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| | issue date = 05/24/2017 | | | issue date = 05/24/2017 |
| | title = Clarification of Responses for Requests for Additional Information, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-423, Revision 1, Technical Specification End States.. | | | title = Clarification of Responses for Requests for Additional Information, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-423, Revision 1, Technical Specification End States.. |
| | author name = Gideon W R | | | author name = Gideon W |
| | author affiliation = Duke Energy Progress, LLC | | | author affiliation = Duke Energy Progress, LLC |
| | addressee name = | | | addressee name = |
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| {{#Wiki_filter:William R. Gideon Vice PresidentBrunswick Nuclear PlantP.O. Box 10429Southport, NC 28461o: 910.457.3698 May 24, 2017 Serial: BSEP 17-0048 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 | | {{#Wiki_filter:William R. Gideon Vice President Brunswick Nuclear Plant P.O. Box 10429 Southport, NC 28461 o: 910.457.3698 May 24, 2017 Serial: BSEP 17-0048 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 |
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| ==Subject:== | | ==Subject:== |
| Brunswick Steam Electric Plant, Unit Nos. 1 and 2 Renewed Facility Operating License Nos. DPR-71 and DPR-62 Docket Nos. 50-325 and 50-324 Clarification of Responses for Requests for Additional Information License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-423, Revision 1, "Technical Specifications End | | Brunswick Steam Electric Plant, Unit Nos. 1 and 2 Renewed Facility Operating License Nos. DPR-71 and DPR-62 Docket Nos. 50-325 and 50-324 Clarification of Responses for Requests for Additional Information License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-423, Revision 1, "Technical Specifications End States, NEDC-32988-A" |
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| States, NEDC-32988-A" | |
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| ==References:== | | ==References:== |
| : 1. Letter from William R. Gideon (Duke Energy) to U.S. Nuclear Regulatory Commission, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-423, Revision 1, "Technical Specifications End States, NEDC 32988-A", dated September 28, 2016, ADAMS Accession Number ML16287A415 | | : 1. Letter from William R. Gideon (Duke Energy) to U.S. Nuclear Regulatory Commission, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-423, Revision 1, "Technical Specifications End States, NEDC 32988-A", dated September 28, 2016, ADAMS Accession Number ML16287A415 |
| : 2. NRR E-mail Capture - Brunswick Unit 1 and Unit 2 - Request for Additional Information Related to LAR to Modify the TS Requirements for End States Associated with the Implementation of the Approved TSTF Traveler TSTF-423-A (MF8466 and MF 8467), | | : 2. NRR E-mail Capture - Brunswick Unit 1 and Unit 2 - Request for Additional Information Related to LAR to Modify the TS Requirements for End States Associated with the Implementation of the Approved TSTF Traveler TSTF-423-A (MF8466 and MF 8467), |
| dated February 3, 2017, ADAMS Accession Number ML17037A002 3. Letter from William R. Gideon (Duke Energy) to U.S. Nuclear Regulatory Commission, Response to Request for Additional Information, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-423, Revision 1, "Technical Specifications End States, NEDC-32988-A," dated March 25, 2017, ADAMS Accession Number ML17086A006 Ladies and Gentlemen: By letter dated September 28, 2016 (i.e., Reference 1), Duke Energy Progress, LLC, (Duke Energy) submitted a license amendment request (LAR) for the Brunswick Steam Electric Plant (BSEP), Unit Nos. 1 and 2. The proposed amendment would modify the Technical Specifications (TSs) to risk-informed requirements regarding selected Required Action end states by incorporating the Boiling Water Reactor (BWR) Owners' Group (BWROG) approved Topical Report NEDC-32988-A, Revision 2, "Technical Justification to Support Risk-Informed Modification to Selected Required Action End States for BWR Plants." Additionally, the proposed amendment would modify the TS Required Actions with a Note prohibiting the use of Limiting Condition for Operation (LCO) 3.0.4.a when entering the preferred end state (i.e., Mode 3) on reactor startup. | | dated February 3, 2017, ADAMS Accession Number ML17037A002 |
| | | : 3. Letter from William R. Gideon (Duke Energy) to U.S. Nuclear Regulatory Commission, Response to Request for Additional Information, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-423, Revision 1, "Technical Specifications End States, NEDC-32988-A," dated March 25, 2017, ADAMS Accession Number ML17086A006 Ladies and Gentlemen: |
| U.S. Nuclear Regulatory Commission Page 3 of 3 cc (with Enclosure): U. S. Nuclear Regulatory Commission, Region II ATTN: Ms. Catherine Haney, Regional Administrator 245 Peachtree Center Ave, NE, Suite 1200
| | By letter dated September 28, 2016 (i.e., Reference 1), Duke Energy Progress, LLC, (Duke Energy) submitted a license amendment request (LAR) for the Brunswick Steam Electric Plant (BSEP), Unit Nos. 1 and 2. The proposed amendment would modify the Technical Specifications (TSs) to risk-informed requirements regarding selected Required Action end states by incorporating the Boiling Water Reactor (BWR) Owners' Group (BWROG) approved Topical Report NEDC-32988-A, Revision 2, "Technical Justification to Support Risk-Informed Modification to Selected Required Action End States for BWR Plants." Additionally, the proposed amendment would modify the TS Required Actions with a Note prohibiting the use of Limiting Condition for Operation (LCO) 3.0.4.a when entering the preferred end state (i.e., |
| | | Mode 3) on reactor startup. |
| Atlanta, GA 30303-1257 U.S. Nuclear Regulatory Commission ATTN: Mr. Andrew Hon (Mail Stop OWFN 8G9A) (Electronic Copy Only) 11555 Rockville Pike
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| Rockville, MD 20852-2738 Andrew.Hon@nrc.gov U.S. Nuclear Regulatory Commission ATTN: Ms. Michelle P. Catts, NRC Senior Resident Inspector
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| 8470 River Road Southport, NC 28461-8869 Chair - North Carolina Utilities Commission (Electronic Copy Only) 4325 Mail Service Center Raleigh, NC 27699-4300 swatson@ncuc.net Mr. W. Lee Cox, III, Section Chief (Electronic Copy Only)
| | U.S. Nuclear Regulatory Commission Page 2 of 3 On February 3, 2017 (i.e., Reference 2), by electronic mail, the NRG provided a request for additional information (RAI) regarding the LAR. Duke Energy responded to the RAI on March 25, 2017 (i.e., Reference 3). The RAI response was discussed, by telephone, with the NRG on April 27, 2017. During this call, it was agreed that clarifying information would be provided to supplement Duke Energy's response to NRG RAI 2. The clarifying information is provided in the Enclosure of this letter. |
| Radiation Protection Section North Carolina Department of Health and Human Services 1645 Mail Service Center Raleigh, NC 27699-1645
| | This document contains no regulatory commitments. |
| | Please refer any questions regarding this submittal to Mr. Lee Grzeck, Manager - Regulatory Affairs, at (910) 457-2487. |
| | I declare, under penalty of perjury, that the foregoing is true and correct. Executed on May 24, 2017. |
| | Siz;Jo William R. Gideon MAT/mat |
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| lee.cox@dhhs.nc.gov BSEP 17-0048 Enclosure Page 1 of 2 Clarifying Information Regarding Response to Request for Additional Information By letter dated September 28, 2016, Duke Energy Progress, LLC, (Duke Energy) submitted a license amendment request (LAR) for the Brunswick Steam Electric Plant (BSEP), Unit Nos. 1 and 2. The proposed amendment would modify the Technical Specifications (TSs) to risk-informed requirements regarding selected Required Action end states by incorporating the Boiling Water Reactor (BWR) Owners' Group (BWROG) approved Topical Report NEDC-32988-A, Revision 2, "Technical Justification to Support Risk-Informed Modification to Selected Required Action End States for BWR Plants." Additionally, the proposed amendment would modify the TS Required Actions with a Note prohibiting the use of Limiting Condition for Operation (LCO) 3.0.4.a when entering the preferred end state (i.e., Mode 3) on reactor startup. On February 3, 2017, by electronic mail, the NRC provided a request for additional
| | ==Enclosure:== |
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| information (RAI) regarding the LAR. Duke Energy responded to the RAI on March 25, 2017. The RAI response was discussed, by telephone, with the NRC on April 27, 2017. During this call, it was agreed that clarifying information would be provided to supplement Duke Energy's response to NRC RAI 2. The clarifying information is provided below. NRC RAI 2 Please provide Emergency Core Cooling Systems (ECCS) analysis and containment analysis and results to verify acceptable ECCS performance, containment integrity, Environmental Equipment Qualification (EEQ), and containment heat removal for a design basis Loss of
| | Clarifying Information Regarding Response to Request for Additional Information |
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| Coolant Accident (LOCA) in Mode 3 when one LPCI pump and one CS pump are concurrently inoperable in this mode. Clarification of BSEP Response to NRC RAI 2: NUREG-1433, "Standard Technical Specifications G eneral Electric BWR/4 Plants," Revision 4, Volume 2, "Bases," states that the Core Spray (CS) System is composed of two independent subsystems. Each subsystem consists of a motor driven pump, a spray sparger above the core, and piping and valves to transfer water from the suppression pool to the sparger. It also states that Low Pressure Coolant Injection (LPCI) is an operating mode of the Residual Heat Removal (RHR) System. There are two LPCI s ubsystems, each consisting of two motor driven pumps and required piping and valves to transfer water from the suppression pool to the Reactor Pressure Vessel (RPV) via the corresponding recirculation loop. TSTF-423 approved elimination of proceeding to Mode 4 for NUREG-1433 Condition A of TS 3.5.1. A. One low pressure ECCS injection/spray subsystem inoperable. OR One LPCI pump in both LPCI subsystems inoperable. Therefore, NUREG-1433 is applicable to one LPCI pump inoperable, two LPCI pumps in a single subsystem inoperable, one LPCI pump in each subsystem inoperable (i.e., two pumps total), or one CS pump inoperable. The maximum level of degradation is two of six low BSEP 17-0048 Enclosure Page 2 of 2 pressure ECCS pumps. In each of these circumstances, it was deemed acceptable to remain in Mode 3 per approval of TSTF-423. Approval of the changes to NUREG-1433, TS 3.5.1 was based on Topical Report NEDC-32988-A. The justification for the changes states: A comparative PSA evaluation of the core damage risks of operation in the current end state versus the proposed Mode 3 end state was performed. The results indicate that the core damage risks while operating in the proposed Mode 3 (assuming the individual failure conditions) are lower or comparable to the current end state. Going to Mode 4 for the specified inoperable conditions would cause loss of both high pressure steam injection systems (HPCI and RCIC), loss of the feedwater/condensate system, and require activating the RHR Shutdown Cooling System. In addition, maintaining the reactor steam dome pressure above 150 psig preserves the availability of the high pressure systems. It is concluded that, based on these lower or equivalent calculated risks, staying in Mode 3 to restore systems back to service is the preferred end state rather than going to Mode 4 or a mode where reactor pressure is 150 psig. The BSEP TS Bases are identical to the NUREG-1433 Bases with respect to CS and LPCI configuration. Additionally, BSEP TS 3.5.1 Condition A is the same as NUREG-1433, TS 3.5.1
| | U.S. Nuclear Regulatory Commission Page 3 of 3 cc (with Enclosure): |
| | U. S. Nuclear Regulatory Commission, Region II ATTN: Ms. Catherine Haney, Regional Administrator 245 Peachtree Center Ave, NE, Suite 1200 Atlanta, GA 30303-1257 U.S. Nuclear Regulatory Commission ATTN: Mr. Andrew Hon (Mail Stop OWFN 8G9A) (Electronic Copy Only) 11555 Rockville Pike Rockville, MD 20852-2738 Andrew.Hon@nrc.gov U.S. Nuclear Regulatory Commission ATTN: Ms. Michelle P. Catts, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 Chair - North Carolina Utilities Commission (Electronic Copy Only) 4325 Mail Service Center Raleigh, NC 27699-4300 swatson@ncuc.net Mr. W. Lee Cox, III, Section Chief (Electronic Copy Only) |
| | Radiation Protection Section North Carolina Department of Health and Human Services 1645 Mail Service Center Raleigh, NC 27699-1645 lee.cox@dhhs.nc.gov |
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| Condition A. BSEP TS 3.5.1 Condition B does not exist in NUREG-1433, TS 3.5.1. BSEP Condition B states: B. One LPCI pump inoperable.
| | BSEP 17-0048 Enclosure Page 1 of 2 Clarifying Information Regarding Response to Request for Additional Information By letter dated September 28, 2016, Duke Energy Progress, LLC, (Duke Energy) submitted a license amendment request (LAR) for the Brunswick Steam Electric Plant (BSEP), Unit Nos. 1 and 2. The proposed amendment would modify the Technical Specifications (TSs) to risk-informed requirements regarding selected Required Action end states by incorporating the Boiling Water Reactor (BWR) Owners' Group (BWROG) approved Topical Report NEDC-32988-A, Revision 2, "Technical Justification to Support Risk-Informed Modification to Selected Required Action End States for BWR Plants." Additionally, the proposed amendment would modify the TS Required Actions with a Note prohibiting the use of Limiting Condition for Operation (LCO) 3.0.4.a when entering the preferred end state (i.e., Mode 3) on reactor startup. |
| AND One core spray (CS) subsystem inoperable. The proposed BSEP markup eliminates proceeding to Mode 4 for Condition B of TS 3.5.1.
| | On February 3, 2017, by electronic mail, the NRC provided a request for additional information (RAI) regarding the LAR. Duke Energy responded to the RAI on March 25, 2017. |
| Having one LPCI and one CS pump inoperable represents a maximum level of degradation of two of six low pressure ECCS pumps; consistent with that allowed in Condition A. As such, the BSEP justification for the change to BSEP TS 3.5.1 C ondition B is that the justification provided in Topical Report NEDC-32988-A for a maximum level of degradation of two of six low pressure ECCS pumps (i.e., a total of two LPCI pumps) provided in TS 3.5.1 Condition A is also applicable to a maximum level of degradation of two of six low pressure ECCS pumps (i.e., one LPCI pump and one CS pump) provided in TS 3.5.1 Condition B. The mitigation capability of having one LPCI pump and one CS pump inoperable is not significantly different than having two LPCI pumps inoperable. Duke Energy's March 25, 2017, response to NRC RAI 2 demonstrates that BSEP is analyzed for concurrent inoperability of one CS and one LPCI pump. The BSEP LOCA analysis demonstrates that the consequences of a LOCA with one CS and one LPCI pump inoperable are mitigated to within acceptable regulatory limits. The BSEP LOCA analysis is performed at 102 percent of Rated Thermal Power (RTP) and fully bounds a
| | The RAI response was discussed, by telephone, with the NRC on April 27, 2017. During this call, it was agreed that clarifying information would be provided to supplement Duke Energy's response to NRC RAI 2. The clarifying information is provided below. |
| | NRC RAI 2 Please provide Emergency Core Cooling Systems (ECCS) analysis and containment analysis and results to verify acceptable ECCS performance, containment integrity, Environmental Equipment Qualification (EEQ), and containment heat removal for a design basis Loss of Coolant Accident (LOCA) in Mode 3 when one LPCI pump and one CS pump are concurrently inoperable in this mode. |
| | Clarification of BSEP Response to NRC RAI 2: |
| | NUREG-1433, "Standard Technical Specifications General Electric BWR/4 Plants," Revision 4, Volume 2, "Bases," states that the Core Spray (CS) System is composed of two independent subsystems. Each subsystem consists of a motor driven pump, a spray sparger above the core, and piping and valves to transfer water from the suppression pool to the sparger. It also states that Low Pressure Coolant Injection (LPCI) is an operating mode of the Residual Heat Removal (RHR) System. There are two LPCI subsystems, each consisting of two motor driven pumps and required piping and valves to transfer water from the suppression pool to the Reactor Pressure Vessel (RPV) via the corresponding recirculation loop. |
| | TSTF-423 approved elimination of proceeding to Mode 4 for NUREG-1433 Condition A of TS 3.5.1. |
| | A. One low pressure ECCS injection/spray subsystem inoperable. |
| | OR One LPCI pump in both LPCI subsystems inoperable. |
| | Therefore, NUREG-1433 is applicable to one LPCI pump inoperable, two LPCI pumps in a single subsystem inoperable, one LPCI pump in each subsystem inoperable (i.e., two pumps total), or one CS pump inoperable. The maximum level of degradation is two of six low |
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| hypothetical Mode 3 LOCA. Additionally, BSEP has committed to follow the guidance established in TSTF-IG-05-02, Revision 2, "Implementation Guidance for TSTF-423, Revision 1, | | BSEP 17-0048 Enclosure Page 2 of 2 pressure ECCS pumps. In each of these circumstances, it was deemed acceptable to remain in Mode 3 per approval of TSTF-423. |
| 'Technical Specifications End States, NEDC-329 88-A.'" Therefore, entry into Mode 3 from either Condition A or Condition B will be limited to no more than seven days.}} | | Approval of the changes to NUREG-1433, TS 3.5.1 was based on Topical Report NEDC-32988-A. The justification for the changes states: |
| | A comparative PSA evaluation of the core damage risks of operation in the current end state versus the proposed Mode 3 end state was performed. The results indicate that the core damage risks while operating in the proposed Mode 3 (assuming the individual failure conditions) are lower or comparable to the current end state. Going to Mode 4 for the specified inoperable conditions would cause loss of both high pressure steam injection systems (HPCI and RCIC), loss of the feedwater/condensate system, and require activating the RHR Shutdown Cooling System. In addition, maintaining the reactor steam dome pressure above 150 psig preserves the availability of the high pressure systems. It is concluded that, based on these lower or equivalent calculated risks, staying in Mode 3 to restore systems back to service is the preferred end state rather than going to Mode 4 or a mode where reactor pressure is 150 psig. |
| | The BSEP TS Bases are identical to the NUREG-1433 Bases with respect to CS and LPCI configuration. Additionally, BSEP TS 3.5.1 Condition A is the same as NUREG-1433, TS 3.5.1 Condition A. |
| | BSEP TS 3.5.1 Condition B does not exist in NUREG-1433, TS 3.5.1. BSEP Condition B states: |
| | B. One LPCI pump inoperable. |
| | AND One core spray (CS) subsystem inoperable. |
| | The proposed BSEP markup eliminates proceeding to Mode 4 for Condition B of TS 3.5.1. |
| | Having one LPCI and one CS pump inoperable represents a maximum level of degradation of two of six low pressure ECCS pumps; consistent with that allowed in Condition A. As such, the BSEP justification for the change to BSEP TS 3.5.1 Condition B is that the justification provided in Topical Report NEDC-32988-A for a maximum level of degradation of two of six low pressure ECCS pumps (i.e., a total of two LPCI pumps) provided in TS 3.5.1 Condition A is also applicable to a maximum level of degradation of two of six low pressure ECCS pumps (i.e., one LPCI pump and one CS pump) provided in TS 3.5.1 Condition B. The mitigation capability of having one LPCI pump and one CS pump inoperable is not significantly different than having two LPCI pumps inoperable. Duke Energy's March 25, 2017, response to NRC RAI 2 demonstrates that BSEP is analyzed for concurrent inoperability of one CS and one LPCI pump. |
| | The BSEP LOCA analysis demonstrates that the consequences of a LOCA with one CS and one LPCI pump inoperable are mitigated to within acceptable regulatory limits. The BSEP LOCA analysis is performed at 102 percent of Rated Thermal Power (RTP) and fully bounds a hypothetical Mode 3 LOCA. Additionally, BSEP has committed to follow the guidance established in TSTF-IG-05-02, Revision 2, "Implementation Guidance for TSTF-423, Revision 1, |
| | 'Technical Specifications End States, NEDC-32988-A.'" Therefore, entry into Mode 3 from either Condition A or Condition B will be limited to no more than seven days.}} |
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MONTHYEARBSEP 16-0087, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-423, Revision 1, Technical Specifications End States, NEDC-32988-A.2016-09-28028 September 2016 License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-423, Revision 1, Technical Specifications End States, NEDC-32988-A. Project stage: Request BSEP 17-0026, Response to Request for Additional Information, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-423,Revision 1, Technical Specifications End States, NEDC-32988-A.2017-03-25025 March 2017 Response to Request for Additional Information, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-423,Revision 1, Technical Specifications End States, NEDC-32988-A. Project stage: Response to RAI BSEP 17-0048, Clarification of Responses for Requests for Additional Information, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-423, Revision 1, Technical Specification End States..2017-05-24024 May 2017 Clarification of Responses for Requests for Additional Information, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-423, Revision 1, Technical Specification End States.. Project stage: Request ML17180A5962017-08-29029 August 2017 Issuance of Amendments to Adopt TSTF-423 Technical Specifications End States, NEDC-32988-A Project stage: Approval 2017-03-25
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Category:Letter type:BSEP
MONTHYEARBSEP 19-0012, Submittal of 2018 Sea Turtle Annual Report2019-01-17017 January 2019 Submittal of 2018 Sea Turtle Annual Report BSEP 18-0052, Annual Radiological Environmental Operating Report - 20172018-05-10010 May 2018 Annual Radiological Environmental Operating Report - 2017 BSEP 18-0051, Annual Radioactive Effluent Release Report - 20172018-04-26026 April 2018 Annual Radioactive Effluent Release Report - 2017 BSEP 18-0045, Request for License Amendment: Technical Specification 3.8.3, Diesel Fuel Oil, One-Time Extension of Main Fuel Oil Storage Tank Completion Time2018-04-25025 April 2018 Request for License Amendment: Technical Specification 3.8.3, Diesel Fuel Oil, One-Time Extension of Main Fuel Oil Storage Tank Completion Time BSEP 18-0054, Response to Request for Additional Information Regarding Inservice Inspection Program Proposed Alternative ISI-09 in Accordance with 10 CFR 50.55a(z)(1) Regarding Reactor Pressure Vessel Circumferential.2018-04-24024 April 2018 Response to Request for Additional Information Regarding Inservice Inspection Program Proposed Alternative ISI-09 in Accordance with 10 CFR 50.55a(z)(1) Regarding Reactor Pressure Vessel Circumferential. BSEP 18-0048, Response to Request for Additional Information Regarding Inservice Inspection Program Proposed Alternative ISI-09 in Accordance with 10 CFR 50.55a(z)(1) Regarding Reactor Pressure Vessel Circumferential Shell Weld Examinations2018-04-11011 April 2018 Response to Request for Additional Information Regarding Inservice Inspection Program Proposed Alternative ISI-09 in Accordance with 10 CFR 50.55a(z)(1) Regarding Reactor Pressure Vessel Circumferential Shell Weld Examinations BSEP 18-0044, Application of Dissimilar Metal Weld Full Structural Overlay - Reactor Pressure Vessel Nozzles N4A and N4D2018-04-11011 April 2018 Application of Dissimilar Metal Weld Full Structural Overlay - Reactor Pressure Vessel Nozzles N4A and N4D BSEP 18-0046, Supplement to Response to Request for Additional Information SRXB-RAI-2 Regarding Request for License Amendment Regarding Core Flow Operating Range Expansion2018-04-10010 April 2018 Supplement to Response to Request for Additional Information SRXB-RAI-2 Regarding Request for License Amendment Regarding Core Flow Operating Range Expansion BSEP 18-0047, Supplement to Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2) for End of Interval Leakage Test2018-04-0505 April 2018 Supplement to Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2) for End of Interval Leakage Test BSEP 18-0041, Request for License Amendment to Revise the Technical Specifications to Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report2018-04-0404 April 2018 Request for License Amendment to Revise the Technical Specifications to Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report BSEP 18-0043, Application of Dissimilar Metal Weld Full Structural Overlay - Reactor Pressure Vessel Nozzles N4A and N4D2018-03-31031 March 2018 Application of Dissimilar Metal Weld Full Structural Overlay - Reactor Pressure Vessel Nozzles N4A and N4D BSEP 18-0035, Response to Request for Additional Information Regarding Request for License Amendment Regarding Core Flow Operating Range Expansion2018-03-29029 March 2018 Response to Request for Additional Information Regarding Request for License Amendment Regarding Core Flow Operating Range Expansion BSEP 18-0042, Cycle 22 Core Operating Limits Report (COLR)2018-03-27027 March 2018 Cycle 22 Core Operating Limits Report (COLR) BSEP 18-0040, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for End of Interval Leakage Test2018-03-23023 March 2018 Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for End of Interval Leakage Test BSEP 18-0039, Proposed In-Service Inspection Alternative for Application of Dissimilar Metal Weld Full Structural Overlay - Nozzles N4A and N4D2018-03-19019 March 2018 Proposed In-Service Inspection Alternative for Application of Dissimilar Metal Weld Full Structural Overlay - Nozzles N4A and N4D BSEP 18-0034, Corrected Affidavit Relating to the Request for License Amendment Regarding Core Flow Operating Range Expansion2018-03-16016 March 2018 Corrected Affidavit Relating to the Request for License Amendment Regarding Core Flow Operating Range Expansion BSEP 18-0032, Additional Testing Information Relating to the Request for License Amendment Regarding Core Flow Operating Range Expansion2018-03-14014 March 2018 Additional Testing Information Relating to the Request for License Amendment Regarding Core Flow Operating Range Expansion BSEP 18-0026, Additional Information Regarding Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for Reactor Pressure Vessel Nozzle-to-Vessel Weld Examination2018-03-0707 March 2018 Additional Information Regarding Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for Reactor Pressure Vessel Nozzle-to-Vessel Weld Examination BSEP 18-0014, Fifth 10-Year Inservice Testing Program Plan2018-02-19019 February 2018 Fifth 10-Year Inservice Testing Program Plan BSEP 18-0021, Response to Request for Additional Information Regarding Request for License Amendment Regarding Core Flow Operating Range Expansion (CAC Nos. MF8864 and MF8865). Without Proprietary Enclosure2018-02-0505 February 2018 Response to Request for Additional Information Regarding Request for License Amendment Regarding Core Flow Operating Range Expansion (CAC Nos. MF8864 and MF8865). Without Proprietary Enclosure BSEP 18-0017, Revision to Radiological Emergency Response Plan and Implementing Procedure2018-01-30030 January 2018 Revision to Radiological Emergency Response Plan and Implementing Procedure BSEP 18-0015, Inservice Inspection Program Proposed Alternative ISI-09 in Accordance with 10 CFR 50.55a(z)(1) Regarding Reactor Pressure Vessel Circumferential Shell Weld Examinations2018-01-23023 January 2018 Inservice Inspection Program Proposed Alternative ISI-09 in Accordance with 10 CFR 50.55a(z)(1) Regarding Reactor Pressure Vessel Circumferential Shell Weld Examinations BSEP 18-0013, Supplement to Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control2018-01-23023 January 2018 Supplement to Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control BSEP 18-0001, Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements2018-01-23023 January 2018 Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements BSEP 18-0012, Application to Revise Technical Specifications to Adopt TSTF-208, Revision 0, Extension of Time to Reach Mode 2 in LCO 3.0.32018-01-23023 January 2018 Application to Revise Technical Specifications to Adopt TSTF-208, Revision 0, Extension of Time to Reach Mode 2 in LCO 3.0.3 BSEP 18-0009, 2017 Sea Turtle Annual Report2018-01-15015 January 2018 2017 Sea Turtle Annual Report BSEP 17-0098, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors2018-01-10010 January 2018 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors BSEP 17-0119, Snubber Program Plan for Fifth 10-Year Interval Inservice Testing Program2018-01-10010 January 2018 Snubber Program Plan for Fifth 10-Year Interval Inservice Testing Program BSEP 17-0115, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control2018-01-0404 January 2018 Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control BSEP 17-0110, Seventh Six-Month Status Report in Response to June 6, 2013, Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions2017-12-20020 December 2017 Seventh Six-Month Status Report in Response to June 6, 2013, Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions BSEP 17-0121, Post-Examination Documentation and Comments for Operator Retake Initial Examination2017-12-14014 December 2017 Post-Examination Documentation and Comments for Operator Retake Initial Examination BSEP 17-0120, Withdrawal of Request for Risk-Informed Exigent License Amendment - Technical Specification 3.8.1, AC Sources - Operating, One-Time Extension of Emergency Diesel Generator Completion Times and Suspension..2017-12-12012 December 2017 Withdrawal of Request for Risk-Informed Exigent License Amendment - Technical Specification 3.8.1, AC Sources - Operating, One-Time Extension of Emergency Diesel Generator Completion Times and Suspension.. BSEP 17-0118, Supplement to Response to Request for Additional Information Regarding Request for Risk-Informed Exigent License Amendment - Technical Specification 3.8.1, AC Sources - Operating, One-Time Extension of Emergency Diesel..2017-12-0707 December 2017 Supplement to Response to Request for Additional Information Regarding Request for Risk-Informed Exigent License Amendment - Technical Specification 3.8.1, AC Sources - Operating, One-Time Extension of Emergency Diesel.. BSEP 17-0117, Response to Request for Additional Information (Probabilistic Risk Assessment and Human Performance Branches) Regarding Request for Risk-Informed Exigent License Amendment - Technical Specification 3.8.1 AC Sources..2017-12-0606 December 2017 Response to Request for Additional Information (Probabilistic Risk Assessment and Human Performance Branches) Regarding Request for Risk-Informed Exigent License Amendment - Technical Specification 3.8.1 AC Sources.. BSEP 17-0116, Response to Request for Additional Information Regarding Request for Risk- Informed Exigent License Amendment - Technical Specification 3.8.1, AC Sources - Operating, One-Time Extension of ..2017-12-0404 December 2017 Response to Request for Additional Information Regarding Request for Risk- Informed Exigent License Amendment - Technical Specification 3.8.1, AC Sources - Operating, One-Time Extension of .. BSEP 17-0104, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for Reactor Pressure Vessel Nozzle-to-Vessel Weld Examination2017-11-29029 November 2017 Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for Reactor Pressure Vessel Nozzle-to-Vessel Weld Examination BSEP 17-0111, Request for Risk-Informed Exigent License Amendment - Technical Specification 3.8.1, AC Sources Operating, One-Time Extension of Emergency Diesel Generator Completion Times and Suspension of Surveillance Requirements2017-11-28028 November 2017 Request for Risk-Informed Exigent License Amendment - Technical Specification 3.8.1, AC Sources Operating, One-Time Extension of Emergency Diesel Generator Completion Times and Suspension of Surveillance Requirements BSEP 17-0109, Response to Request for Additional Information Regarding Request for Emergency License Amendment - Technical Specification 3.8.1, AC Sources - Operating, One-Time Extension of Emergency Diesel Generator Completion Times And.2017-11-24024 November 2017 Response to Request for Additional Information Regarding Request for Emergency License Amendment - Technical Specification 3.8.1, AC Sources - Operating, One-Time Extension of Emergency Diesel Generator Completion Times And. BSEP 17-0108, Request for Emergency License Amendment - Technical Specification 3.8.1, AC Sources - Operating, One-Time Extension of Emergency Diesel Generator Completion Times and Suspension of Surveillance Requirements2017-11-22022 November 2017 Request for Emergency License Amendment - Technical Specification 3.8.1, AC Sources - Operating, One-Time Extension of Emergency Diesel Generator Completion Times and Suspension of Surveillance Requirements BSEP 17-0017, Submittal of Request for License Amendment for Performance-Based Fire Protection Alternative for Thermal Insulation Material2017-11-15015 November 2017 Submittal of Request for License Amendment for Performance-Based Fire Protection Alternative for Thermal Insulation Material BSEP 17-0100, Fifth 10-Year Inservice Testing Interval2017-11-0202 November 2017 Fifth 10-Year Inservice Testing Interval BSEP 17-0089, Updates to Request for License Amendment Regarding Core Flow Operating Range Expansion2017-11-0101 November 2017 Updates to Request for License Amendment Regarding Core Flow Operating Range Expansion BSEP 17-0093, Response to Request for Additional Information Regarding Request for License Amendment Regarding Core Flow Operating Range Expansion2017-11-0101 November 2017 Response to Request for Additional Information Regarding Request for License Amendment Regarding Core Flow Operating Range Expansion BSEP 17-0078, Request for License Amendment - DC Sources - Operating Surveillance Requirement (SR) 3.8.4.52017-10-0303 October 2017 Request for License Amendment - DC Sources - Operating Surveillance Requirement (SR) 3.8.4.5 BSEP 17-0076, Registration for Use of General License Spent Fuel Casks2017-09-0606 September 2017 Registration for Use of General License Spent Fuel Casks BSEP 17-0081, Revision to Radiological Emergency Response Plan Implementing Procedures2017-09-0505 September 2017 Revision to Radiological Emergency Response Plan Implementing Procedures BSEP 17-0039, Submittal of Response to Inspection Report 05000324/2015404 and 05000325/2015404, Dated March 30, 2015, Inspection of Interim Cyber Security Milestones 1-7 and Target Set Requirements2017-08-15015 August 2017 Submittal of Response to Inspection Report 05000324/2015404 and 05000325/2015404, Dated March 30, 2015, Inspection of Interim Cyber Security Milestones 1-7 and Target Set Requirements BSEP 17-0071, ISFSI - Registration for Use of General License Spent Fuel Casks2017-08-15015 August 2017 ISFSI - Registration for Use of General License Spent Fuel Casks BSEP 17-0064, Application of Dissimilar Metal Weld Full Structural Overlay on Reactor Pressure Vessel Nozzle N92017-07-10010 July 2017 Application of Dissimilar Metal Weld Full Structural Overlay on Reactor Pressure Vessel Nozzle N9 BSEP 17-0060, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control.2017-06-29029 June 2017 Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control. 2019-01-17
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARRA-23-0199, Response to Request for Additional Information (RAI) Regarding Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for Inservice Inspection of the Torus Metallic Liner2023-08-18018 August 2023 Response to Request for Additional Information (RAI) Regarding Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for Inservice Inspection of the Torus Metallic Liner RA-22-0147, Duke Energy Carolinas, LLC, and Duke Energy Progress, LLC, Response to Request for Additional Information (RAI) Regarding License Amendment Request for Relocating the Duke Energy Emergency Operations Facility2022-05-13013 May 2022 Duke Energy Carolinas, LLC, and Duke Energy Progress, LLC, Response to Request for Additional Information (RAI) Regarding License Amendment Request for Relocating the Duke Energy Emergency Operations Facility RA-22-0003, Response to Requests for Additional Information for Reactor Vessel Closure Stud Exam Extension Alternative2022-01-31031 January 2022 Response to Requests for Additional Information for Reactor Vessel Closure Stud Exam Extension Alternative RA-21-0275, Response to Request for Additional Information, Exemption Request for Senior Reactor Operator License Application2021-10-25025 October 2021 Response to Request for Additional Information, Exemption Request for Senior Reactor Operator License Application RA-21-0262, Response to Request for Additional Information Regarding Proposed Alternative to ASME Boiler & Pressure Vessel Code Section XI Requirements for Repair/Replacement of Service Water (SW) System Buried Piping2021-10-0404 October 2021 Response to Request for Additional Information Regarding Proposed Alternative to ASME Boiler & Pressure Vessel Code Section XI Requirements for Repair/Replacement of Service Water (SW) System Buried Piping RA-21-0063, 1, 2; Catawba Nuclear Station 1, 2; H. B. Robinson Steam Electric Plant 2; Mcgguire Nuclear Station 1, 2; Oconee Nuclear Station 1, 2, 3; Shearon Harris Nuclear Power Plant 1 - Response to RAI Re Amend for Emergency Plan2021-03-11011 March 2021 1, 2; Catawba Nuclear Station 1, 2; H. B. Robinson Steam Electric Plant 2; Mcgguire Nuclear Station 1, 2; Oconee Nuclear Station 1, 2, 3; Shearon Harris Nuclear Power Plant 1 - Response to RAI Re Amend for Emergency Plan RA-21-0032, Duke Energy - Response to Requests for Additional Info for Request to Use a Provision of Later Edition & Addenda of the ASME Boiler & Pressure Vessel Code, Section XI for Repair/Replacement Activities in Accordance with 10 CFR 50.55a(g)(42021-02-11011 February 2021 Duke Energy - Response to Requests for Additional Info for Request to Use a Provision of Later Edition & Addenda of the ASME Boiler & Pressure Vessel Code, Section XI for Repair/Replacement Activities in Accordance with 10 CFR 50.55a(g)(4)( RA-20-0364, 1 & 2 - Response to RAI for License Amendment Request to Modify Approved 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors Categorization Process2020-11-24024 November 2020 1 & 2 - Response to RAI for License Amendment Request to Modify Approved 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors Categorization Process RA-20-0324, Response to Request for Additional Information for Proposed Alternative for RPV Nozzle-to-Vessel Weld and Inner Radii Examination Requirements2020-10-27027 October 2020 Response to Request for Additional Information for Proposed Alternative for RPV Nozzle-to-Vessel Weld and Inner Radii Examination Requirements RA-19-0380, Response to Request for Additional Information Regarding Advanced Framatome Methodologies License Amendment Request2019-10-17017 October 2019 Response to Request for Additional Information Regarding Advanced Framatome Methodologies License Amendment Request RA-19-0295, Response to Request for Additional Information - License Amendment Request to Revise Units 1 & 2 Technical Specification 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2019-07-25025 July 2019 Response to Request for Additional Information - License Amendment Request to Revise Units 1 & 2 Technical Specification 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies RA-19-0241, Response to Request for Additional Information Regarding Advanced Framatome Methodologies License Amendment Request2019-06-18018 June 2019 Response to Request for Additional Information Regarding Advanced Framatome Methodologies License Amendment Request RA-19-0240, Response to Request for Additional Information Regarding Advanced Framatome Methodologies License Amendment Request2019-05-29029 May 2019 Response to Request for Additional Information Regarding Advanced Framatome Methodologies License Amendment Request RA-19-0217, Supplement to Response to Request for Additional Information - Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery ...2019-05-16016 May 2019 Supplement to Response to Request for Additional Information - Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery ... RA-19-0152, Response to NRC Request for Additional Information (RAI) Regarding Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures,Systems, and Components (Sscs) for Nuclear Power Reactors.2019-04-0808 April 2019 Response to NRC Request for Additional Information (RAI) Regarding Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures,Systems, and Components (Sscs) for Nuclear Power Reactors. RA-19-0150, Response to Request for Additional Information - Request for License Amendment - Technical Specification 3.3.8.1, Loss of Power (LOP) Instrumentation2019-04-0303 April 2019 Response to Request for Additional Information - Request for License Amendment - Technical Specification 3.3.8.1, Loss of Power (LOP) Instrumentation RA-19-0010, Response to NRC RAI Re Application to Adapt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2019-02-13013 February 2019 Response to NRC RAI Re Application to Adapt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors RA-19-0089, Response to Request for Additional Information - Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure...2019-02-0808 February 2019 Response to Request for Additional Information - Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure... RA-18-0246, Revised Response to Request for Additional Information: Request for License Amendment to Revise the Technical Specifications to Relocate the Pressure- Temperature Limit Curves to a Pressure & Temperature ..2018-12-11011 December 2018 Revised Response to Request for Additional Information: Request for License Amendment to Revise the Technical Specifications to Relocate the Pressure- Temperature Limit Curves to a Pressure & Temperature .. RA-18-0178, Response to NRC Request for Additional Information (RAI) Regarding Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for ...2018-11-0202 November 2018 Response to NRC Request for Additional Information (RAI) Regarding Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for ... RA-18-0100, Request for License Amendment Regarding Application of Advanced Framatome Methodologies2018-10-11011 October 2018 Request for License Amendment Regarding Application of Advanced Framatome Methodologies RA-18-0144, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Report2018-09-27027 September 2018 Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Report RA-18-0163, Response to Request for Additional Information - Request for License Amendment to Revise the Technical Specifications to Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report2018-09-27027 September 2018 Response to Request for Additional Information - Request for License Amendment to Revise the Technical Specifications to Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report BSEP 18-0054, Response to Request for Additional Information Regarding Inservice Inspection Program Proposed Alternative ISI-09 in Accordance with 10 CFR 50.55a(z)(1) Regarding Reactor Pressure Vessel Circumferential.2018-04-24024 April 2018 Response to Request for Additional Information Regarding Inservice Inspection Program Proposed Alternative ISI-09 in Accordance with 10 CFR 50.55a(z)(1) Regarding Reactor Pressure Vessel Circumferential. BSEP 18-0048, Response to Request for Additional Information Regarding Inservice Inspection Program Proposed Alternative ISI-09 in Accordance with 10 CFR 50.55a(z)(1) Regarding Reactor Pressure Vessel Circumferential Shell Weld Examinations2018-04-11011 April 2018 Response to Request for Additional Information Regarding Inservice Inspection Program Proposed Alternative ISI-09 in Accordance with 10 CFR 50.55a(z)(1) Regarding Reactor Pressure Vessel Circumferential Shell Weld Examinations BSEP 18-0046, Supplement to Response to Request for Additional Information SRXB-RAI-2 Regarding Request for License Amendment Regarding Core Flow Operating Range Expansion2018-04-10010 April 2018 Supplement to Response to Request for Additional Information SRXB-RAI-2 Regarding Request for License Amendment Regarding Core Flow Operating Range Expansion BSEP 18-0035, Response to Request for Additional Information Regarding Request for License Amendment Regarding Core Flow Operating Range Expansion2018-03-29029 March 2018 Response to Request for Additional Information Regarding Request for License Amendment Regarding Core Flow Operating Range Expansion ML18075A3302018-03-0101 March 2018 Response to Request for Additional Information SNPB-RAI-2 Regarding Request for License Amendment Regarding Core Flow Operating Range Expansion (CAC Nos. MF8864 and MF8865) BSEP 18-0021, Response to Request for Additional Information Regarding Request for License Amendment Regarding Core Flow Operating Range Expansion (CAC Nos. MF8864 and MF8865). Without Proprietary Enclosure2018-02-0505 February 2018 Response to Request for Additional Information Regarding Request for License Amendment Regarding Core Flow Operating Range Expansion (CAC Nos. MF8864 and MF8865). Without Proprietary Enclosure BSEP 17-0115, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control2018-01-0404 January 2018 Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control BSEP 17-0118, Supplement to Response to Request for Additional Information Regarding Request for Risk-Informed Exigent License Amendment - Technical Specification 3.8.1, AC Sources - Operating, One-Time Extension of Emergency Diesel..2017-12-0707 December 2017 Supplement to Response to Request for Additional Information Regarding Request for Risk-Informed Exigent License Amendment - Technical Specification 3.8.1, AC Sources - Operating, One-Time Extension of Emergency Diesel.. BSEP 17-0117, Response to Request for Additional Information (Probabilistic Risk Assessment and Human Performance Branches) Regarding Request for Risk-Informed Exigent License Amendment - Technical Specification 3.8.1 AC Sources..2017-12-0606 December 2017 Response to Request for Additional Information (Probabilistic Risk Assessment and Human Performance Branches) Regarding Request for Risk-Informed Exigent License Amendment - Technical Specification 3.8.1 AC Sources.. BSEP 17-0116, Response to Request for Additional Information Regarding Request for Risk- Informed Exigent License Amendment - Technical Specification 3.8.1, AC Sources - Operating, One-Time Extension of ..2017-12-0404 December 2017 Response to Request for Additional Information Regarding Request for Risk- Informed Exigent License Amendment - Technical Specification 3.8.1, AC Sources - Operating, One-Time Extension of .. BSEP 17-0109, Response to Request for Additional Information Regarding Request for Emergency License Amendment - Technical Specification 3.8.1, AC Sources - Operating, One-Time Extension of Emergency Diesel Generator Completion Times And.2017-11-24024 November 2017 Response to Request for Additional Information Regarding Request for Emergency License Amendment - Technical Specification 3.8.1, AC Sources - Operating, One-Time Extension of Emergency Diesel Generator Completion Times And. RA-17-0039, Response to Request for Additional Information (RAI) Regarding 10 CFR 50.55a(z)(1)Proposed Alternative to ASME Section XI Threads in Flange Examination (17-GO-001)2017-08-0909 August 2017 Response to Request for Additional Information (RAI) Regarding 10 CFR 50.55a(z)(1)Proposed Alternative to ASME Section XI Threads in Flange Examination (17-GO-001) BSEP 17-0048, Clarification of Responses for Requests for Additional Information, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-423, Revision 1, Technical Specification End States..2017-05-24024 May 2017 Clarification of Responses for Requests for Additional Information, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-423, Revision 1, Technical Specification End States.. BSEP 17-0029, Response to Request for Additional Information Regarding Request for License Amendment Regarding Core Flow Operating Range Expansion2017-04-0606 April 2017 Response to Request for Additional Information Regarding Request for License Amendment Regarding Core Flow Operating Range Expansion BSEP 17-0026, Response to Request for Additional Information, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-423,Revision 1, Technical Specifications End States, NEDC-32988-A.2017-03-25025 March 2017 Response to Request for Additional Information, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-423,Revision 1, Technical Specifications End States, NEDC-32988-A. BSEP 17-0019, Enclosure 2 - Response to Request for Additional Information Regarding License Amendment Request for Reactor Protection System (RPS) Electrical Protection Assembly (EPA) Electric Power Monitoring Surveillance Requirements (Srs) 3.3.8.2.2017-03-0101 March 2017 Enclosure 2 - Response to Request for Additional Information Regarding License Amendment Request for Reactor Protection System (RPS) Electrical Protection Assembly (EPA) Electric Power Monitoring Surveillance Requirements (Srs) 3.3.8.2.2 an ML17087A2632017-03-0101 March 2017 Response to Request for Additional Information Regarding License Amendment Request for Reactor Protection System (RPS) Electrical Protection Assembly (EPA) Electric Power Monitoring Surveillance... BSEP 16-0113, High Frequency Supplement to Seismic Hazard Screening Report, Response to Nrg Request for Information Regarding Recommendation 2.1 of Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident2016-12-15015 December 2016 High Frequency Supplement to Seismic Hazard Screening Report, Response to Nrg Request for Information Regarding Recommendation 2.1 of Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident BSEP 16-0104, Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-lchi Accident2016-12-15015 December 2016 Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-lchi Accident BSEP 16-0112, (Bsep), Unit Nos. 1 and 2 - Individual Plant Examination of External Events (IPEEE) Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding ...2016-12-15015 December 2016 (Bsep), Unit Nos. 1 and 2 - Individual Plant Examination of External Events (IPEEE) Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding ... BSEP 16-0109, Response to Request for Additional Information, Revision to Requested Implementation Schedule, and Status Update - License Amendment Request Regarding Relocation of Specific Surveillance Frequency Requirements to Licensee-2016-11-17017 November 2016 Response to Request for Additional Information, Revision to Requested Implementation Schedule, and Status Update - License Amendment Request Regarding Relocation of Specific Surveillance Frequency Requirements to Licensee- BSEP 16-0101, Response to Request for Supplemental Information for License Amendment Request Regarding Core Flow Operating Range Expansion2016-11-0909 November 2016 Response to Request for Supplemental Information for License Amendment Request Regarding Core Flow Operating Range Expansion ML16330A5052016-11-0909 November 2016 Response to Request for Supplemental Information in Support of MELLLA + LAR, Non-Proprietary Information - Class I (Public) BSEP 16-0100, Clarification of Responses for Requests for Additional Information License Amendment Request for Relocation of Specific Surveillance Frequency Requirements to a Licensee-Controlled Program2016-11-0101 November 2016 Clarification of Responses for Requests for Additional Information License Amendment Request for Relocation of Specific Surveillance Frequency Requirements to a Licensee-Controlled Program RA-16-0035, Response to Request for Additional Information (RAI) Regarding Application for Emergency Operations Facility (EOF) Consolidation2016-10-0303 October 2016 Response to Request for Additional Information (RAI) Regarding Application for Emergency Operations Facility (EOF) Consolidation BSEP 16-0070, Response to Request for Additional Information Regarding License Amendment Request to Relocation of Specific Surveillance Frequency Requirements to a Licensee-Controlled Program2016-08-15015 August 2016 Response to Request for Additional Information Regarding License Amendment Request to Relocation of Specific Surveillance Frequency Requirements to a Licensee-Controlled Program BSEP 16-0072, Response to Request for Additional Information Regarding License Amendment Request to Relocation of Specific Surveillance Frequency Requirements to a Licensee-Controlled Program2016-08-0404 August 2016 Response to Request for Additional Information Regarding License Amendment Request to Relocation of Specific Surveillance Frequency Requirements to a Licensee-Controlled Program 2023-08-18
[Table view] |
Text
William R. Gideon Vice President Brunswick Nuclear Plant P.O. Box 10429 Southport, NC 28461 o: 910.457.3698 May 24, 2017 Serial: BSEP 17-0048 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Subject:
Brunswick Steam Electric Plant, Unit Nos. 1 and 2 Renewed Facility Operating License Nos. DPR-71 and DPR-62 Docket Nos. 50-325 and 50-324 Clarification of Responses for Requests for Additional Information License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-423, Revision 1, "Technical Specifications End States, NEDC-32988-A"
References:
- 1. Letter from William R. Gideon (Duke Energy) to U.S. Nuclear Regulatory Commission, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-423, Revision 1, "Technical Specifications End States, NEDC 32988-A", dated September 28, 2016, ADAMS Accession Number ML16287A415
- 2. NRR E-mail Capture - Brunswick Unit 1 and Unit 2 - Request for Additional Information Related to LAR to Modify the TS Requirements for End States Associated with the Implementation of the Approved TSTF Traveler TSTF-423-A (MF8466 and MF 8467),
dated February 3, 2017, ADAMS Accession Number ML17037A002
- 3. Letter from William R. Gideon (Duke Energy) to U.S. Nuclear Regulatory Commission, Response to Request for Additional Information, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-423, Revision 1, "Technical Specifications End States, NEDC-32988-A," dated March 25, 2017, ADAMS Accession Number ML17086A006 Ladies and Gentlemen:
By letter dated September 28, 2016 (i.e., Reference 1), Duke Energy Progress, LLC, (Duke Energy) submitted a license amendment request (LAR) for the Brunswick Steam Electric Plant (BSEP), Unit Nos. 1 and 2. The proposed amendment would modify the Technical Specifications (TSs) to risk-informed requirements regarding selected Required Action end states by incorporating the Boiling Water Reactor (BWR) Owners' Group (BWROG) approved Topical Report NEDC-32988-A, Revision 2, "Technical Justification to Support Risk-Informed Modification to Selected Required Action End States for BWR Plants." Additionally, the proposed amendment would modify the TS Required Actions with a Note prohibiting the use of Limiting Condition for Operation (LCO) 3.0.4.a when entering the preferred end state (i.e.,
Mode 3) on reactor startup.
U.S. Nuclear Regulatory Commission Page 2 of 3 On February 3, 2017 (i.e., Reference 2), by electronic mail, the NRG provided a request for additional information (RAI) regarding the LAR. Duke Energy responded to the RAI on March 25, 2017 (i.e., Reference 3). The RAI response was discussed, by telephone, with the NRG on April 27, 2017. During this call, it was agreed that clarifying information would be provided to supplement Duke Energy's response to NRG RAI 2. The clarifying information is provided in the Enclosure of this letter.
This document contains no regulatory commitments.
Please refer any questions regarding this submittal to Mr. Lee Grzeck, Manager - Regulatory Affairs, at (910) 457-2487.
I declare, under penalty of perjury, that the foregoing is true and correct. Executed on May 24, 2017.
Siz;Jo William R. Gideon MAT/mat
Enclosure:
Clarifying Information Regarding Response to Request for Additional Information
U.S. Nuclear Regulatory Commission Page 3 of 3 cc (with Enclosure):
U. S. Nuclear Regulatory Commission, Region II ATTN: Ms. Catherine Haney, Regional Administrator 245 Peachtree Center Ave, NE, Suite 1200 Atlanta, GA 30303-1257 U.S. Nuclear Regulatory Commission ATTN: Mr. Andrew Hon (Mail Stop OWFN 8G9A) (Electronic Copy Only) 11555 Rockville Pike Rockville, MD 20852-2738 Andrew.Hon@nrc.gov U.S. Nuclear Regulatory Commission ATTN: Ms. Michelle P. Catts, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 Chair - North Carolina Utilities Commission (Electronic Copy Only) 4325 Mail Service Center Raleigh, NC 27699-4300 swatson@ncuc.net Mr. W. Lee Cox, III, Section Chief (Electronic Copy Only)
Radiation Protection Section North Carolina Department of Health and Human Services 1645 Mail Service Center Raleigh, NC 27699-1645 lee.cox@dhhs.nc.gov
BSEP 17-0048 Enclosure Page 1 of 2 Clarifying Information Regarding Response to Request for Additional Information By letter dated September 28, 2016, Duke Energy Progress, LLC, (Duke Energy) submitted a license amendment request (LAR) for the Brunswick Steam Electric Plant (BSEP), Unit Nos. 1 and 2. The proposed amendment would modify the Technical Specifications (TSs) to risk-informed requirements regarding selected Required Action end states by incorporating the Boiling Water Reactor (BWR) Owners' Group (BWROG) approved Topical Report NEDC-32988-A, Revision 2, "Technical Justification to Support Risk-Informed Modification to Selected Required Action End States for BWR Plants." Additionally, the proposed amendment would modify the TS Required Actions with a Note prohibiting the use of Limiting Condition for Operation (LCO) 3.0.4.a when entering the preferred end state (i.e., Mode 3) on reactor startup.
On February 3, 2017, by electronic mail, the NRC provided a request for additional information (RAI) regarding the LAR. Duke Energy responded to the RAI on March 25, 2017.
The RAI response was discussed, by telephone, with the NRC on April 27, 2017. During this call, it was agreed that clarifying information would be provided to supplement Duke Energy's response to NRC RAI 2. The clarifying information is provided below.
NRC RAI 2 Please provide Emergency Core Cooling Systems (ECCS) analysis and containment analysis and results to verify acceptable ECCS performance, containment integrity, Environmental Equipment Qualification (EEQ), and containment heat removal for a design basis Loss of Coolant Accident (LOCA) in Mode 3 when one LPCI pump and one CS pump are concurrently inoperable in this mode.
Clarification of BSEP Response to NRC RAI 2:
NUREG-1433, "Standard Technical Specifications General Electric BWR/4 Plants," Revision 4, Volume 2, "Bases," states that the Core Spray (CS) System is composed of two independent subsystems. Each subsystem consists of a motor driven pump, a spray sparger above the core, and piping and valves to transfer water from the suppression pool to the sparger. It also states that Low Pressure Coolant Injection (LPCI) is an operating mode of the Residual Heat Removal (RHR) System. There are two LPCI subsystems, each consisting of two motor driven pumps and required piping and valves to transfer water from the suppression pool to the Reactor Pressure Vessel (RPV) via the corresponding recirculation loop.
TSTF-423 approved elimination of proceeding to Mode 4 for NUREG-1433 Condition A of TS 3.5.1.
A. One low pressure ECCS injection/spray subsystem inoperable.
OR One LPCI pump in both LPCI subsystems inoperable.
Therefore, NUREG-1433 is applicable to one LPCI pump inoperable, two LPCI pumps in a single subsystem inoperable, one LPCI pump in each subsystem inoperable (i.e., two pumps total), or one CS pump inoperable. The maximum level of degradation is two of six low
BSEP 17-0048 Enclosure Page 2 of 2 pressure ECCS pumps. In each of these circumstances, it was deemed acceptable to remain in Mode 3 per approval of TSTF-423.
Approval of the changes to NUREG-1433, TS 3.5.1 was based on Topical Report NEDC-32988-A. The justification for the changes states:
A comparative PSA evaluation of the core damage risks of operation in the current end state versus the proposed Mode 3 end state was performed. The results indicate that the core damage risks while operating in the proposed Mode 3 (assuming the individual failure conditions) are lower or comparable to the current end state. Going to Mode 4 for the specified inoperable conditions would cause loss of both high pressure steam injection systems (HPCI and RCIC), loss of the feedwater/condensate system, and require activating the RHR Shutdown Cooling System. In addition, maintaining the reactor steam dome pressure above 150 psig preserves the availability of the high pressure systems. It is concluded that, based on these lower or equivalent calculated risks, staying in Mode 3 to restore systems back to service is the preferred end state rather than going to Mode 4 or a mode where reactor pressure is 150 psig.
The BSEP TS Bases are identical to the NUREG-1433 Bases with respect to CS and LPCI configuration. Additionally, BSEP TS 3.5.1 Condition A is the same as NUREG-1433, TS 3.5.1 Condition A.
BSEP TS 3.5.1 Condition B does not exist in NUREG-1433, TS 3.5.1. BSEP Condition B states:
B. One LPCI pump inoperable.
AND One core spray (CS) subsystem inoperable.
The proposed BSEP markup eliminates proceeding to Mode 4 for Condition B of TS 3.5.1.
Having one LPCI and one CS pump inoperable represents a maximum level of degradation of two of six low pressure ECCS pumps; consistent with that allowed in Condition A. As such, the BSEP justification for the change to BSEP TS 3.5.1 Condition B is that the justification provided in Topical Report NEDC-32988-A for a maximum level of degradation of two of six low pressure ECCS pumps (i.e., a total of two LPCI pumps) provided in TS 3.5.1 Condition A is also applicable to a maximum level of degradation of two of six low pressure ECCS pumps (i.e., one LPCI pump and one CS pump) provided in TS 3.5.1 Condition B. The mitigation capability of having one LPCI pump and one CS pump inoperable is not significantly different than having two LPCI pumps inoperable. Duke Energy's March 25, 2017, response to NRC RAI 2 demonstrates that BSEP is analyzed for concurrent inoperability of one CS and one LPCI pump.
The BSEP LOCA analysis demonstrates that the consequences of a LOCA with one CS and one LPCI pump inoperable are mitigated to within acceptable regulatory limits. The BSEP LOCA analysis is performed at 102 percent of Rated Thermal Power (RTP) and fully bounds a hypothetical Mode 3 LOCA. Additionally, BSEP has committed to follow the guidance established in TSTF-IG-05-02, Revision 2, "Implementation Guidance for TSTF-423, Revision 1,
'Technical Specifications End States, NEDC-32988-A.'" Therefore, entry into Mode 3 from either Condition A or Condition B will be limited to no more than seven days.