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| number = ML16026A586 | | number = ML16026A586 | ||
| issue date = 12/08/2015 | | issue date = 12/08/2015 | ||
| title = Draft Request for Additional Information - Emergency Amendment | | title = NRR E-mail Capture - Draft Request for Additional Information - Emergency Amendment | ||
| author name = Regner L | | author name = Regner L | ||
| author affiliation = NRC/NRR/DORL/LPLIV-1 | | author affiliation = NRC/NRR/DORL/LPLIV-1 | ||
| addressee name = Albury C | | addressee name = Albury C, Brost W | ||
| addressee affiliation = South Texas Project Nuclear Operating Co | | addressee affiliation = South Texas Project Nuclear Operating Co | ||
| docket = 05000498 | | docket = 05000498 | ||
| Line 18: | Line 18: | ||
=Text= | =Text= | ||
{{#Wiki_filter: | {{#Wiki_filter:NRR-PMDAPEm Resource From: Regner, Lisa Sent: Tuesday, December 08, 2015 8:02 PM To: Brost, Wendy (webrost@STPEGS.COM); cralbury@stpegs.com Cc: Sterling, Lance (lsterling@STPEGS.COM); Michael Murray; Richards, Drew (amrichards@STPEGS.COM) | ||
); Michael Murray; Richards, Drew (amrichards@STPEGS.COM) | |||
==Subject:== | ==Subject:== | ||
DRAFT Request for Additional | DRAFT Request for Additional Information - Emergency Amendment Importance: High Wendy, Charlie, Below are the draft questions that the staff needs answered for us to complete our review of your Emergency Amendment submitted on December 3. As discussed with you on December 8, your acceptable response is requested within 24 hours, for the staff to make its decision by December 11, as requested in your December 3 submittal. | ||
If you have any questions, please feel free to contact me. | |||
If you have any questions, please feel free to contact me. | |||
Thank you, Lisa | Thank you, Lisa | ||
: 1. Confirm that the most positive moderator density coefficient remains bounding for the moderator feedback effects assumed in Chapter 15.1.5, | : 1. Confirm that the most positive moderator density coefficient remains bounding for the moderator feedback effects assumed in Chapter 15.1.5, Spectrum of Steam System Piping Failures Inside and Outside Containment | ||
: 2. For the Departure from Nucleate Boiling analysis related to Steam Line Break, provide additional information on why the Departure from Nucleate Boiling Ratio changed from 3.011 to 1.811. | : 2. For the Departure from Nucleate Boiling analysis related to Steam Line Break, provide additional information on why the Departure from Nucleate Boiling Ratio changed from 3.011 to 1.811. | ||
: 3. Provide the impacts to the reactor protective system from the modifications to the Digital Rod Position Indication system associated with the removal of control rod D6. | : 3. Provide the impacts to the reactor protective system from the modifications to the Digital Rod Position Indication system associated with the removal of control rod D6. | ||
: 4. Provide the impacts to operator actions or emergency operating procedures as a result of the removal of control rod D6. | : 4. Provide the impacts to operator actions or emergency operating procedures as a result of the removal of control rod D6. | ||
: 5. In order for the staff to assess the potential of the proposed flow restrictor generating loose parts, provide a description of any relevant design features of the flow restrictor, and justify how the thermal expansion of the flow restrictor and its component parts has been addressed. | : 5. In order for the staff to assess the potential of the proposed flow restrictor generating loose parts, provide a description of any relevant design features of the flow restrictor, and justify how the thermal expansion of the flow restrictor and its component parts has been addressed. | ||
: 6. In order for the staff to verify the structural adequacy of the D6 Control Rod Drive Mechanism (CRDM) housing without the drive rod, when subjected to Loss of Cooling Accident or seismic excitations, provide a description of relevant analyses that were performed to model the CRDM without the mass of | : 6. In order for the staff to verify the structural adequacy of the D6 Control Rod Drive Mechanism (CRDM) housing without the drive rod, when subjected to Loss of Cooling Accident or seismic excitations, provide a description of relevant analyses that were performed to model the CRDM without the mass of the drive rod. | ||
Lisa M Regner, Sr. Project Manager, Branch LPLIV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 1 | |||
Lisa.Regner@NRC.Gov Office: O8D08 Mail Stop: O8B01 (301) 415-1906 2 | |||
Hearing Identifier: NRR_PMDA Email Number: 2619 Mail Envelope Properties (9f6e318b32cb43d6982b3644cc128041) | |||
Hearing Identifier: | |||
==Subject:== | ==Subject:== | ||
DRAFT Request for Additional Information - Emergency Amendment | DRAFT Request for Additional Information - Emergency Amendment Sent Date: 12/8/2015 8:01:46 PM Received Date: 12/8/2015 8:01:00 PM From: Regner, Lisa Created By: Lisa.Regner@nrc.gov Recipients: | ||
Tracking Status: None | "Sterling, Lance (lsterling@STPEGS.COM)" <lsterling@STPEGS.COM> | ||
Tracking Status: None | Tracking Status: None "Michael Murray" <mpmurray@STpegs.com> | ||
Tracking Status: None "Richards, Drew (amrichards@STPEGS.COM)" <amrichards@STPEGS.COM> | |||
Tracking Status: None "Brost, Wendy (webrost@STPEGS.COM)" <webrost@STPEGS.COM> | |||
Tracking Status: None "cralbury@stpegs.com" <cralbury@stpegs.com> | |||
Tracking Status: None Post Office: HQPWMSMRS01.nrc.gov Files Size Date & Time MESSAGE 2015 12/8/2015 8:01:00 PM Options Priority: High Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: | |||
Recipients Received: | |||
NRR-PMDAPEm Resource From: Regner, Lisa Sent: Tuesday, December 08, 2015 8:02 PM To: Brost, Wendy (webrost@STPEGS.COM); cralbury@stpegs.com Cc: Sterling, Lance (lsterling@STPEGS.COM); Michael Murray; Richards, Drew (amrichards@STPEGS.COM) | |||
); Michael Murray; Richards, Drew (amrichards@STPEGS.COM) | |||
==Subject:== | ==Subject:== | ||
DRAFT Request for Additional | DRAFT Request for Additional Information - Emergency Amendment Importance: High Wendy, Charlie, Below are the draft questions that the staff needs answered for us to complete our review of your Emergency Amendment submitted on December 3. As discussed with you on December 8, your acceptable response is requested within 24 hours, for the staff to make its decision by December 11, as requested in your December 3 submittal. | ||
If you have any questions, please feel free to contact me. | |||
If you have any questions, please feel free to contact me. | |||
Thank you, Lisa | Thank you, Lisa | ||
: 1. Confirm that the most positive moderator density coefficient remains bounding for the moderator feedback effects assumed in Chapter 15.1.5, | : 1. Confirm that the most positive moderator density coefficient remains bounding for the moderator feedback effects assumed in Chapter 15.1.5, Spectrum of Steam System Piping Failures Inside and Outside Containment | ||
: 2. For the Departure from Nucleate Boiling analysis related to Steam Line Break, provide additional information on why the Departure from Nucleate Boiling Ratio changed from 3.011 to 1.811. | : 2. For the Departure from Nucleate Boiling analysis related to Steam Line Break, provide additional information on why the Departure from Nucleate Boiling Ratio changed from 3.011 to 1.811. | ||
: 3. Provide the impacts to the reactor protective system from the modifications to the Digital Rod Position Indication system associated with the removal of control rod D6. | : 3. Provide the impacts to the reactor protective system from the modifications to the Digital Rod Position Indication system associated with the removal of control rod D6. | ||
: 4. Provide the impacts to operator actions or emergency operating procedures as a result of the removal of control rod D6. | : 4. Provide the impacts to operator actions or emergency operating procedures as a result of the removal of control rod D6. | ||
: 5. In order for the staff to assess the potential of the proposed flow restrictor generating loose parts, provide a description of any relevant design features of the flow restrictor, and justify how the thermal expansion of the flow restrictor and its component parts has been addressed. | : 5. In order for the staff to assess the potential of the proposed flow restrictor generating loose parts, provide a description of any relevant design features of the flow restrictor, and justify how the thermal expansion of the flow restrictor and its component parts has been addressed. | ||
: 6. In order for the staff to verify the structural adequacy of the D6 Control Rod Drive Mechanism (CRDM) housing without the drive rod, when subjected to Loss of Cooling Accident or seismic excitations, provide a description of relevant analyses that were performed to model the CRDM without the mass of | : 6. In order for the staff to verify the structural adequacy of the D6 Control Rod Drive Mechanism (CRDM) housing without the drive rod, when subjected to Loss of Cooling Accident or seismic excitations, provide a description of relevant analyses that were performed to model the CRDM without the mass of the drive rod. | ||
Lisa M Regner, Sr. Project Manager, Branch LPLIV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 1 | |||
the drive rod. | |||
Lisa | Lisa.Regner@NRC.Gov Office: O8D08 Mail Stop: O8B01 (301) 415-1906 2 | ||
Hearing Identifier: | Hearing Identifier: NRR_PMDA Email Number: 2619 Mail Envelope Properties (9f6e318b32cb43d6982b3644cc128041) | ||
==Subject:== | ==Subject:== | ||
DRAFT Request for Additional Information - Emergency Amendment | DRAFT Request for Additional Information - Emergency Amendment Sent Date: 12/8/2015 8:01:46 PM Received Date: 12/8/2015 8:01:00 PM From: Regner, Lisa Created By: Lisa.Regner@nrc.gov Recipients: | ||
Tracking Status: None | "Sterling, Lance (lsterling@STPEGS.COM)" <lsterling@STPEGS.COM> | ||
Tracking Status: None | Tracking Status: None "Michael Murray" <mpmurray@STpegs.com> | ||
Tracking Status: None "Richards, Drew (amrichards@STPEGS.COM)" <amrichards@STPEGS.COM> | |||
Files | Tracking Status: None "Brost, Wendy (webrost@STPEGS.COM)" <webrost@STPEGS.COM> | ||
Tracking Status: None "cralbury@stpegs.com" <cralbury@stpegs.com> | |||
Options | Tracking Status: None Post Office: HQPWMSMRS01.nrc.gov Files Size Date & Time MESSAGE 2015 12/8/2015 8:01:00 PM Options Priority: High Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: | ||
Recipients Received:}} | |||
Latest revision as of 19:44, 4 December 2019
| ML16026A586 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 12/08/2015 |
| From: | Lisa Regner Plant Licensing Branch IV |
| To: | Albury C, Brost W South Texas |
| References | |
| MF7142 | |
| Download: ML16026A586 (3) | |
Text
NRR-PMDAPEm Resource From: Regner, Lisa Sent: Tuesday, December 08, 2015 8:02 PM To: Brost, Wendy (webrost@STPEGS.COM); cralbury@stpegs.com Cc: Sterling, Lance (lsterling@STPEGS.COM); Michael Murray; Richards, Drew (amrichards@STPEGS.COM)
Subject:
DRAFT Request for Additional Information - Emergency Amendment Importance: High Wendy, Charlie, Below are the draft questions that the staff needs answered for us to complete our review of your Emergency Amendment submitted on December 3. As discussed with you on December 8, your acceptable response is requested within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, for the staff to make its decision by December 11, as requested in your December 3 submittal.
If you have any questions, please feel free to contact me.
Thank you, Lisa
- 1. Confirm that the most positive moderator density coefficient remains bounding for the moderator feedback effects assumed in Chapter 15.1.5, Spectrum of Steam System Piping Failures Inside and Outside Containment
- 2. For the Departure from Nucleate Boiling analysis related to Steam Line Break, provide additional information on why the Departure from Nucleate Boiling Ratio changed from 3.011 to 1.811.
- 3. Provide the impacts to the reactor protective system from the modifications to the Digital Rod Position Indication system associated with the removal of control rod D6.
- 4. Provide the impacts to operator actions or emergency operating procedures as a result of the removal of control rod D6.
- 5. In order for the staff to assess the potential of the proposed flow restrictor generating loose parts, provide a description of any relevant design features of the flow restrictor, and justify how the thermal expansion of the flow restrictor and its component parts has been addressed.
- 6. In order for the staff to verify the structural adequacy of the D6 Control Rod Drive Mechanism (CRDM) housing without the drive rod, when subjected to Loss of Cooling Accident or seismic excitations, provide a description of relevant analyses that were performed to model the CRDM without the mass of the drive rod.
Lisa M Regner, Sr. Project Manager, Branch LPLIV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 1
Lisa.Regner@NRC.Gov Office: O8D08 Mail Stop: O8B01 (301) 415-1906 2
Hearing Identifier: NRR_PMDA Email Number: 2619 Mail Envelope Properties (9f6e318b32cb43d6982b3644cc128041)
Subject:
DRAFT Request for Additional Information - Emergency Amendment Sent Date: 12/8/2015 8:01:46 PM Received Date: 12/8/2015 8:01:00 PM From: Regner, Lisa Created By: Lisa.Regner@nrc.gov Recipients:
"Sterling, Lance (lsterling@STPEGS.COM)" <lsterling@STPEGS.COM>
Tracking Status: None "Michael Murray" <mpmurray@STpegs.com>
Tracking Status: None "Richards, Drew (amrichards@STPEGS.COM)" <amrichards@STPEGS.COM>
Tracking Status: None "Brost, Wendy (webrost@STPEGS.COM)" <webrost@STPEGS.COM>
Tracking Status: None "cralbury@stpegs.com" <cralbury@stpegs.com>
Tracking Status: None Post Office: HQPWMSMRS01.nrc.gov Files Size Date & Time MESSAGE 2015 12/8/2015 8:01:00 PM Options Priority: High Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received:
NRR-PMDAPEm Resource From: Regner, Lisa Sent: Tuesday, December 08, 2015 8:02 PM To: Brost, Wendy (webrost@STPEGS.COM); cralbury@stpegs.com Cc: Sterling, Lance (lsterling@STPEGS.COM); Michael Murray; Richards, Drew (amrichards@STPEGS.COM)
Subject:
DRAFT Request for Additional Information - Emergency Amendment Importance: High Wendy, Charlie, Below are the draft questions that the staff needs answered for us to complete our review of your Emergency Amendment submitted on December 3. As discussed with you on December 8, your acceptable response is requested within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, for the staff to make its decision by December 11, as requested in your December 3 submittal.
If you have any questions, please feel free to contact me.
Thank you, Lisa
- 1. Confirm that the most positive moderator density coefficient remains bounding for the moderator feedback effects assumed in Chapter 15.1.5, Spectrum of Steam System Piping Failures Inside and Outside Containment
- 2. For the Departure from Nucleate Boiling analysis related to Steam Line Break, provide additional information on why the Departure from Nucleate Boiling Ratio changed from 3.011 to 1.811.
- 3. Provide the impacts to the reactor protective system from the modifications to the Digital Rod Position Indication system associated with the removal of control rod D6.
- 4. Provide the impacts to operator actions or emergency operating procedures as a result of the removal of control rod D6.
- 5. In order for the staff to assess the potential of the proposed flow restrictor generating loose parts, provide a description of any relevant design features of the flow restrictor, and justify how the thermal expansion of the flow restrictor and its component parts has been addressed.
- 6. In order for the staff to verify the structural adequacy of the D6 Control Rod Drive Mechanism (CRDM) housing without the drive rod, when subjected to Loss of Cooling Accident or seismic excitations, provide a description of relevant analyses that were performed to model the CRDM without the mass of the drive rod.
Lisa M Regner, Sr. Project Manager, Branch LPLIV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 1
Lisa.Regner@NRC.Gov Office: O8D08 Mail Stop: O8B01 (301) 415-1906 2
Hearing Identifier: NRR_PMDA Email Number: 2619 Mail Envelope Properties (9f6e318b32cb43d6982b3644cc128041)
Subject:
DRAFT Request for Additional Information - Emergency Amendment Sent Date: 12/8/2015 8:01:46 PM Received Date: 12/8/2015 8:01:00 PM From: Regner, Lisa Created By: Lisa.Regner@nrc.gov Recipients:
"Sterling, Lance (lsterling@STPEGS.COM)" <lsterling@STPEGS.COM>
Tracking Status: None "Michael Murray" <mpmurray@STpegs.com>
Tracking Status: None "Richards, Drew (amrichards@STPEGS.COM)" <amrichards@STPEGS.COM>
Tracking Status: None "Brost, Wendy (webrost@STPEGS.COM)" <webrost@STPEGS.COM>
Tracking Status: None "cralbury@stpegs.com" <cralbury@stpegs.com>
Tracking Status: None Post Office: HQPWMSMRS01.nrc.gov Files Size Date & Time MESSAGE 2015 12/8/2015 8:01:00 PM Options Priority: High Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received: