ML17304B185
| ML17304B185 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 10/31/2017 |
| From: | Robert Schaaf Plant Licensing Branch II |
| To: | Wells R Tennessee Valley Authority |
| References | |
| Download: ML17304B185 (4) | |
Text
NRR-PMDAPEm Resource From: Schaaf, Robert Sent: Tuesday, October 31, 2017 1:36 PM To: Wells, Russell Douglas Cc: Hulvey, Kimberly Dawn; Schrull, Edward Dustin (edschrull@tva.gov); Nadel, Jared; Saba, Farideh
Subject:
Watts Bar, Unit 2 - Upcoming Steam Generator Tube Inservice Inspection Attachments: SG Phone Call Discussion Points.pdf
- Russ, Inservice inspections of steam generator (SG) tubes play a vital role in assuring SG tube integrity. As we discussed, a telephone conference call has been arranged with members of the Tennessee Valley Authority staff to discuss the ongoing results of the SG tube inspections to be conducted during the ongoing Watts Bar Nuclear Plant, Unit 2, refueling outage. This call should occur after the majority of the tubes have been inspected, but before the SG inspection activities have been completed. A list of discussion points to facilitate this call is enclosed.
The NRC staff will document a 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 301-415-6020.
- Regards, Robert G. Schaaf Robert G. Schaaf Senior Project Manager, Watts Bar/Bellefonte Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop O-8B1A Washington, DC 20555 301-415-6020 (o)
Robert.Schaaf@nrc.gov 1
Hearing Identifier: NRR_PMDA Email Number: 3808 Mail Envelope Properties (Robert.Schaaf@nrc.gov20171031133500)
Subject:
Watts Bar, Unit 2 - Upcoming Steam Generator Tube Inservice Inspection Sent Date: 10/31/2017 1:35:53 PM Received Date: 10/31/2017 1:35:00 PM From: Schaaf, Robert Created By: Robert.Schaaf@nrc.gov Recipients:
"Hulvey, Kimberly Dawn" <kdhulvey@tva.gov>
Tracking Status: None "Schrull, Edward Dustin (edschrull@tva.gov)" <edschrull@tva.gov>
Tracking Status: None "Nadel, Jared" <Jared.Nadel@nrc.gov>
Tracking Status: None "Saba, Farideh" <Farideh.Saba@nrc.gov>
Tracking Status: None "Wells, Russell Douglas" <rdwells0@tva.gov>
Tracking Status: None Post Office:
Files Size Date & Time MESSAGE 1325 10/31/2017 1:35:00 PM SG Phone Call Discussion Points.pdf 102558 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received:
STEAM GENERATOR TUBE INSPECTION DISCUSSION POINTS The following discussion points have been prepared to facilitate the conference call arranged with the licensee to discuss the results of the steam generator tube inspections to be conducted during the RQJRLQJ:DWWV%DU8QLWIDOOUHIXHOLQJRXWDJHThis conference call is scheduled to occur towards the end of the planned SG tube inspections, but before the OLFHQVHH completes the inspections and repairs.
The NRC staff plans to document a summary of the conference call as well as any material that is provided in support of the call.
- 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 ENCLOSURE
- 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.