E-Mail - Palisades Request for InformationML15022A138 |
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Site: |
Palisades |
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Issue date: |
01/22/2015 |
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NRC/RGN-III |
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Download: ML15022A138 (2) |
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Category:Request for Additional Information (RAI)
MONTHYEARML24263A1712024-09-20020 September 2024 Environmental Request for Additional Information ML24192A0012024-07-0606 July 2024 (E-Mail) Palisades Nuclear Plant - Plant - Draft Request for Additional Information: Palisades Operating TS License Amendment Request - June 6, 2024 ML24192A1672024-06-28028 June 2024 Restart - NRC Request for Additional Information - EP ORO Coordination - June 28, 2024 ML24192A1472024-06-28028 June 2024 Email - Palisades Nuclear Plant - Draft Request for Additional Information: Palisades Administrative TS License Amendment Request - June 28, 2024 ML23354A2602023-12-21021 December 2023 Reference Simulator Inspection Request for Information ML23055A1542023-02-24024 February 2023 Attachment: Request for Additional Information on the Palisades PSDAR ML22292A2582022-10-31031 October 2022 PDEP-EAL Amendment RAI ML22102A2482022-04-14014 April 2022 Request for Additional Information Regarding License Amendment Request for Permanently Defueled Technical Specifications ML21274A4172021-10-0505 October 2021 Request for Information for an NRC Triennial Heat Exchanger/Sink Performance Inspection and Request for Information Inspection Report 05000255/2021004 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 ML20272A0112020-09-26026 September 2020 Request for Additional Information - Palisades Relief Request RR 5-8 (Proposed Alternative) for Reactor Pressure Vessel Head Penetration Repairs ML20133K0562020-05-14014 May 2020 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML19357A2752019-12-23023 December 2019 Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team); Inspection Report 05000255/2020011 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 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 ML18337A1402018-11-29029 November 2018 NRR E-mail Capture - Draft Request for Additional Information Related to Palisades Relief Request 5-7 ML18309A1342018-11-0808 November 2018 Supplemental Information Needed for Acceptance or Requested Licensing Action Amendment Request to Revise Technical Specifications to Adopt TSTF-425, Revision 3 ML18094B0922018-04-0505 April 2018 Enclosurequest for Additional Information (Letter to B. 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NRC Information Request 1 IP 71152 Baseline Inspection
- Annual Follow
-up of Selected Issues Document Request List Please provide a copy of the following documents to the onsite NRC resident inspector office prior to the NRC entrance meeting scheduled for Monday February 9, 2015.
These documents may be electronic or hard copy format and are needed to support the baseline inspection.
If you have any questions , please contact the lead inspector
- Mel Holmberg
- phone (630) 82 9-9748 or E-mail - msh@nrc.gov.
A. Provide a copy of the following documents (revisions applicable in 2004) related to the corrective actions taken in response to the October 16, 2004
, discovery of leak path indications in the Inconel buttering of the J
-groove weld on reactor pressure vessel (RPV) head control rod drive mechanism (CRDM) nozzle penetrations 29 and 30 as described in LER 2004 - 002- 00. 1) Site Quality Assurance Program Manual and the supporting referenced industry standard that define a significant condition adverse to quality such as NQA-1 "Quality Assurance Requirements for Nuclear Facility Applications
." 2) Site procedures that implement the Quality Assurance Program Manual related to the corrective action program which include the site procedures that:
- a. Contain a definition of a significant condition adverse to quality.
- b. Contain instructions for identification and classification of conditions adverse to quality and significant conditions adverse to quality.
- c. Contain instructions related to investigations to identify the cause(s) of significant conditions adverse to quality.
- 3) Site approved copy of the vessel head vendor nondestructive examination reports which identified the ultrasonic leakage path identified CRDM nozzle s 29 and 30 including the Owner Acceptance Reviews of these reports.
- 4) Dye penetrant examination records for nozzles 29 and 30 J
-groove welds completed in 2004 (e.g. initial dye penetrant and follow up dye penetrant examination records that record the sizes of the indications identified before and after grinding operations). 5) Condition Reports associated with the indications in the J
-groove welds or UT leakage paths for CRDM nozzle penetrations 29 and 30.
- 6) Records of the completed corrective actions for each of the condition reports in Item 5 above. 7) Cause Investigations/Evaluations completed for the indications in the J
-groove welds or UT leakage paths for CRDM nozzle penetrations 29 and 30.
- 8) Weld records for the fabrication of the original reactor vessel head weld buttering and J
-groove attachment welds at nozzles 29 and 30. Specifically, weld drawings, non
-destructive examination records, weld procedures, weld data sheets, and fabrication process assembly records.
- 9) Document with the reactor vessel head fabrication acceptance criteria applied to the final surface examinations completed on the J
-groove welds at nozzles 29 and 30.
- 10) Post repair drawing or document that records the dimensions of the remaining portion of the original J
-groove weld and shows the location of defective area s identified at nozzles 29 and 30. ADAMS Accession Number ML15022A138
NRC Information Request 2 B. Provide a copy of the following documents (Revisions applicable in 2014) related to letter PNP 2014-100 "Cancellation of Licensee Event Report (LER) 2004
-002, Leak Path Indications Identified in Reactor Pressure Vessel Head Nozzle Penetrations (VHP)
" issued on November 19 th 2014. 1) Latest Revision of the engineering report PLP
-RPT-14-00071. Also provide
- a. List of the non-destructive examination records and data provided to the vendor in support of th is report. b. List of the applicable operating experience records (NRC information notices, Generic Letters, Bulletins, Orders, Licensee Event Reports and industry reports) reviewed by the vendor or site staff in support of this report and identify where this list of operating experience documents reviewed was recorded.
- 2) Any additional evaluations supporting the site decision to cancel LER 2004-002. 3) Applicable site procedure(s) with guidance for revising completed cause evaluation s and retraction of LERs.
- 4) List of prio r Condition Reports (and completed corrective actions) and completed cause evaluations affected by the new cause determination (e.g. embedded welding indications) identified in PLP
-RPT-14-0071 and as discussed in letter PNP 2014-100. 5) Site Quality Assurance Program Manual and the supporting referenced industry standard that define a significant condition adverse to quality such as NQA
-1 "Quality Assurance Requirements for Nuclear Facility Applications."
- 6) Site procedures that implement the Quality Assurance Program Manual related to the corrective action program which include the site procedures that:
- a. Contain a definition of a significant condition adverse to quality.
- b. Contain instructions for identification and classification of conditions adverse to quality and significant conditions adverse to quality.
- c. Contain instructions related to investigations to identify the cause(s) of significant conditions adverse to quality.