ML16008A246

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NRR E-mail Capture - Draft Request for Additional Information for Relief Request 14-ON-001, Letdown Cooler Nozzle Welds (TAC Nos. MF6290, MF6291 and MF6292)
ML16008A246
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 01/07/2016
From: Randy Hall
Plant Licensing Branch II
To: Wasik C
Duke Energy Corp
References
MF6290, MF6291, MF6292
Download: ML16008A246 (4)
v • d • e


Text

NRR-PMDAPEm Resource From: Hall, Randy Sent: Thursday, January 07, 2016 3:29 PM To: Wasik, Christopher J (Christopher.Wasik@duke-energy.com)

Cc: Haile, David Carroll (David.Haile@duke-energy.com); Whited, Jeffrey

Subject:

OCONEE NUCLEAR STATION, UNITS 1, 2 AND 3 - DRAFT REQUEST FOR ADDITIONAL INFORMATION FOR RELIEF REQUEST 14-ON-001, LETDOWN COOLER NOZZLE WELDS (TAC NOS. MF6290, MF6291 AND MF6292)

Attachments: Oconee draft RAI RR 14-ON-001.docx January 7, 2016 Mr. Christopher J. Wasik Manager, Regulatory Affairs Oconee Nuclear Station Duke Energy Carolinas, LLC

SUBJECT:

OCONEE NUCLEAR STATION, UNITS 1, 2 AND 3 - DRAFT REQUEST FOR ADDITIONAL INFORMATION FOR RELIEF REQUEST 14-ON-001, LETDOWN COOLER NOZZLE WELDS (TAC NOS. MF6290, MF6291 AND MF6292)

Chris:

By letter dated May 4, 2015 (Agency-wide Documents and Access Management System (ADAMS) Accession No. ML15132A279), Duke Energy (the licensee) requested the Nuclear Regulatory Commission (NRC) to authorize relief from Section Xl of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code related to inspection of the inside radius sections of the Letdown Cooler nozzles over the duration of the fifth (ten-year) in-service inspection (ISI) interval. This relief request applies to the Oconee Nuclear Station, Units 1, 2 and 3. The licensee is requesting renewal of previously granted relief requests based on the impracticality of performing inspections in the specified areas.

The NRC staff needs additional information to support the completion of its review of the subject relief request.

Therefore, we request your response to the questions in the attached draft request for additional information (RAI).

Please let me know if youd like to have a call with the NRC technical reviewers to clarify the questions in the draft RAI. If a call is not necessary, we request that you submit your written response to the RAI within 30 days, or propose an alternative schedule for your response.

If you have any questions, please contact me at (301) 415-4032.

Sincerely, Randy Hall, Senior Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation USNRC (301) 415-4032 Randy.Hall@nrc.gov 1

Hearing Identifier: NRR_PMDA Email Number: 2584 Mail Envelope Properties (Randy.Hall@nrc.gov20160107152900)

Subject:

OCONEE NUCLEAR STATION, UNITS 1, 2 AND 3 - DRAFT REQUEST FOR ADDITIONAL INFORMATION FOR RELIEF REQUEST 14-ON-001, LETDOWN COOLER NOZZLE WELDS (TAC NOS. MF6290, MF6291 AND MF6292)

Sent Date: 1/7/2016 3:29:23 PM Received Date: 1/7/2016 3:29:00 PM From: Hall, Randy Created By: Randy.Hall@nrc.gov Recipients:

"Haile, David Carroll (David.Haile@duke-energy.com)" <David.Haile@duke-energy.com>

Tracking Status: None "Whited, Jeffrey" <Jeffrey.Whited@nrc.gov>

Tracking Status: None "Wasik, Christopher J (Christopher.Wasik@duke-energy.com)" <Christopher.Wasik@duke-energy.com>

Tracking Status: None Post Office:

Files Size Date & Time MESSAGE 1863 1/7/2016 3:29:00 PM Oconee draft RAI RR 14-ON-001.docx 25680 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

Recipients Received:

DRAFT REQUEST FOR ADDITIONAL INFORMATION RELIEF REQUEST 14-ON-001 LETDOWN COOLER NOZZLE WELDS OCONEE NUCLEAR STATION, UNITS 1, 2 AND 3 DUKE ENERGY CAROLINAS, LLC DOCKET NOS. 50-269, 50-270 AND 50-287 By letter dated May 4, 2015 (Agency-wide Documents and Access Management System (ADAMS) Accession No. ML15132A279), Duke Energy (the licensee) requested the Nuclear Regulatory Commission (NRC) to authorize relief from Section Xl of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code related to inspection of the inside radius sections of the Letdown Cooler nozzles over the duration of the fifth (ten-year) in-service inspection (ISI) interval. This relief request applies to the Oconee Nuclear Station, Units 1, 2 and 3. The licensee is requesting renewal of previously granted relief requests based on the impracticality of performing inspections in the specified areas. To complete its review, the NRC staff requests the following additional information.

1. Please provide a more detailed description of the nozzle inside radius sections that are required to be ultrasonically examined per the ASME Code,Section XI, by either referring to the drawings in the relief request as a guide or by providing a sketch or drawing of the subject welds/nozzles.
2. Section 1 of the relief request states that "... Oconee Unit 1 has two Letdown Coolers 1A and 1B. Each component has typically four B3.160 welds...." Please confirm that the required examination is on the attachment welds of the nozzles, not the nozzles themselves, and that the required examination is on the inside radius of the welds. It appears that the nozzles are forged and are attached to the side of a pipe as a branch connection. The welds are deposited on the inside and outside circumference of the nozzles that are attaching to the pipe. Is the staffs understanding correct? If not, please clarify.
3. Section 1 of the relief request states that "... The coolers also have operational ready spares of similar design that are rotated from spare to installed components as required by maintenance..." What is the relevance of this sentence with respect to the required examination of the subject nozzle weld inside radius sections?
4. Briefly describe the design and operation of the letdown coolers. Are the subject nozzles connected to the tube side or shell side of the letdown cooler? What fluids flow in the tube side and shell side of the coolers? If the fluid is not from the reactor coolant system, is the fluid being chemically treated to minimize corrosion?
5. Discuss how the letdown cooler and letdown system would be affected if the subject nozzles/welds fail completely (i.e., what is the consequence if the nozzles fail?). Section 4 of the relief request states that the nozzles are set-on, discuss the possibility of the nozzle ejecting from the pipe.

2

6. Section 9 the relief request states, "The ultrasonic examination of the weld volume adjacent the inside radius section, as required by ASME Section Xl, Table IWB-2500-1, Examination Category B-D, Item Number B3.150 is a more critical location and will provide adequate assurance of the integrity of the welded connection." Please explain (using the drawings in the relief request, as appropriate) where this B3.150 weld is located with respect to the B3.160 welds. For example, Drawing 1-N37804-2 shows 2 welds (WJ32V and WJ31V) are adjacent to nozzle 2-HP-0524. Are WJ32V and WJ31V the B3.150 welds? Discuss whether flaws or indications have been detected in the B3.150 welds. If the latest inspection results of the B3.150 welds have been submitted to the NRC in a 90-day or an annual report, please provide the date of the submittal. What is the weld filler material of the B3.150 welds?
7. Confirm that the subject nozzles are made of 3-inch, stainless steel forging. What is the nozzle wall thickness? What is the material of the pipe that the nozzle is attached to? What is the nominal pipe size and wall thickness of the pipe to which the nozzle is attached?
8. What are the operating and design pressures and temperatures of the subject nozzles?
9. Are the affected welds identification numbers the same as those described in Relief Request 04-ON-015 submitted on December 1, 2004?
10. What is the weld filler material of the affected nozzles? Is the subject weld a full penetration weld, partial penetration weld, or fillet weld?
11. What is the purpose of the nozzles? Is there a pipe connected to the nozzles? Identify pipe supports that are located in the vicinity of the nozzles.
12. Has there been any leakage from or degradation of the subject welds/nozzles?

NRR-PMDAPEm Resource From: Hall, Randy Sent: Thursday, January 07, 2016 3:29 PM To: Wasik, Christopher J (Christopher.Wasik@duke-energy.com)

Cc: Haile, David Carroll (David.Haile@duke-energy.com); Whited, Jeffrey

Subject:

OCONEE NUCLEAR STATION, UNITS 1, 2 AND 3 - DRAFT REQUEST FOR ADDITIONAL INFORMATION FOR RELIEF REQUEST 14-ON-001, LETDOWN COOLER NOZZLE WELDS (TAC NOS. MF6290, MF6291 AND MF6292)

Attachments: Oconee draft RAI RR 14-ON-001.docx January 7, 2016 Mr. Christopher J. Wasik Manager, Regulatory Affairs Oconee Nuclear Station Duke Energy Carolinas, LLC

SUBJECT:

OCONEE NUCLEAR STATION, UNITS 1, 2 AND 3 - DRAFT REQUEST FOR ADDITIONAL INFORMATION FOR RELIEF REQUEST 14-ON-001, LETDOWN COOLER NOZZLE WELDS (TAC NOS. MF6290, MF6291 AND MF6292)

Chris:

By letter dated May 4, 2015 (Agency-wide Documents and Access Management System (ADAMS) Accession No. ML15132A279), Duke Energy (the licensee) requested the Nuclear Regulatory Commission (NRC) to authorize relief from Section Xl of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code related to inspection of the inside radius sections of the Letdown Cooler nozzles over the duration of the fifth (ten-year) in-service inspection (ISI) interval. This relief request applies to the Oconee Nuclear Station, Units 1, 2 and 3. The licensee is requesting renewal of previously granted relief requests based on the impracticality of performing inspections in the specified areas.

The NRC staff needs additional information to support the completion of its review of the subject relief request.

Therefore, we request your response to the questions in the attached draft request for additional information (RAI).

Please let me know if youd like to have a call with the NRC technical reviewers to clarify the questions in the draft RAI. If a call is not necessary, we request that you submit your written response to the RAI within 30 days, or propose an alternative schedule for your response.

If you have any questions, please contact me at (301) 415-4032.

Sincerely, Randy Hall, Senior Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation USNRC (301) 415-4032 Randy.Hall@nrc.gov 1

Hearing Identifier: NRR_PMDA Email Number: 2584 Mail Envelope Properties (Randy.Hall@nrc.gov20160107152900)

Subject:

OCONEE NUCLEAR STATION, UNITS 1, 2 AND 3 - DRAFT REQUEST FOR ADDITIONAL INFORMATION FOR RELIEF REQUEST 14-ON-001, LETDOWN COOLER NOZZLE WELDS (TAC NOS. MF6290, MF6291 AND MF6292)

Sent Date: 1/7/2016 3:29:23 PM Received Date: 1/7/2016 3:29:00 PM From: Hall, Randy Created By: Randy.Hall@nrc.gov Recipients:

"Haile, David Carroll (David.Haile@duke-energy.com)" <David.Haile@duke-energy.com>

Tracking Status: None "Whited, Jeffrey" <Jeffrey.Whited@nrc.gov>

Tracking Status: None "Wasik, Christopher J (Christopher.Wasik@duke-energy.com)" <Christopher.Wasik@duke-energy.com>

Tracking Status: None Post Office:

Files Size Date & Time MESSAGE 1863 1/7/2016 3:29:00 PM Oconee draft RAI RR 14-ON-001.docx 25680 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

Recipients Received:

DRAFT REQUEST FOR ADDITIONAL INFORMATION RELIEF REQUEST 14-ON-001 LETDOWN COOLER NOZZLE WELDS OCONEE NUCLEAR STATION, UNITS 1, 2 AND 3 DUKE ENERGY CAROLINAS, LLC DOCKET NOS. 50-269, 50-270 AND 50-287 By letter dated May 4, 2015 (Agency-wide Documents and Access Management System (ADAMS) Accession No. ML15132A279), Duke Energy (the licensee) requested the Nuclear Regulatory Commission (NRC) to authorize relief from Section Xl of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code related to inspection of the inside radius sections of the Letdown Cooler nozzles over the duration of the fifth (ten-year) in-service inspection (ISI) interval. This relief request applies to the Oconee Nuclear Station, Units 1, 2 and 3. The licensee is requesting renewal of previously granted relief requests based on the impracticality of performing inspections in the specified areas. To complete its review, the NRC staff requests the following additional information.

1. Please provide a more detailed description of the nozzle inside radius sections that are required to be ultrasonically examined per the ASME Code,Section XI, by either referring to the drawings in the relief request as a guide or by providing a sketch or drawing of the subject welds/nozzles.
2. Section 1 of the relief request states that "... Oconee Unit 1 has two Letdown Coolers 1A and 1B. Each component has typically four B3.160 welds...." Please confirm that the required examination is on the attachment welds of the nozzles, not the nozzles themselves, and that the required examination is on the inside radius of the welds. It appears that the nozzles are forged and are attached to the side of a pipe as a branch connection. The welds are deposited on the inside and outside circumference of the nozzles that are attaching to the pipe. Is the staffs understanding correct? If not, please clarify.
3. Section 1 of the relief request states that "... The coolers also have operational ready spares of similar design that are rotated from spare to installed components as required by maintenance..." What is the relevance of this sentence with respect to the required examination of the subject nozzle weld inside radius sections?
4. Briefly describe the design and operation of the letdown coolers. Are the subject nozzles connected to the tube side or shell side of the letdown cooler? What fluids flow in the tube side and shell side of the coolers? If the fluid is not from the reactor coolant system, is the fluid being chemically treated to minimize corrosion?
5. Discuss how the letdown cooler and letdown system would be affected if the subject nozzles/welds fail completely (i.e., what is the consequence if the nozzles fail?). Section 4 of the relief request states that the nozzles are set-on, discuss the possibility of the nozzle ejecting from the pipe.

2

6. Section 9 the relief request states, "The ultrasonic examination of the weld volume adjacent the inside radius section, as required by ASME Section Xl, Table IWB-2500-1, Examination Category B-D, Item Number B3.150 is a more critical location and will provide adequate assurance of the integrity of the welded connection." Please explain (using the drawings in the relief request, as appropriate) where this B3.150 weld is located with respect to the B3.160 welds. For example, Drawing 1-N37804-2 shows 2 welds (WJ32V and WJ31V) are adjacent to nozzle 2-HP-0524. Are WJ32V and WJ31V the B3.150 welds? Discuss whether flaws or indications have been detected in the B3.150 welds. If the latest inspection results of the B3.150 welds have been submitted to the NRC in a 90-day or an annual report, please provide the date of the submittal. What is the weld filler material of the B3.150 welds?
7. Confirm that the subject nozzles are made of 3-inch, stainless steel forging. What is the nozzle wall thickness? What is the material of the pipe that the nozzle is attached to? What is the nominal pipe size and wall thickness of the pipe to which the nozzle is attached?
8. What are the operating and design pressures and temperatures of the subject nozzles?
9. Are the affected welds identification numbers the same as those described in Relief Request 04-ON-015 submitted on December 1, 2004?
10. What is the weld filler material of the affected nozzles? Is the subject weld a full penetration weld, partial penetration weld, or fillet weld?
11. What is the purpose of the nozzles? Is there a pipe connected to the nozzles? Identify pipe supports that are located in the vicinity of the nozzles.
12. Has there been any leakage from or degradation of the subject welds/nozzles?
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