Letter Sequence Other |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance, Acceptance
Results
Other: HNP-07-114, Documentation of Changes to Severe Accident Mitigation Analysis License Renewal Application, HNP-07-139, Impact of Errors in the SECPOP2000 Computer Code on the Severe Accident Mitigation Alternatives Analysis for Shearon Harris Nuclear Power Plant License Renewal, ML063350276, ML063600250, ML070790140, ML071280403, ML071360138, ML071690054, ML080640200, ML080720335, ML080840431, ML081970434
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MONTHYEARML0633502762006-11-30030 November 2006 Applicant'S Environmental Report - Operating License Renewal Stage Project stage: Other ML0707901402007-03-20020 March 2007 Federal Register Notice 72FR13139, Shearon Harris License Renewal 03/20/07 Project stage: Other ML0707401602007-03-27027 March 2007 Request for Additional Information Regarding Severe Accident Mitigation Alternatives for Shearon Harris Nuclear Power Plant Project stage: RAI ML0636002502007-03-28028 March 2007 Notice of Intent to Prepare an Environmental Impact Statement and Conduct Scoping Process for License Renewal for the Shearon Harris Nuclear Power Plant Project stage: Other Press Release-II-07-013, NRC to Discuss Process for Review of License Renewal Application for Harris Nuclear Plant, Seeks Environmental Input2007-04-11011 April 2007 Press Release-II-07-013: NRC to Discuss Process for Review of License Renewal Application for Harris Nuclear Plant, Seeks Environmental Input Project stage: Request ML0709302892007-04-12012 April 2007 Summary Conference Call 3/27/07, Between the USNRC and Cp&L, Concerning Draft Requests for Additional Information Shearon Harris License Renewal Application Project stage: Draft RAI ML0713003712007-04-18018 April 2007 04/18/2007 Meeting Transcript for Shearon Harris, Unit 1, License Renewal Public Meeting - Afternoon Session, Pages 1-76 Project stage: Meeting ML0713003772007-04-18018 April 2007 04/18/2007 Meeting Transcript for Shearon Harris, Unit 1, License Renewal Public Meeting - Evening Session, Pages 1-62 Project stage: Meeting HNP-07-045, Annual Radiological Environmental Operating Report for 20062007-04-18018 April 2007 Annual Radiological Environmental Operating Report for 2006 Project stage: Request ML0711604622007-04-18018 April 2007 04/18/2007 Slides Used During the Environmental Scoping Meeting Related to the License Renewal Review of Shearon Harris Nuclear Power Plant Project stage: Meeting ML0713000242007-04-20020 April 2007 Multiple Comments (4) Submitted by Progress Energy Third Party Coalitions Consisiting of Resolutions in Support of the Continued Safe and Secure Operation of the Shearon Harris Project stage: Request ML0712804032007-04-26026 April 2007 Ltr from H. Legrand (North Carolina Natural Heritage Program) to R. Franovich (NRC) Shearon Harris Nuclear Power Plant License Renewal Application Review Project stage: Other ML0712004342007-05-14014 May 2007 04/18/2007 Summary of Public Meetings Related to the Review of the Shearon Harris Nuclear Power Plant, License Renewal Application Project stage: Meeting ML0713601382007-05-21021 May 2007 Environmental Site Audit Regarding Shearon Harris Nuclear Power Plant License Renewal Application Project stage: Other ML0716900542007-06-25025 June 2007 06/13/2007 Summary of Conference Call Between NRC and Cp&L, Concerning SAMA Analysis of the Shearon Harris Nuclear Power Plant License Renewal Application Project stage: Other ML0716603222007-07-12012 July 2007 Requests for Additional Information Regarding the Environmental Review for Shearon Harris Nuclear Power Plant License Renewal Application Project stage: RAI HNP-07-105, Response to Requests for Additional Information Regarding the Environmental Review for Shearon Harris Nuclear Power Plant License Renewal Application, Response to RAI No. 1, Item 1 Through Item 72007-08-0808 August 2007 Response to Requests for Additional Information Regarding the Environmental Review for Shearon Harris Nuclear Power Plant License Renewal Application, Response to RAI No. 1, Item 1 Through Item 7 Project stage: Response to RAI ML0722904742007-08-0808 August 2007 Response to Requests for Additional Information Regarding the Environmental Review for Shearon Harris Nuclear Power Plant License Renewal Application Project stage: Response to RAI HNP-07-114, Documentation of Changes to Severe Accident Mitigation Analysis License Renewal Application2007-08-27027 August 2007 Documentation of Changes to Severe Accident Mitigation Analysis License Renewal Application Project stage: Other HNP-07-139, Impact of Errors in the SECPOP2000 Computer Code on the Severe Accident Mitigation Alternatives Analysis for Shearon Harris Nuclear Power Plant License Renewal2007-10-0505 October 2007 Impact of Errors in the SECPOP2000 Computer Code on the Severe Accident Mitigation Alternatives Analysis for Shearon Harris Nuclear Power Plant License Renewal Project stage: Other ML0729200822007-10-19019 October 2007 Index of References - Shearon Harris SEIS License Renewal Project stage: Acceptance Review ML0732007012007-12-10010 December 2007 FRN - Notice of Availability of the Draft Supplement 33 to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants and Public Meeting for the License Renewal of Shearon Harris Nuclear Power Plant, Unit 1 ML0732006652007-12-10010 December 2007 NOA of the Draft Plant-Specific Supplement 33 to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants (Geis) Regarding Sheron Harris Nuclear Power Plant, Unit 1 (MD3611) - Letter Project stage: Draft Other Press Release-II-07-055, NRC Issues Draft Environmental Impact Statement for Harris Nuclear Plant License Renewal; Public Meeting Jan. 30.2007-12-26026 December 2007 Press Release-II-07-055: NRC Issues Draft Environmental Impact Statement for Harris Nuclear Plant License Renewal; Public Meeting Jan. 30. Project stage: Request ML0733203642007-12-31031 December 2007 NUREG-1437 Supp 33 Dfc, Generic Environmental Impact Statement for License Renewal of Nuclear Plants: Regarding Shearon Harris Nuclear Power Plant, Unit 1 (Draft for Comment). Project stage: Draft Other ML0736010052008-01-14014 January 2008 01/30/2008-Notice of Meeting to Discuss the Draft Supplemental Environmental Impact Statement for the License Renewal of Shearon Harris Nuclear Power Plant Unit 1 ML0806402002008-01-27027 January 2008 Comment (3) of Brad Kocher Supporting the License Renewal of the Shearon Harris Facility Project stage: Other ML0806402012008-01-28028 January 2008 Comment (4) of George J. Wilberg Supporting Renewal Harris Nuclear Plant Project stage: Request ML0803703952008-01-28028 January 2008 Comment (2) of Rudolph Williams, for GEIS December 2007 (Harris Nuclear Plant, Unit 1) Project stage: Request ML0806402022008-01-30030 January 2008 Comment (5) of C. Tiffany on Renewal of Shearon Harris License. Licensing Should Be Contingent on FAIL-SAFE Dry-Cask Containment of Hazardous Rad-Waste Project stage: Request ML0803902862008-01-30030 January 2008 Transcript of Shearon Harris, Draft EIS, Public Meeting Afternoon Session, Wednesday, January 30, 2008, Pages 1-36 Project stage: Request ML0804601262008-01-30030 January 2008 Transcript of Shearon Harris Nuclear Power Plant Draft EIS, Public Meeting Evening Session, Wednesday, January 30, 2008, Pages 1-24 Project stage: Request ML0804601542008-01-30030 January 2008 01/30/2008 Slides Used During Dseis Meeting Related to the License Renewal Review of Shearon Harris Nuclear Power Plant Project stage: Meeting ML0804604802008-02-27027 February 2008 Summary of Public Meetings on the Draft Supplemental Environmental Impact Statement Regarding the Shearon Harris Nuclear Power Plant, License Renewal Review ML0807203352008-03-0303 March 2008 Comment (7) of Chatham County Board of Commissioners Opposing Generic Environmental Impact Statement (GEIS) for License Renewal of the Shearon Harris Nuclear Power Plant Project stage: Other ML0807203342008-03-0303 March 2008 Comment (8) of Heinz J. Mueller on Behalf of Us Environmental Protection Agency, Supports Renewal of Operating License for Shearon Harris Power Plant for Another 20 Years Project stage: Request ML0809501862008-03-0505 March 2008 Comment (12) of Liz Cullington, Opposing Generic EIS for License Renewal of Nuclear Plants, Supplement 33: Regarding Shearon Harris Nuclear Power Plant, Unit 1, Draft Report for Comment ML0808404312008-03-0707 March 2008 Comment (5) of Chrys Baggett on Behalf of North Carolina, Dept. of Administration Regarding Deis; License Renewal for Shearon Harris Nuclear Power Plant for an Additional 20 Years of Operation in Wake County Project stage: Other ML0819704342008-08-13013 August 2008 Notice of Availability of the Final Plant-Specific Supplement 33 to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding Shearon Harris Nuclear Power Plant, Unit 1 (TAC No. Md3611) Project stage: Other ML0822502902008-08-31031 August 2008 NUREG-1437 Supplement 33 Generic Environmental Impact Statement for License Renewal of Nuclear Plants: Regarding Shearon Harris Nuclear Power Plant, Unit 1 - Final Report Project stage: Acceptance Review 2007-05-14
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Category:Letter type:HNP
MONTHYEARHNP-18-050, Request to Extend Reactor Vessel Surveillance Capsule Report Submission Date2018-09-17017 September 2018 Request to Extend Reactor Vessel Surveillance Capsule Report Submission Date HNP-18-004, License Amendment Request to Change Shearon Harris Nuclear Power Plant, Unit 1, Emergency Plan Emergency Action Level Scheme2018-08-13013 August 2018 License Amendment Request to Change Shearon Harris Nuclear Power Plant, Unit 1, Emergency Plan Emergency Action Level Scheme HNP-18-035, Relief Request I3R-18, Alternative Repair and Replacement Testing Requirements for the Containment Building Equipment Hatch Sleeve Weld, Lnservice Inspection Program for Containment, Third Ten-Year Interval2018-06-0404 June 2018 Relief Request I3R-18, Alternative Repair and Replacement Testing Requirements for the Containment Building Equipment Hatch Sleeve Weld, Lnservice Inspection Program for Containment, Third Ten-Year Interval HNP-18-049, Submittal of 1 0 CFR 50.54(q) Evaluation Form of Changes to Procedure EMP-420, Emergency Program Maintenance, Revision 192018-05-0303 May 2018 Submittal of 1 0 CFR 50.54(q) Evaluation Form of Changes to Procedure EMP-420, Emergency Program Maintenance, Revision 19 HNP-18-023, Report of Changes Pursuant to 10 CFR 50.59 and Summary of Commitment Changes2018-05-0202 May 2018 Report of Changes Pursuant to 10 CFR 50.59 and Summary of Commitment Changes HNP-18-042, Annual Environmental (Non-radiological) Operating Report2018-04-30030 April 2018 Annual Environmental (Non-radiological) Operating Report HNP-18-032, Annual Radiological Environmental Operating Report2018-04-25025 April 2018 Annual Radiological Environmental Operating Report HNP-18-031, Annual Radioactive Effluent Release Report2018-04-25025 April 2018 Annual Radioactive Effluent Release Report HNP-18-047, Relief Request I4R-18, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program, Fourth Ten-Year Interval, Non-Proprietary Version of Calculation2018-04-20020 April 2018 Relief Request I4R-18, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program, Fourth Ten-Year Interval, Non-Proprietary Version of Calculation HNP-18-045, Submittal of Relief Request I4R-18, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program, Fourth Ten-Year Interval2018-04-18018 April 2018 Submittal of Relief Request I4R-18, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program, Fourth Ten-Year Interval HNP-18-044, Cycle 22 Core Operating Limits Report, Revision O2018-04-16016 April 2018 Cycle 22 Core Operating Limits Report, Revision O HNP-18-039, Supplement to License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses2018-04-13013 April 2018 Supplement to License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses HNP-18-021, Annual Report in Accordance with Technical Specification 6.9.1.22018-02-19019 February 2018 Annual Report in Accordance with Technical Specification 6.9.1.2 HNP-18-020, Supplement to Response to Request for Additional Information Regarding License Amendment Request for Spent Fuel Storage Pool Criticality Analyses2018-02-16016 February 2018 Supplement to Response to Request for Additional Information Regarding License Amendment Request for Spent Fuel Storage Pool Criticality Analyses HNP-18-019, Cycle 21 Core Operating Limits Report, Revision 12018-02-14014 February 2018 Cycle 21 Core Operating Limits Report, Revision 1 HNP-18-017, CFR 50.54(q) Evaluations2018-02-0505 February 2018 CFR 50.54(q) Evaluations HNP-18-001, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors.2018-02-0101 February 2018 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors. HNP-18-002, Response to Request for Additional Information Regarding a License Amendment Request Proposing Changes to Emergency Diesel Generator Technical Specifications Surveillance Requirements2018-01-22022 January 2018 Response to Request for Additional Information Regarding a License Amendment Request Proposing Changes to Emergency Diesel Generator Technical Specifications Surveillance Requirements HNP-18-003, Response to Request for Additional Information Regarding License Amendment Request for Spent Fuel Storage Pool Criticality Analyses2018-01-18018 January 2018 Response to Request for Additional Information Regarding License Amendment Request for Spent Fuel Storage Pool Criticality Analyses HNP-18-007, License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis - Supplement Regarding De Minimis Penetrations2018-01-11011 January 2018 License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis - Supplement Regarding De Minimis Penetrations HNP-18-006, Submittal of 14-Day Special Report for Accident Radiation Monitors2018-01-0404 January 2018 Submittal of 14-Day Special Report for Accident Radiation Monitors HNP-17-093, Supplement to License Amendment Request Proposing a New Set of Fission Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 32017-11-29029 November 2017 Supplement to License Amendment Request Proposing a New Set of Fission Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3 HNP-17-078, Response to Request for Additional Information Regarding a License Amendment Request Proposing Changes to Emergency Diesel Generator Technical Specifications Surveillance Requirements2017-11-27027 November 2017 Response to Request for Additional Information Regarding a License Amendment Request Proposing Changes to Emergency Diesel Generator Technical Specifications Surveillance Requirements HNP-17-082, Response to Request for Additional Information Regarding License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Limit Detailed In..2017-10-30030 October 2017 Response to Request for Additional Information Regarding License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Limit Detailed In.. HNP-17-084, Response to Request for Additional Information Regarding a License Amendment Request Proposing Changes to Emergency Diesel Generator Technical Specifications Surveillance Requirements2017-10-30030 October 2017 Response to Request for Additional Information Regarding a License Amendment Request Proposing Changes to Emergency Diesel Generator Technical Specifications Surveillance Requirements HNP-17-025, Fourth Interval Lnservice Inspection Plan, Third Interval Containment Lnservice Inspection Plan, and Fourth Interval Lnservice Inspection Pressure Test Plan2017-10-23023 October 2017 Fourth Interval Lnservice Inspection Plan, Third Interval Containment Lnservice Inspection Plan, and Fourth Interval Lnservice Inspection Pressure Test Plan HNP-17-072, License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis2017-10-19019 October 2017 License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis HNP-17-077, License Amendment Request Regarding Rod Control Movable Assemblies Technical Specifications2017-10-10010 October 2017 License Amendment Request Regarding Rod Control Movable Assemblies Technical Specifications HNP-17-076, Supplement to License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106, and Delete Duplicate Reporting Requirements.2017-10-0202 October 2017 Supplement to License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106, and Delete Duplicate Reporting Requirements. HNP-17-073, Supplemental Information for License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses2017-09-14014 September 2017 Supplemental Information for License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses HNP-17-062, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal2017-09-13013 September 2017 Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal HNP-17-061, Supplement to License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses2017-07-20020 July 2017 Supplement to License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses HNP-17-008, License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses2017-06-28028 June 2017 License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses HNP-17-003, License Amendment Request for Emergency Diesel Generator Surveillance Requirements Regarding Voltage and Frequency Limits and the Voltage Limit for Emergency Diesel Generator Load Rejection2017-06-0505 June 2017 License Amendment Request for Emergency Diesel Generator Surveillance Requirements Regarding Voltage and Frequency Limits and the Voltage Limit for Emergency Diesel Generator Load Rejection HNP-17-040, Snubber Program Plan2017-06-0101 June 2017 Snubber Program Plan HNP-17-051, 10 CFR 50.54(q) Evaluation2017-05-24024 May 2017 10 CFR 50.54(q) Evaluation HNP-17-050, Transmittal of 10 CFR 50.54(q) Evaluation for Revision 21 to PEP-250, Activation and Operation of the Joint Information Center2017-05-24024 May 2017 Transmittal of 10 CFR 50.54(q) Evaluation for Revision 21 to PEP-250, Activation and Operation of the Joint Information Center HNP-17-041, Response to Request for Additional Information Regarding License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106, and Delete2017-05-22022 May 2017 Response to Request for Additional Information Regarding License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106, and Delete Du HNP-17-033, License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3, Footnote 112017-05-22022 May 2017 License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3, Footnote 11 HNP-17-049, Transmittal of 10 CFR 50.54(q) Evaluation and Revision 26 to PEP-110, Emergency Classification and Protective Action Recommendations.2017-05-18018 May 2017 Transmittal of 10 CFR 50.54(q) Evaluation and Revision 26 to PEP-110, Emergency Classification and Protective Action Recommendations. HNP-17-047, 10 CFR 50.54(q) Evaluation2017-05-18018 May 2017 10 CFR 50.54(q) Evaluation HNP-17-048, Transmittal of 10 CFR 50.54(q) Evaluation and Revision 28 to PEP-230, Control Room Operations.2017-05-18018 May 2017 Transmittal of 10 CFR 50.54(q) Evaluation and Revision 28 to PEP-230, Control Room Operations. HNP-17-046, 10 CFR 50.54(q) Evaluation2017-05-18018 May 2017 10 CFR 50.54(q) Evaluation HNP-17-024, Annual Environmental (Nonradiological) Operating Report2017-04-28028 April 2017 Annual Environmental (Nonradiological) Operating Report HNP-17-023, Annual Radioactive Effluent Release Report2017-04-28028 April 2017 Annual Radioactive Effluent Release Report HNP-17-034, Response to Request for Additional Information Regarding License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106..2017-04-25025 April 2017 Response to Request for Additional Information Regarding License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106.. HNP-17-035, Request for Pilot Plant Status and Fee Waiver to Implement Tornado Missile Risk Evaluator2017-04-12012 April 2017 Request for Pilot Plant Status and Fee Waiver to Implement Tornado Missile Risk Evaluator HNP-17-045, 10 CFR 50.54(q) Evaluation of Change in Emergency Plan Implementation Procedure PEP-241, Revision 7, Technical Support Center (TSC) Emergency Ventilation System Operation2017-03-30030 March 2017 10 CFR 50.54(q) Evaluation of Change in Emergency Plan Implementation Procedure PEP-241, Revision 7, Technical Support Center (TSC) Emergency Ventilation System Operation HNP-17-014, Annual Report in Accordance with Technical Specifications, Section 6.9.1.22017-02-16016 February 2017 Annual Report in Accordance with Technical Specifications, Section 6.9.1.2 HNP-17-015, Summary of 10 CFR 50.54(q) Evaluation2017-02-15015 February 2017 Summary of 10 CFR 50.54(q) Evaluation 2018-09-17
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0ý, --4 an Progress Energy OCT 0 5 2007 SERIAL: HNP-07-139 10 CFR 54 U. S. Nuclear Regulatory Commission ATTENTION:
Document Control Desk Washington, DC 20555
Subject:
SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400 / LICENSE NO. NPF-63 IMPACT OF ERRORS IN THE SECPOP2000 COMPUTER CODE ON THE SEVERE ACCIDENT MITIGATION ALTERNATIVES, ANALYSIS FOR SHEARON HARRIS NUCLEAR POWER PLANT LICENSE RENEWAL
References:
- 1. Letter from Cornelius J. Gannon to the U. S. Nuclear Regulatory Commission (Serial: HNP-06-136), "Application for Renewal of Operating License," dated November 14, 2006 Ladies and Gentlemen:
On November 14, 2006, Carolina Power & Light Company, doing business as Progress Energy Carolinas, Inc., requested the renewal of the operating license for the Shearon Harris Nuclear Power Plant, Unit No. 1, also known as the Harris Nuclear Plant (HNP), to extend the term of its operating license an additional 20 years beyond the current expiration date.The application contained an analysis of Severe Accident Mitigation Alternatives (SAMAs)for the plant.The SAMA analysis was performed using standard computer codes, including SECPOP2000, which was written for the NRC by Sandia National Laboratory.
In mid-2007 three errors were discovered in the SECPOP2000 code. The errors resulted in changes to certain values reported in the SAMA analysis, but did not result in changes regarding cost-effectiveness of any SAMA. A discussion of the impacts of these errors is contained in the Enclosure to this letter.Progress Energy Carolinas, Inc. 4 / Harris Nuclear Plant P. 0. Box 165 New Hill, NC 27562 Document Control Desk HNP-07-139/
Page 2 Please refer any questions regarding this submittal to Mr. Roger Stewart, Supervisor
-License Renewal, at (843) 857-5375.I declare,, under penalty of perjury, that the foregoing is true and correct (Executed on OCT 05 2007 )Sincerely, Christopher L. Burton Director -Site Operations Harris Nuclear Plant CLB/jsk.
Enclosure:
Discussion of the Impact of Errors in the SECPOP2000 Computer Code on the Severe Accident Mitigation Alternatives Analysis for Shearon Harris Nuclear Power Plant License Renewal cc: Mr. P. B. O'Bryan (NRC Senior Resident Inspector, HNP)Ms. B. 0. Hall (Section Chief, N.C. DENR)Mr. M. L. Heath (NRC License Renewal Project Manager, HNP)Ms. M. G. Vaaler (NRC Project Manager, HNP)Dr. W. D. Travers.(NRC Regional Administrator, Region II)Mr. Samuel Hernandez (NRC Environmental Project Manager, HNP)
HNP-07-139 Enclosure Page 1 of 4 Discussion of the Impact of Errors in the SECPOP2000 Computer Code on the Severe Accident Mitigation Alternatives Analysis for Shearon Harris Nuclear Power Plant License Renewal In May 2007 Progress Energy was notified that an error ha d been discovered in the computer code SECPOP2000 (SECPOP), a program prepared for NRC by Sandia National Laboratories.
That error resulted in the format of the SECPOP output file, which was designed to be directly used as the input site file for MACCS2, being incompatible with MACCS2 input format specification for regional economic data. The error resulted in incorrect county agriculture and economic data values being input into MACCS2. The error affected the numerical results (but not conclusions) of the Shearon Harris Nuclear Plant (HNP) License Renewal Environmental Report Severe Accident Mitigation Alternatives (SAMA) analysis.Progress Energy contractors prepared an evaluation of the impact of the SECPOP error on the SAMA results entitled "SAMA Revision Regarding Incompatible SECPOP 2000 and MACCS2 File Formats." It concluded that "...corrections to the SECPOP input had a minimal impact on the averted cost-risk estimates and did not alter the conclusions for any of the Phase 2 SAMAs..." With regard to the effect on quantification (thus cost-effectiveness), the evaluation noted that although "net values" were affected by the correction, "...there were no changes to the conclusions for any of the SAMAs." In other words, none of the Phase 2 SAMAs became cost-effective as a result of the input correction.
In mid-July, Progress was notified of another SECPOP computer code- problem. The second problem related to the way SECPOP county regional economic database entries were coded, specifically the absence of most county "note" entries. Although this entry is not used in the analysis, its absence resulted in SECPOP reading every other affected county entry (for most of the counties).
This caused SECPOP to output county regional economic data for counties that shouldn't have been included in place of those that should have been.After correcting the SECPOP data base by including "notes" for each county and revising the site file input into MACCS2 (which incorporated both the corrected data base and corrected output format), Progress Energy contractors reran MACCS2. The table below shows the baseline risks after this revision, along with the corresponding risks from the original analysis and the previous revision.
With respect to both dose-risk and cost-risk, the revision 1 to revision 2 increases were both less than 1 percent. The revision 2 ("notes")
error, therefore, had almost no effect on the averted cost and no effect on the conclusions for the evaluated SAMAs.
HNP-07-139 Enclosure Page 2 .of 4 Baseline Risks for Harris LR ER SAMA as Affected by SECPOP Errors Revision Dose Risk Cost Risk ($/Ryr) Notes (person-rem/Ryr) 0 28.97 43,030 Original submittal 1 28.97 51,800 Corrects SECPOP format specification problem 2 29.18 52,060 Corrects SECPOP"notes" entry problem'+ revision 1 3 29.03 58,770 Corrects SECPOP county code numbering problem +revision 2 A third SECPOP problem was identified in August 2007. This error was the result of the way county census codes were numbered in the SECPOP data base. The SECPOP code assumed sequential numbering, but some code numbers were missing in the data base, as some counties were "erased" (merged with adjoining counties) between censuses.
These deleted counties caused the wrong counties to be selected by SECPOP for many sites. Progress Energy contractors determined that the HNP results were again affected.
A subsequently corrected data base, which added "null" counties corresponding to the missing codes, was used to evaluate the impact of this SECPOP error on the HNP SAMA results. As shown in the table above, after this correction (revision
- 3) the baseline dose-risk decreased from the previous revision (revision 2)by 0.5 percent and, the cost-risk increased by 13 percent. More than 99.5 percent of the $6,710 per reactor-year cost risk increase was from sequences RC-5 and RC-5C.After rerunning MACCS2, incorporating corrections to all three known SECPOP2000 problems, Progress Energy contractors determined the revised conditional dose and economic costs associated with each of the accident scenarios considered in the HNP SAMA analysis.
The Harris modified Maximum Averted Cost Risk (MACR) (accounts for external events) was then recalculated to ascertain the potential impact on the SAMA analysis.
The modified MACR based on the mean Probabilistic Risk Assessment (PRA) results increased from $3,510,000 to$3,988,000 (13.6 percent increase).
The 95th percentile PRA results sensitivity case was also recalculated and it was determined that the modified MACR increased from $5,265,000 to$5,982,000 (also a 13.6 percent increase).
The changes to the modified MACR estimates did not impact the Phase I screening of the existing SAMAs.In addition to its use as a Phase I screening tool, the MACR is also used to set the risk reduction worth (RRW) review threshold that is used to limit the depth of the importance list review. In this case, the increase in the MACR resulted in a reduction in the Core Damage frequency (CDF)
- 2 1INP-07-139 Enclosure Page 3 of 4 based RRW review threshold from 1.014 to about 1.013, which required the review of six events that were not addressed in the SAMA submittal.
All six of the events are directly related to other events that were reviewed as part of the original analysis or imply the importance of a function that. is already addressed by the existing SAMAs. No new SAMAs are required to address these events.Finally, the SECPOP errors also impacted the averted cost-risks that were calculated for each of the SAMAs. The following table provides a summary of the impact of using the corrected results in conjunction with the mean PRA results in the detailed cost-benefit calculations that were performed.
Results Summary for Correction of SECPOP2000 Errors 1 Through 3 (Mean PRA Results)SAMA ID Cost of Averted. Net Value Averted Net Value Change Implement-Cost- Risk (Base) Cost- Risk (Post SECPOP in Cost.ation (Base) .(Post Corrections)
Effective-SECPOP ness?Corrections)
SAMA 1 $1,000,000
$389,627 -$610,373
$390,555 -$609,445 No SAMA 2 $200,000 $53,062 -$146,938
$58,896 -$141,104 No SAMA 3 $565,000 $34,204 -$530,796
$34,116 -$530,884 No SAMA 4 $150,000 $62,238 -$87,762 $61,906 -$88,094 No SAMA 6 $150,000 $111,240 -$38,760 $111,118 .-$38,882.
No SAMA 7 $1,700,000
$81,860 -$1,618,140
$81,890 -$1,618,110 No SAMA 8 $300,000 $298,979 -$1,021 $299,047 -$953 No SAMA 9 $70,000 $93,614 $23,614 $94,486 $24,486 No SAMA 10 $50,000 $11,222 -$38,778 $10,680 -$39,320 No SAMA 11 $400,000 $8,604 -$391,396
$8,030 -$391,970 No SAMA 12 $275,000 $60,584 -$214,416
$61,364 -$213,636 No SAMA 13 $225,000 $111,148 -$113,852
$111,570 -$113,430 No SAMA 15 $250,000 $93,974 -$156,026
$97,734 -$152,266 No SAMA 16 $400,000 $6,048 -$393,952
$5,446 -$394,554 No SAMA 17 $500,000 $52,820 -$447,180
$59,800 -$440,200 No SAMA 18 $175,000 $35,886 -$139,114
$40,488 -$134,512 No SAMA 19 $50,000 .$9,384 -$40,616 $8,782 -$41,218 No SAMA 21 $3,350,000
$407,428 -$2,942,572
$408,120 -$2,941,880 No SAMA 22 $350,000 $65,813 -$284,188
$74,775 -$275,225 No As demonstrated in the table, the corrections to the SECPOP2000 input had a minimal impact on the averted cost-risk estimates and did not alter the conclusions for any of the Phase 2 SAMAs that are based on the mean PRA results.
HNP-07-139 Enclosure Page 4 of 4 In addition to the review of the mean PRA results estimates, it was necessary to examine how the 9 5 th percentile PRA results quantifications were impacted given that they were also used to identify potentially cost beneficial SAMAs. The following table provides a summary of the cost benefit calculations using the corrected SECPOP2000 input in conjunction with the 9 5 th percentile.PRA results. As with the mean PRA results, there were no changes to the conclusions for any of the SAMAs.Results Summary for Correction of SECPOP2000 Errors I Through 3 (9 5 th Percentile PRA Results)SAMA ID Cost of Averted Net Value Averted Net Value Change Implement-Cost- Risk (Base) Cost- Risk (Post SECPOP in Cost ation (Base) (Post Correction)
Effective-SECPOP ness?Correction)
SAMA 1 $1,000,000
$584,441 -$415,560
$585,833 -$414,168 No SAMA 2 $200,000 $79,593 -$120,407
$88,344 -$111,656 No SAMA 3 $565,000 $51,306 -$513,694
$51,174 -$513,826 No SAMA 4 $150,000 $93,357 -$56,643 $92,859 -$57,141 No SAMA 6 $150,000 $166,860 $16,860 $166,677 $16,677 No SAMA 7 $1,700,000
$122,790 -$1,577,210
$122,835 -$1,577,165 No SAMA 8 $300,000 $448,469 $148,469 $448,571 $148,571 No SAMA 9 $70,000 $140,421 $70,421 $141,729 $71,729 No SAMA 10 $50,000 $16,833 -$33,167 $16,020 -$33,980 No SAMA 11 $400,000 $12,906 -$387,094
$12,045 -$387,955 No SAMA 12 $275,000 $90,876 -$184,124
$92,046 -$182,954 No SAMA 13 $225,000 $166,722 -$58,278 $167,355 -$57,645 No SAMA 15 $250,000 $140,961 -$109,039
$146,601 -$103,399 No SAMA 16 $400,000 $9,072 -$390,928
$8,169 -$391,831 No SAMA 17 $500,000 $79,230 -$420,770
,$89,700 -$410,300 No SAMA 18 $175,000 $53,829 -$121,171
$60,732 -$114,268 No SAMA 19 $50,000 $14,076 -$35,924 $13,173 -$36,827 No SAMA 21 $3,350,000
$611,142 -$2,738,858
$612,180 -$2,737,820 No SAMA 22 $350,000 $98,719 -$251,281
$112,163 -$237,838 No