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Category:Report
MONTHYEARL-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-22-154, Pressure and Temperature Limits Report Revision2022-07-0606 July 2022
Pressure and Temperature Limits Report Revision
L-22-054, Steam Generator Inspection Report- Fall 2021 Refueling Outage2022-02-10010 February 2022
Steam Generator Inspection Report- Fall 2021 Refueling Outage
IR 05000334/20210052021-09-0101 September 2021
Updated Inspection Plan for the Beaver Valley Power Station, Units 1 and 2 (Report 05000334/2021005 and 05000412/2021005)
ML21131A0242021-05-17017 May 2021
Review of Reactor Pressure Vessel Capsule Y Analysis Report
ML21055A0582021-03-10010 March 2021
Review of the Refueling Outage 21 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and F* Reports
L-21-063, Facility Id 04-13361, Unit 2 Emergency Diesel Generator Day Tanks2021-02-0101 February 2021
Facility Id 04-13361, Unit 2 Emergency Diesel Generator Day Tanks
ML21026A3372021-01-26026 January 2021
Steam Generator Inspection Report Revision - Spring 2020 Refueling Outage
L-20-257, Request for One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Pandemic2020-09-22022 September 2020
Request for One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Pandemic
ML21127A1652020-07-17017 July 2020
ODCM: Index, Matrix and History of ODCM Changes
L-21-135, ODCM: Liquid Effluents2020-07-17017 July 2020
ODCM: Liquid Effluents
ML21127A1482020-07-17017 July 2020
ODCM: Controls for RETS and REMP Programs
L-20-116, CFR 50.55a Request Number VRR6, Revision 0, Motor-Operated Valve Test Frequency2020-04-0101 April 2020
CFR 50.55a Request Number VRR6, Revision 0, Motor-Operated Valve Test Frequency
ML19280A0382019-10-22022 October 2019
Ti 2515-191 Summary of Findings
ML21127A1562019-07-17017 July 2019
ODCM: Gaseous Effluents
ML19051A1092019-02-20020 February 2019
LTR-SDA-18-054-NP, Revision 0 - Technical Justification to Support the Extended Volumetric Examination Interval for Beaver Valley Unit 2 Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds
L-19-053, Emergency Response Data System Data Point Library Update2019-02-20020 February 2019
Emergency Response Data System Data Point Library Update
L-18-037, Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2018-06-18018 June 2018
Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models
L-18-017, Request to Extend Enforcement Discretion Provided in Enforcement Guidance Memorandum 15-002 for Tornado-Generated Missile Protection Non-Conformances Identified in Response to Regulatory Issue Summary 2015-06, Tornado.2018-03-15015 March 2018
Request to Extend Enforcement Discretion Provided in Enforcement Guidance Memorandum 15-002 for Tornado-Generated Missile Protection Non-Conformances Identified in Response to Regulatory Issue Summary 2015-06, Tornado.
ML21127A1592018-01-22022 January 2018
ODCM: Radiological Environmental Monitoring Program
L-17-277, Pressure and Temperature Limits Reports, Revisions 8 and 92017-10-0404 October 2017
Pressure and Temperature Limits Reports, Revisions 8 and 9
L-17-259, Mitigating Strategies Assessment (MSA) for Flooding2017-09-20020 September 2017
Mitigating Strategies Assessment (MSA) for Flooding
ML17213A0162017-05-11011 May 2017
Enclosure a: Beaver Valley, Units 1, Seismic Probabilistic Risk Assessment in Response to 50.54(f) Letter with Regard to NTTF 2.1
ML17213A0172017-05-11011 May 2017
Enclosure B: Beaver Valley, Unit 2, Seismic Probabilistic Risk Assessment in Response to 50.54(0 Letter with Regard to NTTF 2.1
ML17024A0362016-12-31031 December 2016
Operating Data Report for 2016
ML16312A3112016-11-0707 November 2016
Spent Fuel Pool Evaluation Supplemental Report. Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force (Ntif) Review...
L-16-327, Technical Basis for Optimization or Elimination of Liquid Penetrant Exams for the Embedded Flaw Repair2016-10-31031 October 2016
Technical Basis for Optimization or Elimination of Liquid Penetrant Exams for the Embedded Flaw Repair
L-16-093, Report of Facility Changes, Tests and Experiments2016-06-0303 June 2016
Report of Facility Changes, Tests and Experiments
L-16-065, Transmittal of 180-Day Steam Generator Tube Inspection Report - Technical Specification 5.6.6.22016-04-0606 April 2016
Transmittal of 180-Day Steam Generator Tube Inspection Report - Technical Specification 5.6.6.2
L-16-006, Submittal of Annual Report Pursuant to 10 CFR 75.11, Location Information2016-01-20020 January 2016
Submittal of Annual Report Pursuant to 10 CFR 75.11, Location Information
L-15-386, Post Accident Monitoring Report Regarding Inoperability of One of the Source Range Nuclear Excore Instrumentation Channel for a Period in Excess of the 30-Day Restoration Time2016-01-0505 January 2016
Post Accident Monitoring Report Regarding Inoperability of One of the Source Range Nuclear Excore Instrumentation Channel for a Period in Excess of the 30-Day Restoration Time
L-15-337, Completion of Required Action by NRC Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events and NRC Order EA-12-051, Reliable Spent Fuel Pool..2015-12-21021 December 2015
Completion of Required Action by NRC Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events and NRC Order EA-12-051, Reliable Spent Fuel Pool..
ML16277A1142015-10-28028 October 2015
ERS-MPD-93-007, Rev. 11, BVPS-U1 Gaseous Radioactivity Monitor Emergency Action Levels.
ML15274A3072015-10-0505 October 2015
Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50 Section 50.54 Seismic Hazard Reevaluations for Recommendation 2.1of the Near-Term Task Force Review
L-15-187, Submittal of 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2015-09-16016 September 2015
Submittal of 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models
ML15132A4962015-05-22022 May 2015
Review of the 2014 Steam Generator Tube Inspection Report (TAC No. M4620)
ML16277A1222015-04-20020 April 2015
ERS-LMR-14-001, Rev. 1, Liquid Monitor Alert Emergency Action Level (EAL) Set Points.
ML15119A1042015-03-31031 March 2015
SG-CCOE-14-4-NP, Revision 1, Examination of Steam Generator Tubes Removed, Part 1 of 4
L-15-091, SG-CCOE-14-4-NP, Revision 1, Examination of Steam Generator Tubes Removed, Part 2 of 42015-03-31031 March 2015
SG-CCOE-14-4-NP, Revision 1, Examination of Steam Generator Tubes Removed, Part 2 of 4
ML21127A1582015-02-11011 February 2015
ODCM: Bases for ODCM Controls
ML16277A1152015-01-30030 January 2015
ERS-HHM-87-014, Rev. 8, Unit 1 / Unit 2 ODCM Gaseous Effluent Monitor Setpoints.
ML15027A2352015-01-28028 January 2015
Regulatory Audit in Support of the License Amendment Request to Implement a Risk-Informed, Performance-Based, Fire Protection Program (Tac Nos. MF3301 & MF3302)
L-14-401, First Energy Nuclear Operating Company (FENOC) Expedited Seismic Evaluation Process (ESEP) Reports Response to NRC Request for Information Pursuant to 10 CFR50.54(f) Regarding Recommendation.1 of the Near-Term Task Force (NTTF) Review of In2014-12-19019 December 2014
First Energy Nuclear Operating Company (FENOC) Expedited Seismic Evaluation Process (ESEP) Reports Response to NRC Request for Information Pursuant to 10 CFR50.54(f) Regarding Recommendation.1 of the Near-Term Task Force (NTTF) Review of In
L-14-352, Steam Generator Tube Inspection Report - Technical Specification 5.6.6.22014-11-0505 November 2014
Steam Generator Tube Inspection Report - Technical Specification 5.6.6.2
ML21127A1442014-10-0707 October 2014
ODCM: Information Related to 40 CFR 190
L-14-259, Firstenergy Nuclear Operating Company'S (Fenoc'S) Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2014-08-28028 August 2014
Firstenergy Nuclear Operating Company'S (Fenoc'S) Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)
ML14224A5772014-07-31031 July 2014
SG-SGMP-14-17, Revision 1, Beaver Valley, Unit 2, End-of-Cycle 17 Analysis and Prediction for End-of-Cycle 18 Voltage-Based Repair Criteria 90-Day Report.
ML14224A5762014-07-31031 July 2014
SG-CCOE-14-1, Revision 0, Generic Letter 95-05 Tube Intersection Burst Test, Leakage Test, and Morphology Conclusions.
ML14224A5752014-06-25025 June 2014
R17 Steam Generator F* (F Star) Report
ML14009A0892014-02-10010 February 2014
Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Daiichi Nuclear Power Plant Accident
2023-08-07
[Table view]
Category:Technical
MONTHYEARL-22-154, Pressure and Temperature Limits Report Revision2022-07-0606 July 2022
Pressure and Temperature Limits Report Revision
L-22-054, Steam Generator Inspection Report- Fall 2021 Refueling Outage2022-02-10010 February 2022
Steam Generator Inspection Report- Fall 2021 Refueling Outage
ML21026A3372021-01-26026 January 2021
Steam Generator Inspection Report Revision - Spring 2020 Refueling Outage
L-21-135, ODCM: Liquid Effluents2020-07-17017 July 2020
ODCM: Liquid Effluents
ML21127A1652020-07-17017 July 2020
ODCM: Index, Matrix and History of ODCM Changes
ML21127A1482020-07-17017 July 2020
ODCM: Controls for RETS and REMP Programs
L-20-116, CFR 50.55a Request Number VRR6, Revision 0, Motor-Operated Valve Test Frequency2020-04-0101 April 2020
CFR 50.55a Request Number VRR6, Revision 0, Motor-Operated Valve Test Frequency
ML21127A1562019-07-17017 July 2019
ODCM: Gaseous Effluents
ML19051A1092019-02-20020 February 2019
LTR-SDA-18-054-NP, Revision 0 - Technical Justification to Support the Extended Volumetric Examination Interval for Beaver Valley Unit 2 Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds
ML21127A1592018-01-22022 January 2018
ODCM: Radiological Environmental Monitoring Program
L-17-277, Pressure and Temperature Limits Reports, Revisions 8 and 92017-10-0404 October 2017
Pressure and Temperature Limits Reports, Revisions 8 and 9
L-17-259, Mitigating Strategies Assessment (MSA) for Flooding2017-09-20020 September 2017
Mitigating Strategies Assessment (MSA) for Flooding
ML17213A0172017-05-11011 May 2017
Enclosure B: Beaver Valley, Unit 2, Seismic Probabilistic Risk Assessment in Response to 50.54(0 Letter with Regard to NTTF 2.1
ML17213A0162017-05-11011 May 2017
Enclosure a: Beaver Valley, Units 1, Seismic Probabilistic Risk Assessment in Response to 50.54(f) Letter with Regard to NTTF 2.1
L-16-327, Technical Basis for Optimization or Elimination of Liquid Penetrant Exams for the Embedded Flaw Repair2016-10-31031 October 2016
Technical Basis for Optimization or Elimination of Liquid Penetrant Exams for the Embedded Flaw Repair
ML16277A1142015-10-28028 October 2015
ERS-MPD-93-007, Rev. 11, BVPS-U1 Gaseous Radioactivity Monitor Emergency Action Levels.
ML16277A1222015-04-20020 April 2015
ERS-LMR-14-001, Rev. 1, Liquid Monitor Alert Emergency Action Level (EAL) Set Points.
ML15119A1042015-03-31031 March 2015
SG-CCOE-14-4-NP, Revision 1, Examination of Steam Generator Tubes Removed, Part 1 of 4
L-15-091, SG-CCOE-14-4-NP, Revision 1, Examination of Steam Generator Tubes Removed, Part 2 of 42015-03-31031 March 2015
SG-CCOE-14-4-NP, Revision 1, Examination of Steam Generator Tubes Removed, Part 2 of 4
ML21127A1582015-02-11011 February 2015
ODCM: Bases for ODCM Controls
ML16277A1152015-01-30030 January 2015
ERS-HHM-87-014, Rev. 8, Unit 1 / Unit 2 ODCM Gaseous Effluent Monitor Setpoints.
ML21127A1442014-10-0707 October 2014
ODCM: Information Related to 40 CFR 190
ML14224A5772014-07-31031 July 2014
SG-SGMP-14-17, Revision 1, Beaver Valley, Unit 2, End-of-Cycle 17 Analysis and Prediction for End-of-Cycle 18 Voltage-Based Repair Criteria 90-Day Report.
ML14224A5762014-07-31031 July 2014
SG-CCOE-14-1, Revision 0, Generic Letter 95-05 Tube Intersection Burst Test, Leakage Test, and Morphology Conclusions.
ML14224A5752014-06-25025 June 2014
R17 Steam Generator F* (F Star) Report
ML13364A1662014-01-29029 January 2014
Interim Staff Evaluation Related to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies)
ML14029A0212014-01-28028 January 2014
Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Beaver Valley Power Station, Units 1 and 2, TAC Nos.: MF0841 and MF0842 (Revision 2)
ML14030A1352014-01-27027 January 2014
WCAP-17790-NP, Revision 1, PWR Vessel Internals Program Plan for Aging Management of Reactor Internals.
ML14030A1342014-01-27027 January 2014
WCAP-17789-NP, Rev. 1, PWR Vessel Internals Program Plan for Aging Management of Reactor Internals.
L-13-387, Firstenergy Nuclear Operating Company Beaver Valley Power Station Units 1 and 2, NFPA 805 Transition Report. Page 284 Through Page T-422013-11-30030 November 2013
Firstenergy Nuclear Operating Company Beaver Valley Power Station Units 1 and 2, NFPA 805 Transition Report. Page 284 Through Page T-42
ML14002A0902013-11-30030 November 2013
Firstenergy Nuclear Operating Company Beaver Valley Power Station Units 1 and 2, NFPA 805 Transition Report. Cover Through Page 283
ML13126A0422013-04-15015 April 2013
RTL A9.630F, 2012 Annual Environmental Operating Report, (Non-Radiological)
ML13126A0392013-04-12012 April 2013
RTL A9.690E, 2012 Radioactive Effluent Release Report and 2012 Annual Radiological Environmental Operating Report, Enclosure 1, Cover Through Enclosure 2, Attachment 3
ML13028A4712013-01-14014 January 2013
SG-SGMP-13-2, Rev. 1, Beaver Valley Unit 2, End-of-Cycle 16 Voltage-Based Repair Criteria 90-Day Report.
ML13008A0482012-10-31031 October 2012
Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix C, Area Walk-by Checklists, Sheet 79 of 123 Through End
ML13008A0472012-10-31031 October 2012
Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix C, Area Walk-by Checklists, Page C-1 Through Sheet 78 of 123
ML16277A1162012-04-26026 April 2012
ERS-ATL-93-021, Rev. 4, Process Alarm Setpoints for Liquid Effluent Monitors.
ML16277A1232012-04-26026 April 2012
ERS-ATL-93-021, Rev. 4, Process Alarm Setpoints for Liquid Effluent Monitors.
ML13151A0602011-09-30030 September 2011
Enclosure C, WCAP-16527-NP, Analysis of Capsule X from Firstenergy Nuclear Operating Company Beaver Valley Unit 2 Reactor Vessel Radiation Surveillance Program, Supplement 1, Revision 1, Dated September 2011
ML13151A0592011-09-30030 September 2011
Enclosure B, WCAP-15571, Analysis of Capsule Y from Beaver Valley, Unit 1 Reactor Vessel Radiation Surveillance Program, Supplement 1, Revision 2, Dated September 2011
ML16277A1242011-08-10010 August 2011
ERS-SFL-88-027, Rev. 3, Process Safety Limits, Alarm Setpoints and EAL Indicator Value for 2CHS-RQ101A/B.
ML16277A1172011-08-0909 August 2011
ERS-JTL-99-005, Rev. 3, Unit 1 Letdown Radiation Monitor (RM-1CH-101) Alarm Setpoint Calculation and Emergency Action Level (EAL) ERS-JTL-99-005 21 Value Determination.
ML16277A1272011-08-0707 August 2011
ERS-SMM-11-002, Containment Radiation Monitor Readings Following Clad Damage (FC2 Loss, FC7 Loss, RC2 Loss and CT2 Potential Loss).
ML16277A1182011-08-0707 August 2011
ERS-SMM-11-002, Containment Radiation Monitor Readings Following Clad Damage (FC2 Loss, FC7 Loss, RC2 Loss and CT2 Potential Loss).
L-11-024, Chapters 5 and 7 of Holtec Licensing Report, in Support of License Amendment Request for Unit 2 Spent Fuel Pool Rerack2011-02-18018 February 2011
Chapters 5 and 7 of Holtec Licensing Report, in Support of License Amendment Request for Unit 2 Spent Fuel Pool Rerack
ML1029404582010-10-18018 October 2010
Holtec Report No: HI-2084175, Licensing Report for Beaver Valley, Unit 2, Rerack.
ML0912102632009-04-0909 April 2009
HI-2084175, Revision 3, Holtec Licensing Report for Beaver Valley, Unit 2 Rerack, Enclosure C
ML0900203862008-12-30030 December 2008
WCAP-16144-NP, Revision 1, Structural Integrity Evaluation of Reactor Vessel Upper Head Penetrations to Support Continued Operation: Beaver Valley Unit 2
ML0829002092008-08-31031 August 2008
WCAP-16158-NP, Revision 0, Technical Basis for Repair Options for Reactor Vessel Head Penetration Nozzles and Attachment Welds: Beaver Valley Unit 2
ML0821900132008-08-0707 August 2008
Monthly Operating Reports Second Quarter 2008
2022-07-06
[Table view] |
Text
RTL#: A9.621B Beaver Valley Power Station Unit 1/2 1/2-0DC-2.04 ODCM: Information Related to 40 CFR 190 Document Owner Manager, Nuclear Environmental & Chemistry Revision Number 2 Level Of Use General Skill Reference Safety Related Procedure Yes Effective Date 10/07/14
Procedure Number:
Beaver Valley Power Station l/2-ODC-2.04
Title:
Unit Level Of Use:
1/2 General Skill Reference ODCM: Information Related to 40 CFR 190 Revision: Page Number.
2 2of6 TABLE OF CONTENTS 1.0 PURPOSE ......................................................................................................................................... 3 2.0 SCOPE .............................................................................................................................................. 3
3.0 REFERENCES
AND COMMITMENTS ......................................................................................... 3 3.1 References .............................................................................................................................. 3 3.2 Comm.itnlents ......................................................................................................................... 3 4.0 RECORDS AND FORMS ................................................................................................................ 4 4.1 Records ................................................................................................................................... 4 4.2 Forms ...................................................................................................................................... 4 5.0 PRECAUTIONS AND LIMITATIONS .......................................................................................... 4 6.0 ACCEPTANCE CRITERIA ............................................................................................................. 4 7.0 PREREQUISIIBS ............................................................................................................................ 5 8.0 PROCEDURE ................................................................................................................................... 5 8.1 Information Related To 40 CFR 190 ...................................................................................... 5 8.2 Inside The Site Boundary Radiation Doses ............................................................................ 6
Proccdurc Number:
Beaver Valley Power Station l/2-0DC-2.04 T"rtlc: Unit Level OfUae:
1/2 u General Skill Reference ODCM: Information Related to 40 CFR 190 Rcviaion: Page Number:
2 3 of6 1.0 PURPOSE 1.1 This procedure provides the steps to be taken when the Total Dose of ODCM Control 4.11.4.1 exceeds twice the limit of any of the ODCM Controls specifying an Offsite Dose Limit.(3.1.2) 1.1.1 Prior to issuance of this procedure, these items were located in Section 4 of the old ODCM. 1 2.0 SCOPE 2.1 This procedure is applicable to all station personnel that are qualified to perform activities as described and referenced in this procedure.
3.0 REFERENCES
AND COMMITMENTS 3.1 References 3.1.1 40 CFRPart 190 3.1.2 l/2-0DC-3.03, ODCM: Controls for RETS and REMP Programs 3.1.3 l/2-ADM-1640, Control of the Offsite Dose Calculation Manual I
3.1.4 l/2-ADM-0100, Procedure Writer's Guide 3.1.5 l/2-ADM-0101, Review and Approval of Documents 3.1.6 CR 05-01169, Chemistry Action Plan for Transition ofRETS, REMP and ODCM.
CA-18, Revise procedure l/2-ODC-2.04 to change document owner from Manager, Radiation Protection to Manager, Nuclear Environmental & qiemistry.
0 3.1.7 10 CFR 72.104, Criteria for Radioactive Materials in Effluents and Direct Radiation from an ISFSI or MRS.
3 .2 Commitments 3.2.1 10 CFR 20.405(c), Special Reports 3.2.2 NUREG-1301, Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors (Generic Letter 89-01, Supplement No. 1) '
Procedure Number.
Beaver Valley Power Station l/2-ODC-2.04
Title:
Unit Level Of Uac:
1/2 General Skill Reference ODCM: Information Related to 40 CFR 190 Revision: Page Number:
2 4 nf6 4.0 RECORDS AND FORMS 4.1 Records 4.1.1 Any calculation supporting ODCM changes shall be documented, as appropriate, by a retrievable document (e.g.; letter or calculation package) with an appropriate RTL number.
4.2 Forms 4.2.1 None 5.0 PRECAUTIONS AND LIMITATIONS 5.1 The Offsite Dose Limits used to show compliance to this procedure are as follows:
5.1.1 ODCM Control 3.11.2.a; Liquid Effluents: _:s 1.5 mrem/quarter Total Body or
_:s 5 mrem/quarter any Organ.
5.1.2 ODCM Control 3.11.2.b; Liquid Effluents: _:s 3 mrem/year Total Body or
< 10 mrem/year any Organ.
5.1.3 ODCM Control 3.11.2.2.a; Gas Effluent-Noble Gas: _:s 5 mrad/quarter Gamma, or
_:s 10 mrad/quarter Beta 5.1.4 ODCM Control 3.11.2.2.b; Gas Effluents-Noble Gas: _:s 10 mrad/year Gamma
_:s 20 mrad/year Beta 5.1.5 ODCM Control 3.112.3.a; Gas Effluents-Particulates & Iodines: :S 7.5 mrem/quarter any organ 5.1.6 ODCM Control 3.11.2.3.b; Gas Effluents-Particulates & Iodines: :S 15 mrem/year any organ 5.1.7 ODCM Control 3.11.4.1; All Fuel Cycle Sources: _:s 25 mrem/year Total Body or any Organ, except the thyroid, which is limited to _:s 75 mrem/year 6.0 ACCEPTANCE CRITERIA 6.1 Any changes to this procedure shall contain sufficient justification that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, 10 CFR 72.104 and Appendix I to 10 CFR 50, and not adversely impact the accuracy or reliability of effluent dose or setpoint calculation. (3.2.2) 6.1.1 All changes to this procedure shall be prepared in accordance with l/2-ADM-0100(3.1.4) and l/2-ADM-1640.C3-l.3) 6.1.2 All changes to this procedure shall be reviewed and approved in accordance with l/2-ADM-0101 (3.t.5) and l/2-ADM-1640.0* 13)
Procedure Number:
Beaver Valley Power Station l/2-0DC-2.04 Titlo: Unit Level OfUac:
1/2 General Skill Reference ODCM: Information Related to 40 CFR 190 Revision: Page Number:
2 5 of6 7.0 PREREQUISITES 7 .1 The user of this procedure shall be familiar with ODCM structure and content.
8.0 PROCEDURE 8.1 Information Related To 40 CFR 190 8 .1.1 CONTROL 3 .11.4.1 requires that when the calculated doses associated with the effluent releases exceed twice the limits ofODCM CONTROL 3.11.1.2.a, 3.11.1.2.b, 3.11.2.2.a, 3.11.2.2.b, 3.11.2.3.a, or 3.11.2.3.b, the following shall be performed:
8.1.1.1 Calculations shall be made including direct radiation contributions from the units (including outside storage tanks, the onsite Independent Spent Fuel Storage Installation (ISFSI), etc.) to determine whether the dose or dose commitment to any MEMBER OF THE PUBLIC from all facility releases of radioactivity and to radiation from uranium fuel cycle sources, which is considered to include the onsite Independent Spent Fuel Storage Installation (ISFSI), exceeds the limits of::;;
25 mrem to the total body or any organ, except the thyroid, which is limited to
- 75 mrem for a calendar year.
8.1.1.1.1 If any of these limits are exceeded, prepare and submit to the Commission within 30 days a Special Report pursuant to 10 CFR 20.405(c).<3.2.1) The following shall be included in the Special Report:
8.1.1.1.1.1 Define the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the limits of ODCM CONTROL 3.11.4.1.
8.1.1.1.1.2 Include the schedule for achieving conformance within the limits of ODCM CONTROL 3.11.4.1.
8.1.1.1.1.3 Include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, which is considered to include the onsite Independent Spent Fuel Storage Installation (ISFSI), including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report.
8.1.1.1.1.4 Describe levels of radiation and concentrations of radioactive material involved, and the cause of exposure levels or concentrations.
8.1.1.1.1.5 If the estimated dose(s) exceeds the limits of ODCM CONTROL 3.11.4.1, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, include a request for a variance in accordance with the provisions of 40 CFR Part 190.
Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.
Procedure Number. ii' Beaver Valley Power Station l/2-0DC-2.04
Title:
Unit Level OfUae:
1/2 General Skill Reference ODCM: Information Related to 40 CFR 190 Revision: Page Number:
2 6of6 8.2 Inside The Site Boundary Radiation Doses 8.2.1 In regards to assessment of radiation doses (from Radioactive Effluents) to MEMBERS OF THE PUBLIC due to their activities inside the site boundary, the following is provided:
8.2.1.1 A separate assessment of radiation doses from radioactive effluents to MEMBERS OF THE PUBLIC due to their activities inside the site boundary is generally not necessary because the exposure time for individuals not occupationally associated with the plant site is minimal in comparison to the exposure time considered for the dose calculation at or beyond the site boundary.
8.2.1.2 For reporting purposes, separate guidance for calculating radiation doses to a MEMBER OF THE PUBLIC inside the site boundary is not needed because the dose assessments for an offsite MEMBER OF THE PUBLIC is also assumed to be for a MEMBER OF THE PUBLIC conducting activities onsite.
8.2.1.2.1 This is verified by showing that the ground release x/Q dispersion parameter used for dose calculation at the site boundary (0.352 miles NW) is greater
_ than the xJQ dispersion parameter at the location where a MEMBER OF THE PUBLIC would most likely have the maximum exposure time (0-0.5 miles N and 0-0.5 miles NNW). A comparison of these x/Q dispersion parameters is as follows:
xiQ Used:ir Dale xiQ WmeanAssiiD'X"l x/QRdmn:es OooJJarioo MEMBFROF1HEPUBUC fu:m Wwld?vfo.ctl.ikdy Have~:Maxii:m.nn 12-00C.-202 Fxpa,ure Tore SireBcum.y ~~Site ~~Site SeeA~F 0352:mib; NW Boorrlny Bcumy 0-05mib;N 0-05 milesNNW 9.24E-5 seo'm' 233E-5 ~ 5.47E-5 seo'm' Toole224 l.03E4 seo'm' 2 76E-5 secln' 6.0lE-5 seo'm' Toole22-5 735E-5 ~ 244E-5seo'm' 557E-5 seo'm' TabJe22-7 9.24E-5 seo'm' 233B-5~ 5.47E-5 seo'm' Toole22-8 9.24E-5~ 233E-5 seo'm' 5.47E-5 seo'm' Table22-9 735E-5 seo'm' 244E-5~ 557E-5 seo'm' Table22-10
-END-