Letter Sequence Supplement |
---|
|
|
|
Similar Documents at Perry |
---|
Category:Letter type:L
MONTHYEARL-24-207, License Renewal Application for the Perry Nuclear Power Plant-Response to Request for Additional Information - Set 12024-09-16016 September 2024 License Renewal Application for the Perry Nuclear Power Plant-Response to Request for Additional Information - Set 1 L-24-201, Spent Fuel Storage Cask Registration2024-09-0909 September 2024 Spent Fuel Storage Cask Registration L-24-200, License Renewal Application for Revision to Supplement 4 for Editorial Corrections2024-09-0505 September 2024 License Renewal Application for Revision to Supplement 4 for Editorial Corrections L-24-188, Submittal of Quality Assurance Program Manual, Revision 302024-08-27027 August 2024 Submittal of Quality Assurance Program Manual, Revision 30 L-24-190, Spent Fuel Storage Cask Registration2024-08-26026 August 2024 Spent Fuel Storage Cask Registration L-24-186, Response to RAI for Exemption Request from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule2024-08-15015 August 2024 Response to RAI for Exemption Request from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule L-24-174, Response to Perry Nuclear Power Plant License Renewal Environmental Report Severe Accident Mitigation Alternatives 2nd Round Request for Additional Information2024-08-15015 August 2024 Response to Perry Nuclear Power Plant License Renewal Environmental Report Severe Accident Mitigation Alternatives 2nd Round Request for Additional Information L-24-178, License Renewal Application Revision O - Supplement 42024-08-0808 August 2024 License Renewal Application Revision O - Supplement 4 L-24-189, License Renewal Application for Revision O - Supplement 12024-08-0707 August 2024 License Renewal Application for Revision O - Supplement 1 L-24-171, Spent Fuel Storage Cask Registration2024-07-30030 July 2024 Spent Fuel Storage Cask Registration L-24-108, License Renewal Application, Revision 0 - Supplement 32024-07-24024 July 2024 License Renewal Application, Revision 0 - Supplement 3 L-24-168, Technical Specification Required Shutdown Due to Increase in RCS Unidentified Leakage2024-07-15015 July 2024 Technical Specification Required Shutdown Due to Increase in RCS Unidentified Leakage L-24-020, License Renewal Application for the Perry Nuclear Power Plant Revision 0, Supplement 22024-06-27027 June 2024 License Renewal Application for the Perry Nuclear Power Plant Revision 0, Supplement 2 L-24-155, Reactor Water Clean Up Leak Detection Loss of Safety Function2024-06-27027 June 2024 Reactor Water Clean Up Leak Detection Loss of Safety Function L-24-036, Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2024-06-27027 June 2024 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models L-24-140, Operation of the Residual Heat Removal Loops B and C Alternate Keep Fill Configuration Was Prohibited by Technical Specifications and Resulted in an Unanalyzed Condition2024-06-20020 June 2024 Operation of the Residual Heat Removal Loops B and C Alternate Keep Fill Configuration Was Prohibited by Technical Specifications and Resulted in an Unanalyzed Condition L-24-116, Response to License Renewal Environmental Report Severe Accident Mitigation Alternatives Requests for Additional Information and Request for Clarification2024-05-16016 May 2024 Response to License Renewal Environmental Report Severe Accident Mitigation Alternatives Requests for Additional Information and Request for Clarification L-24-085, Nudear Power Plant, Submittal of Emergency Plan, Revision 622024-05-0606 May 2024 Nudear Power Plant, Submittal of Emergency Plan, Revision 62 L-24-103, Response to NRC Regulatory Issue Summary 2024-01, Preparation & Scheduling of Operator Licensing Exams2024-05-0202 May 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation & Scheduling of Operator Licensing Exams L-24-096, Submittal of Annual Radiological Environmental Operating Report2024-04-22022 April 2024 Submittal of Annual Radiological Environmental Operating Report L-24-097, Submittal of 2023 Annual Radiological Effluent Release Report2024-04-22022 April 2024 Submittal of 2023 Annual Radiological Effluent Release Report L-24-066, Response to Request for Additional Information Regarding 10 CFR 50.55a Request Number VR-9, Feedwater Check Valve Exercising Test Frequency2024-04-15015 April 2024 Response to Request for Additional Information Regarding 10 CFR 50.55a Request Number VR-9, Feedwater Check Valve Exercising Test Frequency L-24-083, Response to License Renewal Environmental Report Requests for Additional Information and Request for Clarification2024-04-15015 April 2024 Response to License Renewal Environmental Report Requests for Additional Information and Request for Clarification L-24-057, Submittal of the Decommissioning Funding Status Report2024-03-28028 March 2024 Submittal of the Decommissioning Funding Status Report L-24-013, Annual Notification of Property Insurance Coverage2024-03-26026 March 2024 Annual Notification of Property Insurance Coverage L-24-076, Independent Spent Fuel Storage Installation - Supplemental Information for Request for Specific Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.2142024-03-22022 March 2024 Independent Spent Fuel Storage Installation - Supplemental Information for Request for Specific Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 L-24-053, Independent Spent Fuel Storage Installation, Request for Specific Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.2142024-02-27027 February 2024 Independent Spent Fuel Storage Installation, Request for Specific Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 L-23-264, Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule2024-02-23023 February 2024 Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule L-24-050, Retrospective Premium Guarantee2024-02-22022 February 2024 Retrospective Premium Guarantee L-23-207, License Amendment Request (LAR) for Adoption of TSTF-264-A Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2024-01-24024 January 2024 License Amendment Request (LAR) for Adoption of TSTF-264-A Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs L-24-017, 30-Day Voluntary Report in Accordance with Industry Groundwater Protection Initiative2024-01-24024 January 2024 30-Day Voluntary Report in Accordance with Industry Groundwater Protection Initiative L-23-171, CFR 50.55a Request Number VR-9. Revision 0, Feedwater Check Valve Exercising Test Frequency2023-12-0808 December 2023 CFR 50.55a Request Number VR-9. Revision 0, Feedwater Check Valve Exercising Test Frequency L-23-244, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0606 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation L-23-238, Mid-Cycle Revision to the Core Operating Limits Report for Operating Cycle 202023-11-10010 November 2023 Mid-Cycle Revision to the Core Operating Limits Report for Operating Cycle 20 L-23-052, Submittal of the Updated Safety Analysis Report, Revision 232023-10-27027 October 2023 Submittal of the Updated Safety Analysis Report, Revision 23 L-23-206, Ohio National Pollutant Discharge Elimination System (NPDES) Permit 3IB00016 MD2023-09-12012 September 2023 Ohio National Pollutant Discharge Elimination System (NPDES) Permit 3IB00016 MD L-23-205, Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-09-12012 September 2023 Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-23-172, Quality Assurance Program Manual2023-08-31031 August 2023 Quality Assurance Program Manual L-23-001, License Amendment Request to Remove the Table of Contents from the Technical Specifications2023-08-0707 August 2023 License Amendment Request to Remove the Table of Contents from the Technical Specifications L-23-188, Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-08-0707 August 2023 Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-23-174, 30-Day Voluntary Report in Accordance with Industry Groundwater Protection Initiative2023-07-19019 July 2023 30-Day Voluntary Report in Accordance with Industry Groundwater Protection Initiative L-23-146, License Renewal Application for the Perry Nuclear Power Plant2023-07-0303 July 2023 License Renewal Application for the Perry Nuclear Power Plant L-23-051, Plan, Nineteenth Inservice Inspection Summary Report2023-06-22022 June 2023 Plan, Nineteenth Inservice Inspection Summary Report L-23-050, 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2023-06-22022 June 2023 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models L-22-249, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A Revision 2, Change TS 3.8.1. AC Sources-Operating. to Clarify the Power Factor Requirements When Performing Diesel Gener2023-06-0505 June 2023 License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A Revision 2, Change TS 3.8.1. AC Sources-Operating. to Clarify the Power Factor Requirements When Performing Diesel Gener L-23-134, Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations2023-05-23023 May 2023 Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations L-23-065, Annual Financial Report2023-05-22022 May 2023 Annual Financial Report L-23-122, Annual Radiological Environmental Operating Report2023-04-26026 April 2023 Annual Radiological Environmental Operating Report L-23-121, Annual Radiological Effluent Release Report2023-04-26026 April 2023 Annual Radiological Effluent Release Report L-23-061, Submittal of the Decommissioning Funding Status Reports2023-03-31031 March 2023 Submittal of the Decommissioning Funding Status Reports 2024-09-09
[Table view] |
Text
FENOC' Perry Nuclear Power Plant
- . P.O. Box97 10 Center Rdad
- Perry, Ohio 44081 RrstEnergy Nuclear Operating Company Ernest J. Harkness 440-280-5382 Vice President Fax: 44<>-280-S029 February 27, 2014 L-14-090 10 CFR 50.90 ATTN: Document Control Desk U.S .. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Perry Nuclear Power Plant Docket No. 50-440, License No. NPF-58 Acceptance Review Supplemental Information for Alternative Accident Source Term Design Basis Accident Analysis Request for Licensing Action <TAC No. MF3197)
FirstEnergy Nuclear Operating Company submitted a request for licensing action (RLA) to the Nuclear Regulatory Commission (NRC) in a letter dated December 6, 2013 (Accession No. ML13343A013). The RLA requested NRC review of a full implementation of alternative accident source term design basis accident analyses, and an associated technical specification change. In a teleconference on February 11, 2014, the NRC staff identified supplemental information that would need to be provided to accept the submittal for further review. An attachment to this letter provides the information.
There are no regulatory commitments contained in this submittal. If there are any questions or if additional information is required, please contact Mr. Thomas A. Lentz, Manager- Fleet Licensing, at 330-315-6810.
I declare under penalty of perjury that the foregoing is true and correct. Executed on February dJ. 7 , 2014.
Sincerely~ !!*
<?F*~~~J-Ernest J. Harkness
Attachment:
Acceptance Review Supplemental Information for Alternative Accident Source Term Design Basis Accident Analysis Request for Licensing Action cc: NRC Region Ill Administrator NRC Resident Inspector NRC Project Manager State of Ohio (NRC Liaison)
Utility Radiological Safety Board
Attachment L-14-090 Acceptance Review Supplemental Information for Alternative Accident Source Term Design Basis Accident Analysis Request for Licensing Action Page 1of3 FirstEnergy Nuclear Operating Company (FENOC) submitted a request for licensing action (RLA) to the Nuclear Regulatory Commission (NRC) in a letter dated December 6, 2013 (Accession No. ML13343A013). The RLA requested NRC review of a full implementation of alternative.accident source term (AST) design basis accident analyses, and an associated technical specification change. In a teleconference on*
February 11, 2014, the NRC staff identified supplemental information that would need to be provided to accept the submittal for further review. The information needed is presented in bold text, followed by the response .
- FENOC is requested to provide the analysis/evaluation supporting_ a conclusion that:
- 1. The AST analyses performed, using GNF2 so ... rce term, are appropriate to apply to the existing licensing basis fuel bundle design (i.e.;GE-14),
Response
Of the design basis radiological consequence analyses submitted for NRC review, the loss of coolant accident (LOCA) and the control rod drop accident (CRDA) use a fuel fission product inventory as the source term. The main steam line break outside containment
- (MSLBOC) analysis use*s a reactor coolant source term based on Technical Specification specific activity limits rather than the fuel specific core source term.
- Analysis results indicate it is appropriate to apply the GNF2 accident source term while GE14 fuel remains in the core. The analyses support a determination of the impact on offsite and control room dose consequences due to the two different source terms -
Table 1 compares the dose consequences as a result of utilizing the current licensing basis (CLB) source term for GE14 (as clarified by Table 2) with those using the GNF2 source term; all analyses use the new methodology and assumptions used .in the RLA.
Table 1 I
Accident Current Licensing Basis Source Term GNF2 Source Term
_ _ ___.__ Total Effective Dose E uivalent, rem Total Effective Dose Equivalent, rem LOCAj~~~~~~~~-~-~-~~~~~~~
EAB I 21.1 21.2 *1 .
LPZ I 6.5 6.5 I CR I 2*.8 I. 2.8 I
--c~~~___J__. ____________________________________ J__________________. __________________________. ___J EAB I .0.0866 . 0.161 I
-** LPZ . J___ -.. *-----*- ***-----*-**-~:o~!?. . __________________________ J __________________ .. _____________~-~~~~ .. -- ***--* .. --*-*- _____ . . I
---~~_J 0.141 0.263 _______,. l!
Attachment L-14-090 Page 2 of 3 Based on the above, the two different source terms (CLB and GNF2) result in acceptably low dose consequences, and the GNF2 results bound the CLB results for offsite (exclusion area boundary (EAB) and low population zone (LPZ)) and for control room (CR) dose consequences. Therefore, it is appropriate to apply the GNF2 source term dose results to the existing licensing basis fuel bundle design while GE14 fuel remains in the core.
For information, the source term used in the current licensing basis LOCA dose analysis is based on the isotopic quantities provided in Table 2. As indicated in Table 2, certain isotopes in the CLB source term are not utilized in the above source term comparison.
The RADTRAD library is based on isotopes selected in WASH-1400 with the addition of six isotopes per NUREG/CR-4691, "MELCOR Accident Consequence Code System (MACCS)." NUREG/CR-4467, "Relative Importance of Individual Elements to Reactor Accident Consequences Assuming Equal Release Fractions," also did not include these isotopes in its-list of isotopes that could be important-for off-site dose consequence analyses in light water reactors. For the above two reasons, these isotopes were not -
included in the above LOCA source term comparison analysis. For the same reasons, those isotopes were also not included in the CRDA source term comparison analysis.
Table 2 Isotope (Ci/MWth) Isotope (Ci/MWth) Isotope -(Ci/MWth)
Kr83m* 3.23E+03 Ru106 1.83E+04 Cs134 8.10E+03 Kr85 4.16E+02 - Rh105 2.89E+04 Cs136 2.44E+03 Kr85m 6.70E+03 Sb127 3.05E+03 Cs137_ 4.64E+03 Kr87 1.27E+04 Sb129 8.97E+03 Ba137m* 4.40E+03 Kr88 1.79E+04 Te127 3.03E+03 Ba139 4.87E+04 Kr89* 2.17E+04 Te127m 4.10E+02 Ba140 4.70E+04 Rb86 7.81E+01 Te129 8.83E+03 La140 5.06E+04 Sr89 2.41E+04 Te129m 1.31 E+03 La141 4.44E+04 Sr90 3.33E+03 Te131m 3.99E+03 La142 4.27E+04 Sr91 3.05E+04 Te132 3.86E+04 Ce141 4.46E+04 Sr92 3.33E+04 1131 2.72E+04 Ce143 4.08E+04 Y90 3.44E+03 1132 3.92E+04 Ce144 3.70E+04 Y91 3.13E+04 1133 5.50E+04 Pr143 3.95E+04 Y92 3.35E+04 1134 6.02E+04 Nd147 1.80E+04 Y93 3.92E+04 1135 5.15E+04 Np239 5.68E+05 Zr95 4.43E+04 Xe131m* 3.05E+02 Pu238* 3.95E+01 Zr97 4.49E+04 Xe133m* 1.73E+03 Pu239 1.00E+01
Attachment L-14-090 Page 3 of 3 Isotope (Ci/MWth) Isotope (Ci/MWth) Isotope (Ci/MWth)
Nb95 4.46E+04 Xe133 5.28E+04 Pu240 1.25E+01 Mo99 5.14E+04 Xe135m* 1.09E+04 Pu241 2.16E+03 Tc99m 4.50E+04 Xe135 1.91E+04 Am241 2.19E+OO Ru103 4.34E+04 Xe137* 4.79E+04 Cm242 5.80E+02 Ru105 3.07E+04 Xe138* 4.48E+04 Cm244 3.13E+01 Ci/MWth =Curies/Megawatt-thermal
- Isotope is not included in the source term comparison.
- 2. The AST assumptions for the radiological consequences are bounding of both the analyzed and the current fuel bundle design.
Relative to the LOCA dose consequence analysis, the core source term is assumed to be released during the two-hour period between the initial blowdown and termination of the fuel radioactivity release (gap and early in-vessel. release phases). During these two phases, the AST evaluation model assumes that there is no emergency core cooling system (ECCS) flow to the reactor vessel. This assumption is very conservative as compared to the assumptions used to determine normal ECCS acceptance criteria such as fuel peak cladding temperature per 10CFR50 Appendix K, "ECCS evaluation models."
This conservative AST modeling* assumes lhat the entire core will overheat and become damaged. Regulatory Guide 1.183, "Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors," then specifies the fractions of the available radionuclides that are released due to this core wide damage. The results of these analyses bound the amount of damage that could occur during an actual LOCA as evaluated per 10 CFR 50 Appendix K (Appendix K evaluations verify that temperatures .
remain below the regulatory limit of 2200 degrees Fahrenheit) for both the GNF2 fuel and the currently licensed fuel bundle design.
For the CRDA, Global Nuclear Fuel (GNF) determined that approximately 1,200 GE14 and GNF2 fuel rods have the potential to fail. The FENOC AST analysis summary, included as Addendum 5 in the RLA, instead conservatively assumes that all the fuel rods in the 16 GNF2 bundles adjacent to the dropped control rod fail (equal to approximately 1,376 full length rods). This assumption that nearly 15 percent more fuel rods fail in a CRDA event shows that the PNPP AST assumptions for the CRDA are bounding for both the current bundle design and the GNF2 design. The CLB analysis supporting the above Table 1 CRDA results determined a "per rod" source term, then multiplied that by 1,376. As shown for the CRDA results provided in Table 1 above, a comparison of the dose consequences due to the two different source terms, both performed assuming 1,376 failed rods, showed that the resultant dose consequences are low and the GNF2 results bound the CLB results.