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| | author name = Rankin J | | | author name = Rankin J |
| | author affiliation = NRC/NRR/DORL/LPLIII-1 | | | author affiliation = NRC/NRR/DORL/LPLIII-1 |
| | addressee name = Miksa J P | | | addressee name = Miksa J |
| | addressee affiliation = Entergy Nuclear Operations, Inc | | | addressee affiliation = Entergy Nuclear Operations, Inc |
| | docket = 05000255 | | | docket = 05000255 |
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Category:E-Mail
MONTHYEARML24032A2442024-02-0101 February 2024 OEDO-24-00011 - 10 CFR 2.206 Petition Holtec Misuse Decommissioning Fund- Email to Petitioner ML24005A1262024-01-0505 January 2024 Permanently Defueled Emergency Plan Implementation Notification ML23055A1532023-02-24024 February 2023 Request for Additional Information Related to the Post-Shutdown Decommissioning Activities Report ML22343A2282022-12-0909 December 2022 Acceptance Review: Palisades Proposed Exemption from 10 CFR 50.54(w)(1) - Onsite Property Damage Insurance ML22343A1902022-12-0909 December 2022 Acceptance Review: Palisades Proposed Exemption from 10 CFR 140.11 (a)(4) Primary and Secondary Liability Insurance ML22284A0502022-10-0707 October 2022 Acceptance Review: License Amendment Request to Revise License Condition to Eliminate Cyber Security Plan Requirements ML22227A0082022-08-12012 August 2022 Acceptance Review: Exemption Request from 10CFR50.47(b), 10 CFR 50.47(c)(2), and 10 CFR Part 50, Appendix E, Section IV ML22227A0092022-08-12012 August 2022 Acceptance Review: License Amendment Request to Revise Emergency Plan and Emergency Action Level Scheme (L-2022-LLA-0099) ML22179A0752022-06-28028 June 2022 E-mail from Entergy Dated June 28, 2022, Notification of Palisades and Big Rock Point License Transfer (EPIDs L-2022-LLM-0002 and L-2020-LLM-0003) ML22159A2672022-06-0202 June 2022 Answers to Your Questions on Palisades ML22159A2652022-05-0303 May 2022 Questions Asked at Palisades Plant Performance Public Meeting April 26, 2022 ML21328A0062021-11-18018 November 2021 NRR E-mail Capture - (External_Sender) State of Michigan Response - Palisades Nuclear Plant and Big Rock Point Plant - Application for Order Consenting to Transfers of Licenses and Conforming License Amendments ML22208A1052021-11-16016 November 2021 NRR E-mail Capture - (External_Sender) State of Michigan Response - Palisades - Preparation for Issuance of Final Environmental Assessment and Finding of No Significant Impact Holtec Exemption Request to Use Dtf ML21309A5152021-11-0505 November 2021 NRR E-mail Capture - Palisades Nuclear Plant - Preparation for Issuance of Final Environmental Assessment and Finding of No Significant Impact Holtec Exemption Request to Use Dtf ML21309A2982021-11-0505 November 2021 NRR E-mail Capture - Palisades Nuclear Plant and Big Rock Point Plant - Application for Order Consenting to Transfers of Licenses and Conforming License Amendments ML21209A9802021-07-28028 July 2021 NRR E-mail Capture - Palisades Nuclear Plant - Acceptance of Requested Licensing Action, Rescission of Interim Compensatory Measure from Order EA-02-026 ML21189A2462021-07-0606 July 2021 NRR E-mail Capture - Palisades Nuclear Plant - Acceptance of Requested Licensing Action, Proposed Partial Exemption from Record Retention Requirements ML21189A0432021-07-0606 July 2021 NRR E-mail Capture - Palisades Nuclear Plant - Acceptance of Requested Licensing Action, Permanently Defueled Technical Specifications ML21054A1822021-02-23023 February 2021 NRR E-mail Capture - Regarding Public Comment on Palisades Request for Relief RR 5-8 ML21028A4092021-01-27027 January 2021 NRR E-mail Capture - Palisades Nuclear Plant - Acceptance of Holtec Exemption Request from 10CFR50.82(a)(8)(i)(A) and 10CFR50.75(h)(1)(iv) ML21028A0552021-01-27027 January 2021 NRR E-mail Capture - Palisades Nuclear Plant - Acceptance of License Transfer Application ML21007A3752021-01-0707 January 2021 NRR E-mail Capture - Regarding Public Comment on Palisades Nuclear Plant License Transfer (Sierra Club Nuclear Free Michigan) ML21054A1812021-01-0606 January 2021 NRR E-mail Capture - (External_Sender) Regarding Public Comment on Palisades Request for Relief RR 5-8 ML20275A3432020-10-0101 October 2020 Verbal Authorization for Proposed Alternative (RR 5-8) Reactor Vessel Closure Head Penetration Repairs ML20272A0112020-09-26026 September 2020 Request for Additional Information - Palisades Relief Request RR 5-8 (Proposed Alternative) for Reactor Pressure Vessel Head Penetration Repairs ML20262G9622020-09-17017 September 2020 Acknowledgement to Mr. Muhich e-mail, Dated September 15, 2020 (e-mail) ML20241A1802020-08-27027 August 2020 NRR E-mail Capture - Palisades Nuclear Plant- Upcoming Steam Generator Tube Inservice Inspection ML20162A4522020-04-0808 April 2020 Lake Mich Level Correspondence with Ipotter ML19344C7162019-08-25025 August 2019 Response from NEIMA Local Community Advisory Board Questionnaire 08-25-2019 C Ferry ML19344C8072019-08-16016 August 2019 Scanned Response 09-29-2019 I Potter ML19226A2932019-08-14014 August 2019 NRR E-mail Capture - Request for Additional Information Re License Amendment Request to Adopt TSTF-425, Revision 3 for the Palisades Nuclear Plant ML19226A2922019-08-0505 August 2019 NRR E-mail Capture - Draft Request for Additional Information for Palisades License Amendment Request to Adopt TSTF-425 ML19122A4852019-04-29029 April 2019 NRR E-mail Capture - Request for Additional Information for Palisades License Amendment Request to Revise License Conditions Related to NFPA 805 Modifications ML19095A6572019-04-0505 April 2019 NRR E-mail Capture - Acceptance for Review of Application to Revise the Palisades Nuclear Plant License Renewed Facility Operation License Regarding Full Compliance Implementation Date for the Fire Protection Program ML19059A1782019-02-28028 February 2019 Acceptance Review Results for Relief Request No. EN-19-RR-1 to Use ASME Code Case N-831-1 for Entergy Fleet ML19059A0292019-02-27027 February 2019 NRR E-mail Capture - Acceptance Review Results for License Amendment Request to Adopt TSTF-529, Revision 4, Clarify Use and Application Rules, for Entergy Fleet ML19009A5392019-01-0909 January 2019 NRR E-mail Capture - Request for Additional Information for Palisades License Amendment Request to Revise Emergency Diesel Generator Degraded Voltage Surveillance Requirement 3.3.5.2a ML19009A5382018-12-12012 December 2018 NRR E-mail Capture - Draft Request for Additional Information for Palisades License Amendment Request to Revise Emergency Diesel Generator Degraded Voltage Surveillance Requirement 3.3.5.2a ML18337A1382018-11-30030 November 2018 NRR E-mail Capture - Request for Additional Information Related to Palisades Relief Request Number RR 5-7 ML18337A1352018-11-30030 November 2018 NRR E-mail Capture - Acceptance for Review of Application to Revise the Palisades Nuclear Plant License Renewed Facility Operation License Regarding Changes to the Fire Protection Plan ML18337A1402018-11-29029 November 2018 NRR E-mail Capture - Draft Request for Additional Information Related to Palisades Relief Request 5-7 ML18184A2402018-07-0303 July 2018 NRR E-mail Capture - Acceptance for Review of Application to Revise Technical Specification Surveillance Requirement 3.3.5.2a for the Diesel Generator Undervoltage Start ML18101A1132018-04-11011 April 2018 NRR E-mail Capture - Palisades Nuclear Plant - Request for Additional Information Regarding Proposed Alternative for Relevant Condition ML18081A2962018-03-22022 March 2018 NRR E-mail Capture - Palisades Nuclear Plant - Request for Additional Information Regarding Proposed Changes to Site Emergency Plan for Permanently Defueled Condition (CAC MG0198: EPID L-2017-LLA-0305) ML18059A8202018-02-28028 February 2018 NRR E-mail Capture - Palisades Nuclear Plant - Request for Additional Information Regarding Proposed Alternative for Relevant Condition ML17355A0092017-12-20020 December 2017 NRR E-mail Capture - Palisades Nuclear Plant: Acceptance Review for Relief Request No. RR 5-6 - Alternative to the Reexamination Frequency for a Relevant Condition ML17345A0142017-12-0808 December 2017 NRR E-mail Capture - Acceptance Review Results Entergy Request No. EN-17-RR-1 ML17338B1242017-11-30030 November 2017 NRR E-mail Capture - (External_Sender) Palisades Nuclear Plant Flood Hazard Reevaluation Report FHRR Staff Assessment Input ML17335A1042017-11-30030 November 2017 NRR E-mail Capture - Palisades Nuclear Plant - RAI Regarding Proposed Changes to Administrative Controls Section of the Technical Specifications for Permanently Defueled Condition (CAC MG0021; EPID L-2017-LLA-0266) ML17317A0042017-11-0909 November 2017 NRR E-mail Capture - Palisades Nuclear Plant - Acceptance Review for License Amendment Request to Change the Full Compliance Implementation Date for the Fire Protection Transition License Condition 2024-02-01
[Table view] |
Text
1 NRR-PMDAPEm Resource From: Rankin, Jennivine Sent: Thursday, October 23, 2014 8:21 AM To:MIKSA, JAMES P (jmiksa@entergy.com); Smith, Keith E (ksmit21@entergy.com); Hazelhoff, Amy C (ahazelh@entergy.com)
Cc: Hardy, Jeffery A (jhardy@entergy.com); ERICKSON, JEFFREY S (JERICKS@entergy.com)
Subject:
Palisades Nuclear Plant - RAI - Lic ense Amendment Request to Adopt NFPA-805 Performance-Based Standard for Fire Prot ection for Light Water Reactors (MF0382)
Attachments:RAIs.docx Mr. Miksa and Mr Erickson, By letter dated December 12, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12348A455), as supplemented by letters dated February 21, September 30, October 24, December 2, 2013, April 2, May 7, June 17, and August 14, 2014 (ADAMS Accession Nos. ML13079A090, ML13273A469, ML13298A044, ML13336A649, ML14092A126, ML14127A152, ML14169A046, and ML14226A498, respectively), Entergy Nuclear Operations, Inc. (ENO or the licensee) submitted a license amendment request (LAR) to revise Facility Operating License No. DPR 20 for Palisades Nuclear Plant. The LAR would permit transition of the fire protection licensing basis from Title 10 of the Code of Federal Regulations (10 CFR), Section 50.48(b), to 10 CFR 50.48(c), "National Fire Protection Association Standard NFPA 805."
The U.S. Nuclear Regulatory Commission staff has reviewed the information provided and determined that additional information is needed to complete the review.
A clarification teleconference was held on October 21, 2014. During the teleconference, it was agreed that ENO would provide the response to the attached RAIs by November 7, 2014. Please treat this e-mail as formal transmittal of the Request for Additional Information.
Thanks, Jennie Jennie Rankin, Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Hearing Identifier: NRR_PMDA Email Number: 1659 Mail Envelope Properties (Jennivine.Rankin@nrc.gov20141023082100)
Subject:
Palisades Nuclear Plant - RAI - License Amendment Request to Adopt NFPA-805 Performance-Based Standard for Fire Protection for Light Water Reactors (MF0382) Sent Date: 10/23/2014 8:21:15 AM Received Date: 10/23/2014 8:21:00 AM From: Rankin, Jennivine Created By: Jennivine.Rankin@nrc.gov Recipients: "Hardy, Jeffery A (jhardy@entergy.com)" <jhardy@entergy.com> Tracking Status: None "ERICKSON, JEFFREY S (JERICKS@entergy.com)" <JERICKS@entergy.com> Tracking Status: None "MIKSA, JAMES P (jmiksa@entergy.com)" <jmiksa@entergy.com>
Tracking Status: None "Smith, Keith E (ksmit21@entergy.com)" <ksmit21@entergy.com> Tracking Status: None "Hazelhoff, Amy C (ahazelh@entergy.com)" <ahazelh@entergy.com> Tracking Status: None Post Office: Files Size Date & Time MESSAGE 1479 10/23/2014 8:21:00 AM RAIs.docx 33415
Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: Recipients Received:
Request for Additional Information
PRA RA 01.j.01.01
By letter dated August 14, 2014 (ADAMS Accession No. ML14226A498), the response to PRA RAI 01.j.01 states that several 480V motor control centers (MCCs) do not postulate damage beyond the ignition source given that the MCCs are considered by the licensee to be well-sealed and robustly secured. Note that with respect to this issue, new guidance is being developed in draft FAQ 14-0009 to provide clarification of NUREG/CR-6850, "EPRI/NRC-RES Fire PRA Methodology for Assessing Software Quality" guidance on well-sealed and robustly secured cabinets housing circuits with voltages of greater than 440V. Relevant NRC Staff comments are provided in "NRC Comments on MCC Treatment White Paper August 29, 2014" (Comments) (ADAMS Accession number ML14245A133). The NRC comments support the use of a value of 0.1 to characterize the likelihood that such a fire can breach a well-sealed MCC cabinet and damage all cables within 6" from the top of the cabinet. While the NRC staff acknowledges that this guidance is considered draft, it may be used to determine the acceptability of transition risk.
i) Describe how fires breaching well-sealed cabinets are modelled consistent with current draft guidance; and, ii) Provide updated aggregate NFPA-805 Transition PRA results (currently summarized in the response to RAI 30) including fires that breach well-sealed cabinets. NFPA-805 Transition PRA results include total fire CDF and LERF, and CDF and LERF associated with transition. Confirm this update will be in the Fire PRA model to be used for self approval (i.e., implementation item).
PRA RAI 30.01 The response to PRA RAI 30 suggests that weaknesses associated with the Fire Probabilistic Risk Assessment (FPRA) HRA dependency analysis, namely PRA RAIs 01.h and 03 regarding updating the dependency analysis and PRA RAI 01.h.01 regarding its treatment of location, have not been incorporated in FPRA or the updated Attachment W results provided as to the letter dated August 14, 2014.
i) Are the updated dependency and location evaluations included in the updated Attachment W?
ii) If not, indicate whether incorporating the updated evaluations might cause the RG 1.174, "An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis" acceptance guidelines to be exceeded and provide confidence (e.g., with an updated Implementation Item 3) that these evaluations will be completed before using the PRA to support self-
approval.
PRA RAI 30.a.01 The response to PRA RAI 30 states that the FPRA model to be used at the beginning of the self-approval of post-transition changes "would exclude modifications not implemented at the time". Noting that all PRA-credited implementation items and modifications must be completed prior to use of the FPRA model for self-approval, clarify this statement.
PRA RAI 30.c.01
With respect to PRA RAI 30 and Attachment W:
- a. Confirm that the updated Attachment W results provided in Attachment 4 to the letter dated August 14, 2014 reflect all the revisions to VFDRs and recovery actions identified in Attachment 2 to the same letter.
- b. The revised Attachment W, Table W-2, provides negative CDF and LERF Transition risk. Implementation Item 8 indicates that the final risk estimates that will be developed after all modifications and method changes associated with transition are completed will be assessed against these negative values instead of the RG 1.174 acceptable risk increase guidelines. RG 1.174 acceptance guidelines may also be used. If changes to the proposed language in Implementation Item 8 are desired to reflect this, please provide updated proposed language for Implementation Item 8.