ML16076A225
| ML16076A225 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs, Nine Mile Point, Ginna  |
| Issue date: | 03/16/2016 |
| From: | Blake Purnell Plant Licensing Branch III |
| To: | Tom Loomis Exelon Corp |
| References | |
| MF7018, MF7019, MF7020, MF7021, MF7022 | |
| Download: ML16076A225 (3) | |
Text
NRR-PMDAPEm Resource From: Purnell, Blake Sent: Wednesday, March 16, 2016 10:47 AM To: Loomis, Thomas R:(GenCo-Nuc) (thomas.loomis@exeloncorp.com)
Cc: Poole, Justin; James.Barstow@exeloncorp.com
Subject:
Calvert Cliffs, Nine Mile Point, and R. E. Ginna - Request to Use ASME Code Case N-789 as an Alternative to ASME Code Requirements (CAC Nos. MF7018-MF7022)
Attachments: MF7018 Exelon LC Code Case N-789 RAI.docx Mr. Loomis:
By application dated October 28, 2015 (ADAMS Accession No. ML15301A596), Exelon Generation Company, LLC (the licensee) submitted a request in accordance with Paragraph 50.55a(z)(2) of Title 10 of the Code of Federal Regulations (10 CFR) for a proposed alternative to the requirements of Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, of the American Society of Mechanical Engineers (ASME)
Boiler and Pressure Vessel Code (ASME Code) for Calvert Cliffs Nuclear Power Plant, Units 1 and 2; Nine Mile Point Nuclear Station, Units 1 and 2; and R. E. Ginna Nuclear Power Plant. The proposed alternative would allow the licensee to use ASME Code Case N-789, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate-Energy Carbon Steel Piping for Raw Water Service,Section XI, Division 1, in lieu of specified ASME Code requirements.
The U.S. Nuclear Regulatory Commission staff has reviewed the application and determined that it needs additional information to completed its review. A response to the attached request for additional information shall be provided within 30 days from the date of this email.
If you have any questions please contact me at 301-415-1380 or by email.
Sincerely, Blake Purnell, Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Docket Nos. 50-317, 50-318, 50-220, 50-410, and 50-244 1
Hearing Identifier: NRR_PMDA Email Number: 2713 Mail Envelope Properties (Blake.Purnell@nrc.gov20160316104600)
Subject:
Calvert Cliffs, Nine Mile Point, and R. E. Ginna - Request to Use ASME Code Case N-789 as an Alternative to ASME Code Requirements (CAC Nos. MF7018-MF7022)
Sent Date: 3/16/2016 10:46:32 AM Received Date: 3/16/2016 10:46:00 AM From: Purnell, Blake Created By: Blake.Purnell@nrc.gov Recipients:
"Poole, Justin" <Justin.Poole@nrc.gov>
Tracking Status: None "James.Barstow@exeloncorp.com" <James.Barstow@exeloncorp.com>
Tracking Status: None "Loomis, Thomas R:(GenCo-Nuc) (thomas.loomis@exeloncorp.com)" <thomas.loomis@exeloncorp.com>
Tracking Status: None Post Office:
Files Size Date & Time MESSAGE 1508 3/16/2016 10:46:00 AM MF7018 Exelon LC Code Case N-789 RAI.docx 27827 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received:
REQUEST FOR ADDITIONAL INFORMATION PROPOSED ALTERNATIVE TO USE CODE CASE N-789 CALVERT CLIFFS NUCLEAR POWER PLANT, UNITS 1 AND 2 NINE MILE POINT NUCLEAR STATION, UNITS 1 AND 2 R.E. GINNA NUCLEAR POWER PLANT DOCKET NOS. 50-317, 50-318, 50-220, 50-410, AND 50-244 By application dated October 28, 2015 (ADAMS Accession No. ML15301A596), Exelon Generation Company, LLC (the licensee) submitted a request in accordance with Paragraph 50.55a(z)(2) of Title 10 of the Code of Federal Regulations (10 CFR) for a proposed alternative to the requirements of Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (ASME Code) for Calvert Cliffs Nuclear Power Plant, Units 1 and 2, Nine Mile Point Nuclear Station, Units 1 and 2, and R. E. Ginna Nuclear Power Plant. The proposed alternative would allow the licensee to use ASME Code Case N-789, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate-Energy Carbon Steel Piping for Raw Water Service,Section XI, Division 1, in lieu of specified ASME Code requirements.
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the application and determined that the following information is needed for the staff to complete its review.
RAI-1
Section 3.1(a)(1) of Code Case N-789 states: Pressure pads are designed to retain pressure, and may be used only where the piping is predicted to retain full structural integrity until the next refueling outage assuming a corrosion rate of either 2 times the actual measured corrosion rate in that location, or 4 times the estimated maximum corrosion rate for the system.
For the pressure pad design, confirm that the higher of two times the actual measured corrosion rate or four times the estimated maximum corrosion rate will be used. Confirm that if the actual measured corrosion rate in the degraded location is unavailable, the estimated maximum corrosion rate for the system assumed in the design is calculated based on the same degradation mechanism as the degraded location. If this is not the case, describe how the corrosion rate will be determined and provide justification for not using the worst corrosion rate for the pressure pad design.
ENCLOSURE
NRR-PMDAPEm Resource From: Purnell, Blake Sent: Wednesday, March 16, 2016 10:47 AM To: Loomis, Thomas R:(GenCo-Nuc) (thomas.loomis@exeloncorp.com)
Cc: Poole, Justin; James.Barstow@exeloncorp.com
Subject:
Calvert Cliffs, Nine Mile Point, and R. E. Ginna - Request to Use ASME Code Case N-789 as an Alternative to ASME Code Requirements (CAC Nos. MF7018-MF7022)
Attachments: MF7018 Exelon LC Code Case N-789 RAI.docx Mr. Loomis:
By application dated October 28, 2015 (ADAMS Accession No. ML15301A596), Exelon Generation Company, LLC (the licensee) submitted a request in accordance with Paragraph 50.55a(z)(2) of Title 10 of the Code of Federal Regulations (10 CFR) for a proposed alternative to the requirements of Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, of the American Society of Mechanical Engineers (ASME)
Boiler and Pressure Vessel Code (ASME Code) for Calvert Cliffs Nuclear Power Plant, Units 1 and 2; Nine Mile Point Nuclear Station, Units 1 and 2; and R. E. Ginna Nuclear Power Plant. The proposed alternative would allow the licensee to use ASME Code Case N-789, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate-Energy Carbon Steel Piping for Raw Water Service,Section XI, Division 1, in lieu of specified ASME Code requirements.
The U.S. Nuclear Regulatory Commission staff has reviewed the application and determined that it needs additional information to completed its review. A response to the attached request for additional information shall be provided within 30 days from the date of this email.
If you have any questions please contact me at 301-415-1380 or by email.
Sincerely, Blake Purnell, Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Docket Nos. 50-317, 50-318, 50-220, 50-410, and 50-244 1
Hearing Identifier: NRR_PMDA Email Number: 2713 Mail Envelope Properties (Blake.Purnell@nrc.gov20160316104600)
Subject:
Calvert Cliffs, Nine Mile Point, and R. E. Ginna - Request to Use ASME Code Case N-789 as an Alternative to ASME Code Requirements (CAC Nos. MF7018-MF7022)
Sent Date: 3/16/2016 10:46:32 AM Received Date: 3/16/2016 10:46:00 AM From: Purnell, Blake Created By: Blake.Purnell@nrc.gov Recipients:
"Poole, Justin" <Justin.Poole@nrc.gov>
Tracking Status: None "James.Barstow@exeloncorp.com" <James.Barstow@exeloncorp.com>
Tracking Status: None "Loomis, Thomas R:(GenCo-Nuc) (thomas.loomis@exeloncorp.com)" <thomas.loomis@exeloncorp.com>
Tracking Status: None Post Office:
Files Size Date & Time MESSAGE 1508 3/16/2016 10:46:00 AM MF7018 Exelon LC Code Case N-789 RAI.docx 27827 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received:
REQUEST FOR ADDITIONAL INFORMATION PROPOSED ALTERNATIVE TO USE CODE CASE N-789 CALVERT CLIFFS NUCLEAR POWER PLANT, UNITS 1 AND 2 NINE MILE POINT NUCLEAR STATION, UNITS 1 AND 2 R.E. GINNA NUCLEAR POWER PLANT DOCKET NOS. 50-317, 50-318, 50-220, 50-410, AND 50-244 By application dated October 28, 2015 (ADAMS Accession No. ML15301A596), Exelon Generation Company, LLC (the licensee) submitted a request in accordance with Paragraph 50.55a(z)(2) of Title 10 of the Code of Federal Regulations (10 CFR) for a proposed alternative to the requirements of Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (ASME Code) for Calvert Cliffs Nuclear Power Plant, Units 1 and 2, Nine Mile Point Nuclear Station, Units 1 and 2, and R. E. Ginna Nuclear Power Plant. The proposed alternative would allow the licensee to use ASME Code Case N-789, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate-Energy Carbon Steel Piping for Raw Water Service,Section XI, Division 1, in lieu of specified ASME Code requirements.
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the application and determined that the following information is needed for the staff to complete its review.
RAI-1
Section 3.1(a)(1) of Code Case N-789 states: Pressure pads are designed to retain pressure, and may be used only where the piping is predicted to retain full structural integrity until the next refueling outage assuming a corrosion rate of either 2 times the actual measured corrosion rate in that location, or 4 times the estimated maximum corrosion rate for the system.
For the pressure pad design, confirm that the higher of two times the actual measured corrosion rate or four times the estimated maximum corrosion rate will be used. Confirm that if the actual measured corrosion rate in the degraded location is unavailable, the estimated maximum corrosion rate for the system assumed in the design is calculated based on the same degradation mechanism as the degraded location. If this is not the case, describe how the corrosion rate will be determined and provide justification for not using the worst corrosion rate for the pressure pad design.
ENCLOSURE