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| | number = ML12102A044 | | | number = ML12102A044 |
| | issue date = 05/04/2012 | | | issue date = 05/04/2012 |
| | title = Crystal River Nuclear Generating Plant, Unit 3 - Request for Additional Information for Extended Power Uprate License Amendment Request (TAC No. ME6527) | | | title = Request for Additional Information for Extended Power Uprate License Amendment Request |
| | author name = Lingam S P | | | author name = Lingam S |
| | author affiliation = NRC/NRR/DORL/LPLII-2 | | | author affiliation = NRC/NRR/DORL/LPLII-2 |
| | addressee name = Franke J A | | | addressee name = Franke J |
| | addressee affiliation = Florida Power Corp | | | addressee affiliation = Florida Power Corp |
| | docket = 05000302 | | | docket = 05000302 |
| | license number = DPR-072 | | | license number = DPR-072 |
| | contact person = Lingam S P | | | contact person = Lingam S |
| | case reference number = TAC ME6527 | | | case reference number = TAC ME6527 |
| | 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 May 4, 2012 Mr. Jon A. Franke, Vice Crystal River Nuclear Plant ATTN: Supervisor, Licensing & Regulatory 15760 W. Power Line Crystal River, Florida CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT -REQUEST FOR ADDITIONAL INFORMATION FOR EXTENDED POWER UPRATE LICENSE AMENDMENT REQUEST (TAC NO. ME6527) Dear Mr. Franke: By letter dated June 15, 2011, as supplemented by letters dated July 5, 2011; August 11, 2011 (two letters), August 18 and 25, 2011, October 11 and 25, 2011, December 15, 2011 (two letters), December 21,2011, January 5,2012 (two letters), January 19, 2012 (two letters), January 31, 2012, March 19, 2012, March 22, 2012, and April 4, 2012 (two letters), Florida Power Corporation, dOing business as Progress Energy Florida, Inc., submitted a license amendment request for an extended power uprate to increase thermal power level from 2609 megawatts thermal (MWt) to 3014 MWt for Crystal River Unit 3 Nuclear Generating Plant. The U.S. Nuclear Regulatory Commission staff is reviewing the submittal and has determined that additional information is required to complete its evaluation. This request was discussed with Mr. Dan Westcott of your staff on April 10, 2012, and it was agreed that a response to the enclosed request for additional information would be provided within 45 days from the date of this letter. If you have any questions regarding this matter, I can be reached at 301-415-1564. Sincerely, IRA! Siva P. Lingam, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. Request for Additional cc w/encl: Distribution via REQUEST FOR ADDITIONAL INFORMATION REGARDING EXTENDED POWER UPRATE TO INCREASE THERMAL POWER LEVEL FROM 2609 MEGAWATTS THERMAL TO 3014 MEGAWATTS THERMAL CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT DOCKET NO. 50-302 By letter dated June 15, 2011 {Agencywide Documents Access and Management System {ADAMS} Accession No. ML 112070659}, as supplemented by letters dated July 5,2011, August 11, 2011 {two letters}, August 18 and 25, 2011, October 11 and 25, 2011, December 15, 2011 {two letters}, December 21, 2011, January 5, 2012 (two letters), January 19, 2012 (two letters), January 31,2012, March 19,2012, March 22, 2012, and April 4, 2012 {two letters} {ADAMS Accession Nos. ML 112010674, ML 11228A032, ML11234A051, ML11234A427, ML11242A140, ML112860156, ML113040176, ML11354A232, ML11354A233, ML11361A460, ML12011A035, ML12030A209, ML12024A300, ML12024A301, ML 120330114, ML 12081A293, ML 12086A107, ML 12097A183, and ML 12097A246, respectively}, Florida Power Corporation (the licensee), doing business as Progress Energy Florida, Inc., submitted a license amendment request (LAR) for an extended power uprate (EPU) to increase thermal power level from 2609 megawatts thermal (MWt) to 3014 MWt for Crystal River Unit 3 Nuclear Generating Plant (Crystal River 3 or CR-3). In order to complete its review of the above documents, the Nuclear Regulatory Commission (NRC) staff requests additional information originating from our Accident Dose Branch (AADB) related to atmospheric dispersion part: AAOB Requests for Additional Information Please provide detailed information describing how the CR-3 2003 -2007 meteorological data provided in support of the CR-3 EPU original LAR dated June 15, 2011 (ADAMS Accession No. ML 112070659) were measured and processed, and the criteria used to determine the validity of the data. Describe the temporal sequence of the processing steps to generate the hourly data file and criteria for any data substitutions or modifications. The NRC staff has noted some apparent anomalies in the five-year data file and provide the following examples, which should not be regarded as all inclusive. Therefore, please reevaluate the data file and provide justification that the 2003-2007 data are accurate or provide a supplemental file with revisions to identify any data as invalid for which such a justification cannot be provided. Occurrences of data ending in a multiple of 10 for a number of consecutive hours {e.g., 2003, lower level wind direction for day 55, hour 3 through day 57, hour 17; day 58, hour 0 through hour 23; day 66, hour 11 through day 69 through hour 13}. Enclosure Occurrences of identical reported readings for a number of consecutive hours (e.g., 2004, lower level wind direction for day 85, hour 18, through day 86, hour 11; 2004 upper level wind direction for day 260, hour 15, through hour 21). Identical wind direction values reported at both measurement levels (e.g., 2004, day 250, hour 11, through hour 15; 2005, day 222, hour 3 through day 228, hour 9). Page 2.9.2-3 of Attachment 7 to the original LAR states that the main control room (MCR) atmospheric dispersion factors (XIQ values) were calculated using the Murphy-Campe methodology. The calculation is explained on page 13 of a May 23, 1988 letter (ADAMS Accession No. 8805310306) associated with a prior licensing action request from Florida Power Corporation. These values were approved by the NRC as part of the N UREG-0737, "Clarification of TMI Action Plan Requirements," Item 111.0.3.4 review. The Murphy-Campe paper, "Nuclear Power Plant Control Room Ventilation System Design for Meeting General Criterion 19," advises that use of the equation on page 13 may be appropriate for a diffuse source -point receptor case for those cases when dual intakes are adequately separated and meet certain criteria as described in the Murphy-Campe paper. However, it is unclear to the NRC staff that the appropriate criteria are met for the purpose of the current LAR. Regulatory Guide 1.194, "Atmospheric Relative Concentrations for Control Room Radiological Habitability Assessments at Nuclear Power Plants," states that if the previously approved values are based on a misapplication of a methodology, calculational errors are identified in the values, or changes are deemed necessary to ensure adequate protection of the health and safety of the public, the NRC staff will pursue necessary corrections with the licensee or applicant. Therefore, please provide the following information. Confirm that each MCR intake meets the requirements of an engineered safety feature including, as applicable, single-failure criteria for active components, seismic criteria, and missile criteria. Further, confirm that the design details assure that the most contaminated intake is isolated and the least contaminated intake remains in operation to provide control room pressurization. Given that the Murphy-Campe paper provides several equations, to address several different scenarios, provide justification that all of the possible releases for each design basis accident (DBA), including those associated with loss of offsite power or other single failure, meet the criteria which substantiate that use of the equation on page 13 of the May 23, 1988 letter is appropriate. Provide one or more scaled figures, showing true north, with all possible sources and receptors highlighted from which distance and direction inputs can be approximated, for each DBA. Provide the scale of the figure. In addition, provide the height above grade of each source and receptor. Please include figures that show sources and receptors that consider loss of offsite power or other single failure and control room inleakage. | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 4, 2012 Mr. Jon A. Franke, Vice President Crystal River Nuclear Plant (NA2C) |
| -Regulatory Guide 1.145, "Atmospheric Dispersion Models for Potential Accident Consequence Assessments at Nuclear Power Plants,>> states that the selection of X/a values to be used in exclusion area boundary (EAB) or low population zone boundary (LPZ) evaluations should be the maximum 0.5 percentile direction dependent (e.g., S, SSW, SW, etc.) X/a value or the 5 percent overall site limit X/a value for each time interval, whichever is higher. Please provide a summary table for the CR-3 EAB, and a second table for the LPZ, showing all 0.5 percentile direction dependent sector x/a values and the 5 percentile site limit X/a values. A copy of the EAB and LPZ summary pages from the PAVAN computer code output for CR-3 is acceptable. On these summary pages, highlight each of the EAB and LPZ X/Q values listed in Table 2.9.2-5 of Attachment 7 to the original LAR and provide justification for selection of each of the highlighted values. | | ATTN: Supervisor, Licensing & Regulatory Programs 15760 W. Power Line Street Crystal River, Florida 34428-6708 SUB.JECT: CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT - REQUEST FOR ADDITIONAL INFORMATION FOR EXTENDED POWER UPRATE LICENSE AMENDMENT REQUEST (TAC NO. ME6527) |
| May 4, 2012 Mr. Jon A. Franke, Vice Crystal River Nuclear Plant ATTN: Supervisor, Licensing & Regulatory 15760 W. Power Line Crystal River, Florida SUB..CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT -REQUEST FOR ADDITIONAL INFORMATION FOR EXTENDED POWER UPRATE LICENSE AMENDMENT REQUEST (TAC NO. ME6527) Dear Mr. Franke: By letter dated June 15, 2011, as supplemented by letters dated July 5, 2011; August 11, 2011 (two letters), August 18 and 25, 2011, October 11 and 25, 2011, December 15, 2011 (two letters), December 21,2011, January 5,2012 (two letters), January 19, 2012 (two letters), January 31,2012, March 19,2012, March 22,2012, and April 4, 2012 (two letters), Florida Power Corporation, dOing business as Progress Energy Florida, Inc., submitted a license amendment request for an extended power uprate to increase thermal power level from 2609 megawatts thermal (MWt) to 3014 MWt for Crystal River Unit 3 Nuclear Generating Plant. The U.S. Nuclear Regulatory Commission staff is reviewing the submittal and has determined that additional information is required to complete its evaluation. This request was discussed with Mr. Dan Westcott of your staff on April 10, 2012, and it was agreed that a response to the enclosed request for additional information would be provided within 45 days from the date of this letter. If you have any questions regarding this matter, I can be reached at 301-415-1564. Sincerely, IRA! Siva P. Lingam, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-302 Enclosure: Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION: PUBLIC LPL2-2 R/F RidsNrrDorlLpl2-2 RidsNrrPMCrystalRiver RidsNrrLABTullv RidsOgcRp Center RidsNrrDorlDpr RidsAcrsAcnw MailCTR SLingam, NRR RidsRgn2MailCenter RidsNrrDraAadb LBrown, NRR ADAMS A ccesslon N0: ML *Bsy memo OFFICE LPL2-2/PM LPL2-2/LA AADB/BC* LPL2-21BC LPL2-21PM NAME SLingam BTuliV TIate DBroaddus (EBrown for) SLingam DATE 04/13/12 04113/12 04/6/12 05/04/12 05/04/12 | | |
| }} | | ==Dear Mr. Franke:== |
| | |
| | By letter dated June 15, 2011, as supplemented by letters dated July 5, 2011; August 11, 2011 (two letters), August 18 and 25, 2011, October 11 and 25, 2011, December 15, 2011 (two letters), December 21,2011, January 5,2012 (two letters), January 19, 2012 (two letters), |
| | January 31, 2012, March 19, 2012, March 22, 2012, and April 4, 2012 (two letters), Florida Power Corporation, dOing business as Progress Energy Florida, Inc., submitted a license amendment request for an extended power uprate to increase thermal power level from 2609 megawatts thermal (MWt) to 3014 MWt for Crystal River Unit 3 Nuclear Generating Plant. |
| | The U.S. Nuclear Regulatory Commission staff is reviewing the submittal and has determined that additional information is required to complete its evaluation. This request was discussed with Mr. Dan Westcott of your staff on April 10, 2012, and it was agreed that a response to the enclosed request for additional information would be provided within 45 days from the date of this letter. |
| | If you have any questions regarding this matter, I can be reached at 301-415-1564. |
| | Sincerely, IRA! |
| | Siva P. Lingam, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-302 |
| | |
| | ==Enclosure:== |
| | |
| | Request for Additional Information cc w/encl: Distribution via Listserv |
| | |
| | REQUEST FOR ADDITIONAL INFORMATION REGARDING EXTENDED POWER UPRATE TO INCREASE THERMAL POWER LEVEL FROM 2609 MEGAWATTS THERMAL TO 3014 MEGAWATTS THERMAL CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT DOCKET NO. 50-302 By letter dated June 15, 2011 {Agencywide Documents Access and Management System |
| | {ADAMS} Accession No. ML112070659}, as supplemented by letters dated July 5,2011, August 11, 2011 {two letters}, August 18 and 25, 2011, October 11 and 25, 2011, December 15, 2011 {two letters}, December 21, 2011, January 5, 2012 (two letters), |
| | January 19, 2012 (two letters), January 31,2012, March 19,2012, March 22, 2012, and April 4, 2012 {two letters} {ADAMS Accession Nos. ML112010674, ML11228A032, ML11234A051, ML11234A427, ML11242A140, ML112860156, ML113040176, ML11354A232, ML11354A233, ML11361A460, ML12011A035, ML12030A209, ML12024A300, ML12024A301, ML120330114, ML12081A293, ML12086A107, ML12097A183, and ML12097A246, respectively}, Florida Power Corporation (the licensee), doing business as Progress Energy Florida, Inc., submitted a license amendment request (LAR) for an extended power uprate (EPU) to increase thermal power level from 2609 megawatts thermal (MWt) to 3014 MWt for Crystal River Unit 3 Nuclear Generating Plant (Crystal River 3 or CR-3). In order to complete its review of the above documents, the Nuclear Regulatory Commission (NRC) staff requests additional information originating from our Accident Dose Branch (AADB) related to atmospheric dispersion part: |
| | AAOB Requests for Additional Information |
| | : 1. Please provide detailed information describing how the CR-3 2003 - 2007 meteorological data provided in support of the CR-3 EPU original LAR dated June 15, 2011 (ADAMS Accession No. ML112070659) were measured and processed, and the criteria used to determine the validity of the data. Describe the temporal sequence of the processing steps to generate the hourly data file and criteria for any data substitutions or modifications. |
| | The NRC staff has noted some apparent anomalies in the five-year data file and provide the following examples, which should not be regarded as all inclusive. Therefore, please reevaluate the data file and provide justification that the 2003-2007 data are accurate or provide a supplemental file with revisions to identify any data as invalid for which such a justification cannot be provided. |
| | : a. Occurrences of data ending in a multiple of 10 for a number of consecutive hours {e.g., |
| | 2003, lower level wind direction for day 55, hour 3 through day 57, hour 17; day 58, hour 0 through hour 23; day 66, hour 11 through day 69 through hour 13}. |
| | Enclosure |
| | |
| | -2 |
| | : b. Occurrences of identical reported readings for a number of consecutive hours (e.g., |
| | 2004, lower level wind direction for day 85, hour 18, through day 86, hour 11; 2004 upper level wind direction for day 260, hour 15, through hour 21). |
| | : c. Identical wind direction values reported at both measurement levels (e.g., 2004, day 250, hour 11, through hour 15; 2005, day 222, hour 3 through day 228, hour 9). |
| | : 2. Page 2.9.2-3 of Attachment 7 to the original LAR states that the main control room (MCR) atmospheric dispersion factors (XIQ values) were calculated using the Murphy-Campe methodology. The calculation is explained on page 13 of a May 23, 1988 letter (ADAMS Accession No. 8805310306) associated with a prior licensing action request from Florida Power Corporation. These values were approved by the NRC as part of the N UREG-0737, "Clarification of TMI Action Plan Requirements," Item 111.0.3.4 review. The Murphy-Campe paper, "Nuclear Power Plant Control Room Ventilation System Design for Meeting General Criterion 19," advises that use of the equation on page 13 may be appropriate for a diffuse source - point receptor case for those cases when dual intakes are adequately separated and meet certain criteria as described in the Murphy-Campe paper. However, it is unclear to the NRC staff that the appropriate criteria are met for the purpose of the current LAR. |
| | Regulatory Guide 1.194, "Atmospheric Relative Concentrations for Control Room Radiological Habitability Assessments at Nuclear Power Plants," states that if the previously approved values are based on a misapplication of a methodology, calculational errors are identified in the values, or changes are deemed necessary to ensure adequate protection of the health and safety of the public, the NRC staff will pursue necessary corrections with the licensee or applicant. Therefore, please provide the following information. |
| | : a. Confirm that each MCR intake meets the requirements of an engineered safety feature including, as applicable, single-failure criteria for active components, seismic criteria, and missile criteria. |
| | : b. Further, confirm that the design details assure that the most contaminated intake is isolated and the least contaminated intake remains in operation to provide control room pressurization. |
| | : c. Given that the Murphy-Campe paper provides several equations, to address several different scenarios, provide justification that all of the possible releases for each design basis accident (DBA), including those associated with loss of offsite power or other single failure, meet the criteria which substantiate that use of the equation on page 13 of the May 23, 1988 letter is appropriate. |
| | : d. Provide one or more scaled figures, showing true north, with all possible sources and receptors highlighted from which distance and direction inputs can be approximated, for each DBA. Provide the scale of the figure. In addition, provide the height above grade of each source and receptor. Please include figures that show sources and receptors that consider loss of offsite power or other single failure and control room inleakage. |
| | |
| | - 3 |
| | : 3. Regulatory Guide 1.145, "Atmospheric Dispersion Models for Potential Accident Consequence Assessments at Nuclear Power Plants,>> states that the selection of X/a values to be used in exclusion area boundary (EAB) or low population zone boundary (LPZ) evaluations should be the maximum 0.5 percentile direction dependent (e.g., S, SSW, SW, etc.) X/a value or the 5 percent overall site limit X/a value for each time interval, whichever is higher. Please provide a summary table for the CR-3 EAB, and a second table for the LPZ, showing all 0.5 percentile direction dependent sector x/a values and the 5 percentile site limit X/a values. A copy of the EAB and LPZ summary pages from the PAVAN computer code output for CR-3 is acceptable. On these summary pages, highlight each of the EAB and LPZ X/Q values listed in Table 2.9.2-5 of Attachment 7 to the original LAR and provide justification for selection of each of the highlighted values. |
| | |
| | May 4, 2012 Mr. Jon A. Franke, Vice President Crystal River Nuclear Plant (NA2C) |
| | ATTN: Supervisor, Licensing & Regulatory Programs 15760 W. Power Line Street Crystal River, Florida 34428-6708 SUB..IECT: CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT - REQUEST FOR ADDITIONAL INFORMATION FOR EXTENDED POWER UPRATE LICENSE AMENDMENT REQUEST (TAC NO. ME6527) |
| | |
| | ==Dear Mr. Franke:== |
| | |
| | By letter dated June 15, 2011, as supplemented by letters dated July 5, 2011; August 11, 2011 (two letters), August 18 and 25, 2011, October 11 and 25, 2011, December 15, 2011 (two letters), December 21,2011, January 5,2012 (two letters), January 19, 2012 (two letters), |
| | January 31,2012, March 19,2012, March 22,2012, and April 4, 2012 (two letters), Florida Power Corporation, dOing business as Progress Energy Florida, Inc., submitted a license amendment request for an extended power uprate to increase thermal power level from 2609 megawatts thermal (MWt) to 3014 MWt for Crystal River Unit 3 Nuclear Generating Plant. |
| | The U.S. Nuclear Regulatory Commission staff is reviewing the submittal and has determined that additional information is required to complete its evaluation. This request was discussed with Mr. Dan Westcott of your staff on April 10, 2012, and it was agreed that a response to the enclosed request for additional information would be provided within 45 days from the date of this letter. |
| | If you have any questions regarding this matter, I can be reached at 301-415-1564. |
| | Sincerely, IRA! |
| | Siva P. Lingam, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-302 |
| | |
| | ==Enclosure:== |
| | |
| | Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION: |
| | PUBLIC LPL2-2 R/F RidsNrrDorlLpl2-2 RidsNrrPMCrystalRiver RidsNrrLABTullv RidsOgcRp Center RidsNrrDorlDpr RidsAcrsAcnw MailCTR SLingam, NRR RidsRgn2MailCenter RidsNrrDraAadb LBrown, NRR ADAMS A ccesslon N0: ML12102A044 *Bsy memo OFFICE LPL2-2/PM LPL2-2/LA AADB/BC* LPL2-21BC LPL2-21PM NAME SLingam BTuliV TIate DBroaddus SLingam (EBrown for) |
| | DATE 04/13/12 04113/12 04/6/12 05/04/12 05/04/12}} |
Letter Sequence RAI |
|---|
|
Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
Results
Other: 3F0112-11, Corrections to the Extended Power Uprate LAR 309 Vendor Affidavit and Technical Report, 3F0113-08, Attachment D: ANP-3195(NP), Revision 0, Response for Crystal River Unit 3, EPU Licensing Amendment Report NRC Reactor Systems Branch Requests for Additional Information (Non-Proprietary) and Attachment E: Location of Reactor Systems RAI Re, 3F0712-03, Attachment E to 3F0712-03, Technical Report, ANP-3052, Rev. 2, CR-3 EPU Feedwater Line Break Analysis with Failure of First Safety Grade Trip., 3F0912-01, ANP-3156 Np, Crystal River 3 EPU Boric Acid Precipitation RAI Responses, Attachment C, 3F1011-08, ANP-3052, Rev. 0, CR-3 EPU Feedwater Line Break Analysis with Failure of First Safety Grade Trip, 3F1112-02, 17877-0001-100, Rev. 1, CR-3 Inadequate Core Cooling Mitigation System Reliability Assessment, Task 1, Page 174 of 250 Through Page 250 of 250, ML11259A012, ML11300A226, ML11342A195, ML12031A032, ML12053A231, ML12107A068, ML12202A734, ML12205A357, ML12205A358, ML12240A119, ML12255A409, ML12262A385, ML12314A391, ML12314A392, ML12314A393, ML13032A540
|
MONTHYEAR3F0811-04, Response to Request for Additional Information to Support NRC Probabilistic Risk Assessment Licensing Branch Acceptance Review of the CR-3 Extended Power Uprate LAR2011-08-11011 August 2011
Response to Request for Additional Information to Support NRC Probabilistic Risk Assessment Licensing Branch Acceptance Review of the CR-3 Extended Power Uprate LAR
Project stage: Response to RAI
3F0811-02, Response to Request for Additional Information to Support NRC Balance of Plant Branch Acceptance Review of the CR-3 Extended Power Uprate LAR2011-08-11011 August 2011
Response to Request for Additional Information to Support NRC Balance of Plant Branch Acceptance Review of the CR-3 Extended Power Uprate LAR
Project stage: Response to RAI
3F0811-01, Response to Request for Additional Information to Support NRC Instrumentation and Controls Branch Acceptance Review of the CR-3 Extended Power Uprate LAR2011-08-18018 August 2011
Response to Request for Additional Information to Support NRC Instrumentation and Controls Branch Acceptance Review of the CR-3 Extended Power Uprate LAR
Project stage: Response to RAI
3F0811-03, Response to Request for Additional Information to Support NRC Mechanical and Civil Branch Acceptance Review of the CR-3 Extended Power Uprate LAR2011-08-25025 August 2011
Response to Request for Additional Information to Support NRC Mechanical and Civil Branch Acceptance Review of the CR-3 Extended Power Uprate LAR
Project stage: Response to RAI
ML11259A0122011-09-14014 September 2011
NRR E-mail Capture - Clarification for August 25 Emcb RAI Acceptance Review Letter
Project stage: Other
ML11286A0922011-10-11011 October 2011
Response to Request for Additional Information to Support NRC Reactor Systems Branch Acceptance Review of the CR-3 Extended Power Uprate LAR
Project stage: Response to RAI
ML11300A2262011-10-25025 October 2011
Feedwater Line Break Overpressure Protection Analysis to Support NRC Reactor Systems Branch Acceptance Review of the CR-3 Extended Power Update LAR and LAR Approval Schedule
Project stage: Other
3F1011-08, ANP-3052, Rev. 0, CR-3 EPU Feedwater Line Break Analysis with Failure of First Safety Grade Trip2011-10-25025 October 2011
ANP-3052, Rev. 0, CR-3 EPU Feedwater Line Break Analysis with Failure of First Safety Grade Trip
Project stage: Other
ML11326A2312011-12-0707 December 2011
Request for Additional Information for Extended Power Uprate License Amendment Request
Project stage: RAI
ML12205A3572011-12-15015 December 2011
Attachment a to 3F0712-03, CR-3 LOCA Summary Report - EPU/ROTSG/Mark-B-HTP, Revision 4
Project stage: Other
3F1211-05, Response to Request for Additional Information to Support NRC Health Physics and Human Performance Branch Technical Review of the CR-3 Extended Power Uprate LAR2011-12-15015 December 2011
Response to Request for Additional Information to Support NRC Health Physics and Human Performance Branch Technical Review of the CR-3 Extended Power Uprate LAR
Project stage: Response to RAI
3F1211-06, Response to Request for Additional Information to Support NRC Vessels and Internals Integrity Branch Technical Review of the CR-3 Extended Power Uprate LAR2011-12-15015 December 2011
Response to Request for Additional Information to Support NRC Vessels and Internals Integrity Branch Technical Review of the CR-3 Extended Power Uprate LAR
Project stage: Response to RAI
3F1211-10, Response to Request for Additional Information to Support NRC Fire Protection Branch Technical Review of the CR-3 Extended Power Uprate LAR2011-12-21021 December 2011
Response to Request for Additional Information to Support NRC Fire Protection Branch Technical Review of the CR-3 Extended Power Uprate LAR
Project stage: Response to RAI
3F0112-04, Response to Request for Additional Information to Support NRC Steam Generator Tube Integrity and Chemical Engineering Branch Technical Review of the CR-3 Extended Power Uprate LAR2012-01-0505 January 2012
Response to Request for Additional Information to Support NRC Steam Generator Tube Integrity and Chemical Engineering Branch Technical Review of the CR-3 Extended Power Uprate LAR
Project stage: Response to RAI
ML12030A2092012-01-0505 January 2012
Response to Request for Additional Information to Support NRC Instrumentation and Control Branch Technical Review of the CR-3 Extended Power Uprate LAR
Project stage: Response to RAI
ML11342A1952012-01-0606 January 2012
Notice of Consideration of Issuance of Amendment to Facility Operating License and Opportunity for a Hearing and Order Imposing Procedures for Document Access to Sensitive Unclassified Non-safeguards Information
Project stage: Other
ML12024A3002012-01-19019 January 2012
Response to Request for Additional Information to Support NRC Component Performance and Testing Branch Technical Review of the CR-3 Extended Power Uprate LAR
Project stage: Response to RAI
3F0112-06, Response to Request for Additional Information to Support NRC Piping and NDE Branch Technical Review of the CR-3 Extended Power Uprate LAR2012-01-19019 January 2012
Response to Request for Additional Information to Support NRC Piping and NDE Branch Technical Review of the CR-3 Extended Power Uprate LAR
Project stage: Response to RAI
3F0112-11, Corrections to the Extended Power Uprate LAR 309 Vendor Affidavit and Technical Report2012-01-31031 January 2012
Corrections to the Extended Power Uprate LAR #309 Vendor Affidavit and Technical Report
Project stage: Other
ML12003A2172012-02-0808 February 2012
Nuclear Generating Plant - Request for Additional Information for Extended Power Uprate License Amendment Request
Project stage: RAI
ML12052A1302012-03-0202 March 2012
Request for Additional Information for Extended Power Uprate License Amendment Request
Project stage: RAI
ML12053A2312012-03-0202 March 2012
Request for Withholding Proprietary Information from Public Disclosure Related Extended Power Uprate Technical Report
Project stage: Other
3F0312-02, Response to Second Request for Additional Information to Support NRC Instrumentation and Controls Branch (Eicb) Technical Review of the CR-3 Extended Power Uprate LAR2012-03-19019 March 2012
Response to Second Request for Additional Information to Support NRC Instrumentation and Controls Branch (Eicb) Technical Review of the CR-3 Extended Power Uprate LAR
Project stage: Request
3F0312-01, Response to Request for Additional Information to Support NRC PRA Licensing Branch Technical Review of the CR-3 Extended Power Uprate LAR2012-03-22022 March 2012
Response to Request for Additional Information to Support NRC PRA Licensing Branch Technical Review of the CR-3 Extended Power Uprate LAR
Project stage: Response to RAI
ML12031A0322012-03-26026 March 2012
Request for Withholding Proprietary Information from Public Disclosure Related to Extended Power Uprate Technical Report
Project stage: Other
ML12107A0682012-04-0404 April 2012
NRR E-mail Capture - Crystal River, Unit 3 EPU LAR - Clarifications for Component Performance & Testing Branch (Eptb)
Project stage: Other
3F0412-05, Response to Second Request for Additional Information to Support NRC Health Physics and Human Performance Branch (Ahpb) Technical Review of the CR-3 Extended Power Uprate LAR2012-04-0404 April 2012
Response to Second Request for Additional Information to Support NRC Health Physics and Human Performance Branch (Ahpb) Technical Review of the CR-3 Extended Power Uprate LAR
Project stage: Request
3F0412-04, Response to Request for Additional Information to Support NRC Mechanical and Civil Engineering Branch (Emcb) Technical Review of the CR-3 Extended Power Uprate LAR2012-04-0404 April 2012
Response to Request for Additional Information to Support NRC Mechanical and Civil Engineering Branch (Emcb) Technical Review of the CR-3 Extended Power Uprate LAR
Project stage: Response to RAI
3F0412-07, Response to Request for Additional Information to Support NRC Containment and Ventilation Branch (Scvb) Technical Review of the CR-3 Extended Power Uprate LAR2012-04-12012 April 2012
Response to Request for Additional Information to Support NRC Containment and Ventilation Branch (Scvb) Technical Review of the CR-3 Extended Power Uprate LAR
Project stage: Response to RAI
3F0412-06, Response to Request for Additional Information to Support NRC Electrical Systems Branch (Eeeb) Technical Review of the CR-3 Extended Power Uprate LAR2012-04-16016 April 2012
Response to Request for Additional Information to Support NRC Electrical Systems Branch (Eeeb) Technical Review of the CR-3 Extended Power Uprate LAR
Project stage: Response to RAI
3F0412-09, Response to Request for Additional Information to Support NRC Accident Dose Branch (Aadb) Technical Review of the CR-3 Extended Power Uprate LAR2012-04-26026 April 2012
Response to Request for Additional Information to Support NRC Accident Dose Branch (Aadb) Technical Review of the CR-3 Extended Power Uprate LAR
Project stage: Response to RAI
ML12102A0442012-05-0404 May 2012
Request for Additional Information for Extended Power Uprate License Amendment Request
Project stage: RAI
ML12314A3912012-05-31031 May 2012
17877-0002-100, CR-3 Inadequate Core Cooling Mitigation System Reliability Assessment 2
Project stage: Other
ML12205A3582012-05-31031 May 2012
Attachment D to 3F0712-03, Technical Report, ANP-3114(NP), Rev. 0, CR-3 EPU - Feedwater Line Break Analysis Sensitivity Studies.
Project stage: Other
3F0612-05, Response to Request for Additional Information to Support NRC Nuclear Performance and Code Review Branch (Snpb) Technical Review of the CR-3 Extended Power Uprate LAR2012-06-18018 June 2012
Response to Request for Additional Information to Support NRC Nuclear Performance and Code Review Branch (Snpb) Technical Review of the CR-3 Extended Power Uprate LAR
Project stage: Response to RAI
3F0712-03, Attachment E to 3F0712-03, Technical Report, ANP-3052, Rev. 2, CR-3 EPU Feedwater Line Break Analysis with Failure of First Safety Grade Trip.2012-06-30030 June 2012
Attachment E to 3F0712-03, Technical Report, ANP-3052, Rev. 2, CR-3 EPU Feedwater Line Break Analysis with Failure of First Safety Grade Trip.
Project stage: Other
ML12184A3442012-07-0202 July 2012
NRR E-mail Capture - Crystal River, Unit 3 EPU LAR - Discussion/Clarification of Emcb Draft RAIs
Project stage: Draft Other
ML12174A2922012-07-0505 July 2012
Request for Additional Information for Extended Power Uprate License Amendment Request
Project stage: RAI
ML12171A3472012-07-0505 July 2012
Request for Additional Information for Extended Power Uprate License Amendment Request
Project stage: RAI
ML12205A3562012-07-17017 July 2012
Supplement to the Extended Power Uprate License Amendment Request #309
Project stage: Supplement
3F0712-06, Response to Second Request for Additional Information to Support NRC Steam Generator Tube Integrity and Chemical Engineering Branch (Esgb) Technical Review of the CR-3 Extended Power Uprate LAR2012-07-17017 July 2012
Response to Second Request for Additional Information to Support NRC Steam Generator Tube Integrity and Chemical Engineering Branch (Esgb) Technical Review of the CR-3 Extended Power Uprate LAR
Project stage: Request
ML12194A4172012-07-17017 July 2012
Generating Plant - Request for Additional Information for Extended Power Uprate License Amendment Request
Project stage: RAI
3F0712-07, Response to Third Request for Additional Information to Support NRC Health Physics and Human Performance Branch (Ahpb) Technical Review of the CR-3 Extended Power Uprate LAR2012-07-31031 July 2012
Response to Third Request for Additional Information to Support NRC Health Physics and Human Performance Branch (Ahpb) Technical Review of the CR-3 Extended Power Uprate LAR
Project stage: Request
3F0712-08, Response to Second Request for Additional Information to Support NRC PRA Licensing Branch (Apla) Technical Review of the CR-3 Extended Power Uprate LAR2012-07-31031 July 2012
Response to Second Request for Additional Information to Support NRC PRA Licensing Branch (Apla) Technical Review of the CR-3 Extended Power Uprate LAR
Project stage: Request
ML12125A1622012-08-0101 August 2012
Nuclear Generating Plant - Request for Additional Information for Extended Power Uprate License Amendment Request
Project stage: RAI
ML12202A7342012-08-0101 August 2012
Request for Withholding Proprietary Information from Public Disclosure Related to Extended Power Uprate Technical Report
Project stage: Other
ML12202A0602012-08-0202 August 2012
Request for Additional Information for Extended Power Uprate License Amendment Request
Project stage: RAI
ML12213A3032012-08-0303 August 2012
Request for Additional Information for Extended Power Uprate License Amendment Request (Srxb)
Project stage: RAI
ML12219A1912012-08-16016 August 2012
Request for Additional Information for Extended Power Uprate License Amendment Request
Project stage: RAI
3F0812-02, Response to Second Request for Additional Information to Support NRC Electrical Engineering Branch (Eeeb) Technical Review of the CR-3 Extended Power Uprate LAR2012-08-21021 August 2012
Response to Second Request for Additional Information to Support NRC Electrical Engineering Branch (Eeeb) Technical Review of the CR-3 Extended Power Uprate LAR
Project stage: Request
2012-03-26
[Table View] |
|
|---|
Category:Letter
MONTHYEARIR 05000302/20240012024-09-23023 September 2024
Accelerated Decommissioning Partners (ADP) CR3, LLC, Crystal River Unit 3, NRC Inspection Report No. 05000302/2024001
ML24240A1692024-09-18018 September 2024
Cy 2023 Summary of Decommissioning Trust Fund Status
ML24226B2392024-08-27027 August 2024
Application for License Amendment Request to Add License Condition to Include License Termination Plan Requirements – Acknowledgement of Withdrawal
ML24179A0702024-07-26026 July 2024
SHPO S106 Completion Crystal River Unit 3
ML24205A2192024-07-24024 July 2024
Tribal S106 Completion Crystal River Unit 3: Muscogee Nation
ML24205A2182024-07-24024 July 2024
Tribal S106 Completion Crystal River Unit 3: Seminole Nation of Oklahoma
ML24179A0912024-07-24024 July 2024
Tribal S106 Completion Crystal River Unit 3: Seminole Tribe of Florida
ML24205A2202024-07-24024 July 2024
Tribal S106 Completion Crystal River Unit 3_Miccosukee Tribe of Florida
ML24190A1912024-07-0808 July 2024
Fws Concurrence for Crystal River Unit 3
ML24172A2552024-06-20020 June 2024
Fws to NRC Species List: Florida Ecological Services Field Office 06/20/2024
ML24170A9242024-06-18018 June 2024
024-0023697 Crystal River License Termination Plan Unit 3
ML24151A6482024-06-0303 June 2024
Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities
ML24114A2262024-04-24024 April 2024
Amended Special Package Authorization for the Cr3 Middle Package (Crystal River 3 Middle Package - Docket No. 71-9393)
IR 05000302/20230022024-04-17017 April 2024
Accelerated Decommissioning Partners (ADP) CR3, LLC, Crystal River Unit 3 - NRC Inspection Report No. 05000302/2023002
ML24054A0612024-04-0202 April 2024
Request to Initiate Section 106 Consultation Regarding the License Termination Plan for Crystal River Unit 3 in Citrus County, Florida
ML24079A2492024-04-0202 April 2024
Tribal S106 Initiation Crystal River Unit 3-Johnson, Lewis Johnson
ML24054A0582024-04-0202 April 2024
Achp S106 Initiation Crystal River Unit 3 - Letter 1
ML24079A2472024-04-0202 April 2024
Tribal S106 Initiation Crystal River Unit 3-Cypress, Talbert
ML24079A2482024-04-0202 April 2024
Tribal S106 Initiation Crystal River Unit 3-Hill, David Hill
ML24054A0812024-04-0202 April 2024
Tribal S106 Initiation Crystal River Unit 3-Osceola, Marcellus
ML24089A0362024-03-29029 March 2024
Response to Audit Plan in Support of Accelerated Decommissioning Partners and Request to Add License Condition to Include License Termination Plan Requirements. W/Enclosures 1 to 5
ML24073A1922024-03-11011 March 2024
Fws to NRC, List of Threatened and Endangered Species That May Occur in Your Proposed Project Location or May Be Affected by Your Proposed Project
ML24054A6452024-02-29029 February 2024
Letter - Reply to Request for RAI Extension Related to the Crystal River License Termination Plan
ML24030A7482024-02-12012 February 2024
Audit Report Cover Letter and Report - Crystal River Unit 3 Nuclear Generating Plant LTP
ML23342A0942024-01-0909 January 2024
– Independent Spent Fuel Storage Installation Security Inspection Plan
ML23354A0632023-12-22022 December 2023
Cover Letter - Crystal River License Termination Plan Request for Additional Information
ML23345A1882023-12-0606 December 2023
Fws to NRC Crystal River Species List of Threatened and Endangered Species That May Occur in Your Proposed Project Location or May Be Affected by Your Proposed Project
ML23320A2592023-11-17017 November 2023
STC-23 077 Notification of the Crystal River Unit 3 Generating Plant License Termination Plan Public Meeting and Federal Register Notice
ML23313A1322023-11-15015 November 2023
Request for Additional Information for the Environmental Assessment of the License Termination Plan for Crystal River Unit 3 Nuclear Generating Plant
ML23310A0712023-11-0707 November 2023
Audit Plan Cover Letter - Crystal River Unit 3 Nuclear Generating Plant LTP
ML23187A1112023-07-25025 July 2023
Acceptance of Requested Licensing Action License Request to Add License Condition to Include License Termination Plan Requirements
ML23107A2722023-06-13013 June 2023
Letter Transmitting NRC Survey Results for East Settling Pond
ML23160A2962023-06-0909 June 2023
Response to Crystal River, Unit 3 – Supplemental Information Needed for Acceptance on the Application for a License Amendment Regarding Approval of the License Termination Plan
ML23107A2732023-06-0707 June 2023
Orise Independent Survey Report Dcn 5366-SR-01-0
IR 05000302/20220032023-05-25025 May 2023
Accelerated Decommissioning Partners (ADP) CR3, LLC, Crystal River Unit 3 - NRC Inspection Report No. 05000302/2022003
ML23103A1902023-04-19019 April 2023
Request for Supplemental Information Cover Letter
ML23058A2532023-03-22022 March 2023
Accelerated Decommissioning Partners (ADP) CR3, LLC, Crystal River, Unit 3 - NRC Inspection Report No. 05000302/2022003
ML22361A1022023-02-24024 February 2023
Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities
ML22265A0192022-09-26026 September 2022
Nuclear Generating Plant - U.S. Nuclear Regulatory Commissions Analysis of ADP CR3, LLCs Decommissioning Funding Status Report (License No. DPR-72, Docket Nos. 50-302 and 72-1035)
IR 05000302/20220022022-08-0909 August 2022
Accelerated Decommissioning Partners (ADP) CR3, LLC, Crystal River Unit 3 - NRC Inspection Report 05000302/2022002
IR 05000302/20220012022-05-0303 May 2022
Accelerated Decommissioning Partners (ADP) CR3, LLC, Crystal River Unit 3 - NRC Inspection Report 05000302/2022001
ML22116A1752022-04-27027 April 2022
Accelerated Decommissioning Partners (ADP) CR3, LLC, Crystal River Unit 3- Independent Spent Fuel Storage Installation Security Inspection Report 07201035/2022401
ML22105A3992022-04-18018 April 2022
Nuclear Generating Plant - Change in NRC Project Manager
ML22011A1362022-01-31031 January 2022
Independent Spent Fuel Storage Installation Security Inspection Plan
ML22024A2142022-01-24024 January 2022
Nuclear Generating Plant - NMFS NRC Letter - Crystal River Energy Complex Biological Opinion Status (License No. DPR-72, Docket Nos. 50-302 and 72-1035)
IR 05000302/20210042022-01-24024 January 2022
Accelerated Decommissioning Partners (ADP) CR3, LLC, Crystal River Unit 3 - NRC Inspection Report No. 05000302/2021004
ML21351A0052021-12-20020 December 2021
NRC Analysis of ADP CR3, LLC Decommissioning Funding Status Report for the Crystal River Unit 3 Nuclear Generating Plant (License No. DPR-72, Docket Nos. 50-302 and 72-1035)
ML21322A2702021-11-24024 November 2021
Nuclear Generating Plant - Issuance of Amendment No. 260 Approving the Independent Spent Fuel Storage Installation Only Security Plan, Rev 3
IR 05000302/20210032021-11-0909 November 2021
Accelerated Decommissioning Partners (ADP) CR3, LLC, Crystal River Unit 3 - NRC Inspection Report Nos. 05000302/2021003 and 07201035/2021001
ML21288A4292021-10-18018 October 2021
Letter - Crystal River Unit 3 Nuclear Generating Plant - Correction to Safety Evaluation Related to the Issuance of Amendment No. 259 Approving the Independent Spent Fuel Storage Installation Only Emergency Plan
2024-09-23
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML23354A0632023-12-22022 December 2023
Cover Letter - Crystal River License Termination Plan Request for Additional Information
ML23354A0642023-12-22022 December 2023
Enclosure - Crystal River License Termination Plan Request for Additional Information
ML23313A1322023-11-15015 November 2023
Request for Additional Information for the Environmental Assessment of the License Termination Plan for Crystal River Unit 3 Nuclear Generating Plant
ML23103A1922023-04-19019 April 2023
Request for Supplemental Information Enclosure
ML21182A1032021-07-0606 July 2021
Request for Additional Information (RAI) Related to the ISFSI-Only Emergency Plan
ML16032A1772016-02-0404 February 2016
J. Hickman, NRC, Letter to T. Hobbs, Crystal River 3, Request for Additional Information for Emergency Plan Change
ML15026A4162015-02-0202 February 2015
Request for Additional Information Regarding the 10 CFR 50.54(p) Changes to the Security Plans
ML14274A1392015-01-0808 January 2015
Request for Additional Information, License Amendment Request to Revise Technical Specifications and License Conditions to Create Permanently Defueled Technical Specifications
ML14133A5032014-05-14014 May 2014
Correction, Request for Additional Information on the Post Shutdown Decommissioning Activities Report
ML14104A0392014-04-28028 April 2014
Request for Additional Information on the Post Shutdown Decommissioning Activities Report
ML13175A2152013-06-28028 June 2013
Request for Additional Information Regarding Request to Rescind Fukushima-Related Orders
ML13018A3072013-02-0101 February 2013
Request for Additional Information for Extended Power Uprate License Amendment Request
ML12355A6592012-12-21021 December 2012
Nuclear Generating Plant - RAI 9.3 of the Near-Term Task Force Fukushima Dai-ichi..
ML12333A0892012-12-19019 December 2012
Request for Additional Information for Extended Power Uprate License Amendment Request
ML12310A2912012-11-15015 November 2012
Request for Additional Information for Changes to Security Plan
ML12240A0152012-08-28028 August 2012
Request for Additional Information for Extended Power Uprate License Amendment Request
ML12219A1912012-08-16016 August 2012
Request for Additional Information for Extended Power Uprate License Amendment Request
ML12213A3032012-08-0303 August 2012
Request for Additional Information for Extended Power Uprate License Amendment Request (Srxb)
ML12202A0602012-08-0202 August 2012
Request for Additional Information for Extended Power Uprate License Amendment Request
ML12125A1622012-08-0101 August 2012
Nuclear Generating Plant - Request for Additional Information for Extended Power Uprate License Amendment Request
ML12194A4172012-07-17017 July 2012
Generating Plant - Request for Additional Information for Extended Power Uprate License Amendment Request
ML12174A2922012-07-0505 July 2012
Request for Additional Information for Extended Power Uprate License Amendment Request
ML12171A3472012-07-0505 July 2012
Request for Additional Information for Extended Power Uprate License Amendment Request
ML12102A0442012-05-0404 May 2012
Request for Additional Information for Extended Power Uprate License Amendment Request
ML12056A0492012-03-12012 March 2012
Enclosure 3 - Recommendation 2.3: Seismic
ML12056A0512012-03-12012 March 2012
Enclosure 5 - Recommendation 9.3: Emergency Preparedness
ML12056A0502012-03-12012 March 2012
Enclosure 4 - Recommendation 2.3: Flooding
ML12056A0482012-03-12012 March 2012
Enclosure 2 - Recommendation 2.1: Flooding
ML12056A0472012-03-12012 March 2012
Enclosure 1 - Recommendation 2.1: Seismic
ML12052A1302012-03-0202 March 2012
Request for Additional Information for Extended Power Uprate License Amendment Request
ML12003A2172012-02-0808 February 2012
Nuclear Generating Plant - Request for Additional Information for Extended Power Uprate License Amendment Request
ML11326A2312011-12-0707 December 2011
Request for Additional Information for Extended Power Uprate License Amendment Request
ML11308A6592011-11-17017 November 2011
Generating Plant - Request for Additional Information Regarding 60-Day Response to Bulletin 2011-01, Mitigating Strategies
ML11301A1142011-11-0808 November 2011
Request for Additional Information for the Review of the Crystal River Unit 3 Nuclear Generating Plant, License Renewal Application
ML1128602942011-10-12012 October 2011
IR 05000302-11-005; 11/14-18/2011; Crystal River Unit 3, Notification of Inspection and Request for Information
ML11175A1512011-06-30030 June 2011
Request for Additional Information for the Review of the Crystal River Unit 3 Nuclear Generating Plant, License Renewal Application
ML11137A1742011-06-22022 June 2011
Nuclear Generating Plant; H. B. Robinson Steam Electric Plant, 2; and Shearon Harris Nuclear Power Plant, Unit 1 Request for Additional Information Regarding 2011 Decommissioning Funds
ML1115403412011-06-0202 June 2011
Nuclear Generating Plant - Notification of Inspection and Request for Information 05000302/2011501
ML11122A0002011-05-26026 May 2011
Request for Additional Information for the Review of the Crystal River, Unit 3, License Renewal Application
ML1112501592011-05-0505 May 2011
Notice of Inspection and Request for Information 05000302/2011003
ML1108202262011-03-31031 March 2011
Request for Additional Information for the Review of the Crystal River Unit 3 Nuclear Generating Plant, License Renewal Application
ML1031402722010-11-16016 November 2010
Request for Additional Information for the Review of the Crystal Review Unit 3 Nuclear Generating Plant, License Renewal Application
ML1029503292010-11-0808 November 2010
Request for Additional Information for the Review of the Crystal River Unit 3 Nuclear Generating Plant License Renewal Application
ML1030202942010-10-28028 October 2010
Nuclear Generating Plant - Notification of Inspection and Request for Information IR 05000302-10-005
ML1027100652010-10-19019 October 2010
09/27/10 Summary of Telephone Conference Call Held Between NRC and Florida Power Corp., Concerning Draft Request for Information Related to Crystal River, Unit 3, License Renewal Application
ML1026002432010-10-14014 October 2010
Request for Additional Information for the Review of the Crystal River Unit 3 Nuclear Generating Plant, License Renewal Application
ML1022800102010-08-11011 August 2010
Nuclear Generating Plant - Draft RAIs Regarding Crystal River Unit 3 Part 26 Exemption Request
ML1017404972010-07-0808 July 2010
Request for Additional Information for the Review of the Crystal River Unit 3 Nuclear Generating Plant, License Renewal Application
ML1015303972010-07-0808 July 2010
RAI for the Review of the Crystal River Unit 3 Nuclear Generating Plant, License Renewal Application
ML1014105122010-06-0202 June 2010
Request for Additional Information for the Review of the Crystal River Unit 3 Nuclear Generating Plant, License Renewal Application
2023-04-19
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 4, 2012 Mr. Jon A. Franke, Vice President Crystal River Nuclear Plant (NA2C)
ATTN: Supervisor, Licensing & Regulatory Programs 15760 W. Power Line Street Crystal River, Florida 34428-6708 SUB.JECT: CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT - REQUEST FOR ADDITIONAL INFORMATION FOR EXTENDED POWER UPRATE LICENSE AMENDMENT REQUEST (TAC NO. ME6527)
Dear Mr. Franke:
By letter dated June 15, 2011, as supplemented by letters dated July 5, 2011; August 11, 2011 (two letters), August 18 and 25, 2011, October 11 and 25, 2011, December 15, 2011 (two letters), December 21,2011, January 5,2012 (two letters), January 19, 2012 (two letters),
January 31, 2012, March 19, 2012, March 22, 2012, and April 4, 2012 (two letters), Florida Power Corporation, dOing business as Progress Energy Florida, Inc., submitted a license amendment request for an extended power uprate to increase thermal power level from 2609 megawatts thermal (MWt) to 3014 MWt for Crystal River Unit 3 Nuclear Generating Plant.
The U.S. Nuclear Regulatory Commission staff is reviewing the submittal and has determined that additional information is required to complete its evaluation. This request was discussed with Mr. Dan Westcott of your staff on April 10, 2012, and it was agreed that a response to the enclosed request for additional information would be provided within 45 days from the date of this letter.
If you have any questions regarding this matter, I can be reached at 301-415-1564.
Sincerely, IRA!
Siva P. Lingam, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-302
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION REGARDING EXTENDED POWER UPRATE TO INCREASE THERMAL POWER LEVEL FROM 2609 MEGAWATTS THERMAL TO 3014 MEGAWATTS THERMAL CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT DOCKET NO. 50-302 By letter dated June 15, 2011 {Agencywide Documents Access and Management System
{ADAMS} Accession No. ML112070659}, as supplemented by letters dated July 5,2011, August 11, 2011 {two letters}, August 18 and 25, 2011, October 11 and 25, 2011, December 15, 2011 {two letters}, December 21, 2011, January 5, 2012 (two letters),
January 19, 2012 (two letters), January 31,2012, March 19,2012, March 22, 2012, and April 4, 2012 {two letters} {ADAMS Accession Nos. ML112010674, ML11228A032, ML11234A051, ML11234A427, ML11242A140, ML112860156, ML113040176, ML11354A232, ML11354A233, ML11361A460, ML12011A035, ML12030A209, ML12024A300, ML12024A301, ML120330114, ML12081A293, ML12086A107, ML12097A183, and ML12097A246, respectively}, Florida Power Corporation (the licensee), doing business as Progress Energy Florida, Inc., submitted a license amendment request (LAR) for an extended power uprate (EPU) to increase thermal power level from 2609 megawatts thermal (MWt) to 3014 MWt for Crystal River Unit 3 Nuclear Generating Plant (Crystal River 3 or CR-3). In order to complete its review of the above documents, the Nuclear Regulatory Commission (NRC) staff requests additional information originating from our Accident Dose Branch (AADB) related to atmospheric dispersion part:
AAOB Requests for Additional Information
- 1. Please provide detailed information describing how the CR-3 2003 - 2007 meteorological data provided in support of the CR-3 EPU original LAR dated June 15, 2011 (ADAMS Accession No. ML112070659) were measured and processed, and the criteria used to determine the validity of the data. Describe the temporal sequence of the processing steps to generate the hourly data file and criteria for any data substitutions or modifications.
The NRC staff has noted some apparent anomalies in the five-year data file and provide the following examples, which should not be regarded as all inclusive. Therefore, please reevaluate the data file and provide justification that the 2003-2007 data are accurate or provide a supplemental file with revisions to identify any data as invalid for which such a justification cannot be provided.
- a. Occurrences of data ending in a multiple of 10 for a number of consecutive hours {e.g.,
2003, lower level wind direction for day 55, hour 3 through day 57, hour 17; day 58, hour 0 through hour 23; day 66, hour 11 through day 69 through hour 13}.
Enclosure
-2
- b. Occurrences of identical reported readings for a number of consecutive hours (e.g.,
2004, lower level wind direction for day 85, hour 18, through day 86, hour 11; 2004 upper level wind direction for day 260, hour 15, through hour 21).
- c. Identical wind direction values reported at both measurement levels (e.g., 2004, day 250, hour 11, through hour 15; 2005, day 222, hour 3 through day 228, hour 9).
- 2. Page 2.9.2-3 of Attachment 7 to the original LAR states that the main control room (MCR) atmospheric dispersion factors (XIQ values) were calculated using the Murphy-Campe methodology. The calculation is explained on page 13 of a May 23, 1988 letter (ADAMS Accession No. 8805310306) associated with a prior licensing action request from Florida Power Corporation. These values were approved by the NRC as part of the N UREG-0737, "Clarification of TMI Action Plan Requirements," Item 111.0.3.4 review. The Murphy-Campe paper, "Nuclear Power Plant Control Room Ventilation System Design for Meeting General Criterion 19," advises that use of the equation on page 13 may be appropriate for a diffuse source - point receptor case for those cases when dual intakes are adequately separated and meet certain criteria as described in the Murphy-Campe paper. However, it is unclear to the NRC staff that the appropriate criteria are met for the purpose of the current LAR.
Regulatory Guide 1.194, "Atmospheric Relative Concentrations for Control Room Radiological Habitability Assessments at Nuclear Power Plants," states that if the previously approved values are based on a misapplication of a methodology, calculational errors are identified in the values, or changes are deemed necessary to ensure adequate protection of the health and safety of the public, the NRC staff will pursue necessary corrections with the licensee or applicant. Therefore, please provide the following information.
- a. Confirm that each MCR intake meets the requirements of an engineered safety feature including, as applicable, single-failure criteria for active components, seismic criteria, and missile criteria.
- b. Further, confirm that the design details assure that the most contaminated intake is isolated and the least contaminated intake remains in operation to provide control room pressurization.
- c. Given that the Murphy-Campe paper provides several equations, to address several different scenarios, provide justification that all of the possible releases for each design basis accident (DBA), including those associated with loss of offsite power or other single failure, meet the criteria which substantiate that use of the equation on page 13 of the May 23, 1988 letter is appropriate.
- d. Provide one or more scaled figures, showing true north, with all possible sources and receptors highlighted from which distance and direction inputs can be approximated, for each DBA. Provide the scale of the figure. In addition, provide the height above grade of each source and receptor. Please include figures that show sources and receptors that consider loss of offsite power or other single failure and control room inleakage.
- 3
- 3. Regulatory Guide 1.145, "Atmospheric Dispersion Models for Potential Accident Consequence Assessments at Nuclear Power Plants,>> states that the selection of X/a values to be used in exclusion area boundary (EAB) or low population zone boundary (LPZ) evaluations should be the maximum 0.5 percentile direction dependent (e.g., S, SSW, SW, etc.) X/a value or the 5 percent overall site limit X/a value for each time interval, whichever is higher. Please provide a summary table for the CR-3 EAB, and a second table for the LPZ, showing all 0.5 percentile direction dependent sector x/a values and the 5 percentile site limit X/a values. A copy of the EAB and LPZ summary pages from the PAVAN computer code output for CR-3 is acceptable. On these summary pages, highlight each of the EAB and LPZ X/Q values listed in Table 2.9.2-5 of Attachment 7 to the original LAR and provide justification for selection of each of the highlighted values.
May 4, 2012 Mr. Jon A. Franke, Vice President Crystal River Nuclear Plant (NA2C)
ATTN: Supervisor, Licensing & Regulatory Programs 15760 W. Power Line Street Crystal River, Florida 34428-6708 SUB..IECT: CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT - REQUEST FOR ADDITIONAL INFORMATION FOR EXTENDED POWER UPRATE LICENSE AMENDMENT REQUEST (TAC NO. ME6527)
Dear Mr. Franke:
By letter dated June 15, 2011, as supplemented by letters dated July 5, 2011; August 11, 2011 (two letters), August 18 and 25, 2011, October 11 and 25, 2011, December 15, 2011 (two letters), December 21,2011, January 5,2012 (two letters), January 19, 2012 (two letters),
January 31,2012, March 19,2012, March 22,2012, and April 4, 2012 (two letters), Florida Power Corporation, dOing business as Progress Energy Florida, Inc., submitted a license amendment request for an extended power uprate to increase thermal power level from 2609 megawatts thermal (MWt) to 3014 MWt for Crystal River Unit 3 Nuclear Generating Plant.
The U.S. Nuclear Regulatory Commission staff is reviewing the submittal and has determined that additional information is required to complete its evaluation. This request was discussed with Mr. Dan Westcott of your staff on April 10, 2012, and it was agreed that a response to the enclosed request for additional information would be provided within 45 days from the date of this letter.
If you have any questions regarding this matter, I can be reached at 301-415-1564.
Sincerely, IRA!
Siva P. Lingam, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-302
Enclosure:
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PUBLIC LPL2-2 R/F RidsNrrDorlLpl2-2 RidsNrrPMCrystalRiver RidsNrrLABTullv RidsOgcRp Center RidsNrrDorlDpr RidsAcrsAcnw MailCTR SLingam, NRR RidsRgn2MailCenter RidsNrrDraAadb LBrown, NRR ADAMS A ccesslon N0: ML12102A044 *Bsy memo OFFICE LPL2-2/PM LPL2-2/LA AADB/BC* LPL2-21BC LPL2-21PM NAME SLingam BTuliV TIate DBroaddus SLingam (EBrown for)
DATE 04/13/12 04113/12 04/6/12 05/04/12 05/04/12
