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| number = ML15015A666 | | number = ML15015A666 | ||
| issue date = 01/14/2015 | | issue date = 01/14/2015 | ||
| title = | | title = NRR E-mail Capture - NAPS 1&2: RAI-CLARIFICATION of Reactor Coolant System Heatup and Cooldown Technical Specification Figures (Tac. Nos. MF4707 and MF4708) | ||
| author name = Sreenivas V | | author name = Sreenivas V | ||
| author affiliation = NRC/NRR/DORL/LPLII-1 | | author affiliation = NRC/NRR/DORL/LPLII-1 | ||
| addressee name = Heacock D | | addressee name = Heacock D | ||
| addressee affiliation = Dominion Energy Co | | addressee affiliation = Dominion Energy Co | ||
| docket = 05000339 | | docket = 05000339 | ||
| Line 13: | Line 13: | ||
| document type = E-Mail | | document type = E-Mail | ||
| page count = 3 | | page count = 3 | ||
| project = TAC:MF4707, TAC:MF4708 | |||
| stage = Other | |||
}} | }} | ||
=Text= | |||
{{#Wiki_filter:NRR-PMDAPEm Resource From: Sreenivas, V Sent: Wednesday, January 14, 2015 2:04 PM To: 'david.heacock@dom.com' Cc: 'david.sommers@dom.com'; Pascarelli, Robert; Tom Shaub; Jay Leberstien (jay.leberstien@dom.com); 'Gary D Miller'; Vicki Hull (vicki.hull@dom.com) | |||
==Subject:== | |||
NAPS 1&2: RAI-CLARIFICATION OF REACTOR COOLANT SYSTEM HEATUP AND COOLDOWN TECHNICAL SPECIFICATION FIGURES ( TAC. NOS. MF4707 AND MF4708) | |||
REQUEST FOR ADDITIONAL INFORMATION PROPOSED CHANGES TO NORTH ANNA POWER STATION UNITS 1 AND 2 REGARDING CLARIFICATION OF REACTOR COOLANT SYSTEM HEATUP AND COOLDOWN TECHNICAL SPECIFICATION FIGURES NORTH ANNA POWER STATION, UNITS 1 AND 2 By letter dated August 27, 2014, Virginia Electric Power Company (Dominion, the licensee) provided a proposed license amendment request, Clarification of Reactor Coolant System Heatup and Cooldown Technical Specification Figures (Agencywide Documents Access and Management System (ADAMS) | |||
Accession Number ML14246A190). The licensee submitted a request for changes to the North Anna Power Station (North Anna) Units 1 and 2 Technical Specifications pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.90. The proposed amendment would revise Figures 3.4.3-1, Reactor Coolant System Heatup Limitations and 3.4.3-2, Reactor Coolant System Cooldown Limitations, to address vacuum fill operations. | |||
===RAI 1=== | |||
BACKGROUND 10 CFR Part 50, Appendix G requires that pressure-temperature (P-T) limits be developed to bound all ferritic materials in the reactor vessel (RV). Further, Sections I and IV.A of 10 CFR, Part 50, Appendix G specify that all ferritic reactor coolant pressure boundary (RCPB) components outside of the RV must meet the applicable requirements of American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), | |||
Section III, Rules for Construction of Nuclear Facility Components. | |||
ISSUE As clarified in Regulatory Information Summary (RIS) 2014-11, Information on Licensing Applications for Fracture Toughness Requirements for Ferritic Reactor Coolant Pressure Boundary Components (ADAMS Accession No. ML14149A165), P-T limit calculations for ferritic RV components other than those materials with the highest reference temperature, may define curves that are more limiting than those calculated for the RV beltline shell materials because the consideration of stress levels from structural discontinuities (such as nozzles) may produce a lower allowable pressure. | |||
REQUEST Describe how the P-T limit curves for North Anna Units 1 and 2 consider all ferritic pressure boundary components of the reactor vessel that are predicted to experience a neutron fluence exposure greater than 1x1017 n/cm2 (E > 1 MeV) at the end of the licensed operating period. | |||
If the current P-T limit curves do not consider all ferritic pressure boundary components of the reactor vessel that are predicted to experience a neutron fluence exposure greater than 1x1017 n/cm2 (E > 1 MeV) at the end of the licensed operating period, provide appropriately revised P-T limit curves to the NRC for review. | |||
Please submit the response to these RAIs by February 15, 2015. If you have any questions please contact me at your earliest. | |||
1 | |||
V. Sreenivas, PH.D., C.P.M., | |||
Project Manager, Rm.#O8F6, LPL2-1 North Anna Power Stations, Units 1 and 2 Division of Operating Reactor Licensing-NRR (301) 415-2597, v.sreenivas@nrc.gov | |||
***This email message, and any files transmitted with it, may contain confidential, non-public, sensitive and proprietary data intended solely for the person(s) to whom this email message is directly addressed. | |||
Unauthorized use of the data contained in this message is prohibited. If you are not the intended recipient of this message or have received this message in error, please notify the sender immediately by telephone or email Reply and delete the original message and any attachments without keeping a copy*** | |||
2 | |||
Hearing Identifier: NRR_PMDA Email Number: 1812 Mail Envelope Properties (V.Sreenivas@nrc.gov20150114140400) | |||
==Subject:== | |||
NAPS 1&2: RAI-CLARIFICATION OF REACTOR COOLANT SYSTEM HEATUP AND COOLDOWN TECHNICAL SPECIFICATION FIGURES ( TAC. NOS. MF4707 AND MF4708) | |||
Sent Date: 1/14/2015 2:04:19 PM Received Date: 1/14/2015 2:04:00 PM From: Sreenivas, V Created By: V.Sreenivas@nrc.gov Recipients: | |||
"'david.sommers@dom.com'" <david.sommers@dom.com> | |||
Tracking Status: None "Pascarelli, Robert" <Robert.Pascarelli@nrc.gov> | |||
Tracking Status: None "Tom Shaub" <tom.shaub@dom.com> | |||
Tracking Status: None "Jay Leberstien (jay.leberstien@dom.com)" <jay.leberstien@dom.com> | |||
Tracking Status: None | |||
"'Gary D Miller'" <gary.d.miller@dom.com> | |||
Tracking Status: None "Vicki Hull (vicki.hull@dom.com)" <vicki.hull@dom.com> | |||
Tracking Status: None | |||
"'david.heacock@dom.com'" <david.heacock@dom.com> | |||
Tracking Status: None Post Office: | |||
Files Size Date & Time MESSAGE 3659 1/14/2015 2:04:00 PM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: | |||
Recipients Received:}} | |||
Latest revision as of 15:18, 5 February 2020
| ML15015A666 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 01/14/2015 |
| From: | V Sreenivas Plant Licensing Branch II |
| To: | Heacock D Dominion Energy Co |
| References | |
| TAC MF4707, TAC MF4708 | |
| Download: ML15015A666 (3) | |
Text
NRR-PMDAPEm Resource From: Sreenivas, V Sent: Wednesday, January 14, 2015 2:04 PM To: 'david.heacock@dom.com' Cc: 'david.sommers@dom.com'; Pascarelli, Robert; Tom Shaub; Jay Leberstien (jay.leberstien@dom.com); 'Gary D Miller'; Vicki Hull (vicki.hull@dom.com)
Subject:
NAPS 1&2: RAI-CLARIFICATION OF REACTOR COOLANT SYSTEM HEATUP AND COOLDOWN TECHNICAL SPECIFICATION FIGURES ( TAC. NOS. MF4707 AND MF4708)
REQUEST FOR ADDITIONAL INFORMATION PROPOSED CHANGES TO NORTH ANNA POWER STATION UNITS 1 AND 2 REGARDING CLARIFICATION OF REACTOR COOLANT SYSTEM HEATUP AND COOLDOWN TECHNICAL SPECIFICATION FIGURES NORTH ANNA POWER STATION, UNITS 1 AND 2 By letter dated August 27, 2014, Virginia Electric Power Company (Dominion, the licensee) provided a proposed license amendment request, Clarification of Reactor Coolant System Heatup and Cooldown Technical Specification Figures (Agencywide Documents Access and Management System (ADAMS)
Accession Number ML14246A190). The licensee submitted a request for changes to the North Anna Power Station (North Anna) Units 1 and 2 Technical Specifications pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.90. The proposed amendment would revise Figures 3.4.3-1, Reactor Coolant System Heatup Limitations and 3.4.3-2, Reactor Coolant System Cooldown Limitations, to address vacuum fill operations.
RAI 1
BACKGROUND 10 CFR Part 50, Appendix G requires that pressure-temperature (P-T) limits be developed to bound all ferritic materials in the reactor vessel (RV). Further, Sections I and IV.A of 10 CFR, Part 50, Appendix G specify that all ferritic reactor coolant pressure boundary (RCPB) components outside of the RV must meet the applicable requirements of American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),
Section III, Rules for Construction of Nuclear Facility Components.
ISSUE As clarified in Regulatory Information Summary (RIS) 2014-11, Information on Licensing Applications for Fracture Toughness Requirements for Ferritic Reactor Coolant Pressure Boundary Components (ADAMS Accession No. ML14149A165), P-T limit calculations for ferritic RV components other than those materials with the highest reference temperature, may define curves that are more limiting than those calculated for the RV beltline shell materials because the consideration of stress levels from structural discontinuities (such as nozzles) may produce a lower allowable pressure.
REQUEST Describe how the P-T limit curves for North Anna Units 1 and 2 consider all ferritic pressure boundary components of the reactor vessel that are predicted to experience a neutron fluence exposure greater than 1x1017 n/cm2 (E > 1 MeV) at the end of the licensed operating period.
If the current P-T limit curves do not consider all ferritic pressure boundary components of the reactor vessel that are predicted to experience a neutron fluence exposure greater than 1x1017 n/cm2 (E > 1 MeV) at the end of the licensed operating period, provide appropriately revised P-T limit curves to the NRC for review.
Please submit the response to these RAIs by February 15, 2015. If you have any questions please contact me at your earliest.
1
V. Sreenivas, PH.D., C.P.M.,
Project Manager, Rm.#O8F6, LPL2-1 North Anna Power Stations, Units 1 and 2 Division of Operating Reactor Licensing-NRR (301) 415-2597, v.sreenivas@nrc.gov
- This email message, and any files transmitted with it, may contain confidential, non-public, sensitive and proprietary data intended solely for the person(s) to whom this email message is directly addressed.
Unauthorized use of the data contained in this message is prohibited. If you are not the intended recipient of this message or have received this message in error, please notify the sender immediately by telephone or email Reply and delete the original message and any attachments without keeping a copy***
2
Hearing Identifier: NRR_PMDA Email Number: 1812 Mail Envelope Properties (V.Sreenivas@nrc.gov20150114140400)
Subject:
NAPS 1&2: RAI-CLARIFICATION OF REACTOR COOLANT SYSTEM HEATUP AND COOLDOWN TECHNICAL SPECIFICATION FIGURES ( TAC. NOS. MF4707 AND MF4708)
Sent Date: 1/14/2015 2:04:19 PM Received Date: 1/14/2015 2:04:00 PM From: Sreenivas, V Created By: V.Sreenivas@nrc.gov Recipients:
"'david.sommers@dom.com'" <david.sommers@dom.com>
Tracking Status: None "Pascarelli, Robert" <Robert.Pascarelli@nrc.gov>
Tracking Status: None "Tom Shaub" <tom.shaub@dom.com>
Tracking Status: None "Jay Leberstien (jay.leberstien@dom.com)" <jay.leberstien@dom.com>
Tracking Status: None
"'Gary D Miller'" <gary.d.miller@dom.com>
Tracking Status: None "Vicki Hull (vicki.hull@dom.com)" <vicki.hull@dom.com>
Tracking Status: None
"'david.heacock@dom.com'" <david.heacock@dom.com>
Tracking Status: None Post Office:
Files Size Date & Time MESSAGE 3659 1/14/2015 2:04:00 PM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received: