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Category:Letter
MONTHYEARL-24-226, License Renewal Application for the Perry Nuclear Power Plant Revision O - Response to Requests for Confirmatory Information (Rcls) - Set 12024-10-31031 October 2024 License Renewal Application for the Perry Nuclear Power Plant Revision O - Response to Requests for Confirmatory Information (Rcls) - Set 1 IR 05000440/20240032024-10-30030 October 2024 Integrated Inspection Report 05000440/2024003 and 07200069/2024001 ML24303A3282024-10-29029 October 2024 Information Request for the Cyber Security Baseline Inspection Identification to Perform Inspection L-24-179, License Renewal Application for the Perry Nuclear Power Plant Revision 0 - Supplement 52024-10-21021 October 2024 License Renewal Application for the Perry Nuclear Power Plant Revision 0 - Supplement 5 IR 05000334/20240112024-10-17017 October 2024 License Renewal Phase IV Inspection Report 05000334/2024011 ML24281A0662024-10-0404 October 2024 EN 57363 - MPR Associates, Inc. Report in Accordance with 10 CFR Part 21 on Incomplete Dedication of Contactors Supplied as Basic Components L-24-208, License Renewal Application for the Perry Nuclear Power Plant - Responses to Request for Additional Information - Round 1 (Set 2)2024-10-0202 October 2024 License Renewal Application for the Perry Nuclear Power Plant - Responses to Request for Additional Information - Round 1 (Set 2) IR 05000346/20244032024-09-27027 September 2024 Security Baseline Inspection Report 05000346/2024403 ML24269A0552024-09-25025 September 2024 Submittal of the Updated Final Safety Analysis Report, Revision 35 05000346/LER-2021-001-01, Emergency Diesel Generator Speed Switch Failure Due to Direct Current System Ground2024-09-19019 September 2024 Emergency Diesel Generator Speed Switch Failure Due to Direct Current System Ground ML24134A1522024-09-17017 September 2024 Exemption from the Requirements of 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule (EPID L-2024-LLE-0005) - Letter L-24-038, License Amendment Request to Remove the Expired One-Time Action for Valve Leak Repair in Technical Specification (TS) 3.5.2 and to Correct Core Operating Limits Rep Ort (COLR) References2024-09-17017 September 2024 License Amendment Request to Remove the Expired One-Time Action for Valve Leak Repair in Technical Specification (TS) 3.5.2 and to Correct Core Operating Limits Rep Ort (COLR) References L-24-015, Twenty-Ninth Refueling Outage Inservice Inspection Summary Report2024-09-17017 September 2024 Twenty-Ninth Refueling Outage Inservice Inspection Summary Report ML24260A1912024-09-16016 September 2024 Operator Licensing Examination Approval ML24260A2382024-09-16016 September 2024 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information L-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 ML24225A0512024-09-13013 September 2024 Issuance of Alternative Request VR-9, Revision 0, Associated with the Fourth 10-Year Inservice Testing Interval ML24256A0872024-09-11011 September 2024 Fws to NRC, Concurrence with Endangered Species Act Nlaa Determinations for Perry License Renewal ML24255A8032024-09-11011 September 2024 Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report L-24-201, Spent Fuel Storage Cask Registration2024-09-0909 September 2024 Spent Fuel Storage Cask Registration ML24166A0172024-09-0606 September 2024 Ltr. to Glenna Wallace, Chief, Eastern Shawnee Tribe of Oklahoma; Re., NOA of the Draft Site-Specific EIS and Finding of No Historic Properties Affected by Perry Plant Unit 1 Lr ML24250A0412024-09-0606 September 2024 Fws to NRC, Perry Nuclear Plant, Unit 1, License Renewal List of Threatened and Endangered Species That May Occur in Your Proposed Project Location or May Be Affected ML24247A0212024-09-0606 September 2024 NRC Request for Concurrence with Endangered Species Act Determinations for Perry License Renewal, Issuance of Draft Supplemental Environmental Impact Statement, and Opportunity for Public Comment (Consultation Code: 2024-0006782) ML24249A0762024-09-0606 September 2024 Letter to Douglas Lankford, Chief_ Re. NOA of the Draft Site-Specific EIS and Finding of No Historic Properties Affected by Perry Plant Unit 1 Lr ML24249A0752024-09-0606 September 2024 Letter to Charles Diebold, Chief_ Re. NOA of the Draft Site-Specific EIS and Finding of No Historic Properties Affected by Perry Plant Unit 1 Lr ML24249A0782024-09-0606 September 2024 Ltr. to Kenneth Meshigaud, Chairperson, _ Re., NOA of the Draft Site-Specific EIS and Finding of No Historic Properties Affected by Perry Plant Unit 1 Lr ML24249A0862024-09-0606 September 2024 Letter to Regina Gasco-Bentley, Chairperson_ Re. NOA of the Draft Site-Specific EIS and Finding of No Historic Properties Affected by Perry Plant Unit 1 Lr ML24249A0882024-09-0606 September 2024 Letter to Rickey Armstrong, President_ Re. NOA of the Draft Site-Specific EIS and Finding of No Historic Properties Affected by Perry Plant Unit 1 Lr ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification ML24249A1602024-09-0505 September 2024 Information Request to Support Upcoming Material Control and Accounting Inspection at Davis-Besse Nuclear Power Station 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 ML24228A1712024-09-0303 September 2024 Ltr to Brian Dickens, EPA-Perry Nuclear Power Plant Unit 1-Notice of Avail of the Draft Supp 61 to the GEIS for License Renew of Nuclear Plants ML24228A1702024-09-0303 September 2024 Ltr to Rod L. Penfield-Perry Nuclear Power Plant Unit 1-Notice of Avail of the Draft Supp 61 to the GEIS for License Renew of Nuclear Plants IR 05000334/20240052024-08-29029 August 2024 Updated Inspection Plan for Beaver Valley Power Station, Units 1 and 2 (Reports 05000334/2024005 and 05000412/2024005) L-24-188, Submittal of Quality Assurance Program Manual, Revision 302024-08-27027 August 2024 Submittal of Quality Assurance Program Manual, Revision 30 ML24240A1482024-08-27027 August 2024 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML24239A7782024-08-26026 August 2024 Aging Management Audit - Perry Unit 1 - License Renewal Application August 26 2024 L-24-190, Spent Fuel Storage Cask Registration2024-08-26026 August 2024 Spent Fuel Storage Cask Registration ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 IR 05000346/20240052024-08-22022 August 2024 Updated Inspection Plan for Davis-Besse Nuclear Power Station (Report 05000346/2024005) L-24-199, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-08-22022 August 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 IR 05000334/20244022024-08-22022 August 2024 Security Baseline Inspection Report 05000334/2024402 and 05000412/2024402 (Cover Letter Only) IR 05000440/20240052024-08-22022 August 2024 Updated Inspection Plan for Perry Nuclear Power Plant (Report 05000440/2024005) 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-24-186, 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 IR 05000440/20240022024-08-0808 August 2024 Integrated Inspection Report 05000440/2024002 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 IR 05000334/20240022024-08-0505 August 2024 Integrated Inspection Report 05000334/2024002 and 05000412/2024002 IR 05000346/20240022024-08-0101 August 2024 Integrated Inspection Report 05000346/2024002 2024-09-09
[Table view] Category:Safety Evaluation
MONTHYEARML24225A0512024-09-13013 September 2024 Issuance of Alternative Request VR-9, Revision 0, Associated with the Fourth 10-Year Inservice Testing Interval ML24193A2912024-07-16016 July 2024 Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule ML23353A0012024-02-21021 February 2024 – Issuance of Amendment No. 202 to Adopt TSTF-276, Revision 2, Revise DG Full Load Rejection Test ML23313A1352024-01-17017 January 2024 Authorization and Safety Evaluation for Alternative Request RP 5 for the Fifth 10 Year Interval Inservice Testing Program ML23292A2972023-11-17017 November 2023 Table of Contents LAR (L-2023-LLA-0111) ML23198A3592023-10-0202 October 2023 Issuance of Amendment Nos. 322 and 212 Analytical Methodology to the Core Operating Limits Report for a Full Spectrum Loss of Coolant Accident (EPID L-2022-LLA-0129) - Nonproprietary ML23237B4282023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Enclosure 2, Draft Conforming License Amendments ML23237B4302023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Enclosure 4, Safety Evaluation for Transfer of Licenses and Draft Conforming License Amendments (EPID L-2023-LLM-0000) (Public) ML23249A1842023-09-18018 September 2023 Authorization and Safety Evaluation for Alternative Request No. 2-TYP-4-RV-06 ML23172A2852023-08-23023 August 2023 Safety Evaluation Irradiated Fuel Management Plan and Preliminary Decommissioning Cost Estimate ML23188A0982023-07-17017 July 2023 – Correction to the Safety Evaluation Issued Related to Amendment Nos. 321 and 211 Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time ML23102A1472023-05-22022 May 2023 Issuance of Amendment Nos. 321 and 211 Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time ML23019A0032023-03-16016 March 2023 – Issuance of Amendment Nos. 320 and 210 Adoption of Technical Specifications Task Force (Tstf) Traveler Tstf-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML23062A5212023-03-0606 March 2023 – Issuance of Amendment No. 319 Revise Technical Specification (TS) 3.5.2, ECCS – Operating, Limiting Condition for Operation (LCO) 3.5.2, ML22284A1442023-02-0303 February 2023 Issuance of Amendment No. 200 Regarding the Revision of Methodology Used for Flood Hazard Analysis ML22348A1372023-01-0505 January 2023 Issuance of Amendment No. 199 to Adopt TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position ML22269A3582022-11-15015 November 2022 Issuance of Amendment No. 305 Revising the Emergency Plan ML22277A6012022-10-14014 October 2022 Issuance of Amendment No. 304 Revising the Design Basis for the Shield Building Containment Structure ML22277A8142022-10-0707 October 2022 Correction of Errors in Safety Evaluation Associated with License Amendment Nos. 315 and 205 Regarding Changes to the Emergency Preparedness Plan ML22252A2212022-09-30030 September 2022 Authorization and Safety Evaluation for Alternative Request IR-063 ML22210A0102022-09-16016 September 2022 Energy Harbor Fleet- Issuance of Amendments Regarding Adoption of TSTF 554, Revise Reactor Coolant Leakage Requirements ML22222A0862022-09-0101 September 2022 Issuance of Amendment Nos. 317 and 208 Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start and Bus Separation Instrumentation ML22235A7672022-09-0101 September 2022 Correction of Errors in Safety Evaluation Associated with License Amendment Nos. 315 and 205 Regarding Changes to the Emergency Preparedness Plan ML22187A2592022-07-12012 July 2022 Issuance of Relief Proposed Alternative Request Vr 12, Revision 0, Associated with the Fourth 10-Year Inservice Testing Interval ML22202A4642022-06-29029 June 2022 Emergency Plan Safety Evaluation ML22140A2092022-06-28028 June 2022 Issuance of Amendment No. 207 Correct TS 3.1.7 Change Made by TSTF-547 ML22136A1132022-06-21021 June 2022 Issuance of Relief Proposed Alternative Requests VR-10, Revision 0, and VR-11, Revision 0, Associated with the Fourth 10-Year Inservice Testing Interval (EPIDs L-2021-LLR-0096; L-2021-LLR-0097) ML22147A1492022-06-0202 June 2022 Relief Request RP-3 Regarding Fuel Oil Transfer Pump Testing ML22136A1092022-05-24024 May 2022 Proposed Alternative Request RP-2 Regarding the Inservice Testing of Certain Pumps ML22095A2352022-05-10010 May 2022 Issuance of Amendment Nos. 316 and 206 Revise Technical Specification 5.6.3, Core Operating Limits Report (COLR) ML21286A7822022-05-0606 May 2022 Issuance of Amendment Nos. 315 and 205 Regarding Changes to the Emergency Plan ML22118B0382022-05-0505 May 2022 Proposed Alternative Request RP-4 Regarding the Inservice Testing of High-Pressure Injection Pumps ML22077A1342022-05-0202 May 2022 Issuance of Amendment Nos. 314 and 204 Revise Technical Specifications to Adopt TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ML22096A3162022-04-12012 April 2022 Proposed Alternative Request RP-1 Regarding Digital Instrumentation for Inservice Testing ML22082A2532022-03-29029 March 2022 Correction Letter - Issuance of Authorization of Proposed Alternative to Use ASME OM Code Case OMN-27 ML22012A2972022-01-21021 January 2022 Proposed Alternative to Use ASME OM Code Case OMN-27 ML21322A2602022-01-10010 January 2022 Issuance of Amendment No. 197 Regarding the Adoption of TSTF-566, Revision 0, Revise Actions for Inoperable RHR Shutdown Cooling Subsystem, and TSTF-580, Revision 1, Provide Exception from Entering Mode 4 with No Oper ML21270A1122021-11-16016 November 2021 Issuance of Amendment No. 196 Regarding Changes to the Emergency Plan ML21271A0782021-11-0505 November 2021 Issuance of Amendment No. 195 Regarding the Adoption of TSTF-230, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling ML21197A0092021-11-0101 November 2021 Issuance of Amendment Nos. 313 and 203 Reactor Coolant System, Pressure and Temperature Limits Report ML21214A2752021-10-15015 October 2021 Issuance of Amendment Nos. 312 and 202 Atmospheric Dump Valves ML21158A2122021-07-12012 July 2021 Issuance of Amendment No. 194 Regarding the Adoption of TSTF-002, Relocate the 10 Year Sediment Cleaning of the Fuel Oil Storage Tank to Licensee Control ML21153A1762021-06-30030 June 2021 Issuance of Amendment No. 201 Revision of Technical Specifications Related to Steam Generator Tube Inspection, and Repair Methods ML21123A2172021-05-0505 May 2021 Issuance of Relief Requests Vr 4, Revision 0, Vr 6, Revision 0, and Vr 8, Revision 0, Associated with the Fourth 10-Year Inservice Testing Interval (EPIDs L 2021 Llr 0010, L 2021 Llr 0011, L 2021 Llr 0012 COVID-19 ML21123A2892021-05-0404 May 2021 Issuance of Relief Request Vr 7, Revision 0, Associated with the Fourth 10-Year Inservice Testing Interval ML21081A0702021-04-27027 April 2021 Issuance of Amendment No. 193 Regarding the Adoption of TSTF-500, DC Electrical Rewrite - Update to TSTF-360 ML21075A1132021-04-16016 April 2021 Issuance of Amendment Nos. 311, 200, and 302 to Incorporate the Applicable Standard Technical Specification 5.2.2, Unit Staff, Into the Technical Specifications ML21070A0002021-03-22022 March 2021 Issuance of Amendment 310, Revise Technical Specification 5.5.5.1, Unit 1 SG Program, to Defer Spring 2021 Refueling Outage Steam Generator Inspections to Fall 2022 Refueling Outage ML20346A0222021-03-10010 March 2021 Issuance of Amendment Nos. 309 and 199 to Change Technical Specifications to Implement New Surveillance Methods for the Heat Flux Hot Channel Factor ML21063A2532021-03-0505 March 2021 Issuance of Relief Request SR-2, Revision 0, from Certain Requirements of the ASME OM Code (EPID L-2021-LLR-0005 (COVID-19)) 2024-09-13
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Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 November 20, 2008 Mr. Joseph J. Hagan President and Chief Nuclear Officer FirstEnergy Nuclear Operating Company Mail Stop A-GO-19 76 South Main Street Akron, OH 44308
SUBJECT:
BEAVER VALLEY POWER STATION, UNIT NOS. 1 AND 2; DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO.1; AND PERRY NUCLEAR POWER PLANT, UNIT NO.1 - APPLICATION TO USE WEIGHTING FACTORS FOR EXTERNAL EXPOSURE. (TAC NOS. MD8286 THRU MD 8289)
Dear Mr. Hagan:
By the letter dated March 6, 2008, as supplemented by letter dated September 18, 2008, FirstEnergy Nuclear Operating Company (the licensee) requested approval by the Nuclear Regulatory Commission (NRC) for the use of the weighting factors listed in Table 1 of the American National Standard Institute HPS N13.41-1997, "Criteria for Performing Multiple Dosimetry," for external radiation exposures when demonstrating compliance with total effective dose equivalent, based on requirements in Title 10 of the Code of Federal Regulations, Part 20.
The licensee requested approval to use the weighting factors at Beaver Valley Power Station, Units 1 and 2, Davis-Besse Nuclear Power Station, Unit No.1, and Perry Nuclear Power Plant, Unit NO.1. ANSI/HPS N13.41-1997 was approved December 1996.
On the basis of its review, the NRC staff finds the licensee's request acceptable. The enclosed safety evaluation documents the findings. Please contact Christopher Gratton at (301) 415-1055, if you have any questions on this matter.
Y Sincer.eI , . /: ~ ;// }
f!lvru ~
Russell Gibbs, Chief Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-334, 50-412, 50-346, and 50-440
Enclosure:
Safety Evaluation cc: w/encl: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO APPROVAL TO USE EFFECTIVE DOSE EQUIVALENT WEIGHTING FACTORS FOR EXTERNAL RADIATION EXPOSURE FIRSTENERGY NUCLEAR OPERATING COMPANY BEAVER VALLEY POWER STATION. UNITS 1 AND 2 DAVIS-BESSE NUCLEAR POWER STATION. UNIT NO.1 PERRY NUCLEAR POWER PLANT, UNIT NO.1 DOCKET NOS. 50-334. 50-412. 50-346. AND 50-440
1.0 INTRODUCTION
By the letter dated March 6, 2008, as supplemented by letter dated September 18, 2008, FirstEnergy Nuclear Operating Company (the licensee) requested approval by the Nuclear Regulatory Commission (NRC) for the use of the weighting factors listed in Table 1 in the American National Standard Institute (ANSI) HPS N13.41-1997, "Criteria for Performing Multiple Dosimetry," for external radiation exposures when demonstrating compliance with total effective dose equivalent (TEDE), based on requirements in Title 10 of the Code of Federal Regulations (10 CFR), Part 20, for the Beaver Valley Power Station, Units 1 and 2, the Davis-Besse Nuclear Power Station, Unit No.1, and the Perry Nuclear Power Plant, Unit NO.1. ANSI/HPS 1\113.41-1997 was approved December 1996.
The licensee stated that accurate assessment of occupational exposure of workers from external sources of radiation in highly non-uniform radiation fields requires a method for assessing the effective dose equivalent (EDE) and that the use of the proposed weighting factors will improve the accuracy of the licensee's assessment of occupational exposure.
Therefore, the effect of granting this request would be to allow the licensee the option to control EDE using the weighted external exposure measurements in those cases where it is a more accurate predictor of the risk from occupational radiation exposure.
2.0 REGULATORY EVALUATION
Part 20 of 10 CFR defines EDE or HE as the sum of the products of the dose equivalent to each tissue (HT) and the weighting factors (WT) applicable to each of the body organs or tissues that are irradiated (HE = r T WT HT) ." Each tissue weighting factor is the proportion of the risk of stochastic effects resulting from the dose to that organ or tissue to the total risk of stochastic effects when the whole body is irradiated uniformly. The weighting factors are applicable to the organs and tissues whether the dose results from radiation sources internal or external to the body.
Enclosure
-2 For the purposes of implementing workplace controls, and due to the difference in dosimetry methods, 10 CFR Part 20 breaks EDE into two components, dose resulting from radioactive sources internal to the body, and dose resulting from sources external to the body. The doses from external and internal exposures are then summed to obtain the TEDE. Several dose limits (such as those in 20.1201 (a)(1)(i) and 20.1301 (a)) and other requirements in 10 CFR in Part 20 are based on TEDE.
As of February 15, 2008, 10 CFR 20.1003 defines TEDE as the "sum of the effective dose equivalent (for external exposures) and the committed EDE (for internal exposures)." The committed EDE is the sum of the products of the dose equivalents to each tissue, from radioactive material taken into the body, integrated over 50 years, and the weighting factor applicable to that tissue.
In most relatively uniform exposure situations, a single dosimeter, calibrated to measure deep dose equivalent (DOE), worn on the whole body, provides a reasonably accurate estimate of the EDE from external exposures (EDE ex) . If the body is not irradiated uniformly, a single dose measurement can not determine the dose to the various organs and tissues for an accurate determination of the EDEex* To insure a conservative TEDE determination, 10 CFR 20.1201 (c) requires that when external exposure is determined by measurement with an external monitoring device, the DOE, measured for the part of the body receiving the highest exposure, must be used in place of the EDEex, unless the EDEex is determined by a dosimetry method approved by the NRC.
Using DOE in place of EDEex can be overly conservative in extremely non-uniform irradiations (e.g., when only a small portion of the whole body is irradiated). As discussed in NRC Regulatory Issue Summaries 2002-06, 2003-04 and 2004-01, the NRC has approved several methods for determining EDEex, and has encouraged the use of EDE ex in place of DOE for demonstrating compliance with the TEDE requirements in 10 CFR Part 20.
3.0 TECHNICAL EVALUATION
The NRC staff has reviewed the technical approach for estimating EDEex provided in ANSI/HPS N13.41-1997. This multiple dosimetry method divides the whole body into seven separate compartments. Each compartment, or combined compartment (since the ANSI/HPS-N13.41 allows combining adjacent compartments), is monitored separately. The results of the dose measurement for each compartment are weighted with an associated "compartment factor." The resulting weighted doses are then summed to determine the EDE ex for the whole body.
The compartment factors are listed in Table 1 of the ANSI/HPS N13.41. The factor for each compartment was developed by summing the stochastic weighting factors given in 10 CFR Part 20 for all the organs located within that compartment. For each tissue that reside in more than one compartment (i.e., red bone marrow), the weighting factor was apportioned between the compartments based on the fraction of the total mass of the tissue residing in each, using the information in International Commission on Radiation Protection Publication 23.
-3 Fundamental to the ANSIIHPS N13.41 multiple dosimeter method of determining EDEex, are the assumptions that (1) the average dose to the tissues in each compartment can be reasonably measured (with one or more dosimeters), and (2) that the dose distribution across the compartment is sufficiently constant so that this average dose can be applied to each tissue in the compartment. The compartments defined in ANSI/HPS N13.41 are small enough so that under most exposure situations these assumptions are met and a single determination of DDE in each compartment is sufficient. However, this may not be the case in those unusual situations where a significant dose gradient exists across the compartment (particularly the thorax and abdomen compartments). In these cases, dosimeter placement in each compartment becomes critical to ensuring that the EDE ex is not underestimated.
To ensure that the estimates of EDE ex are conservative, the licensee has committed to measuring the dose to each compartment (and/or combined compartment) by locating the dosimeter, calibrated to DDE, at the highest exposed portion of that compartment. The dosimeter location for each compartment will be subject to the same criteria the licensee currently uses for demonstrating compliance with 10 CFR 20.1201 (c).
The licensee has stated that in uniform exposure situations, a single dosimeter placed between the wearer's head and waist, consistent with the licensee's current practice, will be used to monitor monitoring external exposure
4.0 CONCLUSION
The NRC staff concludes that the licensee's commitments to dose measurement using the multiple dosimetry method to determine EDE ex by applying the weighting factors listed in Table 1 of ANSI/HPS N13.41-1997, as discussed above in Section 3.0 of this report, is consistent with the ANSI/HPS standard and with the requirements of 10 CFR Part 20, and is therefore acceptable for the purposes of demonstrating compliance with the TEDE-based requirements in 10 CFR Part 20.
Principal Contributor: R. Pedersen, NRR Date: November 20, 2008
Mr. Joseph J. Hagan November 20,2008 President and Chief Nuclear Officer FirstEnergy Nuclear Operating Company Mail Stop A-GO-19 76 South Main Street Akron, OH 44308 SUB,JECT: BEAVER VALLEY POWER STATION, UNIT NOS. 1 AND 2; DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO.1; AND PERRY NUCLEAR POWER PLANT, UNIT NO.1 - APPLICATION TO USE WEIGHTING FACTORS FOR EXTERNAL EXPOSURE. (TAC NOS. MD8286 THRU MD 8289)
Dear Mr. Hagan:
By the letter dated March 6, 2008, as supplemented by letter dated September 18, 2008, FirstEnergy Nuclear Operating Company (the licensee) requested approval by the Nuclear Regulatory Commission (NRC) for the use of the weighting factors listed in Table 1 of the American National Standard Institute HPS N13.41-1997, "Criteria for Performing Multiple Dosimetry," for external radiation exposures when demonstrating compliance with total effective dose equivalent, based on requirements in Title 10 of the Code of Federal Regulations, Part 20.
The licensee requested approval to use the weighting factors at Beaver Valley Power Station, Units 1 and 2, Davis-Besse Nuclear Power Station, Unit No.1, and Perry Nuclear Power Plant, Unit No.1. ANSI/HPS 1\113.41-1997 was approved December 1996.
On the basis of its review, the NRC staff finds the licensee's request acceptable. The enclosed safety evaluation documents the findings. Please contact Christopher Gratton at (301) 415-1055, if you have any questions on this matter.
Sincerely, IRA!
Russell Gibbs, Chief Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-334, 50-412, 50-346, and 50-440
Enclosure:
Safety Evaluation cc w/encl: Distribution via Listserv DISTRIBUTION:
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