Letter Sequence RAI |
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EPID:L-2017-LLR-0142, Proposed Alternative - Relief Request Number RR 5-6, Alternative to the Reexamination Frequency for a Relevant Condition - Foreign Material in Reactor Vessel (Open) |
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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
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NRR-DMPSPEm Resource From: Rankin, Jennivine Sent: Wednesday, April 11, 2018 8:57 AM To: ERICKSON, JEFFREY S (JERICKS@entergy.com); MIKSA, JAMES P (jmiksa@entergy.com)
Subject:
Palisades Nuclear Plant - Request for additional information regarding proposed alternative for relevant condition (EPID L-2017-LLR-0142)
Attachments: Final PNP RAI Round 2.docx Good morning, By letter dated December 1, 2017 (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML17335A013), as supplemented by letter dated March 27, 2018 (ADAMS Accession No.
ML17335A013), Entergy Nuclear Operations, Inc. (the licensee), submitted Request No. RR 5-6 for Palisades Nuclear Plant to the U.S. Nuclear Regulatory Commission (NRC) for review and approval, pursuant to the requirements of Title 10 of the Code of Federal Regulations, Section 50.55a(z)(2). The licensees application requested that the NRC authorize its proposed alternative to the successive inspection requirement of Paragraph IWB-2420(b) of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, Rules for Inservice Inspection [ISI] of Nuclear Power Plant Components, for a relevant condition.
The relevant condition refers to a piece of primary coolant pump impeller that is lodged in the interior of the reactor pressure vessel.
Based on its review of the amendment request, the NRC staff has determined that additional information is required to complete the review. A draft request for additional information (RAI) was transmitted on April 6, 2018, and a clarification call was held on April 10, 2018. As a result of the clarification phone call, the RAI was modified slightly to further clarify that the information needed by the staff relates to the basis for modeling the impeller piece as a beam loaded by a fixed displacement. As agreed upon, please submit your response to the RAI by April 30, 2018. If you wish to alter the date of your response, please contact me at (301) 415-1530.
Please treat this e-mail as formal transmittal of the RAIs.
- Thanks, Jennie Jennie Rankin, Project Manager Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation 1
Hearing Identifier: NRR_DMPS Email Number: 284 Mail Envelope Properties (BL2PR09MB09617CDE051F86D09926AA7398BD0)
Subject:
Palisades Nuclear Plant - Request for additional information regarding proposed alternative for relevant condition (EPID L-2017-LLR-0142)
Sent Date: 4/11/2018 8:57:26 AM Received Date: 4/11/2018 8:57:28 AM From: Rankin, Jennivine Created By: Jennivine.Rankin@nrc.gov Recipients:
"ERICKSON, JEFFREY S (JERICKS@entergy.com)" <JERICKS@entergy.com>
Tracking Status: None "MIKSA, JAMES P (jmiksa@entergy.com)" <jmiksa@entergy.com>
Tracking Status: None Post Office: BL2PR09MB0961.namprd09.prod.outlook.com Files Size Date & Time MESSAGE 1851 4/11/2018 8:57:28 AM Final PNP RAI Round 2.docx 36106 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received:
REQUEST FOR ADDITIONAL INFORMATION PROPOSED ASME CODE ALTERNATIVE REQUEST NUMBER RR 5-6 ALTERNATIVE TO THE REEXAMINATION FREQUENCY FOR A RELEVANT CONDITION FOREIGN MATERIAL LODGED IN THE REACTOR PRESSURE VESSEL FIFTH 10-YEAR INSERVICE INSPECTION INTERVAL PALISADES NUCLEAR PLANT ENTERGY NUCLEAR OPERATIONS, INC.
RENEWED FACILITY OPERATING LICENSE NO. DPR-20 DOCKET NO. 50-255 By letter dated December 1, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17335A013), as supplemented by letter dated March 27, 2018 (ADAMS Accession No. ML17335A013), Entergy Nuclear Operations, Inc., submitted Request No. RR 5-6 for Palisades Nuclear Plant (PNP) to the U.S. Nuclear Regulatory Commission (NRC) for review and approval, pursuant to the requirements of Title 10 of the Code of Federal Regulations (10 CFR), Section 50.55a(z)(2). The licensees application (also referred to as RR 5-6) requested that the NRC authorize its proposed alternative to the successive inspection requirement of Paragraph IWB-2420(b) of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, Rules for Inservice Inspection [ISI] of Nuclear Power Plant Components, (also referred to as the Code),
for a relevant condition - a piece of primary coolant pump (PCP) impeller that is lodged in the interior of the reactor pressure vessel. The proposed alternative is applicable for the remainder of fifth 10-year ISI interval at PNP, which commenced on December 13, 2015 and ends on December 12, 2025. In accordance with 10 CFR 50.55a(z)(2), the licensee submitted its proposed alternative based on its determination that compliance with the specified Code requirement would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
The NRC staff has determined that additional information is required in order to complete its review of this proposed alternative. The staffs request for additional information (RAI) is provided below.
Regulatory and Technical Basis for Follow-Up RAI-2a Pursuant to 10 CFR 50.55a(g)(4), inservice inspection of ASME Code Class 1, 2, and 3 components shall meet the requirements set forth in the ASME Code,Section XI, including the analytical evaluation requirement of Code Paragraph IWB-3142.4 for acceptance of relevant conditions found by visual examination. The licensees analytical basis for its proposed alternative relies on the results of its 2014 operability evaluation for meeting the analytical evaluation requirement of Code Paragraph IWB-3142.4. For acceptance of conditions by analytical evaluation, IWB-3142.4 also requires that reexaminations of such conditions be performed during successive inspection periods in accordance with IWB-2420 to determine whether any changes to the conditions have occurred that would require further corrective action. The staff must review certain information from the 2014 analytical evaluation in order to
determine whether this condition will remain acceptable for continued service for the duration of this proposed alternative (through December 2025).
Follow-Up RAI-2a:
In your response to RAI 2a, dated March 27, 2018, regarding the fracture analysis for the PCP impeller piece, you described the fatigue crack growth rate analysis performed. For the limiting case of an assumed fragment thickness of 1 inch, you stated that the crack growth rate is very low (less than 5x10-4 inches per loading cycle) and essentially arrests at a depth of approximately 0.75 inches (75% through wall).
From the information provided, it is not clear to the staff why the crack arrests at 75% through wall. Please include the basis for assuming that the fracture of this piece can be modeled as a beam loaded by a fixed displacement, considering that your December 1, 2017, application reports a fluid force of 350 pounds acting on the piece. Alternatively, please provide another method to demonstrate that the piece would be unlikely to fracture.
In addition, please address how you considered the margin against fracture; or if the crack arrests in the piece, please address whether the margin against fracture would become unbounded.