Letter Sequence Response to RAI |
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Results
Other: BSEP 16-0042, Fourth 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 (EA-13-109), BSEP 16-0111, (Bsep), Unit Nos. 1 & 2, Fifth 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 ., BSEP 17-0043, Sixth 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 17-0110, 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 Conditions, ML18130A826, RA-18-0017, (Bsep), Unit No. 1, Completion of Required Action for NRC Order EA-13-109, Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions
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MONTHYEARBSEP 16-0042, Fourth 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 (EA-13-109)2016-06-28028 June 2016
Fourth 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 (EA-13-109)
Project stage: Other
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
Project stage: Request
BSEP 16-0111, (Bsep), Unit Nos. 1 & 2, Fifth 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 .2016-12-15015 December 2016
(Bsep), Unit Nos. 1 & 2, Fifth 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 .
Project stage: Other
BSEP 17-0043, Sixth 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 Conditions2017-06-19019 June 2017
Sixth 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
Project stage: Other
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
Project stage: Request
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
Project stage: Other
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
Project stage: Request
ML18130A7462018-05-10010 May 2018
NRR E-mail Capture - Brunswick - LAR to Relocate PT Limits Curves to PTLR - Draft Supplemental Information Needed
Project stage: Draft Approval
ML18130A8262018-05-15015 May 2018
Supplemental Information Needed for Acceptance. Amendment Request to Revise the Technical Specifications to Relocate the Pressure Temperature Limit Curves to a Pressure and Temperature Limits Report
Project stage: Other
RA-18-0017, (Bsep), Unit No. 1, Completion of Required Action for NRC Order EA-13-109, Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions2018-05-29029 May 2018
(Bsep), Unit No. 1, Completion of Required Action for NRC Order EA-13-109, Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions
Project stage: Other
RA-18-0024, Supplemental Information to Request for License Amendment to Revise the Technical Specifications to Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report2018-05-29029 May 2018
Supplemental Information to Request for License Amendment to Revise the Technical Specifications to Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report
Project stage: Supplement
ML18163A0362018-06-11011 June 2018
NRR E-mail Capture - Brunswick, Unit Nos. 1 and 2 Acceptance of Requested Licensing Action Amendment Request to Revise TSs to Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report (L-2018-LLA-0094)
Project stage: Acceptance Review
ML18225A0122018-08-10010 August 2018
NRR E-mail Capture - Draft Brunswick RAIs - LAR to Revise TS to Relocate the Pressure-Temperature Limits to the Pressure and Temperature Limits Report
Project stage: Draft RAI
ML18250A3082018-08-31031 August 2018
NRR E-mail Capture - Brunswick RAIs - LAR to Revise TS to Relocate the Pressure-Temperature Limits to the Pressure and Temperature Limits Report
Project stage: RAI
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
Project stage: Response to RAI
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 & Temperature2018-12-11011 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
Project stage: Response to RAI
ML19035A0062019-04-22022 April 2019
Issuance of Amendment Nos. 289 and 317 to Relocate the Pressure-Temperature Limits in the Technical Specifications to the Pressure-Temperature Limits Report
Project stage: Approval
2018-05-10
[Table View] |
Text
William R. Gideon Vice President Brunswick Nuclear Plant P.O. Box 10429 Southport, NC 28461 o: 910.832.3698 December 11, 2018 Serial: RA-18-0246 10 CFR 50.90 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 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 and Temperature Limits Report
References:
- 1.
Letter from William R. Gideon (Duke Energy) to the U.S. Nuclear Regulatory Commission Document Control Desk, Request for License Amendment to Revise the Technical Specifications to Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report, dated April 4, 2018, ADAMS Accession Number ML18094B058
- 2.
Letter from William R. Gideon (Duke Energy) to the U.S. Nuclear Regulatory Commission Document Control Desk, Supplemental Information to Request for License Amendment to Revise the Technical Specifications to Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report, dated May 29, 2018, ADAMS Accession Number ML18149A487
- 3.
Letter from William R. Gideon (Duke Energy) to the U.S. Nuclear Regulatory Commission Document Control Desk, 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, dated September 27, 2018, ADAMS Accession Number ML18270A390 Ladies and Gentlemen:
By letter dated April 4, 2018, as supplemented on May 29, 2018 (i.e., References 1 and 2),
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 requested relocation of the Technical Specifications pressure-temperature (P-T) limits to a licensee-controlled Pressure and Temperature Limits Report (PTLR). Additionally, the current 32-effective full power year (EFPY) P-T limits are being updated to 54-EFPY P-T limits.
U.S. Nuclear Regulatory Commission Page 2 of 2 On September 27, 2018, (i.e., Reference 3), Duke Energy responded to a request for additional information (RAI) regarding the proposed amendment. Subsequently, the need to revise the response to SNPB RAI 2 was identified. The revised response is included in the enclosure.
This document contains no new regulatory commitments.
I declare, under penalty of perjury, that the foregoing is true and correct. Executed on December 11, 2018.
Sincerely, wulO William R. Gideon MAT/mat
Enclosure:
Revised Response to SNPB RAI 2 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. Dennis J. Galvin 11555 Rockville Pike Rockville, MD 20852-2738 U.S. Nuclear Regulatory Commission ATTN: Mr. Gale Smith, NRC Senior Resident Inspector 84 70 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, Ill, 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
RA-18-0246 Enclosure Page 1 of 1 Revised Response to SNPB RAI 2 By letter dated April 4, 2018, as supplemented on May 29, 2018, 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 requested relocation of the Technical Specifications pressure-temperature (P-T) limits to a licensee-controlled Pressure and Temperature Limits Report (PTLR). Additionally, the current 32-effective full power year (EFPY)
P-T limits are being updated to 54-EFPY P-T limits.
On September 27, 2018, Duke Energy responded to a request for additional information (RAI) regarding the proposed amendment. Subsequently, the need to revise the response to SNPB RAI 2 was identified. The revised response is provided below.
SNPB RAI 2 In the supplement to the LAR dated May 29, 2018, (WCAP-17660-NP), in Section 2.1 in the subsection titled, "Fuel Cycle Modeling," the licensee described the approach used to determine the reactor pressure vessel neutron fluence for future nominal Maximum Extended Load Line Limit Analysis Plus (MELLLA+) equilibrium fuel cycles. The licensee also provided tables with assumed relative power fraction (RPF), axial power, and axial void fraction distribution inputs to the fluence calculational model for operating under MELLLA+ conditions to be used to confirm that the actual core design is comparable to the nominal. If the actual RPFs, axial power, or axial void fraction distributions are not bounded by those nominally assumed when MELLLA+ is implemented at Brunswick, updated fluence values would need to be determined for input to P-T limits re-assessment. However, the licensee does not describe an approach for determining updated fluence values.
Describe the approach for determining updated fluence values if the actual RPFs, axial power, or axial void fraction distributions are not bounded by those assumed in the WCAP-17660-NP fluence analysis when MELLLA+ is implemented at BSEP.
Response to SNPB RAI 2 If the assumptions supporting the fluence projections in WCAP-17660-NP are not implemented or are not realistic for actual MELLLA+ operating conditions, then the actual neutron fluence will diverge from the fluence projections. Neutron fluence will be re-evaluated on an as-needed basis to include operating data and new fuel projections.
