ML12265A144: Difference between revisions
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| number = ML12265A144 | | number = ML12265A144 | ||
| issue date = 10/01/2012 | | issue date = 10/01/2012 | ||
| title = | | title = Upcoming Steam Generator Tube Inservice Inspection | ||
| author name = Hughey J | | author name = Hughey J | ||
| author affiliation = NRC/NRR/DORL/LPLI-2 | | author affiliation = NRC/NRR/DORL/LPLI-2 | ||
| addressee name = Joyce T | | addressee name = Joyce T | ||
Line 9: | Line 9: | ||
| docket = 05000311 | | docket = 05000311 | ||
| license number = DPR-075 | | license number = DPR-075 | ||
| contact person = Hughey J | | contact person = Hughey J | ||
| case reference number = TAC ME9602 | | case reference number = TAC ME9602 | ||
| document type = Letter | | document type = Letter | ||
Line 18: | Line 18: | ||
=Text= | =Text= | ||
{{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 October 1, 2012 Mr. Thomas Joyce President and Chief Nuclear Officer PSEG Nuclear LLC-N09 P.O. Box 236 Hancocks Bridge, NJ 08038 SALEM NUCLEAR GENERATING STATION, UNIT NO.2 -UPCOMING STEAM GENERATOR TUBE INSERVICE INSPECTION (TAC NO. ME9602) Dear Mr. Joyce: Inservice inspections of steam generator (SG) tubes playa vital role in assuring SG tube integrity. Based on my discussion with Mr. Paul Duke on September 20,2012, a conference call will be arranged with members of your staff to discuss the ongoing results of the SG tube inspections to be conducted during the upcoming fall 2012 refueling outage for Salem Nuclear Generating Station, Unit No.2. 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 Nuclear Regulatory Commission (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, please contact me at (301) 415-3204. ;AfJ*John D. Hughey, Project Manager Plant licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. Steam Generator Tube Inspection Discussion cc w/encl: Distribution via STEAM GENERATOR TUBE INSPECTION DISCUSSION The Nuclear Regulatory Commission staff plans to document a summary of the conference call as well as any material that is provided in support of the call. Discuss any trends in the amount of primary-to-secondary leakage observed during the recently completed cycle. Discuss whether any secondary side pressure tests were performed during the outage and the associated results. Discuss any exceptions taken to the industry guidelines. For each steam generator (SG), provide a description of the inspections performed including the areas examined and the probes used (e.g., dents/dings, sleeves, 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. 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). Describe repair/plugging plans. Describe in-situ pressure test and tube pull plans and results (as applicable and if available). 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 | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 1, 2012 Mr. Thomas Joyce President and Chief Nuclear Officer PSEG Nuclear LLC-N09 P.O. Box 236 Hancocks Bridge, NJ 08038 | ||
-2 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). Discuss any unexpected or unusual results. Provide the schedule for SG-related activities during the remainder of the current outage. | |||
October 1, 2012 Mr. Thomas Joyce President and Chief Nuclear Officer PSEG Nuclear LLC-N09 P.O. Box 236 Hancocks Bridge, NJ 08038 SALEM NUCLEAR GENERATING STATION, UNIT NO.2 -UPCOMING STEAM GENERATOR TUBE INSERVICE INSPECTION (TAC NO. ME9602) Dear Mr. Joyce: Inservice inspections of steam generator (SG) tubes playa vital role in assuring SG tube integrity. Based on my discussion with Mr. Paul Duke on September 20, 2012, a conference call will be arranged with members of your staff to discuss the ongoing results of the SG tube inspections to be conducted during the upcoming fall 2012 refueling outage for Salem Nuclear Generating Station, Unit No.2. 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 Nuclear Regulatory Commission (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, please contact me at (301) 415-3204. Sincerely, IRA! John D. Hughey, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. Steam Generator Tube Inspection Discussion cc w/encl: Distribution via Listserv DISTRIBUTION: Public RidsOgcRp Resource KKarwoski, NRR LPL 1-2 RtF RidsRgn1 MailCenter Resource TO'Hara, RI RidsNrrDorlLpl1-2 Resource RidsAcrsAcnw_MailCTR Resource A.lohnson, NRR RidsNrrLAABaxter Resource RidsNrrDeEsgb Resource RidsNrrPMSalem Resource Accession No*.. ML12265A144 OFFICE LPL 1-2/PM LPL 1-2/LAit | ==SUBJECT:== | ||
}} | SALEM NUCLEAR GENERATING STATION, UNIT NO.2 - UPCOMING STEAM GENERATOR TUBE INSERVICE INSPECTION (TAC NO. ME9602) | ||
==Dear Mr. Joyce:== | |||
Inservice inspections of steam generator (SG) tubes playa vital role in assuring SG tube integrity. Based on my discussion with Mr. Paul Duke on September 20,2012, a conference call will be arranged with members of your staff to discuss the ongoing results of the SG tube inspections to be conducted during the upcoming fall 2012 refueling outage for Salem Nuclear Generating Station, Unit No.2. 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 Nuclear Regulatory Commission (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, please contact me at (301) 415-3204. | |||
;AfJ* | |||
John D. Hughey, Project Manager Plant licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-311 | |||
==Enclosure:== | |||
Steam Generator Tube Inspection Discussion Points cc w/encl: Distribution via Listserv | |||
STEAM GENERATOR TUBE INSPECTION DISCUSSION POINTS The Nuclear Regulatory Commission 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 (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. | |||
: 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 | |||
-2 | |||
: 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 SG-related activities during the remainder of the current outage. | |||
October 1, 2012 Mr. Thomas Joyce President and Chief Nuclear Officer PSEG Nuclear LLC-N09 P.O. Box 236 Hancocks Bridge, NJ 08038 | |||
==SUBJECT:== | |||
SALEM NUCLEAR GENERATING STATION, UNIT NO.2 - UPCOMING STEAM GENERATOR TUBE INSERVICE INSPECTION (TAC NO. ME9602) | |||
==Dear Mr. Joyce:== | |||
Inservice inspections of steam generator (SG) tubes playa vital role in assuring SG tube integrity. Based on my discussion with Mr. Paul Duke on September 20, 2012, a conference call will be arranged with members of your staff to discuss the ongoing results of the SG tube inspections to be conducted during the upcoming fall 2012 refueling outage for Salem Nuclear Generating Station, Unit No.2. 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 Nuclear Regulatory Commission (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, please contact me at (301) 415-3204. | |||
Sincerely, IRA! | |||
John D. Hughey, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-311 | |||
==Enclosure:== | |||
Steam Generator Tube Inspection Discussion Points cc w/encl: Distribution via Listserv DISTRIBUTION: | |||
Public RidsOgcRp Resource KKarwoski, NRR LPL 1-2 RtF RidsRgn1 MailCenter Resource TO'Hara, RI RidsNrrDorlLpl1-2 Resource RidsAcrsAcnw_MailCTR Resource A.lohnson, NRR RidsNrrLAABaxter Resource RidsNrrDeEsgb Resource RidsNrrPMSalem Resource Accession No* .. ML12265A144 OFFICE LPL 1-2/PM LPL 1-2/LAit LPL 1-2/LA ESGB/BC NRR/LPL 1-2/BC NAME JHughey SLent ABaxter GKulesa MKhanna DATE 9/25/2012 9/25/2012 9/25/2012 9/27/2012 10101/2012 OFFICIAL RECORD COpy}} |
Latest revision as of 23:14, 11 November 2019
ML12265A144 | |
Person / Time | |
---|---|
Site: | Salem ![]() |
Issue date: | 10/01/2012 |
From: | John Hughey Plant Licensing Branch 1 |
To: | Joyce T Public Service Enterprise Group |
Hughey J | |
References | |
TAC ME9602 | |
Download: ML12265A144 (4) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 1, 2012 Mr. Thomas Joyce President and Chief Nuclear Officer PSEG Nuclear LLC-N09 P.O. Box 236 Hancocks Bridge, NJ 08038
SUBJECT:
SALEM NUCLEAR GENERATING STATION, UNIT NO.2 - UPCOMING STEAM GENERATOR TUBE INSERVICE INSPECTION (TAC NO. ME9602)
Dear Mr. Joyce:
Inservice inspections of steam generator (SG) tubes playa vital role in assuring SG tube integrity. Based on my discussion with Mr. Paul Duke on September 20,2012, a conference call will be arranged with members of your staff to discuss the ongoing results of the SG tube inspections to be conducted during the upcoming fall 2012 refueling outage for Salem Nuclear Generating Station, Unit No.2. 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 Nuclear Regulatory Commission (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, please contact me at (301) 415-3204.
- AfJ*
John D. Hughey, Project Manager Plant licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-311
Enclosure:
Steam Generator Tube Inspection Discussion Points cc w/encl: Distribution via Listserv
STEAM GENERATOR TUBE INSPECTION DISCUSSION POINTS The Nuclear Regulatory Commission 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 (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.
- 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
-2
- 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 SG-related activities during the remainder of the current outage.
October 1, 2012 Mr. Thomas Joyce President and Chief Nuclear Officer PSEG Nuclear LLC-N09 P.O. Box 236 Hancocks Bridge, NJ 08038
SUBJECT:
SALEM NUCLEAR GENERATING STATION, UNIT NO.2 - UPCOMING STEAM GENERATOR TUBE INSERVICE INSPECTION (TAC NO. ME9602)
Dear Mr. Joyce:
Inservice inspections of steam generator (SG) tubes playa vital role in assuring SG tube integrity. Based on my discussion with Mr. Paul Duke on September 20, 2012, a conference call will be arranged with members of your staff to discuss the ongoing results of the SG tube inspections to be conducted during the upcoming fall 2012 refueling outage for Salem Nuclear Generating Station, Unit No.2. 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 Nuclear Regulatory Commission (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, please contact me at (301) 415-3204.
Sincerely, IRA!
John D. Hughey, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-311
Enclosure:
Steam Generator Tube Inspection Discussion Points cc w/encl: Distribution via Listserv DISTRIBUTION:
Public RidsOgcRp Resource KKarwoski, NRR LPL 1-2 RtF RidsRgn1 MailCenter Resource TO'Hara, RI RidsNrrDorlLpl1-2 Resource RidsAcrsAcnw_MailCTR Resource A.lohnson, NRR RidsNrrLAABaxter Resource RidsNrrDeEsgb Resource RidsNrrPMSalem Resource Accession No* .. ML12265A144 OFFICE LPL 1-2/PM LPL 1-2/LAit LPL 1-2/LA ESGB/BC NRR/LPL 1-2/BC NAME JHughey SLent ABaxter GKulesa MKhanna DATE 9/25/2012 9/25/2012 9/25/2012 9/27/2012 10101/2012 OFFICIAL RECORD COpy