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| number = ML13269A389
| number = ML13269A389
| issue date = 10/21/2013
| issue date = 10/21/2013
| title = Three Mile Island Nuclear Station, Unit 1 - Upcoming Steam Generator Tube Inspection (TAC No. MF2799)
| title = Upcoming Steam Generator Tube Inspection
| author name = Hughey J D
| author name = Hughey J
| author affiliation = NRC/NRR/DORL/LPLI-2
| author affiliation = NRC/NRR/DORL/LPLI-2
| addressee name = Pacilio M J
| addressee name = Pacilio M
| addressee affiliation = Exelon Nuclear
| addressee affiliation = Exelon Nuclear
| docket = 05000289
| docket = 05000289
| license number =  
| license number =  
| contact person = Ennis R B
| contact person = Ennis R
| case reference number = TAC MF2799
| case reference number = TAC MF2799
| document type = Letter
| document type = Letter
| page count = 4
| page count = 4
| project = TAC:MF2799
| project = TAC:MF2799
| stage = Other
}}
}}


=Text=
=Text=
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 October 21, 2013 SUBJECT: THREE MILE ISLAND NUCLEAR STATION, UNIT 1 -UPCOMING STEAM GENERATOR TUBE INSERVICE INSPECTION (TAG NO. MF2799) Dear Mr. Pacilio: lnservice inspections of steam generator (SG) tubes play a vital role in assuring SG tube integrity. Based on my discussion with Ms. Wendi Croft of your staff on September 25, 2013, 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 refueling outage for Three Mile Island Nuclear Station, Unit 1. 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. Docket No. 50-289 Enclosure: John D. Hughey, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Steam Generator Tube Inspection Discussion Points cc w/encl: Distribution via Listserv 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 (SG) tube inspections to be conducted during the upcoming fall 2013 refueling outage at Three Mile Island, Unit 1 (TMI-1 ). This conference call is scheduled to occur towards the end of the planned SG tube inspections, but before the inspections and repairs are completed. 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 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 percent of dents/dings greater than 5 volts and a 20 percent sample between 2 and 5 volts), and the expansion criteria. 5. For each area examined (e.g., tube supports, denVdings, 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 (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 PWSCG 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:
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 21, 2013 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
 
==SUBJECT:==
THREE MILE ISLAND NUCLEAR STATION, UNIT 1 -UPCOMING STEAM GENERATOR TUBE INSERVICE INSPECTION (TAG NO. MF2799)
 
==Dear Mr. Pacilio:==
 
lnservice inspections of steam generator (SG) tubes play a vital role in assuring SG tube integrity. Based on my discussion with Ms. Wendi Croft of your staff on September 25, 2013, 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 refueling outage for Three Mile Island Nuclear Station, Unit 1. 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.
John D. Hughey, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-289
 
==Enclosure:==
 
Steam Generator Tube Inspection Discussion Points cc w/encl: Distribution via Listserv
 
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 (SG) tube inspections to be conducted during the upcoming fall 2013 refueling outage at Three Mile Island, Unit 1 (TMI-1 ).
This conference call is scheduled to occur towards the end of the planned SG tube inspections, but before the inspections and repairs are completed.
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 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 percent of dents/dings greater than 5 volts and a 20 percent sample between 2 and 5 volts), and the expansion criteria.
: 5. For each area examined (e.g., tube supports, denVdings, 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 (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 PWSCG 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;
* 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); Enclosure
* a description of any loose parts detected and their location within the SG (including the source or nature of the loose part, if known);
-2 -* if the loose parts were removed from the SG; and
Enclosure
* 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, feed-ring 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.
* if the loose parts were removed from the SG; and
October 21, 2013 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 SUBJECT: THREE MILE ISLAND NUCLEAR STATION, UNIT 1 -UPCOMING STEAM GENERATOR TUBE INSERVICE INSPECTION (TAC NO. MF2799) Dear Mr. Pacilio: lnservice inspections of steam generator (SG) tubes play a vital role in assuring SG tube integrity. Based on my discussion with Ms. Wendi Croft of your staff on September 25, 2013, 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 refueling outage for Three Mile Island Nuclear Station, Unit 1. 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. Docket No. 50-289 Enclosure: Sincerely, Ira/ John D. Hughey, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Steam Generator Tube Inspection Discussion Points cc w/encl: Distribution via Listserv DISTRIBUTION: Public LPL 1-2 R/F RidsNrrDorllpl1-2 Resource RidsNrrLAABaxter Resource MGray, RI/DRS Accession No.: ML 13269A389 OFFICE LPL1-2/PM NAME REnnis DATE 09/30/2013 JHughey, NRR/DORL RidsRgn1 Mail Center Resource RidsAcrsAcnw_MaiiCTR Resource RidsNrrDeEsgb Resource RidsNrrPMThreeMilelsland Resource LPL 1-2/LA ESGB/BC ABaxter GKulesa 10/02/2013 10/18/2013 OFFICIAL RECORD COPY KKarwoski, NRR/DE EMurphy, NRR/DE/ESGB AJohnson, NRR/DE/ESGB CHunt, NRR/DE/ESGB GHunegs. RI/DRP LPL 1-2/BC (Al LPL1-2/PM VRodriguez JHughey 10/21/2013 10/21/13
* 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, feed-ring 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 21, 2013 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
 
==SUBJECT:==
THREE MILE ISLAND NUCLEAR STATION, UNIT 1 -UPCOMING STEAM GENERATOR TUBE INSERVICE INSPECTION (TAC NO. MF2799)
 
==Dear Mr. Pacilio:==
 
lnservice inspections of steam generator (SG) tubes play a vital role in assuring SG tube integrity. Based on my discussion with Ms. Wendi Croft of your staff on September 25, 2013, 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 refueling outage for Three Mile Island Nuclear Station, Unit 1. 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. 50-289
 
==Enclosure:==
 
Steam Generator Tube Inspection Discussion Points cc w/encl: Distribution via Listserv DISTRIBUTION:
Public                           JHughey, NRR/DORL                        KKarwoski, NRR/DE LPL 1-2 R/F                     RidsRgn1 Mail Center Resource            EMurphy, NRR/DE/ESGB RidsNrrDorllpl1-2 Resource       RidsAcrsAcnw_MaiiCTR Resource            AJohnson, NRR/DE/ESGB RidsNrrLAABaxter Resource       RidsNrrDeEsgb Resource                  CHunt, NRR/DE/ESGB MGray, RI/DRS                   RidsNrrPMThreeMilelsland Resource        GHunegs. RI/DRP Accession No.: ML13269A389 OFFICE     LPL1-2/PM       LPL 1-2/LA           ESGB/BC             LPL 1-2/BC (Al     LPL1-2/PM NAME        REnnis          ABaxter              GKulesa            VRodriguez         JHughey DATE        09/30/2013      10/02/2013            10/18/2013          10/21/2013         10/21/13 OFFICIAL RECORD COPY}}

Latest revision as of 13:08, 4 November 2019

Upcoming Steam Generator Tube Inspection
ML13269A389
Person / Time
Site: Three Mile Island Constellation icon.png
Issue date: 10/21/2013
From: John Hughey
Plant Licensing Branch 1
To: Pacilio M
Exelon Nuclear
Ennis R
References
TAC MF2799
Download: ML13269A389 (4)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 21, 2013 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

THREE MILE ISLAND NUCLEAR STATION, UNIT 1 -UPCOMING STEAM GENERATOR TUBE INSERVICE INSPECTION (TAG NO. MF2799)

Dear Mr. Pacilio:

lnservice inspections of steam generator (SG) tubes play a vital role in assuring SG tube integrity. Based on my discussion with Ms. Wendi Croft of your staff on September 25, 2013, 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 refueling outage for Three Mile Island Nuclear Station, Unit 1. 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.

John D. Hughey, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-289

Enclosure:

Steam Generator Tube Inspection Discussion Points cc w/encl: Distribution via Listserv

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 (SG) tube inspections to be conducted during the upcoming fall 2013 refueling outage at Three Mile Island, Unit 1 (TMI-1 ).

This conference call is scheduled to occur towards the end of the planned SG tube inspections, but before the inspections and repairs are completed.

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 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 percent of dents/dings greater than 5 volts and a 20 percent sample between 2 and 5 volts), and the expansion criteria.
5. For each area examined (e.g., tube supports, denVdings, 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 (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 PWSCG 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);

Enclosure

  • if the loose parts were removed from the SG; and
  • 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, feed-ring 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 21, 2013 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

THREE MILE ISLAND NUCLEAR STATION, UNIT 1 -UPCOMING STEAM GENERATOR TUBE INSERVICE INSPECTION (TAC NO. MF2799)

Dear Mr. Pacilio:

lnservice inspections of steam generator (SG) tubes play a vital role in assuring SG tube integrity. Based on my discussion with Ms. Wendi Croft of your staff on September 25, 2013, 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 refueling outage for Three Mile Island Nuclear Station, Unit 1. 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. 50-289

Enclosure:

Steam Generator Tube Inspection Discussion Points cc w/encl: Distribution via Listserv DISTRIBUTION:

Public JHughey, NRR/DORL KKarwoski, NRR/DE LPL 1-2 R/F RidsRgn1 Mail Center Resource EMurphy, NRR/DE/ESGB RidsNrrDorllpl1-2 Resource RidsAcrsAcnw_MaiiCTR Resource AJohnson, NRR/DE/ESGB RidsNrrLAABaxter Resource RidsNrrDeEsgb Resource CHunt, NRR/DE/ESGB MGray, RI/DRS RidsNrrPMThreeMilelsland Resource GHunegs. RI/DRP Accession No.: ML13269A389 OFFICE LPL1-2/PM LPL 1-2/LA ESGB/BC LPL 1-2/BC (Al LPL1-2/PM NAME REnnis ABaxter GKulesa VRodriguez JHughey DATE 09/30/2013 10/02/2013 10/18/2013 10/21/2013 10/21/13 OFFICIAL RECORD COPY

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