ML20105A471

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

ML20105A471
Person / Time
Site:	Wolf Creek
Issue date:	04/14/2020
From:	Benham R Wolf Creek
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RA 20-0026
Download: ML20105A471 (2)

Text

Ron Benham Manager Nuclear and Regulatory Affairs April 14, 2020 RA 20-0026 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

Subject:

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

To Whom It May Concern:

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

Procedure Effective Date EPP 06-012, Rev. 17 March 16, 2020 The attached summary of the changes to the implementing procedure explain 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, Ron Benham RDB/rlt

Attachment:

Summary of Changes to One Procedure that Implements the Radiological Emergency Response Plan (RERP) for Wolf Creek Generating Station (WCGS) cc: S. A. Morris (NRC), w/a N. OKeefe (NRC), w/a B. K. Singal (NRC), w/a Senior Emergency Preparedness Inspector (NRC), w/a Senior Resident Inspector (NRC), w/a

Attachment to RA 20-0026 Page 1 of 1 Summary of Changes to One Procedure that Implements the Radiological Emergency Response Plan (RERP) for Wolf Creek Generating Station (WCGS)

1. Procedure EPP 06-012, Dose Assessment, Rev. 17 The procedure provides guidance for determining release rates and for estimating off-site dose to the Whole Body and Thyroid.

The procedure is being revised to make:

1. A minor editorial change to correct grammar.

2. A change to step 6.4 moved important guidance to a note. This step formatting change is editorial and does not affect the intent of the step action.

3. The Emergency Dose Calculation Program (EDCP) Spent Fuel Pool (SFP) option allows the operator to calculate releasable activity from a fire in the SFP. This activity is based on values from the most recent refueling outage. The procedure guidance references the SFP refuel data. The tables that provide this SFP refuel data tables have been updated. The procedure is being changed to reflect the updated data.

The change incorporated Condition Report (CR) # 130293, Procedure Change Request (PCR) # 70552 and PCR # 70553.

The change does not reduce the effectiveness of the Emergency Plan.