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Category:E-Mail
MONTHYEARML23248A2612023-09-0505 September 2023 NRR E-mail Capture - Brunswick Steam Electric Plant, Units 1 and 2 - Acceptance of License Amendment Request to Revise the 10 CFR 50.69 Categorization Process ML23202A0652023-07-19019 July 2023 NRR E-mail Capture - Request for Additional Information - Brunswick Steam Electric Plant, Units 1 and 2, Torus Liner Inspection Alternative Request (L-2022-LLR-0089) ML23142A2732023-05-22022 May 2023 Duke Fleet - Request for Additional Information Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) ML23073A2282023-03-13013 March 2023 Duke Fleet- Adoption of TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements - Acceptance Review ML23032A2472023-01-26026 January 2023 Document Request Letter for Brunswick Upcoming RP Inspection 2023002 ML23018A1892023-01-17017 January 2023 Document Request for RP Inspection at Brunswick Inspection Report 2023-01 ML23006A0642023-01-0606 January 2023 NRR E-mail Capture - Acceptance Review Results for Brunswick, Unit Nos. 1 and 2 - Proposed Alternative Request RA-22-0308 ML23006A1892023-01-0606 January 2023 NRR E-mail Capture - Corrected - Acceptance Review Results for Brunswick, Unit Nos. 1 and 2 - Proposed Alternative Request RA-22-0308 NRC-2100-2022, EN 55999 Valcor Coil Shell Assemblies Final Notification (004)2022-09-12012 September 2022 EN 55999 Valcor Coil Shell Assemblies Final Notification (004) NRC 2110-2022, EN 55999 - Valcor Engineering Corporation (009)2022-07-18018 July 2022 EN 55999 - Valcor Engineering Corporation (009) ML22115A1412022-04-25025 April 2022 NRR E-mail Capture - Duke Common EOF Relocation - Request for Addition Information ML22038A1572022-02-0707 February 2022 NRR E-mail Capture - Duke Energy Fleet - Acceptance of License Amendment Request Regarding Adoption of TSTF-541, Revision 2 ML22018A0272022-01-18018 January 2022 2022 All RFI Responses - Exercise and Program Inspections - Revl ML21357A0472021-12-23023 December 2021 NRR E-mail Capture - Brunswick Steam Electric Plant, Units 1 and 2 - Acceptance of License Amendment Request Regarding Adoption of TSTF-580 ML21361A0122021-12-23023 December 2021 NRR E-mail Capture - Accepted for Review - Duke Energy Fleet License Amendment Request to Relocate Emergency Operations Facility ML21354A8612021-12-15015 December 2021 NRR E-mail Capture - Request for Additional Information - Duke Fleet Request RA-19-0352 - Alternative for RPV Closure Stud Exams (L-2020-LLR-0156) ML21277A0952021-10-0101 October 2021 NRR E-mail Capture - Request for Additional Information - Brunswick Exemption Request from 10CFR 55.47 License Operator Exam Two-year Waiver Limit ML21200A1582021-07-16016 July 2021 NRR E-mail Capture - Accepted for Review - Brunswick License Amendment Request to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery ML21168A0042021-06-17017 June 2021 Notification of Inspection and Request for Information ML21137A1622021-04-26026 April 2021 NRR E-mail Capture - Accepted for Review - Brunswick License Amendment Request to Adopt TSTF-505 Risk-Informed Completion Time (L-2021-LLA-0060) ML21082A0162021-03-22022 March 2021 Accepted for Review - Brunswick License Amendment Request to Change Tech Spec Limit for Standby Liquid Control System Boron Solution Storage Tank Volume L-2021-LLA-0022 ML21075A0032021-03-12012 March 2021 Emergency Preparedness Exercise Inspection Request for Information for - Brunswick, Catawba, North Anna, Oconee, Vogtle 1 & 2 ML21049A2632021-02-0404 February 2021 NRR E-mail Capture - Request for Additional Information - Duke Energy Fleet License Amendment Request to Revise Emergency Plan ML21019A3772021-01-13013 January 2021 002 Radiation Safety Baseline Inspection Information Request ML21007A3722021-01-0707 January 2021 NRR E-mail Capture - Acceptance Review - Duke Fleet - RA-19-0352 - Proposed Alternative for Reactor Vessel Close Stud Examinations (L-2020-LLR-0156) ML20323A4072020-11-18018 November 2020 NRR E-mail Capture - Request for Additional Information - Brunswick License Exemption Request from 10CFR73 Annual Force on Force Exercise Requirements (EPIC L-2020-LLE-0180) ML20309A5212020-10-29029 October 2020 Request for Additional Information - Brunswick License Amendment Request to Modify Its Approved 10 CFR 50.69, Risk-Informed Categorization and Treatment of SSC Categorization Process ML20294A0642020-10-20020 October 2020 NRR E-mail Capture - Accepted for Review - Duke Energy Fleet License Amendment Request to Adopt TSTF-582 RPV Water Inventory Control Enhancements(L-2020-LLA-0218) ML20297A3102020-10-13013 October 2020 NRR E-mail Capture - Acceptance Review - Duke Fleet - RA-20-0191 - Request to Use a Provision of a Later Edition of the ASME B&PV Code, Section XI - IWA-5120, IWA-5213, IWA-5241, IWA-5242, and IWA-5250 (L-2020-LLR-0126) ML20297A3082020-10-0707 October 2020 NRR E-mail Capture - Acceptance Review - Duke Fleet - RA-20-0263 - Request to Use a Provision of a Later Edition of the ASME B&PV Code, Section XI for Repair/Replacement (L-2020-LLR-0124) ML20297A3092020-10-0606 October 2020 NRR E-mail Capture - Acceptance Review - Duke Fleet - RA-20-0262 - Request to Use a Provision of a Later Edition of the ASME B&PV Code, Section XI - IWA-4540(b) (L-2020-LLR-0125) ML20275A2972020-10-0101 October 2020 NRR E-mail Capture - Request for Additional Information - Brunswick Request for Alternate Examination of Reactor Vessel Nozzles ML21033A8562020-08-0505 August 2020 NRR E-mail Capture - Accepted for Review - Brunswick Relief Request for RPV Nozzle-to-Vessel Weld and Inner Radii Examination Requirements EPID-L-2020-LLR-0091 ML20121A1262020-04-29029 April 2020 Radiation Safety Baseline Inspection Information Request ML20111A1212020-04-20020 April 2020 NRR E-mail Capture - Accepted for Review - Brunswick Request for Alternative to Examination Category B-N-1 (VT-3) Visual Examination of Accessible Areas of the Reactor Vessel Interior - EPID: L-2020-LLR-0048 ML20017A1602020-01-17017 January 2020 E-mail Notification of Inspection and Request for Additional Information ML19283D0852019-10-0909 October 2019 Request for Additional Information - Brunswick Atrium 11 LAR ML19252A4572019-09-0808 September 2019 (FEMA Email 09-08-19) Tentative Notification of Brunswick Preliminary Capability Assessment Results ML19252A4092019-09-0606 September 2019 (E-mail to FEMA 09-06-19) FEMA Notification for Planned Restart of Brunswick Units 1 and 2 ML19219A2132019-08-0707 August 2019 NRR E-mail Capture - Duke Energy Fleet - Acceptance of Requested Licensing Action Amendment Requests to Relocate the TSs Staff Qualification Requirements to the Duke Energy Corporation QAPD ML19179A1312019-06-27027 June 2019 NRR E-mail Capture - Brunswick RAIs - LAR to Revise TS 5.5.12, Primary Containment Leakage Rate Testing Program for Permanent Extension of Maximum Appendix J Test Intervals (L 2019-LLA-0031) ML19177A0122019-06-25025 June 2019 NRR E-mail Capture - Draft Brunswick RAIs - LAR to Revise TS 5.5.12, Primary Containment Leakage Rate Testing Program for Permanent Extension of Maximum Appendix J Test Intervals (L 2019-LLA-0031) ML19162A3902019-06-11011 June 2019 NRR E-mail Capture - Brunswick Steam Electric Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Fourth 10-Year Inservice Inspection Interval ISI-12 ML19162A3912019-06-11011 June 2019 NRR E-mail Capture - Duke Energy Fleet - Acceptance of Requested Licensing Action Relief Request (19-GO-001) Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination in Lieu of Radiography ML19092A1152019-04-0101 April 2019 NRR E-mail Capture - Brunswick Steam Electric Plant, Unit Nos. 1 and 2 - Acceptance of Requested Licensing Action Amendment Request to Modify Surveillance Requirements for Safety Relief Valves (L-2019-LLA-0043) ML19092A1142019-04-0101 April 2019 NRR E-mail Capture - Brunswick Plant, Unit 1 and 2 - Acceptance of Requested Licensing Action Amendment Request to Modify TS 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies (L-2019-LLA-0031) ML19067A2712019-03-0707 March 2019 NRR E-mail Capture - Brunswick 3rd Round RAI - LAR to Allow Implementation of the Provisions 10 CFR 50.69 ML19065A0962019-03-0606 March 2019 NRR E-mail Capture - Brunswick RAIs - LAR to Revise Allowable Value for TS 3.3.8.1 Time Delay on Loss of Voltage ML19058A0742019-02-26026 February 2019 NRR E-mail Capture - Draft Brunswick RAIs - LAR to Revise Allowable Value for TS 3.3.8.1 Time Delay on Loss of Voltage ML19056A2212019-02-25025 February 2019 NRR E-mail Capture - Brunswick Draft 3rd Round RAI - LAR to Allow Implementation of the Provisions 10 CFR 50.69 2023-09-05
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I Richard Emch - FW: Cooling Towers Page 1 111 II I Richard Emch FW: Cooling Towers Page From: "Kozyra, Jan" <jan.kozyra~pgnmail.com>
To: "Richard Emch" <RLE~nrc.gov>
Date: Wed, Jun 22, 2005 3:40 PM
Subject:
FW: Cooling Towers See below. The condensate cooling mod was not installed; the 375 gpm is not being used.
- -----Original Message-----
> From: Turkal, Mark
> Sent: Wednesday, June 22, 2005 3:13 PM
> To: Kozyra, Jan
Subject:
RE: Cooling Towers
> <<EPU Mods.pdf>>
> Jan,
> As we discussed, Brunswick ultimately determined that the condensate
> cooling modification was not necessary. The primary reason for the
> mod was a concern with resin breakdown due to higher condensate
> temperatures expected post-EPU. Rather than install a new cooling
> system, we found resin that could better withstand increased
> temperature and this obviated the need for new system. The attached
> pdf is the section of our original EPU submittal which states that
> the modifications needed for implementation planned actions not
> commitments and that the list may change based on further engineering
> evaluations.
> Mark
> -----Original Message-----
> From: Kozyra, Jan
> Sent: Wednesday, June 22, 2005 12:32 PM
> To: Turkal, Mark
Subject:
Cooling Towers
> See attached, page 36041, first column, "Cooling Tower Impacts, and
> third column, "Water Use Impacts."
> << File: getdoc.pdf >>
c:\temD\GWI00001 .TMP -Pacie Paae 11 I c:\temo\GWIOOOO1 .TMP Mail Envelope Properties (42B9BE98.9C1:14: 51649)
Subject:
FW: Cooling Towers Creation Date: Wed, Jun 22,2005 3:38 PM From: "Kozyra, Jan" <ian.kozyra@pgnmail.com>
Created By: Jan.kozyra@pgnmail .com Recipients nrc.gov OWGWPO02.HQGWDO01 RLE (Richard Emch)
Post Office Route OWGWPO02.HQGWDO01 nrc.gov Files Size Date & Time MESSAGE 1285 Wednesday, June 22,2005 3:38 PM TEXT.htm 2904 EPU Mods.pdf 20657 Mime.822 1 Options Expiration Date: None Priority: Standard Reply Requested: No Return Notification: None Concealed
Subject:
No Security: Standard
ENCLOSURE 2 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-325 AND 50-324/LICENSE NOS. DPR-71 AND DPR-62 REQUEST FOR LICENSE AMENDMENTS EXTENDED POWER UPRATE List of Planned Modifications The following is a list of currently planned modifications necessary to support Extended Power Uprate (EPU). Unless otherwise indicated, the modifications will be implemented on both Brunswick Steam Electric Plant (BSEP) Unit 1 and Unit 2. These modifications will be implemented during the next two refueling outages on each unit (i.e., refueling outages beginning in March 2002 (BI14R1) and March 2004 (B1l5RI) for Unit 1 and March 2003 (B216R1) and March 2005 (B217R1) for Unit 2). Modifications performed during the first refueling outage on each unit will allow for a 5 to 7 percent uprate, from Rated Thermal Power (RTP). Modifications performed during the second refueling outage should allow the units to achieve the full uprate to 2923 megawatts thermal (MWt). The following modifications constitute planned actions on the part of Carolina Power & Light (CP&L) Company. Further evaluations may identify the need for additional modifications or, on the contrary, obviate the need for some modifications. As such, this list is not a formal commitment to implement the modifications exactly as described or per the proposed schedule. Additionally, various setpoint changes and changes to indicating ranges on certain control room and in-plant instrumentation, which may be necessary, are not listed.
Modifications Supporting Initial Uprate
- 1. First Load of GE14 Fuel Unit 2 loaded the first batch of GE14 fuel during the Spring 2001 refueling outage.
- 2. High Pressure Turbine Replacement and Electro-Hydraulic Control Admission Mode Change
- 3. Main Generator Rewind (Unit 1)
This modification was completed on Unit 2 during the Spring 2001 refueling outage.
- 4. Reactor Feedwater Pump Turbine Replacement
- 5. Isophase Bus Cooling Upgrade (Unit 1)
- 6. Out-of-Step Relay and Blocking Modification This modification addresses grid stability issues under EPU conditions.
- 7. Feedwater Heater Replacement Unit 1 will require replacement of feedwater heaters SA and 5B to support the initial uprate.
Unit 2 does not require replacement of any feedwater heaters to support the initial uprate.
However, for convenience, feedwater heater 4B, whose replacement is required to support the full uprate, will be replaced during the Spring 2003 refueling outage.
- 8. Condensate Cooling Modification E2-1
- 9. Generator Lockout Load Shed Modification This modification assures adequate loss-of-coolant accident voltage support following a generator lockout.
- 10. Nuclear Instrumentation Upgrade This modification results in a revision to the BSEP long-term solution to thermal-hydraulic stability from the existing Boiling Water Reactor Owners' Group (BWROG) Enhanced Option I-A long-term solution to the BWROG Option III solution. CP&L has requested, via separate submittal, a license amendment request (Serial: BSEP 01-0076, dated June 26, 2001) which supports this change.
- 11. Main Steam and Feedwater Vibration Monitoring Instrumentation
- 12. Potential modifications supporting Alternative Source Term implementation Modifications Supporting Full Uprate
- 1. Standby Liquid Control (SLC) Upgrade SLC upgrade supports the transition to GE14 fuel design, necessary to achieve the full EPU.
This modification is not required until the second reload with GE14 on each unit. As such, the associated license amendments, revising the sodium pentaborate solution concentration requirements contained in Technical Specification 3.1.7, "Standby Liquid Control (SLC)
System," will be submitted separate from the EPU submittal. Since Unit 2 has already had one reload using GE14 fuel, issuance of this amendment will be required in Spring 2003, to support initial Unit 2 uprate.
- 2. Stator Cooling Water Upgrade
- 3. Power System Stabilizer This modification will provide feedback to the voltage regulatory to dampen oscillations following grid disturbances.
- 4. Isophase Bus Cooling Upgrade (Unit 2)
- 5. Main Transformer Replacement/Rewind
- 6. Condensate System Upgrade
- 7. Feedwater Heater Replacement Unit I will require replacement of feedwater heaters 3A, 3B, and 4A to support the final uprate. Unit 2 will require replacement of feedwater heater 4B (i.e., to be performed during the Spring 2003, refueling outage) to support the final uprate.
- 8. Moisture Separator Reheater (MSR) Upgrade
- 9. Reactor Building Component Cooling Water System Heat Exchanger Retubing (Unit 1)
- 10. Condensate Filter Demineralizer (CFD) Upgrade This modification will install longer filter elements to increase CFD filter element life.
E2-2
I
- 11. MSR Relief Valve Modifications This modification will implemient higher setpoints and replace a spring in one valve
- 12. Reactor Feed Pump Upgrade E2-3