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Category:Emergency Preparedness-Emergency Plan Implementing Procedures
MONTHYEARML19246A3512019-09-0303 September 2019
Independent Spent Fuel Storage Installation, and Monticello - Offsite Nuclear Emergency Plan Revision
ML19014A0392019-01-14014 January 2019
Independent Spent Fuel Storage Installation, and Monticello, Offsite Nuclear Emergency Plan Revision
L-MT-17-001, Change to Emergency Plan Implementing Procedure2017-01-0404 January 2017
Change to Emergency Plan Implementing Procedure
L-MT-16-057, Revision to Emergency Plan2016-11-0101 November 2016
Revision to Emergency Plan
L-MT-16-011, Changes to the Emergency Plan, Including Revision 19 to Emergency Preparedness Training Program Description2016-02-25025 February 2016
Changes to the Emergency Plan, Including Revision 19 to Emergency Preparedness Training Program Description
ML14198A3982014-07-17017 July 2014
Revised Emergency Plan and Emergency Plan Implementing Procedures (Epips)
L-MT-04-029, Revisions to the Monticello Nuclear Generating Plant (MNGP) Emergency Plan Implementing Procedures2004-04-27027 April 2004
Revisions to the Monticello Nuclear Generating Plant (MNGP) Emergency Plan Implementing Procedures
ML0411403552004-04-15015 April 2004
Emergency Plan Implementing Procedures
ML0409900852004-04-0202 April 2004
Rev. 32 to Emergency Plan Implementing Procedure A.2-101, Classification of Emergencies.
L-MT-04-022, Emergency Plan, Revision 25 and Emergency Plan Implementing Procedure A.2-101, Revision 322004-04-0202 April 2004
Emergency Plan, Revision 25 and Emergency Plan Implementing Procedure A.2-101, Revision 32
L-MT-04-004, Emergency Plan Implementing Procedure A.2-201, Revision 12, On-Site Protective Action2004-02-0202 February 2004
Emergency Plan Implementing Procedure A.2-201, Revision 12, On-Site Protective Action
L-MT-03-095, Transmittal of Revised Emergency Plan Implementing Procedures for Monticello. Revisions Includes A.2-106, Revision 23, A.2-107, Revision 23, A.2-213, Revision 11, A.2-413, Revision 17, A.2-414, Revision 21, A.2-502, Revision 52003-12-22022 December 2003
Transmittal of Revised Emergency Plan Implementing Procedures for Monticello. Revisions Includes A.2-106, Revision 23, A.2-107, Revision 23, A.2-213, Revision 11, A.2-413, Revision 17, A.2-414, Revision 21, A.2-502, Revision 5
L-MT-03-073, Revisied Emergency Plan Implementing Procedures2003-10-17017 October 2003
Revisied Emergency Plan Implementing Procedures
L-MT-03-072, Revision 10 to A.2-807, Off-Site Dose Assessment and Protective Action Recommendations.2003-09-24024 September 2003
Revision 10 to A.2-807, Off-Site Dose Assessment and Protective Action Recommendations.
L-MT-03-069, to Emergency Plan Implementing Procedure A.5-30, Casualty Care at the Local Hospital2003-09-0909 September 2003
to Emergency Plan Implementing Procedure A.5-30, Casualty Care at the Local Hospital
L-MT-03-062, Emergency Plan Implementing Procedures for A.2-213, Rev. 10 and A.2-410, Rev. 142003-08-26026 August 2003
Emergency Plan Implementing Procedures for A.2-213, Rev. 10 and A.2-410, Rev. 14
L-MT-03-054, Emergency Plan Implementing Procedure A.5-200, Rev. 4, Contaminated Casualty Transport2003-07-30030 July 2003
Emergency Plan Implementing Procedure A.5-200, Rev. 4, Contaminated Casualty Transport
L-MT-03-049, Emergency Plan Implementing Procedure, Revision 5 to A.2-206, Working Control During Emergencies.2003-07-0101 July 2003
Emergency Plan Implementing Procedure, Revision 5 to A.2-206, Working Control During Emergencies.
L-MT-03-046, Emergency Plan Implementing Procedures, Revision 12 to A.2-3022003-06-13013 June 2003
Emergency Plan Implementing Procedures, Revision 12 to A.2-302
L-MT-03-032, Emergency Plan Implementing Procedures A.2-209, Revision 14, Responsibilities of Radiological Emergency & A.2-806, Revision 5, Radiation Protection Support in the Eof.2003-05-22022 May 2003
Emergency Plan Implementing Procedures A.2-209, Revision 14, Responsibilities of Radiological Emergency & A.2-806, Revision 5, Radiation Protection Support in the Eof.
L-MT-03-028, Emergency Plan Implementing Procedure A.2-101, Revision 30, and Emergency Plan2003-04-23023 April 2003
Emergency Plan Implementing Procedure A.2-101, Revision 30, and Emergency Plan
L-MT-03-026, Emergency Plan Implementing Procedures2003-04-14014 April 2003
Emergency Plan Implementing Procedures
L-MT-03-021, Emergency Plan Implementing Procedures2003-03-14014 March 2003
Emergency Plan Implementing Procedures
ML0300802772002-12-30030 December 2002
Emergency Plan Implementing Procedures
ML0233304672002-11-15015 November 2002
Emergency Plan Implementing Procedures
ML0229603582002-10-10010 October 2002
Transmittal of Revisions to Monticello Nuclear Generating Plant Emergency Plan Implementing Procedures. Procedures Include A.2-INDEX Revision 78) & A.2-410 (Revision 12)
ML0229104372002-10-0808 October 2002
Revision to Monticello Nuclear Generating Plant Emergency Plan Implementing Procedures
ML0228201392002-09-27027 September 2002
Emergency Plan Implementing Procedures (Epip), EPIP A.2-805, Revision 5, Technical Support in EOF
ML0228305292002-09-26026 September 2002
Offsite Nuclear Emergency Plan Implementing Procedures
ML0226801612002-09-10010 September 2002
Revision 13 to EPIPs A.2-301, Emergency Evacuation
ML0224001802002-08-21021 August 2002
DAEC Emergency Planning Department Procedure Entire EAL Basis Document (Table of Contents Rev) (Copy 91)
ML0222803542002-08-0808 August 2002
DAEC Emergency Planning Department Procedure Transmittal Acknowledgment Memo
ML0220405982002-07-10010 July 2002
Revisions to Emergency Plan Implementing Procedures
ML0217107252002-06-10010 June 2002
Emergency Plan Implementing Procedures
ML0208703312002-03-0707 March 2002
Revision 8 to EPIP A.2-401, Emergency Exposure Control.
ML0207200352002-02-22022 February 2002
Submittal of Revised Monticello Nuclear Generating Plant Emergency Plan Implementing Procedures A.2-210 (Rev 6), A.2-213 (Rev 8), A.2-406 (Rev 17), A.2-802 (Rev 4) & A.2-810 (Rev 2)
ML0205001792002-01-25025 January 2002
Emergency Plan Implementing Procedures, Revision 16 to A.2-102, Revision 15 to A.2-103 and Revision 77 to A.2-INDEX
2019-09-03
[Table view]
Category:Letter type:L
MONTHYEARL-MT-23-054, Subsequent License Renewal Application Supplement 82024-01-11011 January 2024
Subsequent License Renewal Application Supplement 8
L-MT-23-047, License Amendment Request: Revision to the MNGP Pressure Temperature Limits Report to Change the Neutron Fluence Methodology and Incorporate New Surveillance Capsule Data2023-12-29029 December 2023
License Amendment Request: Revision to the MNGP Pressure Temperature Limits Report to Change the Neutron Fluence Methodology and Incorporate New Surveillance Capsule Data
L-MT-23-056, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 Part 22023-12-18018 December 2023
Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 Part 2
L-MT-23-042, 2023 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462023-12-11011 December 2023
2023 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46
L-MT-23-052, Subsequent License Renewal Application Supplement 72023-11-30030 November 2023
Subsequent License Renewal Application Supplement 7
L-MT-23-051, Update to the Technical Specification Bases2023-11-28028 November 2023
Update to the Technical Specification Bases
L-MT-23-049, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 12023-11-21021 November 2023
Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1
L-MT-23-043, 10 CFR 50.55a(z)(1) Request Regarding OMN-17, Revision 1. VR-092023-11-13013 November 2023
10 CFR 50.55a(z)(1) Request Regarding OMN-17, Revision 1. VR-09
L-MT-23-038, License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.62023-11-10010 November 2023
License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.6
L-MT-23-046, Subsequent License Renewal Application Response to Request for Additional Information Round 2 - Set 12023-11-0909 November 2023
Subsequent License Renewal Application Response to Request for Additional Information Round 2 - Set 1
L-MT-23-041, Subsequent License Renewal Application Response to Request for Confirmation of Information Set 22023-10-0303 October 2023
Subsequent License Renewal Application Response to Request for Confirmation of Information Set 2
L-MT-23-037, Subsequent License Renewal Application Response to Request for Additional Information Set 32023-09-22022 September 2023
Subsequent License Renewal Application Response to Request for Additional Information Set 3
L-MT-23-036, Subsequent License Renewal Application Response to Request for Additional Information Set 2 and Supplement 62023-09-0505 September 2023
Subsequent License Renewal Application Response to Request for Additional Information Set 2 and Supplement 6
L-MT-23-035, Subsequent License Renewal Application Supplement 52023-08-28028 August 2023
Subsequent License Renewal Application Supplement 5
L-MT-23-034, Subsequent License Renewal Application Response to Request for Additional Information Set 12023-08-15015 August 2023
Subsequent License Renewal Application Response to Request for Additional Information Set 1
L-MT-23-028, 2023 Refueling Outage 90-Day Inservice Inspection (ISI) Summary Report2023-07-31031 July 2023
2023 Refueling Outage 90-Day Inservice Inspection (ISI) Summary Report
L-MT-23-032, 10 CFR 50.55a(z)(2) Request Regarding MO-2397, VR-112023-07-31031 July 2023
10 CFR 50.55a(z)(2) Request Regarding MO-2397, VR-11
L-MT-23-031, Subsequent License Renewal Application Supplement 4 and Responses to Request for Confirmation of Information - Set 12023-07-18018 July 2023
Subsequent License Renewal Application Supplement 4 and Responses to Request for Confirmation of Information - Set 1
L-MT-23-030, Subsequent License Renewal Application Supplement 32023-07-0404 July 2023
Subsequent License Renewal Application Supplement 3
L-MT-23-025, Subsequent License Renewal Application Supplement 22023-06-26026 June 2023
Subsequent License Renewal Application Supplement 2
L-MT-23-019, Submittal of 2022 Annual Radiological Environmental Operating Report2023-05-10010 May 2023
Submittal of 2022 Annual Radiological Environmental Operating Report
L-MT-23-020, Submittal of 2022 Annual Radioactive Effluent Release Report2023-05-10010 May 2023
Submittal of 2022 Annual Radioactive Effluent Release Report
L-MT-23-021, Core Operating Limits Report (COLR) for the Monticello Nuclear Generating Plant for Cycle 322023-05-0202 May 2023
Core Operating Limits Report (COLR) for the Monticello Nuclear Generating Plant for Cycle 32
L-MT-23-017, 2022 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP)2023-04-18018 April 2023
2022 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP)
L-MT-23-010, Subsequent License Renewal Application Supplement 12023-04-0303 April 2023
Subsequent License Renewal Application Supplement 1
L-MT-23-013, Core Operating Limits Report (COLR) for Cycle 31, Revision 32023-03-28028 March 2023
Core Operating Limits Report (COLR) for Cycle 31, Revision 3
L-MT-23-012, Core Operating Limits Report (COLR) for Monticello Nuclear Generating Plant Cycle 31, Revision 22023-03-17017 March 2023
Core Operating Limits Report (COLR) for Monticello Nuclear Generating Plant Cycle 31, Revision 2
L-MT-23-008, 10CFR50.55a Request to Use Later Edition of ASME Section XI for ISI Code of Record (RR-003)2023-02-0707 February 2023
10CFR50.55a Request to Use Later Edition of ASME Section XI for ISI Code of Record (RR-003)
L-MT-23-004, CFR 50.55a Request RR-001, Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI for the Monticello Third Interval Containment Inservice Inspection Program2023-01-23023 January 2023
CFR 50.55a Request RR-001, Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI for the Monticello Third Interval Containment Inservice Inspection Program
L-MT-23-005, Response to the NRC Request for Additional Information Regarding the 50.55a Request Pr 08, HPCI Pump Quarterly Testing (EPID Number L-2022-LLR-0088)2023-01-0606 January 2023
Response to the NRC Request for Additional Information Regarding the 50.55a Request Pr 08, HPCI Pump Quarterly Testing (EPID Number L-2022-LLR-0088)
L-MT-22-049, Industry Groundwater Protection Initiative Special Report2022-12-15015 December 2022
Industry Groundwater Protection Initiative Special Report
L-MT-22-052, L-MT-22-052 Monticello Nuclear Generating Plant 10 CFR 50.55a Request No. Pr 08, Request for HPCI Pump Quarterly Alternative2022-12-15015 December 2022
L-MT-22-052 Monticello Nuclear Generating Plant 10 CFR 50.55a Request No. Pr 08, Request for HPCI Pump Quarterly Alternative
L-MT-22-046, 2022 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462022-12-13013 December 2022
2022 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46
L-MT-22-048, Update to the Monticello Technical Specification Bases2022-11-28028 November 2022
Update to the Monticello Technical Specification Bases
L-MT-22-047, Withdrawal of Request for Relief from ASME OM Code for the Sixth Inservice Testing Interval2022-11-10010 November 2022
Withdrawal of Request for Relief from ASME OM Code for the Sixth Inservice Testing Interval
L-MT-22-045, Letter Submitting Post-Exam Package2022-11-0404 November 2022
Letter Submitting Post-Exam Package
L-MT-22-030, Sixth Interval Inservice Testing (1ST) Plan2022-09-0606 September 2022
Sixth Interval Inservice Testing (1ST) Plan
L-MT-22-037, Supplement to 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval, Alternative VR-10, Excess Flow Check Valve Testing Frequency2022-08-29029 August 2022
Supplement to 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval, Alternative VR-10, Excess Flow Check Valve Testing Frequency
L-MT-22-007, Response to Request for Additional Information for the Monticello Nuclear Generating Plant Alternative Request VR-08 (EPID: L-MT-22-007)2022-07-22022 July 2022
Response to Request for Additional Information for the Monticello Nuclear Generating Plant Alternative Request VR-08 (EPID: L-MT-22-007)
L-MT-22-026, Changes to the Emergency Plan2022-07-19019 July 2022
Changes to the Emergency Plan
L-MT-22-024, Response to a Request for Additional Information for the Monticello Nuclear Generating Plant Related to the Amendment to Adopt Advanced Framatome Methodologies2022-06-0606 June 2022
Response to a Request for Additional Information for the Monticello Nuclear Generating Plant Related to the Amendment to Adopt Advanced Framatome Methodologies
L-MT-22-022, Response to a Request for Additional Information: Monticello Alternative VR-10, Excess Flow Check Valve Testing Frequency2022-05-25025 May 2022
Response to a Request for Additional Information: Monticello Alternative VR-10, Excess Flow Check Valve Testing Frequency
L-MT-22-017, 2021 Annual Radiological Environmental Operating Report2022-05-11011 May 2022
2021 Annual Radiological Environmental Operating Report
L-MT-22-018, 2021 Annual Radioactive Effluent Release Report2022-05-11011 May 2022
2021 Annual Radioactive Effluent Release Report
L-MT-22-016, 2021 Annual Report of Individual Monitoring2022-04-28028 April 2022
2021 Annual Report of Individual Monitoring
L-MT-22-019, Withdrawal of Requests for Relief from ASME OM Code for the Sixth Inservice Testing Interval2022-04-18018 April 2022
Withdrawal of Requests for Relief from ASME OM Code for the Sixth Inservice Testing Interval
L-MT-22-010, License Amendment Request to Revise Technical Specification 3.6.1.8 Residual Heat Removal (RHR) Drywell Spray Header and Nozzle Surveillance Frequency2022-03-18018 March 2022
License Amendment Request to Revise Technical Specification 3.6.1.8 Residual Heat Removal (RHR) Drywell Spray Header and Nozzle Surveillance Frequency
L-MT-22-012, Special Report for the Bypass of the Offgas Treatment Storage System2022-03-15015 March 2022
Special Report for the Bypass of the Offgas Treatment Storage System
L-MT-22-008, 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval Alternative Related to Excess Flow Check Valve Testing Frequency (L-MT-22-008)2022-03-0707 March 2022
10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval Alternative Related to Excess Flow Check Valve Testing Frequency (L-MT-22-008)
L-MT-22-006, 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval OMN-26 (L-MT-22-006)2022-02-18018 February 2022
10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval OMN-26 (L-MT-22-006)
2024-01-11
[Table view] |
Text
2807 West County Road 75 Monticello, MN 55362 Xcel Energy RESPONSIBLE BY NATURE 800.895.4999 xcelenergy. com November 1, 2016 L-MT-16-057 10 CFR 50.54(q)(5) 10 CFR 72.44(f)
ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Monticello Nuclear Generating Plant Docket 50-263 Renewed Facility Operating License No. DPR-22 Change to the Monticello Nuclear Generating Plant (MNGP) Emergency Plan Pursuant to 10 CFR 50.54(q)(5) and 10 CFR 72.44(f), Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy, submits a summary of changes to a MNGP Emergency Plan Implementing Procedure (EPIP) as Enclosure 1. The new revision to the EPIP is provided in Enclosure 2. The EPIP changes have been reviewed and do not result in a reduction in the effectiveness of the Emergency Plan.
Summary of Commitments There are no new commitments and no revisions to existing commitments in this letter.
~~.
Peter A. Gardner Site Vice President, Monticello Nuclear Generating Plant Northern States Power Company- Minnesota Enclosures (2) cc: Emergency Response Coordinator, Region Ill, USNRC (with Enclosures)
Resident Inspector, MNGP, USNRC (with Enclosure 1)
Administrator, Region Ill, USNRC (w/o Enclosures)
Chief, Plant Support Branch, Division of Reactor Safety, Region Ill, USNRC (with Enclosure 1)
Director, Division of Spent Fuel Management, Office of Nuclear Material Safety and Safeguards (with Enclosure 1)
ENCLOSURE 1 Monticello Nuclear Generating Plant Summary of Changes -10 CFR 50.54(q)(5)
Description (Executive Summary)
A.2-405 (Release Rate Determinations) is being revised as described below:
Change (1)
Step 6.1.3 (which became 6.1.2 per the below Change 2), 6.2.2, 6.5.1 and 6.5.2 were revised to eliminate an outdated method of obtaining release rate by taking readings out in the field, or from a functional radiation monitor, and using calculations to obtain a uCi/sec value. The steps were updated to obtain a release rate by taking readings out in the field, or from a functional radiation monitor, and inputting them into*
the current Dose Assessment software, Unified RASCAL Interface (URI).
This is an aligning change that's necessary based on the implementation of URI that occurred in 2014. URI is Monticello Nuclear Generating Plant's (MNGP) current dose projection software in use to meet the requirement to have methods, systems and equipment for assessment of radioactive releases. The implementation of URI was evaluated as a change to the Emergency Plan per 10CFR 50.54(q) in 2014.
However, the previous evaluation did not include this particulw change to the A.2-405 Emergency Plan Implementing Procedure; Therefore, it will be evaluated further as a change to the emergency plan under this evaluation.
Change (2)
Reordered steps 6.1.2 and 6.1.3 to allow for more effective flow of actions while determining Reactor Building Vent (RBV) Release Rate. Step 6.1.3 is a conditional step that is more efficient to perform before considering step 6.1.2, which is also a conditional step. This change is editorial in nature and there is no change of intent. Therefore, it does not require further review.
Change (3)
Deleted Figures 7.1 (RBV Exhaust Conversion Factor Table) and 7.2 (Stack Exhaust Conversion Factor Table) and the explanation of how the conversion factor in steps 6.5.1 and 6.5.2 were derived, within section 4.0. These conversion tables and explanation are no longer needed, based on the above removal of the outdated calculations in steps 6.1.3 (which became 6.1.2 per Change 1), 6.2.2, 6.5.1 and 6.5.2. This change is editorial in nature and there is no change of intent. Therefore, it does not require further review.
Change (1)
==
Description:==
A change that occurred in 2014 updated the site's dose assessment software to URI. The implementation of URI was evaluated under 10CFR 50.54(q) evaluation number MT-2014-212 and was determined to be an improved method of obtaining assessment data lAW the existing dose assessment requirements and capabilities contained in the MNGP Emergency Plan.
As part of this change, however, A.2-405 should have been updated to reflect the different input values that URI requires. A dose assessment software that was used prior to URI (Midas) required a release rate value in uCi/sec in order to provide a dose assessment. Therefore, A.2-405 was written to provide the user with manual calculations (if rad monitors are non-functional) that would yield a uCi/sec release rate value from manually obtained dose rate readings for input into Midas. The current URI software only requires a contact Page 1 of 2
dose rate value of mrem/hr or rem/hr (if rad monitors are non-functional) as input to calculate the dose assessment. It's no longer necessary to convert the reading into a uCi/sec value using flow rate, etc. In addition, URI includes the release rate as part of the dose assessment, for use if needed.
Doc ID or (Procedure Number) I Revision Number: A.2-405 I 15 Document
Title:
Release Rate Determinations Licensing/Basis Affected:
- 10 CFR Appendix E to Part 50
- Implementation of URI complies with the commitments made to the NRC in letters L-MT-13-052 and L-XE-13-014 for having multi-source dose assessment capability.
Evaluation Determination Regulatory Compliance Basis:
This change aligns with the previous implementation URI back in 2014, evaluated under 10CFR 50.54(q) evaluation MT-2014-212. The new program made the release rate calculations contained in A.2-405 obsolete, based on the input values needed to enter into URI in order to run a dose assessment. This change supports the requirements of 10CFR 50.47(b)(9) which continue to be met.
Emergency Plan Effectiveness Basis:
The revised version of A.2-405 will correct inaccurate calculations that currently exist in the procedure, which has rendered it unable to be performed as written. The change will incorporate URI as a method of determining release rate, as needed, and provide a more efficient means to obtain a dose assessment from a contact reading, if radiation monitors are non-functional. No reduction in effectiveness of the site's Emergency Plan results from this change.
Page 2 of 2
ENCLOSURE2 Monticello Nuclear Generating Plant A.2-405, Release Rate Determinations, Revision 15 7 pages follow
MONTICELLO NUCLEAR GENERATING PLANT A.2-405 TITLE: RELEASE RATE DETERMINATIONS Revision 15 Page 1 of 7 IApproval: PCR 01523921 REFERENCE USE
- Procedure should be at the work location.
- Procedure segments may be performed from memory.
- Use the procedure to verify segments have been completed.
- Mark off steps within the segment before continuing.
MONTICELLO NUCLEAR GENERATING PLANT A.2-405 TITLE: RELEASE RATE DETERMINATIONS Revision 15 Page 2 of 7 EMERGENCY PLAN IMPLEMENTING PROCEDURE- TABLE OF CONTENTS SECTION PAGE 1.0 PURPOSE ........................................................................................................... 3 2.0 APPLICABILITY .................................................................................................. 3 3.0 ORGANIZATION AND RESPONSIBILITIES ....................................................... 3 4.0 DISCUSSION ...................................................................................................... 3 5.0 PRECAUTIONS ................................................................................................... 3 6.0 INSTRUCTIONS .................................................................................................. 4 6.1 Determining RBV Release Rate ............................................................... 4 6.2 Determining Stack Release Rate .............................................................. 5 6.3 Determining Discharge Canal Release Rate ............................................ 6 6.4 Determining Release Rate from Unmonitored Release ............................ 6 6.5 Determining Release Rate from Hard Pipe Vent ...................................... 6 7.0 FIGURES ............................................................................................................ 7 7.1 Summary of Significant Changes .............................................................. 7
MONTICELLO NUCLEAR GENERATING PLANT A.2-405 TITLE: RELEASE RATE DETERMINATIONS Revision 15 Page 3 of 7 1.0 PURPOSE The purpose of this procedure is to provide guidance and criteria for making release rate determinations for accidental releases from Monticello Nuclear Generating Plant.
2.0 APPLICABILITY 2.1 An unplanned release of radioactivity has occurred.
2.2 The REC/CSL has requested a determination of the release rate.
3.0 ORGANIZATION AND RESPONSIBILITIES 3.1 The Radiological Emergency Coordinator (REC) is responsible for:
3.1.1 Overall direction of the Radiation Protection and Chemistry Group activities.
3.1.2 Release rate determination lAW this procedure in the absence of the Chemistry Section Leader.
3.2 The Chemistry Section Leader (CSL) is responsible for:
3.2.1 Implementation of this procedure, including release rate determination(s) as required by the REC.
3.2.2 Coordination of chemistry group activities.
3.3 The Radiation Protection Technicians (Rad Prot Tech) are responsible for:
3.3.1 Radiation surveys or sampling lAW applicable procedures to assist in release rate determinations.
4.0 DISCUSSION This procedure is used in the event that the monitors are not available or operable, providing direction for obtaining representative samples.
5.0 PRECAUTIONS 5.1 Exposures of sampling and analysis personnel SHALL be in accordance with A.2-401 (EMERGENCY EXPOSURE CONTROL).
5.2 Exposures to all personnel due to sampling and analysis operations should be maintained as low as reasonably achievable. Techniques such as temporary shielding, remote handling and sample dilution prior to analysis should be considered to reduce exposure to personnel.
MONTICELLO NUCLEAR GENERATING PLANT A.2-405 TITLE: RELEASE RATE DETERMINATIONS Revision 15 Page 4 of 7 5.3 When actual or potential radiation levels so warrant, high range portable survey instruments and self-reading dosimeters should be provided to sampling personnel. Alarming dosimeters should also be considered.
5.4 Appropriate extremity dosimeters should be provided and worn when handling samples which themselves represent high level radiation sources.
5.5 Two-person teams should be used when possible.
6.0 INSTRUCTIONS 6.1 Determining RBV Release Rate 6.1.1 lEthe RBV effluent monitors are operable, THEN read RBV effluent monitor release rate in the Control Room (Panel C-257 and C-258),
OR read data from SPDS System, OR read data from Data Acquisition System.
6.1.2 lEthe RBV effluent monitors are inoperable, THEN:
A. Direct a Rad Prot Spec to take a direct dose rate reading from the outside of the plenum ducts on the north side of the Reactor Building. This is accomplished by:
- 1. Obtain an extended probe dose rate meter from Access Control.
- 2. Proceed to the roof of the Turbine Building via the Admin Building north staircase to the Admin Building roof, up the ladder on the east side of the Turbine Building.
- 3. Take a contact radiation reading on the enclosed ductwork on the north side of the Reactor Building.
- 4. Take three dose rate readings, on the east, middle, and west sides of the enclosure.
- 5. Use the highest dose rate reading.
B. Using the dose reading obtained above direct a Dose Projection Specialist to implement FP-EDCM-DP-01 (OFFSITE DOSE ASSESSMENT USING THE UNIFIED RASCAL INTERFACE) from the Emergency Dose Calculation Manual.
MONTICELLO NUCLEAR GENERATING PLANT A2-405 TITLE: RELEASE RATE DETERMINATIONS Revision 15 Page 5 of 7 6.1.3 lEthe RBV activity exceeds 10 )lCi/cc at any time during a release, THEN consider a manual purge of the RBV WRGM units when the activity decreases below 9 )lCi/cc:
A Set SUPV mode with key 64.
B. Set Ml-009 to 0001 (MON-0-0-9-ITEM-0-0-0-1-ENTER).
C. Press the PURGE button and wait for purge to complete
(-2 minutes).
D. Reset Ml-009 to 0000 (MON-0-0-9-ITEM-0-0-0-0-ENTER).
E. Press EFF button.
F. Set OPER mode and remove key 64.
6.2 Determining Stack Release Rate 6.2.1 lEthe Stack effluent monitors are operable, THEN read Stack effluent monitor release rate in the Control Room (Panel C-257 and C-258),
OR read data from SPDS system, OR read data from Data Acquisition System.
6.2.2 IF the Stack effluent monitors are inoperable, THEN A Direct a Rad Prot Spec to take a direct Dose Rate Reading from the Stack Pipe. This is accomplished by:
- 1. Obtain an extended probe dose rate meter from Access Control.
- 2. Proceed to the Stack.
- 3. Take a contact dose rate reading on the Stack pipe. Access to the pipe is from the platform on the second level of the Stack, through the lsokenetic Probe penetration on the south side of the block work that surrounds the Stack pipe.
B. Using the dose reading obtained above direct a Dose Projection Specialist to implement FP-EDCM-DP-01 (OFFSITE DOSE ASSESSMENT USING THE UNIFIED RASCAL INTERFACE) from the Emergency Dose Calculation Manual.
MONTICELLO NUCLEAR GENERATING PLANT A.2-405 TITLE: RELEASE RATE DETERMINATIONS Revision 15 Page 6 of 7 6.3 Determining Discharge Canal Release Rate 6.3.1 Sample and analyze Discharge Canal lAW A.2-410 (OUT-OF-PLANT SURVEYS).
6.3.2 Calculate release rate lAW EDCM-03 (Liquid Release to River Dose Calculation).
6.4 Determining Release Rate from Unmonitored Release NOTE: The location of the actual field dose rate is vital to the accuracy of the release rates determined by this procedure. A location near the site boundary should be considered when obtaining this reading. The greater the distance from the plant, the less the error will be in the release rate determination. The closer to the plant, the greater the likelihood that a significant error will be introduced.
6.4.1 Direct a Rad Prot Tech to obtain an outdoor gamma dose rate of the plume resulting from the unmonitored release. (This dose rate may be obtained from either the on-site out-of-plant survey teams or the off-site field teams).
6.4.2 Direct a Dose Projection Specialist to implement FP-EDCM-DP-01 (OFFSITE DOSE ASSESSMENT USING THE UNIFIED RASCAL INTERFACE) from the Emergency Dose Calculation Manual.
6.5 Determining Release Rate from Hard Pipe Vent 6.5.1 For potential Hard Pipe Vent releases, perform the following:
A. Obtain current Containment Monitor reading (Rem/hr).
B. Using the dose reading obtained above direct a Dose Projection Specialist to implement FP-EDCM-DP-01 (OFFSITE DOSE ASSESSMENT USING THE UNIFIED RASCAL INTERFACE) from the Emergency Dose Calculation Manual.
6.5.2 For a release which is occurring, perform the. following:
A. Obtain ARM-135 reading in mrem/hr or using a hand held dose rate meter obtain a contact does rate (mrem/hr) on the Hard Pipe Vent near the ARM-135 monitor.
B. Using the dose reading obtained above direct a Dose Projection Specialist to implement FP-EDCM-DP-01 (OFFSITE DOSE ASSESSMENT USING THE UNIFIED RASCAL INTERFACE) from the Emergency Dose Calculation Manual.
MONTICELLO NUCLEAR GENERATING PLANT A.2-405 TITLE: RELEASE RATE DETERMINATIONS Revision 15 Page 7 of 7 7.0 FIGURES FIGURE 7.1 Summary of Significant Changes Section Change and Reason for the Change 4.0 Deleted explanation of the conversion factors that were used to determine Hard Pipe Vent Release Rate based on new instruction to use URI/MUMs in place of manual calculation.
6.1.2 Revised instructions on determining RBV Release Rate when effluent monitors are inoperable to direct the use of URI/MUMs in place on manual calculation.
6.2.2 Revised instructions on determining Stack Release Rate when effluent monitors are inoperable to direct the use of URI/MUMs in place on manual calculation.
6.5.1' 6.5.2 Revised instructions on determining Hard Pipe Vent Release Rate to direct the use of URI/MUMs in place on manual calculation.
Figures 7.1, Deleted conversion factor tables that are no longer needed for 7.2 (old) manual calculations.
