AEP-NRC-2020-40, Calculation PRA-QNT-009, Rev. 0, Evaluation of Risk Significance of Short-Term ILRT Extension
ML20164A046 | |
Person / Time | |
---|---|
Site: | Cook |
Issue date: | 05/22/2020 |
From: | Sattler J Jensen Hughes |
To: | American Electric Power, Indiana Michigan Power Co, Office of Nuclear Material Safety and Safeguards |
Shared Package | |
ML20164A044 | List: |
References | |
AEP-NRC-2020-40 PRA-QNT-009 | |
Download: ML20164A046 (33) | |
Text
- Enclosure 3 to AEP-NRC-2020-40 Evaluation of Risk Significance of Short-Term ILRT Extension
D. C. COOK NUCLEAR PLANT C!JAMERICAN" EUCTRIC POWER
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CALCULATION/REPORT COVER SHEET D Full Rev D Addendum Document No. PRA-QNT-009 Rev No. 0 D Status Change
Title:
Evaluation of Risk Significance of Short-Term ILRT Extension STATUS: ~ Approved D Superseded 0 Voided I D Information Only Document Type/Class: I~ Calculation D Report ID Class 1 D Class 2 ~ Class 3 QUALITY SYSTEM UNIT COMPUTER REVIEW METHOD:
CLASSIFICATION: CODE: NO.: MEDIA: ~ Detailed Review D Safety-Related 0Yes 0 Alternate Calculation 0 Non-Safety Related with ~No 0 Other NAPL 12 Special Requirements 0 N/A - Status/Class Change Only
~ Non-Safety Related Do any assumptions require later verification? 0Yes ~No / If yes, Action No.
Description:
The purpose of this analysis is to provide a risk assessment of temporarily extending the currently allowed containment Type A Integrated Leak Rate Test (ILRT) interval by 6 months from 15 years to 15.5 years for Unit 1 of the Donald C. Cook Nuclear Plant (CNP).
If the Reviewer is the Preparer's supervisor, the supervisor review is needed and is approved: ~NIA Supervisor's Manager's Name Title Signature Date Qualification Matrix Verification
- The responsible Engineering Supervisor/Manager approval signature also serves to signify that the qualifications of the individual(s) assigned as Preparer(s) and Reviewer(s) and Independent Design Verifier(s) were verified in the Plant Qualification Matrix.
Preparation & Review PREPARED BY: REVIEWED BY: *APPROVED BY:
Name: James Heyeck Chris Peckat Greg Hill
Title:
PRA Contractor Nuclear Engineer Sr Supervisor Organization: Jensen Hughes NSA/PRA NSA/PRA Signature:
Date:
D Sign-offs for additional Preparer(s) and Reviewer(s) on next page
! This document includes the following pages: 1-32 (32 pages total) ! Page 1
0 JENSEN HUGHES Advancing the Science of Safety Donald C. Cook Nuclear Plant:
Evaluation of Risk of Short-Term ILRT Extension PRA-QNT-009 Prepared for:
,,,,.. INDIANA
,ii,jf MICHIGAN POWER" A unit ofAmerican Electric Power Donald C. Cook Nuclear Plant Indiana Michigan Power Company Project Number: 1EAT1V046 Project
Title:
Short-Term ILRT Extension Revision: O Name and Date Digitally signed by Justin Sattler Preparer: Justin Sattler Date: 2020.05.22 10:22:04-05'00'
=- 7
~ig itally signed by Matt Johnson Reviewer: Matthew Johnson 1 IOJl'<~,,_____ _ _ Qate: 2020.05.22 12:29:36-05'00'
___ .J Review Method Design Review r;gJ Alternate Calculation Er Th Orn S bLI 0 -- igitally signed by Eric Thornsbury Approver: Eric Thornsbury *1 C ry~o/'l:,c;=us, E=~thornsbu,y@jens_enhughes.com, O=Jensan
-Hughes, OU=R1sk Informed Services, CN=Enc Thornsbury 1 -=.O*tej2020.os.22 13:4B:s2-04*00*
Revision 0 Page 2 of 32
PRA-QNT-009 Evaluation of Risk Significance of Short-Term ILRT Extension REVISION RECORD
SUMMARY
Revision Revision Summary 0 Initial Issue Revision 0 Page 3 of 32
PRA-QNT-009 Evaluation of Risk Significance of Short-Term ILRT Extension TABLE OF CONTENTS 1.0 PURPOSE ..............*........................................................................................................ 5 2.0 SCOPE ........................................................................................................................... 5
3.0 REFERENCES
............................................................................................................... *7 4.0 ASSUMPTIONS AND LIMITATIONS ............................................................................. 10 5.0 METHODOLOGY AND INPUTS .................................................................................... 11 5.1 General Resources Available ...................................................................................... 11 5.2 Plant Specific Inputs ................................................................................................... 12 5.3 Impact of Extension on Detection of Component Failures that Lead to Leakage (Small and Large) ............................................................................................................... 14 6.0 CALCULATIONS ...........................................................................................................15 6.1 Step 1 - Quantify the Risk in Terms of Frequency per Reactor Year .......................... 16 6.2 Step 2 - Develop Plant-Specific Person-Rem Dose (Population Dose) ....................... 19 6.3 Step 3- Evaluate Risk Impact of Extending Type A Test Interval from 15 to 15.5 Years