NL-21-1104, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis

Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis

ML21355A422
Person / Time
Site:	Hatch, 07200036
Issue date:	12/20/2021
From:	Gayheart C Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
NL-21-1104
Download: ML21355A422 (4)

Text

Regulatory Affairs 3535 Colonnade Parkway Birmingham, AL 35243 205.992.5000 December 20, 2021 Docket Nos.: 50-321 NL-21-1104 50-366 72-36 U. S. Nuclear Regulatory Commission Director, Division of Spent Fuel Management Office of Nuclear Material Safety and Safeguards ATTN: Document Control Desk Washington, D. C. 20555-0001 Edwin I. Hatch Nuclear Plant Units 1 and 2 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis Ladies and Gentlemen:

In accordance with 10 CFR 50.54(q)(5) and 10 CFR 72.44(f), Southern Nuclear Operating Company (SNC) hereby submits descriptions of changes to the emergency plan and a summary of the analysis demonstrating that the changes do not reduce the effectiveness of the plan. The emergency plan continues to meet the requirements in 10 CFR 50 Appendix E and the planning standards of 10 CFR 50.47(b). A description of the changes and a summary of the 50.54(q) analysis is enclosed.

This letter contains no NRC commitments. If you have any questions, please contact Jamie Coleman at (205) 992-6611.

Respectfully submitted, Cheryl Gayheart Regulatory Affairs Director CAG/efb/cbg

Enclosure:

1. Description of Emergency Plan Changes and Summary of 50.54(q) Analysis

U. S. Nuclear Regulatory Commission NL-21-1104 Page 2 cc: NRC Regional Administrator, Region II NRC NRR Project Manager - Hatch NRC Senior Resident Inspector - Hatch Georgia - State Board of Health - Director of Radiation Control SNC Records RTYPE: CHA02.004

Edwin I. Hatch Nuclear Plant Units 1 and 2 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis Enclosure 1 Description of Emergency Plan Changes and Summary of 50.54(q) Analysis to NL-21-1104 SNC 50.54(q) Summary of Analysis Description of Emergency Plan Changes and Summary of 50.54(q) Analysis On November 30th, 2021, Edwin I. Hatch Nuclear Plant (HNP) Units 1 and 2 implemented changes to the emergency plan implementing procedures for the HNP emergency classification scheme as follows:

The Initiating Condition for RS2 and RG2 in procedures NMP-EP-141-002, Hatch Emergency Action Levels and Basis, NMP-EP-141-002-F01, Hatch-Hot Initiating Condition Matrix and NMP-EP-141-002-F02, Hatch-Cold Initiating Condition Matrix were revised to read:

x RS2 Lowering of Spent Fuel Pool Level to 1.82 feet x RG2 Spent Fuel pool level cannot be restored to at least 1.82 feet for 60 minutes or longer (Note 1)

To align with current SNC design documents, the value of 1.4 feet for the spent fuel pool level was changed to 1.82 feet. SNC design documentation is consistent with the bottom of the sensor weight being at position 1.4 feet; however, due to the dead zone of the sensor, the actual low-level reading is 1.67 feet. In addition, a sufficient amount is added to compensate for instrument inaccuracy. Therefore, SNC changed the EAL matrix value for RG2 and RS2 from 1.4 feet to 1.82 feet.

These updates correct the affected Emergency Action Levels (EALs) and implementing procedures. The EAL modifications do not alter the intent of any specific EAL described in NEI 99-01 Rev. 6. The new level does not reduce the ability to assess, classify, and declare an emergency condition within 15 minutes of the available indications. The proposed change is made based on engineering calculations evaluating instrument response behavior, spent fuel pool configuration, and instrument uncertainty. The meaning or intent of the basis for the EAL is unchanged.

SNC has written 50.54(q) evaluations for these changes and has concluded that the changes do not result in a reduction in effectiveness. The SNC Standard Emergency Plan, HNP Emergency Plan, and the HNP EAL implementing procedures continue to meet the requirements in 10 CFR 50 Appendix E and the planning standards of 10 CFR 50.47(b).

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