 The attached summary of the changes to the implementing procedure explains that these changes do not reduce the effectiveness of the WCGS RERP.

This letter contains no commitments. If you have any questions concerning this matter, please contact me at (620) 364-4204.

Sincerely, Dustin T. Hamman DTH/jkt

Attachment:

Summary of Changes to One Procedure that Implements the Radiological Emergency Response Plan (RERP) for Wolf Creek Generating Station (WCGS) cc: S. S. Lee (NRC), w/a R. J. Lewis, (NRC), w/a G. E. Werner (NRC), w/a Senior Emergency Preparedness Inspector (NRC), w/a Senior Resident Inspector (NRC), w/a P.O. Box 411 l Burlington, KS 66839 l 620-364-8831

Attachment to RA 23-0015 Page 2 of 2 Summary of Changes to One Procedure that Implements the Radiological Emergency Response Plan (RERP) for Wolf Creek Generating Station (WCGS)

1. Procedure EPP 06-017, CORE DAMAGE ASSESSMENT METHODOLOGY, Rev. 5 EPP 06-017, Rev 5, Core Damage Assessment Methodology, provides guidance for the assessment of the degree of core damage during an emergency event. This information contains guidance for determination of the degree of damage to the fuel rod cladding, that results in the release of the fission product inventory in the fuel rod gap space; determination of the degree of core overheating that results in the release of fission product inventory in the fuel pellets and also contains a best estimate dose assessment for high activity sample collection.

A new step was added to provide guidance that accidents involving temperature transients in containment potentially introduce a Thermally Inducted Current (TIC) inaccuracy and the possible effect on GTRE0059 and GTRE0060, when it can occur and how it can affect the calculations. This new step helps the Nuclear Engineers assess the impact of TIC on core damage assessment. The step used to estimate fuel over-temperature damage based on containment hydrogen concentration was changed to reflect the most recent guidance. SAM TSG-05, COMPUTATIONAL AIDS superseded SAM CA-01, SEVERE ACCIDENT MANAGEMENT GUIDELINE COMPUTATIONAL AID. Figure 1, Note, RCS @10%

TECHNICAL SPECIFICATION 3.4.16, was changed to Reference 3.1.3 as the chart was changed in Rev. 4, but the note was missed in the Rev 4 revision.

Minor changes include a new reference. Also, changing a value to an equivalent value to be consistent with APF 06-002-03, Rev 1, EAL Classification Matrix. All other changes are editorial in nature.

These changes do not reduce the effectiveness of the Wolf Creek Radiological Emergency Response Plan.