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| | number = ML082540198 | | | number = ML082540198 |
| | issue date = 10/01/2008 | | | issue date = 10/01/2008 |
| | title = LaSalle County Station, Units 1 and 2, Request for Additional Information, License Amendment Request to Revise Local Power Range Monitor Calibration Frequency (TAC Nos. MD9414 and MD9415) | | | title = Request for Additional Information, License Amendment Request to Revise Local Power Range Monitor Calibration Frequency |
| | author name = Sands S P | | | author name = Sands S |
| | author affiliation = NRC/NRR/DORL/LPLIII-2 | | | author affiliation = NRC/NRR/DORL/LPLIII-2 |
| | addressee name = Pardee C G | | | addressee name = Pardee C |
| | addressee affiliation = Exelon Generation Co, LLC | | | addressee affiliation = Exelon Generation Co, LLC |
| | docket = 05000373, 05000374 | | | docket = 05000373, 05000374 |
| | license number = NPF-011, NPF-018 | | | license number = NPF-011, NPF-018 |
| | contact person = Sands S P,NRR/DORL, 415-3154 | | | contact person = Sands S,NRR/DORL, 415-3154 |
| | case reference number = TAC MD9414, TAC MD9415 | | | case reference number = TAC MD9414, TAC MD9415 |
| | document type = Letter, Request for Additional Information (RAI) | | | document type = Letter, Request for Additional Information (RAI) |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 October 1, 2008 Mr. Charles G. Pardee Chief Nuclear Officer and Senior Vice President Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 LASALLE COUNTY STATION, UNITS 1 AND 2 -REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST TO REVISE LOCAL POWER RANGE MONITOR CALIBRATION FREQUENCY (TAC NOS. MD9414 AI\ID MD9415) | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 1, 2008 Mr. Charles G. Pardee Chief Nuclear Officer and Senior Vice President Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 SUB.JECT: LASALLE COUNTY STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST TO REVISE LOCAL POWER RANGE MONITOR CALIBRATION FREQUENCY (TAC NOS. |
| | MD9414 AI\ID MD9415) |
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| ==Dear Mr. Pardee:== | | ==Dear Mr. Pardee:== |
| By letter to the Nuclear Regulatory Commission (NRC) dated July 25, 2008, Exelon Generation Company, LLC submitted a request to revise Technical Specification (TS) 3.3.1.1, "Reactor Protection System (RPS) Instrumentation," Surveillance Requirement (SR) 3.3.1.1.8 and TS 3.3.1.3, "Oscillation Power Range Monitor (OPRM) Instrumentation," SR 3.3.1.3.2 to increase the frequency interval between local power range monitor calibrations from 1000 effective full power hours (EFPH) to 2000 EFPH, for the LaSalle County Station, Units 1 and 2. The NRC staff has accepted your license amendment request for review and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. During a discussion with your staff on September 10, 2008, it was agreed that you would provide a response 30 days from the date of this letter. The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources.
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| 'If circumstances result in the need to revise the requested response date, please contact me at (301) 415-3154.
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| Sincerely,
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| P. Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-373 and Request for Additional cc w/encl: See next LaSalle County Station, Units 1 and 2 cc: Distribution via Listserv Robert Cushing, Chief, Public Utilities Division Illinois Attorney General's Office 100 W. Randolph Street Chicago, IL 60601 REQUEST FOR ADDITIONAL INFORMATION LASALLE COUNTY STATION, UNITS 1 AND 2 DOCKET NOS. 50-373 AND 50-374 In reviewing the Exelon Generation Company's (Exelon's) submittal dated July 25, 2008, related to your request for a license amendment to revise Local Power Range Monitor (LPRM) calibration frequency, for the LaSalle County Station (LSCS), Units 1 and 2, the NRC staff has determined that the following information is needed in order to complete its review: Provide the plant specific LPRM uncertainty analysis to demonstrate that the LPRM response uncertainty value used in the Minimum Critical Power Ratio (MCPR) safety limit analysis would remain bounding if the LPRM calibration interval were extended from 1000 Effective Full Power Hours (EFPH) to 2000 EFPH. This analysis should account for 25 percent extension (i.e., 2500 EFPH) allowed by SR 3.0.2. 1.1. Include a description of the method and assumptions used for this analysis.
| | By letter to the Nuclear Regulatory Commission (NRC) dated July 25, 2008, Exelon Generation Company, LLC submitted a request to revise Technical Specification (TS) 3.3.1.1, "Reactor Protection System (RPS) Instrumentation," Surveillance Requirement (SR) 3.3.1.1.8 and TS 3.3.1.3, "Oscillation Power Range Monitor (OPRM) Instrumentation," SR 3.3.1.3.2 to increase the frequency interval between local power range monitor calibrations from 1000 effective full power hours (EFPH) to 2000 EFPH, for the LaSalle County Station, Units 1 and 2. |
| | The NRC staff has accepted your license amendment request for review and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. During a discussion with your staff on September 10, 2008, it was agreed that you would provide a response 30 days from the date of this letter. |
| | The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources. 'If circumstances result in the need to revise the requested response date, please contact me at (301) 415-3154. |
| | Sincerely, |
| | *~&tiu:.~/~ *:~Nt.v Steph~n P. san~s, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-373 and 50-374 |
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| ===1.2. Include=== | | ==Enclosure:== |
| the derivation of the values of the standard deviations summarized in Attachment 5 and provide an example of a calculation.
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| This example should include the applicable LPRM calibration data and the associated data deduction that are used to calculate the exposure uncertainty for a LPRM. 1.3. Explain how the LPRIVI decay factor was obtained and provide an example calculation to show the result of the calculated decay factor from the exposure data for one LPRM. Also, provide information to demonstrate that the value specified in the attachments is adequate for determining the LPRM uncertainties.
| | Request for Additional Information cc w/encl: See next page |
| | |
| | LaSalle County Station, Units 1 and 2 cc: |
| | Distribution via Listserv Robert Cushing, Chief, Public Utilities Division Illinois Attorney General's Office 100 W. Randolph Street Chicago, IL 60601 |
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| ===1.4. Explain===
| | REQUEST FOR ADDITIONAL INFORMATION LASALLE COUNTY STATION, UNITS 1 AND 2 DOCKET NOS. 50-373 AND 50-374 In reviewing the Exelon Generation Company's (Exelon's) submittal dated July 25, 2008, related to your request for a license amendment to revise Local Power Range Monitor (LPRM) calibration frequency, for the LaSalle County Station (LSCS), Units 1 and 2, the NRC staff has determined that the following information is needed in order to complete its review: |
| how the accumulated exposure values were obtained. | | : 1. Provide the plant specific LPRM uncertainty analysis to demonstrate that the LPRM response uncertainty value used in the Minimum Critical Power Ratio (MCPR) safety limit analysis would remain bounding if the LPRM calibration interval were extended from 1000 Effective Full Power Hours (EFPH) to 2000 EFPH. This analysis should account for 25 percent extension (i.e., 2500 EFPH) allowed by SR 3.0.2. |
| 1.5. The analysis summarized in Attachment 5 evaluates the increase in LPRM response uncertainty when accounting for the TS SR 3.0.2 allowed 25 percent extension of the calibration interval (i.e., 2500 EFPH), however the upper bound calibration interval used was of 2500 MWD/MT. This value equates to 2336 EFPH. When comparing the results shown in Attachment 4 to those in Attachment 5, it was noted that the difference between them increases as the exposure interval increases. | | 1.1. Include a description of the method and assumptions used for this analysis. |
| Based on the information provided, the NRC staff does not have confidence that if the analysis was performed for 2500 EFPH instead of 2336 EFPH, the increase of standard deviation not would be significantly higher than stated in Attachment | | 1.2. Include the derivation of the values of the standard deviations summarized in Attachment 5 and provide an example of a calculation. This example should include the applicable LPRM calibration data and the associated data deduction that are used to calculate the exposure uncertainty for a LPRM. |
| : 5. Thus, the uncertainty value assumed in the MCPR analysis could be exceeded.
| | 1.3. Explain how the LPRIVI decay factor was obtained and provide an example calculation to show the result of the calculated decay factor from the exposure data for one LPRM. |
| Provide an analysis that confirms that the change in LPRM calibration "frequency continues to allow the 25 percent extension. Provide a description of the method used to collect the data used by the analyses referenced in Attachments 4 and 5. | | Also, provide information to demonstrate that the value specified in the attachments is adequate for determining the LPRM uncertainties. |
| | 1.4. Explain how the accumulated exposure values were obtained. |
| | 1.5. The analysis summarized in Attachment 5 evaluates the increase in LPRM response uncertainty when accounting for the TS SR 3.0.2 allowed 25 percent extension of the calibration interval (i.e., 2500 EFPH), however the upper bound calibration interval used was of 2500 MWD/MT. This value equates to 2336 EFPH. When comparing the results shown in Attachment 4 to those in Attachment 5, it was noted that the difference between them increases as the exposure interval increases. Based on the information provided, the NRC staff does not have confidence that if the analysis was performed for 2500 EFPH instead of 2336 EFPH, the increase of standard deviation not would be significantly higher than stated in Attachment 5. Thus, the uncertainty value assumed in the MCPR analysis could be exceeded. Provide an analysis that confirms that the change in LPRM calibration "frequency continues to allow the 25 percent extension. |
| | : 2. Provide a description of the method used to collect the data used by the analyses referenced in Attachments 4 and 5. |
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| ===2.1. Include===
| | -2 2.1. Include the nature of the data points used by Attachment 5 for each interval and the reason of why the range selection of +/-500 MWD/MT is conservative and acceptable. |
| the nature of the data points used by Attachment 5 for each interval and the reason of why the range selection of +/-500 MWD/MT is conservative and acceptable. | | 2.2. Explain the criteria for double counting the collected data used and how the double counting of data contributed to the total uncertainty. |
| | 2.3. The third paragraph on page 6 of Attachment 1 indicates that the calculation data between 2000 MWD/MT and 2500 MWD/MT were used to calculate the standard deviations for both 2000 MW D/MT and 2500 MW D/MT calibration intervals. Provide an analysis to quantify the effect of the use of overlapping data range on the calculated standard deviations for the 2000 MWD/MT and 2500 MWD/MT calibration intervals. |
| | : 3. The first paragraph on page 5 of Attachment 1 states that "LSCS currently uses an improved POWERPLEX - III core monitoring system and newer design LPRM chambers that exhibit more consistent sensitivity behavior than the older LPRM detectors." Provide a comparison of the LPRM exposure uncertainties based on appropriate core monitoring systems (CMS) and LPRM calibration data to show that the newer CMS and LPRM detectors provides more accurate power indications than that based on the older CMS and LPRM detectors. |
| | : 4. Address the newer design of LPRM chambers in more detail? How was the plant exposure data collected from 1996 through 2006 applied to the new LPRM chambers? |
| | : 5. The last paragraph on page 4 of Attachment 1 states that the current frequency interval is based, in part, on operating experience with previous core monitoring systems and that LSCS currently uses an improved POWERPLEX - III core monitoring system. The NRC staff found several records that document LSCS issues regarding POWERPLEX - II from 1999 to 2002. Specifically, the issues are: POWERPLEX - II use of non-conservative steam tables for core monitoring; an error in one input into POWERPLEX - II calculation resulting in exceeding the authorized thermal power; feedwater flow input problems; and Unit 2 use of a revised POWERPLEX - II deck which did not contain all the gamma TIP data constants necessary to monitor core thermal limits to the correct accuracy. How does the LSCS transition to POWERPLEX -III assure that errors of this nature are not repeated? |
| | : 6. Provide a discussion to confirm that the OPRM and RBM systems will not be adversely affected by the requested extension of calibration frequency with respect to the LPRM input to these systems. |
| | : 7. Demonstrate that there is no reduction in opportunity to detect the failure of the LPRM by the requested extension of calibration frequency. If there is a reduction in opportunity to detect the failure of the LPRM, demonstrate that the increased risk is small and acceptable. |
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| ===2.2. Explain===
| | October 1, 2008 Mr. Charles G. Pardee Chie"f Nuclear Officer and Senior Vice President Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 SUB-JECT: LASALLE COUNTY STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMEI\IDMENT REQUEST TO REVISE LOCAL POWER RANGE MONITOR CALIBRATION FREQUENCY (TAC NOS. |
| the criteria for double counting the collected data used and how the double counting of data contributed to the total uncertainty.
| | MD9414 AI\lD MD9415) |
| 2.3. The third paragraph on page 6 of Attachment 1 indicates that the calculation data between 2000 MWD/MT and 2500 MWD/MT were used to calculate the standard deviations for both 2000 MW D/MT and 2500 MW D/MT calibration intervals.
| |
| Provide an analysis to quantify the effect of the use of overlapping data range on the calculated standard deviations for the 2000 MWD/MT and 2500 MWD/MT calibration intervals. The first paragraph on page 5 of Attachment 1 states that "LSCS currently uses an improved POWERPLEX
| |
| -III core monitoring system and newer design LPRM chambers that exhibit more consistent sensitivity behavior than the older LPRM detectors." Provide a comparison of the LPRM exposure uncertainties based on appropriate core monitoring systems (CMS) and LPRM calibration data to show that the newer CMS and LPRM detectors provides more accurate power indications than that based on the older CMS and LPRM detectors. Address the newer design of LPRM chambers in more detail? How was the plant exposure data collected from 1996 through 2006 applied to the new LPRM chambers? The last paragraph on page 4 of Attachment 1 states that the current frequency interval is based, in part, on operating experience with previous core monitoring systems and that LSCS currently uses an improved POWERPLEX
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| -III core monitoring system. The NRC staff found several records that document LSCS issues regarding POWERPLEX
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| -II from 1999 to 2002. Specifically, the issues are: POWERPLEX
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| -II use of non-conservative steam tables for core monitoring; an error in one input into POWERPLEX
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| -II calculation resulting in exceeding the authorized thermal power; feedwater flow input problems; and Unit 2 use of a revised POWERPLEX
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| -II deck which did not contain all the gamma TIP data constants necessary to monitor core thermal limits to the correct accuracy.
| |
| How does the LSCS transition to POWERPLEX -III assure that errors of this nature are not repeated? Provide a discussion to confirm that the OPRM and RBM systems will not be adversely affected by the requested extension of calibration frequency with respect to the LPRM input to these systems. Demonstrate that there is no reduction in opportunity to detect the failure of the LPRM by the requested extension of calibration frequency.
| |
| If there is a reduction in opportunity to detect the failure of the LPRM, demonstrate that the increased risk is small and acceptable.
| |
| October 1, 2008 Mr. Charles G. Pardee Chie"f Nuclear Officer and Senior Vice President Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 LASALLE COUNTY STATION, UNITS 1 AND 2 -REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMEI\IDMENT REQUEST TO REVISE LOCAL POWER RANGE MONITOR CALIBRATION FREQUENCY (TAC NOS. MD9414 AI\lD MD9415) | |
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| ==Dear Mr. Pardee:== | | ==Dear Mr. Pardee:== |
| By letter to the Nuclear Regulatory Commission (NRC) dated July 25,2008, Exelon Generation Company, LLC submitted a request to revise Technical Specification (TS) 3.3.1.1, "Reactor Protection System (RPS) Instrumentation," Surveillance Requirement (SR) 3.3.1.1.8 and TS 3.3.1.3, "Oscillation Power Range Monitor (OPRM) Instrumentation," SR 3.3.1.3.2 to increase the frequency interval between local power range monitor calibrations from 1000 effective full power hours (EFPH) to 2000 EFPH, for the LaSalle County Station, Units 1 and 2. The NRC staff has accepted your license amendment request for review and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. During a discussion with your staff on September 10, 2008, it was agreed that you would provide a response 30 days "from the date of this letter. The !\IRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources. | | |
| If circumstances result in the need to revise the requested response date, please contact me at (301) 415-3154. | | By letter to the Nuclear Regulatory Commission (NRC) dated July 25,2008, Exelon Generation Company, LLC submitted a request to revise Technical Specification (TS) 3.3.1.1, "Reactor Protection System (RPS) Instrumentation," Surveillance Requirement (SR) 3.3.1.1.8 and TS 3.3.1.3, "Oscillation Power Range Monitor (OPRM) Instrumentation," SR 3.3.1.3.2 to increase the frequency interval between local power range monitor calibrations from 1000 effective full power hours (EFPH) to 2000 EFPH, for the LaSalle County Station, Units 1 and 2. |
| Sincerely, IRAI Stephen P. Sands, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-373 and 50-374 | | The NRC staff has accepted your license amendment request for review and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. During a discussion with your staff on September 10, 2008, it was agreed that you would provide a response 30 days "from the date of this letter. |
| | The !\IRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-3154. |
| | Sincerely, IRAI Stephen P. Sands, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-373 and 50-374 |
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| ==Enclosure:== | | ==Enclosure:== |
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| Request for Additional Information cc w/encl: See next page DISTRIBUTION: | | Request for Additional Information cc w/encl: See next page DISTRIBUTION: |
| PUBLIC LPL3-2 R/F RidsNrrDorlLpl3-2 RidsNrrBCGCranston RidsNrrPMLaSalie RidsNrrLAEW hitt RidsAcrsAcnw&mMailCenter RidsOgcRp RidsRgn3MailCenter RidsNrrDorlDpr ADAMS Accession Number: ML082540198 OFFICE NAME DATE LPL3-2/PM 09 108 LPL3-2/LA . SRXB/BC GCranslon (SMiranda for) 09 119108 LPL3-2/BC OFFICIAL RECORD COpy}} | | PUBLIC LPL3-2 R/F RidsNrrDorlLpl3-2 RidsNrrBCGCranston RidsNrrPMLaSalie RidsNrrLAEW hitt RidsAcrsAcnw&mMailCenter RidsOgcRp RidsRgn3MailCenter RidsNrrDorlDpr ADAMS Accession Number: ML082540198 OFFICE LPL3-2/PM LPL3-2/LA . ~ SRXB/BC LPL3-2/BC GCranslon NAME SSands~0 (SMiranda for) |
| | DATE 09 I~ 108 09 119108 OFFICIAL RECORD COpy}} |
Letter Sequence RAI |
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MONTHYEARRS-08-091, Request for a License Amendment to Revise Local Power Range Monitor Calibration Frequency2008-07-25025 July 2008
Request for a License Amendment to Revise Local Power Range Monitor Calibration Frequency
Project stage: Request
ML0824603762008-09-17017 September 2008
Request for Withholding Information from Public Disclosure for LaSalle County Station, Unit Nos. 1 and 2
Project stage: Withholding Request Acceptance
ML0825401982008-10-0101 October 2008
Request for Additional Information, License Amendment Request to Revise Local Power Range Monitor Calibration Frequency
Project stage: RAI
ML0901500142009-01-15015 January 2009
County 1 and LaSalle County 2 -Follow-up RAIs Regarding LPRM LAR (MD9414 and MD9415)
Project stage: RAI
RS-09-026, Additional Information Supporting the Request for a License Amendment to Revise Local Power Range Monitor Calibration Frequency2009-02-17017 February 2009
Additional Information Supporting the Request for a License Amendment to Revise Local Power Range Monitor Calibration Frequency
Project stage: Request
RS-09-063, Additional Information Supporting the Request for a License Amendment to Revise Local Power Range Monitor Calibration Frequency2009-05-0808 May 2009
Additional Information Supporting the Request for a License Amendment to Revise Local Power Range Monitor Calibration Frequency
Project stage: Request
ML0913301312009-05-13013 May 2009
Additional RAIs to Support LaSalle LAR to Revise LPRM Calibration Frequency (MD9415, MD9415)
Project stage: RAI
RS-09-100, Additional Information Supporting the Request for a License Amendment to Revise Local Power Range Monitor Calibration Frequency2009-07-27027 July 2009
Additional Information Supporting the Request for a License Amendment to Revise Local Power Range Monitor Calibration Frequency
Project stage: Request
ML0924407552009-09-16016 September 2009
License Amendment, the Amendments Revise Technical Specification (TS) 3.3.1.1, Reactor Protection System (RPS) Instrumentation, Surveillance Requirement (SR) 3.3.1.1.8 and TS 3.3.1.3, Oscillation Power Range Monitor (Oprm)...
Project stage: Other
ML0927202312009-10-0202 October 2009
Correction Letter for License Amendment Nos. 195 and 182, Revise Local Power Range Monitor Calibration Frequency
Project stage: Other
2009-10-02
[Table View] |
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Category:Letter
MONTHYEARIR 05000373/20243012024-10-31031 October 2024
Initial License Examination Report 05000373/2024301 05000374/2024301
IR 05000373/20244042024-10-23023 October 2024
County Station – Security Baseline Inspection Report 05000373/2024404 and 05000374/2024404
RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024
Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests
05000373/LER-2023-001-01, Air Circuit Breaker (Acb) Mechanically Operated Contacts (MOC) Switch Failed to Actuate2024-10-0909 October 2024
Air Circuit Breaker (Acb) Mechanically Operated Contacts (MOC) Switch Failed to Actuate
ML24275A2442024-10-0303 October 2024
Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing
IR 05000373/20244012024-09-27027 September 2024
County Station – Security Baseline Inspection Report 05000373/2024401 and 05000374/2024401
ML24263A2062024-09-19019 September 2024
Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 for LaSalle County Station - Holtec MPC-68MCBS
ML24260A0492024-09-16016 September 2024
Operator Licensing Examination Approval - Lasalle County Station, Unit 1 and 2, September 2024
RS-24-090, Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-09-12012 September 2024
Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds
ML24255A8642024-09-0606 September 2024
Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification
ML24249A1362024-09-0404 September 2024
EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21
IR 05000373/20240052024-08-29029 August 2024
Updated Inspection Plan and Assessment Follow-Up Letter for Lasalle County Station (Report 05000373/2024005; 05000374/2024005)
IR 05000373/20244022024-08-28028 August 2024
County Station - Cyber Security Inspection Report 05000373/2024402 and 05000374/2024402
ML24239A3972024-08-23023 August 2024
Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243
05000373/LER-2024-004-01, Emergency Diesel Generator Auto-Start and Load Due to Loss of System Auxiliary Transformer2024-08-22022 August 2024
Emergency Diesel Generator Auto-Start and Load Due to Loss of System Auxiliary Transformer
IR 05000373/20240022024-08-13013 August 2024
County Station - Integrated Inspection Report 05000373/2024002 and 05000374/2024002
ML24222A6772024-08-0909 August 2024
Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition
IR 05000373/20244202024-08-0505 August 2024
County Station - Security Baseline Inspection Report 05000373 2024420 and 05000374 2024420
05000373/LER-2024-003-01, Supplement to Technical Specification (TS) Limiting Condition for Operation (LCO) 3.6.1.3 Completion Time Exceeded2024-07-31031 July 2024
Supplement to Technical Specification (TS) Limiting Condition for Operation (LCO) 3.6.1.3 Completion Time Exceeded
ML24208A0962024-07-25025 July 2024
57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification
RS-24-064, Nuclear Radiological Emergency Plan Document Revisions2024-06-28028 June 2024
Nuclear Radiological Emergency Plan Document Revisions
ML24178A2522024-06-27027 June 2024
County Station – Acknowledgement of Response to NRC Inspection Report 05000373/2024001 and 05000374/2024001 and Disputed Non-Cited Violation
05000373/LER-2024-004, Emergency Diesel Generator Auto-Start and Load Due to Loss of Station Auxiliary Transformer2024-06-19019 June 2024
Emergency Diesel Generator Auto-Start and Load Due to Loss of Station Auxiliary Transformer
RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024
Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations
05000373/LER-2024-003, Technical Specification (TS) Limiting Condition for Operation (LCO) 3.6.1.3 Completion Time Exceeded2024-06-0606 June 2024
Technical Specification (TS) Limiting Condition for Operation (LCO) 3.6.1.3 Completion Time Exceeded
IR 05000373/20240102024-05-29029 May 2024
County Station - Commercial Grade Dedication Inspection Report 05000373/2024010 and 05000374/2024010
ML24079A0762024-05-23023 May 2024
Issuance of Amendments to Adopt TSTF 264
ML24142A3352024-05-21021 May 2024
Quad Cities—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes
05000373/LER-2024-002, Reactor Protection System Half Scram Due to Motor Generator Set Electric Power Monitoring Assembly Output Breaker Trip2024-05-17017 May 2024
Reactor Protection System Half Scram Due to Motor Generator Set Electric Power Monitoring Assembly Output Breaker Trip
RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024
2023 Corporate Regulatory Commitment Change Summary Report
ML24131A1512024-05-13013 May 2024
County Station - Integrated Report 05000373/2024001 and 05000374/2024001
IR 05000373/20240012024-05-13013 May 2024
County Station - Integrated Report 05000373/2024001 and 05000374/2024001
RS-24-038, Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-05-0202 May 2024
Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds
RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024
Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests
05000373/LER-2024-001, Core Operating Limits Report Thermal Limits Exceeded2024-04-26026 April 2024
Core Operating Limits Report Thermal Limits Exceeded
ML24108A1562024-04-15015 April 2024
Updated Final Safety Analysis Report (Ufsar), Revision 26 and Fire Protection Report (Fpr), Revision 11
ML24103A2042024-04-12012 April 2024
Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition
RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024
Constellation Energy Generation, LLC - Annual Property Insurance Status Report
ML24071A2122024-03-12012 March 2024
County Station - Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection
IR 05000373/20230062024-02-28028 February 2024
Annual Assessment Letter for Lasalle County Station, Units 1 and 2 (Report 05000373/2023006; 05000374/2023006)
RS-24-014, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2024-02-22022 February 2024
Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors
ML24018A0682024-02-0909 February 2024
Issuance of Amendment Nos. 262 and 247 Revised Design Bases of Lower Downcomer Braces
IR 05000373/20230042024-01-24024 January 2024
County Station - Integrated Inspection Report 05000373/2023004 and 05000374/2023004
ML24024A1332024-01-24024 January 2024
Confirmation of Initial License Examination
IR 05000373/20230122024-01-18018 January 2024
County Station - Biennial Problem Identification and Resolution Inspection Report 05000373/2023012 and 05000374/2023012
ML23354A2902024-01-0505 January 2024
Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0028 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting))
ML23360A6082023-12-27027 December 2023
County Station Request for Information for NRC Commercial Grade Dedication Inspection: Inspection Report 05000373/2024010 and 05000374/2024010
ML23278A1292023-12-14014 December 2023
Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines
ML23305A1402023-12-13013 December 2023
Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580
05000373/LER-2023-002, Turbine Stop Valve Limit Switch Failure Due to Lubricant Degradation2023-12-0404 December 2023
Turbine Stop Valve Limit Switch Failure Due to Lubricant Degradation
2024-09-06
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML24197A0162024-07-12012 July 2024
NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC - Fleet Request - License Amendment Request to Adopt TSTF-591
ML24142A3352024-05-21021 May 2024
Quad Cities—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes
ML23360A6082023-12-27027 December 2023
County Station Request for Information for NRC Commercial Grade Dedication Inspection: Inspection Report 05000373/2024010 and 05000374/2024010
ML23264A7992023-09-21021 September 2023
NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC – Fleet Request – License Amendment Request to Adopt TSTF-580, Revision 1
ML23264A1512023-09-21021 September 2023
Notification of Upcoming Biennial Problem Identification and Resolution Inspection LaSalle and RFI
ML23208A3182023-07-27027 July 2023
Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and RFI
ML23153A1562023-06-0202 June 2023
NRR E-mail Capture - RAI LaSalle pressure-temperature Limits Report (PTLR) Amendment Request
ML23150A2482023-05-25025 May 2023
NRR E-mail Capture - RAI Re LaSalle Downcomer Analysis Amendment Request
ML23110A3202023-04-21021 April 2023
Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection
ML22361A0792022-12-27027 December 2022
Notification of NRC Baseline Inspection and Request for Information (05000374/2023001)
ML22256A0112022-09-12012 September 2022
NRR E-mail Capture - Request for Additional Information LaSalle County Station, Units 1 and 2 and Quad Cities Nuclear Power Station, Units 1 and 2 License Amendments Related to Fuel Storage
ML22138A4112022-05-18018 May 2022
NRR E-mail Capture - Lasalle 1 and 2 - (RAI) License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies, with Changes to TS Sections 4.3.1 and 5.6.5 (EPID-L-2021-LLA-0124)
ML22126A0392022-05-0606 May 2022
NRR E-mail Capture - Lasalle 1 and 2 Draft (RAI) License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies, with Proposed Changes to TS Sections 4.3.1 and 5.6.5
IR 05000373/20224032022-04-0707 April 2022
County Station Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000373/2022403 and 05000374/2022403
ML22062B0232022-03-0303 March 2022
NRR E-mail Capture - EPID-L-2022-LLR-0028, LaSalle Unit 1, Request for Additional Information (Rai), LaSalle Unit 1, Relief Request I4R-13 Relief from Code Examinations for 1B33-F060A and 1B33-F060B Repairs
ML22041B5362022-02-10010 February 2022
NRR E-mail Capture - Constellation Energy Generation, LLC - Request for Additional Information Regarding Fleet License Amendment Request to Adopt TSTF-541
ML22020A0642022-01-13013 January 2022
NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative for Repair of Water Level Instrumentation Partial Penetration Nozzles
ML21292A1782021-10-19019 October 2021
Information Request for a NRC Post-Approval Site Inspection for License Renewal 05000373/2022010
ML21256A1902021-09-10010 September 2021
NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application
ML21207A0072021-07-26026 July 2021
NRR E-mail Capture - La Salle Units 1 and 2 - Request for Additional Information (RAI) License Amendment Request to Incorporate Licensing Topical Report NEDE-33885P-A, Revision 1, GNF CRDA Application Methodology(EPID-L-2021-LLA-0016)
ML21190A0192021-07-0808 July 2021
NRR E-mail Capture - Exelon Fleet - Request for Additional Information Regarding Adoption of TSTF-582 and TSTF-583-T
ML21187A2972021-07-0707 July 2021
Information Request for an NRC Triennial 10 CFR 50.59 (Evaluation of Changes, Tests, and Experiments) Baseline Inspection
ML21144A2132021-05-24024 May 2021
NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application
ML21117A0342021-05-0505 May 2021
Request for Additional Information Regarding Proposed Alternative to Use ASME Code Case N-893
ML21119A2282021-04-29029 April 2021
NRR E-mail Capture - Request for Additional Information (RAI) - LaSalle, EPID-L-2020-LLA-0018, License Amendment Request (LAR) TSTF-505
ML21077A1902021-03-18018 March 2021
NRR E-mail Capture - Lasalle Units 1 and 2 - Request for Additional Information (RAI) Request for License Amendment Regarding Ultimate Heat Sink, (EPID-L-2020-LLA-0165)
ML21068A2762021-03-0909 March 2021
NRR E-mail Capture - La Salle Units 1 and 2 - Request for Additional Information (RAI) Relief Request I4R-12 Relief from Code Surface Examinations for 2B33-F060B Valve Repair (EPID-L-2020-LLA-0016)
ML21067A6752021-03-0808 March 2021
NRR E-mail Capture - La Salle Units 1 and 2 - Request for Additional Information (RAI) UHS Amendment Request (EPID-L-2020-LLA-0165)
ML21060B4352021-03-0101 March 2021
NRR E-mail Capture - Second Round - Request for Additional Information (Rais) EPID-L-2020-LLA-0018, LaSalle License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 2
ML21062A0652021-03-0101 March 2021
NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative to Documentation Requirements for Pressure Retaining Bolting
ML21053A0252021-02-20020 February 2021
NRR E-mail Capture - Request for Additional Information (Rais) - LaSalle Request for Exemption from Pre-Access Drug and Alcohol Testing
ML21049A2572021-02-18018 February 2021
Request for Additional Information Byron/Dresden Proposed Changes to Site Emergency Plans to Support Post-Shutdown and Permanently Defueled Conditions (EPID-2020-LLA-0240 & EPID-2020-LLA-0237)
ML21048A0432021-02-16016 February 2021
County Station - Notification of NRC Design Bases Assurance Inspection (Programs) and Initial Request for Information - Inspection Report 05000373/2021011 and 05000374/2021011
ML20364A2452020-12-29029 December 2020
Notification of an NRC Triennial Heat Sink Performance Inspection and Request for Information; Inspection Report 05000373/2021002; 05000374/2021002
ML20346A1042020-12-11011 December 2020
NRR E-mail Capture - LaSalle County Station, Units 1 and 2 - Request for Additional Information Regarding the License Amendment Request to Adopt 10 CFR 50.69
ML20330A1892020-11-25025 November 2020
Request for Information for an NRC Post-Approval Site Inspection for License Renewal; Inspection Report 05000374/2021010
ML20321A0852020-11-16016 November 2020
Notification of NRC Baseline Inspection and Request for Information (05000374/2021001)
ML20247J4082020-09-29029 September 2020
Apla Request for Additional Information LAR 50.69 and TSTF-505 (Epids L-2020-LLA-0017) and
ML20253A3422020-09-17017 September 2020
Correction to Request for Additional Information Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors (EPID-2020-LLA-0017)
ML20253A2272020-09-16016 September 2020
Correction to Request for Additional Information Application to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b
ML20240A2182020-09-0303 September 2020
Request for Additional Information Regarding Amendment Request for Amendments to Renewed Facility Operating Licenses to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Co
ML20239A7262020-08-27027 August 2020
Supplemental Information Needed for Acceptance of Requested Licensing Action Regarding Request for a License Amendment to Technical Specification 3.7.3, Ultimate Heat Sink
ML20239A7982020-08-25025 August 2020
NRR E-mail Capture - Exelon Generation Company, LLC - Fleet License Amendment Request to Adopt TSTF-568, Revision 2
ML19275H1362019-10-0202 October 2019
NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Request to Use ASME Code Case N-879
ML19179A0612019-07-19019 July 2019
Three Mile Point 1 - Supplemental Information Needed to Proposed Alternative to Use ASME Code Case N-879
ML19120A2302019-04-29029 April 2019
Ltr. 04/29/19 LaSalle County Station, Units 1 and 2 - Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team); Inspection Report 05000373/2019012; 05000374/2019012 (DRS-M.Jones)
ML19087A2682019-03-28028 March 2019
NRR E-mail Capture - Request for Additional Information (RAI) - LaSalle 1 and 2, EPID-L-2018-LLA-0162, LAR Removal of Operating Mode Restrictions for Performing Surveillance Testing of the Div 3 Battery and HPCS DG
ML19065A0902019-03-0505 March 2019
NRR E-mail Capture - LaSalle 1 and 2, EPID-L-2018-LLR-0162, LAR Removal of Operating Mode Restrictions for Performing Surveillance Testing of the Div 3 Battery and HPCS DG, Additional Draft Request for Additional Information (RAI)
ML19058A2392019-02-27027 February 2019
Information Request to Support Upcoming Problem Identification and Resolution Inspection at LaSalle County Station, Units 1 and 2
ML19036A6562019-02-0505 February 2019
NRR E-mail Capture - LaSalle 1 and 2, EPID-L-2018-LLR-0123, Relief Request I3R-15, Third Inservice Inspection Interval, Request for Additional Information (RAI)
2024-07-12
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 1, 2008 Mr. Charles G. Pardee Chief Nuclear Officer and Senior Vice President Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 SUB.JECT: LASALLE COUNTY STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST TO REVISE LOCAL POWER RANGE MONITOR CALIBRATION FREQUENCY (TAC NOS.
MD9414 AI\ID MD9415)
Dear Mr. Pardee:
By letter to the Nuclear Regulatory Commission (NRC) dated July 25, 2008, Exelon Generation Company, LLC submitted a request to revise Technical Specification (TS) 3.3.1.1, "Reactor Protection System (RPS) Instrumentation," Surveillance Requirement (SR) 3.3.1.1.8 and TS 3.3.1.3, "Oscillation Power Range Monitor (OPRM) Instrumentation," SR 3.3.1.3.2 to increase the frequency interval between local power range monitor calibrations from 1000 effective full power hours (EFPH) to 2000 EFPH, for the LaSalle County Station, Units 1 and 2.
The NRC staff has accepted your license amendment request for review and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. During a discussion with your staff on September 10, 2008, it was agreed that you would provide a response 30 days from the date of this letter.
The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources. 'If circumstances result in the need to revise the requested response date, please contact me at (301) 415-3154.
Sincerely,
- ~&tiu:.~/~ *:~Nt.v Steph~n P. san~s, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-373 and 50-374
Enclosure:
Request for Additional Information cc w/encl: See next page
LaSalle County Station, Units 1 and 2 cc:
Distribution via Listserv Robert Cushing, Chief, Public Utilities Division Illinois Attorney General's Office 100 W. Randolph Street Chicago, IL 60601
REQUEST FOR ADDITIONAL INFORMATION LASALLE COUNTY STATION, UNITS 1 AND 2 DOCKET NOS. 50-373 AND 50-374 In reviewing the Exelon Generation Company's (Exelon's) submittal dated July 25, 2008, related to your request for a license amendment to revise Local Power Range Monitor (LPRM) calibration frequency, for the LaSalle County Station (LSCS), Units 1 and 2, the NRC staff has determined that the following information is needed in order to complete its review:
- 1. Provide the plant specific LPRM uncertainty analysis to demonstrate that the LPRM response uncertainty value used in the Minimum Critical Power Ratio (MCPR) safety limit analysis would remain bounding if the LPRM calibration interval were extended from 1000 Effective Full Power Hours (EFPH) to 2000 EFPH. This analysis should account for 25 percent extension (i.e., 2500 EFPH) allowed by SR 3.0.2.
1.1. Include a description of the method and assumptions used for this analysis.
1.2. Include the derivation of the values of the standard deviations summarized in Attachment 5 and provide an example of a calculation. This example should include the applicable LPRM calibration data and the associated data deduction that are used to calculate the exposure uncertainty for a LPRM.
1.3. Explain how the LPRIVI decay factor was obtained and provide an example calculation to show the result of the calculated decay factor from the exposure data for one LPRM.
Also, provide information to demonstrate that the value specified in the attachments is adequate for determining the LPRM uncertainties.
1.4. Explain how the accumulated exposure values were obtained.
1.5. The analysis summarized in Attachment 5 evaluates the increase in LPRM response uncertainty when accounting for the TS SR 3.0.2 allowed 25 percent extension of the calibration interval (i.e., 2500 EFPH), however the upper bound calibration interval used was of 2500 MWD/MT. This value equates to 2336 EFPH. When comparing the results shown in Attachment 4 to those in Attachment 5, it was noted that the difference between them increases as the exposure interval increases. Based on the information provided, the NRC staff does not have confidence that if the analysis was performed for 2500 EFPH instead of 2336 EFPH, the increase of standard deviation not would be significantly higher than stated in Attachment 5. Thus, the uncertainty value assumed in the MCPR analysis could be exceeded. Provide an analysis that confirms that the change in LPRM calibration "frequency continues to allow the 25 percent extension.
- 2. Provide a description of the method used to collect the data used by the analyses referenced in Attachments 4 and 5.
-2 2.1. Include the nature of the data points used by Attachment 5 for each interval and the reason of why the range selection of +/-500 MWD/MT is conservative and acceptable.
2.2. Explain the criteria for double counting the collected data used and how the double counting of data contributed to the total uncertainty.
2.3. The third paragraph on page 6 of Attachment 1 indicates that the calculation data between 2000 MWD/MT and 2500 MWD/MT were used to calculate the standard deviations for both 2000 MW D/MT and 2500 MW D/MT calibration intervals. Provide an analysis to quantify the effect of the use of overlapping data range on the calculated standard deviations for the 2000 MWD/MT and 2500 MWD/MT calibration intervals.
- 3. The first paragraph on page 5 of Attachment 1 states that "LSCS currently uses an improved POWERPLEX - III core monitoring system and newer design LPRM chambers that exhibit more consistent sensitivity behavior than the older LPRM detectors." Provide a comparison of the LPRM exposure uncertainties based on appropriate core monitoring systems (CMS) and LPRM calibration data to show that the newer CMS and LPRM detectors provides more accurate power indications than that based on the older CMS and LPRM detectors.
- 4. Address the newer design of LPRM chambers in more detail? How was the plant exposure data collected from 1996 through 2006 applied to the new LPRM chambers?
- 5. The last paragraph on page 4 of Attachment 1 states that the current frequency interval is based, in part, on operating experience with previous core monitoring systems and that LSCS currently uses an improved POWERPLEX - III core monitoring system. The NRC staff found several records that document LSCS issues regarding POWERPLEX - II from 1999 to 2002. Specifically, the issues are: POWERPLEX - II use of non-conservative steam tables for core monitoring; an error in one input into POWERPLEX - II calculation resulting in exceeding the authorized thermal power; feedwater flow input problems; and Unit 2 use of a revised POWERPLEX - II deck which did not contain all the gamma TIP data constants necessary to monitor core thermal limits to the correct accuracy. How does the LSCS transition to POWERPLEX -III assure that errors of this nature are not repeated?
- 6. Provide a discussion to confirm that the OPRM and RBM systems will not be adversely affected by the requested extension of calibration frequency with respect to the LPRM input to these systems.
- 7. Demonstrate that there is no reduction in opportunity to detect the failure of the LPRM by the requested extension of calibration frequency. If there is a reduction in opportunity to detect the failure of the LPRM, demonstrate that the increased risk is small and acceptable.
October 1, 2008 Mr. Charles G. Pardee Chie"f Nuclear Officer and Senior Vice President Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 SUB-JECT: LASALLE COUNTY STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMEI\IDMENT REQUEST TO REVISE LOCAL POWER RANGE MONITOR CALIBRATION FREQUENCY (TAC NOS.
MD9414 AI\lD MD9415)
Dear Mr. Pardee:
By letter to the Nuclear Regulatory Commission (NRC) dated July 25,2008, Exelon Generation Company, LLC submitted a request to revise Technical Specification (TS) 3.3.1.1, "Reactor Protection System (RPS) Instrumentation," Surveillance Requirement (SR) 3.3.1.1.8 and TS 3.3.1.3, "Oscillation Power Range Monitor (OPRM) Instrumentation," SR 3.3.1.3.2 to increase the frequency interval between local power range monitor calibrations from 1000 effective full power hours (EFPH) to 2000 EFPH, for the LaSalle County Station, Units 1 and 2.
The NRC staff has accepted your license amendment request for review and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. During a discussion with your staff on September 10, 2008, it was agreed that you would provide a response 30 days "from the date of this letter.
The !\IRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-3154.
Sincerely, IRAI Stephen P. Sands, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-373 and 50-374
Enclosure:
Request for Additional Information cc w/encl: See next page DISTRIBUTION:
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DATE 09 I~ 108 09 119108 OFFICIAL RECORD COpy
