ML11277A286
| ML11277A286 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 10/04/2011 |
| From: | Patrick Boyle Division of Operating Reactor Licensing |
| To: | Shaub T Dominion Energy Co |
| References | |
| Download: ML11277A286 (4) | |
Text
1 NRR-PMDAPEm Resource From:
Boyle, Patrick Sent:
Tuesday, October 04, 2011 12:44 PM To:
Tom Shaub; 'david.sommers@dom.com'; 'gary.d.miller@dom.com' Cc:
Martin, Robert
Subject:
Conference call to discuss: North Anna Nuclear Power Plant, Unit 2, Steam Generator Tube In-service Inspection
2 Routine outage call for North Anna Nuclear Power Plant In-service inspections of steam generator (SG) tubes play a vital role in assuring SG tube integrity. A telephone conference call has been arranged to discuss the results of the recently completed SG tube inspections at the North Anna Nuclear Power Plant Unit 2. Enclosed is a list of discussion points to facilitate this call.
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.
Docket No.50-339 Steam Generator Tube Inspection Discussion Points STEAM GENERATOR TUBE INSPECTION DISCUSSION POINTS
- 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).
3
- 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
Hearing Identifier:
NRR_PMDA Email Number:
166 Mail Envelope Properties (Patrick.Boyle@nrc.gov20111004124300)
Subject:
Conference call to discuss: North Anna Nuclear Power Plant, Unit 2, Steam Generator Tube In-service Inspection Sent Date:
10/4/2011 12:43:58 PM Received Date:
10/4/2011 12:43:00 PM From:
Boyle, Patrick Created By:
Patrick.Boyle@nrc.gov Recipients:
"Martin, Robert" <Robert.Martin@nrc.gov>
Tracking Status: None "Tom Shaub" <tom.shaub@dom.com>
Tracking Status: None
"'david.sommers@dom.com'" <david.sommers@dom.com>
Tracking Status: None
"'gary.d.miller@dom.com'" <gary.d.miller@dom.com>
Tracking Status: None Post Office:
Files Size Date & Time MESSAGE 3199 10/4/2011 12:43:00 PM Options Priority:
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