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Cook Nuclear Plant Unit Nos. 1 and 2 - Acceptance Review for LAR to Revise Environmental Technical Specifications (L-2018-LLA-0570) ML19011A3512019-01-11011 January 2019 NRR E-mail Capture - Request for Additional Information DC Cook Unit 1 Leak Before Break Amendment ML19009A5402019-01-0909 January 2019 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Acceptance Review for LAR to Revise Battery Monitoring and Maintenance TS ML18313A0802018-11-0808 November 2018 NRR E-mail Capture - D.C. Cook Units 1 and 2 - RAI for RPV Threads in Flange Alternative ML18275A0532018-10-0101 October 2018 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Acceptance Review for LAR to Revise Battery Monitoring and Maintenance TS 2023-02-21
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NRR-PMDAPEm Resource From: Dietrich, Allison Sent: Friday, May 29, 2015 6:28 AM To: 'hlkish@aep.com' Cc: Dinsmore, Stephen; Biro, Mihaela; Rosenberg, Stacey; Pelton, David;
'dmburgoyne@aep.com'; 'Michael K Scarpello (mkscarpello@aep.com)'
Subject:
APLA RAI for DC Cook Emergency License Amendment Request Attachments: RAI - APLA - May 29 2015.docx By letter dated May 28, 2015, Indiana Michigan Power Company (I&M, the licensee) submitted an emergency license amendment request for the Donald C. Cook Nuclear Plant (CNP) Unit 1. The proposed amendment would revise TS 3.8.1 to permit a one-time extension of the completion time for an inoperable emergency diesel generator (EDG). It would also permit extensions of several surveillance frequencies for support equipment for the affected EDG.
The U.S. Nuclear Regulatory Commission (NRC) staff in the Probabilistic Risk Assessment Branch of the Office of Nuclear Reactor Regulation is currently reviewing your submittal. The staff has determined that additional information is needed in order to complete the review. A request for additional information (RAI) is attached.
Please respond to this request by May 29, 2015.
Sincerely, Allison W. Dietrich, Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation 301-415-2846 1
Hearing Identifier: NRR_PMDA Email Number: 2118 Mail Envelope Properties (C0A338EE37A11447B136119705BF9A3F0289E2F05907)
Subject:
APLA RAI for DC Cook Emergency License Amendment Request Sent Date: 5/29/2015 6:28:00 AM Received Date: 5/29/2015 6:27:00 AM From: Dietrich, Allison Created By: Allison.Dietrich@nrc.gov Recipients:
"Dinsmore, Stephen" <Stephen.Dinsmore@nrc.gov>
Tracking Status: None "Biro, Mihaela" <Mihaela.Biro@nrc.gov>
Tracking Status: None "Rosenberg, Stacey" <Stacey.Rosenberg@nrc.gov>
Tracking Status: None "Pelton, David" <David.Pelton@nrc.gov>
Tracking Status: None
"'dmburgoyne@aep.com'" <dmburgoyne@aep.com>
Tracking Status: None
"'Michael K Scarpello (mkscarpello@aep.com)'" <mkscarpello@aep.com>
Tracking Status: None
"'hlkish@aep.com'" <hlkish@aep.com>
Tracking Status: None Post Office: HQCLSTR02.nrc.gov Files Size Date & Time MESSAGE 1040 5/29/2015 6:27:00 AM RAI - APLA - May 29 2015.docx 19913 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received:
DONALD C. COOK NUCLEAR PLANT, UNIT 1 By letter dated May 28, 2015, the Indiana Michigan Power Company (l&M), the licensee for Donald C. Cook Nuclear Plant (CNP) Unit 1, requested an amendment to the Appendix A TechnicalSpecifications (TS) for Renewed Facility Operating License DPR-58. The proposed amendmentwould revise TS 3.8.1 to permit extending the Completion Time (CT) from 14 days to 65 days for aninoperable emergency diesel generator (EDG). The proposed amendment would also revise theTS Surveillance Requirement 3.8.1.2 and 3.8.1.3 to extend the Surveillance Frequency (SF) from31 days to 82 days, or within 3 days following the inoperable EDG being restored to service, and TSSurveillance Requirement 3.8.1.7 to extend the SF from 92 days to 145 days, or within 3 daysfollowing the inoperable EDG being restored to service.
In order for the staff to proceed with its review of the proposed change, the following information is needed:
- 1. Provide clarification on changes made to the 2009 PRA Model of Record and the Fire PRA Model of Record in developing the PRA to support the Unit 1 AB EDG one-time CT extension. (Note: this request was communicated to the licensee via telephone on May 28, 2015, and a response was provided to the NRC on May 28, 2015.)
- 2. Confirm that CDFinst and LERFinst (page 6, PRA-QNT-005) are also zero maintenance estimates.
- 3. Do the risk calculations include changes to the other surveillance intervals requested for 3.8.1.2, 3.8.1.3, and 3.8.1.7, or can those impacts be determined to be negligible based on the potential impact on the risk assessment?
- 4. The submittal provides a typical but not all inclusive list of other activities that will be performed during the one-time EDG CT extension (page 20 of enclosure 2). The submittal also states that required surveillances with short duration are not considered (Page 8 of PRA-QNT-005). However, some surveillances of short duration may increase the likelihood of a transient with a demand for the EDGs. How has this been considered?
- 5. The updated internal events results are included in both Table 5.4-1 (PRA-QNT-004) and Table 5.6-1 (PRA-QNT-005). CDF increased from 1.412E-5/yr in the 2009 model of record to 1.268E-4/yr in the updated internal events model. Apparently this increase was primarily due to the removal of the reduction factor on CCFs for loss of CCW and ESW. Confirm that the updated internal events model increased the CDF by a factor of 10 over the 2009 model because of the modified CCF values.
- 6. A new human action 1FSBO---RCC-OMAassociated with the new CVCS cross-tie and cooldown has been introduced. Table 5.2-1 (page 35 PRA-QNT-004), states that the execution time is 15 minutes and assigns a value of 6.58E-4. Provide a summary of all the actions needed to establish the cross-tie including time available, time needed, and the joint HEP used in the sequences.