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Cook 50.54(f) SPRA Submittal - Completeness Review Done and Path Forward ML19333B8042019-11-29029 November 2019 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Acceptance Review for LAR to Adopt TSTF-569 (L-2019-LLA-0248) ML19309F9212019-11-0505 November 2019 Request for Eportal Access for Audit Review of the DC Cook SPRA Supporting Documents ML19270E7372019-09-26026 September 2019 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Acceptance Review for LAR to Adopt TSTF-421, Reactor Coolant Pump Flywheel Inspection Program ML19207A4642019-07-26026 July 2019 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Acceptance Review for LAR to Delete Diesel Generator Load Test Resistor Banks ML19204A0962019-07-23023 July 2019 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Request for Additional Information Related to Unit 2 Leak Before Break Analysis and Deletion of Containment Humidity Monitors for Unit Nos. 1 and 2 ML19211C3032019-07-0303 July 2019 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 & 2 - Request for Additional Information Related to LAR to Address NSAL-15-1 ML19175A3032019-06-24024 June 2019 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit No. 2 - Acceptance Review for LAR to Revise Battery Monitoring and Maintenance TS ML19092A4802019-04-0202 April 2019 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Acceptance Review for LAR to Adopt TSTF-563 ML19092A4792019-04-0202 April 2019 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Acceptance Review for LAR to Address Issues Identified in Westinghouse Document NSAL-15-1 2024-08-01
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1 NRR-PMDAPEm Resource From: dmburgoyne@aep.com Sent: Thursday, January 10, 2013 2:18 PM To: Wengert, Thomas Cc: hletheridge@aep.com
Subject:
Fw: DC Cook U2 - Review of 2012 SG Tube Inspection Report (TAC No. ME9720)
Good afternoon, In December you sent questions to us regarding the U2 SG Tube Inspection Report. Due to the holidays and vacations, we were unable to schedule a conference call; however, the lead for the technical organization drafted the following responses to the questions. If you would still like to have a conference call, please let me know and we will get that arranged. 1. In the SG tube inspection report the licensee stated that secondary side inspections were performed in all four SGs, and then described the scope of inspections. When discussing the scope of inspection, you specifically discussed SG23. Please clarify which inspections were performed in each SG and which were limited to just SG 23.
Response: Visual inspection of the divider lane and annulus region at the top of the tubesheet was performed in all four steam generators. Select inner bundle passes i.e. inserting a remote video probe into the tube bundle at the top of the tubesheet was also performed in all four SGs, primarily to examine the sludge pile region. The reference to SG 23 was intended to denote that this was the only steam generator in which FOSAR (foreign object search and retrieval) efforts were performed. The need for FOSAR resulted from two new possible loose part signals that were detected during the eddy current inspection, both in SG 23. As a result, FOSAR was performed to examine these specific locations.
A sludge rock was found in one location and nothing was found at the second location. The sludge rock could not be removed and was dispositioned to be left in service. Bounding eddy current examinations were performed in these regions and no additional possible loose part signals were identified. No tube wear was detected at the location of the possible loose part signals nor in any of the bounding tubes examined.
- 2. In a response to a request for additional information dated August 5, 2008 on the 2007 SG tube inservice inspections (ADAMS Accession No. ML082390706), you reported that an area of minor surface pitting was found on the underside of the primary separator diffuser window (also known as the primary separator intermediate plate assembly) on SG 22. However, in your October 2, 2012, letter you indicated that steam drum inspections performed in two SGs during the previous inspection identified no degradation or abnormal conditions. Please clarify.
Response:
The minor pitting was reported on SG 22 during the previous inspection as described above. Phrasing in our October 2, 2012 letter should have denoted this condition and clarified that no significant degradation had previously been noted during steam drum inspections. Due to the inconsequential nature of the pitting, it was not considered a degradation mechanism of concern nor an abnormal condition on a steam generator that has been in service since 1989.
Thank you, Danielle Burgoyne Licensing Activity Coordinator Donald C. Cook Nuclear Plant Phone: 269.466.2871
2
Forwarded by Helen L Etheridge/BC1/AEPIN on 12/19/2012 08:25 AM -----
"Wengert, Thomas" <Thomas.Wengert@nrc.gov>
12/18/2012 11:29 AM To"hletheridge@aep.com" <hletheridge@aep.com>
cc"mkscarpello@aep.com" <mkscarpello@aep.com>, "jrwaters@aep.com" <jrwaters@aep.com>SubjectDC Cook U2 - Review of 2012 SG Tube Inspection Report (TAC No. ME9720)
Helen, The staff in the NRC's Division of Engineering are reviewing your October 2, 2012, submittal concerning the 2012 Steam Generator Tube Inspection Report for DC Cook Unit 2 (ADAMS Accession No. ML12284A278) and would like clarification of the submittal as follows:
- 1. In the SG tube inspection report the licensee stated that secondary side inspections were performed in all four SGs, and then described the scope of inspections. When discussing the scope of inspection, you specifically discussed SG23. Please clarify which inspections were performed in each SG and which were limited to just SG 23.
- 2. In a response to a request for additional information dated August 5, 2008 on the 2007 SG tube inservice inspections (ADAMS Accession No. ML082390706), you reported that an area of minor surface pitting was found on the underside of the primary separator diffuser window (also known as the primary separator intermediate plate assembly) on SG 22. However, in your October 2, 2012, letter you indicated that steam drum inspections performed in two SGs during the previous inspection identified no degradation or abnormal conditions. Please clarify.
DC Cook can provide a response to these clarification questions either by e-mail or a phone call, whichever you prefer. The NRC staff will document the response in our steam generator report review.
Please contact me if you have questions or if you would like to have a conference call with the NRC staff to clarify.
Regards, Tom Wengert Project Manager - DC Cook and Prairie Island USNRC NRR/DORL/LPL3-1 (301) 415-4037
This e-mail message and all attachments transmitted with it from the Nuclear Generation Group of American Electric Power are for the sole use of the intended recipient(s) and may contain confidential and privileged information. Any unauthorized review, use, disclosure or distribution is prohibited. If you are not the intended recipient, please contact the sender by reply e-mail and destroy all copies of the original message.
Hearing Identifier: NRR_PMDA Email Number: 575 Mail Envelope Properties (OFCF168FF0.3AD2A631-ON85257AEF.006979B5-85257AEF.006A075E)
Subject:
Fw: DC Cook U2 - Review of 2012 SG Tube Inspection Report (TAC No. ME9720) Sent Date: 1/10/2013 2:18:09 PM Received Date: 1/10/2013 2:19:06 PM From: dmburgoyne@aep.com Created By: dmburgoyne@aep.com Recipients: "hletheridge@aep.com" <hletheridge@aep.com> Tracking Status: None "Wengert, Thomas" <Thomas.Wengert@nrc.gov> Tracking Status: None
Post Office: aep.com Files Size Date & Time MESSAGE 5622 1/10/2013 2:19:06 PM
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