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| | number = ML16302A453 | | | number = ML16302A453 |
| | issue date = 12/12/2016 | | | issue date = 12/12/2016 |
| | title = South Texas Project, Units 1 and 2 - Closeout of Request for Additional Information Questions That Are No Longer Applicable, Resolution of Generic Safety Issue (GSI) 191 (CAC Nos. MF2400-MF2409) | | | title = Closeout of Request for Additional Information Questions That Are No Longer Applicable, Resolution of Generic Safety Issue (GSI) 191 (CAC Nos. MF2400-MF2409) |
| | author name = Regner L M | | | author name = Regner L |
| | author affiliation = NRC/NRR/DORL/LPLIV-1 | | | author affiliation = NRC/NRR/DORL/LPLIV-1 |
| | addressee name = Powell G T | | | addressee name = Powell G |
| | addressee affiliation = South Texas Project Nuclear Operating Co | | | addressee affiliation = South Texas Project Nuclear Operating Co |
| | docket = 05000498, 05000499 | | | docket = 05000498, 05000499 |
| | license number = NPF-076, NPF-080 | | | license number = NPF-076, NPF-080 |
| | contact person = Regner L M | | | contact person = Regner L |
| | case reference number = CAC MF2400, CAC MF2401, CAC MF2402, CAC MF2403, CAC MF2404, CAC MF2405, CAC MF2406, CAC MF2407, CAC MF2408, CAC MF2409 | | | case reference number = CAC MF2400, CAC MF2401, CAC MF2402, CAC MF2403, CAC MF2404, CAC MF2405, CAC MF2406, CAC MF2407, CAC MF2408, CAC MF2409 |
| | document type = Letter, Request for Additional Information (RAI) | | | document type = Letter, Request for Additional Information (RAI) |
| | page count = 6 | | | page count = 6 |
| | project = CAC:MF2400, CAC:MF2401, CAC:MF2402, CAC:MF2403, CAC:MF2404, CAC:MF2405, CAC:MF2406, CAC:MF2407, CAC:MF2408, CAC:MF2409 | | | project = CAC:MF2400, CAC:MF2401, CAC:MF2402, CAC:MF2403, CAC:MF2404, CAC:MF2405, CAC:MF2406, CAC:MF2407, CAC:MF2408, CAC:MF2409 |
| | | stage = RAI |
| }} | | }} |
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| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. G. T. Powell Executive Vice President and CNO STP Nuclear Operating Company South Texas Project P.O. Box 289 VVadsworth, TX 77483 December 12, 2016 SUBJECT: SOUTH TEXAS PROJECT, UNITS 1 AND 2 -RE: CLOSEOUT OF REQUEST FOR INFORMATION QUESTIONS THAT ARE NO LONGER APPLICABLE ASSOCIATED VVITH THE RESOLUTION OF GENERIC SAFETY ISSUE 191 (CAC NOS. MF2400, MF2401, MF2402, MF2403, MF2404, MF2405, MF2406, MF2407, MF2408, AND MF2409) Dear Mr. Powell: On September 13, 2004, the U.S. Nuclear Regulatory Commission (NRC) issued Generic Letter (GL) 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-VVater Reactors" (Agencywide Documents Access and Management System (ADAMS) Accession No. ML042360586), to address a generic safety concern, generic safety issue (GSI) 191, over possible blockage of emergency core cooling sump strainers during design-basis accidents at pressurized-water power reactors. The STP Nuclear Operating Company (STPNOC) responded to GL 2004-02 for the South Texas Project, Units 1 and 2 (STP), by letter dated March 8, 2005, as supplemented by letters dated July 13 and August 31, 2005; January 30, 2006; and February 29 and December 11, 2008 (ADAMS Accession Nos. ML050770105, ML052000281, ML052500311, ML060370145, ML080700338, and ML083520326, respectively). On June 4, 2012 (ADAMS Accession No. ML 13025A360), STPNOC submitted a letter stating its intention to resolve GSl-191, site specifically, through a risk-informed approach; further, it stated it did not intend to respond to the open NRC request for additional information (RAI) questions issued by letters dated June 2, 2005, February 9, 2006, and December 23, 2009 (ADAMS Accession Nos. ML051530285, ML060390246, and ML093410607, respectively). The licensee stated that it would not use a deterministic method and would submit a license amendment request and exemption requests to resolve GSl-191. Subsequently, by letter dated June 19, 2013 (ADAMS Package Accession No. ML 131750250), as supplemented by letter dated October 3, 2013 (ADAMS Accession No. ML 13295A222), STPNOC submitted license amendment and exemption requests. The NRC staff's review of the license amendment and exemption requests is ongoing; however, the NRC staff has determined that the June 4, 2012, license amendment and exemption requests supersede the previous submittals; therefore, the NRC's review of G. Powell -2 -STPNOC's efforts to respond to GL 2004-02 prior to June 2012 have been terminated. For this reason, the RAls issued on June 2, 2005, February 9, 2006, and December 23, 2009, are no longer applicable. By letters dated October 31, November 13, November 21 and December 23, 2013 (two letters); January 9, February 13, February 27, March 17, March 18, May 15 (two letters), May 22, June 25, and July 15, 2014; March 10, and March 25, 2015 (ADAMS Accession Nos. ML13323A673, ML13323A128, ML13338A165, ML14015A312, ML14015A311, ML 14029A533, ML 14052A110, ML 14072A075, ML 14086A383, ML 14087A126, ML 14149A353, ML 14149A354, ML 14149A439, ML 14178A467, ML 14202A045, ML 15072A092, and ML 15091A440, respectively), STPNOC submitted supplemental information in support of the license amendment and exemption requests to resolve GSl-191 using a risk-informed methodology. By letter dated August 20, 2015, STPNOC provided a supplement to the license amendment and exemption requests changing its approach from strictly risk-informed, to a deterministic and risk-informed methodology, called 'RoverD'. Additional supplements were submitted by STPNOC on April 13, May 11, June 9, June 16, July 18, July 21 (two letters), July 28, September 12, October 20, and December 7, 20161 (ADAMS Accession Nos. ML 15246A125, ML 16111B204, ML 16154A117, ML 16176A148, ML 16196A241, ML 16209A226, ML 16229A189, ML 16230A232, ML 16221A393, ML 16272A162, ML 16302A015, and [see footnote], respectively) in response to NRC staff RAls. Due to the methodology change described in the letter dated August 20, 2015, the licensee submitted a clarification letter dated June 9, 2016, providing a list of RAI question responses that it stated are no longer applicable with the basis for eliminating this content from the NRC staff's review. The NRC staff reviewed the questions and the licensee's basis for removing questions from the NRC staff's review as provided in the June 9 and December 7, 2016, letters. The NRC's conclusions are provided in the Enclosure to this document. This was discussed with Mr. Wayne Harrison, Mr. Drew Richards, and Mr. Steven Blossom of your staff on November 16, 2016. 1 The ADAMS Accession No. was not available at the time of the issuance of this letter. | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 12, 2016 Mr. G. T. Powell Executive Vice President and CNO STP Nuclear Operating Company South Texas Project P.O. Box 289 VVadsworth, TX 77483 |
| G. Powell -3 -If you have any questions, please contact me at 301-415-1906 or via e-mail at Lisa.Regner@nrc.gov. Docket Nos. 50-498 and 50-499 Enclosure: As stated cc w/encl: Distribution via Listserv Lisa M. Regner, Senior Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation REQUEST FOR ADDITIONAL INFORMATION QUESTIONS THAT ARE NO LONGER APPLICABLE RESOLUTION OF GENERIC SAFETY ISSUE 191 STP NUCLEAR OPERATING COMPANY SOUTH TEXAS PROJECT, UNITS 1AND2 DOCKET NOS. 50-498 AND 50-499 The NRC staff determined that the following questions in request for additional information (RAI) letter dated April 15, 2014 (ADAMS Accession No. ML 14087A075), are no longer applicable: | | |
| * CASA Grande, General -1.a, 1.b, and 1.c. | | ==SUBJECT:== |
| * CASA Grande, Plant Configuration -1.a, 1.b, 2.a, 2.b, 3.a, 3.b, and 3.c. | | SOUTH TEXAS PROJECT, UNITS 1 AND 2 - RE: CLOSEOUT OF REQUEST FOR INFORMATION QUESTIONS THAT ARE NO LONGER APPLICABLE ASSOCIATED VVITH THE RESOLUTION OF GENERIC SAFETY ISSUE 191 (CAC NOS. MF2400, MF2401, MF2402, MF2403, MF2404, MF2405, MF2406, MF2407, MF2408, AND MF2409) |
| * CASA Grande, LOCA [loss-of-coolant accident] Frequencies -1.a, 1. b, 3, and 4. | | |
| * CASA Grande to PRA [probabilistic risk assessment] Interface, General -1.a, 1.b, 2.a, 2.b, 3, 4.a, 4.b, 4.c, 5, 6.a, 6.b, and 6.c. | | ==Dear Mr. Powell:== |
| | |
| | On September 13, 2004, the U.S. Nuclear Regulatory Commission (NRC) issued Generic Letter (GL) 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-VVater Reactors" (Agencywide Documents Access and Management System (ADAMS) Accession No. ML042360586), to address a generic safety concern, generic safety issue (GSI) 191, over possible blockage of emergency core cooling sump strainers during design-basis accidents at pressurized-water power reactors. |
| | The STP Nuclear Operating Company (STPNOC) responded to GL 2004-02 for the South Texas Project, Units 1 and 2 (STP), by letter dated March 8, 2005, as supplemented by letters dated July 13 and August 31, 2005; January 30, 2006; and February 29 and December 11, 2008 (ADAMS Accession Nos. ML050770105, ML052000281, ML052500311, ML060370145, ML080700338, and ML083520326, respectively). |
| | On June 4, 2012 (ADAMS Accession No. ML13025A360), STPNOC submitted a letter stating its intention to resolve GSl-191, site specifically, through a risk-informed approach; further, it stated it did not intend to respond to the open NRC request for additional information (RAI) questions issued by letters dated June 2, 2005, February 9, 2006, and December 23, 2009 (ADAMS Accession Nos. ML051530285, ML060390246, and ML093410607, respectively). The licensee stated that it would not use a deterministic method and would submit a license amendment request and exemption requests to resolve GSl-191. |
| | Subsequently, by letter dated June 19, 2013 (ADAMS Package Accession No. ML131750250), |
| | as supplemented by letter dated October 3, 2013 (ADAMS Accession No. ML13295A222), |
| | STPNOC submitted license amendment and exemption requests. |
| | The NRC staff's review of the license amendment and exemption requests is ongoing; however, the NRC staff has determined that the June 4, 2012, license amendment and exemption requests supersede the previous submittals; therefore, the NRC's review of |
| | |
| | G. Powell STPNOC's efforts to respond to GL 2004-02 prior to June 2012 have been terminated. For this reason, the RAls issued on June 2, 2005, February 9, 2006, and December 23, 2009, are no longer applicable. |
| | By letters dated October 31, November 13, November 21 and December 23, 2013 (two letters); |
| | January 9, February 13, February 27, March 17, March 18, May 15 (two letters), May 22, June 25, and July 15, 2014; March 10, and March 25, 2015 (ADAMS Accession Nos. ML13323A673, ML13323A128, ML13338A165, ML14015A312, ML14015A311, ML14029A533, ML14052A110, ML14072A075, ML14086A383, ML14087A126, ML14149A353, ML14149A354, ML14149A439, ML14178A467, ML14202A045, ML15072A092, and ML15091A440, respectively), STPNOC submitted supplemental information in support of the license amendment and exemption requests to resolve GSl-191 using a risk-informed methodology. |
| | By letter dated August 20, 2015, STPNOC provided a supplement to the license amendment and exemption requests changing its approach from strictly risk-informed, to a deterministic and risk-informed methodology, called 'RoverD'. Additional supplements were submitted by STPNOC on April 13, May 11, June 9, June 16, July 18, July 21 (two letters), July 28, September 12, October 20, and December 7, 2016 1 (ADAMS Accession Nos. ML15246A125, ML16111B204, ML16154A117, ML16176A148, ML16196A241, ML16209A226, ML16229A189, ML16230A232, ML16221A393, ML16272A162, ML16302A015, and [see footnote], respectively) in response to NRC staff RAls. |
| | Due to the methodology change described in the letter dated August 20, 2015, the licensee submitted a clarification letter dated June 9, 2016, providing a list of RAI question responses that it stated are no longer applicable with the basis for eliminating this content from the NRC staff's review. |
| | The NRC staff reviewed the questions and the licensee's basis for removing questions from the NRC staff's review as provided in the June 9 and December 7, 2016, letters. The NRC's conclusions are provided in the Enclosure to this document. |
| | This was discussed with Mr. Wayne Harrison, Mr. Drew Richards, and Mr. Steven Blossom of your staff on November 16, 2016. |
| | 1 The ADAMS Accession No. was not available at the time of the issuance of this letter. |
| | |
| | G. Powell If you have any questions, please contact me at 301-415-1906 or via e-mail at Lisa.Regner@nrc.gov. |
| | Lisa M. Regner, Senior Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-498 and 50-499 |
| | |
| | ==Enclosure:== |
| | |
| | As stated cc w/encl: Distribution via Listserv |
| | |
| | REQUEST FOR ADDITIONAL INFORMATION QUESTIONS THAT ARE NO LONGER APPLICABLE RESOLUTION OF GENERIC SAFETY ISSUE 191 STP NUCLEAR OPERATING COMPANY SOUTH TEXAS PROJECT, UNITS 1AND2 DOCKET NOS. 50-498 AND 50-499 The NRC staff determined that the following questions in request for additional information (RAI) letter dated April 15, 2014 (ADAMS Accession No. ML14087A075), are no longer applicable: |
| | * CASA Grande, General - 1.a, 1.b, and 1.c. |
| | * CASA Grande, Plant Configuration - 1.a, 1.b, 2.a, 2.b, 3.a, 3.b, and 3.c. |
| | * CASA Grande, LOCA [loss-of-coolant accident] Frequencies - 1.a, 1. b, 3, and 4. |
| | * CASA Grande to PRA [probabilistic risk assessment] Interface, General - 1.a, 1.b, 2.a, 2.b, 3, 4.a, 4.b, 4.c, 5, 6.a, 6.b, and 6.c. |
| * STP PRA Model, Success Criteria -1, 2.a, 2.b, 3.a, 3.b, and 3.d. | | * STP PRA Model, Success Criteria -1, 2.a, 2.b, 3.a, 3.b, and 3.d. |
| * STP PRA Model, Human Reliability Analysis -1, 2, 3.a, 3.b, 3.c, 4.a, 4.b, 5, and 6. | | * STP PRA Model, Human Reliability Analysis - 1, 2, 3.a, 3.b, 3.c, 4.a, 4.b, 5, and 6. |
| * Results Interpretation, Quantification -1.a, 1.b, and 2. | | * Results Interpretation, Quantification - 1.a, 1.b, and 2. |
| * Results Interpretation, Uncertainty Analysis -1.a, 1.b, 1.c, 4.a, 4.b, 4.c, 4.d, 5, and 6. | | * Results Interpretation, Uncertainty Analysis - 1.a, 1.b, 1.c, 4.a, 4.b, 4.c, 4.d, 5, and 6. |
| * Radiation Protection and Consequence Branch -1 and 3. | | * Radiation Protection and Consequence Branch - 1 and 3. |
| * Mechanical and Civil Engineering Branch -1. | | * Mechanical and Civil Engineering Branch - 1. |
| * Component Performance, NOE [non-destructive examination] and Testing Branch (EPNB) -1, 2, 3, 4, 5, 6.a, and 6.b. | | * Component Performance, NOE [non-destructive examination] and Testing Branch (EPNB) - 1, 2, 3, 4, 5, 6.a, and 6.b. |
| * Steam Generator tube Integrity and Chemical Engineering Branch (ESGB), Chemical Effects -1.a, 1.b, 1.c, 1.d, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11.a, 11.b, 12, 13.a, 13.b, 13.c, 14.a, 14.b, 14.c, 15, 16, 17, 18.a, 18.b, 18.c, 19, 20, 21, 22.a, and 22.b. | | * Steam Generator tube Integrity and Chemical Engineering Branch (ESGB), Chemical Effects - 1.a, 1.b, 1.c, 1.d, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11.a, 11.b, 12, 13.a, 13.b, 13.c, 14.a, 14.b, 14.c, 15, 16, 17, 18.a, 18.b, 18.c, 19, 20, 21, 22.a, and 22.b. |
| * ESGB, Coatings -2, 4, 5, 6.a, 6.b, and 6.c. | | * ESGB, Coatings - 2, 4, 5, 6.a, 6.b, and 6.c. |
| * Containment and Ventilation Branch (SCVB) -1.b, 2.b, 3.b, 5, 8, and 9.b. | | * Containment and Ventilation Branch (SCVB) - 1.b, 2.b, 3.b, 5, 8, and 9.b. |
| * Reactor Systems Branch (SRXB) -2.a, 2.b, 2.c, 2.d, 2.e, 5.a, 5.b, 5.c, 6, and 8. Enclosure | | * Reactor Systems Branch (SRXB) - 2.a, 2.b, 2.c, 2.d, 2.e, 5.a, 5.b, 5.c, 6, and 8. |
| -2 -* Safety Issue Resolution Branch (SSIB)-3, 5, 9, 11.a, 11.b, 11.d, 11.e, 14, 15.a, 15.b, 15.c, 15.d, 16.a, 16.b, 16.c, 16.d, 17.a, 17.b, 17.c, 17.d, 17.e, 17.f, 18, 19, 20, 21, 22, 23, 24, 25, 26.a, 26.b, 26.d, 26.e, 26.f, 28, 30, 33, 34, 35, 36, 37, 38, 40, and 41.a.
| | Enclosure |
| * Technical Specifications Branch (STSB) -1 and 2. The NRC staff determined that the response to SNPB-4 in the April 15, 2015, RAI is no longer applicable because the plant's licensing basis analysis for boric acid precipitation (BAP) was changed. The original RAI and its response are superseded by question SNPB-3-33 in an NRC RAI dated April 11, 2016 (ADAMS Accession No. ML 16082A507), which discussed the new STP BAP analysis. The NRC staff determined that question CASA Grande, LOCA Frequencies -1.b is still applicable; there is information the NRC staff intends to use in its safety evaluation regardless of STP's methodology change. This was discussed with Wayne Harrison of your staff and a mutually agreeable resolution determined as ... The NRC staff determined that the following questions in RAI dated March 3, 2015 (ADAMS Accession No. ML 14357A171), are no longer applicable: | | * Safety Issue Resolution Branch (SSIB)-3, 5, 9, 11.a, 11.b, 11.d, 11.e, 14, 15.a, 15.b, 15.c, 15.d, 16.a, 16.b, 16.c, 16.d, 17.a, 17.b, 17.c, 17.d, 17.e, 17.f, 18, 19, 20, 21, 22, 23, 24, 25, 26.a, 26.b, 26.d, 26.e, 26.f, 28, 30, 33, 34, 35, 36, 37, 38, 40, and 41.a. |
| * PRA Licensing Branch (APLA), Project Quality Assurance -2. | | * Technical Specifications Branch (STSB) - 1 and 2. |
| * ESGB, Chemical Effects -33 and 34. | | The NRC staff determined that the response to SNPB-4 in the April 15, 2015, RAI is no longer applicable because the plant's licensing basis analysis for boric acid precipitation (BAP) was changed. The original RAI and its response are superseded by question SNPB-3-33 in an NRC RAI dated April 11, 2016 (ADAMS Accession No. ML16082A507), which discussed the new STP BAP analysis. |
| * SSIB -45, 53, and 58. The NRC staff determined that questions SCVB -10 through 18 in the RAI dated March 3, 2015, are still applicable. The licensee's revised responses to each of these questions were provided in an August 20, 2015, supplement (ADAMS Accession No. ML 15246A 128) and the NRC staff intends to use the information in its safety evaluation. This information was discussed with Mr. Wayne Harrison of your staff on xxxxx. | | The NRC staff determined that question CASA Grande, LOCA Frequencies - 1.b is still applicable; there is information the NRC staff intends to use in its safety evaluation regardless of STP's methodology change. This was discussed with Wayne Harrison of your staff and a mutually agreeable resolution determined as ... |
| G. Powell -3 -If you have any questions, please contact me at 301-415-1906 or via e-mail at Lisa.Regner@nrc.gov. Docket Nos. 50-498 and 50-499 Enclosure: As stated Sincerely, /RA/ Lisa M. Regner, Senior Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation cc w/encl: Distribution via Listserv DISTRIBUTION: PUBLIC LPL4-1 Reading RidsACRS_MailCTR Resource RidsNrrDeEmcb Resource RidsNrrDeEpnb Resource RidsNrrDeEsgb Resource RidsNrrDorllpl4-1 Resource RidsNrrDraAphb Resource RidsNrrDraApla Resource RidsNrrDraArcb Resource RidsNrrDssSnpb Resource RidsNrrDssSrxb Resource RidsNrrDssSsib Resource RidsNrrDssStsb Resource RidsNrrLAJBurkhardt Resource RidsNrrPMSouthTexas Resource RidsRgn4MailCenter Resource ADAMS A ccess1on N ML 16302A 3 0. 45 *b 1yemail OFFICE NRR/DORL/LPL4-1 /PM NRR/DORL/LPL4-1 /LA NRR/DE/EMCB/BC* NRR/DE/EPNB/BC* NAME LRegner JBurkhardt JQuichocho DAiiey DATE 10/31/16 10/31/16 11/30/16 10/26/16 OFFICE NRR/DE/ESGB/BC(A)* NRR/DRA/APLA/BC* NRR/DRA/ARCB/BC* NAME PKlein SRosenberg US hoop DATE 11/22/16 11/30/16 12/07/16 OFFICE NRR/DSS/SNPB/BC* NRR/DSS/SRXB/BC* NRR/DSS/SSIB/BC* NAME Rlukes EOesterle (JWhitman for) VCusumano DATE 11/30/16 11/22/16 11/30/16 OFFICE NRR/DSS/STSB/BC* NRR/DORL/LPL4-1 /BC NRR/DORL/LPL4-1 /PM NAME AKlein RPascarelli LRegner DATE 10/24/16 12/09/16 12/12/16 OFFICIAL RECORD COPY | | The NRC staff determined that the following questions in RAI dated March 3, 2015 (ADAMS Accession No. ML14357A171), are no longer applicable: |
| }} | | * PRA Licensing Branch (APLA), Project Quality Assurance - 2. |
| | * ESGB, Chemical Effects - 33 and 34. |
| | * SSIB -45, 53, and 58. |
| | The NRC staff determined that questions SCVB - 10 through 18 in the RAI dated March 3, 2015, are still applicable. The licensee's revised responses to each of these questions were provided in an August 20, 2015, supplement (ADAMS Accession No. ML15246A128) and the NRC staff intends to use the information in its safety evaluation. |
| | This information was discussed with Mr. Wayne Harrison of your staff on xxxxx. |
| | |
| | G. Powell If you have any questions, please contact me at 301-415-1906 or via e-mail at Lisa.Regner@nrc.gov. |
| | Sincerely, |
| | /RA/ |
| | Lisa M. Regner, Senior Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-498 and 50-499 |
| | |
| | ==Enclosure:== |
| | |
| | As stated cc w/encl: Distribution via Listserv DISTRIBUTION: |
| | PUBLIC RidsNrrDraArcb Resource LPL4-1 Reading RidsNrrDssSnpb Resource RidsACRS_MailCTR Resource RidsNrrDssSrxb Resource RidsNrrDeEmcb Resource RidsNrrDssSsib Resource RidsNrrDeEpnb Resource RidsNrrDssStsb Resource RidsNrrDeEsgb Resource RidsNrrLAJBurkhardt Resource RidsNrrDorllpl4-1 Resource RidsNrrPMSouthTexas Resource RidsNrrDraAphb Resource RidsRgn4MailCenter Resource RidsNrrDraApla Resource ADAMS A ccess1on N0. ML16302A453 *b1yemail OFFICE NRR/DORL/LPL4-1 /PM NRR/DORL/LPL4-1 /LA NRR/DE/EMCB/BC* NRR/DE/EPNB/BC* |
| | NAME LRegner JBurkhardt JQuichocho DAiiey DATE 10/31/16 10/31/16 11/30/16 10/26/16 OFFICE NRR/DE/ESGB/BC(A)* NRR/DRA/APLA/BC* NRR/DRA/ARCB/BC* |
| | NAME PKlein SRosenberg US hoop DATE 11/22/16 11/30/16 12/07/16 OFFICE NRR/DSS/SNPB/BC* NRR/DSS/SRXB/BC* NRR/DSS/SSIB/BC* |
| | NAME Rlukes EOesterle (JWhitman for) VCusumano DATE 11/30/16 11/22/16 11/30/16 OFFICE NRR/DSS/STSB/BC* NRR/DORL/LPL4-1 /BC NRR/DORL/LPL4-1 /PM NAME AKlein RPascarelli LRegner DATE 10/24/16 12/09/16 12/12/16 OFFICIAL RECORD COPY}} |
Letter Sequence RAI |
|---|
CAC:MF2400, Control Room Habitability (Approved, Closed) CAC:MF2401, Control Room Habitability (Approved, Closed) CAC:MF2402, Control Room Habitability (Approved, Closed) CAC:MF2403, Control Room Habitability (Approved, Closed) CAC:MF2404, Control Room Habitability (Approved, Closed) CAC:MF2405, Control Room Habitability (Approved, Closed) CAC:MF2406, Control Room Habitability (Approved, Closed) CAC:MF2407, Control Room Habitability (Approved, Closed) CAC:MF2408, Control Room Habitability (Approved, Closed) CAC:MF2409, Control Room Habitability (Approved, Closed) |
Administration
- Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting
|
MONTHYEARML15274A5992015-10-0101 October 2015
10-01-15 Public Phone Call
Project stage: Request
ML16011A0612016-02-0202 February 2016
Summary of 10/1/15 Meeting with STP Nuclear Operating Company to Discuss Revised Pilot Submittal and Request for Exemptions for a Risk-Informed Approach to Resolve Generic Safety Issue (GSI)-191 at South Texas Project, Units 1 and 2 (CAC MF
Project stage: Meeting
ML16028A1522016-02-18018 February 2016
1/14/2016 Summary of Public Meeting with STP Nuclear Operating Company Regarding Modifications to the Licensee'S Risk-Informed Generic Safety Issue (GSI) 191 Application and Supplements for South Texas Project, Units 1 and 2
Project stage: Meeting
ML16088A2432016-04-0101 April 2016
2/18/2016, Summary of Public Meeting with STP Nuclear Operating Company Regarding Open Items, Risk-Informed Generic Safety Issue (GSI) 191 Application and Supplements for South Texas Project, Units 1 and 2 (CAC Nos. MF2400-MF2409)
Project stage: Meeting
ML16092A0442016-04-11011 April 2016
Summary of 3/3/2016 Public Meeting with STP Nuclear Operating Company Regarding Open Items, Risk-Informed Generic Safety Issue (GSI) 191 Application and Supplements for South Texas Project, Units 1 and 2 (CAC Nos. MF2400-MF2409)
Project stage: Meeting
ML16082A5072016-04-11011 April 2016
Request for Additional Information, Phased Response Requested, Exemption and License Amendment Request for a Risk-Informed Approach to Resolve Generic Safety Issue (GSI)-191 (CAC Nos. MF2400-MF2409)
Project stage: RAI
ML16095A0102016-04-13013 April 2016
Summary of November 17-19, 2015 Thermal-Hydraulic Review at Texas A&M University; Pilot Submittal and Request for Exemptions for a Risk-Informed Approach to Resolve Generic Safety Issue (GSI)-191 (CAC MF2400-MF2409)
Project stage: Other
ML16092A0852016-04-13013 April 2016
3/17/2016 Summary of Public Meeting with STP Nuclear Operating Company Regarding Open Items, Risk-Informed Generic Safety Issue (GSI) 191 Application and Supplements for South Texas Project, Units 1 and 2 (CAC Nos. MF2401-MF2409)
Project stage: Meeting
ML16096A0652016-04-13013 April 2016
Summary of February 4 and 16, 2016, Regulatory Audit at Westinghouse in Rockville, MD, Boric Acid Precipitation, Exemption and License Amendment Request, Risk-Informed Approach to Resolve Generic Safety Issue 191
Project stage: Other
ML16111A0272016-04-18018 April 2016
STP Nuclear Operating Company Slideshow for Public Meeting on April 21, 2016 for GSI-191 Resolution (CAC No. MF2400-01)
Project stage: Meeting
ML16103A3442016-04-26026 April 2016
Summary of February 24-26, 2016 Audit, Debris Transport Review at Alion Science and Technology Corporation, Albuquerque, Nm; Pilot Submittal and Exemption Request, Risk-Informed Approach to Resolve GSI 191
Project stage: Other
ML16032A4032016-04-26026 April 2016
FRN, Draft Environmental Assessment and Finding of No Significant Impact, Revise Licensing Basis as Documented in the UFSAR and Request for Exemptions, Risk-Informed Approach to Address GSI-191 (CAC MF2400-MF2409)
Project stage: Draft Other
ML16032A3872016-04-26026 April 2016
Draft Environmental Assessment and Finding of No Significant Impact, Revise Licensing Basis as Documented in the UFSAR and Request for Exemptions, Risk-Informed Approach to Address GSI-191 (CAC MF2400-MF2409)
Project stage: Draft Other
ML16127A4002016-05-11011 May 2016
Audit Summary, Thermal-Hydraulic Review on February 23-25, 2016 at Texas A&M University; Pilot Submittal and Request for Exemptions for a Risk-Informed Approach to Resolve Generic Safety Issue 191 (CAC MF2400-MF2409)
Project stage: Other
ML16125A2902016-05-26026 May 2016
Request for Additional Information, Risk Review, Exemption and License Amendment Request for a Risk-Informed Approach to Resolve Generic Safety Issue (GSI)-191 (CAC Nos. MF2400-MF2409)
Project stage: RAI
ML16141B0812016-05-31031 May 2016
Audit Summary, Risk Audit on April 12-13, 2016, at Alumni Center at the University of Texas, Austin, Tx; Pilot Generic Safety Issue 191 Submittal and Exemption Request, and Draft Request for Additional Information
Project stage: Draft RAI
ML16175A1082016-06-24024 June 2016
Summary of 4/21/2016 Public Meeting with STP Nuclear Operating Company Regarding Open Items, Risk-Informed Generic Safety Issue (GSI) 191 Application and Supplements for South Texas Project, Units 1 and 2
Project stage: Meeting
ML16190A0082016-07-13013 July 2016
Summary of 6/22/2016 Public Meeting with STP Nuclear Operating Company Regarding Open Items, Risk-Informed Generic Safety Issue (GSI) 191 Application and Supplements for South Texas Project, Units 1 and 2 (CAC Nos. MF2400-MF2409)
Project stage: Meeting
ML16194A2342016-07-21021 July 2016
Request for Withholding Information from Public Disclosure - 5/6/16 Affidavit Executed by D. Munoz and M. Rozboril, Alion Science and Technology, Response to Follow-up RAIs 18, 38, and 44
Project stage: RAI
ML16242A0102016-08-23023 August 2016
NRR E-mail Capture - (External_Sender) FW: South Texas Project GSI-191 Draft Risk Responses to Questions for Public Meeting on August 29, 2016
Project stage: Request
ML16242A0092016-08-25025 August 2016
NRR E-mail Capture - (External_Sender) South Texas Project GSI-191 Draft thermal-hydraulic Responses to Questions for Public Meeting on August 29, 2016
Project stage: Request
ML16238A5272016-09-0101 September 2016
Summary of 7/28/16, Public Meeting with STP Nuclear Operating Company to Discuss the License Amendment and Exemption Requests to Use a Risk-Informed Approach to the Resolution of GSI-191 (CAC Nos. MF2400 - MF2409)
Project stage: Meeting
ML16258A3672016-09-0606 September 2016
NRR E-mail Capture - (External_Sender) South Texas Project Generic Safety Issue 191 Resolution SNPB-3-2, Bullet 4 16 -inch Bounding Break Clarification for September 14, 2016 Public Meeting
Project stage: Request
ML16258A1002016-09-12012 September 2016
NRR E-mail Capture - (External_Sender) South Texas Project Generic Safety Issue 191 Resolution RAI APLA-3-2 Clarification for September 14, 2016 Public Meeting
Project stage: Request
ML16258A1042016-09-12012 September 2016
NRR E-mail Capture - (External_Sender) South Texas Project Generic Safety Issue 191 Resolution RAI SNPB-3-13 Clarification for September 14, 2016 Public Meeting
Project stage: Request
ML16258A0962016-09-13013 September 2016
NRR E-mail Capture - (External_Sender) South Texas Project Generic Safety Issue 191 Resolution RAI SSIB-3-4 Clarification for September 14, 2016 Public Meeting
Project stage: Request
ML16258A0982016-09-13013 September 2016
NRR E-mail Capture - (External_Sender) South Texas Project Generic Safety Issue 191 Resolution RAI 33 Clarification for September 14, 2016 Public Meeting
Project stage: Request
ML16258A2072016-09-14014 September 2016
NRR E-mail Capture - (External_Sender) South Texas Project Generic Safety Issue 191 Resolution RAI 37 Clarification for September 14, 2016 Public Meeting
Project stage: Request
ML16258A2082016-09-14014 September 2016
NRR E-mail Capture - (External_Sender) South Texas Project Generic Safety Issue 191 Resolution RAI 34 Clarification for September 14, 2016 Public Meeting
Project stage: Request
ML16246A0222016-10-0505 October 2016
Summary of Public Meeting with STP Nuclear Operating Company Regarding Open Items Related to Risk-Informed Generic Safety Issue (GSI) 191 Application and Supplements for South Texas Project, Units 1 and 2 (CAC Nos. MF2400 - MF2409)
Project stage: Meeting
ML16279A3312016-10-27027 October 2016
Summary of Public Meeting with STP Nuclear Operating Company Regarding Open Items, Risk-Informed Generic Safety Issue (GSI) 191 Application and Supplements for South Texas Project, Units 1 and 2 (CAC Nos. MF2400-MF2409)
Project stage: Meeting
ML16302A4532016-12-12012 December 2016
Closeout of Request for Additional Information Questions That Are No Longer Applicable, Resolution of Generic Safety Issue (GSI) 191 (CAC Nos. MF2400-MF2409)
Project stage: RAI
ML16351A1502016-12-16016 December 2016
Correction Letter Closeout of Request for Information Questions That Are No Longer Applicable Associated with the Resolution of Generic Safety Issue 191 (CAC Nos. MF2400 - MF2409)
Project stage: RAI
ML16278A5982017-05-0202 May 2017
Letter, Environmental Assessment and Finding of No Significant Impact, Revise Licensing Basis as Documented in the UFSAR and Request for Exemptions, Risk-Informed Approach to Address GSI-191 (CAC MF2400 to MF2409)
Project stage: Other
ML16278A5992017-05-0202 May 2017
Environmental Assessment and Finding of No Significant Impact, Revise Licensing Basis as Documented in the UFSAR and Request for Exemptions, Risk-Informed Approach to Address GSI-191 (CAC MF2400 to MF2409)
Project stage: Other
ML17137A3252017-05-17017 May 2017
Safety Evaluation of LAR by South Texas Project Nuclear Operating Company to Adopt a Risk-Informed Resolution of Generic Safety Issue-191
Project stage: Approval
ML17151A8432017-06-16016 June 2017
OEDO-17-00326 - EDO Response to ACRS Chairman, Safety Evaluation of License Amendment Request by STP Nuclear Operating Company to Adopt a Risk-Informed Resolution of Generic Safety Issue-191
Project stage: Approval
NRC-2016-0092, South Texas Project, Units 1 and 2 - FRN: Exemption from the Requirements of 10 CFR 50.46 and 10 CFR Part 50, Appendix a, General Design Criteria 35, 38, 41 (CAC Nos. MF2402-MF2409)2017-07-11011 July 2017
South Texas Project, Units 1 and 2 - FRN: Exemption from the Requirements of 10 CFR 50.46 and 10 CFR Part 50, Appendix a, General Design Criteria 35, 38, 41 (CAC Nos. MF2402-MF2409)
Project stage: Approval
ML17037C8712017-07-11011 July 2017
Letter, Exemption from the Requirements of 10 CFR Part 50, Section 50.46 (CAC Nos. MF2402-MF2409)
Project stage: Approval
ML17037C8762017-07-11011 July 2017
FRN: Exemption from the Requirements of 10 CFR 50.46 and 10 CFR Part 50, Appendix a, General Design Criteria 35, 38, 41 (CAC Nos. MF2402-MF2409)
Project stage: Approval
ML17055A5002017-07-11011 July 2017
Enclosure 4 to Amendment Nos. 212 and 198, Resolution of Licensee Comments on Safety Evaluation - Risk-Informed Approach to Resolve Generic Safety Issue 191
Project stage: Approval
ML17019A0032017-07-11011 July 2017
Attachment 2 to Safety Evaluation - In-Vessel Thermal-Hydraulic Analysis, Issuance of Amendment Nos. 212 and 198 - Risk-Informed Approach to Resolve Generic Safety Issue 191
Project stage: Approval
ML17038A2232017-07-11011 July 2017
Issuance of Amendment Nos. 212 and 198 - Risk-Informed Approach to Resolve Generic Safety Issue 191
Project stage: Approval
ML17019A0022017-07-11011 July 2017
Safety Evaluation, Enclosure 3 to Amendment Nos. 212 and 198 - Risk-Informed Approach to Resolve Generic Safety Issue 191
Project stage: Approval
2016-05-31
[Table View] |
Closeout of Request for Additional Information Questions That Are No Longer Applicable, Resolution of Generic Safety Issue (GSI) 191 (CAC Nos. MF2400-MF2409)| ML16302A453 |
| Person / Time |
|---|
| Site: |
South Texas  |
|---|
| Issue date: |
12/12/2016 |
|---|
| From: |
Lisa Regner
Plant Licensing Branch IV |
|---|
| To: |
Gerry Powell
South Texas |
|---|
| Regner L |
| References |
|---|
| CAC MF2400, CAC MF2401, CAC MF2402, CAC MF2403, CAC MF2404, CAC MF2405, CAC MF2406, CAC MF2407, CAC MF2408, CAC MF2409 |
| Download: ML16302A453 (6) |
|
|
|---|
Category:Letter
MONTHYEARNOC-AE-240040, 10 CFR 50.46 Thirty-Day Report of Significant ECCS Model Changes2024-10-31031 October 2024
10 CFR 50.46 Thirty-Day Report of Significant ECCS Model Changes
ML24304B0512024-10-30030 October 2024
Cycle 26 Core Operating Limits Report
IR 05000498/20244022024-10-23023 October 2024
Security Baseline Inspection Report 05000498/2024402 and 05000499/2024402
05000499/LER-2024-003, Containment Isolation Valve Inoperable Resulting in Condition Prohibited by Technical Specification and Prevention of Fulfillment of Safety Function2024-10-22022 October 2024
Containment Isolation Valve Inoperable Resulting in Condition Prohibited by Technical Specification and Prevention of Fulfillment of Safety Function
ML24295A0772024-10-21021 October 2024
Licensed Operator Positive Fitness-for-Duty Test
05000499/LER-2024-002, Two Control Room Envelope HVAC Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-10-17017 October 2024
Two Control Room Envelope HVAC Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function
ML24290A1162024-10-16016 October 2024
Change to South Texas Project Electric Generating Station (STPEGS) Emergency Plan
IR 05000498/20243012024-10-0707 October 2024
NRC Examination Report 05000498/2024301 and 05000499/2024301
ML24255A0322024-09-30030 September 2024
The Associated Independent Spent Fuel Storage Installation - Notice of Consideration of Approval of Direct Transfer of Licenses and Opportunity to Request a Hearing (EPID L-2024-LLM-0002) - Letter
ML24269A1762024-09-25025 September 2024
Tpdes Permit Renewal Application WQ0001 908000
05000498/LER-2024-004, Loss of Offsite Power Resulting in Unit 1 Automatic Reactor Trip and Actuation of Emergency Diesel Generators and Auxiliary Feedwater Pumps2024-09-19019 September 2024
Loss of Offsite Power Resulting in Unit 1 Automatic Reactor Trip and Actuation of Emergency Diesel Generators and Auxiliary Feedwater Pumps
ML24271A3022024-09-18018 September 2024
STP-2024-09 Post-Exam Comments - Redacted
ML24274A0902024-09-16016 September 2024
Written Response - EA-24-026 STP Operator - Redacted
ML24250A1882024-09-11011 September 2024
Request for Information for an NRC Post-Approval Site Inspection for License Renewal
05000499/LER-2024-001-01, Supplement to Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators2024-08-29029 August 2024
Supplement to Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators
IR 05000498/20240052024-08-22022 August 2024
Updated Inspection Plan for South Texas Project Electric Generating Station, Units 1 and 2 (Report 05000498/2024005 and 05000499/2024005)
IR 05000498/20240022024-08-0909 August 2024
Integrated Inspection Report 05000498/2024002 and 05000499/2024002
IR 05000498/20240102024-08-0808 August 2024
Biennial Problem Identification and Resolution Inspection Report 05000498/2024010 and 05000499/2024010
ML24218A1462024-07-26026 July 2024
2. EPA Comments on South Texas Project Exemption Ea/Fonsi
ML24207A1782024-07-25025 July 2024
Licensed Operator Positive Fitness-For-Duty Test
05000499/LER-2024-001, Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators2024-07-0202 July 2024
Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators
05000498/LER-2024-003, Condition Prohibited by Technical Specifications and Potential Loss of Safety Function Due to Inoperable Low Head Safety Injection Pump2024-07-0101 July 2024
Condition Prohibited by Technical Specifications and Potential Loss of Safety Function Due to Inoperable Low Head Safety Injection Pump
05000498/LER-2024-002-01, Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-06-27027 June 2024
Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function
05000498/LER-2023-003-01, Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-06-19019 June 2024
Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function
ML24141A0482024-05-17017 May 2024
EN 56958_1 Ametek Solidstate Controls, Inc
ML24137A0882024-05-15015 May 2024
Operator Licensinq Examination Schedule Revision 3
ML24136A2842024-05-15015 May 2024
Independent Spent Fuel Storage Installation Supplement to Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance
ML24136A2872024-05-15015 May 2024
Submittal of 2024 Nrc/Fema Evaluated Exercise Scenario Manual
ML24130A2712024-05-0909 May 2024
Re Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function
ML24128A1572024-05-0707 May 2024
Independent Spent Fuel Storage Installation Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance
IR 05000498/20240012024-05-0606 May 2024
Integrated Inspection Report 05000498/2024001 & 05000499/2024001
ML24120A3762024-04-29029 April 2024
Annual Dose Report for 2023
05000498/LER-2023-004-01, Condition Prohibited by Technical Specifications Due to Inoperable Train of Essential Chilled Water2024-04-25025 April 2024
Condition Prohibited by Technical Specifications Due to Inoperable Train of Essential Chilled Water
ML24116A3032024-04-25025 April 2024
Operations Quality Assurance Plan Condition Adverse to Quality Definition Change Resulting in a Reduction in Commitment
ML24116A2282024-04-25025 April 2024
Annual Environmental Operating Report
ML24117A1602024-04-24024 April 2024
2023 Radioactive Effluent Release Report
ML24102A2452024-04-23023 April 2024
Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0046 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting))
ML24113A3122024-04-22022 April 2024
Cycle 24 Core Operating Limits Report
ML24097A0072024-04-0606 April 2024
Relief Request Number RR-ENG-4-07 – Request for an Alternative to ASME Code Case N-729-6 for Reactor Vessel Head Penetration 75
05000498/LER-2024-001, Re Two Steam Generator Power Operated Relief Valves (Porvs) Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-04-0101 April 2024
Re Two Steam Generator Power Operated Relief Valves (Porvs) Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function
ML24088A3022024-03-28028 March 2024
Financial Assurance for Decommissioning - 2024 Update
ML24081A3972024-03-21021 March 2024
Response to Request for Additional Information for Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
ML24080A2902024-03-19019 March 2024
Nuclear Liability Certificates of Insurance
ML24066A2002024-03-0606 March 2024
10 CFR 50.46 Thirty-Day Report of Significant ECCS Model Changes
ML24079A1312024-03-0505 March 2024
Nuclear Insurance Protection
ML24060A1742024-02-28028 February 2024
Submittal of Annual Fitness for Duty Performance Report for 2023
IR 05000498/20230062024-02-28028 February 2024
Annual Assessment Letter for South Texas Project Electric Generating Station, Units 1 and 2 (Report 05000498/2023006 and 05000499/2023006)
IR 05000498/20240132024-02-27027 February 2024
Design Basis Assurance Inspection (Programs) Commercial Grade Dedication IR 05000498/2024013 and 05000499/2024013
ML24022A2252024-02-20020 February 2024
Issuance of Amendment Nos. 227 and 212 to Authorize the Revision of the Alternative Source Term Dose Calculation
ML24050A0082024-02-19019 February 2024
Evidence of Financial Protection
2024-09-30
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML24207A1782024-07-25025 July 2024
Licensed Operator Positive Fitness-For-Duty Test
ML24052A0112024-02-16016 February 2024
NRR E-mail Capture - South Texas Project - Draft Request for Additional Information - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications (L-2023-LLE-0046)
ML24024A1162024-01-24024 January 2024
STP Unit 2 Request for Information
ML23334A0062023-11-29029 November 2023
NRR E-mail Capture - South Texas Project - Request for Additional Information - Proposed Alternative to ASME BPV Code Requirements
ML23319A4442023-11-15015 November 2023
NRR E-mail Capture - South Texas Project - Draft Request for Additional Information - Proposed Alternative to ASME BPV Code Requirements
ML23278A1532023-10-0505 October 2023
NRR E-mail Capture - South Texas Project – Request for Additional Information - Request for Indirect Transfer of Licenses and Conforming Amendments (L-2023-LLM-0004)
ML23264A0972023-09-21021 September 2023
NRR E-mail Capture - South Texas Project - Request for Additional Information - License Amendment Request to Revise the Alternate Source Term Dose Calculation (L-2023-LLA-0047)
ML23255A2862023-09-12012 September 2023
NRR E-mail Capture - South Texas Project – Draft Request for Additional Information – License Amendment Request to Revise the Alternate Source Term Dose Calculation (L-2023-LLA-0047)
ML23145A1872023-05-24024 May 2023
July 2023 Emergency Preparedness Program Inspection - Request for Information
ML22255A1542022-09-13013 September 2022
Operating Company Information Request for the Cyber Security Baseline Inspection 05000498/2022401 and 05000499/2022401
ML22206A0142022-07-20020 July 2022
NRR E-mail Capture - South Texas Project - Request for Additional Information - 10 CFR 20.2002 Alternate Disposal Request
ML22194A0502022-07-0707 July 2022
NRR E-mail Capture - South Texas Project - Updated Draft Request for Additional Information - 10 CFR 20.2002 Alternate Disposal Request
ML22194A0492022-06-0808 June 2022
NRR E-mail Capture - South Texas Project - Draft Request for Additional Information - 10 CFR 20.2002 Alternate Disposal Request
ML22123A3272022-05-0303 May 2022
STP EP Exercise Inspection July 2022 RFI
ML22084A0762022-04-0404 April 2022
Notification of NRC Design Bases Assurance Inspection (Team) (05000498/2022012 and 05000499/2022012) and Request for Information
ML21286A5732021-10-18018 October 2021
Notification of NRC Design Bases Assurance Inspection (Programs) (05000498/2022011 and 05000499/2022011) and Request for Information
ML21166A2392021-06-16016 June 2021
Notification of Inspection (NRC Inspection Report 05000498/2021003 and 05000499/2021003) and Request for Information
ML21160A1522021-06-0909 June 2021
Request for Information NRC Inspection 2021-003 Public Radiation Safety
ML21133A2372021-05-0505 May 2021
Request for Additional Information: STP EP Exercise Inspection - July 2021
ML21039A8902021-02-0808 February 2021
NRR E-mail Capture - South Texas Project - Request for Additional Information - 1RE22 Inspection Summary Report for Steam Generator Tubing
ML21029A3312021-01-29029 January 2021
NRR E-mail Capture - South Texas Project - Draft Request for Additional Information - 1RE22 Inspection Summary Report for Steam Generator Tubing
ML20280A5452020-08-17017 August 2020
STP 2020 PIR Request for Information
ML20111A0052020-04-17017 April 2020
NRR E-mail Capture - South Texas Project - Request for Additional Information - Proposed Alternative to ASME OM Code 2012 Edition - Relief Request PRR-01
ML20070N0222020-03-10010 March 2020
NRC Selection for Onsite Review
ML20057G4612020-02-26026 February 2020
05000498/499 Request for Information - Occupational Radiation Safety Inspection
ML20045E2172020-02-13013 February 2020
Licensed Operator Positive Fitness-For-Duty Test
ML20036F5862020-02-0404 February 2020
Request for Additional Information - Proposed Alternative to ASME Code Requirements for the Repair of Essential Cooling Water System Class 3 Buried Piping (EPID L-2019-LLR-0096)Redacted
ML19165A1032019-06-14014 June 2019
NRR E-mail Capture - Draft RAI for STP TS 3.8.1.1 Sbdg SR Change
ML19081A1512019-03-21021 March 2019
NRR E-mail Capture - Draft Round 2 RAI - Sbdg Voltage and Frequency LAR (L-2018-LLA-0078)
ML18283B9522018-10-10010 October 2018
NRR E-mail Capture - Final RAI - South Texas Standby DG TS Change (L-2018-LLA-0078)
ML18263A1432018-09-12012 September 2018
NRR E-mail Capture - Final RAI for South Texas Project RR-ENG-E-16 (L-2018-LLR-0097)
ML18197A4172018-07-17017 July 2018
Notification of NRC Triennial Heat Sink Performance Inspection (05000498/2018003 and 05000499/2018003) and Request for Information
ML18003B4222018-01-0303 January 2018
NRR E-mail Capture - Final Request for Additional Information Amendment Request to Modify the Emergency Response Organization for South Texas Project
ML17229B4672017-08-16016 August 2017
Notification of NRC Inspection 05000499/2017008 and Request for Information
ML17132A0712017-05-15015 May 2017
Information Request the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000498/2017407; 05000499/2017407
ML17103A6272017-04-13013 April 2017
Notification of Evaluations of Changes, Tests, and Experiments Inspection (05000498/2017007 and 05000499/2017007) and Request for Information
ML16351A1502016-12-16016 December 2016
Correction Letter Closeout of Request for Information Questions That Are No Longer Applicable Associated with the Resolution of Generic Safety Issue 191 (CAC Nos. MF2400 - MF2409)
ML16302A4532016-12-12012 December 2016
Closeout of Request for Additional Information Questions That Are No Longer Applicable, Resolution of Generic Safety Issue (GSI) 191 (CAC Nos. MF2400-MF2409)
ML16343A0422016-12-0808 December 2016
Request for Additional Information for the Review of the South Texas Project, Units 1 and 2 License Renewal Application (CAC NOS. ME4936, ME4937)
ML16340A1022016-12-0505 December 2016
Requests for Additional Information for the Review of the South Texas Project License Renewal Application (CAC Nos. ME4936 and ME4937)
ML16246A0952016-09-15015 September 2016
Correction to 8/26/16 Request for Additional Information Enclosure, License Amendment Request to Revise Technical Specification 5.3.2 to Allow Operation with 56 Full-Length Control Rod Assemblies
ML16214A2912016-08-26026 August 2016
Summary of June 28-30, 2016, Regulatory Audit at Westinghouse in Rockville, MD, License Amendment Request to Revise Technical Specification 5.3.2 to Allow Operation with 56 Full-Length Control Rod Assemblies
ML16187A0522016-07-0707 July 2016
Request for Additional Information Regarding License Renewal Application
ML16141B0812016-05-31031 May 2016
Audit Summary, Risk Audit on April 12-13, 2016, at Alumni Center at the University of Texas, Austin, Tx; Pilot Generic Safety Issue 191 Submittal and Exemption Request, and Draft Request for Additional Information
ML16125A2902016-05-26026 May 2016
Request for Additional Information, Risk Review, Exemption and License Amendment Request for a Risk-Informed Approach to Resolve Generic Safety Issue (GSI)-191 (CAC Nos. MF2400-MF2409)
ML16127A4522016-05-12012 May 2016
Supplemental Information Needed for Acceptance of Requested Licensing Action, Amendment Request to Revise Technical Specification 5.3.2 to Allow Operation with 56 Full-Length Control Rod Assemblies
ML16104A3522016-04-22022 April 2016
Requests for Additional Information Set 35 for the Review of the South Texas Project License Renewal Application (Tac Nos. ME4936, ME4937)
ML16082A5072016-04-11011 April 2016
Request for Additional Information, Phased Response Requested, Exemption and License Amendment Request for a Risk-Informed Approach to Resolve Generic Safety Issue (GSI)-191 (CAC Nos. MF2400-MF2409)
ML16082A4842016-03-22022 March 2016
NRR E-mail Capture - South Texas Project Units 1 & 2, Draft Request for Additional Information for Risk Review for GSI-191
ML16081A0042016-03-18018 March 2016
NRR E-mail Capture - South Texas Project Units 1 & 2, Draft Request for Additional Information for Thermal-hydraulic Review for GSI-191
2024-07-25
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 12, 2016 Mr. G. T. Powell Executive Vice President and CNO STP Nuclear Operating Company South Texas Project P.O. Box 289 VVadsworth, TX 77483
SUBJECT:
SOUTH TEXAS PROJECT, UNITS 1 AND 2 - RE: CLOSEOUT OF REQUEST FOR INFORMATION QUESTIONS THAT ARE NO LONGER APPLICABLE ASSOCIATED VVITH THE RESOLUTION OF GENERIC SAFETY ISSUE 191 (CAC NOS. MF2400, MF2401, MF2402, MF2403, MF2404, MF2405, MF2406, MF2407, MF2408, AND MF2409)
Dear Mr. Powell:
On September 13, 2004, the U.S. Nuclear Regulatory Commission (NRC) issued Generic Letter (GL) 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-VVater Reactors" (Agencywide Documents Access and Management System (ADAMS) Accession No. ML042360586), to address a generic safety concern, generic safety issue (GSI) 191, over possible blockage of emergency core cooling sump strainers during design-basis accidents at pressurized-water power reactors.
The STP Nuclear Operating Company (STPNOC) responded to GL 2004-02 for the South Texas Project, Units 1 and 2 (STP), by letter dated March 8, 2005, as supplemented by letters dated July 13 and August 31, 2005; January 30, 2006; and February 29 and December 11, 2008 (ADAMS Accession Nos. ML050770105, ML052000281, ML052500311, ML060370145, ML080700338, and ML083520326, respectively).
On June 4, 2012 (ADAMS Accession No. ML13025A360), STPNOC submitted a letter stating its intention to resolve GSl-191, site specifically, through a risk-informed approach; further, it stated it did not intend to respond to the open NRC request for additional information (RAI) questions issued by letters dated June 2, 2005, February 9, 2006, and December 23, 2009 (ADAMS Accession Nos. ML051530285, ML060390246, and ML093410607, respectively). The licensee stated that it would not use a deterministic method and would submit a license amendment request and exemption requests to resolve GSl-191.
Subsequently, by letter dated June 19, 2013 (ADAMS Package Accession No. ML131750250),
as supplemented by letter dated October 3, 2013 (ADAMS Accession No. ML13295A222),
STPNOC submitted license amendment and exemption requests.
The NRC staff's review of the license amendment and exemption requests is ongoing; however, the NRC staff has determined that the June 4, 2012, license amendment and exemption requests supersede the previous submittals; therefore, the NRC's review of
G. Powell STPNOC's efforts to respond to GL 2004-02 prior to June 2012 have been terminated. For this reason, the RAls issued on June 2, 2005, February 9, 2006, and December 23, 2009, are no longer applicable.
By letters dated October 31, November 13, November 21 and December 23, 2013 (two letters);
January 9, February 13, February 27, March 17, March 18, May 15 (two letters), May 22, June 25, and July 15, 2014; March 10, and March 25, 2015 (ADAMS Accession Nos. ML13323A673, ML13323A128, ML13338A165, ML14015A312, ML14015A311, ML14029A533, ML14052A110, ML14072A075, ML14086A383, ML14087A126, ML14149A353, ML14149A354, ML14149A439, ML14178A467, ML14202A045, ML15072A092, and ML15091A440, respectively), STPNOC submitted supplemental information in support of the license amendment and exemption requests to resolve GSl-191 using a risk-informed methodology.
By letter dated August 20, 2015, STPNOC provided a supplement to the license amendment and exemption requests changing its approach from strictly risk-informed, to a deterministic and risk-informed methodology, called 'RoverD'. Additional supplements were submitted by STPNOC on April 13, May 11, June 9, June 16, July 18, July 21 (two letters), July 28, September 12, October 20, and December 7, 2016 1 (ADAMS Accession Nos. ML15246A125, ML16111B204, ML16154A117, ML16176A148, ML16196A241, ML16209A226, ML16229A189, ML16230A232, ML16221A393, ML16272A162, ML16302A015, and [see footnote], respectively) in response to NRC staff RAls.
Due to the methodology change described in the letter dated August 20, 2015, the licensee submitted a clarification letter dated June 9, 2016, providing a list of RAI question responses that it stated are no longer applicable with the basis for eliminating this content from the NRC staff's review.
The NRC staff reviewed the questions and the licensee's basis for removing questions from the NRC staff's review as provided in the June 9 and December 7, 2016, letters. The NRC's conclusions are provided in the Enclosure to this document.
This was discussed with Mr. Wayne Harrison, Mr. Drew Richards, and Mr. Steven Blossom of your staff on November 16, 2016.
1 The ADAMS Accession No. was not available at the time of the issuance of this letter.
G. Powell If you have any questions, please contact me at 301-415-1906 or via e-mail at Lisa.Regner@nrc.gov.
Lisa M. Regner, Senior Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-498 and 50-499
Enclosure:
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REQUEST FOR ADDITIONAL INFORMATION QUESTIONS THAT ARE NO LONGER APPLICABLE RESOLUTION OF GENERIC SAFETY ISSUE 191 STP NUCLEAR OPERATING COMPANY SOUTH TEXAS PROJECT, UNITS 1AND2 DOCKET NOS. 50-498 AND 50-499 The NRC staff determined that the following questions in request for additional information (RAI) letter dated April 15, 2014 (ADAMS Accession No. ML14087A075), are no longer applicable:
- CASA Grande, General - 1.a, 1.b, and 1.c.
- CASA Grande, Plant Configuration - 1.a, 1.b, 2.a, 2.b, 3.a, 3.b, and 3.c.
- CASA Grande, LOCA [loss-of-coolant accident] Frequencies - 1.a, 1. b, 3, and 4.
- CASA Grande to PRA [probabilistic risk assessment] Interface, General - 1.a, 1.b, 2.a, 2.b, 3, 4.a, 4.b, 4.c, 5, 6.a, 6.b, and 6.c.
- STP PRA Model, Success Criteria -1, 2.a, 2.b, 3.a, 3.b, and 3.d.
- STP PRA Model, Human Reliability Analysis - 1, 2, 3.a, 3.b, 3.c, 4.a, 4.b, 5, and 6.
- Results Interpretation, Quantification - 1.a, 1.b, and 2.
- Results Interpretation, Uncertainty Analysis - 1.a, 1.b, 1.c, 4.a, 4.b, 4.c, 4.d, 5, and 6.
- Radiation Protection and Consequence Branch - 1 and 3.
- Mechanical and Civil Engineering Branch - 1.
- Component Performance, NOE [non-destructive examination] and Testing Branch (EPNB) - 1, 2, 3, 4, 5, 6.a, and 6.b.
- Steam Generator tube Integrity and Chemical Engineering Branch (ESGB), Chemical Effects - 1.a, 1.b, 1.c, 1.d, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11.a, 11.b, 12, 13.a, 13.b, 13.c, 14.a, 14.b, 14.c, 15, 16, 17, 18.a, 18.b, 18.c, 19, 20, 21, 22.a, and 22.b.
- ESGB, Coatings - 2, 4, 5, 6.a, 6.b, and 6.c.
- Containment and Ventilation Branch (SCVB) - 1.b, 2.b, 3.b, 5, 8, and 9.b.
- Reactor Systems Branch (SRXB) - 2.a, 2.b, 2.c, 2.d, 2.e, 5.a, 5.b, 5.c, 6, and 8.
Enclosure
- Safety Issue Resolution Branch (SSIB)-3, 5, 9, 11.a, 11.b, 11.d, 11.e, 14, 15.a, 15.b, 15.c, 15.d, 16.a, 16.b, 16.c, 16.d, 17.a, 17.b, 17.c, 17.d, 17.e, 17.f, 18, 19, 20, 21, 22, 23, 24, 25, 26.a, 26.b, 26.d, 26.e, 26.f, 28, 30, 33, 34, 35, 36, 37, 38, 40, and 41.a.
- Technical Specifications Branch (STSB) - 1 and 2.
The NRC staff determined that the response to SNPB-4 in the April 15, 2015, RAI is no longer applicable because the plant's licensing basis analysis for boric acid precipitation (BAP) was changed. The original RAI and its response are superseded by question SNPB-3-33 in an NRC RAI dated April 11, 2016 (ADAMS Accession No. ML16082A507), which discussed the new STP BAP analysis.
The NRC staff determined that question CASA Grande, LOCA Frequencies - 1.b is still applicable; there is information the NRC staff intends to use in its safety evaluation regardless of STP's methodology change. This was discussed with Wayne Harrison of your staff and a mutually agreeable resolution determined as ...
The NRC staff determined that the following questions in RAI dated March 3, 2015 (ADAMS Accession No. ML14357A171), are no longer applicable:
- PRA Licensing Branch (APLA), Project Quality Assurance - 2.
- ESGB, Chemical Effects - 33 and 34.
The NRC staff determined that questions SCVB - 10 through 18 in the RAI dated March 3, 2015, are still applicable. The licensee's revised responses to each of these questions were provided in an August 20, 2015, supplement (ADAMS Accession No. ML15246A128) and the NRC staff intends to use the information in its safety evaluation.
This information was discussed with Mr. Wayne Harrison of your staff on xxxxx.
G. Powell If you have any questions, please contact me at 301-415-1906 or via e-mail at Lisa.Regner@nrc.gov.
Sincerely,
/RA/
Lisa M. Regner, Senior Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-498 and 50-499
Enclosure:
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