ML050630434
| ML050630434 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 03/15/2005 |
| From: | Dan Collins NRC/NRR/DLPM/LPD1 |
| To: | Levis W Public Service Enterprise Group |
| Collins D S, NRR/DLPM, 415-1427 | |
| References | |
| TAC MC6279 | |
| Download: ML050630434 (6) | |
Text
March 15, 2005 Mr. William Levis Senior Vice President & Chief Nuclear Officer PSEG Nuclear LLC - X04 Post Office Box 236 Hancocks Bridge, NJ 08038
SUBJECT:
SALEM NUCLEAR GENERATING STATION, UNIT NO. 2 - UPCOMING STEAM GENERATOR TUBE INSERVICE INSPECTION (TAC NO. MC6279)
Dear Mr. Levis:
Inservice inspections (ISIs) of steam generator (SG) tubes play a vital role in assuring that adequate structural integrity of the tubes is maintained. As required by the plant Technical Specifications, reporting requirements range from submitting a special report, within 15 days following completion of each ISI of SG tubes, that identifies the number of tubes plugged and/or repaired; to submitting a special report, within 12 months following completion of the inspection, that provides complete results of the SG tube ISI. The special report containing the complete results shall include the following:
- 1. Number and extent of tubes inspected.
- 2. Location and percent of wall-thickness penetration for each indication of an imperfection.
- 3. Identification of tubes plugged and/or repaired.
A phone conference has been arranged with members of your staff to discuss the ongoing results of the SG tube inspections to be conducted during the upcoming Salem Nuclear Generating Station Unit 2 No. refueling outage. This phone call will occur after the majority of the tubes have been inspected, but before the SG inspection activities have been completed.
Attached is a list of discussion points to facilitate this phone conference.
The staff plans to document a brief summary of the conference call, as well as any material that you may have provided to the staff in support of the call.
Sincerely,
/RA/
Daniel Collins, Senior Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-311
Enclosures:
As stated cc w/encls: See next page
Mr. William Levis Senior Vice President & Chief Nuclear Officer PSEG Nuclear LLC - X04 Post Office Box 236 Hancocks Bridge, NJ 08038
SUBJECT:
SALEM NUCLEAR GENERATING STATION, UNIT NO. 2 - UPCOMING STEAM GENERATOR TUBE INSERVICE INSPECTION (TAC NO. MC6279)
Dear Mr. Levis:
Inservice inspections (ISIs) of steam generator (SG) tubes play a vital role in assuring that adequate structural integrity of the tubes is maintained. As required by the plant Technical Specifications, reporting requirements range from submitting a special report, within 15 days following completion of each ISI of SG tubes, that identifies the number of tubes plugged and/or repaired; to submitting a special report, within 12 months following completion of the inspection, that provides complete results of the SG tube ISI. The special report containing the complete results shall include the following:
- 1. Number and extent of tubes inspected.
- 2. Location and percent of wall-thickness penetration for each indication of an imperfection.
- 3. Identification of tubes plugged and/or repaired.
A phone conference has been arranged with members of your staff to discuss the ongoing results of the SG tube inspections to be conducted during the upcoming Salem Nuclear Generating Station Unit 2 No. refueling outage. This phone call will occur after the majority of the tubes have been inspected, but before the SG inspection activities have been completed.
Attached is a list of discussion points to facilitate this phone conference.
The staff plans to document a brief summary of the conference call, as well as any material that you may have provided to the staff in support of the call.
Sincerely,
/RA/
Daniel Collins, Senior Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-311
Enclosures:
As stated cc w/encls: See next page DISTRIBUTION DRoberts ECobey, RGN-I DCollins KKarwoski MMurphy PUBLIC PDI-2 Reading CRaynor CHolden Assession Number: ML050630434 OFFICE PDI-2/PM PDI-2/LA PDI-2/SC NAME DCollins CRaynor DRoberts DATE 3/8/05 3/7/05 3/14/05 OFFICIAL RECORD COPY
Salem Nuclear Generating Station, Unit No. 2 cc:
Mr. Michael H. Brothers Vice President - Nuclear Assessments PSEG Nuclear P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. Michael Gallagher Vice President - Eng/Tech Support PSEG Nuclear P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. Thomas P. Joyce Site Vice President - Salem PSEG Nuclear P.O. Box 236 Hancocks Bridge, NJ 08038 Ms. Christina L. Perino Director - Regulatory Assurance PSEG Nuclear - N21 P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. George H. Gellrich Plant Support Manager PSEG Nuclear P.O. Box 236 Hancocks Bridge, NJ 08038 Jeffrie J. Keenan, Esquire PSEG Nuclear - N21 P.O. Box 236 Hancocks Bridge, NJ 08038 Ms. R. A. Kankus Joint Owner Affairs PECO Energy Company Nuclear Group Headquarters KSA1-E 200 Exelon Way Kennett Square, PA 19348 Lower Alloways Creek Township c/o Mary O. Henderson, Clerk Municipal Building, P.O. Box 157 Hancocks Bridge, NJ 08038 Dr. Jill Lipoti, Asst. Director Radiation Protection Programs NJ Department of Environmental Protection and Energy CN 415 Trenton, NJ 08625-0415 Brian Beam Board of Public Utilities 2 Gateway Center, Tenth Floor Newark, NJ 07102 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Senior Resident Inspector Salem Nuclear Generating Station U.S. Nuclear Regulatory Commission Drawer 0509 Hancocks Bridge, NJ 08038 Mr. Carl J. Fricker Plant Manager PSEG Nuclear - N21 P.O. Box 236 Hancocks Bridge, NJ 08038
Enclosure STEAM GENERATOR TUBE INSPECTION DISCUSSION POINTS PREPARED BY THE OFFICE OF NUCLEAR REACTOR REGULATION PSEG NUCLEAR SALEM NUCLEAR GENERATING STATION, UNIT NO. 2 DOCKET NO. 50-311 The following discussion points have been prepared to facilitate the phone conference arranged with PSEG Nuclear to discuss the results of the steam generator (SG) tube inspections to be conducted during the upcoming Salem Nuclear Generating Station, Unit No. 2 refueling outage.
This phone call is scheduled to occur towards the end of the planned SG tube inspection interval, but before the unit completes the inspections and repairs.
The NRC staff plans to document a brief 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 SG, 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. Also, discuss the extent of the rotating probe inspections performed in the portion of tube below the expansion transition region (reference NRC Generic Letter 2004-01, Requirements for Steam Generator Tube Inspections).
5.
For each area examined (e.g., tube supports, dent/dings, sleeves, etc.), provide a summary of the number of indications identified to-date of each degradation mode (e.g.,
number of circumferential primary water stress-corrosion cracking (PWSCC) 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 PWSCC 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.
Provide the schedule for SG-related activities during the remainder of the current outage.
9.
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 if the loose parts were removed from the SG indications of tube damage associated with the loose parts the source or nature of the loose parts if known