Letter Sequence RAI |
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TAC:ME9682, (Approved, Closed) TAC:ME9683, (Approved, Closed) TAC:ME9684, (Approved, Closed) TAC:ME9685, (Approved, Closed) TAC:ME9692, (Approved, Closed) TAC:ME9693, (Approved, Closed) |
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MONTHYEARRS-12-151, Fifth Interval Lnservice Inspection Program Plan and Relief Requests2012-09-28028 September 2012 Fifth Interval Lnservice Inspection Program Plan and Relief Requests Project stage: Request RS-12-150, Fifth Interval Inservice Inspection Program Plan and Relief Requests2012-09-28028 September 2012 Fifth Interval Inservice Inspection Program Plan and Relief Requests Project stage: Request RS-12-202, Supplement to the Dresden Nuclear Power Station Fifth Inservice Inspection Interval Relief Request I5R-012012-11-19019 November 2012 Supplement to the Dresden Nuclear Power Station Fifth Inservice Inspection Interval Relief Request I5R-01 Project stage: Supplement ML12331A2772012-11-28028 November 2012 Supplemental Information Needed for Acceptance of RLA, I5R-02 Project stage: Acceptance Review RS-12-203, Supplement to Quad Cities Nuclear Power Station Fifth Inservice Inspection Interval Relief Request I5R-012012-11-28028 November 2012 Supplement to Quad Cities Nuclear Power Station Fifth Inservice Inspection Interval Relief Request I5R-01 Project stage: Supplement RS-12-205, Supplement to Fifth Inservice Inspection Interval Relief Request I5R-022012-11-28028 November 2012 Supplement to Fifth Inservice Inspection Interval Relief Request I5R-02 Project stage: Supplement ML12348A8302012-12-13013 December 2012 NRR E-mail Capture - Acceptance Review of Dresden, Units 2 and 3, Relief Request I5R-02 Project stage: Acceptance Review ML12348A4272012-12-21021 December 2012 Request for Additional Information Related to the Request for Alternative I5R-03 Project stage: RAI RS-13-005, Supplemental to Dresden and Quad Cities Fifth Inservice Inspection Interval Relief Request I5R-032013-01-10010 January 2013 Supplemental to Dresden and Quad Cities Fifth Inservice Inspection Interval Relief Request I5R-03 Project stage: Supplement RS-13-040, Supplement to the Dresden Nuclear Power Station Fifth Inservice Inspection Interval Relief Request I5R-042013-01-24024 January 2013 Supplement to the Dresden Nuclear Power Station Fifth Inservice Inspection Interval Relief Request I5R-04 Project stage: Supplement ML13099A2802013-04-0909 April 2013 NRR E-mail Capture - Finalized Dresden RAI I5R-01 I5R-02 and I5R-07 Project stage: RAI ML13110A0072013-04-19019 April 2013 NRR E-mail Capture - RAI for Dresden Units 2 and 3 Exelon Generation Company, LLC Relief Request Nos. I5R-01, I5R-02, and I5R-07 Docket Numbers 50-237 and 50-249 TAC Nos. ME9682-83, ME9684-85, and ME9692-93 Project stage: RAI ML13115A2322013-04-24024 April 2013 NRR E-mail Capture - Quad Cities Relief Request Nos. I5R-01, I5R-02, and I5R-06 - Request for Additional Information Project stage: RAI ML13123A0852013-05-0202 May 2013 NRR E-mail Capture - Dresden Relief Request No. I5R-02 - Request for Additional Information Project stage: RAI RS-13-147, Additional Information Supporting Fifth Inservice Inspection Interval Relief Requests I5R-01, I5R-02, and I5R-062013-05-30030 May 2013 Additional Information Supporting Fifth Inservice Inspection Interval Relief Requests I5R-01, I5R-02, and I5R-06 Project stage: Request RS-13-107, Supplement to Fifth Inservice Inspection Interval Relief Requests I5R-01, I5R-02, and I5R-072013-06-0303 June 2013 Supplement to Fifth Inservice Inspection Interval Relief Requests I5R-01, I5R-02, and I5R-07 Project stage: Supplement ML13258A0032013-09-30030 September 2013 Safety Evaluation for the Fifth 10-Year Interval Inservice Inspection Relief Request for Exelon Generation Boiling Water Reactor (TAC Nos. ME9682, ME9683, ME9684, ME9685, ME9686, ME9687, ME9688, Etc.) Project stage: Approval ML13260A5852013-09-30030 September 2013 Cover Letter -Safety Evaluation in Support of Request for Relief Associated with the Fifth 10-Year Interval Inservice Inspection Program (TAC Nos. ME9682, ME9683, ME9684, ME9685, ME9686, ME9687, ME9688, Etc Project stage: Approval ML13267A0972013-09-30030 September 2013 Safety Evaluation in Support of Request for Relief Associated with the Fifth 10 Year Interval Inservice Inspection Program Project stage: Approval 2013-01-24
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Category:E-Mail
MONTHYEARML24271A0282024-09-26026 September 2024 E-Mail - Dresden Nuclear Power Station, Unit 1 - Site Visit Request for Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations ML24250A1062024-09-0606 September 2024 NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC - Fleet Request - Proposed Alternative to Utilize Code Case OMN-32 (L-2024-LLR-0030) ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 ML24233A2472024-08-20020 August 2024 Acceptance of Requested Licensing Action Request for Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations ML24176A0232024-06-21021 June 2024 NRR E-mail Capture - Dresden Nuclear Power Station, Units 2 and 3 - Acceptance Review of the Amendment Request to Adopt 10 CFR 50.69 ML24159A0122024-06-0606 June 2024 NRR E-mail Capture - Dresden Nuclear Power Station, Units 2 and 3 - Acceptance of Licensing Amendment to Adopt TSTF-505 and TSTF-591 ML24131A0612024-05-10010 May 2024 NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request - Acceptance of Proposed Alternative to Utilize Code Case OMN-32 (L-2024-LLR-0030) ML24066A0802024-04-0101 April 2024 Email to Christian Williams Decision on the Exemption Request for Dresden Nuclear Power Station Unit 2 and Unit 3 Independent Spent Fuel Storage Installation in Morris, Illinois ML24065A4892024-03-28028 March 2024 Email to Christian Williams Availability of Environmental Assessment for the Exemption Request for Dresden Nuclear Power Station Unit 2 and Unit 3 Independent Spent Fuel Storage Installation in Morris, Illinois ML24078A3772024-03-15015 March 2024 Email to the State of Illinois Requesting Review of the Dresden Exemption Request Environmental Assessment ML24066A0872024-03-0404 March 2024 NRR E-mail Capture - Dresden 2 and 3 - Request for Additional Information for Alternative Request I5R-22 ML24067A1242024-03-0101 March 2024 Email to Christian Williams: Request for Additional Information Regarding Dresden Relief Request Dated February 23, 2024 ML24065A2922024-02-28028 February 2024 2/28/24 Email from Constellation: Clarifying Information Regarding Dresden Relief Request Dated February 23, 2024 ML23339A0882023-12-0404 December 2023 NRR E-mail Capture - NRC Acceptance Review Re Dresden, Units 2 and 3 Request for Relief I5R-22 ML23328A0092023-11-22022 November 2023 Supplement - Dresden Security Rule Exemption Request ISFSI Docket No. Reference (EPID L-2023-LLE-0031) (Email) ML23304A0172023-10-30030 October 2023 NRR E-mail Capture - Final RCI - Constellation Energy Generation, LLC - Dresden 1, 2 & 3 - Exemption from Security Rule (L-2023-LLE-0031) ML23268A0022023-09-22022 September 2023 NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request - Acceptance of License Amendment Request to Adopt TSTF-264-A, Revision 0 ML23264A7992023-09-21021 September 2023 NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC Fleet Request License Amendment Request to Adopt TSTF-580, Revision 1 ML23263A9932023-09-20020 September 2023 NRR E-mail Capture - Dresden Nuclear Power Station, Units 2 and 3 - Acceptance of Licensing Action Submittal Re Amendment to Adopt TSTF-564 ML23163A2292023-06-12012 June 2023 NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request - Acceptance of License Amendment Request to Adopt TSTF-580, Revision 1 ML23052A0652023-02-21021 February 2023 NRR E-mail Capture - Dresden Units 2 and 3 - Request for Additional Information for Alternative Request RV-23H ML23026A0172023-01-23023 January 2023 NRR E-mail Capture - (External_Sender) IEMA Response Action - Request for Comments on the Proposed Issuance of Amendment to Technical Specification 4.3.1 for Dresden Nuclear Power Station, Units 2 and 3 ML23019A0132023-01-12012 January 2023 NRR E-mail Capture - Final RAI Dresden 2 and 3 - License Amendment Pertaining to GNF3 Fuel Transition ML22354A2622022-12-20020 December 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request - Acceptance of Request to Use Certain Provisions of the 2019 Edition of the ASME BPV Code, Section XI ML22325A1212022-11-21021 November 2022 NRR E-mail Capture - NRC Acceptance Review Re Dresden, Units 2 and 3 Request for Relief RV-02D (EPID L-2022-LLR-0075), RV-03 (EPID L-2022-LLR-0076), and RV-23H ML22301A0902022-10-28028 October 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request - Acceptance of License Amendment Request to Adopt TSTF-301, Revision 2 ML22290A0842022-10-13013 October 2022 NRR E-mail Capture - Dresden 2 and 3 - RAI License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies ML22258A1882022-09-15015 September 2022 NRR E-mail Capture - Acceptance Review: Dresden 2 and 3 License Amendment Request to Revise Technical Specification 3.1.4, ML22258A1872022-09-13013 September 2022 NRR E-mail Capture - NRC Acceptance Review Dresden, Units 2 and 3, Amendment Request - Transition to GNF3 Fuel ML22229A0752022-08-16016 August 2022 NRR E-mail Capture - NRC Acceptance Review Dresden, Units 2 and 3 Request for Relief 16R-09 ML22229A0762022-08-16016 August 2022 NRR E-mail Capture - NRC Acceptance Review Dresden, Units 2 and 3 Request for Relief 16R-10 ML22203A0442022-07-21021 July 2022 Request for Additional Information (RAI) ML22200A0782022-07-19019 July 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request to Use Honeywell Mururoa V4F1 R Supplied Air Suits ML22199A2412022-07-18018 July 2022 NRR E-mail Capture - Acceptance Review: Dresden Units 2 and 3 - License Amendment Request New Fuel Vault Storage and SFP Criticality Safety Analysis Methodology ML22199A2422022-07-13013 July 2022 NRR E-mail Capture - Draft RAI Dresden 2 and 3 Proposed Alternative Related to Sblc Nozzle Inspection for the Sixth Inservice Inspection Interval ML22103A2132022-04-12012 April 2022 NRR E-mail Capture - NRC Acceptance Review Dresden, Units 2 and 3 Request for Relief (16R-02) - EPID L-2022-LLR-0038 ML22103A2112022-04-12012 April 2022 NRR E-mail Capture - NRC Acceptance Review Dresden, Units 2 and 3 Request for Relief (16R-01) - EPID L-2022-LLR-0037 ML22041B5362022-02-10010 February 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Request for Additional Information Regarding Fleet License Amendment Request to Adopt TSTF-541 ML22039A2042022-02-0808 February 2022 NRR E-mail Capture - Public Meeting Dresden/Quad Cities - Proposed Alternative to Use ASME Code Case N-921 ML22027A3592022-01-26026 January 2022 U1: CY2022 Inspection Plan, Docket No. 05000010, License No. DPR-2 ML22020A0642022-01-13013 January 2022 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative for Repair of Water Level Instrumentation Partial Penetration Nozzles ML21321A3802021-11-17017 November 2021 NRR E-mail Capture - NRC Acceptance Review of Dresden Nuclear Power Station, Units 2 and 3, Request for Exemption from 10 CFR 2.109(b) ML21301A0672021-10-28028 October 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Acceptance of License Amendment Request to Adopt TSTF-541 ML21256A1902021-09-10010 September 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21252A0482021-09-0707 September 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Fleet Alternative Request for Repair of Water Level Instrumentation Partial Penetration Nozzles ML21244A4012021-08-10010 August 2021 (Final) Request for Information (RAI) Dresden, Units 1, 2, 3, and ISFSI Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR 50 Appendix E ML21215A3502021-08-0303 August 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Acceptance of License Amendment Request to Adopt TSTF-554 ML21190A0192021-07-0808 July 2021 NRR E-mail Capture - Exelon Fleet - Request for Additional Information Regarding Adoption of TSTF-582 and TSTF-583-T ML21154A0142021-05-28028 May 2021 NRR E-mail Capture - Extension of Comment Period for the Exelon Generation Company, LLC License Transfer Application ML21154A0132021-05-28028 May 2021 NRR E-mail Capture - Extension of Comment Period for the Exelon Generation Company, LLC License Transfer Application 2024-09-06
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1 NRR-PMDAPEm Resource From: Mozafari, Brenda Sent: Tuesday, April 09, 2013 12:46 PM To: Mitchel.Mathews@exeloncorp.com
Subject:
Finalized Dresden RAI I5R-01 I5R-02 and I5R-07 (3).docx Attachments:
Draft Dresden RAI I5R-01 I5R-02 and I5R-07 (3).docx Mitchel, By letter to the U.S. Nuclear Regulatory Commission (NRC) dated September 28, 2012 (Agencywide Documents Access and management System (ADAMS) Accession No. ML12275A069), as supplemented by letter dated November 19, 2012 (ADAMS) Accession No. ML123250319), Exelon Generation Company, LLC (the licensee) submitted proposed relief requests (RR) I5R-01, I5R-02, and I5R-07. The NRC staff determined that the following additional information is necessary to complete the review of RR I5R-01, I5R-02, and I5R-07.
Your response was received on April 1, 2013, supporting the date we agreed on by phone March 22, 2013.
Based on the NRC staff's review of Relief Request I5R-01:
- 1. Discuss in the Relief Request why the proposed alternative provides reasonable assurance of structural integrity or leak tightness of the subject component(s).
- 2. Discuss in the Relief Request how the specified requirements of this section would result in hardship or unusual difficulty without a compensating increase in the level of quality and quality and safety.
- 3. Provide a technical basis as to why the ultrasonic testing is not required.
Based on the staff's review of Relief Request I5R-02:
- 1. Do the augmented inspection programs for IGSCC Category B-G (Generic Letter 88-01), service water integrity (Generic Letter 89-13), FAC (Generic Letter 89-09), and high-energy line break (HELB)(USNRC Branch Technical Position MEB 3-1) remain unaffected (as described in the initial DNPS RI-ISI submittal dated October 18, 2000) by the RI-ISI program developed for the fifth interval?
- 2. Are the inspection locations in the DNPS RI-ISI programs that have been developed for the fifth 10-year interval the same locations as those in the fourth interval RI-ISI programs approved in the NRC staff's September 4, 2003, safety evaluation? If not, please summarize the changes to the program and what caused those changes.
- 3. If there are changes in the inspection locations for the DNPS fifth 10-year interval RI-ISI programs please provide information for the fifth interval program regarding:
examinations/system/components/degradation mechanisms/class, etc. similar to that provided in Tables 2, 3, 4, 5 and 6 of the original submittal of the RI-ISI program for the DNPS third 10-year inservice inspection interval dated October 18, 2000 (ADAMS Accession No. ML003762371).
Based on the staff's review of Relief Request I5R-07:
- 1. The staff requests that the licensee identify whether there are any furnace-sensitized stainless steel vessel attachment welds associated with the RVI components at the Dresden Nuclear Power Station, Units 2 and 3. It is requested that the licensee provide an explanation regarding the type of inspection program and any additional augmented inspection progr am that are implemented for any existing furnace-sensitized stainless steel attachment welds in these boiling water reactor (BWR) units.
2 2. The staff requests that the licensee confirm whether NUREG-0619, "BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking," will be used for the inspection of feedwater sparger tee welds and feedwater sparger piping brackets.
- 3. Section 4.1 item 5 of the BWRVIP-100-A report, "Updated Assessment of the Fracture Toughness of Irradiated Stainless Steel for BWR Core Shrouds," states that fracture toughness values of stainless steel materials that are exposed to a neutron fluence value greater than 1 X 10 21 n/cm 2 (E > 1 MeV) are lower than those used in Appendix C of the BWRVIP-76 report, "BWR Core Shroud Inspection and Flaw Evaluation Guidelines." Identify whether the core shroud welds and base materials will be exposed to a neutron fluence value greater than 1 X 10 21 n/cm 2 (E > 1 MeV) during the current ISI interval. Since the inspection frequency in the BWRVIP-76 report is based on fracture toughness values which are not consistent with the BWRVIP-100-A report, the staff requests that the licensee address the following issue:
The inspection frequency and strategy that are specified in Section 3 of the BWRVIP-76 report require further evaluation taking into account the lower fracture toughness values that are specified in the BWRVIP-100-A report.
- 4. Dresden and Quad Cities (D/QC) Safety Evaluation Report, "NUREG-1796, Related to the License Renewal of the Dresden Nuclear Power Station, Units 2 and 3 and Quad Cities Nuclear Power Station, Units 1 and 2," License Renewal Commitment (LRA) #9 in Appendix A of NUREG-1796 states that the licensee should implement the staff approved AMP for the steam dryers at the D/QC units. In July 2009, the BWRVIP issued a staff approved topical report BWRVIP-139-A, "BWR Vessel and Internals Project, Steam Dryer Inspection and Flaw Evaluation Guidelines." The staff requests that the licensee confirm that it will comply with the guidelines addressed in the BWRVIP-139-A report as per LRA #9 in NUREG-1796.
- 5. Consistent with the LRA commitment #9, with respect to the AMP related to the top guide, the licensee should confirm that it will comply with the inspection guidelines addressed in the BWRVIP-26-A and BWRVIP-183 reports.
Thank you for your support. This email will be placed in ADAMS as an official agency record for reference.
Brenda L. Mozafari Senior Project Manager, NRR/DORL U.S. Nuclear Regulatory Commission
301-415-2020 email: brenda.mozafari@nrc.gov
Hearing Identifier: NRR_PMDA Email Number: 662 Mail Envelope Properties (Brenda.Mozafari@nrc.gov20130409124600)
Subject:
Finalized Dresden RAI I5R-01 I5R-02 and I5R-07 (3).docx Sent Date: 4/9/2013 12:46:25 PM Received Date: 4/9/2013 12:46:00 PM From: Mozafari, Brenda Created By: Brenda.Mozafari@nrc.gov Recipients: "Mitchel.Mathews@exeloncorp.com" <Mitchel.Mathews@exeloncorp.com> Tracking Status: None Post Office: Files Size Date & Time MESSAGE 5626 4/9/2013 12:46:00 PM Draft Dresden RAI I5R-01 I5R-02 and I5R-07 (3).docx 26998 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: Recipients Received: OFFICE OF NUCLEAR REACTOR REGULATION REQUEST FOR ADDITIONAL INFORMATION FOR DRESDEN UNITS 2 and 3 EXELON GENERATION COMPANY, LLC RELIEF REQUEST NOS. I5R-01, I5R-02, and I5R-07 DOCKET NUMBERS 50-237 and 50-249 TAC Nos. ME9682-83, ME9684-85, and ME9692-93
By letter to the U.S. Nuclear Regulatory Commission (NRC) dated September 28, 2012 (Agencywide Documents Access and management System (ADAMS) Accession No. ML12275A069), as supplemented by letter dated November 19, 2012 (ADAMS) Accession No. ML123250319), Exelon Generation Company, LLC (the licensee) submitted proposed relief requests (RR) I5R-01, I5R-02, and I5R-07. The NRC staff has determined that the following additional information is necessary to complete the review of RR I5R-01, I5R-02, and I5R-07.
Based on the staff's review of Relief Request I5R-01:
- 1. Discuss in the Relief Request why the proposed alternative provides reasonable assurance of structural integrity or leak tightness of the subject component(s).
- 2. Discuss in the Relief Request how the specified requirements of this section would result in hardship or unusual difficulty without a compensating increase in the level of quality
and quality and safety.
- 3. Provide a technical basis as to why the ultrasonic testing is not required.
Based on the staff's review of Relief Request I5R-02:
- 1. Do the augmented inspection programs for IGSCC Category B-G (Generic Letter 88-01), service water integrity (Generic Letter 89-13), FAC (Generic Letter 89-09), and high-energy line break (HELB)(USNRC Branch Technical Position MEB 3-1) remain unaffected (as described in the initial DNPS RI-ISI submittal dated October 18, 2000) by the RI-ISI program developed for the fifth interval?
- 2. Are the inspection locations in the DNPS RI-ISI programs that have been developed for the fifth 10-year interval the same locations as those in the fourth interval RI-ISI programs approved in the NRC staff's September 4, 2003, safety evaluation? If not, please summarize the changes to the program and what caused those changes.
- 3. If there are changes in the inspection locations for the DNPS fifth 10-year interval RI-ISI programs please provide information for the fifth interval program regarding: examinations/system/components/degradation mechanisms/class, etc. similar to that provided in Tables 2, 3, 4, 5 and 6 of the original submittal of the RI-ISI program for the DNPS third 10-year inservice inspection interval dated October 18, 2000 (ADAMS Accession No. ML003762371).
Based on the staff's review of Relief Request I5R-07:
- 1. The staff requests that the licensee identify whether there are any furnace-sensitized stainless steel vessel attachment welds associated with the RVI components at the Dresden Nuclear Power Station, Units 2 and 3. It is requested that the licensee provide an explanation regarding the type of inspection program and any additional augmented inspection program that are implemented for any existing furnace-sensitized stainless steel attachment welds in these boiling water reactor (BWR) units.
- 2. The staff requests that the licensee confirm whether NUREG-0619, "BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking," will be used for the inspection of feedwater sparger tee welds and feedwater sparger piping brackets.
- 3. Section 4.1 item 5 of the BWRVIP-100-A report, "Updated Assessment of the Fracture Toughness of Irradiated Stainless Steel for BWR Core Shrouds," states that fracture toughness values of stainless steel materials that are exposed to a neutron fluence value greater than 1 X 10 21 n/cm 2 (E > 1 MeV) are lower than those used in Appendix C of the BWRVIP-76 report, "BWR Core Shroud Inspection and Flaw Evaluation Guidelines." Identify whether the core shroud welds and base materials will be exposed to a neutron fluence value greater than 1 X 10 21 n/cm 2 (E > 1 MeV) during the current ISI interval. Since the inspection frequency in the BWRVIP-76 report is based on fracture toughness values which are not consistent with the BWRVIP-100-A report, the staff requests that the licensee address the following issue:
The inspection frequency and strategy that are specified in Section 3 of the BWRVIP-76 report require further evaluation taking into account the lower fracture toughness values that are specified in the BWRVIP-100-A report.
- 4. Dresden and Quad Cities (D/QC) Safety Evaluation Report, "NUREG-1796, Related to the License Renewal of the Dresden Nuclear Power Station, Units 2 and 3 and Quad Cities Nuclear Power Station, Units 1 and 2," License Renewal Commitment (LRA) #9 in Appendix A of NUREG-1796 states that the licensee should implement the staff approved AMP for the steam dryers at the D/QC units. In July 2009, the BWRVIP issued a staff approved topical report BWRVIP-139-A, "BWR Vessel and Internals Project, Steam Dryer Inspection and Flaw Evaluation Guidelines." The staff requests that the licensee confirm that it will comply with the guidelines addressed in the BWRVIP-139-A report as per LRA #9 in NUREG-1796.
- 5. Consistent with the LRA commitment #9, with respect to the AMP related to the top guide, the licensee should confirm that it will comply with the inspection guidelines addressed in the BWRVIP-26-A and BWRVIP-183 reports.