ML19288A012
| ML19288A012 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 10/11/2019 |
| From: | Martha Barillas NRC/NRR/DORL/LPL2-2 |
| To: | Hamilton T, Zaremba A Duke Energy Carolinas |
| References | |
| L-2019-LRO-0078 | |
| Download: ML19288A012 (4) | |
Text
1 NRR-DRMAPEm Resource From:
Barillas, Martha Sent:
Friday, October 11, 2019 9:00 AM To:
Tanya.Hamilton@duke-energy.com; 'Arthur.Zaremba@duke-energy.com'; Earp Jr.,
Dennis Cc:
Shoop, Undine; Barillas, Martha; Hood, Tanya; Zeiler, John; Davis, Bradley
Subject:
Shearon Harris Nuclear Power Plant, Unit 1-Upcoming Steam Generator Tube Inservice Inspection Attachments:
STEAM GENERATOR TUBE INSPECTION DISCUSSION POINTS.docx Ms. Hamilton, Inservice inspections of steam generator (SG) tubes play a vital role in assuring SG tube integrity. A telephone conference call has been arranged with members of your staff to discuss the ongoing results of the SG tube inspections to be conducted during the upcoming cycle 23 Shearon Harris Nuclear Power Plant, Unit 1 refueling outage. This call will occur after the majority of the tubes have been inspected, but before the SG inspection activities have been completed.
Enclosed is a list of discussion points to facilitate this call.
The NRC staff will document a publicly available summary of the conference call, including any material that you provide to the NRC staff in support of the call.
Should you have any questions, you can contact me at 301-415-2760.
Sincerely, Martha Barillas-Project Manager NRR/Division of Operating Reactor Licensing US Nuclear Regulatory Commission 301-415-2760 DOCKET 50-400
Enclosure:
Steam Generator Tube Inspection Discussion Points
Hearing Identifier:
NRR_DRMA Email Number:
260 Mail Envelope Properties (SN6PR09MB2765617AB2202BA969B5E65EF2970)
Subject:
Shearon Harris Nuclear Power Plant, Unit 1-Upcoming Steam Generator Tube Inservice Inspection Sent Date:
10/11/2019 9:00:19 AM Received Date:
10/11/2019 9:00:00 AM From:
Barillas, Martha Created By:
Martha.Barillas@nrc.gov Recipients:
"Shoop, Undine" <Undine.Shoop@nrc.gov>
Tracking Status: None "Barillas, Martha" <Martha.Barillas@nrc.gov>
Tracking Status: None "Hood, Tanya" <Tanya.Hood@nrc.gov>
Tracking Status: None "Zeiler, John" <John.Zeiler@nrc.gov>
Tracking Status: None "Davis, Bradley" <Bradley.Davis@nrc.gov>
Tracking Status: None "Tanya.Hamilton@duke-energy.com" <Tanya.Hamilton@duke-energy.com>
Tracking Status: None
"'Arthur.Zaremba@duke-energy.com'" <Arthur.Zaremba@duke-energy.com>
Tracking Status: None "Earp Jr., Dennis" <Dennis.Earp@duke-energy.com>
Tracking Status: None Post Office:
SN6PR09MB2765.namprd09.prod.outlook.com Files Size Date & Time MESSAGE 1068 10/11/2019 9:00:00 AM STEAM GENERATOR TUBE INSPECTION DISCUSSION POINTS.docx 23741 Options Priority:
Standard Return Notification:
No Reply Requested:
No Sensitivity:
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Recipients Received:
STEAM GENERATOR TUBE INSPECTION DISCUSSION POINTS The following discussion points have been prepared to facilitate the conference call arranged to discuss the results of the steam generator tube inspections to be conducted during the upcoming Cycle 23 Refueling Outage. This conference call is scheduled to occur towards the end of the planned SG tube inspections, but before the unit completes the inspections and repairs.
- 1. Discuss any trends in the amount of primary-to-secondary leakage observed during the recently completed cycle.
- 2. Discuss whether any secondary side pressure tests were performed during the outage and the associated results.
- 3. Discuss any exceptions taken to the industry guidelines.
- 4. For each steam generator, provide a description of the inspections performed including the areas examined and the probes used (e.g., dents/dings, sleeves, expansion-transition, U-bends with a rotating probe), the scope of the inspection (e.g., 100% of dents/dings greater than 5 volts and a 20% sample between 2 and 5 volts), and the expansion criteria.
- 5. For each area examined (e.g., tube supports, dent/dings, sleeves, etc), provide a summary of the number of indications identified to-date for each degradation mode (e.g., number of circumferential primary water stress corrosion cracking indications at the expansion transition).
For the most significant indications in each area, provide an estimate of the severity of the indication (e.g., provide the voltage, depth, and length of the indication). In particular, address whether tube integrity (structural and accident induced leakage integrity) was maintained during the previous operating cycle. In addition, discuss whether any location exhibited a degradation mode that had not previously been observed at this location at this unit (e.g., observed circumferential primary water stress corrosion cracking at the expansion transition for the first time at this unit).
- 6. Describe repair/plugging plans.
- 7. Describe in-situ pressure test and tube pull plans and results (as applicable and if available).
- 8. Discuss the following regarding loose parts:
what inspections are performed to detect loose parts a description of any loose parts detected and their location within the SG (including the source or nature of the loose part, if known) if the loose parts were removed from the SG indications of tube damage associated with the loose parts
- 9. Discuss the scope and results of any secondary side inspection and maintenance activities (e.g., in-bundle visual inspections, feedring inspections, sludge lancing, assessing deposit loading, etc).
- 10. Discuss any unexpected or unusual results.
- 11. Provide the schedule for steam generator-related activities during the remainder of the current outage.