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| number = ML17038A229
| number = ML17038A229
| issue date = 02/07/2017
| issue date = 02/07/2017
| title = RAI Formal Release for Callaway SG Tube Inspection Report, MF8474
| title = NRR E-mail Capture - RAI Formal Release for Callaway SG Tube Inspection Report, MF8474
| author name = Klos J
| author name = Klos J
| author affiliation = NRC/NRR/DORL/LPLIV-1
| author affiliation = NRC/NRR/DORL/LPLIV-1
Line 16: Line 16:


=Text=
=Text=
{{#Wiki_filter:1 NRR-PMDAPEm Resource From: Klos, John Sent: Tuesday, February 07, 2017 9:28 AM To: 'Telwood@ameren.com' Cc: Klos, John
{{#Wiki_filter:NRR-PMDAPEm Resource From:                             Klos, John Sent:                             Tuesday, February 07, 2017 9:28 AM To:                               'Telwood@ameren.com' Cc:                               Klos, John


==Subject:==
==Subject:==
RAI formal release for Callaway SG tube inspection report, MF8474 Importance:High
RAI formal release for Callaway SG tube inspection report, MF8474 Importance:                       High


==Dear Mr. Elwood,==
==Dear Mr. Elwood,==


By letter dated October 11, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16286A547), Union Electric Company (dba Ameren Missouri, the licensee), submitted information summarizing the 2016 steam generator tube inspections performed at Callaway Plant, Unit 1, during refueling outage 21.  
By letter dated October 11, 2016 (Agencywide Documents Access and Management System (ADAMS)
 
Accession No. ML16286A547), Union Electric Company (dba Ameren Missouri, the licensee), submitted information summarizing the 2016 steam generator tube inspections performed at Callaway Plant, Unit 1, during refueling outage 21.
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the submittal and determined that the attached request for additional information (RAI) is needed to complete its technical review and make a regulatory finding regarding this report.  
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the submittal and determined that the attached request for additional information (RAI) is needed to complete its technical review and make a regulatory finding regarding this report.
 
You have stated that there is no necessity for a clarification call; therefore, this RAI is now issued formally and it will be due on March 3, 3017.
You have stated that there is no necessity for a clarification call; therefore, this RAI is now issued formally and it will be due on March 3, 3017.
REQUESTS FOR ADDITIONAL INFORMATION 2016 STEAM GENERATOR TUBE INSPECTIONS CALLAWAY PLANT, UNIT 1 DOCKET NUMBER 50-483 By letter dated October 11, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16286A547), Union Electric Company (dba Ameren Missouri, the licensee), submitted information summarizing the 2016 steam generator tube inspections performed at Callaway Plant, Unit 1, during refueling outage 21.  
REQUESTS FOR ADDITIONAL INFORMATION 2016 STEAM GENERATOR TUBE INSPECTIONS CALLAWAY PLANT, UNIT 1 DOCKET NUMBER 50-483 By letter dated October 11, 2016 (Agencywide Documents Access and Management System (ADAMS)
 
Accession No. ML16286A547), Union Electric Company (dba Ameren Missouri, the licensee), submitted information summarizing the 2016 steam generator tube inspections performed at Callaway Plant, Unit 1, during refueling outage 21.
Regulatory Basis for RAIs: The regulations in Title 10 of the Code of Federal Regulations (10 CFR) establish the requirements with respect to the integrity of the SG tubing. Specifically, the General Design Criteria (GDC) in Appendix A to 10 CFR Part 50 state that the RCPB shall have "an extremely low probability of abnormal leakage ... and of gross rupture" (GDC 14, "Reactor pressure coolant boundary"), "shall be designed with sufficient margin to assure that the design conditions - are not exceeded -" (GDC 15, "Reactor coolant system design"), "shall be designed with sufficient margin that when stressed -(1) the boundary behaves in a nonbrittle manner, and (2) the probability of rapidly propagating fracture is minimized" (GDC 31, "Fracture prevention of reactor coolant pressure boundary"), shall be of "the highest quality standards practical" (GDC 30, "Quality of reactor coolant pressure boundary"), and "shall be designed to permit periodic inspection and testing...to assess...structural and leaktight integrity" (GDC 32, "Inspection of reactor coolant pressure boundary").  
Regulatory Basis for RAIs:
 
The regulations in Title 10 of the Code of Federal Regulations (10 CFR) establish the requirements with respect to the integrity of the SG tubing. Specifically, the General Design Criteria (GDC) in Appendix A to 10 CFR Part 50 state that the RCPB shall have an extremely low probability of abnormal leakage ... and of gross rupture (GDC 14, Reactor pressure coolant boundary), shall be designed with sufficient margin to assure that the design conditions are not exceeded (GDC 15, Reactor coolant system design), shall be designed with sufficient margin that when stressed (1) the boundary behaves in a nonbrittle manner, and (2) the probability of rapidly propagating fracture is minimized (GDC 31, Fracture prevention of reactor coolant pressure boundary), shall be of the highest quality standards practical (GDC 30, Quality of reactor coolant pressure boundary), and shall be designed to permit periodic inspection and testing...to assess...structural and leaktight integrity (GDC 32, Inspection of reactor coolant pressure boundary).
2Paragraph 50.55a(c)(1) of 10 CFR specifies that components that are part of the reactor coolant pressure boundary (RCPB) must meet the requirements for Class 1 components in Section III of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code). Paragraph 50.55a(g)(4) of 10 CFR further requires, in part, that throughout the service life of a Pressurized-Water Reactor facility, ASME Code Class 1 components meet the requirements, except design and access provisions and preservice examination requirements in Section XI, "Rules for Inservice Inspection (ISI) of Nuclear Power Plant Components," of the ASME Code, to the extent practical. This requirement includes the inspection and repair criteria of Section XI
1
 
of the ASME Code.
 
Section 50.36 of 10 CFR, "Technical specifications," establishes the requirements related to the content of the TSs. Pursuant to 10 CFR 50.36, TSs are required to include items in the following five categories related to station operation: (1) Safety limits, limiting safety system settings, and limiting control settings; (2) LCOs; (3) Surveillance requirements (SRs); (4) Design features; and (5) Administrative controls. Paragraph 50.36(c)(5) of 10 CFR defines administrative controls as, the "provisions relating to organization and management, procedures, recordkeeping, review and audit, and reporting necessary to assure the operation of the facility in a safe manner." Programs established by the licensee to operate the facility in a safe manner, including the Steam Generator (SG) Program, are listed in the administrative controls section of the TSs. The Callaway TS defines the SG Program in TS 5.5.9, while the reporting requirements relating to implementation of the SG Program are defined in TS 5.6.10.


Callaway TS 5.5.9 requires that an SG Program be established and implemented to ensure that SG tube integrity is maintained. Specification 5.5.9.a requires that a condition monitoring assessment be performed during each outage in which the SG tubes are inspected to confirm that the performance criteria are being met. SG tube integrity is maintained by meeting the performance criteria specified in TS 5.5.9.b. for structural and leakage integrity, consistent with the plant design and licensing basis. The applicable tube repair criteria specified in TS 5.5.9. c. are that tubes found during ISI to contain flaws with a depth equal to or exceeding 40 percent (%) of the nominal wall thickness shall be plugged. Specification 5.5.9.d. includes provisions regarding the scope, frequency, and methods of SG tube inspections. These provisions require that the inspections be performed with the objective of detecting flaws of any type that: (1) may be present along the length of a tube, from the tube-to-tubesheet weld at the tube inlet to the tube-to-tubesheet weld at the tube outlet; and (2) may satisfy the applicable tube repair criteria.  
Paragraph 50.55a(c)(1) of 10 CFR specifies that components that are part of the reactor coolant pressure boundary (RCPB) must meet the requirements for Class 1 components in Section III of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code). Paragraph 50.55a(g)(4) of 10 CFR further requires, in part, that throughout the service life of a Pressurized-Water Reactor facility, ASME Code Class 1 components meet the requirements, except design and access provisions and preservice examination requirements in Section XI, Rules for Inservice Inspection (ISI) of Nuclear Power Plant Components, of the ASME Code, to the extent practical. This requirement includes the inspection and repair criteria of Section XI of the ASME Code.
Section 50.36 of 10 CFR, Technical specifications, establishes the requirements related to the content of the TSs. Pursuant to 10 CFR 50.36, TSs are required to include items in the following five categories related to station operation: (1) Safety limits, limiting safety system settings, and limiting control settings; (2) LCOs; (3)
Surveillance requirements (SRs); (4) Design features; and (5) Administrative controls.
Paragraph 50.36(c)(5) of 10 CFR defines administrative controls as, the provisions relating to organization and management, procedures, recordkeeping, review and audit, and reporting necessary to assure the operation of the facility in a safe manner. Programs established by the licensee to operate the facility in a safe manner, including the Steam Generator (SG) Program, are listed in the administrative controls section of the TSs. The Callaway TS defines the SG Program in TS 5.5.9, while the reporting requirements relating to implementation of the SG Program are defined in TS 5.6.10.
Callaway TS 5.5.9 requires that an SG Program be established and implemented to ensure that SG tube integrity is maintained. Specification 5.5.9.a requires that a condition monitoring assessment be performed during each outage in which the SG tubes are inspected to confirm that the performance criteria are being met.
SG tube integrity is maintained by meeting the performance criteria specified in TS 5.5.9.b. for structural and leakage integrity, consistent with the plant design and licensing basis. The applicable tube repair criteria specified in TS 5.5.9. c. are that tubes found during ISI to contain flaws with a depth equal to or exceeding 40 percent (%) of the nominal wall thickness shall be plugged. Specification 5.5.9.d. includes provisions regarding the scope, frequency, and methods of SG tube inspections. These provisions require that the inspections be performed with the objective of detecting flaws of any type that: (1) may be present along the length of a tube, from the tube-to-tubesheet weld at the tube inlet to the tube-to-tubesheet weld at the tube outlet; and (2) may satisfy the applicable tube repair criteria.
RAI:
: 1. Please provide a listing of all service induced indications that were recorded in the steam generator eddy current inspections during refueling outage 21.
Thanks in advance, John Klos DORL Callaway, Columbia Project Manager U.S. NRC, Office of Nuclear Reactor Regulation, Division of Operating Reactor Licensing, O8E7 NRC/NRR/DORL/LPL4-1, MS O8H4A Washington, DC 20555-0001 301.415.5136, 301.415.2102 (fax)
John.Klos@NRC.gov 2


RAI: 1. Please provide a listing of all service induced indications that were recorded in the steam generator eddy current inspections during refueling outage 21.
Hearing Identifier:   NRR_PMDA Email Number:         3326 Mail Envelope Properties     (997f983cd19146d88288eabe292a7568)
 
Thanks in advance, John Klos DORL Callaway, Columbia Project Manager U.S. NRC, Office of Nuclear Reactor Regulation, Division of Operating Re actor Licensing, O8E7  NRC/NRR/DORL/LPL4-1, MS O8H4A Washington, DC 20555-0001 301.415.5136, 301.415.2102 (fax)
John.Klos@NRC.gov
 
Hearing Identifier: NRR_PMDA Email Number: 3326   Mail Envelope Properties   (997f983cd19146d88288eabe292a7568)


==Subject:==
==Subject:==
RAI formal release for Callaway SG tube inspection report, MF8474 Sent Date:   2/7/2017 9:28:14 AM Received Date: 2/7/2017 9:28:17 AM From:   Klos, John Created By:   John.Klos@nrc.gov Recipients:     "Klos, John" <John.Klos@nrc.gov>
RAI formal release for Callaway SG tube inspection report, MF8474 Sent Date:             2/7/2017 9:28:14 AM Received Date:         2/7/2017 9:28:17 AM From:                 Klos, John Created By:           John.Klos@nrc.gov Recipients:
Tracking Status: None "'Telwood@ameren.com'" <Telwood@ameren.com>
"Klos, John" <John.Klos@nrc.gov>
Tracking Status: None Post Office:   HQPWMSMRS02.nrc.gov
Tracking Status: None
 
"'Telwood@ameren.com'" <Telwood@ameren.com>
Files     Size     Date & Time MESSAGE   5739     2/7/2017 9:28:17 AM
Tracking Status: None Post Office:           HQPWMSMRS02.nrc.gov Files                         Size                     Date & Time MESSAGE                       5739                     2/7/2017 9:28:17 AM Options Priority:                     High Return Notification:           No Reply Requested:               No Sensitivity:                   Normal Expiration Date:
 
Recipients Received:}}
Options Priority:     High   Return Notification:   No   Reply Requested:   No   Sensitivity:     Normal Expiration Date:     Recipients Received:}}

Latest revision as of 10:24, 4 December 2019

NRR E-mail Capture - RAI Formal Release for Callaway SG Tube Inspection Report, MF8474
ML17038A229
Person / Time
Site: Callaway Ameren icon.png
Issue date: 02/07/2017
From: John Klos
Plant Licensing Branch IV
To: Elwood T
AmerenUE
References
MF8474
Download: ML17038A229 (3)
v • d • e


Text

NRR-PMDAPEm Resource From: Klos, John Sent: Tuesday, February 07, 2017 9:28 AM To: 'Telwood@ameren.com' Cc: Klos, John

Subject:

RAI formal release for Callaway SG tube inspection report, MF8474 Importance: High

Dear Mr. Elwood,

By letter dated October 11, 2016 (Agencywide Documents Access and Management System (ADAMS)

Accession No. ML16286A547), Union Electric Company (dba Ameren Missouri, the licensee), submitted information summarizing the 2016 steam generator tube inspections performed at Callaway Plant, Unit 1, during refueling outage 21.

The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the submittal and determined that the attached request for additional information (RAI) is needed to complete its technical review and make a regulatory finding regarding this report.

You have stated that there is no necessity for a clarification call; therefore, this RAI is now issued formally and it will be due on March 3, 3017.

REQUESTS FOR ADDITIONAL INFORMATION 2016 STEAM GENERATOR TUBE INSPECTIONS CALLAWAY PLANT, UNIT 1 DOCKET NUMBER 50-483 By letter dated October 11, 2016 (Agencywide Documents Access and Management System (ADAMS)

Accession No. ML16286A547), Union Electric Company (dba Ameren Missouri, the licensee), submitted information summarizing the 2016 steam generator tube inspections performed at Callaway Plant, Unit 1, during refueling outage 21.

Regulatory Basis for RAIs:

The regulations in Title 10 of the Code of Federal Regulations (10 CFR) establish the requirements with respect to the integrity of the SG tubing. Specifically, the General Design Criteria (GDC) in Appendix A to 10 CFR Part 50 state that the RCPB shall have an extremely low probability of abnormal leakage ... and of gross rupture (GDC 14, Reactor pressure coolant boundary), shall be designed with sufficient margin to assure that the design conditions are not exceeded (GDC 15, Reactor coolant system design), shall be designed with sufficient margin that when stressed (1) the boundary behaves in a nonbrittle manner, and (2) the probability of rapidly propagating fracture is minimized (GDC 31, Fracture prevention of reactor coolant pressure boundary), shall be of the highest quality standards practical (GDC 30, Quality of reactor coolant pressure boundary), and shall be designed to permit periodic inspection and testing...to assess...structural and leaktight integrity (GDC 32, Inspection of reactor coolant pressure boundary).

1

Paragraph 50.55a(c)(1) of 10 CFR specifies that components that are part of the reactor coolant pressure boundary (RCPB) must meet the requirements for Class 1 components in Section III of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code). Paragraph 50.55a(g)(4) of 10 CFR further requires, in part, that throughout the service life of a Pressurized-Water Reactor facility, ASME Code Class 1 components meet the requirements, except design and access provisions and preservice examination requirements in Section XI, Rules for Inservice Inspection (ISI) of Nuclear Power Plant Components, of the ASME Code, to the extent practical. This requirement includes the inspection and repair criteria of Section XI of the ASME Code.

Section 50.36 of 10 CFR, Technical specifications, establishes the requirements related to the content of the TSs. Pursuant to 10 CFR 50.36, TSs are required to include items in the following five categories related to station operation: (1) Safety limits, limiting safety system settings, and limiting control settings; (2) LCOs; (3)

Surveillance requirements (SRs); (4) Design features; and (5) Administrative controls.

Paragraph 50.36(c)(5) of 10 CFR defines administrative controls as, the provisions relating to organization and management, procedures, recordkeeping, review and audit, and reporting necessary to assure the operation of the facility in a safe manner. Programs established by the licensee to operate the facility in a safe manner, including the Steam Generator (SG) Program, are listed in the administrative controls section of the TSs. The Callaway TS defines the SG Program in TS 5.5.9, while the reporting requirements relating to implementation of the SG Program are defined in TS 5.6.10.

Callaway TS 5.5.9 requires that an SG Program be established and implemented to ensure that SG tube integrity is maintained. Specification 5.5.9.a requires that a condition monitoring assessment be performed during each outage in which the SG tubes are inspected to confirm that the performance criteria are being met.

SG tube integrity is maintained by meeting the performance criteria specified in TS 5.5.9.b. for structural and leakage integrity, consistent with the plant design and licensing basis. The applicable tube repair criteria specified in TS 5.5.9. c. are that tubes found during ISI to contain flaws with a depth equal to or exceeding 40 percent (%) of the nominal wall thickness shall be plugged. Specification 5.5.9.d. includes provisions regarding the scope, frequency, and methods of SG tube inspections. These provisions require that the inspections be performed with the objective of detecting flaws of any type that: (1) may be present along the length of a tube, from the tube-to-tubesheet weld at the tube inlet to the tube-to-tubesheet weld at the tube outlet; and (2) may satisfy the applicable tube repair criteria.

RAI:

1. Please provide a listing of all service induced indications that were recorded in the steam generator eddy current inspections during refueling outage 21.

Thanks in advance, John Klos DORL Callaway, Columbia Project Manager U.S. NRC, Office of Nuclear Reactor Regulation, Division of Operating Reactor Licensing, O8E7 NRC/NRR/DORL/LPL4-1, MS O8H4A Washington, DC 20555-0001 301.415.5136, 301.415.2102 (fax)

John.Klos@NRC.gov 2

Hearing Identifier: NRR_PMDA Email Number: 3326 Mail Envelope Properties (997f983cd19146d88288eabe292a7568)

Subject:

RAI formal release for Callaway SG tube inspection report, MF8474 Sent Date: 2/7/2017 9:28:14 AM Received Date: 2/7/2017 9:28:17 AM From: Klos, John Created By: John.Klos@nrc.gov Recipients:

"Klos, John" <John.Klos@nrc.gov>

Tracking Status: None

"'Telwood@ameren.com'" <Telwood@ameren.com>

Tracking Status: None Post Office: HQPWMSMRS02.nrc.gov Files Size Date & Time MESSAGE 5739 2/7/2017 9:28:17 AM Options Priority: High Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

Recipients Received:

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