RA-13-019, Transmittal of Emergency Plan Implementing Procedures, EMG-NGGC-0002, Revisions 5 and 6, EMG-NGGC-0004, Revisions 3 and 4 and EMG-NGGC-0005, Revisions 3 and 4: Difference between revisions

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{{Adams
#REDIRECT [[RA-13-019, Annual Dose Report for 2012]]
| number = ML13248A131
| issue date = 08/23/2013
| title = Transmittal of Emergency Plan Implementing Procedures, EMG-NGGC-0002, Revisions 5 and 6, EMG-NGGC-0004, Revisions 3 and 4 and EMG-NGGC-0005, Revisions 3 and 4
| author name = Waldrep B
| author affiliation = Duke Energy Carolinas, LLC
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000261, 05000302, 05000324, 05000325, 05000400
| license number = DPR-023, DPR-062, DPR-071, DPR-072, NPF-063
| contact person =
| case reference number = RA-13-019, FOIA/PA-2015-0005
| document report number = EMG-NGGC-0002, Rev 5, EMG-NGGC-0002, Rev 6, EMG-NGGC-0004, Rev 3, EMG-NGGC-0004, Rev 4, EMG-NGGC-0005, Rev 3, EMG-NGGC-0005, Rev 4
| document type = Emergency Preparedness-Emergency Plan Implementing Procedures, Letter type:RA
| page count = 289
}}
 
=Text=
{{#Wiki_filter:Benjamin C. Waldrep DUKE            ,A~ft            DUKECharlotte,                                526 South Church Street NC 28202
`2 ENERGY.                                                                          MailingAddress:
Mail Code EC07H /P.O. Box 1006 Charlotte, NC 28201-1006 704-382-8162 704-382-4541 fax 10 CFR 50.4(b)(5)(iii) 10 CFR 50.54(q)(5) 10 CFR 50, Appendix E, Section V Serial: RA-13-019 August 23, 2013 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-325 AND 50-324 / RENEWED LICENSE NOS. DPR-71 AND DPR-62 CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT DOCKET NO. 50-302 / LICENSE NO. DPR-72 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400 / RENEWED LICENSE NO. NPF-63 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261 / RENEWED LICENSE NO. DPR-23
 
==SUBJECT:==
TRANSMITTAL OF EMERGENCY PLAN IMPLEMENTING PROCEDURES EMG-NGGC-0002, REVISIONS 5 AND 6, EMG-NGGC-0004, REVISIONS 3 AND 4 AND EMG-NGGC-0005, REVISIONS 3 AND 4 Ladies and Gentlemen:
In accordance with 10 CFR 50.4(b)(5)(iii), 10 CFR 50.54(q)(5) and 10 CFR 50, Appendix E, Section V, Duke Energy Progress, formerly known as Carolina Power & Light Company (CP&L) and Duke Energy Florida, formerly known as Florida Power Corporation (FPC) are transmitting revised fleet Emergency Plan Implementing Procedures, EMG-NGGC-0002, Off-site Dose Assessment, Revisions 5 and 6, EMG-NGGC-0004, Maintenance of the Emergency Response OrganizationNotification System, Revisions 3 and 4 and EMG-NGGC-0005, Activation of the Emergency Response OrganizationNotification System, Revisions 3 and 4. The effective date of EMG-NGGC-0002, Revision 5, EMG-NGGC-0004, Revision 3 and EMG-NGGC-0005, Revision 3 was July 24, 2013. The effective date of EMG-NGGC-0002, Revision 6, EMG-NGGC-0004, Revision 4 and EMG-NGGC-0005, Revision 4 was August 22, 2013. Both the July 24, 2013 and August 22, 2013 revisions have been evaluated in accordance with 10 CFR 50.54(q) and determined not to reduce the effectiveness of the Radiological Emergency Response Plans (Emergency Plans) for the facilities listed above and that the Plans, as changed, continue to meet the standards of 10 CFR 50.47(b) and the requirements of 10 CFR 50, Appendix E.
Enclosures Ia, lb and 1c providel0 CFR 50.54(q)(5) analysis summaries for the July 24, 2013 and August 22, 2013 revisions. Enclosures 2a, 2b, 2c, 2d, 2e and 2f provide copies of both the July 24, 2013 and August 22, 2013 revisions.
 
United States Nuclear Regulatory Commission RA-1 3-019 Page 2 No new commitments have been made in this submittal. If you have additional questions, please call Mike Austin at 980-373-4134.
Sincerely, Benjamin C. WaldN Vice President - Cd        Governance &
Operations Support
 
United States Nuclear Regulatory Commission RA-1 3-019 Page 3 c:      USNRC - Region I USNRC - Region II USNRC Resident Inspector - BSEP, Unit Nos. 1 and 2 USNRC Resident Inspector - CR3 USNRC Resident Inspector - SHNPP, Unit No. 1 USNRC Resident Inspector - HBRSEP, Unit No. 2 C. Gratton, NRR Project Manager - BSEP, Unit Nos. 1 and 2; CR3 A. Hon, NRR Project Manager - SHNPP, Unit No. 1 S. Lingam, NRR Project Manager - HBRSEP, Unit No. 2
 
United States Nuclear Regulatory Commission RA-13-019 Page 4 bc:    (w/o Enclosure)
Chris Nolan Julie Olivier Mike Austin Kent Crocker Tony Pilo Gregg Simmons Carl Bergstrom Dave Corlett Richard Hightower Lee Grzeck Daniel Westcott (w/ Enclosure)
Christine Caudell (For RNP Licensing/Nuclear Records Files)
Frieda Frando (For CR3 Licensing/Nuclear Records Files)
Mike Wallace (For HNP Licensing/Nuclear Records Files)
Bill Murray (For BNP Licensing/Nuclear Records Files)
File: (Corporate)
 
Enclosure la 10 CFR 50.54(q)(5) Analysis Summary for EMG-NGGC-0002, Rev. 5 and 6 Brunswick Steam Electric Plant, Unit Nos. I and 2 Docket Nos. 50-325 and 50-324 / Renewed License Nos. DPR-71 and DPR-62 Crystal River Unit 3 Nuclear Generating Plant Docket No. 50-302 / License No. DPR-72 Shearon Harris Nuclear Power Plant, Unit No. 1 Docket No. 50-400 1 Renewed License No. NPF-63 H. B. Robinson Steam Electric Plant, Unit No. 2 Docket No. 50-261 / Renewed License No. DPR-23
 
United States Nuclear Regulatory Commission RA-13-019, Enclosure la Page 1 of 1 10 CFR 50.54(q)(5) Analysis Summary for EMG-NGGC-0002, Rev. 5 and 6 In accordance with 10 CFR 50.54(q)(5), Duke Energy Progress and Duke Energy Florida are providing an analysis summary for the revised Fleet Emergency Plan Implementing Procedure EMG-NGGC-0002, Off-site Dose Assessment, Revisions 5 and 6. The analysis summary for changes associated with program elements, administrative changes, and editorial corrections is described below. Specific procedure changes associated with Revision 5 are included on page 87 of the attached document (Enclosure 2a) and changes associated with Revision 6 are included on page 88 of the attached document (Enclosure 2b).
EMG-NGGC-0002, Revision 5. Change Justifications (1) This revision removes directions in the fleet procedures to access the dose assessment program (RASCAL) as an editorial revision. By removing the software path to access RASCAL, this change could affect the timeliness of performing a Dose Projection, however, not beyond the times currently established in the Emergency Plan. This change continues to comply with planning standards, as described in 10 CFR 50.47(b) and NRC requirements, as described in 10 CFR 50, Appendix E.
EMG-NGGC-0002, Revision 6. Change Justifications (1) This revision adds clarification to Step 3.5.2 of Attachment 8. The step was changed from "SELECT mettower." to "SELECT mettower from the Windows Start Bar."
(2) This revision restores deleted steps from the previous revision to locate the dose assessment program RASCAL. Duke Energy is in the process of transitioning from the Windows XP operating system to Windows 7 operating system and will begin using the Duke Energy Applications Environment to access programs. As a result of this change, the procedural direction in the corporate fleet procedures to access RASCAL was removed from EMG-NGGC-0002 as an editorial revision. This revision restores the original instructions for Windows XP as well as adds instructions for the Windows 7 pathways to access RASCAL. This change continues to comply with planning standards, as described in 10 CFR 50.47(b) and NRC requirements, as described in 10 CFR 50, Appendix E.
Evaluation Conclusion The changes in Revisions 5 and 6 of EMG-NGGC-0002 do not reduce the effectiveness of the Emergency Plans for Brunswick Steam Electric Plant Unit Nos. I and 2, Crystal River Unit 3 Nuclear Generating Plant, Harris Nuclear Plant, Unit No. 1, or H.B. Robinson Steam Electric Plant Unit No. 2 and continue to meet NRC requirements, as described in 10 CFR 50.47(b) and 10 CFR 50, Appendix E.
These changes do not impact the current Emergency Action Level schemes.
 
Enclosure lb 10 CFR 50.54(q)(5) Analysis Summary for EMG-NGGC-0004, Rev. 3 and 4 Brunswick Steam Electric Plant, Unit Nos. 1 and 2 Docket Nos. 50-325 and 50-324 / Renewed License Nos. DPR-71 and DPR-62 Crystal River Unit 3 Nuclear Generating Plant Docket No. 50-302 / License No. DPR-72 Shearon Harris Nuclear Power Plant, Unit No. 1 Docket No. 50-400 / Renewed License No. NPF-63 H. B. Robinson Steam Electric Plant, Unit No. 2 Docket No. 50-261 / Renewed License No. DPR-23
 
United States Nuclear Regulatory Commission RA-13-019, Enclosure lb Page 1 of 1 10 CFR 50.54(q)(5) Analysis Summary for EMG-NGGC-0004, Rev. 3 and 4 In accordance with 10 CFR 50.54(q)(5), Duke Energy Progress and Duke Energy Florida are providing an analysis summary for the revised Fleet Emergency Plan Implementing Procedure EMG-NGGC-0004, Maintenance of the Emergency Response OrganizationNotification System, Revisions 3 and 4. The analysis summary for changes associated with program elements, administrative changes, and editorial corrections is described below. Specific procedure changes associated with Revision 3 are included on page 21 of the attached document (Enclosure 2c) and specific changes associated with Revision 4 are included on page 22 of the attached document (Enclosure 2d).
EMG-NGGC-0004, Revision 3. Change Justifications (1) This revision removes directions in the fleet procedure to access the Emergency Response Organization Notification System (EverBridge) as an editorial revision. This change continues to comply with planning standards, as described in 10 CFR 50.47(b) and NRC requirements, as described in 10 CFR 50, Appendix E.
EMG-NGGC-0004, Revision 4, Change Justifications (1) This revision restores deleted steps from the previous revision to locate the Emergency Response Organization Notification System (EverBridge). Duke Energy is in the process of transitioning from the Windows XP operating system to Windows 7 operating system and will begin using the Duke Energy Applications Environment to access programs. As a result of this change, the procedural direction in the corporate fleet procedures to access EverBridge was removed from EMG-NGGC-0004 as an editorial revision. Revision 4 of EMG-NGGC-0004 restores the original instructions for Windows XP as well as adds instructions for the Windows 7 pathways to access EverBridge. This change continues to comply with planning standards, as described in 10 CFR 50.47(b) and NRC requirements, as described in 10 CFR 50, Appendix E.
Evaluation Conclusion The changes included in Revisions 3 and 4 of EMG-NGGC-0004 do not reduce the effectiveness of the Emergency Plans for Brunswick Steam Electric Plant Unit Nos. 1 and 2, Crystal River Unit 3 Nuclear Generating Plant, Harris Nuclear Plant, Unit No. 1, or H.B. Robinson Steam Electric Plant Unit No. 2 and continue to meet NRC requirements, as described in 10 CFR 50.47(b) and 10 CFR 50, Appendix E.
These changes do not impact the current Emergency Action Level schemes.
 
Enclosure Ic 10 CFR 50.54(q)(5) Analysis Summary for EMG-NGGC-0005, Rev. 3 and 4 Brunswick Steam Electric Plant, Unit Nos. I and 2 Docket Nos. 50-325 and 50-324 / Renewed License Nos. DPR-71 and DPR-62 Crystal River Unit 3 Nuclear Generating Plant Docket No. 50-302 / License No. DPR-72 Shearon Harris Nuclear Power Plant, Unit No. 1 Docket No. 50-400 / Renewed License No. NPF-63 H. B. Robinson Steam Electric Plant, Unit No. 2 Docket No. 50-261 / Renewed License No. DPR-23
 
United States Nuclear Regulatory Commission RA-13-019, Enclosure 1c Page 1 of 1 10 CFR 50.54(q)(5) Analysis Summary for EMG-NGGC-0005, Rev. 3 and 4 In accordance with 10 CFR 50.54(q)(5), Duke Energy Progress and Duke Energy Florida are providing an analysis summary for the revised Fleet Emergency Plan Implementing Procedure EMG-NGGC-0005, Activation of the Emergency Response OrganizationNotification System, Revisions 3 and 4. The analysis summary for changes associated with program elements, administrative changes, and editorial corrections is described below. Specific procedure changes associated with Revision 3 are included on page 27 of the attached document (Enclosure 2e) and specific changes associated with Revision 4 are included on page 27 of the attached document (Enclosure 2f).
EMG-NGGC-0005, Revision 3. Change Justifications (1) This revision removes directions in the fleet procedures to access the Emergency Response Organization Notification System (EverBridge) as an editorial revision. This change continues to comply with planning standards, as described in 10 CFR 50.47(b) and NRC requirements, as described in 10 CFR 50, Appendix E.
EMG-NGGC-0005, Revision 4. Change Justifications (1) This revision restores deleted steps from the previous revision to locate the Emergency Response Organization Notification System (EverBridge). Duke Energy is in the process of transitioning from the Windows XP operating system to Windows 7 operating system and will begin using the Duke Energy Applications Environment to access programs. As a result of this change, the procedural direction in the corporate fleet procedures to access EverBridge was removed from EMG-NGGC-0005 as an editorial revision. Revision 4 of EMG-NGGC-0005 restores the original instructions for Windows XP as well as adds instructions for the Windows 7 pathways to access EverBridge. This change continues to comply with planning standards, as described in 10 CFR 50.47(b) and NRC requirements, as described in 10 CFR 50, Appendix E.
Evaluation Conclusion The changes included in Revisions 3 and 4 of EMG-NGGC-0005 do not reduce the effectiveness of the Emergency Plans for Brunswick Steam Electric Plant Unit Nos. 1 and 2, Crystal River Unit 3 Nuclear Generating Plant, Harris Nuclear Plant, Unit No. 1, or H.B. Robinson Steam Electric Plant Unit No. 2 and continue to meet NRC requirements, as described in 10 CFR 50.47(b) and 10 CFR 50, Appendix E.
These changes do not impact the current Emergency Action Level schemes.
 
Enclosure 2a EMG-NGGC-0002, Off-site Dose Assessment, Revision 5
* Progress Energy                                R Reference Use NUCLEAR GENERATION GROUP STANDARD PROCEDURE VOLUME 99 BOOK/PART 99 EMG-NGGC-0002 OFF-SITE DOSE ASSESSMENT REVISION 5 Nuclear
                            /i    I~ lGeneration
((  GGGroup I EMG-NGGC-0002                    Rev. 5        Page 1 of 87
 
TABLE OF CONTENTS SECTION                                                                                                                            PAGE 1.0    PURPO SE .................................................................................................................. 4
 
==2.0    REFERENCES==
....................................................................................................                4 3.0    DEFINITIO NS ....................................................................................................              5 4.0    RESPO NSIBILITIES ............................................................................................                10 5.0    PREREQ UISITES .................................................................................................              11 6.0    PRECAUTIO NS AND LIM ITATIO NS ..................................................................                              11 7.0    SPECIAL TO O LS AND EQ UIPM ENT ...................................................................                            13 8.0    ACCEPTANC E CRITERIA ..................................................................................                        13 9.0    INSTRUCTIO NS ...................................................................................................              13 9.1  RASCAL Program Startup ...............................................................................                      13 9.2  This Section Deleted ........................................................................................                13 9.3  Select RASCAL Model ......................................................................................                  14 9.4  Select Event Type .............................................................................................              14 9.5  Select Event Location ......................................................................................                14 9.6  Select Nuclear Power Plant Type Source Term ...............................................                                  15 9.7  Select Nuclear Power Plant Release Path ........................................................                            20 9.8  Select Spent Fuel Type Source Term ..............................................................                            30 9.9  Select the Spent Fuel Release Path ................................................................                          33 9.10 SELECT Meteorology ......................................................................................                    35 9.11 INPUT Meteorology ........................................................................................                    36 9.12 SELECT Calculate Doses ................................................................................                      38 9.13 REVIEW Detailed Results ................................................................................                      39 9.14 Dose Projection Results ..................................................................................                    39 9.15 Save the Case .................................................................................................              43 9.16 Field Measurem ents to Dose Model (FM Dose) ...............................................                                  44 9.17 Multiple Release Points ....................................................................................                  45 10.0    RECO RDS ...............................................................................................................      45 EMG-NGGC-0002                                                  Rev. 5                                                      Page 2 of 87
 
TABLE OF CONTENTS SECTION                                                                                                          PAGE ATTACHMENTS 1    RASCAL General Flowpath ..................................................................................      46 2    Source Term Type Selection Guide ....................................................................            47 3    Weather Report Symbol, Model Class, and Intensity ..........................................                    49 4    Multiple Release Point Calculation Sheet ...........................................................            50 5    Brunswick Unit 1 and 2 Specific Actions and Parameters .................................... 51 6    Crystal River Specific Actions and Parameters ...................................................                60 7    H.B. Robinson Specific Actions and Parameters .................................................                  70 8    Shearon Harris Specific Actions and Parameters ..............................................                    71
 
==SUMMARY==
OF CHANGES ............................................................................................      87 I EMG-NGGC-0002                                    Rev. 5                                                    Page 3 of 87
 
1.0  PURPOSE 1.1  The purpose of this procedure is to provide Nuclear Generation Group (NGG) guidance for performing offsite radiological dose assessments from the Technical Support Center or Emergency Operations Facility. This procedure is not for offsite dose assessment by on-shift Control Room Staff.
1.2  This procedure is to be used in conjunction with Radiological Assessment System for Consequence Analysis (RASCAL) Version 3.0.5 software during a declared plant emergency involving a release or potential release of airborne radioactive materials to the environment. This procedure should be used for all RASCAL Source Term Options except for Monitored Releases - Mixtures. For monitored releases, the use of RASCAL is described in site procedures as listed in References 2.2.7 through 2.2.10.
1.3  This procedure describes an adequate method for assessing actual or potential offsite consequences of a radiological emergency condition as delineated in 10CFR50.47(b)(9).
1.4  This procedure is an emergency plan implementing procedure. Any revisions must be carefully considered for emergency plan impact.
 
==2.0  REFERENCES==
 
2.1  Developmental 2.1.1 EPA 400 R-92-001, Manual of Protective Action Guides and Protective Actions For Nuclear Incidents 2.1.2 NUREG/BR-0150, Volume 1, Revision 4, RTM-96 Response Technical Manual 2.1.3 U.S. Department of Health, Education, and Welfare, Radiological Health Handbook, 1970 2.1.4 Crystal River NOCS 00387, Method for Transmitting and Radiological Data to the TSC and EOF 2.1.5 Crystal River NOCS 40188, Instructions for Accessing Meteorological and Radiological Data to the TSC and EOF 2.1.6 R-RP-11-01-F1F - Radiation Protection and Emergency Preparedness personnel have not effectively implemented actions to improve accuracy or timeliness of emergency plan dose projections (NCR 481263)
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2.2  Implementing 2.2.1 NUREG-1887, RASCAL 3.0.5: Description of Models and Methods 2.2.2 NUREG-1889, RASCAL 3.0.5 Workbook 2.2.3 Crystal River Nuclear Plant Final Safety Analysis Report (FSAR) 2.2.4 CR-3, Radiological Emergency Response Plan (RERP) 2.2.5 Harris Nuclear Plant FSAR Table 9.4.0-2 2.2.6 Crystal River Engineering Evaluation EEF-00-009, Revision 1 - Radiation Monitor Response Factors 2.2.7 EPRAD-03, H.B. Robinson Steam Electric Plant Dose Projections 2.2.8 PEP-344, HNP Offsite Dose Assessment Based on Monitored Releases 2.2.9 EM-204B, Offsite Dose Assessment During Radiological Emergencies for Monitored Releases - Mixtures (CR3) 2.2.10 OPEP-03.4.8, Brunswick Nuclear Plant Offsite Dose Estimates Based on Monitored Releases 2.2.11 CSP-NGGC-2505, Software Quality Assurance and Configuration Control of Business Computer Systems 3.0 DEFINITONS 3.1  Adverse Met Data The worst case meteorological conditions: G stability class and wind speed of 1.0 mph.
3.2  Committed Dose Equivalent Dose equivalent to organs or tissues of reference that will be received from an intake of radioactive material by an individual during the 50-year period following the intake.
3.3  Committed Effective Dose Equivalent Sum of the products of the weighting factors applicable to each of the body organs or tissues that are irradiated and the committed dose equivalent to these organs or tissues.
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3.0  DEFINITONS (continued) 3.4  Core Melt Deformation of fuel pellet configuration due to excessive core temperature releasing large quantities of gaseous and particulate fission products.
3.5  Decay Calculator The Decay Calculator (DecayCalc) computes radiological decay and daughter ingrowth. It computes the activity remaining after the decay time selected. It includes access to the RASCAL radionuclide database and has the ability to display decay chains as a table or as a graphic. DecayCalc is not linked to any other RASCAL module. Decay calculations are available within the STDose and FM Dose models when appropriate. The same decay data and decay calculation routines are used throughout RASCAL.
3.6  Deep Dose Equivalent External whole-body exposure at a tissue depth of 1 cm (1000 mg/cm 2 ).
3.7  Delta T Measurement of the difference in air temperature between two different elevations above ground level. The value provides a measure of the atmospheric stability.
3.8  Depletion Reduction of the concentration of the plume (i.e., deposition and dispersion).
3.9  Deposition Means of puff depletion that deposits particulate radioactive material on the ground.
3.10  Derived Intervention Level (DIL)
A value that corresponds to a health effect threshold or Protective Action Guideline (PAG). A DIL can be used to relate environmental measurements or laboratory analyses to the potential for health affects or the need for protective actions.
3.11 Dose Equivalent Product of the absorbed dose in rad, a quality factor related to the biological effectiveness of the radiation involved and any other modifying factors. Units are typically in rem.
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3.0  DEFINITONS (continued) 3.12 Early Phase The period at the beginning of a nuclear incident when immediate decisions for effective use of protective actions are required and must be based primarily on predictions of radiological conditions in the environment. This phase may last from hours to days. For the purposes of dose projections, it is assumed to last four (4) days.
3.13 Effective Dose Equivalent The sum of the products of the dose equivalent to each organ and a weighting factor, where the weighting factor is the ratio of the risk of mortality from delayed health effects arising from irradiation of a particular organ or tissue to the total risk of mortality from delayed health effects when the whole body is irradiated uniformly to the same dose. This unit in Rem is considered equivalent to the Deep Dose Equivalent for the purposes of dose projections because the external exposures are considered to be uniform across the whole body.
3.14  Field Measurement to Dose - (FMDose)
The FMDose model computes emergency worker limits and early-phase and intermediate-phase doses and derived intervention levels (DILs) from the analyses of field measurements. The results of the analysis of field measurements may be entered directly in FMDose. All results are presented as tables. The intermediate-phase DILs are also presented graphically. FM Dose includes access to the RASCAL radionuclide database and has the ability to display decay chains as a table or as a graphic.
3.15 Gas Gap Failure Degradation of the protective cladding around the fuel pellets due to elevated core temperature releasing only radionuclides contained in the space between pellet and the cladding.
3.16 Ground Surface Correction Factor The ground surface correction factor is used in the calculation of ground-shine dose. Its value may be from 0.1 to 1.0. It is used to reduce the dose due to the effects of scattering off uneven ground.
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3.0  DEFINITONS (continued) 3.17 Intermediate Phase The period beginning after the incident source and releases have been brought under control and reliable environmental measurements are available for use as a basis for decisions on additional protective actions and extending until these protective actions are terminated. This phase may overlap the early and late phases and may last from weeks to many months. For the purpose of dose projection, it is assumed to last for one year.
3.18 Late Phase The period beginning when recovery action designed to reduce radiation levels in the environment to permanently acceptable levels are commenced, and ending when all recovery actions have been completed. This period may extend from months to years (also referred to as the recovery phase).
3.19 Meteorological Data Processor STDose module used for entering meteorological data and preparing the data for use by the atmospheric transport and diffusion models in RASCAL.
Meteorological data for the site (release point) and 35 additional meteorological observation points may be entered and processed for use by the STDose models. The model is generally accessed directly from the STDose user interface. This method is common when supporting an event using real-time meteorology. The program may also be run stand alone, directly from Windows.
This mode of operation is common when building predefined data sets.
3.20 Partitioning Reduction of non-noble gases when the steam generator tube leak is below the water level of the generator. This is highly unlikely at CR3 because most of the tube length in a once-through steam generator is above the secondary level.
This is not applicable to BNP.
3.21 Release Duration Period of time from the beginning of the release until the end of the release or the projected end of the release. This can be determined by estimating the completion of a damage control mission, performance of a repair to stop the release, or the estimated time until the RCS, Containment Vessel Sump or Steam Generator temperature is below 2000 F for a pressurized water reactor.
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3.0  DEFINITONS (continued) 3.22 Resuspension Factor The resuspension factor is used to calculate air concentrations from ground surface measurements. Its value may be from 1 E-1 1 to 1 E -2. It is used in all intermediate-phase calculations and in early-phase calculations when measured air concentrations are not used (that is, when "Use Air" is not checked on the Enter Field Data form).
3.23 Seabreeze Effect Wind circulation system produced when the land temperature is higher than the ocean temperature causing a lower level wind direction from sea to land. The consequence of a release traveling to sea and returning back to land can impact the projected dose in an upward factor. For BNP the seabreeze effect, if confirmed by a meteorologist, can exist between the 160 and 2690 bearings.
3.24 Sigma-Theta Standard deviation of a set of wind range measurements. The value provides a measure of atmospheric stability. The CR3 Sigma-Theta meter automatically calculates and displays the standard deviation of wind range for the previous 15 minutes.
3.25 Source Term to Dose (STDose)
The STDose of RASCAL provides estimates of the integrated doses and consequences resulting from the accidental release of radionuclides to the atmosphere. The model requires only information that might be available during an emergency. STDose should be used to assess the consequences of potential or ongoing releases. The program is used in conjunction with the Meteorological Data Processor Program.
3.26 Spike Factor Rapid decrease in pressure of the primary system causes an increase in the rate at which the radioactive fission products in the fuel rod cladding gap escape into the coolant. The RASCAL default spiking factor of 100 is recommended initially and then adjusted after primary coolant analysis. This is not necessarily an indication of fuel damage.
3.27 Stability Class Lettering system from A to G to designate certain atmospheric conditions which affect the dispersion of the plume. Class A indicates rapid dispersion, less concentrated plume (unstable conditions). Class G indicates slow dispersion, more concentrated plume (stable conditions).
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3.0  DEFINITONS (continued) 3.28 Total Effective Dose Equivalent (TEDE)
Early or plume phase TEDE that RASCAL calculates is the sum of the external gamma dose (cloudshine) from the plume, the committed effective dose equivalent (CEDE), and the external dose over a four-day period from radionuclides deposited on the ground (4-day groundshine dose).
3.29 Weathering Factor The fraction of radioactivity remaining after being affected by average weather conditions for a specified period of time.
4.0  RESPONSIBILITIES 4.1  Dose Assessment/Projection Coordinator or Team Leader 4.1.1  Calculate the TEDE and the thyroid CDE, of off-site dose consequences from a release of radioactivity.
4.1.2 Report dose projection results to the Radiological Control Manager (RCM) or Radiation Control Coordinator (RCC) /Radiological Control Director (RCD) if the EOF is not activated in a timely manner.
4.1.3 Communicate periodically with State and other agency dose assessment representatives to compare and contrast cases and results that were generated. A comparison also provides a means of peer checking input data and assumptions.
4.2  Dose Assessment Team 4.2.1  Implement the steps of this procedure to generate dose projections for review by the Dose Assessment/Projection Coordinator or Team Leader.
4.2.2  Solicit input from Accident Assessment personnel as needed for plant conditions.
4.3  Accident Assessment Team 4.3.1  Inform the Dose Assessment Team of plant conditions that may impact a radiological release to the environment such as time of core uncovered, percent fuel damage, etc.
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5.0  PREREQUISITES 5.1  Personnel performing RASCAL dose assessment during an emergency, drill, or exercise are trained and qualified per station procedures.
6.0  PRECAUTIONS AND LIMITATIONS 6.1  Ifthe release pathway is monitored, then the RASCAL Source Term Option for Monitored Releases - Mixtures is the preferred dose projection method. This method requires the use of site specific information and therefore the use of RASCAL for monitored releases is provided in site specific procedures (References 2.2.7 - 2.2.10). Exit this procedure and use the appropriate site procedure.
6.2  RASCAL requires stability class to be entered as an alphabetic value (e.g., A, B, C...). OSI/PI and ERFIS report stability class as a numeric value (e.g., 1, 2, 3...). They convert directly, 1=A, 2=B, 3=C, etc.
6.3  Several different input models should be run when data permits due to inherent uncertainties associated with generating dose projections using RASCAL. For example, when grab sample release data is available for a stack release, projections may be made using both a release rate model and release concentration model.
6.4  The release duration should be based on available information. If release duration information in not known, then use a default value of 1 hour (RNP should use 2 hours). The dose projections should be modified as more accurate information becomes available.
6.5  Meteorological conditions should be monitored approximately every 15 minutes for changes and RASCAL dose projections updated accordingly.
6.6  RASCAL dose projections should be updated accordingly when new data becomes available for plant, meteorological or event conditions.
6.7  Dose projections saved for various source terms may be re-opened and modified as necessary. The re-opened case should be renamed as applicable based on changes to event type, source term, release path, etc.
6.8  Consider radiation monitor operability and status prior to use for dose projections.
6.9  Sea breeze affect is NOT a specific calculation option for RASCAL; however, the meteorological program will model sea breeze if additional meteorological weather stations are used. Failure to consider the effects of a sea breeze on plume projections could result in large errors in both the projected plume location and intensity. Sea breeze is not a factor for HNP or RNP.
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6.0  PRECAUTIONS AND LIMITATIONS (continued) 6.10  BNP verification of ERFIS data shall be accomplished by comparing the Control Room readouts in the event the RMS/ERFIS interface multiplexer is in alarm.
6.11 CR3, RNP, and HNP normally uses the option of "Not an Isolated Stack" because the release points do NOT meet the height and separation distance requirements of an isolated release point 6.12 CR3 recorder AH-1003-TIR Channel 4 indicates total Reactor Building stack flow. AH-294-FT measures Reactor Building purge flow rate only and does NOT include make up flow.
6.13 CR3 instrumentation available during a station blackout includes:
* RM-Gs 1, 3, 5, 7, 9, 11, 25, 26, 27, 28, 29, 30
* RM-Ls 2, 7
* Primary Meteorological Tower local (at the tower only) readouts RM-A1, RM-A2 control room display units are powered, but pumps, skids and detectors are NOT powered.
6.14 RNP specific: RASCAL uses effective release height to model mixed mode releases. A release height of two hundred three (203) feet should be chosen for releases through the plant vent stack. Two hundred three feet is equivalent to the elevated level sensors at sixty-two (62) meters on the site meteorological tower. A release height of 36 feet should be chosen for release points other than the plant vent stack. Thirty-six feet is equivalent to the ground level sensors at eleven (11) meters on the site meteorological tower.
6.15 Verification of release mitigation actions being planned or taken is vital to accurate dose projections. Actions such as plume wash down may reduce the amount of radioactive materials released to the public.
6.16 Many screens in RASCAL contain a "Help" button. Clicking on the Help button provides useful information from the code developer related to information/options on that screen.
6.17 Dose projection results must be approved prior to communicating the information to offsite agencies. This information is typically transmitted via the Emergency Notification Form (ENF) which is approved by the Emergency Operations Facility Command position (e.g., Emergency Response Manager.)
6.18 Verify that the correct units and prefixes are selected when entering data. For example: height (feet or meters); prefix (milli, kilo, etc.); activity (becquerel or curie).
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7.0  SPECIAL TOOLS AND EQUIPMENT 7.1    RASCAL software version 3.0.5 on compatible computer 8.0  ACCEPTANCE CRITERIA N/A 9.0  INSTRUCTIONS Section 9.0 contains steps primarily associated with generic RASCAL operation. A specific Attachment exists for each NGG Site and should be referenced for additional site guidance and parameters.
0      Brunswick Unit 1 and 2 (BNP):    Attachment 5
* Crystal River 3 (CR3):            Attachment 6
* H.B. Robinson (RNP):              Attachment 7
* Shearon Harris (HNP):            Attachment 8 In addition, RASCAL is a software program and alternate key strokes may be used to obtain the end result. Section 9.0 describes one acceptable method to calculate dose assessments using the RASCAL software. There are multiple options available in RASCAL that may be utilized at the discretion of the user in the calculations of dose assessments 9.1  RASCAL Program Startup 9.1.1 LOG ON to the computer designated for RASCAL using your corporate ID and password, if not already operating.
9.1.2 START the RASCAL program.
9.1.3 IF computer difficulties are experienced when attempting to run RASCAL, THEN USE another computer AND contact the Technology Service Desk to resolve difficulties.
9.1.5 WHEN the RASCAL program starts and displays text showing the version, THEN SELECT the "OK" button (lower right) on the screen to initiate projection process.
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9.3    Select RASCAL Model 9.3.1  IF projecting doses from potential or ongoing releases and plant conditions, source term, and meteorological data are available, THEN SELECT Source Term to Dose Model (STDose) and proceed to step 9.4. This option is normally used for early phase dose assessment.
9.3.2 IF projecting doses from a release and at least one ground sample concentration is available, THEN SELECT Field Measurement to Dose Model (FMDose) and PROCEED to step 9.16. This option is NOT normally used for performing early phase dose projections.
9.4  Select Event Type 9.4.1 IF the actual or potential release is from a plant system, THEN CHOOSE Nuclear Power Plant AND GO TO Step 9.4.5.
9.4.2 IF the actual or potential release is from the Spent Fuel Pool, THEN choose Spent Fuel AND GO TO Step 9.4.5.
9.4.3 Do NOT select Fuel Cycle / UF6 / Criticality. This option is NOT currently applicable for NGG.
9.4.4 Do NOT select Other Radioactive Material Releases; This option is NOT currently applicable for NGG.
9.4.5 SELECT "OK" in the lower right corner of the Event Type Selection window and a
      ,,"mark will appear in front of Event Type when this step is complete.
9.5  Select Event Location 9.5.1 In the Site Names drop-down menu box, CLICK on the drop-down menu arrow, scroll down to and SELECT the applicable Site:
            " Brunswick - Unit 1
            " Brunswick - Unit 2
* Crystal River - Unit 3
            " H. B. Robinson - Unit 2
            " Shearon Harris - Unit 1 9.5.2 SELECT OK and a / mark will appear in front of Event Location when this step is complete.
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9.5  Select Event Location (continued) 9.5.3 IF EVENT TYPE is Nuclear Power Plant THEN GO to step 9.6, OTHERWISE GO to step 9.8 for Spent Fuel.
9.6  Select Nuclear Power Plant Type Source Term This section contains options to be used for selecting source term. Sections related to source terms that are not appropriate do NOT need to be completed and the user may proceed to the desired option.
* Time Core is Uncovered - Section 9.6.1
* Ultimate Core Damage State - Section 9.6.2
* Containment Radiation Monitor - Section 9.6.3
* Coolant Sample - Section 9.6.4
* Containment Air Sample - Section 9.6.5
* Effluent Isotopic Release Rates - Section 9.6.6
* Effluent Isotopic Release Concentrations - Section 9.6.7
* Monitored Releases - Mixtures - Go to site specific procedure (References 2.2.7 -
22.10)
NOTE:    Additional guidance related to Source Term and Release Path option selection is provided in Attachment 2 for all sites, Attachment 5 for BNP, Attachment 6 for CR3 and Attachment 8 for HNP.
9.6.1 IF the Time Core is Uncovered option is selected, THEN PERFORM the following steps.
: 1. IF the reactor is shutdown, THEN ENTER the date and time of shutdown.
: 2. IF the reactor is not shutdown, THEN ENTER the date and time of the start of the release in the "Reactor shutdown" field.
: 3. IF the reactor core is uncovered, THEN SELECT Yes AND ENTER the date AND time the core was uncovered. Otherwise, SELECT No.
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9.6  Select Nuclear Power Plant Type Source Term (continued)
: 4. IF the reactor core is recovered, THEN SELECT Yes AND ENTER the date AND time the core was recovered. Otherwise, SELECT No. This step is not available if No was selected in 9.6.1.3.
: 5. SELECT OK and a Vmark will appear in front of Source Term when this step is complete.
: 6. GO TO Step 9.7.
9.6.2 IF the Ultimate Core Damage State option is selected, THEN PERFORM the following steps.
: 1. IF the reactor is shutdown, THEN ENTER the date and time of shutdown.
: 2. IF the reactor is not shutdown, THEN ENTER the date and time of the start of the release in the "Reactor shutdown" field.
: 3. SELECT ONE of the following ultimate core damage states. Read all three before selecting.
: a. No core damage - normal coolant activity. CHOOSE this option if no core damage is suspected AND ENTER the time of normal coolant release date and time.
: b. Increased fuel pin leakage. CHOOSE this option if a rapid shutdown or depressurization has occurred AND ENTER the time of increased fuel pin leakage date and time. A coolant contamination spike factor of 100 is appropriate as long as the core remains covered.
: c. Cladding failure (gap release) - with percent. CHOOSE this option if the core is uncovered OR there is an indication of mechanical damage.
(1) DETERMINE AND ENTER percentage of gap release using the applicable site specific Attachment or other station procedures.
(2) ENTER completion of cladding failure date and time.
: 4. SELECT OK and a /mark will appear in front of Source Term when this step is complete.
: 5. GO TO Step 9.7.
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9.6  Select Nuclear Power Plant Type Source Term (continued) 9.6.3 IF the primary Containment Radiation Monitor option is selected, THEN PERFORM the following steps. BNP has a primary and secondary containment whereas CR3, HNP and RNP only have one "primary" containment.
: 1. IF the reactor is shutdown, THEN ENTER the date and time of shutdown.
: 2. IF the reactor is not shutdown, THEN ENTER the date and time of the start of the release in the "Reactor shutdown" field.
: 3. IF the dose assessment is for Brunswick, THEN SELECT monitor location for in dry well. BNP does not have a monitor in the wet well and the PWRs only have one option of containment dome for monitor location.
: 4. OBTAIN the radiation monitor reading(s) for the applicable site:
: a. Brunswick - Unit 1:
                * (1)D22-RM-4195
                " (1)D22-RM-4196
                * (1)D22-RM-4197
                " (1)D22-RM-4198
: b. Brunswick - Unit 2:
                " (2)D22-RM-4195
                " (2)D22-RM-4196
                " (2)D22-RM-4197
                " (2)D22-RM-4198
: c. Crystal River - Unit 3: RM-G29 or RM-G30
: d. H. B. Robinson - Unit 2: R-2, R-32A or R-32B
: e. Shearon Harris - Unit 1: RM 3589 or RM 3590
: 5. ENTER the following for the radiation monitor:
: a. Date
: b. Time
: c. Radiation monitor reading in R/hr
: 6. The use of the Add Row, Delete Row and Sort Rows buttons are optional and NOT required. Monitor readings for multiple times may be entered if the reading is changing by selecting the Add Row button. The Sort Row button arranges the readings by time.
: 7. SELECT OK and a ",markwill appear in front of Source Term when this step is complete.
: 8. GO TO Step 9.7.
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9.6  Select Nuclear Power Plant Type Source Term (continued) 9.6.4 IF the Coolant Sample option is selected, THEN PERFORM the following steps.
: 1. ENTER the Sample ID.
: 2. ENTER the date AND time the sample was taken.
: 3. VERIFY the correct sample activity units by clicking on the > symbol AND REVISE as necessary.
: 4. ENTER the sample nuclides AND activity for each nuclide.
: 5. SELECT OK and a ,mark will appear in front of Source Term when this step is complete.
: 6. GO TO Step 9.7.
9.6.5 IF the Containment Air Sample option is selected, THEN PERFORM the following steps.
: 1. ENTER the Sample ID.
: 2. ENTER the date AND time the sample was taken.
: 3. VERIFY the correct sample activity units by clicking on the > symbol AND REVISE as necessary.
: 4. ENTER the sample radionuclide AND activity for each radionuclide.
: 5. SELECT OK and a /mark will appear in front of Source Term when this step is complete.
: 6. GO TO Step 9.7.
9.6.6 IF the Effluent Isotopic Release Rates option is selected, THEN PERFORM the following steps.
: 1. ENTER the measurement location (sample origin).
: 2. VERIFY the correct Effluent release rate units by clicking on the > symbol AND REVISE as necessary. CONVERT units as necessary.
: 3. ENTER the applicable Start date AND Start time for each release period.
: 4. ENTER the applicable Stop date AND Stop time for each release period.
: 5. ENTER the nuclides AND release rates for each period.
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: 6. 9.6      Select Nuclear Power Plant Type Source Term (continued)
: 7.      VERIFY the percent enrichment is five percent (5%).
: 8.      SELECT OK and a /mark will appear in front of Source Term when this step is complete.
: 9.      GO TO Step 9.7 to enter Release Path information.
9.6.7 IF the Effluent Isotopic Release Concentrations option is selected, THEN PERFORM the following steps.
: 1. ENTER the measurement location (sample origin).
: 2. VERIFY the correct Effluent flow rate units by clicking on the > symbol AND REVISE as necessary. CONVERT units as necessary.
: 3. VERIFY the correct Effluent concentration units by clicking on the > symbol AND REVISE as necessary. Convert units as necessary.
: 4. ENTER the applicable Start date AND Start time for each release period.
: 5. ENTER the applicable Stop date AND Stop time for each release period.
: 6. ENTER the applicable Effluent flow rate for each release period.
: 7. ENTER the nuclides AND concentrations for each period.
: 8. VERIFY the percent enrichment is five percent (5%).
: 9. IF the sample analysis period results are greater than 24 hours prior to the release, AND require decay calculation per the RCC/RCD or RCM THEN SELECT DECAY.
: a. SELECT the period to decay isotopes.
: b. SELECT the time AND units to adjust the source for decay prior to release time.
: c. SELECT OK.
: 10. SELECT OK and a v/mark will appear in front of Source Term when this step is complete.
: 11. GO TO Step 9.7 to enter Release Path information.
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9.7    SELECT Nuclear Power Plant Release Path This section contains options to be used for selecting a release path. Sections related to release paths that are not appropriate do NOT need to be completed and the user may proceed to the desired option:
* Through the Wet Well - Section 9.7.1
* Through the Dry Well Wall - Section 9.7.2
* Bypass Secondary Containment - Section 9.7.3
* Containment Leakage/Failure - Section 9.7.4
* Steam Generator Tube Rupture - Section 9.7.5
* Containment Bypass - Section 9.7.6
* Direct to Atmosphere - Section 9.7.7 NOTE:      Additional guidance related to Source Term and Release Path option selection is provided in Attachment 2 for all sites, Attachment 5 for BNP, Attachment 6 for CR3 and Attachment 8 for HNP.                                                              J NOTE: Sections 9.7.1 - 9.7.3 and section 9.7.7 are used for BNP release pathways.
Sections 9.7.4 - 9.7.6 and section 9.7.7 are used for CR3, HNP, and RNP release pathways.
9.7.1 IF the Through the Wet Well option is selected, THEN PERFORM the following steps.
This option is ONLY applicable to Brunswick Units 1 and 2 and assumes that the release passes by a wet pathway through the suppression pool into the secondary containment wet-well atmosphere. Particulates and aerosols airborne in the secondary containment wet well are reduced by factors to account for their interactions with the suppression pool under subcooled or saturated conditions.
: 1. ENTER a Pathway description.
: 2. IF the release point is through the reactor building, turbine building or radwaste building THEN SELECT Not an isolated stack.
: a. ENTER 0 meters for the release height. This is considered a Ground release.
: b. SELECT YES for Consider building wake effects.
: c. GO TO Step 9.7.1.4.
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9.7 SELECT Nuclear Power Plant Release Path (continued)
: 3. IF the release point is through the Main Stack THEN SELECT Isolated stack.
: a. ENTER 100 meters for the stack height. This is considered an Elevated release.
: b. IF the ambient air temperatures are not known THEN ENTER NO for Consider plume rise.
: c. IF the ambient air temperatures are known and will be used in the meteorological data set THEN ENTER YES for Consider plume rise.
: d. IF desired to edit plume rise settings THEN SELECT Edit Plume Rise Settings and revise:
: 1) Effluent flow rate and units
: 2)    Stack diameter and units
: 3)    Effluent Temperature and units
: 4. ENTER the date AND time of the release start to wet well.
: 5. SELECT the Percent Volume OR Containment Pressure/Hole Size option.
: 6. ENTER the current date AND current time for each event row used.
: a. IF the Percent Volume option is selected, THEN SELECT the Event Setting options based on the following table.
Event                      Event Setting Choices Leak Rate (REQUIRED)        Total Failure (100%/hr)
Percent Volume in % per day or % per hour Design (0.50%/d)
Filters (OPTIONAL)          On Off Filter Rel Frac (Filter    Noble gases Release Fractions)        Halogens (OPTIONAL)        Other radionuclides Wet Well (OPTIONAL)        Saturated Subcooled EMG-NGGC-0002                            Rev. 5                                Page 21 of 87
 
9.7  SELECT Nuclear Power Plant Release Path (continued)
: b. IF the Containment Pressure/Hole Size option is selected, THEN SELECT the Event Setting options based on the following table.
Event                    Event Setting Choices Leak Rate                Containment pressure and units (REQUIRED)      Hole area or diameter and units Filters (OPTIONAL)        On Off Filter Rel Frac (Filter  Noble gases Release Fractions)      Halogens (OPTIONAL)      Other radionuclides Wet Well (OPTIONAL)      Saturated Subcooled
: 7. SELECT OK and a V'mark will appear in front of Release Path when this step is complete.
: 8. GO TO Step 9.10.
9.7.2 IF the Through the Dry Well Wall option is selected, THEN PERFORM the following steps. This option is ONLY applicable to Brunswick Units 1 and 2 and assumes that the release passes by a dry pathway through the primary system into the secondary containment dry-well atmosphere without passing through the suppression pool.
Particulates and aerosols airborne in the secondary containment dry well are reduced by factors to account for the actions of sprays or natural processes.
: 1. ENTER a Pathway description.
: 2. IF the release point is through the reactor building, turbine building or radwaste building THEN SELECT Not an isolated stack.
: a. ENTER 0 meters for the release height. This is considered a Ground release.
: b. SELECT YES for Consider building wake effects.
: c. ENTER the date AND time of the release start to dry well.
: d. GO TO Step 9.7.2.4.
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9.7 SELECT Nuclear Power Plant Release Path (continued)
: 3. IF the release point is through the Main Stack THEN SELECT Isolated stack.
: a. ENTER 100 meters for the stack height. This is considered an Elevated release.
: b. IF the ambient air temperatures are not known THEN ENTER NO for Consider plume rise.
: c. IF the ambient air temperatures are known and will be used in the meteorological data set THEN ENTER YES for Consider plume rise.
: d. IF desired to edit plume rise settings THEN SELECT Edit Plume Rise Settings and revise:
: 1)  Effluent flow rate and units
: 2)  Stack diameter and units
: 3)  Effluent Temperature and units
: 4. ENTER the date AND time of the release start to dry well.
: 5. SELECT the Percent Volume OR Containment Pressure/Hole Size option.
: 6. ENTER the current date AND current time for each event row used.
: a. IF the Percent Volume option is selected, THEN SELECT the Event Setting options based on the following table.
Event                          Event Setting Choices Leak Rate (REQUIRED)          Total Failure (100%/hr)
Percent Volume in % per day or % per hour Design (0.50%/d)
Filters (OPTIONAL)            On Off Filter Rel Frac (Filter        Noble gases Release Fractions)            Halogens (OPTIONAL)            Other radionuclides Sprays (OPTIONAL)              On Off I EMG-NGGC-0002                    I            Rev. 5                              Page 23 of 87
 
9.7  SELECT Nuclear Power Plant Release Path (continued)
: b. IF the Containment Pressure/Hole Size option is selected, THEN SELECT the Event Setting options based on the following table.
Event                      Event Setting Choices Leak Rate (REQUIRED)      Containment pressure and units Hole area or diameter and units Filters (OPTIONAL)        On Off Filter Rel Frac (Filter    Noble gases Release Fractions)        Halogens (OPTIONAL)        Other radionuclides Sprays (OPTIONAL)          On Off
: 7. SELECT OK and a -'mark will appear in front of Release Path when this step is complete.
: 8. GO TO Step 9.10.
9.7.3 IF the Bypass Secondary Containment option is selected, THEN PERFORM the following steps. This option is ONLY applicable to Brunswick Units 1 and 2.
: 1. ENTER a Pathway description.
: 2. IF the release point is through the reactor building, turbine building or radwaste building THEN SELECT Not an isolated stack.
: a. ENTER 0 meters for the release height. This is considered a Ground release.
: b. SELECT YES for Consider building wake effects.
: c. GO TO Step 9.7.3.4.
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9.7 SELECT Nuclear Power Plant Release Path (continued)
: 3. IF the release point is through the Main Stack THEN SELECT Isolated stack.
: a. ENTER 100 meters for the stack height. This is considered an Elevated release.
: b. IF the ambient air temperatures are not known THEN ENTER NO for Consider plume rise.
: c. IF the ambient air temperatures are known and will be used in the meteorological data set THEN ENTER YES for Consider plume rise.
: d. IF desired to edit plume rise settings THEN SELECT Edit Plume Rise Settings and revise:
: 1) Effluent flow rate and units
: 2)    Stack diameter and units
: 3)    Effluent Temperature and units.
If plume rise is being considered and the effluent temperature is unknown assume the effluent temperature is the same as the ambient outside temperature.
: 4. ENTER the current date AND current time for each event row used.
: 5. SELECT the Event Setting options based on the following table.
Event                            Event Setting Choices Leak Rate (REQUIRED)            Flow rate for the coolant bypassing the containment and units Filters (OPTIONAL)              On I    _    _  __              I    Off
: 6. SELECT OK AND a ,/mark will appear in front of Release Path when this step is complete.
: 7. GO TO Step 9.10.
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9.7  SELECT Nuclear Power Plant Release Path (continued) 9.7.4 IF the Containment LeakagelFailure option is selected, THEN PERFORM the following steps. This option is NOT applicable to Brunswick Units 1 and 2.
: 1. ENTER a description for the release pathway.
: 2. SELECT the Not an isolated stack AND ENTER the release height as listed below.
: a. Crystal River - Unit 3: 0 meters
: b. H. B. Robinson - Unit 2 plant vent: 62 meters or 203 feet
: c. H. B. Robinson - Unit 2, non-plant vent: 11 meters or 36 feet
: d. Shearon Harris - Unit 1, See Attachment 8 Section 2.0
: 3. SELECT Yes for Consider building wake effects.
: 4. ENTER the date AND time of the release start to containment. This step is NOT applicable if the source term is "containment air sample".
: 5. SELECT the Percent Volume OR Containment Pressure/Hole Size option.
: a. IF the Percent Volume option is selected, THEN SELECT the Event Setting options based on the following table.
Event                    Event Setting Choices Sprays                  On Off Leak Rate                Total Failure (100%/hr)
Percent Volume in % per day or % per hour Design
: b. IF the Containment Pressure/Hole Size option is selected, THEN SELECT the Event Setting options based on the following table.
Event                        Event Setting Choices Sprays                      On Off Leak Rate                    Containment pressure and units Hole area or diameter and units I EMG-NGGC-0002                                Rev. 5                1            Page 26 of 87
 
9.7  SELECT Nuclear Power Plant Release Path (continued)
: 6. SELECT OK and a /mark will appear in front of Release Path when this step is complete.
: 7. GO TO Step 9.10.
9.7.5 IF the Steam Generator Tube Rupture option is selected, THEN PERFORM the following steps. This option is NOT applicable to Brunswick Units 1 and 2.
: 1. IF the release is through a secondary side Pressure Operated Relief Valve (PORV),
a safety valve or turbine building exhaust, or directly to atmosphere through a leaking/failed component, THEN SELECT the Safety Valve/ADV/Turbine Building exhaust option.
: a. ENTER the appropriate release height as shown below:
: 1) Crystal River - Unit 3: 0 meters or 0 feet
: 2)  H. B. Robinson - Unit 2: 11 meters or 36 feet
: 3)  Shearon Harris - Unit 1: See Attachment 8 Section 2.0
: b. GO TO Step 9.7.5.3
: 2. IF the release is through the condenser to a plant vent via either a Steam Jet Air Ejector or a Condenser Vacuum Pump, THEN SELECT Steam Jet Air Ejector.
: a. ENTER the appropriate release height as shown below:
: 1) Crystal River - Unit 3: 0 meters or 0 feet
: 2)  H. B. Robinson - Unit 2: 62 meters or 203 feet
: 3)  Shearon Harris - Unit 1: See Attachment 8 Section 2.0
: 3. SELECT Yes to "consider building wake effects".
: 4. ENTER the Steam Generator water mass IF known otherwise use default value of 9.30 E+04 lb.
: 5. ENTER the Steaming rate IF known otherwise use default value of 7.50E+04 lb/h.
: 6. ENTER the current date AND current time for each event row used.
I EMG-NGGC-0002                                Rev. 5              1            Page 27 of 87
 
9.7  SELECT Nuclear Power Plant Release Path (continued) 11 NOTE: In RASCAL, charging flow is a generic term used to describe the leak through the tubes. The charging flow is the value that quantifies the leak or net flow.            II
: 7. SELECT the Event Setting options based on the following table.
Event                        Event Setting Choices Leak Rate into SG            Number of ruptured tubes (REQUIRED)            Charging flow and units SG Condition                  Partitioned - it is partitioned ifthe break is under the secondary side water in the steam generator.
Not Partitioned - it is not partitioned ifthe break is above the secondary side water or the secondary side is solid due to in-leakage of primary coolant.
: 8. SELECT OK and a -'mark will appear in front of Release Path when this step is complete.
: 9. GO TO Step 9.10.
9.7.6 IF the Containment Bypass option is chosen, THEN PERFORM the following steps.
This option is NOT applicable to Brunswick Units 1 and 2.
: 1. ENTER a description for the release pathway.
: 2. SELECT the Not an isolated stack AND ENTER the release height as shown below:
: a. Crystal River- Unit 3:0 feet
: b. H. B. Robinson - Unit 2
* Plant Vent Stack: 62 meters or 203 feet
* Non-Plant Vent Stack Pathway: 11 meters or 36 feet
: c. Shearon Harris - Unit 1: See Attachment 8 Section 2.0
: 3. SELECT Yes to Consider building wake effects.
: 4. ENTER the current date AND current time for each event row used.
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9.7  SELECT Nuclear Power Plant Release Path (continued)
: 5. SELECT the Event Setting options based on the following table.
Event                          Event Setting Choices Leak Rate (REQUIRED)          Flow rate for the coolant bypassing the containment and units Filters (OPTIONAL)            On Off
: 6. SELECT OK and a Vmark will appear in front of Release Path when this step is complete.
: 7. GO TO Step 9.10.
9.7.7 IF the release is Direct to Atmosphere THEN PERFORM the following steps. This release pathway is applicable to all Plants and is used automatically for the following source term options:
* Effluent Isotopic Release Rates
* Effluent Isotopic Release Concentrations
          "      Monitored Releases - Mixtures
: 1. IF the release point is through the Brunswick Unit I or 2 Main Stack THEN SELECT Isolated stack.
: a. ENTER 100 meters for the stack height. This is considered an Elevated release.
: b. IF the ambient air temperatures are not known THEN ENTER NO for Consider plume rise.
: c. IF the ambient air temperatures are known and will be used in the meteorological data set THEN ENTER YES for Consider plume rise.
: d. IF desired to edit plume rise settings THEN SELECT Edit Plume Rise Settings and revise:
: 1)    Effluent flow rate and units
: 2)    Stack diameter and units
: 3)    Effluent Temperature and units IEMG-NGGC-0002                      I              Rev. 5                1                Page 29 of 87
 
9.7  SELECT Nuclear Power Plant Release Path (continued)
: e. GO TO Step 9.7.7.4.
: 2. SELECT the Not an isolated stack AND ENTER the release height as listed below for all releases except from Brunswick Unit 1 or 2 Main Stack:
: a. Brunswick - Unit 1 and Unit 2: 0 meters
: b. Crystal River - Unit 3: 0 meters
: c. H. B. Robinson - Unit 2 plant vent: 62 meters or 203 feet
: d. H. B. Robinson - Unit 2, non-plant vent: 11 meters or 36 feet
: e. Shearon Harris - See Attachment 8, Section 2.0
: 3. SELECT Yes for Consider building wake effects.
: 4. ENTER the start date AND time of the release to atmosphere.
: 5. ENTER End of release to atmosphere data by using one of the two options below:
: a. IF the End time is known for the release period THEN ENTER the stop date AND time of the release to atmosphere.
: b. IF the Release duration option is selected THEN ENTER the days, hours and minutes.
: 6. SELECT OK and a V'mark will appear in front of Release Path when this step is complete.
: 7. GO TO Step 9.10.
9.8  SELECT Spent Fuel Type Source Term This section contains options to be used for selecting source terms for Spent Fuel accidents. Sections related to source terms that are not appropriate do NOT need to be completed and the user may proceed to the desired option.
* Pool Storage - Uncovered Fuel - Section 9.8.1
* Pool Storage - Damaged Assembly Under Water - Section 9.8.2
    "  Dry Storage Cask Release - Section 9.8.3 EMG-NGGC-0002                              Rev. 5                            Page 30 of 87
 
9.8  SELECT Spent Fule Type Source Term (continued)
NOTE:    Attachment 2 provides a summary of available source term selection criteria.
9.8.1 IF the spent fuel pool has been drained OR spent fuel has been uncovered > 2 hours, THEN SELECT Pool Storage - Uncovered Fuel AND PERFORM the following steps.
: 1. SELECT HIGH for Density of fuel pool racking. This step is NOT applicable to Brunswick Unit 1 and 2.
SNOTE: For a fuel uncovered event, material is not considered available for release until two (2) hours after uncovered time. All fuel is considered to be damaged.
: 2. SPECIFY the amount of fuel in the pool. IF the Number of batches is selected for Amount of fuel in the pool THEN ENTER the number of batches in the pool since last irradiation as applicable for the Site location.
: a. Brunswick - Unit 1 and 2: < 180 days, 180+ days
: b. Crystal River - Unit 3:
: 1)  IF the refuel outage occurred <1 year ago, THEN ENTER <1 year =1; 1-2 years = 0; >2 years = last refuel number -1.
: 2)  IF the refuel outage occurred 1-2 years ago, THEN ENTER <1 year = 0; 1-2 years = 1; >2 years = last refuel number -1.
: 3)  IF the refuel outage occurred >2 years ago, THEN ENTER <1 year = 0; 1-2 years = 0; >2 years = last refuel number.
: c. H. B. Robinson - Unit 2: <1 year, 1-2 years, and >2 years
: d. Shearon Harris - Unit 1: <1 year, 1-2 years, and >2 years
: 3. IF the Number of assemblies is selected for Amount of Fuel in the pool THEN ENTER the number of assemblies in the pool since last irradiation as applicable for the Site location.
: a. Brunswick - Unit 1 and 2: < 180 days, 180+ days
: b. Crystal River- Unit 3: <1 year, 1-2 years, and >2 years
: c. H. B. Robinson - Unit 2: <1 year, 1-2 years, and >2 years
: d. Shearon Harris - Unit 1: <1 year, 1-2 years, and >2 years I EMG-NGGC-0002                                    Rev. 5            1          Page 31 of 87
 
9.8  SELECT Spent Fule Type Source Term (continued)
: 4. ENTER the date and time of fuel uncovered.
: 5. IF the pool is totally drained, THEN SELECT YES AND ENTER the date and time pool was drained. Otherwise, SELECT NO.
: 6. IF the fuel is recovered, THEN SELECT YES AND ENTER the date and time fuel is recovered. Otherwise, SELECT NO.
: 7. SELECT OK to proceed with case development and a / mark will appear in front of Source Term when this step is complete.
: 8. GO to Step 9.9.
9.8.2 IF fuel assemblies have been damaged during handling, THEN SELECT Pool Storage
        - Damaged Assembly Under Water AND PERFORM the following steps.
: 1. ENTER the number of damaged assemblies.
: 2. ENTER the Last date of irradiation OR ENTER how long, in years and days the damaged assemblies have been in storage.
: 3. ENTER the date and time the damage occurred to the fuel.
: 4. SELECT OK and a V mark will appear in front of Source Term when this step is complete.
: 5. GO to Step 9.9.
9.8.3 IF the spent fuel is damaged due to a dry storage cask event, THEN SELECT dry fuel storage cask event AND PERFORM the following steps.
: 1. SELECT the type of cask if known OTHERWISE, SELECT UNKNOWN AND ENTER the number of fuel assemblies in a cask.
: 2. ENTER the Last date of irradiation OR ENTER how long, in years the damaged assemblies have been in storage.
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9.8  SELECT Spent Fule Type Source Term (continued)
NOTES:    1. No release is projected for a loss of cask cooling less than 24 hours of the thermal limit. Another event type must be selected.
: 2. A very minimal or no release is projected for a cask engulfed in fire. Another event type must be selected.
: 3. ENTER the type of event as major damage AND ENTER percent of fuel elements damaged OTHERWISE SELECT Loss of cooling greater than 24 hours (thermal limit).
: 4. SELECT OK and a ' mark will appear in front of Source Term when this step is complete.
9.9 SELECT the Spent Fuel Release Path 9.9.1  IF the release point is through the Brunswick Unit I or 2 Main Stack THEN SELECT Isolated stack. OTHERWISE GO to step 9.9.2.
: 1. ENTER 100 meters for the stack height. This is considered an Elevated release.
: 2. IF the ambient air temperatures are not known THEN ENTER NO for Consider plume rise.
: 3. IF the ambient air temperatures are known and will be used in the meteorological data set THEN ENTER YES for Consider plume rise.
: 4. IF desired to edit plume rise settings THEN SELECT Edit Plume Rise Settings and revise:
: a. Effluent flow rate and units
: b. Stack diameter and units
: c. Effluent Temperature and units
: 5. GO TO Step 9.9.4.
9.9.2 ENTER the Pathway Description I EMG-NGGC-0002                  I            Rev. 5                          Page 33 of 87
 
9.9  SELECT the Spent Fuel Release Path (continued) 9.9.3 SELECT the NOT an isolated stack AND ENTER the release height as listed below.
: 1. Brunswick - Unit 1 and Unit 2: 0 meters
: 2. Crystal River - Unit 3: 0 meters
: 3. H. B. Robinson - Unit 2 plant vent: 62 meters or 203 feet
: 4. H. B. Robinson - Unit 2, unmonitored or dry fuel cask event: 11 meters or 36 feet
: 5. Shearon Harris - Unit 1:
: a. Stack 1:      27.4 meters (90 feet)
: b. Stack 3:      19.2 meters (63 feet)
: c. Stack 5:      24.1 meters (79 feet)
: d. Stack 5A:    18.3 meters (60 feet) 9.9.4 SELECT Yes for Consider building wake effects.
9.9.5 ENTER the start date AND time of the release to atmosphere.
9.9.6 ENTER End of release to atmosphere data by using one of the two options below.
: 1. IF the End time is known for the release period THEN ENTER the stop date AND time of the release to atmosphere.
: 2. IF the Release duration option is selected THEN ENTER the days, hours and minutes.
9.9.7 IF the building with the fuel damage accident is intact, and the operating ventilation system provides filtered releases (they do not have to be safety grade filters) THEN ENTER YES to filtered pathway condition if the filter system includes both HEPA and charcoal. If the system only includes HEPA filters only select YES if all fuel had decayed for more than 3 months. Otherwise, ENTER no for all other conditions.
9.9.8 SELECT the Leak rate to atmosphere as Total failure OR Percent volume. Total failure default is 100% since this is essentially the fastest rate at which the fission products can escape the building.
: 1. IF Percent volume is selected THEN enter the leak rate in % per hour.
9.9.9 SELECT OK and a -/mark will appear in front of Release Path when this step is complete.
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9.10  SELECT Meteorology NOTES:
: 1. Meteorological data should be obtained from the appropriate source. ERFIS or PICS (CR3) should be used as the primary source for meteorological data. Every effort should be made to obtain on site meteorological data. The National Weather Service, Weather Services International (wsi.com), etc. may also be used to obtain meteorological data.
: 2. The pre-defined (non site specific) meteorological data may also be used if ERFIS data is unavailable. The pre-defined meteorological data is based on visual observation of existing weather conditions. Example: Summer-Afternoon-Rainy should be chosen if visual observation of the weather support the conditions.
: 3. (HNP) All release points at HNP are considered to be a around level release due to the stack heiaht beina less than 2.5 times the heiaht of any surroundina building.
Therefore, the 12.5 m wind direction and speeds are used as input into the meteorological data.
9.10.1 OBTAIN meteorological data for the desired Site by referring to Attachment 3 and the applicable site specific Attachment. Attachment 3 contains standard nomenclature for weather report symbols, model classes and intensities if a weather forecast is provided by an offsite weather agency.
          "      Brunswick Unit 1 and 2 (BNP):      Attachment 5
* Crystal River 3 (CR3):            Attachment 6
* H.B. Robinson (RNP):              Attachment 7
* Shearon Harris (HNP):              Attachment 8 9.10.2 CONTINUE to 9.11 to input meteorological data.
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9.11 INPUT Meteorology 9.11,1 SELECT Actual Observations and Forecasts IF available OTHERWISE PROCEED to step 9.11.2.
: 1. SELECT Create New OR SELECT Edit Existing.
: 2. SELECT Enter Data.
: 3. SELECT OBS for observed data OR FCST for forecast data TYPE as appropriate.
CAUTION RASCAL rounds meteorological data times to the nearest quarter hour. Ifthe meteorological data time is the same as the release time and both are in the second half of a quarter hour (e.g., 0008-0014), RASCAL rounds the meteorological data time to 0015 which is after the release time and causes an error. To prevent this error, meteorological time should be adjusted to the first half of the quarter hour (e.g., 0000-0007).
: 4. ENTER the date and time for each data set.
: 5. ENTER the Direction "From" in degrees for each data set.
: a. IF the instrument reading is greater than 360, THEN subtract 360 from the reading and enter.
: 6. ENTER the speed in mph.
: a. IF an adverse met data dose projection is being performed, THEN ENTER a speed of 1 mph. (HNP)
: 7. ENTER stability class using the drop-down list selection.
: a. IF an adverse met data dose projection is being performed THEN ENTER a stability class of G. (HNP)
: 8. ENTER the Precipitation type using the drop-down list selection.
            " No precipitation: <0.01 in/hr.
            " Light rain: 0.01 to 0.04 in/hr.
* Rain: >0.04 to 0.2 in/hr.
            " Heavy rain: >0.2 in/hr.
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9.11 INPUT Meteorology (continued)
: 9. ENTER OPTIONAL parameters if desired but they are NOT required:
: a. Air Temperature in degrees Fahrenheit
: b. Air Pressure (mb)
: c. Dew Point in degrees Fahrenheit
: 10. IF an additional record is going to be added SELECT Add record.
: a. REPEAT steps 9.11.1.3-9.11.1.10.
: 11. SELECT "OK" in the bottom right of the screen.
: 12. SELECT "Save and Process Data".
: 13. ENTER a name for the meteorological observation data set. This allows for repeated updating of new met data saved under different names for future retrieval.
Example: 090108 1100 (Date and time)
NOTE: The parameters listed below are not normally changed from the computer specified default values but the option is available. The RCC/RCD or RCM should be consulted prior to changing.
: 14. VERIFY the following options are selected AND EDIT as necessary.
: a. Data set description: Created automatically from first site data record
: b. Save data set as: Event-specific data set
: c. Data processing options - Estimate missing stability using: Wind speed, time of day, etc. (recommended)
: d. Adjust stability for consistency: Yes (recommended)
: e. Modify winds for topography: Yes
: 15. SELECT OK.
: 16. SELECT Return.
: 17. SELECT OK and a / mark will appear in front of Meteorology when this step is complete.
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9.11  INPUT Meteorology (continued)
: 18. GO TO Step 9.12.
9.11.2 IF no actual observation or forecast data is available SELECT Predefined Data (Non Site-specific).
: 1. SELECT the available data set that most resembles current weather conditions at the site.
: 2. SELECT OK and a / mark will appear in front of Meteorology when this step is complete.
9.12  SELECT Calculate Doses 9.12.1 SELECT the appropriate distances for calculations. Typically the "Close in + out to10 miles" option is chosen to supply the required results.
9.12.2 IF the dose assessment is for Brunswick Unit 1 or 2 GO TO step 9.12.6.
9.12.3 SELECT user defined distances AND Set Close Distances.
9.12.4 ENTER the applicable site boundary distance of the non-UF6 Release as applicable:
: 1. Crystal River 3: REPLACE 1.000 mile with 0.83 miles.
: 2. Harris Plant: REPLACE 0.500 miles with 0.47 miles.
: 3. Robinson Plant: REPLACE 0.200 miles with 0.265 miles.
9,12.5 SELECT OK.
CAUTION The "Start of release to atmosphere plus" value is NOT the same      as the release provides for a time duration duration. The "Start of release to atmosphere plus" long enough for the entire plume to pass over the region of interest. This time includes the release duration plus enough time for the entire plume to cover the area of interest. The wind speed needs to be taken into account.
9.12.6  COMPLETE the "End Calculations at" field.
: 1. SELECT "Start of release to atmosphere plus" THEN ENTER the number of hours. The default is 6 hours and is sufficient during the early phases of a release, OR
: 2. SELECT User specified time THEN ENTER the date and time. This option is normally used as additional information becomes available.
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9.12  SELECT Calculate Doses (continued) 9.12.7  ENTER the Case description. A case description is required for identification of variations of case input data.SELECT OK to begin calculations and a -/ mark will appear in front of Calculate Doses when this step is complete.
9.13  REVIEW Detailed Results This step is optional and can be used to view detailed results that are useful in comparing projections with field team data. However critical information shall not be delayed to perform review details.
9.13.1  SELECT Detailed Results.
9.13.2  SELECT the desired options on the Detailed Results of Dose Calculations screen.
9.13.3  SELECT Display Selected Result button and the graphic display of plume footprint for the calculated case is presented on screen. POSITION cursor over cell to view specific bearing, distance, or dose.
9.13.4  SELECT OK, then EXIT to return to primary screen for completing a dose assessment.
9.14  Dose Projection Results CAUTION Time is of the essence when conducting and approving dose projections. Dose projection results may escalate OR preclude emergency action level declarations.
NOTE:          Projections developed when there is no release in progress and using "what if' data parameters are not required to be reviewed and approved. "What if' scenarios should not be disseminated to ERO personnel excluding the RCM or RCC or RCD.
9.14.1  SELECT AND PRINT the reports from the Maximum Dose Values tab AND the Source Term Summary tab.
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9.14  Dose Projection Results (continued)
                                                                                                  --- I The appropriate printer must be selected in the Print Setup option under the IINOTE:        RASCAL File menu. This is in addition to the Windows default printer selection.
9.14.2  PEER CHECK the dose assessment with the assistance of another dose assessment team member, leader, RCC, RCD or RCM. The peer check shall at a minimum provide verification that:
: a. Release parameters are correct
: b. The results do not affect the current EAL classification
: c. The results do not change any Protective Action Recommendations 9.14.3  COMPARE dose projection results with alternate methods of dose projection, if available. These include:
: a. Comparison with field monitoring. The RASCAL detailed results provides the capability to determine location and time specific values for dose rates and airborne concentrations. These detailed results should be compared with actual field measurements and adjustments made as necessary. Field measurements may be available from utility teams, state teams, or federal teams, including fly-over surveys.
: b. Comparison with state or NRC dose projection results. Share dose projection results with state and NRC dose projection personnel. Attempt to explain any significant differences as time permits.
9.14.4  IF the dose projection is incorrect, THEN develop a new dose projection.
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9.14  Dose Projection Results (continued) 9.14.5  IF the projection is correct, THEN provide the RCM the projection print-outs for approval.
NOTE:        Dose projection results must be approved prior to communicating the information to offsite agencies. This information is typically transmitted via the Emergency Notification Form (ENF) which is approved by the Emergency Operations Facility Command position (e.g., Emergency Response Manager.)
9.14.6  The RCM shall REVIEW AND APPROVE the projection. Approval is to acknowledge the:
* Dose projection is accurate.
* PARs are developed.
Information is communicated for ENF transmittal. Dose information from the Maximum Dose Values Report should be converted from Rem to mRem prior to entering it on the ENF.
9.14.7  The RCM shall SIGN AND DATE the dose projection to denote approval.
9.14.8  The RCM shall IMMEDIATELY COMMUNICATE dose projection results for evaluation of an EAL classification impact to the Site Emergency Coordinator.
9.14.9  The RCM shall COMMUNICATE dose projection results IMMEDIATELY to the EOF if PARs are impacted OR no later than the next EOF briefing if PARs are not impacted.
9.14.10 PROVIDE a copy to the RASCAL Case Summary to State Dose Projection personnel at the State EOC and/or EOF for each projection released on the Emergency Notification Form (ENF).
9.14.11  IF the dose calculation is for CRYSTAL RIVER 3 THEN fill in the blank projection duration (Item 14) of the Florida Nuclear Plant Emergency Notification Form with the correct time frame.
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9.14  Dose Projection Results (continued)
I1NOTE:
If an approved computer application is available for transferring dose projection information to the ENF electronically, then this application should be used.
II 5
i 9.14.12  ENTER the Noble Gas Activity and the Iodine Activity in Curies for Release Magnitude on Line 14 of the ENF using the Source Term Summary Report. The total activity is acceptable for reporting purposes unless a specific breakdown is requested by local State or county emergency management personnel. This step is NOT applicable to CR3.
9.14.13  CONVERT the RASCAL results in REM to mRem AND ENTER the Total Effective Dose Equivalent (TEDE) in mRem for the following distances in the appropriate blocks of the ENF using the Maximum Dose Values Report:
* site boundary
* 2.0 mile
* 5.0 mile, and 0    10 mile 9.14.14  CONVERT the RASCAL results in REM to mRem AND ENTER the Thyroid Committed Dose Equivalent (CDE) in mRem for the following distances in the appropriate blocks of the ENF using the Maximum Dose Values Report:
* site boundary,
* 2.0 mile
* 5.0 mile, and
* 10 mile I EMG-NGGC-0002                                Rev. 5                            Page 42 of 87
 
9.15  Save the Case 9.15.1 SELECT Save Case to save the projection for future review or revision. Consider the following:
: 1. The user creates the file name and RASCAL saves the projection file with a .STD extension.
: 2. The default folder for saved cases is C:\Program Files\RASCAL3\Save Case\.
: 3. The user may create a new subfolder for a group of projections for the current event. The recommended location for a new subfolder on the C: drive is under the default Save Case folder.
: 4. The case may be saved to a shared folder to allow both the TSC and EOF access.
The recommended location for a shared folder is in the applicable site drive:\Shared\RASCAL\. For example Crystal River 3 would use L:\Shared\RASCAL\. Subfolders may be created in the shared directory if desired.
: 5. The case may be saved to a specific file that is used for direct input to the Emergency Notification Form via WEBEOC. The case should only be saved here after approval by the RCM. The file name must remain as exists (e.g., don't add a date). Saving the case to this file will delete the previous case saved in this location. The specific location for each site is:
: a. BNP    K:SHARED\EP\ENF DATA\BNP WEBEOC.STD
: b. CR3    Does not have direct transfer to ENF capability
: c. HNP    Y:\Shared\Emergency Preparedness\ENFData\ HNP Unit 1 WebEOC.STD
: d. RNP    V:\Shared\Emergency Preparedness\ENF DATA\RNP Dose.STD 9.15.2    IF the default folder is not going to be used THEN CHANGE the directory as applicable.
9.15.3    ENTER a File Name.
NOTE:          If the shared case is to be modified, it needs to be copied back to the C:\RASCAL\Save Case\ folder on the hard drive. Otherwise, an error is encountered when editing met data.
9.15.4    SELECT Save.
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9.16  Field Measurements to Dose Model (FMDose)
The Field Measurement to Dose model would normally be used after releases had ended to determine whether the area is habitable or do residents need long-term relocation. The model estimates doses based upon measurement of ground contamination.
9.16.1 IF projecting doses from a release and at least one ground sample concentration for that sample location is available, THEN select Field Measurement to Dose Model (FMDose). This option is NOT normally used for performing early phase dose projections.
9.16.2 SELECT Event Description.
: 1. ENTER the Event name.
: 2. The following information is OPTIONAL and not required. ENTER the following as desired.
: a. Date AND time the release started.
: b. Release location in latitude AND longitude degrees.
: 3. SELECT OK and a "mark will appear in front of Event Description when this step is complete.
9.16.3 SELECT Sample Data.
: 1. ENTER the Sample ID.
: 2. ENTER the Date AND time the sample was analyzed.
: 3. VERIFY the correct sample ground concentration units by clicking on the >
symbol AND REVISE as necessary.
: 4. ENTER the sample nuclide AND ground concentration for each radionuclide.
: 5. The following information is OPTIONAL and not required. ENTER the following as desired.
: a. Sample location in latitude AND longitude degrees.
: b. Sample description.
: 6. SELECT OK and a -*'mark will appear in front of Sample Data when this step is complete.
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9.16  Field Measurements to Dose Model (FMDose) (continued) 9.16.4 SELECT Calculation Options AND REVISE the following parameters as necessary.
: 1. Intermediate Phase
: a. Reentry delay in days
: b. Select the DIL marker nuclide. The DIL marker is a single radionuclide contained in deposition or a sample that is easily identified in the field. It is used to determine areas of concern before performing a comprehensive isotopic analysis.
: 2. Factors used with Ground Concentrations
: a. Ground roughness correction factor
: b. Initial resuspension factor per meter
: c. Inadvertent ingestion rate in cm2 per day
: d. Occupancy time in hours per week
: e. Calculation settings in the desired units.
: 3. SELECT OK and a ,mark will appear in front of Calculation Options when this step is complete.
9.16.5 SELECT Compute Doses.
: 1. SELECT the desired data to review. Options include:
* Intermediate Phase Doses
* Deposition Exposure Rate DILs
* Marker Nuclide Concentration DILS
: 2. SELECT Print as desired.
9.16.6 SAVE the case per Section 9.15.
9.17  Multiple Release Points 9.17.1 PERFORM a separate RASCAL dose projection run for each release point.
9.17.2 Attachment 4, Multiple Release Point Calculation Sheet can be used as an aid for radioactive material releases from multiple plant locations.
10.0  RECORDS Records generated as a result of the performance of this procedure shall be submitted to Emergency Preparedness for retention in the plant vault.
EMG-NGGC-0002                  I            Rev. 5                              Page 45 of 87
 
ATTACHMENT I Sheet I of I RASCAL General Flowpath Select an event type -
Nuclear Power Plant or Spent Fuel Nuclear Power Plant                                      Soent Fuel Choose Event Location                              Choose Event Location Choose Source Term and Enter Required                  Choose Source Term and Enter Required Information:                                          Information:
    " Time Core is Uncovered
    " Ultimate Core Damage State                          " Pool Storage - Uncovered Fuel
    " Containment Radiation Monitor                        " Pool Storage - Damaged Assembly
    " Coolant Sample                                        Underwater
    " Containment Air Sample                              " Dry Storage - Cask Release
    " Effluent Isotopic Release Rates
    " Effluent Isotopic Release Concentrations
    " Monitored Releases - Mixtures                        Choose Release Path and Enter Required Information.
k Choose Release Path and Enter Required Information:
      " Wet Well
      " Dry Well
      " Secondary Containment Bypass
      " Containment Leakage/Failure
      " Steam Generator Tube Rupture V
Enter Meteorology Calculate Doses EMG-NGGC-0002                                    Rev. 5                  1              Page 46 of 87 1
 
ATTACHMENT 2 Sheet I of 2 Source Term Type Selection Guide This table lists all the source term types available for nuclear power plant accidents, guidance on when to use each type and the source terms available.
Source Term Type                          When Used                                        Data Needed      Available Release Paths Time Core Uncovered      Use when you can estimate how long the core will be      Reactor Shutdown? Date/Time BWR:
(Procedure Step 9.6.1)    uncovered and you want RASCAL to estimate the core      Core Uncovered? Date/Time  Wet Well damage that will result. Catastrophic event/release. Core Recovered? Date/Time  Dry Well However, if the release is in progress or has occurred                              Secondary Containment Bypass and is via a monitored pathway, use of the Monitored                                PWR:
Releases - Mixtures option is preferred and performed                                Containment leakage/failure in accordance with a site specific procedure.                                        Steam generator tube rupture Containment bypass Ultimate Core Damage      Use this option when you believe you can make a valid    Reactor Shutdown? Date/Time BWR:
State                    estimate of the amount of core damage that has          Core Damage state          Wet Well (Procedure Step 9.6.2)    occurred. It can also be used for "what if' analyses.      No damage                Dry Well However, if the release is in progress or has occurred    Fuel pin leakage          Secondary Containment Bypass and is via a monitored pathway, use of the Monitored      Cladding failure          PWR:
Releases - Mixtures option is preferred and performed                                Containment leakage/failure in accordance with a site specific procedure.            Time/Date coolant release  Steam generator tube rupture Containment bypass Containment Radiation  Use containment radiation monitor when you have          Reactor Shutdown? Date/Time BWR:
Monitor                readings from the containment monitor, you want the      Core Uncovered? Date/Time  Wet Well (Procedure Step 9.6.3)    code to estimate the core damage from the readings.      Containment Monitor        Dry Well However, if the release is in progress or has occurred  Reading/Date/Time          PWR:
and is via a monitored pathway, use of the Monitored                                Containment leakage/failure Releases - Mixtures option is preferred and performed in accordance with a site specific procedure.
Coolant Sample          Use coolant sample when you know the coolant            Sample ID                  BWR:
(Procedure Step 9.6.4)    activity and coolant will be released to the atmosphere. Date/Time                  Secondary Containment Bypass However, if the release is in progress or has occurred  Activity (Isotopic)        PWR:
and is via a monitored pathway, use of the Monitored                                Steam generator tube rupture Releases - Mixtures option is preferred and performed                                Containment bypass in accordance with a site specific procedure.
Containment Air Sample  Use air sample when you know the activity in the        Sample ID                  BWR:
(Procedure Step 9.6.5)    containment air and it will be released to the                                      Wet Well atmosphere via Containment leakage or failure.          Date/Time                  Dry Well However, if the release is in progress or has occurred  Activity (Isotopic)        Secondary Containment Bypass and is via a monitored pathway, use of the Monitored                                PWR:
Releases - Mixtures option is preferred and performed                                Containment leakage/failure
__                        in accordance with a site specific procedure.
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ATTACHMENT 2 Sheet 2 of 2 Source Term Type Selection Guide Source Term Type                              When Used                                        Data Needed            Available Release Paths Effluent Isotopic Release  Use the effluent rate when the release is through a      Release Location Rates                      sampled pathway that allows determination of the (Procedure Step 9.6.6)    release rate of nuclides in terms of activity per unit    Release Period(s) Date/Time      Release direct to atmosphere time.                                                    Activity (Isotopic)/unit time Effluent Isotopic Release  Use the effluent concentration when the release is        Release Location Concentrations            through a sampled pathway that allows determination of the release flow rate and the concentrations of        Release Period(s) Date/Time      Release direct to atmosphere (Procedure Step 9.6.7)    nuclides in terms of activity per unit volume.            Activity (Isotopic)/volume Monitored Releases -      Use the gross concentration method when you know          Reactor Shutdown? Date/Time Mixtures                  the concentration of the activity being released, but    Date/Time (Site specific procedures) you  do not know      composition thethe          by nuclide. Site                                        Release direct to atmosphere procedures  provide      method to calculate release    Sample Date/Time BNP: OPEP-03.4.8          rates (Ci/sec) for noble gases, iodines and particulates  Release Rate Unit CR3: EM-204B              using radiation monitor and flow rate information.        Release rates for:
noble gases HNP: PEP-344 iodines RNP: EPRAD-03                                                                          particulates Pool Storage -            Use this source term when fuel is exposed above the      Density of fuel pool racking Uncovered Fuel            water.                                                    Number or batches of assemblies  Spent fuel release pathway (Procedure step 9.8.1)                                                              irradiated within 1,2 and 3 years Fuel uncovered? Date/Time Pool totally drained? Yes/No Fuel recovered? Yes/No Pool Storage -              Use this source term when there are damaged              Number of damaged assemblies Damaged Assembly          assemblies underwater.                                    Age of damaged assemblies or      Spent fuel release pathway Underwater                                                                          how long damaged assemblies (Procedure step 9.8.2)                                                              have been in storage When damage occurred -
Date/Time Dry Storage - Cask          Use this source term when there are damaged              Type of Cask Release                    assemblies in a cask.                                    Age of damaged assemblies        Spent fuel release pathway (procedure step 9.8.3)                                                              Type of Event EMG-NGGC-0002                                                                    Rev. 5                                  Page 48 of 87
 
ATTACHMENT 3 Sheet I of I Weather Report Symbol, Model Class, and Intensity The following table lists typical nomenclature used by offsite weather agencies to report actual and forecast meteorological data. The table can be used to aid in interpretation of offsite meteorological information received.
WEATHER REPORT SYMBOL              MODEL CLASS            INTENSITY None                                    NONE                  ---
A                                        SNOW              Moderate IC-, IP-                                SNOW                Light IC, IP                                  SNOW              Moderate IC+, IP+                                SNOW                Heavy L-, L, L+                                RAIN                Light R-, RW-                                  RAIN                Light R, RW                                    RAIN              Moderate R+, RW+                                  RAIN              Heavy S-, SG-, SP-, SW-                        SNOW                Light S, SG, SP, SW                            SNOW              Moderate S+, SG+, SP+, SW+                        SNOW                Heavy ZL-, ZL, ZL+, ZR-                        RAIN                Light ZR                                        RAIN              Moderate ZR+                                      RAIN              Heavy I EMG-NGGC-0002                                Rev. 5            1              Page 49 of 87
 
ATTACHMENT 4 Sheet I of 1 Multiple Release Point Calculation Sheet RELEASE                          TIME      TEDE                TEDE              TEDE                TEDE              Total Curies CHARACTERISTIC                                (Site Boundary)    (2 Mile)          (5 Mile)            (10 Mile)
Main Stack Turbine Building Reactor or Auxiliary Building Torus Vent Other (1)TEDE SUM TOTAL (2) CURIE SUM TOTAL                        ________(2)
TIME      Thyroid CDE        Thyroid CDE      Thyroid CDE          Thyroid CDE (Site Boundary)    (2 Mile)          (5 Mile)            (10 Mile)
Main Stack Turbine Building Reactor or Auxiliary Building Torus Vent Other (3) Thyroid CDE TOTAL NOTE: TEDE and Thyroid CDE Summation are in units of REM and must be converted to Units of mrem prior to entering the information onto the Emergency Notification Form ((1) or (3)  Rem x 1000 =  _      mrem)
(1) Each TEDE Column Total corresponds to the TEDE line of the Emergency Notification Form.
(2) Enter the Sum of Total Curies on line 14 MAGNITUDE: (Other) of the Emergency Notification Form (BNP, HNP and RNP only).
(3) Thyroid CDE Column Total corresponds to line 16 (Thyroid CDE) of the Emergency Notification Form (BNP, HNP and RNP only).
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ATTACHMENT 5 Sheet I of 9 Brunswick Unit 1 and 2 Specific Actions and Parameters This attachment contains the following sections:
1.0    Brunswick Unit 1 and 2 Default Data 2.0    Data Sheet for Dose Projections 3.0    Meteorology 4.0    BNP Pathway/Source Term Option Guidance 1.0    Brunswick Unit 1 and 2 Default Data Unit 1:
Average reactor power    2923      Coolant volume    3.379E+04    Avg. fuel burnup-    30000 MW(th)                              (gal)                          MWD/MTU (in reactor)
Number of assemblies      560      Containment        1.641 E+05  Avg. fuel burnup-    50000 in core                            volume (ft3)                  MWDIMTU (in spent fuel storage)
Unit 2:
Average reactor power    2923      Coolant volume      3.218E+04  Avg. fuel burnup-        30000 MW(th)                              (gal)                          MWDIMTU (in reactor)
Number of assemblies in  560      Containment        1.641 E+05 Avg. fuel burnup-        50000 core                                volume (ft3)                  MWD/MTU (in spent fuel storage)
EMG-NGGC-0002                                Rev. 5                        Page 51 of 87
 
ATTACHMENT 5 Sheet 2 of 9 Brunswick Unit I and 2 Specific Actions and Parameters 2.0  Data Sheet for Dose Projections CHARACTERISTIC      TIME Main Stack          Release Rate (jt Ci/cc)
Flow Rate (CFM)
Turbine Building    #1 Release Rate (li Ci/cc)
                        #1 Flow Rate (CFM)
                        #2 Release Rate (li Ci/cc)
                        #2 Flow Rate (CFM)
Reactor Building    Release Rate (uCi/cc)
Flow Rate (CFM)
Torus Vent          Release Rate (jt Ci/cc)
Core Uncovered      Time (1) lost/ (2) Returned Effective Filtration Yes / No Release Height      Ground Elevated Release Duration    Anticipated Length of Time Shutdown            Date Time Met Data Wind Speed  Upper Lower Met Data Direction  Upper Lower Stability            Class Seabreeze            Yes / No EMG-NGGC-0002                                            Rev. 5                        Page 52 of 87
 
ATTACHMENT 5 Sheet 3 of 9 Brunswick Unit I and 2 Specific Actions and Parameters 3.0      METEOROLOGY 3.1    IF available ACQUIRE meteorological data by ERFIS.
3.1.1  PRESS the RETURN <CR> key a couple of times to awake the terminal.
3.1.2 IF the Terminal server port has been Logged-Off, THEN ENTER your name when prompted, AND PRESS RETURN <CR>. Any name will do, such as your last name.
NOTES:
: 1. The server prompt looks like "local>" or "DSVRxx" where xx is one of many ERFIS terminal server numbers.
: 2. Several of the connect messages may have to be tried to find an active connection.
: 3. Use Connect Sim for link to Simulator. This provides canned data. The other four will connect to live met data.
3.1.3 IF terminal is not in the above prompt condition at start of entry, THEN CONTACT ERFIS duty pager.
3.1.4 TYPE any one of the following at the keyboard, WHEN either of the prompts are displayed:
0    CONNECT    SIM        <CR> For the Simulator Computer.
0    CONNECT    ECO1A      <CR>  For the U1 ERFIS  Computer    TRA.
0    CONNECT    ECO1B      <CR>  For the U1 ERFIS  Computer    RTAD.
0    CONNECT    ECO2A      <CR>  For the U2 ERFIS  Computer    TRA.
0    CONNECT    ECO2B      <CR>  For the U2 ERFIS  Computer    RTAD.
3.1.5 TYPE your assigned USERNAME at the next LOGIN prompt. For example:
USERNAME: xxxxxxxxxx gepacuser <CR>
3.1.6 TYPE your assigned PASSWORD at the next LOGIN prompt. For example:
PASSWORD: xxxxxxxxxx gepac <CR>IF your next prompt is "Enter your last Name:" For example: xxxxxx <CR>
I EMG-NGGC-0002                    I              Rev. 5                            Page 53 of 87
 
ATTACHMENT 5 Sheet 4 of 9 Brunswick Unit I and 2 Specific Actions and Parameters 3.0    METEOROLOGY 3.1.7 TYPE your last name or work group, for example OPS, CHEMISTRY etc.
THEN the Computer Node prompt will appear (i.e., $, ECQ1A::>, ECO1 B::>,
ECO2A::>, or ECO2B::>).
3.1.8 TYPE W <CR> and the ERFIS computer will display your WEATHER for the previous 15 minutes. The W*EATHER is a logical name assigned to all the computers listed above.
NOTES:
: 1. Typing W <CR> is all that is necessary because no other DIGITAL Command starts with this letter.
: 2. Weather is obtained by modem from the ERFIS computer to the MET Tower every 15 minutes.
Always use the Logical W*EATHER for update to obtain the latest information.
3.1.9 TYPE LOG <CR> to end the connection to any of the above Computers, AND TERMINATE the process.
3.2  IF ERFIS data is unavailable THEN OBTAIN Brunswick Nuclear Power Plant (BNP)
Meteorological Data from the National Weather Service OR Wilmington National Weather Service data by phone. (See EPL-O01, Emergency Phone List, for the telephone number).
3.3  DETERMINE the Sea Breeze Potential.
3.3.1  IF all of the following conditions are present, THEN the potential for a Sea Breeze Effect exists:
: 1. BNP wind direction is between 16' and 2690, AND
: 2. BNP Stability class of A, B, or C
: 3. Meteorological Data Record time is between 0700 and 1900 hours, AND
: 4. Meteorological Data Record date and date of Sea Breeze onset time are the same.
EMG-NGGC-0002                                Rev. 5                          Page 54 of 87
 
ATTACHMENT 5 Sheet 5 of 9 Brunswick Unit 1 and 2 Specific Actions and Parameters 3.0    METEOROLOGY 3.4    IF a Sea Breeze is present, THEN RASCAL projections may underestimate the dose by a factor of 2.5, and the plume behavior may be erratic. Entering additional weather station data will improve the accuracy of modeling a sea breeze condition.
3.4.1  IF Sea Breeze conditions exist during the case calculations, THEN CONSPICUOUSLY MARK printed reports as such.
3.4.2  POINT this out AND COMMUNICATE to the RCD, RCM, and other dose projection coordinators, when the reports are made available to them.
3.5    OBTAIN stability class from the Met Tower.
3.6    DETERMINE the stability class.
3.6.1  IF available OBTAIN data for stability class from the Met Tower.
3.6.2 IF stability class data is not available from the Met Tower THEN CALL the National Weather Service to obtain the data.
3.6.3 IF stability class data is not available from the Met Tower or National Weather Service THEN DETERMINE the class using the following steps.
NOTES:
: 1. Delta T - (Preferred method of determination) - Temperature difference between the 10m and 100m measuring points on the Met tower. Normally a negative number, but could be positive if a temperature inversion exists.
: 2. Sigma theta - (Secondary method of determination) -Standard deviation of the horizontal wind direction fluctuation.
: 1. IF meteorological data is available THEN OBTAIN Delta T1 and Delta T2.
: a. CALCULATE the Differential Temperature BY SUMMING Delta T1 and Delta T2 THEN DIVIDING by 2. See equation below:
DTI+DT2=                C/100M 2
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ATTACHMENT 5 Sheet 6 of 9 Brunswick Unit I and 2 Specific Actions and Parameters 3.0  METEOROLOGY
: b. COMPARE the differential temperature in the table below to the Pasquill categories to determine the stability class.
STABILITY                PASQUILL            Differential Temperature CII00M CLASSIFICATION              CATEGORIES Extremely Unstable                    A                            <-1.9 Moderately Unstable                    B                        -1.9 TO -1.7 Slightly Unstable                      C                        -1.7 TO -1.5 Neutral                                D                        -1.5 TO -0.5 Slightly Stable                        E                        -.05 TO +1.5 Moderately Stable                      F                        +1.5 TO +4.0 Extremely Stable                      G                            > +4.0
: 2. IF there is no stability class data readily available, AND it is raining THEN ASSUME the stability class is D, OTHERWISE ESTIMATE the current Atmospheric Stability Class by visual observation using the following table:
SUNNY DAY            CLOUDY          CLOUDY          CLEAR NIGHT DAY            NIGHT LIGHT WIND/OR              B                  C                E                F CALM
      *4 m/sec or 8.9 mph MODERATELY                C                  D                D                D STRONG WIND
      &#x17d;4 m/sec or 8.9 mph IEMG-NGGC-0002                  I              Rev. 5            1                Page 56 of 87
 
ATTACHMENT 5 Sheet 7 of 9 Brunswick Unit I and 2 Specific Actions and Parameters 3.0  METEOROLOGY 3.6.4 REFER to the following table when an elevated release exists since, maximum radiological exposures may occur beyond the site boundary depending on Stability Class. For example:
STABILITY CLASS                    DOWNWIND DISTANCE A                                0.27 MILES B                                0.45 MILES C                                0.76 MILES D                                1.8 MILES E                                3.5 MILES F                                9  MILES G                                33 MILES I EMG-NGGC-0002            I            Rev. 5                          Page 57 of 87
 
ATTACHMENT 5 Sheet 8 of 9 Brunswick Unit I and 2 Specific Actions and Parameters 4.0 BNP PATHWAY/SOURCE TERM OPTION GUIDANCE "p
Pathways Vessel ---- Drywell  ----------- Environment--------------------------  pathway 1 unmonitored Vessel ---- Drywell -----
Reactor Building -------- Environment --------- pathway 2 monitored Vessel---Drywell--Reactor Building SBGT--stack--Environment-- pathway 3 monitored Vessel---Torus ------ Environment          --------------------        pathway 4 unmonitored Vessel--- Torus---Reactor Building--SBGT-- stack--Environment--- pathway 5 monitored Vessel--- Torus---Reactor Building --------- Environment --------- pathway 6 monitored Vessel ---- Turbine Building---Environment ------------------            pathway 7 unmonitored Vessel---- Turbine Building---Environment-------------------              pathway 8 monitored Vessel---- Turbine Building---SBGT ----- stack      ----------------- pathway 9 monitored EMG-NGGC-0002                I            Rev. 5                                Page 58 of 87
 
ATTACHMENT 5 Sheet 9 of 9 Brunswick Unit I and 2 Specific Actions and Parameters Source Term Pathway 1    ---------------- Time Core is Uncovered Containment Radiation Monitor Containment Air Sample Pathway 2  ---------------    Time Core is Uncovered Containment Radiation Monitor Containment Air Sample Pathway 3  ---------------    Time Core is Uncovered Containment Radiation Monitor Containment Air Sample Pathway 4  ----------------  Time Core is Uncovered Containment Radiation Monitor Containment Air Sample Pathway 5    ----------------  Time Core is Uncovered Containment Radiation Monitor Containment Air Sample Pathway 6  ----------------    Time Core is Uncovered Containment Radiation Monitor Containment Air Sample Pathway 7  ---------------  Time Core is Uncovered Ultimate Core Damage State Coolant Sample Pathway 8  ---------------    Time Core is Uncovered Ultimate Core Damage State Coolant Sample Pathway 9  ---------------    -Time Core is Uncovered Ultimate Core Damage State Coolant Sample EMG-NGGC-0002                          Rev. 5                      Page 59 of 87 1
 
ATTACHMENT 6 Sheet I of 10 Crystal River Specific Actions and Parameters This attachment contains:
1.0    Crystal River 3 Default Data - Sheet 1 2.0    CR3 Accident Types With Rascal Source Term/Release Path Options - Sheet 2 This sheet provides guidance for selecting RASCAL source term and release path options.
Assumptions should be verified with the Technical Support Team and/or the Accident Assessment Team.
3.0    Site Boundary (0.83 miles) Dose Estimate Credibility Evaluation - Sheet 3 4.0    Meteorological Data Input Sheet - Sheet 5 5.0    Radiological Data Input Sheet - Sheet 6 6.0    Alternate Methods For Determining Meteorological Data - Sheet 7 7.0    Methods For Determining Core Damage - Sheet 8 1.0    Crystal River 3 Default Data (Edit plant parameters as necessary.)
Average reactor power        2609    Coolant volume      9.401 E+04 Avg. fuel burnup-      42000 MW(th)                                    )MWDIMTU                            (in
                                    )(gal)                        reactor)
Number of assemblies in      177    Containment        2.000E+06  Avg. fuel burnup-      35000 core                                volume (ft3)                  MWDIMTU (in spent fuel storage)
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ATTACHMENT 6 Sheet 2 of 10 Crystal River Specific Actions and Parameters 2.0    CR3 ACCIDENT TYPES WITH RASCAL SOURCE TERM I RELEASE PATH OPTIONS ACCIDENT TYPE                  RELEASE POINT                  RASCAL SOURCE                          RASCAL RELEASE TERM OPTIONS                              PATH OPTIONS Ultimate Core Damage State LOCA in containment          Containment to atmosphere                                            Containment Leakage/Failure Containment Rad Monitor              with pressure/hole size selected OR percent volume Containment Air Sample              selected for Design Basis Leakage Time Core is Uncovered Containment to Intermediate      Ultimate Core Damage State          Containment Leakage/Failure Bldg                  Containment Rad Monitor              with pressure/hole size selected Containment Air Sample Time Core is Uncovered Containment to Aux Bldg          Refer to LOCA in Aux Bldg            Refer to LOCA in Aux Bldg Post-accidentMonitored                      Release  - Mixture      Release Direct to Atmosphere Coolant Sample                      Containment Bypass or eCore Damage State        Containment Leakage/Failure Ultimate Cselected Time Core is Uncovered LOCA in Aux Bldg            Aux Bldg                        Monitored Release - Mixture*        Release Direct to Atmosphere Effluent Isotopic Release Conc Ultimate Core Damage State          Containment Bypass or Containment Rad Monitor              Containment Leakage/Failure selected Steam Gen Tube Rupture      Steaming to atmosphere          Coolant Sample                      Steam Generator Tube Ultimate Core Damage State          Rupture Condenser to Aux Bldg vent      Monitored Release - Mixture*        Release Direct to Atmosphere Ultimate Core Damage State          Steam Generator Tube Rupture Fuel Handling                Aux Bldg                        Pool Storage - Damage                Spent Fuel Release Path Underwater Pool Storage - Fuel Uncovered Monitored Release - Mixture*          Release Direct to Atmosphere Waste Gas Decay Tank        Aux Bldg                        Monitored Release - Mixture*          Release Direct to Atmosphere Effluent Isotopic Release Conc Effluent Isotopic Release Rate
* Monitored Release - Mixture is the preferred option if the release is monitored EMG-NGGC-0002                                              Rev. 5                                              Page 61 of 87
 
ATTACHMENT 6 Sheet 3 of 10 Crystal River Specific Actions and Parameters 3.0      Site Boundary (0.83 miles) Dose Estimate Credibility Evaluation Dose estimates in the first hour of a release may be compared with estimates in this table as a credibility check; however, actual dose rates could vary by orders of magnitude depending on plant conditions. Row 1 for extended shutdown conditions, all other rows for on-line conditions.
Monitor Reading or        Type of        Notes          Thyroid      TEDE              Gas            Iodine Accident Type          Source Term                      mR per      mR per          Ci/sec          Ci/sec Estimate                      one hour    one hour Extended Shutdown:          RASCAL ST            12            730        1000 RM-A2 Accident Range at 10 Ci/sec (0.45 pCi/cc)
RM-AI Accident Range        Worksht ST          1, 3            2.6          1.8 at 1 Ci/sec (4.3E-2 pCi/cc)
RM-A2 Accident Range        Worksht ST          1, 3            2.6          1.8 at 1 Ci/sec (1.4E-2 pCi/cc)
RM-G29/30                    Worksht ST          3,4            280          12 at 100 R/hr                  RASCAL ST          2,4              12          0.6 LOCAN                        CR3 Default        3, 5          < 0.1        < 0.1          1.OE-5          1.OE-7 NO Core Damage              RASCAL ST            6              0.2          0.5 LOCAG                        CR3 Default        3, 5            15          1.8            0.7            0.01 Clad Failure                RASCAL ST            7              770          38 LOCAC                        CR3 Default        3, 5            130          29              14            0.086 Fuel Melting                RASCAL ST            7            6300        350 WGDTR                        CR3 Default        3,5              9          0.1            5.4          4.2E-5 FHA                          CR3 Default        3,5              11          110            68            6.7E-3 RASCALST            8            < 0.1        0.1 SGTRN                        CR3 Default        3,5              24            1            0.016          0.016 NO Core Damage              RASCAL ST            9            < 0.1        < 0.1 Typical RCS          10            < 0.1        < 0.1 SGTRG                        CR3 Default      3,5,11            2.7E5      1.3E4            1100              180 Clad Failure                RASCAL ST            9              100            5 SGTRC                        CR3 Default      3, 5,11          2.1 E6      1.2E5          2.2E4            1400 Fuel Melt                    RASCAL ST            9              730          42 I EMG-NGGC-0002                                        Rev. 5          1              Page 62 of 87
 
ATTACHMENT 6 Sheet 4 of 10 Crystal River Specific Actions and Parameters 3.0 Continued Standard Assumptions:
RASCAL model, NO holdup time, release height 0, building wake Yes, E stability class, 1 rn/sec wind, NO rain, RB cfm=50,000; AB cfm=156,000 Assumption Notes From Table:
: 1. Base lI/NG Ratio=l, Iodine DFs: Partitioning=1, Plateout=3, Sprays=10, Filters=20 Base P/NG Ratio=0.1, Particulate DFs: Partitioning=l, Plateout=10, Sprays=10, Filters=100
: 2. RASCAL options: Containment Radiation Monitor, Containment Leakage/Failure
: 3. RASCAL options: Monitored Release - Mixtures, Release Direct to Atmosphere. The site boundary doses for RM-A1 and RM-A2 are equal because both monitors are assumed at 1 Ci/sec. However, because of the higher flow rate on RM-A2, less pCi/cc is required to achieve I Ci/sec.
: 4. 30 psig, 1 square inch hole, spray off
: 5. 2001 default Ci/sec calculations were used to derive total pCi/cc and allocation percentages for noble gases and halogens.
: 6. RASCAL options: Ultimate Core Damage State, Containment Bypass, 100 gpm
: 7. RASCAL options: Ultimate Core Damage State, Containment Leakage/Failure, Design Basis Leakage
: 8. 1 assembly damaged, 1 month old, RASCAL options: Assembly Damaged Underwater, Release Direct Atmosphere, 100% / hr
: 9. RASCAL options: Ultimate Core Damage State, Steam Generator Tube Rupture, 100 gpm
: 10. RASCAL options: Coolant Sample (typical on-line concentrations), Steam Generator Tube Rupture, 100 gpm
: 11. There is a huge disparity between the CR3 default doses and doses derived using the standard RASCAL source terms. The RASCAL source terms should be considered more credible. The CR3 default doses should be viewed as the upper limit doses bounding a SGTR event with core damage.
: 12. The TEDE dose is the EM-202 EAL 1.4 Protective Action Guideline (PAG) threshold value for extended shutdown conditions as documented in Calculation N12-0001.
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ATTACHMENT 6 Sheet 5 of 10 Crystal River Specific Actions and Parameters 4.0          METEOROLOGICAL DATA INPUT SHEET DATE/TIME OF TRIP:                                    DATE/TIME OF RELEASE:
Sources listed by priority - enter number of source data used in each column heading
: 1. 33ft Primary Tower
: 2. 175ft Primary Tower
: 3. 33ft Alternate Tower
: 4. Other METEOROLOGICAL DATA Rec    Obs    Date  Data        Wind                Wind            Sigma Theta Deg        Stability        Rain        Air Or            Time      Direction            Speed                    or              Class          Inches      Temp Fcst                      From                mph              Wind Range Deg                            Per        Deg F Deg                                          or                              15 min Delta T Deg F
          .4-      4      4      I                4                    +                      4              I.              I
          -I-      4      4      4                4                    +                      4              4                I
          +        4      4      4                4                    +                      4              4                4
          +        4
* 4                                      1~                      I              I                I
          -I-      4      4      4                1                                            1              4                4 IEMG-NGGC-0002                              I                        Rev. 5                      1              Page 64 of 87
 
ATTACHMENT 6 Sheet 6 of 10 Crystal River Specific Actions and Parameters 5.0    RADIOLOGICAL DATA SHEET Projection  Date  Data  Accident  Release  Release    Release  Gas pCilcc Iodine  Release    Sprays Number            Time    Type      Start    Stop    Flow Rate            pci/cc  Filtered    On/Off Time    Time      CFMIGPM                      Yes/No I EMG-NGGC-0002                                        Rev. 5                            Page 65 of 87        :
 
ATTACHMENT 6 Sheet 7 of 10 Crystal River Specific Actions and Parameters 6.0  ALTERNATE METHODS FOR DETERMINING METEOROLOGICAL DATA: The following steps are OPTIONAL and may be used as needed to obtain data.
6.1    ESTIMATE wind direction, wind speed, and wind range BY OBSERVING cooling tower vapor, flags, fossil stack smoke, etc.
6.2    DETERMINE Stability class by using Sigma Theta (preferred), Delta T, or wind range. Wind range is the difference (in degrees) between the highest and lowest wind direction tracing on the recorder for a 15 minute period.
SIGMA THETA              DELTA T            WIND RANGE,      STABILITY CLASS (degrees)            (DEGREES)              (degrees)
                > 22.5                < -1.46              > 135    A (most dispersed plume)
            < 22.5 to 17.5        -1.45 to -1.31        134 to 105  B
            < 17.5 to 12.5        -1.30 to -1.16          104 to 75  C
            < 12.5 to 7.5        -1.15 to -0.39          74 to 45  D
            < 7.5 to 3.8          -0.38 to 1.15          44 to 23  E
            < 3.8 to 2.1          1.16 to 3.07          22 to 13  F
                < 2.1                  > 3.08                < 12    G (most concentrated plume) 6.3    DETERMINE wind direction by estimating the average value of the tracing for a 15 minute period.
6.4    OBTAIN weather data via the intra/internet by CHOOSING sites as required listed below.
6.4.1    GO TO AccuWeather.com.          ENTER zip code 34428 AND hour-by-hour.
6.4.2 GO TO Weather.com. ENTER zip code 34428 AND select hourly.
6.4.3 GO TO Energy Control Center: Progress Net, Business Units and Departments, Energy Control Center Florida, Forecasts, Real Time Weather, Zone City Forecasts, THEN CLICK west central Florida area on map.
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ATTACHMENT 6 Sheet 8 of 10 Crystal River Specific Actions and Parameters 6.5    OBTAIN meteorological data from the following sources if desired, however, non-local backup sources may NOT be representative. Phone numbers are in the Off-site Support Directory.
0      Primary Backup - FAA Flight Service Station in Gainesville, FL.
0      Secondary Backup - Tampa Weather Service in Ruskin, FL.
6.6    REFER to the following table to DETERMINE sectors affected based on the wind from direction.
DEGREES        SECTORS            DEGREES        SECTORS        DEGREES    SECTORS 349-11 (349-        HJ K        102-123 (462-483)    NP Q        214-236      BC D 371) 12-33 (372-393)      J KL        124-146 (484-506)    PQ R        237-258      CDE 34-56 (394-416)      KL M        147-168 (507-528)    QRA        259-281      DE F 57-78 (417-438)      LM N        169-191 (529-540)    RAB        282-303      EFG 79-101 (439-        MNP              192-213        ABC        304-326      FGH 461) 327-348      GHJ 7.0  METHODS FOR DETERMINING CORE DAMAGE This section lists three methods of selecting accident type based on the level of core damage. Each method has advantages and disadvantages. Use the most appropriate method (or combination) to predict the level of core damage. Methods are:
* Based on RM-G29 and RM-G30 readings
* Based on Iodine ratio
              "  Based on RCS pressure and temperature I EMG-NGGC-0002                  I            Rev. 5                            Page 67 of 87
 
ATTACHMENT 6 Sheet 9 of 10 Crystal River Specific Actions and Parameters 7.1 DETERMINE BASED ON RM-G29 AND RM-G30 NOTE:    This method can be performed quickly, but requires a breach of the Reactor Coolant System. The monitor readings assume thorough mixing of the Reactor Building atmosphere which may take several hours. Earlier readings will likely be higher (conservative).
7.1.1    OBTAIN RM-G29 and RM-G30 readings.
* IGNORE spikes AND ESTIMATE the sustained monitor reading.
* DETERMINE accident type using the estimated value and the following data:
RM-G29/30 R/HR                          ACCIDENT TYPE
                      <100                                  Normal Coolant 100 - 25000 WITH RB SPRAY            Gas Gap Damage 100 - 75000 WITHOUT RB SPRAY          Gas Gap Damage
                      >25000 WITH RB SPRAY                  Core Melt
                      >75000 WITHOUT RB SPRAY                Core Melt 7.2 DETERMINE BASED ON IODINE RATIOS.
NOTE:    This method requires a gamma isotopic of a grab sample, which must be performed offsite.
There is NO way to distinguish between a gap release and a core melt release using iodine ratios.
7.2.1 ANALYZE a liquid or gas sample representative of the post-accident source term.
7.2.2 DETERMINE the ratio of 1-131 to Total Iodine.
* IF 1-131/Total Iodine is < 0.05 THEN ASSUME LOCAN or SGTRN.
* IF 1-131/Total Iodine is _&#x17d;0.05 THEN ASSUME LOCAG or SGTRG.
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ATTACHMENT 6 Sheet 10 of 10 Crystal River Specific Actions and Parameters 7.3      DETERMINE BASED ON RCS PRESSURE AND TEMPERATURE
                                                                                                                        --- I NOTE:              This method can be performed quickly, but will NOT indicate mechanically-induced core damage. The intersection of pressure from the Y axis and temperature from the X axis is the level of core damage. (Regions are from the Inadequate Core.)
7.3.1    LOCATE the region on the graph where the RCS Pressure (psig) and the Tincore (degrees F) intersect.
7.3.2 IF intersection is Region 1 OR Region 2 THEN NO fuel damage exists. RCS activity is considered normal.
7.3.3 IF intersection is Region 3 THEN possible gas gap failure exists.
7.3.4 IF intersection is Severe Accident Region THEN possible core melt exists.
30( 00 275 50          'JSATURATIONJ  _
2500o 22550 20000 S175 WW  150 jO 0o                                                                                    /
                                                      -                                    -
REGION 1I
  'f)  125 REGION 3 50                                                                      TCLA-2! 1400 OF
                  -0
                                                /
* j            SEVERE 0    -                                                                                  ACCIDENT 25                                                                                            REGION 50 -                                                                                    TCLAD > t:800 &deg;F 0 .      '
200    300    400  500  600  700  800  900  1000  1100 1200 1300  1400    1500 1600  1700    1800 Tincore (*F)
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ATTACHMENT 7 Sheet I of I H.B. Robinson Specific Actions and Parameters 1.0    H.B. Robinson Default Data Average reactor power        2339    Coolant volume      4.468E+04  Avg. fuel burnup-      30000 MW(th)                                    )MWDIMTU                              (in
                                        )(gal)                          reactor)
Number of assemblies in      157    Containment          2.100E+06  Avg. fuel burnup-      50000 core                                  volume (ft3)                    MWD/MTU (in spent fuel storage) 2.0    Release Height Parameters USE the following height for radiological release points to the environment:
* Plant Vent Stack:                  62 meters (203 feet)
* Other non-vent stack releases:      11 meters (36 feet)
Thirty-six (36) feet is equivalent to the ground level sensors at eleven (11) meters on the site meteorological tower.
3.0    Meteorological Data 3.1    OBTAIN met data from the appropriate source (OSI/PI, ERFIS, National Weather Service, Weather Services International (WSI), etc.).
3.2    IF a weather agency provides a written weather report, Attachment 3 provides information for weather report symbols. The minimum met data required for dose projection model is wind speed and direction.
3.3    IF OSI/PI and ERFIS are unavailable THEN REFER to EPRAD-03 for further guidance to obtain meteorological data.
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ATTACHMENT 8 Sheet I of 16 Shearon Harris Specific Actions and Parameters This attachment contains the following sections:
1.0    Shearon Harris Default Data - Sheet 1 2.0    Effective Release Heights - Sheet 1 3.0    Meteorological Data - Sheet 2 4.0    Calculate Dose Equivalent Activity - Sheet 7 5.0    HNP Source Term Type Selection Guide - Sheet 11 1.0    Shearon Harris Default Data 1.1    Following R17, when comparing RASCAL results with other agencies, it will be important to communicate the changes from the default values in the plant parameter table.
1.2    Following R17, VERIFY that the HNP Plant Parameters match the value in the following table, IF not THEN adjust to those values Average reactor power            2948*      Coolant              7.71OE+04    Avg. fuel burnup-    39,870**
MW(th)                                      volume                            MWDIMTU (in (gal)                              reactor)
Number of assemblies in          157        Containment          2.344E+06    Avg. fuel burnup-    59,800**
core                                        volume (ft3)                      MWDIMTU (in spent I_                              I        _ I_                                  fuel storage)        _
*From EC 74914 IMPLEMENT LICENSE CHANGE FOR THE MUR UPRATE, B.1.2 Table 1
**From EC75840 HNP CYCLE 18 CORE DESIGN AND SAFETY ANALYSIS, Table B.1: Cycle 18 Neutronics Results.
Avg. Fuel burnup (in reactor) parameter is based upon two-thirds of the EC 75840 value per NUREG 1887 Section 1.1.6 2.0    Effective Release Heights (enter the release height of the release point) 2.1    Use the following height for stack releases.
0    Stack  1 (RAB & FHB)          27.4  meters  (90 feet) 0    Stack  3 (TB)                  19.2  meters  (63 feet) 0    Stack  5 (WPB)                24.1  meters  (79 feet) 0    Stack  5A (WPB)                18.3  meters  (60 feet)
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ATTACHMENT 8 Sheet 2 of 16 Shearon Harris Specific Actions and Parameters 2.2    Use the following height for non-stack releases.
                "  Steam dumps                18.3  meters (60 feet)
* PORVs                      14.9  meters (49 feet)
                "  Main Steam Safeties        15.9  meters (52 feet)
* CVPETS (TB Stack)          19.2  meters (63 feet) 2.3    If the release is not from one of the fixed sources noted above, then enter the actual height of the release point.
3.0  Meteorological Data 3.1    OBTAIN met data from the appropriate source (OSI/PI, ERFIS, National Weather Service, Weather Services International (VVSI), etc.). For guidance on obtaining data from ERFIS, see the EP Training Module EP-08, ERFIS located at:
http://nqgweb/hnppassportdm/Mcen/EP-MODU LEEP08. Ddf NOTE: All release points at HNP are considered to be a ground level release due to the stack height being less than 2.5 times the height of any surrounding building. Therefore, the 12.5 m wind direction and speeds are used as input into the meteorological data.
3.2    The HNP Site Meteorological Data inputs from ERFIS are:
: a. Wind Direction (from) in degrees (ERFIS ID MMT1014 Avg. Wind Direction @
12.5 m)
: b. Speed (mph) (ERFIS ID MMT1008 Avg. Wind Speed @ 12.5 m) 3.3    IF a weather agency provides a written weather report, Attachment 3 provides information for weather report symbols. The minimum met data required for dose projection model is wind speed and direction.
3.4    The default data set for HNP is HARR - Shearon Harris. Other data sets based on met data monitoring locations applicable for performing complex calculations are:
* BUY - Burlington
* FAY - Fayetteville
* HARR - Shearon Harris (Default)
* GSO - Greensboro
* IGX - Chapel Hill
* MEB- Maxton
* RDU - Raleigh-Durham 3.5    IF OSI/PI and ERFIS are unavailable THEN ACESS met data via modem connection.
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ATTACHMENT 8 Sheet 3 of 16 Shearon Harris Specific Actions and Parameters CAUTION For cyber security reasons, the phone line connection at the modem must only be connected while the EOF is activated.
3.5.1  CONNECT phone line to the modem.
3.5.2 SELECT mettower.
3.5.3 WAIT for Windows to display the CONNECT TO box.
3.5.4 SELECT OK.
3.5.5 WAIT for Windows to display the CONNECT box.
3.5.6 SELECT the DIAL.
3.5.7 WAIT for the HyperTerminal screen to be displayed. The display will have a clear screen.
3.5.8 VERIFY the Caps Lock is off OTHERWISE turn the Caps Lock off.
3.5.9 TYPE in "u" THEN CLICK the Enter key. The "u" will NOT be seen but the following display will appear.
USER MENU (C) Communications Menu            (T) Test Menu (F) System Functions Menu          (Z) Zeno Program Menu (S) Sample Period Menu              (Q) Quit (D) Data Retrieval Menu            (H) Help I EMG-NGGC-0002              I              Rev. 5                          Page 73 of 87
 
ATTACHMENT 8 Sheet 4 of 16 Shearon Harris Specific Actions and Parameters 3.5.10 TYPE in "d" THEN CLICK the Enter key. The following display will appear.
DATA RETRIEVAL MENU (A) Show Records AFTER Specified Time          (F) Flash Memory Information (B) Show Records BETWEEN Timespan              (D) Delete All Data Records (Ln) Show LAST n Records                        (N) Number Of Records Logged
(*) Show ALL Data Records                      (U) User Menu
(@n) Show n Unmarked Records                    (Q) Quit (M) Mark Recently Shown Data                    (H) Help (C) Compute Data Logging Capacity Precede Any "Show Data" Command With An 'X' For X-Modem Transfer (e.g. Enter 'X*' To Send All Data Sets Via X-Modem) 3.5.11 TYPE in I1 (NOTE: this is a small "I"and a "1") THEN CLICK the Enter key.
The following display of the last 15-minute average Met data will appear.
Sample display:
IEMG-NGGC-0002                            Rev. 5            1            Page 74 of 87
 
ATTACHMENT 8 Sheet 5 of 16 Shearon  Harris  Specific    Actions and Parameters NOTE:      Lines 2 and 3 below provide the data codes. Lines 4 and 5 provide the respective values. For example, the first value in line 2 (DATE) corresponds to the first value in line 4 (02/04/10), the third value in line 2 (AT 11 1 av) corresponds to the third value in line 4 (63.57), etc. Each data code in lines 2 and 3 has a corresponding value in lines 4 and 5. The table on the next page explains the codes on lines 2 and 3.
Line 1    Hit The Space Bar To Halt The Log Data Output.
Line2      DATE TIME AT 11 1 avWSPD_61 avWVAR_61 avWDIR_61 avWDIR_12_avWVAR_12 Line 3    _avWSPD 12 avAT 60 1 avRH_11_avDTIavDT_2_av                          RAIN BP_
av SOLAR av DP av Line4      02/04/1008:30:01 63.57 6.30 15.78 359.25 3.30 15.34                  4.14 62.7 Line 5    3 93.88 -0.96 -0.85        0.00 30.00      0.21 61.81 Line 2 and Line 3 Code                    Description                  ERFIS ID DATE                          Date                                  N/A TIME                          Time                                  N/A AT 11 1 av WSPD 61 av                    Avg. Wind Speed @ 61.4 m              MMT1010 WVAR 61 av                    Avg. Wind Direction Variance @ 61.4 m MMT1012 WDIR 61 av                    Avg. Wind Direction @ 61.4 m          MMT1013 WDIR 12 av                    Avg. Wind Direction @ 12.5 m          MMT1014 WVAR 12 av                    Avg. Wind Direction Variance @ 12.5 m MMT1009 WSPD 12_av                    Avg. Wind Speed @ 12.5 m              MMT1008 AT 60 1 av RH 11 av                      Avg. Relative Humidity                MMT1018 DT 1 av                        Avg. Delta Temperature 1 C/100 m      MMT1005 DT 2 av                        Avg. Delta Temperature 2 C/100 m      MMT1004 RAIN                          Precipitation, 15 min                MMT1003 BP av                          Avg. Barometric Pressure              MMT1002 SOLAR-av                      Avg. Solar Radiation Langley/Min      MMT1001 DP-av                        Avg. Dew Point, OF                    MMT1000 EMG-NGGC-0002                                  Rev. 5                          Page 75 of 87
 
ATTACHMENT 8 Sheet 6 of 16 Shearon Harris Specific Actions and Parameters DATA RETRIEVAL MENU (A) Show Records AFTER Specified Time                  (F) Flash Memory Information (B) Show Records BETWEEN Timespan                      (D) Delete All Data Records (Ln) Show LAST n Records                              (N) Number Of Records Logged
(*) Show ALL Data Records                              (U) User Menu
(@n) Show n Unmarked Records                  (Q) Quit (M) Mark Recently Shown Data                  (H ) Help (C)    Compute Data Logging Capacity Precede Any "Show Data" Command With An 'X' For X-Modem Transfer (e.g. Enter 'X*' To Send All Data Sets Via X-Modem) 3.5.12 TYPE in "q" THEN CLICK the Enter key to quit the Met menu.
3.5.13 SELECT the CALL dropdown AND THEN the DISCONNECT option on the HyperTerminal Command Bar at the top to terminate the modem connection to the Met Tower.
3.5.14 IF there is an extended period of inactivity THEN the Met Tower processor will automatically terminate the User interface menu.
: 1. At this point data may be retrieved again by going to step 4.4.6 if this attachment.
3.5.15 VERIFY the phone line is disconnected at the modem when the EOF is deactivated.
3.6    USE the following ERFIS Points if needed for met data:
* Speed in mph    - MMT1008
* Stability Class - MMT1017 3.7    IF OSI/PI and ERFIS are not available to provide the stability class THEN an alternate method that may be used is shown below.
3.7.1 IF only one ERFIS AT channel is available (computer point MMT 1004 or MMT 1005), THEN USE the following table to determine the stability class.
EMG-NGGC-0002                                  Rev. 5                              Page 76 of 87
 
ATTACHMENT 8 Sheet 7 of 16 Shearon Harris Specific Actions and Parameters Stability Classes AT in &deg;C/100m                Class
_<-1.9&deg;                    A or 1
                                  >-1.9  0 to*_< -1.70          B or 2
                                  >-1.7 0 to_<-1.5 0          C or 3
                                  >-1.5  0 to*_< -0.5 0        D or 4
                                  >-0.50 to <+1.50              E or 5
                                  >+1.5 0 to_< +4.00            F or 6
                                  >+4.04                      G or 7 3.7.2 IF the stability class is not available THEN USE the following table to choose the appropriate value:
Surface Wind    Daytime Solar Radiation                        Nighttime Conditions  Day or Speed (mph)      (For moderate cloud cover move one                                    Night column to the right)
Summer\      Spring &Fall        Winter      Thin        <3/8      Heavy overcast    cloud    Overcast Clear Sky    Clear Sky                        (>1/2 cloud  cover    or Rain cover)
      <4.5            A            A-B                B            E            F        D 2t 4.5 to 9.0    A-B          B                  C            E            F        D
      > 9.0 to 13.5    B            B-C                C            D            E        D
      > 13.5          C            C-D                D            D            D        D I EMG-NGGC-0002                                    Rev. 5                                  Page 77 of 87 1
 
ATTACHMENT 8 Sheet 8 of 16 Shearon Harris Specific Actions and Parameters 4.0 Calculate Dose Equivalent Activity IF requested CALCULATE Dose Equivalent Activity for noble gas, halogen and particulates using the following tables.
4.1    CALCULATE Xe-133 (Noble Gas) Dose Equivalent.
Nuclide        Activity        X    D=F, /DCFxe. 1 3  Xe-133 Equivalent (CO)                                    __        _    _
Kr-85                          X    6.5E-02 Kr-85m                          X    4.7E+00 Kr-87                          X    2.6E+01 Kr-88                          X    6.5E+01 Xe-131m                        X    2.5E-01 Xe-133                          X    1.OE+00 Xe-133m                        X    8.5E-01 Xe-135                          X    7.OE+00 Xe-135m                        X    1.3E+01 Xe-1 38                        X    3.6E+01 4.2    CALCULATE 1-1311 (Halogen) Dose Equivalent.
Nuclide        Activity        X    DCF- / DCFI. 13 1 = 1-131 Equivalent (Ci) 1-131                          X    1.OE+00          =
1-132                          X    5.9E-03 1-133                          X    1.7E-01 1-134                          X    1.OE-03 1-135                          X    2.9E-02 LEMG-NGGC-0002                                Rev. 5                    Page 78 of 87
 
ATTACHMENT 8 Sheet 9 of 16 Shearon Harris Specific Actions and Parameters 4.0  Calculate Dose Equivalent Activity 4.3    CALCULATE Cs-137 (Particulate) Dose Equivalent.
Nuclide    Activity      X    DCF* / DCFcs.137    = Xe-133 Equivalent (Ci)
Cs-134                    X    1.5E+00 Cs-136                    X    4.4E-01 Cs-137                    X    1.OE+00 Sb-1 27                  X    2.3E-01 Sb-129                    X    4.9E-02 Te-129m                  X    7.1E-01 Te-131m                  X    2.1E-01 Te-132                    X    2.9E-01 Sr-89                    X    1.2E+00 Sr-90                    X    3.9E+01 Sr-91                    X    5.9E-02 Ba-140                    X    1.3E-01 Mo-99                    X    1.3E-01 Ru-103                    X    3.2E-01 Y-91                      X    1.4E+00 La-140                    X    2.7E-01 I EMG-NGGC-0002                          Rev. 5          1          Page 79 of 87
 
ATTACHMENT 8 Sheet 10 of 16 Shearon Harris Specific Actions and Parameters 4.0  Calculate Dose Equivalent Activity 4.4    The following table and calculations provide insight for the Dose Equivalent activities calculated above.
NOTE: The Dose Conversion Factors (DCF) in the following equations are taken from Tables 5-1 and 5-2 of EPA 400-92-01, Manual of Protective Action Guides and Protective Actions for Nuclear Incidents. The DCFs for the Xe-1 33 noble gas equivalent and the Cs-1 37 particulate equivalent are combined exposure pathway DCFs from Table 5-1. The DCFs for the 1-131 halogen equivalent are from Table 5-2.
Dose Conversion Factors mrem (DCFi)
Isotope    DCF        Isotope        DCF    Isotope    DCF Kr-85    1.3E+00      1-133        2.2E+05    Sr-89    5.OE+04 Kr-85m 9.3E+01        1-134        1.3E+03    Sr-90    1.6E+06 Kr-87    5.1E+02      1-135        3.8E+04    Sr-91    2.4E+03 Kr-88    1.3E+03      Cs-134      6.3E+04    Ba-140    5.3E+03 Xe-131m 4.9E+00      Cs-136      1.8E+04  Mo-99      5.2E+03 Xe-133 2.OE+01        Cs-137      4.1 E+04  Ru-103    1.3E+04 Xe-133m 1.7E+01      Sb-127      9.5E+03  Y-91      5.9E+04 Xe-135 1.4E+02        Sb-129      2.OE+03  La-140    1.1E+04 Xe- 135m 2.5E+02    Te-129m      2.9E+04 Xe-1 38 7.2E+02      Te-131m      8.6E+03 1-131    1.3E+06    Te-132        1.2E+04 1-132    7.7E+03 Equivalent activities are derived by the summation of multiplying the activity of the isotope times the ratio of the DCF for each isotope to the target isotope. Formulas for determining equivalent values are:
EMG-NGGC-0002                                  Rev. 5                            Page 80 of 87
 
ATTACHMENT 8 Sheet 11 of 16 Shearon Harris Specific Actions and Parameters 4.0 Calculate Dose Equivalent Activity 4.5  The following table and calculations provide insight for the Dose Equivalent activities calculated above. (Continued)
Xe-133 equivalent (Noble Gases)
A xDCF Xe'33    TEDE      AxDC D CF ,
Where: Ai = Activity of the isotope.
DCFi = DCF of the isotope.
1 33 DCFxe-13 3 = DCF for Xe 1-131 Equivalent(Haloqens)
A xDCF 1131 CDE        Ix  C      I DCF    1-131 Where: Ai = Activity of the isotope.
DCFi = DCF of the isotope.
DCFI1 31 = DCF for 1131 Cs-137 equivalent (Particulates)
A xDCF DCI-3 Where: A* = Activity of the isotope.
DCFj = DCF of the isotope.
7 DCFcs-1 3 7 = DCF for Cs13 EMG-NGGC-0002                                  Rev. 5                      Page 81 of 87
 
ATTACHMENT 8 Sheet 12 of 16 Shearon Harris Specific Actions and Parameters 5.0    HNP Source Term Type Selection Guide This table lists all the source term types available for HNP accidents, guidance on when to use each type and the source terms available and where to obtain the required data for RASCAL inputs.
Source Term Type                    When Used                Source Data Needed      Obtain From    Available Release Paths Data        Obtain From Time Core Uncovered          Use when you can estimate        Reactor Shutdown?          EOF SRO    Containment leakage/failure (RCB      EOF AAT (Procedure Step 9.6.1)      how long the core will be        Date/Time                            Leak Rate by percent volume or RCB uncovered and you want                                                  pressure/hole size)
RASCAL to estimate the            Core Uncovered?            EOF SRO core damage that will result. Date/Time                            Steam generator tube rupture by Catastrophic event/release.                                            # of ruptured tubes                  EOF AAT Core Recovered?            EOF SRO    or by charging flow                  EOF SRO/ERFIS However, if the release is in    Date/Time progress or has occurred                                                Containment bypass (RCS leak rate    EOF SRO and is via a monitored                                                  into RAB; Filters - Yes if building pathway, use of the                                                    normal filtered or emergency filtered Monitored Releases -                                                    exhaust systems are operating)
Mixtures option is preferred.                                                                                Attachment 8 Not an Isolated Stack                Section 2.0
_______________________Release                                                          Height_________
Reactor Shutdown?          EOF SRO Ultimate Core Damage        Use this option when you State                        believe you can make a valid      Date/Time                            Steam generator tube rupture by (Procedure Step 9.6.2)      estimate of the amount of                                              # of ruptured tubes                  EOF AAT core damage that has              Core Damage state                    or by charging flow                  EOF SRO/ERFIS occurred. It can also be used      No damage                  EOF AAT for '"what if' analyses.            Fuel pin leakage                    Containment bypass (RCS leak rate    EOF SRO Cladding failure                    into RAB; Filters - Yes if building However, if the release is in                                          normal filtered or emergency filtered progress or has occurred          Time/Date coolant release    EOF AAT  exhaust systems are operating) and is via a monitored                                                                                        Attachment 8 pathway, use of the                                                    Not an Isolated Stack                Section 2.0 Monitored Releases -                                                  Release Height Mixtures option is preferred. I EMG-NGGC-0002                                                                    Rev. 5                                      Page 82 of 87
 
ATTACHMENT 8 Sheet 13 of 16 Shearon Harris Specific Actions and Parameters Containment Radiation Use containment radiation    Reactor Shutdown?            EOF SRO  Containment leakage/failure (RCB      EOF AAT Monitor              monitor when you have        Date/Time                            Leak Rate by percent volume or RCB (Procedure Step 9.6.3) readings from the            Core Uncovered?                      pressure/hole size) containment monitor, you      Date/Time want the code to estimate                                          Not an Isolated Stack                Attachment 8 the core damage from the                                            Release Height                        Section 2.0 readings.                    Containment Monitor        ERFIS/
Reading/Date/Time          MCR HP-However, if the release is in (RM-01CR-3589-SA/SB)        RMS Tech progress or has occurred and is via a monitored pathway, use of the Monitored Releases -
Mixtures option is preferred.
Coolant Sample        Use coolant sample when      Sample ID                  OSC      Steam generator tube rupture by (Procedure Step 9.6.4) you know the coolant activity Date/Time                  Chemistry # of ruptured tubes                  EOF AAT and coolant will be released                              Coord. or by charging flow                  EOF SRO/ERFIS to the atmosphere.
Activity (Isotopic - verify OSC      Containment bypass (RCS leak rate    EOF SRO However, if the release is in units Chemistry reports in  Chemistry into RAB; Filters - Yes if building progress or has occurred      pCi/ml)                    Coord. normal filtered or emergency filtered and is via a monitored                                              exhaust systems are operating) pathway, use of the                                                                                      Attachment 8 Monitored Releases -                                                Not an Isolated Stack                Section 2.0 Mixtures option is preferred.                                      Release Height EMG-NGGC-0002                                                          Rev. 5                                      Page 83 of 87
 
ATTACHMENT 8 Sheet 14 of 16 Shearon Harris Specific Actions and Parameters Containment Air Sample    Use air sample when you        Sample ID                    OSC      Containment leakage/failure (RCB  EOF AAT (Procedure Step 9.6.5)    know the activity in the      Date/Time                    Chemistry Leak Rate by percent volume or RCB containment air and it will be                              Coord. pressure/hole size) released to the atmosphere via Containment leakage or                                  OSC      Not an Isolated Stack              Attachment 8 Activity (Isotopic - verify            Release Height                    Section 2.0 failure.                                                    Chemistry units Chemistry reports in pCi/ml)                      Coord.
However, if the release is in progress or has occurred and is via a monitored pathway, use of the Monitored Releases -
Mixtures option is preferred.
Effluent Isotopic Release Use the effluent rate when    Release Location              ERFIS/    Release direct to atmosphere Rates                    the release is through a                                    MCR HP-                                      Attachment 8 (Procedure Step 9.6.6)    sampled pathway that allows    Release Period(s)            RMS Tech  Not an Isolated Stack              Section 2.0 determination of the release  Date/Time                              Release Height rate of nuclides in terms of  Activity (Isotopic)/unit time OSC activity per unit time.        (Need to calculate release    Chemistry rate:                        Coord.
A(pCi/ml) x F(Ft3 /min) x4.7E(-4) = R (Ci/sec)
Isotopic Activity - Plant Vent Stack, TB or WPB Vent Stack Air Sample -
verify units Chemistry reports in pCi/ml)
Flow Rate - Plant Vent        EOF SRO/
Stack, TB or WPB Vent        MCR HP-Stack Process Flow Rate      RMS Tech
                                                            - verify units plant data in ft 3/min I EMG-NGGC-0002                                                              Rev. 5                  1                  Page 84 of 87
 
ATTACHMENT 8 Sheet 15 of 16 Shearon Harris Specific Actions and Parameters Effluent Isotopic Release Use the effluent              Release Location            ERFIS/    Release direct to atmosphere Concentrations            concentration when the                                    MCR HP-                                      Attachment 8 (Procedure Step 9.6.7)    release is through a sampled  Release Period(s)            RMS Tech  Not an Isolated Stack              Section 2.0 pathway that allows          Date/Time                              Release Height determination of the release  Isotopic Activity - Plant    OSC flow rate and the            Vent Stack, TB or WPB        Chemistry concentrations of nuclides in Vent Stack Air Sample -      Coord.
terms of activity per unit    verify units Chemistry volume.                      reports in pCi/ml)
Flow Rate - WRGM Eff.        EOF SRO/
Channel Plant Vent Stack    MCR HP-3509-1;, WPB Stack 5        RMS Tech 3546-1; WPB Stack 5A 3547-1; or TB Stack 3 3536-1 Process Flow Rate
                                                          - verify units plant data in ft 3/min Monitored Releases -      Use the gross concentration  See Procedure PEP-344                  See Procedure PEP-344 for data Mixtures                  method when you know the      for data needed                        needed concentration of the activity (Site specific procedure) being released, but you do not know the composition by nuclide. Site procedures provide the method to calculate release rates (Ci/sec) for noble gases, iodines and particulates using radiation monitor and flow rate information.
Pool Storage -            Use this source term when    Density of fuel pool        EOF AAT  Spent fuel release pathway Uncovered Fuel            fuel is exposed above the    racking (Procedure step 9.8.1)    water.                        Number or batches of                  Not an Isolated Stack              Attachment 8 assemblies irradiated                  Release Height                      Section 2.0 within 1,2 and 3 years Filtered if E12 or E13 is operating EOF SRO Fuel uncovered?              EOF SRO Date/Time Pool totally drained?
Yes/No Fuel recovered? Yes/No EMG-NGGC-0002                                                              Rev. 5                                      Page 85 of 87
 
ATTACHMENT 8 Sheet 16 of 16 Shearon Harris Specific Actions and Parameters Pool Storage -        Use this source term      Number of damaged        EOF AAT  Spent fuel release pathway Damaged Assembly      when there are damaged    assemblies Underwater            assemblies underwater. Age of damaged                    Not an Isolated Stack              Attachment 8 (Procedure step 9.8.2)                          assemblies or how long            Release Height                    Section 2.0 damaged assemblies                Filtered ifE12 or E13 is operating EOF SRO have been in storage When damage occurred - Date/Time Dry Storage - Cask    Use this source term      Not applicable to HNP              Not applicable to HNP Release                when there are damaged (procedure step 9.8.3) assemblies in a cask.                            I        I I EMG-NGGC-0002                                                  Rev. 5                                    Page 86 of 87
 
==SUMMARY==
OF CHANGES PRR 6176154 SECTION/STEP                                  CHANGES 3.5.2, Old 9.1.3, Removed program location description for WIN7 implementation.
9.1.2            (Editorial)
I EMG-NGGC-0002                  I        Rev. 5                          Page 87 of 87
 
Enclosure 2b EMG-NGGC-0002, Off-site Dose Assessment, Revision 6
 
NUCLEAR GENERATION GROUP STANDARD PROCEDURE VOLUME 99 BOOK/PART 99 EMG-NGGC-0002 OFF-SITE DOSE ASSESSMENT REVISION 6 EMG-NGGC-0002              Rev. 6        Page 1 of 88
 
TABLE OF CONTENTS SECTION                                                                                                                                              PAGE 1.0      PURPOSE...*............................................                                                                  ...........                4 2 .0      R E F E R E NC E S ...............................................................................................                        . . .. . 4 3.0      DEFINITIONS .........................................................                                                                                5 4 .0      R E S P ON S IB ILIT IE S .............................................................................................                        . . 10 5.0      P R E R E Q UIS IT E S ...              *.....................................                                                .................. 11 6.0      PRECAUTIONS AND LIM ITATIO NS ................. . .                                            ......              ......  ..................... 11 7.0      SPECIAL TOOLS AND EQUIPM ENT ..................................................................                                                    13 8.0      A C C E PTA NC E C R IT E R IA ............              ......................      ..........................              .....    .......... 13 9 .0      INS T R UCT IO NS ...............................................................................................                            . . . 13 9.1    RASCAL Program Startup .......................................                                                                                  13 9.2    T his Section D eleted ........                              .        ...................................                        ... ....... 13 9.3    Select RASCAL Model......                          ........                  ..............                              .........            14 9.4    Select Event Type.                      .................................                                                      .........        14 9 .5    S e le ct E ve nt Location ....................................................................................                            . . 14 9.6    Select Nuclear Power Plant Type Source Term*..........................                                                                      ... 15 9.7    Select Nuclear Power Plant Release Path.... ............................                                                                        20 9.8    Select Spent Fuel Type Source Term ...............                                                    ................                          30 9.9    Select the Spent Fuel Release Path ................................                                                                              33 9.10 S E LE C T Meteo ro logy ....................................................                      ........................................ 35 9 .1 1 IN P UT Me te o ro lo g y ........................................................................................                            . . 36 9.12 S ELEC T C alculate D oses ................................................................................                                        38 9.13 R EV IEW D etailed R esults..................................................................... 39 9 .14 D ose P rojection R esults ................................................................................                                . . 39 9.15 Save the Case ....................                                                    ...            ............                                  43 9.16 Field Measurements to Dose Model (FMDose) .................................................                                                        44 9 .17 Multiple R e lease P oints ..................................................................................                                . . 45 1 0 .0    R E C O R D S ...............................................................................................................                      45 EMG-NGGC-0002              .                                          Rev. 6                                                              Page 2 of 88
 
TABLE OF CONTENTS SECTION                                                                                                                      PAGE ATTACHMENTS 1    R A S C A L G e ne ral F low path ...................................................................................... 46 2    Source Term Type Selection G uide ............. .....................................................                        47 3    W eather Report Symbol, Model Class, and Intensity ................................................                          49 4    Multiple Release Point Calculation Sheet .........................                              ........................  . 50 5    Brunswick Unit 1 and 2 Specific Actions and Parameters ...................                                                  51 6    Crystal River Specific Actions and Parameters                                                  ...........                  60 7    H.B. Robinson Specific Actions and Parameters ..............................                                                70 8    Shearon Harris Specific Actions and Parameters                                    ........................                  71 S UMMA R Y O F C HA NG ES ............................................................................................            87 EMG-NGGC-0002                                          Rev. 6                                                      Page 3 of 88
 
1.0 PURPOSE 1.1  The purpose of this procedure is to provide Nuclear Generation Group (NGG) guidance for performing offsite radiological dose assessments from the Technical Support Center or Emergency Operations Facility. This procedure is not for offsite dose-assessment by on-shift Control Room Staff.
1.2  This procedure is to be used in conjunction with Radiological Assessment System for Consequence Analysis (RASCAL) Version 3.0.5 software during a declared plant emergency involving a release or potential release of airborne radioactive materials to the environment. This procedure should be used for all RASCAL Source Term Options except for Monitored Releases - Mixtures. For monitored releases, the use of RASCAL is described in site procedures as listed in References 2.2.7 through 2.2.10.
1.3  This procedure describes an adequate method for assessing actual or potential offsite consequences of a radiological emergency condition as delineated in 10CFR50.47(b)(9).
1.4  This procedure is an emergency plan implementing procedure. Any revisions must be carefully considered for emergency plan impact.
 
==2.0  REFERENCES==
 
2.1  Developmental 2.1.1    EPA 400 R-92-001, Manual of Protective. Action Guides and Protective Actions For Nuclear Incidents 2.1.2    NUREG/BR-0150, Volume 1, Revision 4, RTM-96 Response Technical Manual 2.1.3    U.S. Department of Health, Education, and Welfare, Radiological. Health Handbook, 1970 2.1.4 Crystal River NOCS 00387, Method for Transmitting and Radiological
:Data to the TSC and EOF 2.1.5 Crystal River NOCS 40188, Instructions for Accessing Meteorological and Radiological Datato the TSC and EOF 2.1.6    R-RP-1 1-01-F1 F - Radiation Protection and Emergency Preparedness personnel have not effectively implemented actions to improve accuracy or timeliness of emergency plan dose projections (NCR 481263)
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2.2    Implementing 2.2.1  NUREG-1887, RASCAL 3.0.5: Description of Models and Methods 2.2.2  NUREG-1889, RASCAL 3.0.5 Workbook
          ..2.2.3  Crystal River Nuclear Plant Final Safety Analysis Report (FSAR) 2.2.4  CR-3, Radiological Emergency Response Plan (RERP) 2.2.5  Harris Nuclear Plant FSAR Table 9.4.0-2 2.2.6  Crystal River Engineering Evaluation EEF-00-009, Revision 1 - Radiation Monitor Response Factors 2.2.7  EPRAD-03, H.B. Robinson Steam Electric Plant Dose Projections 2.2.8  PEP-344, HNP Offsite Dose Assessment Based on Monitored Releases 2.2.9 EM-204B, Offsite Dose Assessment During Radiological Emergencies for Monitored Releases - Mixtures (CR3) 2.2.10 OPEP-03.4.8, Brunswick Nuclear Plant Offsite Dose Estimates Based on Monitored Releases 2.2.11 CSP-NGGC-2505, Software Quality Assurance and Configuration Control of Business Computer Systems 3.0  DEFINITONS 3.1    Adverse Met Data The worst case meteorological conditions: G stability class and wind speed of 1.0 mph.
3.2    Committed Dose Equivalent Dose equivalent to organs or tissues of reference that will be received from an intake of radioactive material by an individual during the 50-year period following the intake.
3.3    Committed Effective Dose Equivalent Sum of the products of the weighting factors applicable to each of the body organs or tissues that are irradiated and the committed dose equivalent to these organs or tissues.
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3.0  DEFINITONS (continued) 3.4  Core Melt Deformation of fuel pellet configuration due to excessive core temperature releasing large quantities of gaseous and particulate fission products.
3.5  Decay Calculator The Decay Calculator (DecayCalc) computes radiological decay and daughter ingrowth. It computes the activity remaining after the decay time selected. It includes access to the RASCAL radionuclide database and has the ability to
          .display decay chains as a table or as a graphic. DecayCalc is not linked to any other RASCAL module. Decay calculations are available within the STDose and FMDose models when appropriate. The same decay data and decay calculation routines are used throughout RASCAL.
3.6  Deep Dose Equivalent 2
External whole-body exposure at a tissue depth of 1 cm (1000 mg/cm ).
3.7  Delta T Measurement of the difference in air temperature between two different elevations above ground level. The value provides a measure of the atmospheric stability.
3.8  Depletion Reduction of the concentration of the plume (i.e., deposition and dispersion).
3.9  Deposition Means of puff depletion that deposits particulate radioactive material on the ground.
3.10  Derived Intervention Level (DIL)
A value that corresponds to a health effect threshold or Protective Action Guideline (PAG). A DIL can be used to relate environmental measurements or laboratory analyses to the potential for health affects or the need for protective actions.
3.11  Dose Equivalent Product of the absorbed dose in rad, a quality factor related to the biological effectiveness of the radiation involved and any other modifying factors. Units are typically in rem.
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3.0  DEFINITONS (continued) 3.12 Early Phase The period at the beginning ofa nuclear incident when immediate decisions for effective use of protective actions are required and must be based primarily on predictions of radiological conditions in the. environment. This phase may last from hours to days. For the purposes of dose projections, it is assumed to last four (4) days.
3.13 Effective Dose Equivalent The sum of the products of the dose equivalent to each organ and a weighting factor, where the weighting factor is the ratio of the risk of mortality from delayed health effects arising from irradiation of a particular organ or tissue to the total risk of mortality from delayed health effects when the whole body is irradiated uniformly to the same dose. This unit in Rem is considered equivalent to the Deep Dose Equivalent for the purposes of dose projections because the external exposures are considered to be uniform across the whole body.
3.14  Field Measurement to Dose - (FMDose)
The FMDose model computes emergency worker limits and early-phase and intermediate-phase doses and derived intervention levels (DILs) from the analyses of field measurements. The results of the. analysis of field.
measurements may be entered directly in FMDose. All results are presented as tables. The intermediate-phase DILs are also presented graphically. FMDose includes access to the RASCAL radionuclide database and has the ability to display decay chains as a table or as a graphic.
3.15 Gas Gap Failure Degradation of the protective cladding around the fuel pellets due to elevated core temperature releasing only radionuclides contained in the space between pellet and the cladding.
3.16 Ground Surface Correction Factor The ground surface correction factor is used in'the calculation of ground-shine.
dose. Its value may be from 0.1 to 1.0. It is used to reduce the dose due to the effects. of scattering off.uneven ground...                              ..
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3.0  DEFINITONS (continued) 3.17  Intermediate Phase The period beginning after the incident source and releases have been brought under control and. reliable environmental measurements are available for .use as a basis for decisions on additional protective actions and extending until these protective actions are terminated. This phase may overlap the early and late phases and may last from weeks to many months. For the purpose of dose projection, it is assumed to last for one year.
3.18  Late Phase The period beginning when recovery action designed to reduce radiation levels in the environment to permanently acceptable levels are commenced, and ending when all recovery actions have been completed. This period may extend from. months to years (also referred to as the recovery phase).
3.19  Meteorological Data Processor STDose module used for entering meteorological data and preparing the data for use by the atmospheric transport and diffusion models in RASCAL.
Meteorological data for the site (release point) and 35 additional meteorological observation points may be entered and processed for use by the STDose models. The model is generally accessed directly from the STDose user interface. This method is common when supporting an event using real-time meteorology. The program may also be run stand alone, directly from Windows.
This mode of operation is common when building predefined data sets.
3.20  Partitioning Reduction of non-noble gases when the steam generator tube leak is below.the water level of the generator. This is highly unlikely at CR3 because most of the.
tube length in a once-through steam generator is above the secondary level.
This is not applicable to. BNP.
3.21 ..Release Duration Period of time from the beginning of the release until the end of the release or the projectedend of the release. This can be determined by estimating the completion of a damage control mission, performance of a repair to stop the release, or the estimated time until the RCS, Containment Vessel Sump or Steam Generator temperature is below 2000 F for a pressurized water reactor.
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3.0  DEFINITONS (continued) 3.22  Resuspension Factor The resuspension factor is used to calculate air concentrations from ground surface measurements. Its value may be from 1 E-11 to1 E -2. It is used in all intermediate-phase calculations and in early-phase calculations when measured air concentrations are not used (that is, when "Use Air" is not checked on the Enter Field Data form).
3.23  Seabreeze Effect Wind circulation system produced when the land temperature is higher than the ocean temperature causing a lower level wind direction from sea to land.. The consequence of a release traveling to sea and returning back to land can impact the projected dose in an upward factor. For BNP the seabreeze effect, if confirmed by a meteorologist, can exist between the 160 and 2690 bearings.
3.24  Sigma-Theta Standard deviation of a set of wind range measurements. The value provides a measure of atmospheric stability. The CR3.Sigma-Theta meter automatically calculates and displays the standard deviation of wind range.for the previous 15 minutes.
3.25  Source Term to Dose (STDose)
The STDose of RASCAL provides estimates of the integrated doses-and consequences resulting from the accidental release of radionuclides to the atmosphere. The model requires only information that might be available during an emergency. STDose should be used to assess the consequences of potential or ongoing releases. The program is used in conjunction with the Meteorological Data Processor Program.
3.26  Spike Factor Rapid decrease in pressure of the primary system causes an increase in the rate at which the radioactive fission products in the fuel rod cladding gap escape into the coolant. The RASCAL default spiking factor of 100 is recommended initially and then adjusted after primary coolantanalysis. This is not necessarily an indication of fuel damage.
* 3.27. Stability Class Lettering system from A to G to designate certain atmospheric conditions which affect the dispersion of the plume. Class A indicates rapid dispersion, less concentrated plume (unstable conditions). Class G indicates slow dispersion, more concentrated plume (stable conditions).
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3.0  DEFINITONS (continued) 3.28  Total Effective Dose Equivalent (TEDE)
Early or plume phase TEDE that RASCAL calculates is the sum of the external gamma dose (cloudshine) from the plume, the committed effective dose equivalent (CEDE), and the external dose over a four-day period from radionuclides deposited on the ground (4-day groundshine dose).
3.29 Weathering Factor The fraction of radioactivity remaining after being affected by average weather conditions for a specified period of time.
4.0  RESPONSIBILITIES 4.1  Dose Assessment/Projection Coordinator or Team Leader 4.1.1    Calculate the TEDE and the thyroid CDE, of off-site.dose consequences from a release of radioactivity.
4.1.2    Report dose projection results to the Radiological. Control Manager (RCM) or Radiation Control Coordinator (RCC) /Radiological Control Director (RCD) if the EOF is not activated in a timely manner.
4.1.3 Communicate periodically with State and other agency dose assessment representatives to compare and contrast cases and results that were generated. A comparison also provides a means of peer checking input data and assumptions.
4.2  Dose Assessment Team 4.2.1    Implement the steps of this procedure to generate dose projections for review by the Dose Assessment/Projection Coordinator or Team Leader.
4.2.2 Solicit input from Accident Assessment personnel as needed for plant conditions.
4.3  Accident Assessment Team 4.4
            .3:.11 Inform the Dose Assessment Team of plant conditions that may impact a radiological release to the environment such as time of core uncovered, percent fuel damage, etc.
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5.0  PREREQUISITES
    *5.1  Personnel performing RASCAL dose assessment during an emergency, drill, or exercise are trained and qualified per station procedures.
6.0  PRECAUTIONS AND LIMITATIONS 6.1  If the release pathway is monitored, then the RASCAL Source Term Option for Monitored Releases - Mixtures is the preferred dose projection method. This method requires the use of site specific information and therefore the use of RASCAL for monitored releases is provided in site specific procedures (References 2.2.7 - 2.2.10). Exit this procedure and use the appropriate site procedure.
6.2  RASCAL.requires stability class to be entered as an alphabetic value. (e.g., A, B, C ... ) OSI/PI and ERFIS report stability class as a numeric value (e.g., 1, 2, 3...). They convert directly, 1=A, 2=B, 3=C, etc.
6.3  Several different input models should be run when data permits due to inherent uncertainties associated with generating dose projections using RASCAL. For example, when grab sample release data is available for a stack release, projections may be made using both a release rate model and release concentration model.
6.4  The release duration should be based on available information. If release duration information in not known, then use a default value of 1 hour (RNP should use 2 hours). The dose projections should be modified as more accurate information becomes available.
6.5  Meteorological conditions should be monitored approximately every 15 minutes for changes and RASCAL dose projections updated accordingly.
6.6  RASCAL.dose projections should be updated accordingly when new data becomes available for plant, meteorological or event conditions.
6.7. Dose projections saved for various source terms may be re-opened and modified as necessary. The re-open.ed.case should be renamed as applicable..
based on changes to event type, source term, release path, etc.
6.8  Consider radiation monitor operability and status prior to use for dose projections..
6.9  Sea breeze affect is NOT a specific calculation option for RASCAL; however, the meteorological program will model sea breeze if additional meteorological weather stations are used. Failure to consider the effects of a sea breeze on plume projections could result in large errors in both the projected plume location and intensity. Sea breeze is not a factor for HNP or RNP.
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6.0 PRECAUTIONS AND LIMITATIONS (continued) 6.10  BNP verification of ERFIS data shall be accomplished by comparing the Control Room readouts in the event the. RMS/ERFIS interface multiplexer is in alarm.
6.11  CR3, RNP, and HNP normally uses the option of "Not an Isolated Stack" because the release points do NOT meet the height and separation distance requirements of an isolated release point 6.12  CR3 recorder AH-1003-TIR Channel 4 indicates total Reactor Building stack flow. AH-294-FT measures Reactor Building purge flow rate only and does NOT include make up flow.
6.13  CR3 instrumentation available during a station blackout includes:.
* RM-Gs 1, 3, 5, 7,.9,11,25,26,27,28,29,30
* RM-Ls 2, 7
* Primary Meteorological Tower local (at the tower only) readouts
          .      RM-A1, RM-A2 control room display units are powered, but pumps, skids and detectors are NOT powered.
6.14  RNP specific: RASCAL uses effective release height to model mixed mode releases. A release height of two hundred three (203) feet should be chosen for releases through the plant vent stack. Two hundred three feet is equivalent to the elevated level.sensors at sixty-two (62) meters on the site. meteorological tower. A release height of 36 feet should be chosen for release points other than the plant vent stack. Thirty-six feet is equivalent to the ground level sensors at eleven (11) meters on the site. meteorological tower.
6.15  Verification of release mitigation actions being planned or taken is vital to accurate dose projections. Actions such as plume wash down may reduce the amount.of radioactive materials released to the public..
6..16 Many screens in .RASCAL contain a "Help" button.. Clicking on.the Help. button.
provides useful information from the code developer related to information/options on.that screen.
6.17  Dose projection results must be approved prior to communicating the information to offsite agencies. This information is typically transmitted via the Emergency Notification Form (ENF) which is approved by the Emergency Operations Facility Command position (e.g., Emergency Response Manager.)
6.18  Verify that the correct units and prefixes are selected when entering data. For example: height (feet or meters); prefix (milli, kilo, etc.); activity (becquerel or curie).
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7.0  SPECIAL TOOLS AND EQUIPMENT 7.1    RASCAL software version 3.0.5 on compatible computer 8.0  ACCEPTANCE CRITERIA N/A 9.0  INSTRUCTIONS Section 9.0 contains steps primarily associated with generic RASCAL operation. A specific Attachment exists for each NGG Site and should be referenced for additional site guidance and parameters.
* Brunswick Unit 1 and 2 (BNP):    Attachment 5
* Crystal River 3 (CR3):            Attachment 6 H.B. Robinson (RNP):            Attachment 7.
Shearon Harris (HNP):            Attachment 8 In addition, RASCAL is a software program and alternate key strokes may be used to obtain the end result. Section 9.0 describes one acceptable method to calculate dose assessments using the RASCAL software.. There are multiple options available in RASCAL that may be utilized at the discretion of the user in the calculations of dose assessments 9.1  RASCAL Program Startup 9.1.1 IF not already operating, THEN LOG ON to the computer designated for RASCAL using your corporate ID and password with one of the following options:
* Double click on the RASCAL desktop icon
            ' IF using a Windows XP Desktop, THEN SELECT Start>Programs>Emergency Preparedness >RASCAL 3.0.5.
* IF using a Windows 7 Desktop, THEN SELECT Start>All Programs>DAE>Shortcuts Tab>Search RASCAL 3.0.5>Select RASCAL 310:5 and. Run Application.
9.1.2 IF computer difficulties are experienced when attempting to run RASCAL, THEN USE.
another.computer AND contact the Technology Service Desk to resolve difficulties.
9.1.3 WHEN the RASCAL program starts and displays text showing the version, THEN SELECT the "OK" button (lower right) on the screen to initiate projection process.
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9.2 THIS SECTION DELETED EMG-NGGC-0002            Rev. 6 Page 14 of.88
 
9.3    Select RASCAL Model 9.3.1  IF projecting doses from potential or ongoing releases and plant conditions, source term, and meteorological data are available, THEN SELECT Source Term-to Dose Model (STDose) and proceed to step 9.4. This option is normally used for early phase dose assessment.
9.3.2 IF projecting doses from a release and at least one ground sample concentration is available, THEN SELECT Field Measurement.to Dose Model (FMDose) and PROCEED to step 9.16. This option is NOT normally used for performing early phase dose projections.                                          .
9.4    Select Event Type 9.4.1 IF the actual or potential release is from a plant system, THEN CHOOSE Nuclear Power Plant AND GO TO Step 9.4.5.
9.4.2 IF the actual or potential release is from the Spent Fuel Pool, THEN choose Spent Fuel AND GO TO Step 9.4.5.
9.4.3 Do NOT select Fuel Cycle / UF6 / Criticality. This option is. NOT currently applicable for NGG.
9.4.4. Do NOT select Other Radioactive Material Releases. This option is NOT currently applicable for NGG.
9.4.5 SELECT "'OK"in the lower right corner of the Event Type Selection window and a Vmark will appear in front-of Event Type when this step is complete.
9.5    Select Event Location 9.5.1 In the Site Names drop-down menu box, CLICK on the drop-down menu arrow, scroll down. to and SELECT the applicable Site:.
Brunswick  -Unit I
* Brunswick - Unit 2
              .. CrystalIRiver - Unit 3.
* H. B. Robinson - Unit 2
* Shearon Harris - Unit 1 9.5.2 SELECT OK and a V mark will appear in front of Event Location when this step is complete.
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9.5    Select Event Location (continued) 9.5.3 IF EVENT TYPE is Nuclear Power Plant THEN GO to step 9.6, OTHERWISE GO to step 9.8 for Spent Fuel.
9.6    Select Nuclear Power Plant Type Source Term This section contains options to be -used for selecting source term. Sections related to source terms that are not appropriate do NOT need to be completed and the user may proceed to the desired option.
* Time Core is Uncovered - Section 9.6.1
* Ultimate Core Damage State - Section 9.6.2
* Containment Radiation Monitor - Section 9.6.3 Coolant Sample - Section 9.6.4
* Containment Air Sample - Section 9.6.5
* Effluent Isotopic Release Rates - Section.9.6.6
* Effluent Isotopic Release Concentrations - Section 9.6.7
            . Monitored Releases - Mixtures - Go to site specific procedure (References 2.2.7 -
2.2.10)
NOTE:      Additional guidance related to SourceTerm and Release Path option selection is provided in Attachment 2 for all sites, Attachment 5 for BNP, Attachment 6 for CR3.
and Attachment 8 for HNP.
9.6.1 IF the Time Core is Uncovered option is selected, THEN PERFORM the following steps.
: 1. IF the reactor is shutdown, THEN ENTER the date and time of-shutdown.
: 2. IF the reactor is not shutdown, THEN ENTER the date and time of the start of the release in the "Reactor shutdown" field.
: 3. IF the. reactor core is uncovered, THEN SELECT Yes AND ENTER the date AND time the core was uncovered. Otherwise, SELECT No..
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9.6  Select Nuclear Power Plant Type Source Term (continued)
: 4. IF the reactor core is recovered, THEN SELECT Yes AND ENTER the date AND time the core was recovered. Otherwise, SELECT No. This step is not available if No was selected in 9.6.1.3.
: 5. SELECT OK and a -/mark will appear in front of Source Term when this step is complete.
: 6. GO TO Step 9.7.
9.6.2 IF the Ultimate Core Damage State option is selected, THEN PERFORM the following steps.
: 1. IF the reactor is shutdown,. THEN ENTER the date and time of shutdown.
: 2. IF the reactor is not shutdown, THEN. ENTER the date and time of the start of the release in the "Reactor shutdown" field.
: 3. SELECT ONE of the following ultimate core damage states. Read all three before selecting.
: a. No core damage - normal coolant activity. CHOOSE this option if no core damage is suspected AND ENTER the time of normal coolant release date and time.
: b. Increased fuel pin leakage. CHOOSE this option if a rapid shutdown or depressurization has occurred AND ENTER the time of increased fuel pin leakage date and time. A coolant contamination spike factor of 100 is appropriate as long as the core remains covered.
: c. Cladding failure (gap release)*- with percent. CHOOSE this option if the.
core is uncovered OR there is an indication of mechanical damage.
(1) DETERMINE AND ENTER percentage of gap release using the applicable site specific Attachment or other station procedures.
(2) ENTER completion of cladding failure date and time.
: 4. SELECT OK and a "/mark.will appear in front of.Source Term when this step is complete.
      .5.. GO TO Step 9.7.
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9.6  Select Nuclear Power.Plant Type Source Term (continued) 9.6.3 IF the primary Containment Radiation Monitor option is selected, THEN PERFORM the following steps. BNP has a primary and secondary containment whereas CR3, HNP and RNP only have one "primary" containment.
: 1. IF the reactor is shutdown, THEN ENTER the date and time of shutdown.
: 2. IF the reactor is not shutdown, THEN ENTER the date and time of the start of the release in the "Reactor shutdown" field.
: 3. IF the dose assessment is for Brunswick, THEN SELECT monitor location for in dry well. BNP does not have a monitor in the wet well and the PWRs only have.
one option of containment dome for monitor location.
: 4. OBTAIN the radiation monitor reading(s) for the applicable site:
: a. Brunswick - Unit 1:
                " (1)D22-RM-4195
                * (1)D22-RM-4196
                " (1)D22-RM-4197
                * (1)D22-RM-4198
: b. Brunswick - Unit 2:
                * (2)D22-RM-4195
                * (2)D22-RM-4196 e (2)D22-RM-4197 e (2)D22-RM-4198
: c. Crystal River - Unit 3: RM-G29 or RM-G30
: d. H. B. Robinson - Unit 2: R-2, R-32A or R-32B
          -e. Shearon Harris - Unit 1: RM 3589 or RM 3590
: 5. ENTER the following for the radiation monitor:
: a. Date.
: b. Time.
: c. Radiation monitor reading in R/hr
: 6. The use of the Add Row, Delete Row.and Sort Rows buttons are optional-and NOT required. Monitor readings for multiple times may be entered if the reading is changing by selecting the Add Row button. The Sort Row button arranges the
          " readings by time.
: 7. SELECT OK and a -mark will appear in front of Source Term when this step is complete.
: 8. GO TO Step 9.7.
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9.6    Select Nuclear Power Plant Type Source Term (continued) 9.6.4 IF the Coolant Sample option is selected, THEN PERFORM the following steps.
: 1. ENTER the Sample ID.
: 2. ENTER the date AND time the sample was taken.
: 3. VERIFY the correct sample activity units by clicking on the > symbol AND REVISE as necessary.
: 4. ENTER the sample nuclides AND activity for each nuclide.
: 5. SELECT OK and a ,-mark will appear in front of Source Term when this step is complete.
: 6. GO TO Step 9.7.
9.6.5 IF the Containment Air Sample option is selected, THEN PERFORM the following steps.
: 1. ENTER the Sample ID.
: 2. ENTER the date AND time the sample was taken.
    .. 3.. VERIFY the correct sample activity units by clicking on the > symbol AND REVISE as necessary.
: 4. ENTER the sample radionuclide AND activity for each radionuclide.
: 5. SELECT OK and a Vmark will appear in front of Source Term when this step is'.
complete.
: 6. GO TO Step 9.7.
9.6.6 IF the Effluent Isotopic Release Rates option is. selected, THEN PERFORM the following steps.
: 1. ENTER the measurement location (sample origin).
: 2. VERIFY the correct Effluent release rate units by clicking on the > symbol AND
            .REVISE as necessary. CONVERT units as necessary.
: 3. ENTER the applicable Start date AND Start time for each release period.
: 4. ENTER the applicable Stop date AND Stop time for each release period.
: 5. ENTER the nuclides AND release rates for each period.
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: 6. 9.6      Select Nuclear Power Plant Type Source Term (continued)
: 7.      VERIFY the percent enrichment.. is five percent (5%).
8..      SELECT OK and a Vmark will appear in front of Source Term when this step is complete.
: 9.      GO TO Step 9.7 to enter Release Path information.
9.6.7  IF the Effluent Isotopic Release Concentrations option is selected, THEN PERFORM the following steps.
: 1. ENTER the measurement location (sample origin).
: 2. VERIFY the correct Effluent flow rate units by clicking on the > symbol AND REVISE as necessary. CONVERT units as necessary..
      *3. VERIFY the correct Effluent concentration Units by clicking on the > symbol AND REVISE as necessary. Convert units as necessary.
4.. ENTER the applicable Start date AND Start time for each release period.
: 5. ENTER the applicable Stop date AND Stop time for each release period.
: 6. ENTER the applicable Effluent flow rate for each release period.
: 7. ENTER the nuclides AND concentrations for each period.
: 8. VERIFY the percent enrichment is five percent (5%).
: 9. IF the sample analysis period results are greater than 24 hours prior to the release, AND require decay calculation per-the RCC/RCD or:RCM THEN SELECT DECAY.
: a. SELECT the period to decay isotopes.
: b. SELECT the time AND units to adjust the source.for decay prior to release time.
: c. SELECT OK.
: 10. SELECT OK and a Vmark will appear in front of Source Term when this step is complete.
11.. GO TO Step 9.7 to enter Release Path information.
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9.7    SELECT Nuclear Power Plant Release Path This section contains options to be used for selecting a release path. Sections related to release paths that are not appropriate do NOT need to be completed and the user may proceed to the desired option:
* Through the Wet Well - Section 9.7. 1
* Through the Dry Well Wall - Section 9.7.2
* Bypass Secondary Containment - Section 9.7.3
* Containment Leakage/Failure - Section 9.7.4
* Steam Generator Tube Rupture - Section 9.7.5
* Containment Bypass - Section 9.7.6
* Direct to Atmosphere    - Section 9.7.7 NOTE:      Additional guidance related to Source Term and Release Path option selection is provided in Attachment 2 for all sites, Attachment 5 for BNP, Attachment 6 for CR3 and Attachment 8 for HNP.
NOTE: Sections 9.7.1 - 9.7.3 and section 9.7.7 are used for BNP release pathways.
Sections 9.7.4 - 9.7.6 and section 9.7.7 are used for CR3, HNP, and RNP release
        *pathways.
9.7.1 IF the Through the Wet Well option is selected, THEN PERFORM the following steps.
This option is ONLY applicable to Brunswick Units 1 and 2 and assumes that the release passes by a wet pathway through the suppression pool into the secondary containment wet-well atmosphere. Particulates and aerosols airborne in the secondary containment wet well are reduced by factors to account for their interactions with the suppression pool Under subcooled or saturated conditions.
: 1. ENTER a Pathway description.
: 2. IF the release point is through the reactor building, turbine building or radwaste building THEN SELECT Not an isolated stack.
: a. ENTER 0 meters for the release. height. This is considered a Ground release.
: b. SELECT YES for Consider building wake effects....
: c. GO TO Step 9.7.1.4.
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9.7  SELECT Nuclear Power Plant Release Path (continued)
: 3. IF the release point is through the Main Stack THEN SELECT Isolated stack.
: a. ENTER 100 meters for the stack height. This is considered an Elevated release.
: b. IF the ambient air temperatures are not known THEN ENTER NO for Consider plume rise.
: c. IF the ambient air temperatures are known and will be used in the meteorological data set THEN ENTER YES for Consider plume rise.
: d. IF desired to edit plume rise settings THEN SELECT Edit Plume Rise Setti.ngs and revise:
: 1)    Effluent flow rate and units
: 2)    Stack diameter and units
: 3)    Effluent Temperature:and units.
: 4. ENTER the date AND time of the release start to wet well.
: 5. SELECT the Percent Volume OR Containment Pressure/Hole Size option.
: 6. ENTER the current date AND current time for each event row used.
: a. IF the Percent Volume option is selected, THEN SELECT the Event Setting options based on the following table.
Event                        Event Setting Choices Leak Rates(REQUIRED)          Total Failure (100%/hr)
Percent Volume in % per day or % per hour Design (0.50%Id)
Filters (OPTIONAL)            On Off Filter Rel.Frac (Filter      Noble gases Release Fractions)          Halogens (OPTIONAL)          Other radionuclides Wet Well (OPTIONAL)          Saturated
                  .. __. ___.
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9.7  SELECT Nuclear Power Plant Release Path (continued) b..IF the Containment Pressure/Hole Size option is selected, THEN SELECT the Event Setting options based on the following table..
Event                      Event Setting Choices Leak Rate                  Containment pressure and units (REQUIRED)        Hole area or diameter and units Filters (OPTIONAL)          On
                                "__
_ __ _ __ Off Filter Rel Frac (Filter    Noble gases Release Fractions)        Halogens (OPTIONAL)        Other radionuclides Wet Well (OPTIONAL)        Saturated Subcooled
: 7. SELECT OK and a Vimarkmwill appear in front.of Release Path when this step is.
complete.
: 8. GO.TO Step 9.10.
9.7.2 IF the Through the Dry Well Wall option is selected, THEN PERFORM the following steps. This option is ONLY applicable to Brunswick .Units 1 and 2 and assumes that the release passes by'a dry pathway through the prim'ary system into the secondary containment dry-well atmosphere without passing through the suppression pool.
Particulates and aerosols airborne in the secondary containment dry well are reduced by factors to account for the actions of sprays or natural processes.
: 1. ENTER a Pathway description.
: 2. IF the release point is through the reactor building, turbine building or radwaste building THEN SELECT Not an isolated stack.
: a. ENTER 0 meters for the release height. This is considered a Ground release.
: b. SELECT YES for Consider building. wake effects.
: c. ENTER the date AND time of the -release start to dry well.
d.. GO TO Step 9.7.2.4.                  .
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9.7  SELECT Nuclear Power Plant Release Path (continued)
: 3. IF the release point is through the Main Stack.THEN SELECT Isolated stack.
: a. ENTER 100 meters for the stack height. This is considered an Elevated release.
: b. IF the ambient air temperatures are not knownTHEN ENTER NO for Consider plume rise.
C. IF the ambient air temperatures are known and will be used in the meteorological data set THEN ENTER YES for Consider plume rise.
: d. IF desiredto edit plume rise settings THEN SELECT Edit Plume Rise Settings and revise:
: 1)    Effluent flow rate and units
: 2)    Stack diameter and units
: 3)    Effluent Temperature. and. units
    *4. ENTER the date AND time of the release start to dry well.
: 5. SELECT the Percent Volume OR Containment Pressure/Hole Size option.
: 6. ENTER the current date AND current time for each event row used.
a, IF the Percent Volume option is selected, THEN SELECT the Event Setting options based on the following table.
Event                          Event Setting Choices Leak Rate (REQUIRED)            Total Failure (100%/hr).
Percent Volume in % per day or % per hour Design (0.50%/d)
Filters (OPTIONAL)              On Off Filter Rel Frac (Filter        Noble gases Release Fractions)            Halogens (OPTIONAL)            Other radionuclides Sprays (OPTIONAL)              On.
* Off EMG-NGGC-0002                                    Rev. 6                              Page 24 of 88
 
9.7  SELECT Nuclear Power Plant Release Path (continued)
: b. IF the Containment Pressure/Hole Size option is selected, THEN SELECT the Event Setting options based on the following table.
Event                      Event Setting Choices Leak Rate (REQUIRED)        Containment pressure and units Hole area or diameter and units Filters (OPTIONAL)          On Off Filter. Rel Frac (Filter    Noble gases.
Release Fractions)        Halogens (OPTIONAL)        Other radionuclides Sprays (OPTIONAL)          On Off
: 7. SELECT OK and a ,"mark will appear in front of Release Path when this step is complete.
: 8. GOTOStep9.10.
9.7.3 IF the Bypass Secondary Containment option is selected, THEN PERFORM the following steps. This option is ONLY applicable to Brunswick Units 1 and 2.
: 1. ENTER a Pathway description.
: 2. IF the release point is through the reactor building, turbine building or radwaste building THEN SELECT Not an isolated stack.
: a. ENTER 0 meters for the release height. This is considered a Ground release.
: b. SELECT YES for Consider building wake effects.
: c. GOTO Step 917.3.4.
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9.7 SELECT Nuclear Power Plant Release Path (continued)
: 3. IF the release point is through the Main Stack THEN SELECT Isolated stack.
: a. ENTER 100 meters for the stack height. This is considered an Elevated release.
: b. IF the ambient air temperatures are not known THEN ENTER NO for Consider plume rise.
: c. IF the ambient air temperatures are known and will be used in the meteorological data set THEN ENTER YES for Consider plume rise.
: d. IF desired to edit plume rise settings THEN SELECT Edit Plume Rise Settings and revise:
: 1)    Effluent flow rate and units
: 2)    Stack diameter and units
: 3)    Effluent Temperature and units...
If plume rise is being considered and the effluent temperature is unknown assume the effluent temperature is the sameas the ambient outside temperature.
: 4. ENTER the current date AND current time for each event row used.
: 5. SELECT the Event Setting options based on the following table.
Event                          Event Setting Choices Leak Rate (REQUIRED)            Flow.ratefor the coolant bypassing the containment and units Filters (OPTIONAL)              On
_Off
: 6. SELECT OK AND a ,;"mark will appear in front of Release Path when this step is complete.
: 7. GOTOStep9.10.
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9.7  SELECT Nuclear Power Plant Release Path (continued) 9.7.4 IF the Containment Leakage/Failure option is selected, THEN PERFORM the following steps. This option is NOT applicable to Brunswick Units 1 and 2.
      .1. ENTER a description for the release pathway.
: 2. SELECT the Not an isolated stack AND ENTER the release height as listed below.
: a. Crystal River - Unit 3: 0 meters
: b. H. B. Robinson - Unit 2 plant vent: 62 meters or 203 feet
: c. H. B.. Robinson -. Unit 2, non-plant vent: 11 meters or 36 feet
: d. Shearon Harris - Unit 1, See Attachment 8 Section 2.0
: 3. SELECT Yes for Consider building wake effects.
: 4. ENTER the date AND time of the release start to containment. This step is NOT applicable if the source term is "containment air sample".
: 5. SELECT the Percent Volume OR Containment Pressure/Hole Size option.
: a. IF the Percent Volume option is selected, THEN SELECT the Event Setting options based on the following table.
Event                          Event Setting Choices Sprays                        On Off Leak Rate                      Total Failure (100%/hr)
Percent Volume in % per day or % per hour
_____ ___..
_____  ____      Design
: b. IF the Containment Pressure/Hole Size option is selected, THEN SELECT the Event Setting options based on the following table.
Event                              Event Setting Choices Sprays                            On Off Leak Rate                          Containment pressure and units
                    .. __ _"  _    _      "_ '    Hole area or diameter and units EMG-NGGC-0002                                        Rev. 6                            Page 27 of 88
 
9.7  SELECT Nuclear Power Plant Release Path (continued)
: 6. SELECT OK and a "mark will appear in front of Release Path when this step is complete.
: 7. GOTOStep9.10.
9.7.5 IF the Steam'Generator Tube Rupture option is selected, THEN PERFORM the following steps. This option is NOT applicable to Brunswick Units 1 and 2.
: 1. IF the release is through a secondary. side Pressure Operated Relief Valve (PORV),
a safety valve or turbine building exhaust, or directly to atmosphere through a leaking/failed component, THEN SELECT the Safety Valve/ADV/Turbine Building exhaust option.
: a. ENTER the appropriate release height as shown below:
: 1)  Crystal River - Unit 3: 0 meters or 0 feet
: 2)  H. B. Robinson  - Unit 2: 11 meters or 36 feet
: 3)  Shearon Harris - Unit 1: See Attachment 8 Section 2.0
: b. GO TO Step 9.7.5.3
: 2. IF the release is through the condenser to a plant vent via either a Steam Jet Air Ejector or a Condenser Vacuum Pump, THEN SELECT Steam Jet Air Ejector.
: a. ENTER the appropriate release height as shown below:
: 1)  Crystal River - Unit 3: 0 meters or 0 feet
: 2)    H. B. Robinson - Unit 2: 62 meters or 203 feet
: 3)  Shearon Harris  - Unit 1: See Attachment 8 Section 2.0
: 3. SELECT Yes to "consider building wake effects".
: 4. ENTER the Steam Generator water mass IF known otherwise use default value of 9.30 E+04 lb.
: 5. ENTER the Steaming rate IF known otherwise use default value of 7.50E+04 lb/h.
6:. ENTER the current date-AND current time for each event row used.
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9.7    SELECT Nuclear Power Plant Release Path (continued)
I NOTE:    In RASCAL, charging flow is a generic term used to describe the leak through I
            !:the tubes. The charging flow is the value that quantifies the leak ornet flow.              .
: 7. SELECT the Event Setting options based on the following table.
Event                        Event Setting Choices Leak Rate into SG            Number of ruptured tubes
              *(REQUIRED)          Charging flow and units SG Condition                  Partitioned - it is partitioned if the break is under the secondaryside water in the steam. generator.
Not Partitioned - it is not partitioned if the break is above the secondary side water or the secondary side is solid due to in-leakage of primary coolant.
: 8. SELECT OK and. a -/mark will appear in front of Release Path when this step is, complete.
: 9. GO TO Step 9.10.
9.7.6 IF the Containment Bypass option is chosen, THEN PERFORM the following steps.
This option is NOT applicable to Brunswick Units 1 and 2.
: 1. ENTER a description for the release pathway.
: 2. SELECT the Not an isolated stack AND ENTER the release height as shown below:
: a. Crystal River - Unit 3: 0 feet
: b. H. B. Robinson - Unit 2
                  . Plant Vent Stack: 62 meters or 203 feet
* Non-Plant:Vent Stack Pathway: 11 meters or 36 feet c.
c.Shearon Harris - Unit 1:- See Attachment 8 Section 2.0
: 3. SELECT Yes to Consider building wake effects.
4.. ENTER the current date AND current time for each event row used.
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9.7  SELECT Nuclear Power Plant Release Path (continued)
: 5. SELECT the Event Setting options based on the following table.
Event                          Event Setting Choices Leak Rate (REQUIRED)          Flow rate for the coolant bypassing the containment and units*
Filters (OPTIONAL)            On Off
: 6. SELECT OK and a ,'mark will appear in front of Release Path when this step is complete.
: 7. GO TO.Step 9.10.
*9.7.7 IF the release is Direct to Atmosphere THEN PERFORM the following steps. This release pathway is applicable to all Plants and is used automatically for the following source term options:.
* Effluent Isotopic Release Rates
* Effluent Isotopic Release Concentrations
* Monitored Releases - Mixtures
: 1. IF the release point is through the Brunswick Unit 1 or 2 Main Stack THEN SELECT. Isolated stack.
: a. ENTER 100 meters for the stack height. This is considered an Elevated release.
: b. IF the ambient air temperatures are not known THEN ENTER NO for Consider plume rise.
: c. IF the ambient air temperatures are known and will be used in the
* meteorological data set THEN ENTER YES for Consider plume rise.
: d. IF desired to edit plume rise settings THEN SELECT Edit Plume Rise Settings and revise:
: 1)    Effluent flow rate and units
: 2)    Stack diameter and units
: 3)    Effluent Temperature and units EMG-NGGC-0002                                    Rev. 6                                  Page 30 of 88 1*...
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* 9.7  SELECT Nuclear Power Plant Release Path (continued)
: e. GO TO Step 9.7.7.4.
: 2. SELECT the Not an isolated stack AND ENTER the release height as listed below for all releases except from Brunswick Unit 1 or 2 Main Stack:
: a. Brunswick - Unit 1 and Unit 2: 0 meters
: b. Crystal River- Unit 3:0 meters
: c. H. B. Robinson  -  Unit 2 plant vent: 62 meters or 203 feet
: d. H. B. Robinson - Unit 2, non-plant vent: 11 meters or 36 feet e.. Shearon Harris - See Attachment 8, Section 2.0
: 3. SELECT Yes for Consider building wake effects.
4.. ENTER-the start date AND time of the release to atmosphere.
: 5. ENTER End of release to atmosphere data by using one of the two options below:
: a. IF the End time is known for the release period THEN ENTER the stop date.
AND time of the release to atmosphere.
: b. IF the Release duration option is selected THEN ENTER the days, hours and minutes.
: 6. SELECT OK and a Vmark will appear in front of Release Path when this step is complete.
: 7. GO TO Step9.10..
9.8  SELECT Spent Fuel Type Source Term This section. contains options to be used.for selecting source terms for Spent Fuel accidents. Sections related to source terms that: are not appropriate do. NOT need to be completed and the user may proceed to the desired option.
:.Pool Storage - Uncovered Fuel- Section 9.8.1
    . Pool Storage  -  Damaged Assembly Under Water - Section 9.8.2
    .      Dry Storage Cask Release - Section 9.8.3 EMG-NGGC-0002                                  Rev 6                          Page 31 of 88
 
9.8  SELECT Spent Fule Type Source Term (continued)
NOTE      Attachment 2 provides a summary of available source term selection criteria.
9,8.1 IF the spent fuel pool has been drained OR spent fuel hasbeen uncovered > 2 hours, THEN SELECT Pool Storage - Uncovered Fuel AND PERFORM the following steps.
: 1. SELECT HIGH for Density of fuel pool racking. This step is NOT applicable to Brunswick Unit 1 and 2.
NOTE: For a fuel uncovered event, material is not considered available for release until two (2) hours after uncovered time. All fuel is considered to be damaged.
: 2. SPECIFY the amount of fuel in the pool. IF the Number of batches is selected for Amount of fuel in the pool THEN ENTER the number of batches in the pool since last irradiation as applicable for the Site location.
: a. Brunswick- Unit 1 and 2: < 180 days, 18O+ days
: b. Crystal River - Unit 3:
: 1)  IF the refuel outage occurred <1 year ago, THEN ENTER <1 year =1; 1-2 years = 0; >2 years = last refuel number -1.
: 2)  IF the refuel outage occurred 1-2 years ago, THEN ENTER <1 year = 0; 1-2 years = 1; >2 years last refuel number -1.
: 3)  IF the refuel outage occurred >2 years ago, THEN ENTER <1 year =.0; 1-2 years = 0; >2 years = last refuel number.
: c. H. B. Robinson - Unit12: <1 year, 1-2 years, and >2 years
: d. Shearon Harris:- Unit 1: <1 year, 1-2 years, and >2 years
: 3. IF-the Number of assemblies is selected for Amount of. Fuel in the pool THEN ENTER the number of assemblies in the pool since last irradiation as applicable for the Site location.
a.. Brunswick - Unit 1 and 2: < 180 days, 180+.days b:  Crystal River.- Unit 3: <1 year, 1-2 years, and >2 years
: c. H. B. Robinson    7 Unit 2: <1 year, 1-2 years, and >2.years
: d. Shearon Harris - Unit 1: <1 year,.1-2 years, and >2 years EMG-NGGC-0002                                    Rev. 6                        Page 32 of 88
 
9.8  SELECT Spent Fule Type Source Term (continued)
: 4. ENTER the date and time of fuel uncovered.
: 5. IF the pool is totally drained, THEN SELECT YES AND ENTER the date and time pool was drained. Otherwise, SELECT NO.
: 6. IF the fuel is recovered, THEN SELECT YES AND ENTER the date and time fuel is recovered. Otherwise, SELECT NO.
: 7. SELECT OK to proceed with case development and a -/ mark will appear in front of Source Term when this step is complete.
: 8. GO to Step 9.9.
9.8.2 IF fuel assemblies have been damaged during handling, THEN SELECT Pool Storage
      -  Damaged Assembly Under Water AND PERFORM the following steps.
: 1. ENTER the number of damaged assemblies.
: 2. ENTER the Last date of irradiation OR ENTER how long, in years and days the damaged assemblies have been in storage.
: 3. ENTER the date and time the damage occurred to the fuel.
: 4. SELECT OK and a , mark will appear in front of Source Term when this step is complete.
: 5. GO to Step 9.9.
9.8.3 IF the spent fuel is damaged due to a dry storage cask event, THEN SELECT dry fuel storage cask event AND PERFORM the following steps.
: 1. SELECT the type of cask if known OTHERWISE, SELECT UNKNOWN AND ENTER the number of fuel assemblies in a cask.:
: 2. ENTER the Last date of irradiation OR ENTER how long, in years the damaged assemblies have been in storage.
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9.8  SELECT Spent Fule Type Source Term (continued)
NOTES:    1. No release is projected for a loss of cask cooling less than 24 hours of the thermal limit. Another event type must be selected.
: 2. A very minimal or no release is projected for a cask engulfed in fire. Another event type must.be selected.
: 3. ENTER the type of event as major damage AND ENTER percent of fuel elements damaged OTHERWISE SELECT Loss of cooling greater than 24 hours (thermal limit).
4... SELECT OK and a        mark will appear in front of Source Term when this step is complete.
9.9 SELECT the Spent Fuel Release Path 9.9.1  IF the release point is through the Brunswick Unit 1 or 2 Main Stack THEN SELECT Isolated stack. OTHERWISE GO to step 9.9.2.
: 1. ENTER 100 meters for the stack height, This is considered an Elevated release.
: 2. IF the ambient air temperatures are not known THEN ENTER NO for Consider plume rise.
: 3. IF the ambient air temperatures are known and will be used in the meteorological data set THEN ENTER YES for Consider plume rise.
: 4. IF desired to edit plume rise settings THEN SELECT Edit Plume Rise Settings and revise:
: a. Effluent flow rate and units
: b. Stack diameter and units
: c. Effluent Temperature and units
: 5. GO TO Step 9.9.4.
9 9.2 ENTER the Pathway Description EMG-NGGC- 00 02                              Rev. 6                            Page 34 of 88
 
9.9    SELECT the Spent Fuel Release Path (continued) 9.9.3 SELECT the NOT an isolated stack AND ENTER the release height as listed below.
: 1. Brunswick - Unit 1 and Unit 2 0 meters
: 2. Crystal River - Unit 3  0 meters
: 3. H. B. Robinson - Unit 2 plant vent: 62 meters or 203 feet
: 4. H. B. Robinson - Unit 2, unmonitored or dry fuel cask event: 11 meters or 36 feet
: 5. Shearon Harris - Unit 1:
: a. Stack 1:      27.4 meters (90 feet)
: b. Stack 3:      1.9.2 meters (63 feet)
: c. Stack 5:      24.1 meters (79 feet)
: d. Stack 5A:    18.3 meters (60 feet) 9.9.4 SELECT Yes for Consider building wake effects.
9.9.5 ENTER the start date AND time of the release to atmosphere.
9.9.6 ENTER End of release to atmosphere data by using one of the two options below.
: 1. IF the End time is known for the release period THEN ENTER the stop date AND time of the release to atmosphere.
: 2. IF the Release duration option is selected THEN ENTER the days, hours and minutes.
9.9.7 IF the building with the fuel damage accident is intact, and the operating ventilation system provides filtered releases (they do not have to be safety grade filters) THEN ENTER YES to filtered pathway condition if the filter system includes both HEPA and
    ....charcoal. If the system only includes HEPA filters only select YES if all fuel had.
decayed for more than 3 months. Otherwise, ENTER no for all other conditions.
9.9.8 SELECT the Leak rate to atmosphere as Total failure OR Percent volume. Total failure default is 100% since this is essentially the fastest rate at which the fission products can escape the building.
: 1. IF Percent volume is selected THEN enter the leak rate in % per hour.
9.9.9 SELECT OK and.a Vmark will appear in front of Release Path when. this step is complete.
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9.10    SELECT Meteorology..
NOTES:
: 1. Meteorological data should be obtained from the appropriate source. ERFIS or PICS (CR3) should be used as the primary source for meteorological data. Every effort should be made to obtain on site meteorological data. The National Weather Service, Weather Services International (wsi.com), etc. may also be used to obtain meteorological data.
: 2. The pre-defined (non site specific) meteorological data may also be used if ERFIS data is unavailable. The pre-defined meteorological data is based on visual
* observation of existing weather conditions. Example: Summer-Afternoon-Rainy.
should be chosen if visual observation of the weather support the conditions.
: 3. (HNP) All release points at HNP are considered- to be a around level release due, to the stack heiciht beinq less than 2.5 times the heicht of anv.surroundina building.
Therefore, the 12.5 m wind direction and speeds are used as input into the meteorological data.
9.10.1 OBTAIN meteorological data for the desired Site by referring to Attachment 3 and the.
applicable site specific Attachment. Attachment 3 contains standard. nomenclature for weather report symbols, model classes and intensities if a weather forecast is provided by an offsite weather agency.
* Brunswick Unit 1 and 2 (BNP):        Attachment 5
* Crystal River 3 (CR3):.              Attachment 6 H.B. Robinson (RNP):                Attachment 7
          * .Shearon      Harris (HNP):              Attachment 8 9.10..2 CONTINUE to 9.11 to input. meteorological data.
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9.11 INPUT Meteorology 9.11.1 SELECT Actual Observations and Forecasts IF available OTHERWISE PROCEED to step 9.11.2.
: 1. SELECT Create New OR SELECT Edit Existing.
: 2. SELECT Enter Data.
: 3. SELECT OBS for observed data OR FCST for forecast data TYPE as appropriate.
CAUTION RASCAL rounds meteorological data times to the nearest quarter hour. If the meteorological data time is the same as the release time and both are in the second half of a quarter hour (e.g., 0008-0014), RASCAL rounds the meteorological data time to 0015 which is after the release time and causes an error. To prevent this error, meteorological time should be adjusted to the first half of the quarter hour (e.g., 0000-0007).
: 4. ENTER the date and time for each data set.
: 5. ENTER the Direction "From" in degrees for each data set.
: a. IF the instrument reading is greater than 360, THEN subtract 360 from the reading and enter.
: 6. ENTER the speed in mph.
: a. IF an adverse.met data dose projection is being performed, THEN ENTER.a speed of 1 mph. (HNP)
: 7. ENTER stability class using the drop-down list selection.
: a. IF an'adverse met data dose projection is being performed THEN ENTER a
              ..stability class.of G. (HNP)
: 8. ENTER the Precipitation type using the drop-down list selection.
No precipitation: <0.01 in/hr.
* Light rain: 0.01 to 0.04 in/hr.
* Rain: >0.04 to 0.2 inhr.
            . Heavy rain:. >0.2 in/hr..
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9.11 INPUT Meteorology (continued)
: 9. ENTER OPTIONAL parameters if desired but they are NOT required:
: a. Air Temperature in degrees Fahrenheit
: b. Air Pressure (mb)
: c. Dew Point in degrees Fahrenheit
: 10. IF an additional record is going to be added SELECT Add record.
: a. REPEAT steps 9.11.1.3-9.11.1.10.
: 11. SELECT "OK" in the bottom right of the screen.
: 12. SELECT "Save and Process Data".
: 13. ENTER a name for the meteorological observation data set. This allows for repeated updating of new met data saved under different names for future retrieval.
Example: 090108 1100 (Date and time)
NOTE: The parameters listed below are not normally changed from the computer specified default values but the option is available. The RCC/RCD or RCM should be consulted prior to changing.
: 14. VERIFY the following options are selected AND EDIT as necessary.
: a. Data set description: Created automatically from first site data record
: b. Save data set as: Event-specific data set
: c. Data processing options - Estimate missing stability using: Wind speed, time of day, etc. (recommended)
: d. Adjust stability for consistency: Yes (recommended)
: e. Modify winds for topography: Yes
: 15. SELECT OK.
: 16. SELECT Return.
: 17. SELECT OK and a ,/mark will appear in front of Meteorology when this step is complete.
                                            .. . . .- v.:. ... .. ... .
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9.11  INPUT Meteorology (continued)
: 18. GO TO Step 9.12.
9.11.2 IF no actual observation or forecast data is available SELECT Predefined Data (Non Site-specific).
: 1. SELECT the available data set that most resembles current weather conditions at the site.
: 2. SELECT OK and a .,mark will appear in front of Meteorology when this step is complete.
9.12  SELECT Calculate Doses 9.12.1 SELECT the appropriate distances for calculations. Typically the "Close in + out to10 miles" option is chosen to supply the required results.
9.12.2 IF the dose assessment is for Brunswick Unit 1 or 2 GO TO step 9.12.6.
9.12.3 SELECT user defined distances AND Set Close Distances.
9.12.4. ENTER the applicable site boundary distance. of the non-UF6 Release as applicable:
: 1. Crystal River 3: REPLACE 1.000 mile with 0.83 miles.
: 2. Harris Plant: REPLACE 0.500 miles with 0.47 miles.
: 3. Robinson Plant: REPLACE 0.200 miles with 0.265 miles.
9.12.5 SELECT OK.
CAUTION The "Start of release to atmosphere plus" value is NOT the same as the release duration. The."Start of release to atmosphere plus" provides for a time duration.
long enough for the entire plume to pass over the region of interest. This time includes the release duration plus enough time for the entire plume to: cover the area of interest. The wind speed needs to be taken into account.
9.12.6    COMPLETE the "End Calculations at".field..
: 1. SELECT "Start of release to atmosphere plus" THEN ENTER the number of hours. The .default is 6. hours and is sufficient during the early phases of a.
release, OR
: 2. SELECT User specified time THEN ENTER the date and time. This option is normally used as additional information becomes available.
EMG-NGGC-0002                                  Rev. 6                              Page 39 of 88
 
9.12  SELECT Calculate Doses (continued) 9.12.7. ENTER the Case description. A case description is required for identification of variations of case input data.SELECT OK to begin calculations and a V mark will appear in front of Calculate Doses when this step is complete.
9.13  REVIEW Detailed Results This step is optional and can be used to view detailed results that are useful in comparing projections with field team data. However critical information shall not be delayed to perform review details.                  .
9.13.1  SELECT Detailed Results.
9.13.2  SELECT the desired options on the Detailed Results of Dose Calculations screen.
9.13.3  SELECT Display Selected Result button and the graphic display of plume footprint for the calculated case is presented on screen. POSITION cursor over cell to view specific bearing, distance, or dose.
9.13.4  SELECT OK, then EXIT to return to primary screen for completing a dose assessment..
9.14  Dose Projection Results CAUTION Time is Of the essence when conducting and approving dose projections. Dose projection results may escalate OR preclude emergency action level declarations.
NOTE:          Projections developed when there is no release in progress and using what if' data parameters are not required to be reviewed and apprioved. "What if' scenarios should not be disseminated to ERO personnel excluding the. RCM or RCC or RCD.
9.14.1  SELECT AND PRINT the reports from the Maximum Dose Values tab AND the Source Term Summary tab.
                              ......            e.                            P ge40o 88 .2
                                              . Rev. 6 E MG-NGGC-0002 I      .      Page 40 of 88 .
 
9.14  Dose Projection Results (continued)
I                                                                        I NOTE:        The appropriate printer must be selected in the Print Setup option under the        fl RASCAL File menu. This is in addition to the Windows default printer selection.
9.14.2  PEER*CHECK the dose assessment with the assistance of another dose assessment team member, leader, RCC, RCD or RCM. The peer check shall at a minimum provide verification that:
        *a. Release parameters are correct
: b. The results do not affect the current EAL classification.
: c. The results do not change any Protective Action Recommendations 9.14.3  COMPARE dose projection results with alternate methods of dose projection, if available. These include:
: a. Comparison with field monitoring. The RASCAL detailed results provides the capability to determine location and time specific values for dose rates and airborne concentrations. These detailed results should -be compared with actual field measurements and adjustments made as necessary. Field measurements may be available from utility teams, state teams, or federal teams, including fly-over surveys.
: b. Comparison with state or NRC dose projection results. Share dose projection results-with state and NRC dose projection personnel. Attempt to.explain any significant differences as time permits.
9.14.4  IF the dose projection is incorrect, THEN develop a new dose.projection.
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9.14    Dose Projection Results (continued) 9.14.5    IF the projection is correct, THEN provide the RCM the projection print-outs for approval.
[
NOTE:            Dose projection results must be approved prior to communicating the Tinformation.to offsite agencies. This information is typically transmitted via the.
Emergency Notification Form (ENF) which is approved by the Emergency Operations Facility Command position (e.g., Emergency Response Manager.)
9.14.6    The RCM shall REVIEW AND APPROVE the projection. Approval is to acknowledge the:
Dose projection is accurate.
* PARs are developed..
* Information is communicated for ENF transmittal. Dose information from the Maximum Dose Values Report should be converted from Rem to mRem prior to entering it on the ENF.
9.14.7    The RCM shall SIGN AND DATE the dose projection to denote approval.
9.14.8    The RCM *shall IMMEDIATELY COMMUNICATE dose projection results for evaluation of an EAL classification impact to the Site Emergency Coordinator.
9.14.9. The RCM shall COMMUNICATE dose projection results IMMEDIATELY to the EOF if PARs are impacted OR no later than the next EOF briefing if PARs are not impacted, 9.14.10 PROVIDE a copy to the RASCAL Case Summary to State Dose Projection personnel. at the State EOC .and/or EOF for each projection released on the Emergency Notification Form (ENF).
9.14.11  IF the dose calculation is for CRYSTAL RIVER 3 THEN fill in the blank projection
            .duration (Item 14) of the Florida Nuclear Plant Emergency Notification Form with the correct time frame, EMG-NGGC-0002                                  Rev. 6                            Pag.e 42 of 88
 
9.14    Dose Projection Results (continued)
IINOTE:      If an approved computer application is available for transferring dose projection information to the ENF electronically, then this application should be used.      I 9.14.12  ENTER the Noble Gas Activity and the Iodine Activity in Curies for Release Magnitude on Line 14 of the ENF using the Source Term Summary Report. The total activity is acceptable for reporting purposes unless a specific breakdown is requested by local State or county emergency management personnel. This step is NOT applicable to CR3.
9.14.13  CONVERT the RASCAL results in REM to mRem AND ENTER the Total Effective Dose Equivalent (TEDE) in mRem for the following distances in the appropriate blocks of the ENF using the Maximum Dose Values Report:
* site boundary
* 2.0 mile
* 5.0 mile, and
* 10 mile 9.14.14  CONVERT the RASCAL results in REM to mRem AND ENTER the Thyroid Committed Dose Equivalent (CDE) in mRem for the following distances in the appropriate blocks of the ENF using the Maximum Dose Values Report:
* site boundary,
* 2.0 mile
                  *5.0 mile, and
            *10      mile EMG-NGGC-0002                                  Rev. 6                            Page 43 of 88
 
9.15    Save the Case 9.15.1 SELECT Save Case to save the projection for future review or revision. Consider the.
following:
: 1. The user creates the file name and RASCAL saves the projection file with a .STD extension.
: 2. The default folder for saved cases is C:\Program Files\RASCAL3\Save Case\.
: 3. The user may create a new subfolder for a group of projections for the current event. The recommended location for a new subfolder on the C: drive is under the default Save Case folder.
: 4. The case may be saved to a shared folder to allow both the TSC and EOF access.
The recommended location for a shared folder is in the applicable site drive:\Shared\RASCAL\. For example Crystal River 3 would use L:\Shared\RASCAL\. Subfolders may be created in the shared directory if desired.
      .5. The case may be -savedto a specific filethat is used for direct input to the Emergency Notification Form via WEBEOC. The case should only be saved here after approval by the RCM. The file name must remain as exists (e.g,, don't add a date). Saving the case to this file will delete the previous case saved in this location. The specific location for each site is:
: a. BNP    K:SHARED\EP\ENF DATA\BNP WEBEOC.STD b,    CR3    Does not have direct transfer to ENF capability
: c. HNP    Y:\Shared\Emergency Preparedness\ENF_Data\ HNP Unit 1 WebEOC.STD
: d. RNP .. V\Shared\Emergency Preparedness\ENF DATA\RNP Dose.STD 9.15.2    IF the default folder is not going to be used THEN CHANGE the directory as applicable.
9.15.3    ENTER a File Name.
NOTE:            1f the shared case is to be modified, it needs to be copied back to the C:\RASCAL\Save Case\ folder on the hard drive. Otherwise, ai error is encountered when editing met data.
9.15.4    SELECT Save.
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9.16  Field Measurements to Dose Model (FMDose)
The Field Measurement to Dose model would normally be used after releases had ended to determine whether the area is habitable or do residents need long-term relocation. The model estimates doses based upon measurement of ground contamination.
9.16.1 IF projecting doses from a release and at least one ground sample concentration for that sample location is available, THEN select Field Measurement to Dose Model (FMDose). This option is NOT normally used for performing early phase dose projections.
9.16.2 SELECT Event Description.
: 1. ENTER the Event name.
: 2. The following information is OPTIONAL and not required. ENTER the following as desired.
: a. Date AND time the release started.
: b. Release location in latitude AND longitude degrees.
: 3. SELECT OK and a /mark will appear in front of Event Description when this step is complete.
9.16.3 SELECT Sample Data.
1.,  ENTER the Sample ID.
2..ENTER theDate AND time the sample was analyzed.
        *3. VERIFY the correct sample ground concentration units by clicking on the >
symbol AND REVISE as necessary.
: 4. ENTER the sample nuclide.AND ground concentration for each radionuclide...
: 5. The following information is OPTIONAL and not required.: ENTER the following as desired.
: a. Sample location in latitude AND longitude degrees.
: b. Sample description.
: 6. SELECT OK and a ,"mark will appear in front of Sample Data when this step is complete.
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9.16  Field Measurements to Dose Model (FMDose) (continued) 9.16.4 SELECT Calculation Options AND REVISE the following parameters as necessary.
: 1. Intermediate Phase
: a. Reentry delay in days
: b. Select the DIL marker nuclide. The DIL marker is a single radionuclide contained in deposition or a sample that is easily identified in the field. It is used to determine areas of concern before performing a comprehensive isotopic analysis.
        .2. Factors used. with. Ground Concentrations
: a. Ground roughness correction factor
: b. Initial resuspension factor per meter
: c. Inadvertent ingestion rate in cm 2 perday
: d. Occupancy time in hours per week
: e. Calculation settings in the desired units.
3.. SELECT OK and a .mark will appear in front of Calculation Options when this step is complete.
9.16.5 SELECT Compute Doses.
SELECT the desired data to review. Options include:
S
* Intermediate Phase Doses
              . Deposition Exposure Rate DILs
* Marker Nuclide Concentration DILS
: 2. SELECT Print as desired.
9.16.6 SAVE the case per Section 9.15..
9.17  Multiple Release Points 9.17.1 PERFORM a separate RASCAL dose projection run for each release point.
9.17.2 Attachment 4, Multiple Release Point Calculation Sheet can be used as an aid for radioactive material releases from multiple plant locations.
10.0  RECORDS Records generated as a result of the performance of this procedure shall be submitted to Emergency Preparedness for retention in the plant vault.
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ATTACHMENT 1 Sheet I of 1 RASCAL General Flowpath Select an event type -
Nuclear Power Plant or Spent Fuel Nuclear Power Plant                                      Spent Fuel Choose Event Location                                Choose Event Location Choose Source Term and Enter Required                    Choose Source Term and Enter Required Information:                                            Information:
e Time Core is Uncovered.
    " Ultimate Core Damage State                            . Pool Storage - Uncovered Fuel
    " Containment Radiation Monitor                          " Pool Storage - Damaged Assembly
    . Coolant Sample                                            Underwater
    " Containment Air Sample
* Dry Storage - Cask Release
    " Effluent Isotopic Release Rates
    " " Effluent Isotopic ReleaseConcentrations
      , Monitored.Releases - Mixtures
* Choose Release Path and Enter Required Information.
Choose Release Path and Enter Required Information:.:
* Wet Well
          .DryWell
* Secondary Conf.ainment Bypass
        " Containment Leakage/Failure
        " Steam Generator Tube Rupture F
Enter Meteorology.
Calculate Doses EMG-NGGC-0002                              *N      0Rev.
6                                page 47 of 88
 
ATTACHMENT 2 Sheet 1 of 2 Source Term Type Selection Guide This table lists all the source term: types available for nuclear power plant accidents, guidance on when to use each type and the source terms available.
      'Source Term Type                                                  When Used "                                      Data Needed        Available Release Paths Time Core Uncovered                              Use when you can estimate how long the core will be      Reactor Shutdown? Date/Time  BWR:
(Procedure Step 9.6.1)                          u.ncovered and you. want RASCAL to estimate the core      Core Uncovered 7 Date/Time  Wet Well damage that will result. Catastrophic event/release.      Core Recovered.? Date/Time  Dry Well However, if the release is in progress or has occurred                                Secondary Containment Bypass and is via a monitored-pathway, use of the Monitored Releases - Mixtures option is preferred and performed                                Containment leakage/failure in accordance with a site specific procedure.          ..                              Steam generator tube rupture
      .. __.._                                                  .-                                                                      Containment bypass UltimateCore Damage-                            Use this option when you believe you can make a valid    Reactor shutdown? Date/Time  BWR:
State                                          estimate of the amOunt of core damage that has            Core Damage state.          Wet Well (Procedure Step 9.6.2)                          o5ccurred..It can also be used for 'what if' analyses.      No damage .              Dry Well However,if the release is in progress or has occurred      Fuel pin leakage          Secondary Containment Bypass and is via a monitored pathway, use Of the Monitored        Cladding failure          PWR:
Releases - Mixtures option is preferred and performed                        "      Containment leakage/failure.
in accordance with a site specific procedure....        Time/Date coolant.release    Steam generator tube rupture
                  .. __._.._*_"_. _*_._Containment                                  ...                                                            bypass Containment Radiation                          Use. containment. radiation monitor when you have        Reactor Shutdown? Date/Time BWR:
Monitor                                        readings:from the, containment monitor, you want the    Core Uncovered? Date/Time    Wet Well (Procedure Step 9.6.3)                          code to estimate the core damage from the readings.      Containment Monitor          Dry Well However, if the release is in progress.or has occurred  Reading/Date/Time,          PWR:
and is via a monitored pathway, use of the Monitored
* Containment leakage/failure Releases- Mixtures option is preferred and performed
                                                  *in accordance with a site specificd.procedure.                                            .      _
* CoolantSample                                    Use coolant sample when you know the coolant            Sample ID                    BWR:
(Procedure Step 9.6.4)                  "        activity and coolant will be released to.the atmosphere. Date/Time.                  Secondary Containment Bypass However, if the release is in progress or hasoccurred    Activity (Isotopic)          PWR:
and is via. a monitored pathway, use of the Monitored                                Steam generator tube rupture Releases.- Mixtures option is preferred and performed                                Containment bypass
                "_    _          _                in accordance with a site specific procedure.                                      "
Containment Air Sample                          Use' air sample when you know the activity in the        Sample ID. "BWR:
(Procedure Step 9:6.5)                          containment. air and it will be released to the                                      Wet Well atmosphere via Containment leakage or failure..          Date/Time                    Dry Well However, if the release is in progress or has occurred  Activity (Isotopic)          Secondary Containment Bypass andis via a monitored pathway, use of the Monitored                                  PWR:
Releases - Mixtures option is preferred and performed    .                            Containment leakage/failure in accordance with.a site specific procedure.                                ..
.EMG-NGGC-0002                                                                                          Rev. 6                              Page 48 of 88:
 
ATTACHMENT 2 Sheet 2 of 2' Source Term Type Selection Guide Source Term Type                              When Used                                            Data Needed          Available Release Paths Effluent Isotopic Release'  Use the effluent rate when the release is through a        Release Location Rates                        sampled pathway that allows determination of the (Procedure Step 9.6.6)      release rate of nuclides in terms.of activity perunit      Release Period(s) Date/Time      Release direct to atmosphere time...                    ..              .'            Activity (Isotopic)/unit time Effluent Isotopic Release    Use the effluent -concentration when the release iS Release Location Concentrations              through a sampled pathway that allows determination (Procedure ro.edureStep      of the release flow rate. and the concentrations of Release Period(s) Date/Time.            Release direct to atmosphere 9..7 9.6.7)                                          volume
                            .nuclides in terms of activity per unit volume.          . Activitity (sotopic)/volume Iooi)vlm Monitored Releases -        Use the gross concentration method when you know          Reactor Shutdown? Date/Time Mixtures                r  the concentration of the activity. being released, but (Site sPecific procedures)  youdo not know the composition by nuclide. Site            Date/Time                        Release direct to atmosphere (i      .      procedures providethe method to calculate release . Sample Date/Time BNP:; OPEP-03.4.8            rates (Ci/sec) for noblegases, iodines and particulates Release Rate Unit using radiation monitor and flow rate. information.
CR3: EM-204B                                                          .                Release rates for:
HNP-: .'PEP-344                                                                            noble gases iodines RNP; EPRAD-03                                                                                ai particulates Pool Storage -
* Use this source term When fuel is exposed abovethe        Density of fuel pool.racking Uncovered Fuel              water.                                                    Number or batches of assemblies  Spent fuel release pathway (Procedure step 9.8.1)                                                                  irradiated within.1,2 and 3 years Fuel uncovered? Date/Time.
Pool totally drained? Yes/No Fuel recovered? Yes/No        .
Pool. Storage -        "    Use this source term when there are damaged                Number of damaged assemblies Damaged Assembly            assemblies underwater.                                  ' Age of damaged assemblies or      Spent fuel release pathway Underwater                                                                              how long damaged assemblies (Procedure step 9.8.2).                                                                have .been in storage When damage occurred
*__              _..                                                                    Date/Time Dry Storage - Cask          Use this source term when there are damaged                Type of Cask Release-                    assemblies in a cask.                '                    Age of damaged assemblies        Spent fuel release pathway (procedure step 9.8.3) ' "                  ."Type                                                of Event EMG-NGGC-0002                                                                    " Rev. 6.                                    Page 49 of 88
 
ATTACHMENT 3 Sheet 1 of I Weather Report Symbol, Model Class, and Intensity The following table lists typical nomenclature used by offsite weather agencies to report actual and forecast meteorological data. The table can be used to aid in interpretation of offsite meteorological information received.
WEATHER REPORT SYMBOL              MODEL CLASS            INTENSITY                "
None                                    NONE A                                      SNOW              Moderate:.
IC-, IP-                                SNOW                Light IC, .IP ..                              SNOW              Moderate IC+, IP+                              .SNOW                Heavy L-, L, L+                                RAIN                Light R-, RW-..                                RAIN                Light R, RW                                    RAIN              Moderate R+, RW+                                  RAIN              Heavy S-, SG-, SP-, SW-                      SNOW                Light S, SG, SP, .SW ..                      SNOW              Moderate S+, SG+, SP+, SW+                      SNOW                Heavy ZL-, ZL, ZL+, ZR-*                      RAIN                Light ZR.                                      RAIN              Moderate
            .ZR+.                                    RAIN              Heavy Rev. 6                                      of 88.
EMG-NGGc-b002                                                                  Page .50 MG. N...00"                                  Rev. 6                          Pae"50    of 8
 
                                                                      . ATTACHMENT 4 Sheet 1 of I Multiple Release Point Calculation Sheet RELEASE                              TIME      TEDE                TEDE.              TEDE              TEDE              Total Curies CHARACTERISTIC                                (Site Boundary)    .(2 Mile)          (5"Mile)          (10 Mile)
Main Stack Turbine Building        .  ... .
Reactor or Auxiliary Building                            .. '_"_'
Torus Vent Other
*(1) TEDE.SUM TOTAL (2) CURIE SUM TOTAL              if                                              Z'I                1--                -  (2)
      .                              TIME      Thyroid CDE          Thyroid CDE        Thyroid CDE      Thyroid.CDE
.      "    ."'(Site                                Boundary)      (2 Mile)          (5. Mile).        (10 Mile)
  .Main.Stack Turbine Building .
:Reactor or Auxiliary Building                  . _    _"_...._"
:Torus Vent Other (3) Thyroid CDE TOTAL NOTE: TEDE and Thyroid CDE.Summation are in units of REM and must be converted to Units of mrem prior to entering the information onto the Emergency Notification. Form ((1) or (3)      Rem x 1000 = " . mrem)
(1) Each TEDE Column Total corresponds to the TEDE line of theEmergency Notification Form.          *
(2) Enter the Sum of Total Curies on line 14 MAGNITUDE: (Other). of the.Emergency Notification Form (BNP, HNP and RNP only).
(3) Thyroid CDE Column Totalcorresponds to line 16 (Thyroid CDE) of the Emergency Notification Form (BNP, HNP and RNP only).
EMG-NGGC-0002                                                                  Rev. 6                                Page 51 of 88
 
ATTACHMENT 5 Sheet I of 9 Brunswick Unit 1 and 2 Specific Actions and Parameters This attachment contains the following sections:
1.0  Brunswick Unit 1 and 2 Default Data 2.0  Data Sheet for Dose Projections 3.0  Meteorology 4.0    BNP Pathway/Source Term Option Guidance 1.0    Brunswick Unit 1 and 2 Default Data Unit 1:
Average reactor power    2923      coolant volume    3.379E+04    Avg. fuel burnup-      30000 MW(th)                                                              MWD/MTU (in
..iW ______th)___                    (gel)_
___'          __ ..      .reactor) "_*_._-_*
.Number of assemblies    560        Containment        1.641 E+05  Avg. fuel burnup-      50000 in core                            volume (ft3)                    MWD/MTU (in spent fuel storage)
Unit 2:
Average reactor power    2923      Coolant volume      3.218E+04  Avg. fuel burnup-        30000 MW(th)                              (gal)                          MWD/MTU (in reactor)
Number.of assemblies in. 560      Containment        1.641 E+05  Avg, fuel burn.up-      50000 core                                volume (ft 3)                  MWD/MTU (in spent fuel storage)
EMG-NGGC-0002                                Rev. 6                          Page 52 of 88
 
ATTACHMENT 5 Sheet 2 of 9 Brunswick Unit I and 2 Specific Actions and Parameters 2.0  Data Sheet for Dose Projections CHARACTERISTIC      TIME Main Stack          Release.Rate (p>"Ci/cc).      ....                    _  __"
Flow Rate (CFM)
Turbine Building    #1 Release Rate (p Ci/cc)
                        #1 Flow Rate (CFM)
                        #2 Release Rate (p*Ci/cc)
                        #2 Flow Rate (CFM)
Reactor Building    Release Rate (uCi/cc)
Flow Rate (CFM) '
Torus Vent          Release Rate (pi Ci/cc)....
Core Uncovered      Time (1) lost/ (2) Returned Effective Filtration Yes . No Release Height      Ground.
Elevated Release Duration    Anticipated Length of Time Shutdown            Date Time Met Data Wind Speed  Upper Lower Met Data Direction  Upper Lower Stability            Class Seabreeze            Yes/  No EMG-NGGC-0002                                                Rev. 6                      Page 53 of 88
 
ATTACHMENT 5 Sheet 3 of 9.
Brunswick Unit I and 2 Specific Actions and Parameters 3.0      METEOROLOGY 3.1    IF available ACQUIRE meteorological data by ERFIS.
3.1.1  PRESS the RETURN <CR> key a couple of times to awake theterminal.
3.1.2  IF the Terminal server port has been Logged-Off, THEN ENTER your name when prompted, AND PRESS RETURN <CR>. Any name-will do, such as your last name.
NOTES:
: 1. The server prompt looks like "local>" or "DSVRxx" where xx is one of many ERFIS terminal server numbers.
: 2. Several of the connect messages may have to be tried to find an active connection.
: 3. Use Connect Sim for link to Simulator. This provides canned data. The other four will connect to live met data.
3.1.3  IF terminal is not in the above prompt condition at start of entry, THEN CONTACT ERFIS duty pager.
3.1.4 TYPE any one of the following at the keyboard, WHEN either.of the prompts are displayed:                                    .
* CONNECT    SIM        <CR>  For the Simulator Computer.
* CONNECT    ECO1A    <CR>  For the Ul ERFIS Computer      TRA.
                            . CONNECT    ECO1B      <CR>  For the Ul ERFIS Computer      RTAD.
                      .0      CONNECT    ECO2A      <CR>  For the u2 ERFIS Computer      TRA.
* CONNECT    ECO2B      <CR>  For the U2 ERFIS Computer      RTAD.
3.1.5 TYPE your assigned USERNAME at the next LOGIN prompt. For example:
USERNAME: xxxxxxxxxx gepacuser <CR>
3.1.6 TYPE your assigned PASSWORD at the next LOGiN prompt. For example:-
PASSWORD: xxxxxxxxxx gepac <CR>IF your nextprompt is "Enter your last Name:" For example: xxxxxx <CR>
EMG-NGGC-0002                                    Rev. 6                            Page 54 of 88
 
ATTACHMENT 5 Sheet 4 of 9 Brunswick Unit 1 and 2 Specific Actions and Parameters 3.0    METEOROLOGY 3.1.7 TYPE your last name or work group, for example OPS, CHEMISTRY etc.
THEN the Computer Node prompt will appear (i.e., $, ECO1A::>; ECO1 B::>,
ECO2A::>, or ECO2B :>).
3.1.8 TYPE W <CR> and the ERFIS computer will display your WEATHER for the previous 15 minutes. The W*EATHER is a logical name assigned to all the computers listed above.
NOTES:
: 1. Typing W <CR> is all that is necessary because no other DIGITAL Command starts with this letter.
: 2. Weather is obtained by modem from the ERFIS computer to the MET Tower every 15 minutes.
Always use the Logical W*EATHER for update to obtain the latest information.
3.1.9 TYPE LOG <CR> to end the connection to any of the above Computers, AND TERMINATE the process.
3.2    IF ERFIS data is unavailable THEN OBTAIN Brunswick Nuclear Power Plant (BNP)
            ..Meteorological. Data from. the.. National Weather Service OR.Wilmington National Weather Service data by phone. (See EPL-001, Emergency Phone List, for the telephone number).
3.3    .DETERMINE the Sea Breeze Potential.
3.3.1  IF all of the following conditions are present, THEN the potential for a Sea Breeze Effect exists:
: 1. BNP wind direction is between 160 and 2690, AND
: 2. BNP Stability class of A, B, or C
: 3. "Meteorological      Data Record time is between 0700 and 1900 hours, AND
: 4. Meteorological Data Record date and date of Sea Breeze onset time are the same.
EMG-NGGC-0002                                  Rev. 6                          Page 55 of 88
 
ATTACHMENT 5 Sheet 5 of 9 Brunswick Unit I and 2 Specific Actions and Parameters 3.0    METEOROLOGY 3.4    IF a Sea Breeze is present, THEN RASCAL projections may underestimate the dose by a factor of 2.5, and the plume behavior may be erratic. Entering additional weather station data will improve the accuracy of modeling a sea breeze condition.
3.4.1  IF Sea Breeze conditions exist .during the case calculations, THEN CONSPICUOUSLY MARK printed reports as such.
3.4.2. POINT this out AND COMMUNICATE to the RCD, RCM, and other dose projection coordinators, when the reports are made available to them.
3.5    OBTAIN stability class from the Met Tower.
        .3.6... DETERMINE the stability class.
1.6.1. IF available OBTAIN data for stability class from the Met Tower.
3.6.2  IF stability class data is not available from the Met Tower THEN CALL the National Weather Service to. obtain the data.
3.6.3  IF stability class data is'not availablefrom the Met Tower or National Weather Service THEN DETERMINE the class using the following steps.
NOTES:
1 Delta T - (Preferred method of determination) - Temperature difference between the 1Om and 100m measuring points on the Met tower. Normally a negative number, but could be positive if
  .a temperature inversion exists.
: 2. Sigma theta - (Secondary method of determination) -Standard deviation of the horizontal wind.
direction fluctuation..                                        ..
: 1. IF meteorological data. is.available THEN OBTAIN. Delta T1 and Delta T2.
: a. CALCULATE the Differential Temperature BY SUMMING Delta T1 and Delta T2 THEN DIVIDING by 2. See equation below:
DT1+DT2=                  C/1 00M 2
EMG-NGGC-0002                                    Rev. 6                          Page 56 o.f 88
 
ATTACHMENT 5 Sheet 6 of 9 Brunswick Unit 1 and 2 Specific Actions and Parameters 3.0  METEOROLOGY'
: b. COMPARE the differential temperature in the table below to the Pasquill categories to determine the stability class.
STABILITY                PASQUILL            Differential Temperature C1100M CLASSIFICATION            CATEGORIES                                                  3 Extremely Unstable                    A                              <- .9 Moderately Unstable                  B                          -1.9.TO -1.7        ..
Slightly Unstable                    C                          -1.7 TO -1.5 Neutral                              D                          -1.5 TO -0.5 Slightly Stable                      E                        -.05 TO +1.5 Moderately Stable                    F                        +1.5 TO +4.0 Extremely Stable                      G                              > +4.0
: 2. IF.there.is no stability class data readily available, AND it is raining THEN ASSUME the stability class is D, OTHERWISE ESTIMATE the current Atmospheric Stability Class by visual observation using the following table:
SUNNY DAY            CLOUDY          CLOUDY          CLEAR NIGHT DAY            NIGHT LIGHTWIND/OR"                B                  C                E                  F CALM
_4m/secor8.9 mph MODERATELY                  C                  D                D                D STRONG WIND
    . ._!4 m/sec or 8.9 mph EMG-NGGC-0002.                                  Rev. 6                              Page 57 of 88
 
ATTACHMENT 5 Sheet 7 of 9 Brunswick Unit I and 2 Specific Actions and Parameters 3.0 METEOROLOGY 3.6.4 REFER to the following table when an elevated release exists since, maximum radiological exposures may occur beyond the site boundary depending on Stability Class. For example:
STABILITY CLASS                    DOWNWIND DISTANCE A                                0.27 MILES B                              0.45 MILES C                              0.76 MILES D                              1.8 MILES
:E                              335 MILES F                                9  MILES G                                33 MILES EMG-NGGC-0002                          R6Pe8f Rev. 6                        Pa ge 58 of 88
 
ATTACHMENT 5 Sheet 8 of 9 Brunswick Unit 1 and 2 Specific Actions and Parameters 4.0    BNP PATHWAY/SOURCE TERM OPTION GUIDANCE Pathways.
    ...Vessel ---- Drywell- ----------------- Environment ----  - ---------- pathway.:1 unmonitored Vessel ---- Drywell-----Reactor Building -----  7--Environment ------ f-pathway 2 monitored Vessel---Drywell--Reactor Building SBGT--stack--Environment-- pathway 3 monitored Vessel---Torus ------ Environment--....-                      -              pathway 4 .. unmonitored Vessel---.Torus---Reactor Building--SBGT-- stack--Environment--- pathway 5 monitored Vessel--- Torus---Reactor Building--- ---Environment                          pathway 6 monitored Vessel---- Turbine Building---Environment 7                ----------------
                                                                  "                pathway 7. unmonitored Vessel----Turbine Building---Environment--                                      ---........
pathway 8 monitored Vessel----Turbine Building---SBGT----stack                    ".......--...... pathway 9 mfonitored EMG-NGGC-0002                                    Rev. 6                                      Page 59 of 88
 
ATTACHMENT 5 Sheet 9 of 9 Brunswick Unit 1 and 2 Specific Actions and Parameters Source Term Pathway 1    ------------------            Time Core is Uncovered Containment Radiation Monitor Containment Air Sample 2
Pathway    -----------------------------    Time Core is Uncovered Containment Radiation Monitor.
Containment Air Sample Pathway 3----          ------              Time Core is Uncovered Containment Radiation Monitor Containment Air Sample Pathway 4        ----------------          Time Core is Uncovered Containment Radiation Monitor Containment Air Sample Pathway 5 -----------------                  Time Core is Uncovered.
Containment Radiation Monitor Containment Air Sample Pathway 6 ------                ----------  Time Core is.Uncovered Containment Radiation Monitor Containment Air Sample Pathway 7      --------          -------    Time Core is Uncovered    .
Ultimate Core Damage State Coolant.Sample Pathway 8            ----          ------ Time Core is Uncovered Ultimate Core Damage State.
Coolant Sample Pathway 9 -------        -----------
                                    .      . Time Core is Uncovered
                  . ....                        Ultimate Core Damage: State Coolant Sample' EMG-NGGC-0002                                        Rev. 6                    Page 60 of 88
 
ATTACHMENT 6 Sheet I of 10 Crystal River Specific Actions and Parameters This attachment contains:
1.0    Crystal River 3 Default Data -  Sheet 1 2.0    CR3 Accident Types With Rascal Source Term/Release Path Options - Sheet 2 This sheet provides guidance for selecting RASCAL source term and release path options..
Assumptions should be verified with the Technical Support Team and/or the Accident Assessment Team.
3.0    Site Boundary (0.83 miles) Dose Estimate Credibility Evaluation - Sheet 3 4.0    Meteorological Data Input Sheet - Sheet 5 5.0    Radiological Data Input Sheet - Sheet      6 6.0    Alternate Methods For Determining Meteorological Data - Sheet 7 7.0    Methods For Determining Core Damage          -  Sheet 8.
1.0    Crystal River 3 Default Data (Edit plant parameters as necessary.)
Average reactor power        2609    Coolant volume.      9.401 E+04-. Avg. fuel burnup-    ...42000 MW(th)                                                                  MWD/MTU (in
                                      -(ga!) .reactor)'
Number of assemblies in      177      Containment          2.000E+06  Avg. fuel burnup-        35000 core                                  volume (ft3)                      MWD/MTU (in spent fuel storage)
EMG-NGGC-0002                                    Rev. 6                            Page 61 of 88
 
ATTACHMENT 6 Sheet 2 of 10 Crystal River Specific Actions and Parameters 2.0    CR3 ACCIDENT TYPES WITH RASCAL SOURCE TERM I RELEASE PATH OPTIONS ACCIDENT TYPE                    RELEASE POINT                RASCAL SOURCE                          RASCAL RELEASE TERM OPTIONS                              PATH OPTIONS
                                              .                    Ultimate Core Damage State LOCA in containment            Containment to atmosphere                                          Containment Leakage/Failure Containment Rad Monitor              with pressure/hole size selected. OR percent volume Containment Air Sample                selected for Design Basis
                          * * '"  *                                        .  . .    .Leakage                      '
Time Core is Uncovered Containment to Intermediate    Ultimate Core Damage State            Containment Leakage/Failure Bldg                  Containment Rad Monitor.              with pressure/hole size selected Containment Air Sample Time Core is Uncovered Containment to Aux Bldg        Refer to LOCA inAux Bldg              Refer to LOCA inAux Bldg Monitored Release - Mixture*
Post-accident venting                                                Release Direct to Atmosphere Coolant Sample                        Containment Bypass or Ultimate Core Damage State            Containment Leakage/Failure selected Time Core is Uncovered LOCA inAux Bldg                Aux Bldg                        Monitored Release - Mixture*          Release Direct to Atmosphere Effluent Isotopic Release Conc Ultimate Core Damage State            Containment Bypass or Containrment Rad Mdnitor          .Containment      Leakage/Failure selected Steam Gen Tube Rupture          Steaming to atmosphere          Coolant Sample Ultimate Core Damage State Condenser to Aux Bldg vent      Monitored Release - Mixture*          Release Direct to Atmosphere Ultimate Core Damage State            Steam .Generator Tube Rupture Fuel Handling                  Aux Bldg                        Pool Storage - Damage                Spen~t Fuel Release Path
                                                          *'        Underwater Pool Storage - Fuel Uncovered Monitored Release .Mixture*          Release Direct to Atmosphere Waste Gas Decay.Tank            Aux Bldg.                      Monitored Release - Mixture.*        Release Direct to Atmosphere
* Effluent Isotopic Release Conc.
Effluent Isotopic Release Rate
                            ."Monitored Release.- Mixture is the preferred.option if the release.is monitored.
EMG-NGGC-0002                                                Rev. 6                                                Page 62 of 88
 
ATTACHMENT 6 Sheet 3 of 10 Crystal River Specific Actions and Parameters 3.0        Site Boundary (0.83 miles) Dose. Estimate Credibility Evaluation Dose. estimates in the first hour of a release may be compared with estimates .in this table as a credibility check; however, actual dose rates could vary. by orders of magnitude depending on plant conditions. Row 1 for extended shutdown conditions, all other rows for on-line conditions.
Monitor Reading or            Type of      Notes          Thyroid        TEDE                    Gas                        Iodine Accident Type            Source Term                    mR per        mR per                Ci/sec                        Ci/sec Estimate                    one hour      &#xfd;one hour Extended Shutdown:                RASCAL ST        12              730          1000 RM-A2 Accident Range at 10 Ci/sec (0.45 pCi/cc)
RM-AI Accident Range            Worksht ST      1, 3              2.6            1.8 at 1 Ci/sec (4.3E-2 pCi/cc)
RM-A2 Accident Range            WorkshtST        1,3        . 2.6            1.8 at 1 Ci/sec (1.4E-2 pCi/cc)
RM-G29130                        Worksht ST      3, 4            280              12 at 100 R/hr                      RASCAL ST        2,4              .12            0.6 LOCAN                            CR3 Default      3, 5            < 0.1          < 0.1                1.OE-5                        1.OE-7 NO Core Damage                  RASCAL ST          6              0.2            0.5      ......                                    :_"    "
'LOCAG                            CR3Default      3,5                15      .1.8                      0.7                          0.01
.Clad Failure                    RASCAL ST          7              770            .38                  ...........
LOCAC                            CR3 Default      3, 5            130            29                    14                        0.086 Fuel Melting                    RASCAL ST          7            6.300          350 *                        *-      .                  _
WGDTR                            CR3 Default      3, 5                9            0.1                  5.4            ....  ::M.A42E-5 FHA                    .        CR3 Default      3,.5              11            110.                  68..                      6.7E-3.
  *___......_                ___  RASCAL ST.        8            < 0.1          " 0.1'              i      ""        "              i  "    "
SGTRN                            CR3 Default      3, 5              24            1                  0.016                        0.016 NO Core Damage                  RASCAL ST          9    .      < 0.1          < 0.1
*_  _    _  _  _ __  _  _  _  _ Typical RCS      10            <0.1          <0.1  " "        ""            _;
SGTRG                            CR3 Default    3,5, 11          2.7E5          1.3E4                1100                          180 Clad Failure                      RASCAL ST          9              100              5                                  "  _                "
SGTRC                            CR3 Default    3,5, 11_1        2.1E6          1.2E5                '2.2E4                        1400 Fuel Melt                        RASCAL ST        .9          . 730 ..          42            ._._.__....        ,        _....
EMG-NGGC-0002                                          Rev. 6                                  Page 63 of 88
 
ATTACHMENT 6 Sheet 4 of 10 Crystal River Specific Actions and Parameters 3.0  Continued Standard Assumptions:
RASCAL model, NO holdup time, release height 0, building wake Yes, E stability class, 1 m/sec wind, NO rain, RB cfm=50,000; AB cfm=156,000 Assumption Notes From Table:
: 1. Base lI/NG Ratio=1, Iodine DFs:. Partitioning=l, Plateout=3, Sprays=10, Filters=20 Base PING Ratio=0.1, Particulate DFs: Partitioning=l, Plateout=10, Sprays=10, Filters=100
: 2.      RASCAL options: Containment Radiation Monitor, Containment Leakage/Failure
    .3.    'RASCAL options: Monitored Release - Mixtures, Release Direct to Atmosphere. The site boundary doses for RM-A1 and RM-A2 are equal because both monitors are assumed at 1.
Ci/sec. However, because of the higher flow rate.on RM-A2, less.pCi/cc is required to achieve. 1 Ci/sec.
: 4.      30 psig, 1 square inch hole, spray off
: 5.      2001 default Ci/sec calculations were used to derive total pCi/cc and allocation percentages for noble gases and halogens.
: 6.      RASCAL options: Ultimate Core Damage-State, Containment Bypass, 100 gpm.
: 7.      RASCAL. options: Ultimate Core Damage State, Containment Leakage/Failure,.- Design Basis Leakage
    *8.      1 assembly damaged, 1 month old, RASCAL options: Assembly Damaged Underwater, Release Direct Atmosphere, .100% / hr        *
: 9.      RASCAL options: Ultimate Core Damage State, Steam Generator Tube Rupture, 100 gpm 10:    RASCAL options: Coolant Sample (typical omnline concentrations), Steam Generator Tube Rupture, 100 gpm      *
: 11. There is a huge disparity between the CR3 default doses and doses derived using the standard RASCAL source terms. The RASCAL source terms should be considered more -
credible. The CR3 default doses should be viewed as the upper limit doses bounding a SGTR event with core damage.
: 12. The TEDE dose is the .EM-202 EAL. 1.4 Protective Action Guideline (PAG) threshold value.
for extended shutdown conditions as documented in Calculation N12-0001.
EMG-NGGC-0002.                                Rev. 6                              Page 64 of 88
 
ATTACHMENT 6 Sheet 5 of 10 Crystal River Specific Actions and Parameters
.4.0          METEOROLOGICAL DATA INPUT SHEET DATE/TIME OF TRIP:                    *____"  ___            DATE/TIME OF RELEASE:._              _      _    _
SoUrces listed by priority - enter number of source data used in each column heading
: 1. 33ft Primary Tower
: 2. 175ft Primary Tower
: 3. 33ft Alternate Tower
: 4. Other METEOROLOGICAL DATA Rec  Obs    Date    .Data                Wind                Wind      .      Sigma Theta Deg        Stability          Rain    Air Or .Time        "  "*: '* .:
Direction            Speed            Wind. R or la~nge Deg Class            Inches  Temp F:cst                              ..From                mph              W        nPer                                    Deg.F
                                                .Deg                                        or                              15mi Delta T Deg F E.MG.-NGGC-0002                                                              Rev. 6                                      Page 65of 88
 
ATTACHMENT 6 Sheet 6 of 10 Crystal River Specific Actions and Parameters 5.0:    RADIOLOGICAL DATA SHEET Projection  Date  Data  Accident  Release. Release    Release  Gas pCi/cc  Iodine  Release    Sprays Number          Time    Type      Start    Stop      Flow Rate            *pCi/cc  Filtered    On/Off Time. Time    CFM/GPM        .                Yes/No EMG-NGGC-0002                                          Rev. 6                            Page 66 of 88
 
ATTACHMENT 6 Sheet 7 of 10 Crystal River Specific Actions and Parameters 6.0      ALTERNATE METHODS FOR DETERMINING METEOROLOGICAL DATA: The following steps are OPTIONAL and may be used as needed to obtain data.
6.1    ESTIMATE wind direction, wind speed, and wind range BY OBSERVING cooling tower vapor, flags, fossil stack smoke, etc.
6.2    DETERMINE Stability class by using Sigma Theta (preferred), Delta T, or wind range. Wind range is the difference (in degrees) between the highest and lowest wind direction tracing on the recorder for a 15 minute period.
SIGMA THETA                DELTA T            WIND RANGE      STABILITY CLASS (degrees)            (DEGREES)                (degrees)
                    > 22.5 .-                1.46                  > 1.35  A (mostdispersed
* _    _    _plume)
                < 22.5 to 17.5        -1.45 to -1.31            134 to 105 B
                < 17.5 to 12.5        -1.30 to-1.16              104 to 75  C
                < 12.5 to 7.5        -1.15 to -0.39              74 to 45  D
                < 7.5 to3.8          -0.38 to 1.15              44 to 23  E
                < 3.8 to 2.1          1.16 to 3.07              22 to 13  F
                    <2.1                  > 3.08 .                  12    G (most concentrated plume) 6.3    DETERMINE wind direction .by estimating the average value of the tracing for a 15 minute period.
6.4    OBTAIN weather data via the intra/internet by CHOOSING sites as required listed below.
6.4.1    GO TO AccuWeather.com.            ENTER zip code 34428 AND hour-by-hour..
6.4.2    GO TO Weather.com. ENTER zip code 34428 AND select hourly.
6A4.3    GO TO Energy.Control Center: Progress Net, Business Units and Departments, Energy Control Center Florida, Forecasts, Real Time Weather, Zone City Forecasts, THEN CLICK west central Florida area on map.
EM G-NGGC-0 002                                      Rev. 6                          Page 6 of&#xfd; 87 EMGN.C-002Re.                                              6Pae                              6  o.8
 
ATTACHMENT 6 Sheet 8 of 10 Crystal River Specific Actions and Parameters 6.5      OBTAIN meteorological data from the following sources if desired, however, non-local backup sources may NOT be representative. Phone numbers are in the Off-
            .site Support Directory.
0        Primary Backup - FAA Flight.Service Station in Gainesville, FL.
0        Secondary Backup - Tampa Weather Service in Ruskin, FL.
6.6      REFER to the following table to DETERMINE sectors affected based on the wind from direction.
DEGREES          SECTORS.            DEGREES      SECTORS          DEGREES    SECTORS.
349-11 (349-            HJK        102-123 (462-483)    NPQ            214-236      BC D 3 7 1).        ..                                          ....
    .12-33 (372-393)          J KL      124-146 (484-506)    P Q R        237-258      C DE 34-56 (394-416)        K L M.. 147-168 (507-528)    QR A          259-281. DE F 57-78 (417-438)        LMN        169&#xfd;191 (529-540)    R AB          282-303      EF G 79-101 (439-          MN P              192-213        A BC          304-326      FG H 461)                          .. .
                                                                              .327-348    GHJ 7.0  METHODS FOR DETERMINING CORE DAMAGE This section lists three methods of selecting accident type based on the level of core damage. Each method has advantages and disadvantages. Use the. most appropriate method (or combination) to predict the level of core damage. Methods are:
            .      Based on RM-G29 and RM-G30 readings                        .
* Based on Iodine ratio
            '      Basedon RCS pressure and temperature
                                                .  .        ,
EMG-NGGC-0002                                  Rev. 6                              Page 68 of
 
ATTACHMENT 6 Sheet 9 of 10 Crystal River Specific Actions and Parameters 7.1 DETERMINE BASED ON RM-G29 AND RM-G30 NOTE:    This method can be performed quickly, but requires a breach of the Reactor Coolant System. The monitor readings assume thorough mixing of the Reactor Building atmosphere which may take several hours. Earlier readings will likely be higher (conservative).
7.1.1  OBTAIN RM-G29 and RM-G30 readings.
* IGNORE spikes AND ESTIMATE the sustained monitor reading.
* DETERMINE accident type using the estimated value and the following data:
RM-G29/30 R/HR                            ACCIDENT TYPE
                    <100                ..                  Normal Coolant 100 - 25000 WITH RB SPRAY                Gas Gap Damage
                    .100 - 75000 *WITHOUT RB SPRAY          Gas Gap Damage
                    >25000 WITH RB SPRAY                    Core-Melt
                    >75000 WITHOUT RB SPRAY                  Core Melt 7.2 DETERMINE BASED ON IODINE RATIOS.
NOTE:    This method requires a gamma isotopic of a grab sample, which must be performed offsite..
There is NO way to distinguish between a gap release and a core melt release using iodine ratios.
7.2.1 ANALYZE a liquid or gas sample representative of the post-accident source term.
7.22.2 DETERMINE the ratio of 1-131 to Total Iodine.
* IF 1-131/Total Iodine is < 0.05 THEN ASSUME LOCAN or SGTRN.
            .      IF 1-1.31/Total Iodine is >. 0.05 THEN ASSUME LOCAG or SGTRG.
EMG-NGGC-0002.                                Rev.                          Page 69 of 88
 
ATTACHMENT 6 Sheet 10 of 10 Crystal River Specific Actions and Parameters 7.3        DETERMINE BASED ON RCS PRESSURE AND TEMPERATURE NOTE:            This method can be performed quickly, but will NOT indicate mechanically-induced core damage. The intersection of pressure from the Y axis and temperature from the X axis is the level of core damage. (Regions are from the Inadequate Core.)
              ..7.3.1  LOCATE the region on the graph where the RCS Pressure (psig) and the Tincore (degrees F) intersect.
7.3.2 IF intersection is Region. 1 OR Region 2 THEN. NO fuel damage exists. RCS activity is considered normal.
7.3.3 IF intersection is Region 3 THEN possible gas gap failure exists.
7.3.4 IF intersection is Severe Accident Region THEN possible core meltexists.
3000 2750 2500 2250 2000              RE7ThI 1
  . 1750 W 1500 1250
___      - EGIO___ I                  ___ ___I                O N3__
1000 750                      ~
____ ~ ~~ -___-__-
                                            ~ ~ ~    __- ~    ~ ~ ~ ~ ~ ~
__-__  ___  __-        T,
                                                                                    -TD1400 a__    F
_    __  _  I  _        _                                          SEVERE.
500 250 0
200 .. 300  400  500      600    700  800. 900    1000 1100. 1200 1300. 1400      1500 1600 -1700 1800.
Tincore (&deg;F)
EMG-NGG.-0002                                            Rev. 6                                      Page 70 of 88
 
ATTACHMENT 7 Sheet I of I H.B. Robinson Specific Actions and Parameters 1.0    H.B. Robinson Default Data.
Average reactor power        2339    Coolant volume      4.468E+04  Avg. fuel burnup-    *30000 MW(th)                                (gal)                            MWD/MTU (in reactor)
Number of assemblies in      157    Containment          2.100E+06  Avg. fuel burnup-      50000 core                                  volume (ft)                      MWD/MTU (in spent fuel storage) 2.0    Release Height Parameters USE the following height for radiological release points to the environment:
* Plant Vent Stack:                  62 meters (203 feet)
              ,      Other non-vent stack releases:      11 meters (36 feet)
Thirty-six (36) feet is equivalent to.the ground level sensors at el.even.(11) meters on the site meteorological tower.
3.0    Meteorological Data 3.1-  OBTAIN met data from the appropriate source (OSI/PI;,ERFIS, National Weather Service, Weather Services International (WSI), etc.).
3.2    IF a weather agency provides a written weather report, Attachment 3 provides information for weather report symbols. The minimum met data required for dose projection model is wind speed and direction.
3.3    IF OSI/PI and ERFIS. are unavailable THEN REFER to E.PRAD-03 for further guidance to obtain meteorological data.
EMG-NGGC:-0002                                  Rev. 6                              Page 71 of 88
 
ATTACHMENT 8 Sheet 1 of 16 Shearon Harris Specific Actions and Parameters This attachment contains the following sections:
1.0    Shearon Harris Default Data - Sheet. 1 2.0    Effective Release Heights - Sheet 1 3.0    Meteorological Data - Sheet 2
        .4.0    Calculate Dose Equivalent Activity        -  Sheet 7 5.0    HNP Source Term Type Selection Guide - Sheet 11 1.0      Shearon Harris Default Data 1.1    Following R17, when comparing RASCAL results with. other agencies, it will be important to communicate the changes from the default values in the plant parameter table.
1.2    Following R17, VERIFY that the HNP. Plant Parameters match the value in the following table, IF not THEN adjust to those values Average reactor power            2948*      Coolant              7.710E+04    Avg. fuel burnup-    39,870**
MW(th)                                      volume                            MWD/IMTU (in II                    (gal)                              reactor)
Number of assemblies in.      .157        Containment          2.344E+06    Avg. fuel burnup-    59,800-*
core                                        volume.(ft 3 )                    MWDIMTU (in spent
  .. _ ..        _*_...                    _fuel                                  storage)
*From EC 74914 IMPLEMENT LICENSE CHANGE FOR THE MUR UPRATE, B.1.2 Table 1
**From EC75840 HNP CYCLE 18 CORE DESIGN AND SAFETY ANALYSIS, Table B.1:Cycle 18 Neutronics Results.
Avg. Fuel burnup (in reactor) parameter is based upon two-thirds of the EC 75840 value' per NUREG 1887 Section' 2.0      Effective Release Heights.(enter the release height of the.release' point) 2.1    Use the following height for stack releases.
                    , Stack      1 (RAB &FHB)          .27.4  meters  (90 feet)
* Stack    3 (TB)                  .19.2 meters  (63 feet)
* Stack      5 (WPB)                24.1  meters  (79 feet)
                    * ...Stack  5A (WPB)                18.3 meters  (60 feet)
EMG-NGGC-0002                                        Rev. 6                                Page.72 of 88
 
ATTACHMENT 8 Sheet 2 of 16 Shearon Harris Specific Actions and Parameters 2.2    Use the following height for non-stack releases.
                  . Steam dumps                .18.3  meters (60 feet)
* PORVs                        14.9  meters (49 feet)
* Main Steam Safeties          15.9  meters (52 feet)
* CVPETS (TB Stack)            1.9.2 meters (63 feet) 2.3    If the release is not from one of the fixed sources noted above, then enter the actual height of the release point.
3.0    Meteorological Data
    .. 3.1. OBTAIN met data from the appropriate source (OSI/PI, ERFIS, National Weather Service, Weather Services International (WSI), etc.). For guidance on obtaining data from ERFIS, see the EP Training Module EP-08, ERFIS located at:
http://nqqweb/hnppassportdm/Mqen/EP-MODULEEP08.pdf NOTE: All release points at HNP are considered-to be a ground level release due to the stack height being less than 2.5 times the height of any surrounding building. Therefore, the 12.5 m wind direction and speeds are used as input into the meteorological data.
3.2    The HNP Site Meteorological'Data inputsfro0m ERFIS are:
: a. Wind Direction (from).in.degrees (ERFIS ID MMT1014 Avg. Wind Direction @
12.5 m)
: b. Speed (mph) (ERFIS ID MMT1008 Avg. Wind Speed @ 12.5 m) 3.3    IF a weather agency provides a written. weather report, Attachment 3 provides information for weather report symbols. The minimum met data required for dose projection model is wind speed and direction.
      .3.4    The default data set for HNP is HARR - Shearon Harris, Other data-sets based on met data .monitoring locations applicable for performing complex calculations are:
              . ..        BUY - Burlington
* FAY - Fayetteville
* HARR - Shearon Harris (Default)
* GSO - Greensboro
* IGX - Chapel Hill
                        . MEB- Maxton
                      . RDU- Raleigh-Durham 3.5    IF OSI/PI and ERFIS are unavailable THEN ACESS met data via modem connection.
EMG-NGGC-0002                                Rev. 6                            Page 73 of 88
 
ATTACHMENT 8 Sheet 3 of 16 Shearon Harris Specific Actions and Parameters CAUTION For cyber security reasons, the phone line connection at the modem must only be connected while the EOF is activated.
3.5.1 CONNECT phone line to the modem.
3.5.2 SELECT mettower from the Windows Start Bar.
3.5.3 WAIT for Windows to display the CONNECT TO box.
3.5.4 SELECT OK.
3.5.5 WAIT for Windows to display the CONNECT box.
3.5.6 SELECT the DIAL.
3.5.7  WAIT for the HyperTerminal screen to be displayed. The display will have a clear screen.
          '3.5.8 VERIFY the Caps Lock is off OTHERWISE turn the Caps Lock off.
        "3.5.9, TYPE in "u" THEN CLICK the Enter key. The "u' will NOT be seen but the following display will appear.
USER MENU (C) Communications. Menu          .(T) Test*Menu (F) System Functions Menu          (Z) Zeno Program Menu (S) Sample Period Menu              (Q) Quit (D) Data Retrieval Menu            (H) Help EMG-NGGC-0002                            Rev. 6                          Page 74 of 88
 
ATTACHMENT 8 Sheet 4 of 16 Shearon Harris Specific Actions and Parameters 3.5.10 TYPE in "d"THEN CLICK the Enter key. The following display will appear.
DATA RETRIEVAL MENU (A) Show Records AFTER Specified Time            (F) Flash Memory Information (B) Show Records BETWEEN Timespan                (D) Delete All Data Records (Ln) Show LAST n Records                        (N) Number Of Records Logged
(,) Show ALL Data Records                      .(U) User Menu
(@n) Show n Unmarked Records                    (Q) Quit (M) Mark Recently Shown Data                    (H) Help
              ..(C) Compute Data Logging Capacity.
Precede Any "Show Data" Command With An 'X' For X-Modem Transfer (e.g. Enter 'X*' To Send.All Data Sets Via X-Modem) 3.5.11 TYPE in I1 (NOTE: this is a small "I"and a "1") THEN CLICK the Enter key.
The following display of the last 15-minute average Met data will appear.
            " Sample display: .
EMG-NGGC-0002                            Rev. 6                            Page 75 of 88
 
ATTACHMENT 8 Sheet 5 of 16 Shearon Harris Specific Actions and Parameters NOTE:      Lines 2 and 3 below provide the data codes. Lines 4 and 5 provide the respective values. For example, the first value in line 2 (DATE) corresponds to the first value in line 4 (02/04/10), the third value in line 2 (AT 11 1av) corresponds to the third value in line 4 (63.57), etc. Each data code in lines 2 and 3 has a corresponding Value in lines 4 and 5. The table on the next page explains the codes on lines 2 and 3.
Line 1    Hit The Space Bar To Halt The Log Data Output.
Line.2    DATE      TIME. AT_11_1_avWSPD_61_avWVAR_61_avWDIR_61-avWDIR_12_avWVAR_12 Line 3    _av WSPD_12_avAT_60 1 av RH.11_av DT_1av.-DT_2_av.                          RAIN -BP.
av.SOLAR av DP av .
Line 4  . 02/04/10 08:30:01. 63.57.      6.30    15..78 359.25        3.30  15.34    4.1.4 62.7 Line5      3 93.88 -0.96      -0.85    0.00    30.00    0.21    61.81 Line 2 and Line 3 Code                    Description                        ERFIS ID DATE                          Date                                        N/A TIME                          Time                                        N/A AT 11 1 av WSPD 61 av                    Avg. Wind Speed @ 61.4 m                    MM T 010 WVAR-61 av                    Avg. Wind Direction Variance @ 61.4 m      MMT1012.
WDIR 61 av                    Avg. Wind  Direction @ 61.4 m              MMT1013 WDIR 12 av                    Avg. Wind  Direction @ 12.5 m              MMT1014.
WVAR 12 av                    Avg..Wind  Direction WVriance @ 12.5 m    MMT1009 WSPD 12 av                    Avg. Wind  Speed @ 12.5 m                  MMT1008 AT 60-1.av RH .11 av                      Avg. Relative Humidity ..........        ".MMT1018 DT 1 av                        Avg. Delta Temperature 1.C/100 m            MMT1005.
DT 2 av                        Avg. Delta Temperature.2 C/100 m            MMT1004 RAIN                          Precipitation, 15 min                      MMT1003 BP av                          Avg. Barometric Pressure                    MMT1002.
SOLAR-av                      Avg. Solar Radiation Lingley/Min            MMT100I DP-av                          Avg. Dew.Point,&deg;F                          MMT1000 E*-NG0.                      Rv    6Pge7                                    of.8 EMG-NG GC-0002                                  Rev. 6                                  Page 76 of 88
 
ATTACHMENT 8 Sheet 6 of 16.
Shearon Harris Specific Actions and Parameters DATA RETRIEVAL MENU (A) Show Records AFTER Specified Time                (F) Flash Memory Information (B) Show Records BETWEEN Timespan                    (D) Delete All Data Records (Ln) Show LAST n Records                              (N) Number Of Records Logged
(,) Show ALL Data Records                            (U) User Menu
(@n) Show n Unmarked Records                  (Q) Quit (M) Mark Recently Shown Data                  (H) Help (C) Compute Data Logging Capacity
    .Precede Any "Show.Data" Command With An. 'X' For X-Modem Transfer (e.g. Enter 'X*' To Send All Data Sets Via X-Modem).
3.5.12 TYPE in "q" THEN CLICK the Enter key to quit the Met menu.
            .3.5.13 SELECT the CALL dropdown AND THEN the DISCONNECT option on the HyperTerminal Command Bar at the top to terminate the modem connection to the Met Tower.
3.5.1.4 IF there is an extended period of inactivity THEN the Met Tower processor will automatically terminate the User interface menu.
: 1. At this .point data may be retrieved again by going to step 4.4.6. if this.
attachment.
3.5.15 VERIFY the phone line is disconnected at the modem when the EOF is deactivated.
    .3.6    USE -the following ERFIS Points if needed for met data:..
Speed in mph - MMT1008 Stability Class.- MMT1017 3.7    IF OSI/PI and ERFIS are not available to provide the stability class THEN an alternate method that may be used is shown below.
3.7.1 IF only one ERFIS AT channel is available (computer point MMT 1004 or MMT .1005), THEN USE the following table to determine the stability class.-
EMG-NGGC-0002                                  Rev. 6                            Page 77of 88
 
ATTACHMENT 8 Sheet 7 of 16 Shearon Harris Specific Actions and Parameters Stability Classes AT in &deg;C/100m                  Class
_<-19&deg; ..          ...        A or 1
                                >-1.9  0 to*_<  -1.7 0        B or 2
                                >-1.7  0 to*_<-1.5 0            C or 3
                                >-1.5 0.to*-< -0.5 0            D or 4
                                >-0.50 to <+1.5&deg;                E or 5
                                >+1.5  0    to    +4.00        F or6
                                >+4.00                        G or 7 3.7.2 IF the stability class is not.available. THEN. USE the following table.to choose the appropriate value:
Surface Wind    Daytime Solar Radiation                          Nighttime Conditions  Day or Speed (mph)                                                                            Night (For moderate cloud cover move one column to the right)
Summer\      Spring &Fall          Winter      Thin        <3/8      Heavy overcast    cloud    Overcast Clear Sky    Clear Sky                          (>1/2 cloud  cover    or Rain cover)
      <4.5            A            A-B                    B          E            F        D
      >4.5 to 9.0    A-B          B                    C            E            F        D
      >9.0to13.5      B            B-C                  C            D            E        D
      >13.5          C
                    *~~~            C-D  ...              D    ~      D D    .D  . D        D EMG-NGGC-0002                                        Rev. 6                                Page 78 of 88
 
ATTACHMENT 8 Sheet 8 of 16 Shearon Harris Specific Actions and Parameters 4.0 Calculate Dose Equivalent Activity IF requested CALCULATE. Dose Equivalent Activity for noble gas, halogen and particulates using the following tables.
4.1        CALCULATE Xe-133 (Noble Gas).Dose Equivalent.
Nuclide      Activity        X    DCFd/ DCFxe.!3 3        =    Xe-133 Equivalent (Ci)
Kr-85                        X    6.5E-02 Kr-85m.                      X    4.7E+00 Kr-87                        X    2.6E+01              - -.
Kr-88    "                  X    6.5E+01                  =
Xe-131m                      X    2.5E-01 Xe-133                      X. 1.OE+00 Xe-133m:                    X. 8.5E-01          .      =
Xe-135                      X    7:OE+00                  =.-
Xe-135m                      X1.3E+01 X.
Xe-138                      X    3.6E+01 F ..
4.2        CALCULATE 1-131 (Halogen) Dose Equivalent.
      "NuClide      Activity        X    DCFjDCF, 1 3 1          =    1-131 Equivalent (Ci) 1-131                        X    1"OE+00 1-132                        X    5.9E-03
        .1-133  .X                      . 1.7E-01        ... .                -
1-134                        X    1.OE-03                = ,
      .1-135                          X    2.9E-02 EMG-NGGC-0002                                Rev. 6 "                            Page 79 of 88
 
ATTACHMENT 8 Sheet 9 of 16 Shearon Harris Specific Actions and Parameters 4.0  Calculate Dose Equivalent Activity 4.3      CALCULATE Cs-1 37 (Particulate) Dose Equivalent.
Nuclide            Activity    X    DCF_/ DCFcs.137          = Xe-133 Equivalent (Ci)
Cs-134                          X    1.5E+00 Cs-1 36                        X  4.4E-01                  =
Cs-137.                        X    1.OE+00 Sb-127                          X  2.3E-01 Sb-129                          X  4.9E-02 Te-129m                        X  7.1E-01 Te-131m                        X  2.1E-O01 Te-132                          X  2.9E-01 Sr-89                          X    1.2E+00 Sr-90                          X  3.9E+01 Sr-91                          X  5.9E-02:
Ba-140                          X. .1.3E-01 Mo-99                          X    1:.3E-01 Ru-1.03                        X  3.2E-01
* Y-91                            X    1.4E+00 La-140.                        X  2.7E7-01:
                ,. . ' ,            -** .          ,  . . , ,i .    , . ; ." - " . . ..; .,.F.
EMG-NGGC-0002                                Rev. 6                                  Page 80 o .f .88 EMG-NG''02Re.                                6Paei8                                          o 88
 
ATTACHMENT 8 Sheet 10 of 16 Shearon Harris Specific Actions and Parameters 4.0  Calculate Dose Equivalent Activity 4.4    The following table and calculations provide insight for the Dose Equivalent activities calculated above.
NOTE:. The Dose Conversion. Factors (DCF&#xfd; in the following equations are taken from Tables.5-1 and 5-2 of EPA 400-92-01, Manual of Protective Action Guides and. Protective Actions for Nuclear Incidents. The DCFs for the Xe-1 33 noble gas equivalent and the Cs-1 37 particulate equivalent are combined exposure pathway DCFs from Table 5-1. The DCFs for the 1-131 halogen equivalent are from Table 5-2.
Dose Conversion Factors mrem (DCFi)
Isotope        DCF      Isotope      DCF    Isotope    DCF Kr-85      1.3E+00      1-133        2.2E+05  Sr-89    5.OE+04 Kr-85mr. 9.3E+0i      1-134        1.3E+03  Sr-90    1.6E+06 Kr-87      5.1E+021    1-135        3.8E+04. Sr-91    2.4E+03-Kr-88      1.3E+03    Cs-134        6.3E+04  Ba-140    5.3E+03 Xe- 131 m  4.9E+00    Cs-1 36      1.8E+04  Mo-99    5.2E+03 Xe-133    2.OE+01    C.s- 137      4.1E+04  Ru-103    1.3E+04 Xe-1 33m  *1.7E+0-1.
Sb-127        9.5E403  Y-91      5.9E+04 1.4E+02    Sb.-129      2.OE+03  La-140    1.1E+04 Xe-135m 2.5E+02        Te-129m      2.9E+04 Xe-1.38 7.2E+02        Te-.131m      8.6E+03 1-131      1.3E+06    Te-132        1.2E+04 1-132      7.7E+03 Equivalent activities are derived by the summation of multiplying the activity of the isotope times the ratio of the DCF for each isotope to the target isotope. Formulas.for determining equivalent values are:
EMG-NGGC-0002                .                  Rev. 6                          Page 81 of 88
 
ATTACHMENT 8 Sheet 11 of 16 Shearon Harris Specific Actions and Parameters 4.0  Calculate Dose Equivalent Activity 4.5    The following table and calculations provide insight for the Dose Equivalent activities calculated above. (Continued)
Xe-133 eauivalent (Noble Gases)
A xDCF
                          ~DCF X\,'-133 Where: Al= Activity of the isotope.
DCFI = DCF of the isotope.
133 DCFxe-133 = DCF for Xe 1-131 Equivalent (Halogens) 11wCDL      ADCF DC Where: A =.Activity of. the isotope.
DCFi = DCF of the isotope.
DCFM 1 3 1 = DCF for 1131 Cs-137 equivalent (Particulates)
CS' 37    ..      A xDCF DC1    -'137 Where:, Ai = Activity of the isotope.
DCFj = DCF of the isotope.
DCFcs-137 = DCF for Cs137 EMG-NGGC-0002                                  Rev. 6                        Page 82 of 88
 
ATTACHMENT 8 Sheet 12 of 16 Shearon Harris Specific Actions and:Parameters 5.0    HNP Source Term Type Selection Guide This table lists all the source term. types available for HNP accidents, guidance on when to use each type and the source terms available and where to obtain the required data for :RASCAL inputs.
Source Term Type              When Used            Source. Data Needed'    Obtain From      Available Release Paths Data        Obtain From Time Core Uncovered      Use when you can estimate      Reactor Shutdown?        EOF SRO      Containment leakage/failure (RCB      FOF AAT
(.Procedure Step 9.6.1). how long the core will, be    Date/Time.                            Leak Rate by percent volume or RCB uncovered and you Want                                                pressure/hole size)
RASCAL to estimate the        Core Uncovered?        . EOF SRO core damage that will result. Date/Time                              Steam generator tube rupture by Catastrophic event/release.                                          # of ruptured tubes                  EOF AAT Core Recovered?            EOF SRO      or by charging flow                  EOF SRO/ERFIS However, if the release is in  Date/Time progress or has occurred                                              Containment bypass (RCS leak rate    EOF SRO and is via a monitored-                                              into RAB; Filters - Yes if building pathway, use of the                                                  normal filtered or emergency filtered Monitored Releases -                                                  exhaust systems are operating)
Mixtures option is preferred.                                                                              Attachment 8 Not an Isolated Stack                Section 2.0 Release Height Ultimate Core Damage    Use this option when you      Reactor Shutdown?          EOF SRO State                    believe you can make a valid  Date/Time                              Steam generator tube rupture by (Procedure Step 9.6.2)  estimate of the amount of                                            # of ruptured.tubes.                  EOF AAT core damage that has.        Core Damage state                      or by charging flow                  .EOF SRO/ERFIS occurred. It can also be used    No damage                EOF AAT for...'what if' analyses..      Fuel pin leakage..                    Containment bypass (RCS leak rate    EOF SRO Cladding failure ...                  into RAB: Filters.- Yes.if building However, if the release is in                                      . normal filtered or emergency filtered progress or has occurred      Time/Date coolant release  EOF AAT    exhaust systems are operating) and is via a monitored                                                                                      Attachment 8 pathway, use of the                                                  Not an Isolated Stack  .            Section 2.0 .
Monitored Releases -                                                  Release Height Mixtures option is preferred.
EMG-NGGC-0002                                                            Rev. 6                                        Page 83 of 88
 
ATTACHMENT 8 Sheet 13 of 16 Shearon Harris Specific Actions and Parameters Containment Radiation. Use containment radiation. Reactor Shutdown?              EOF SRO    Containment leakage/failure (RCB      EOF.AAT
    'Monitor                monitor when you have          Date/Time                                  Leak Rate by percent volume or RCB (Procedure Step 9.6.3)  readings from the              Core Uncovered?                            pressure/hole size) containment monitor, you      Date/Time want the code to estimate                                                Not an Isolated Stack                Attachment 8 the core damage from the                                                  Release Height                        Section 2.0 readings.                      Containment Monitor          ERFIS/
Reading/Date/Time            MCR HP-However, if the release is in  (RM-01CR-3589-SA/SB)        RMS Tech progress or has occurred and is via a monitored pathway, use of the.
Monitored Releases                                            ..-
Mixtures option is preferred.                                      . *_._                      _..
Coolant Sample          Use coolant samplewhen        Sample ID                    OSC          Steam generator tube rupture by (Procedure -Step 9.6.4)  you know the cdolan.t activity Date/Time                    Chemistry    #.of ruptured tubes                  EoF AAT and coolant will be released                                Coord.        or by charging flow                  EOF SRO/ERFIS
                            -to the'atmosphere.
Activity (Isotopic7- verify  OSC          Containment bypass (RCS leak rate    EOF SRO However, if the release is in  units Chemistry reports'in  Chemistry    into RAB; Filters - Yes.if building progress orhas occurred        pCi/ml)                      Coord.        normal filtered or emergency filtered and is via a monitored                                                    exhaust systems are operating) pathway, use of the                                                                                            Attachment 8 Monitored Releases.-                    .                .              Not an Isolated Stack                Section 2.0 Mixtures option is preferred.  .                                          Release Height E.MG-NGGC-0002                                                              Rev. 6                                          Page 84 of 88
 
ATTACHMENT 8 Sheet 14 of 16 Shearon Harris Specific Actions and Parameters Containment Air Sample    Use air sample when, you      Sample ID                      OSC      Containment leakage/failure (RCB  EOF AAT (Procedure Step 9.6.5)    know the activity in the      Date/Time                      Chemistry Leak Rate by percent volume or RCB containment air and it will be                                Coord. pressure/hole size) released to the atmosphere via .Containment leakage or                                  .OSC        Not an Isolated Stack              Attachment 8 failure.                      Activity .(Isotopic - verify              Release Height                    Section 2.0.
units Chemistry reports in    .Chemistry pCi/ml)                        Coord.
However, if the release is in progress or has occurred.
and is via a monitored patfiway, use of the Monitored Releases -
Mixtures option is preferred.
Effluent Isotopic Release Use the effluent rate when. Release Location                ERFIS/    Release direct to atmosphere MCR HP-Rates                    the release is through a                                                                                    Attachment 8 (Procedure Step 9.6.6)    sampled pathway that allows    Release Period(s).            .RMS Tech. NOt an Isolated Stack              Section 2.0 determination of the release  Date/Time                                Release Height rate of nuclides in terms of  Activity (Isotopic)/unit time  OSC activity per unit time.        (Need to calculate release      Chemistry rate:                          Coord.
A(pCi/inl) x F(Ft 3/min) x4.7E(-4) .=R (Ci/sec)
Isotopic Activity -. Plant Vent Stack,. TB orWPB Vent Stack Air Sample -
verify units Chemistry reports in pCi/ml)
Flow Rate - Plant Vent          EOF SRO/
Stack, TB or WPB Vent          MCR HP-Stack Process Flow Rate        RMS Tech
                                                          - verify units plantdata in ft3/m in * - .    .        .
EMG-NGGC-0002                                                              Rev. 6.                                      Page 85 of 88
 
ATTACHMENT 8 Sheet 15 of 16 Shearon. Harris Specific Actions and. Parameters Effluent Isotopic Release      Use the effluent                Release Location            ERFIS/    Release direct to atmosphere Concentrations                concentration when the                                        MCR HP-                                        Attachment 8 (Procedure Step 9.6.7)        release is through a sampled Release Period(s)              RMS Tech  Not an Isolated Stack
* Section 2.0 pathway that allows.            Date/Time                            Release Height determination of the-release      Isotopic Activity - Plant  OSC flow rate and the                Vent Stack, TB or WPB        Chemistry concentrations of nuclides in Vent Stack Air Sample -        Coord.
terms of activity per unit .  .verify units Chemistry volume.                          reports in pCi/ml)
                                                                .Flow Rate - WRGM Eff..      EOF SRO/
Channel Plant Vent Stack    MCR HP-3509-1 ;, WPB Stack 5      RMS Tech 3546-1; WPB Stack 5A 3547-1; or TB Stack 3 3536-1 Process Flow Rate
                                                                  - verify units plant data in ft3/min .
Monitored Releases -          Use the gross concentration      See Procedure PEP-344                See Procedure PEP-344 for data Mixtures                      method when you know the        .for data needed                      needed
  *(site specific procedure)    concentratiOn of the activity being released, but you do not know the composition by nuclide. Site procedures provide the method to calculate release rates
                                .(Ci/sec) for noble gases, iodines and particulates using radiation monitor and
_____________                  flow rate information.
Pool Storage-                  Use this sourceterm when        Density of fuel pool        EOF AAT  Spent fuel release pathway Uncovered Fuel                fuel is exposed above the        racking
  &#xfd;Procedure step 9.8.1)        water.        .              . Number or batches of                  Not an Isolated Stack                Attachment 8 assemblies irradiated                Release Height                        Section 2.0 within 1,2. and 3 years Filtered if E12 or E13 is operating  EOF SRO Fuel uncovered?            EOF SRO Date/Time Pool totally drained?
Yes/No
                "______.    ....
__.".__"__-__                                    Fuel recovered? Yes/No                                              ...
EMG-NGGC-0002                                                                      Rev. 6                                    Page 86 of 88
 
ATTACHMENT 8 Sheet 16 of 16 Shearon. Harris *Specific Actions and Parameters Pool Storage -            Use this source term        Number of damaged      EOF AAT  Spent fuel release pathway Damaged Assembly          when there are damaged      assemblies                        N        se          kn Underwater                assemblies underwater.      Age of damaged                              H Ieate      t (Procedure step 9.8.2)      .                  . assemblies or how long            Release Height                      Section 2.0 damaged assemblies                Filtered if E12 or E13 is operating EOF SRO have been in storage When damage
                                *_ _'_'_.occurred                .- Date/Time Dry Storage- Cask '      Use this source term        Not applicable to HNP            Not applicable to HNP Release                  when there are damaged (procedure step 9.8.3)    assemblies in a cask.        "
EM-NG-002Rv.6Pae.7of8 EMG-NGGC.-OO02.                                                      Rev. 6                                    Page 87 of 88
 
==SUMMARY==
OF CHANGES EMG-NGGC-0002 REV 5 PRR 617154 SECTION/STEP                                      CHANGES Att. 8 step 3.5.2, Removed program locationdescription for WIN7 implementation.
9.1.2, Old 9.1.3  (Editorial).
EMG-NGGC-0002 REV 6 PRR 615736, CR.619320 SECTION/STEP                                      CHANGES Summary of        Corrected PRR number for revision 5 (PRR 619325)
Changes Section 9.1.1 &    Added removed RASCAL program instructions from. previous revision and Attachment 8      added location description for Windows 7 Desktop for WIN7 Step 3.5.2        implementation.
Reverted Att. 8 step 3.5.2 back to the previous revision.
EMG-NGGC-0002                                Rev.6 .a.e886f.8                  Page 88 of 88
 
Enclosure 2c EMG-NGGC-0004, Maintenance of the Emergency Response Organization, Revision 3
 
Progress Energy                              R Reference Use NUCLEAR GENERATION GROUP STANDARD PROCEDURE VOLUME 99 BOOK/PART 99 EMG-NGGC-0004 MAINTENANCE OF THE EMERGENCY RESPONSE ORGANIZATION NOTIFICATION SYSTEM REVISION 3
 
TABLE OF CONTENTS SECTION                                                                                                                    PAGE 1.0    PURPOSE ....................................................................................................            4
 
==2.0    REFERENCES==
.................................................................................................            4 2.1    Developm ental References .........................................................................                  4 2.2    Im plem enting References ...........................................................................                4 3.0    DEFINITIO NS ...................................................................................................        4 4.0    RESPO NSIBILITIES ........................................................................................              5 4.1    Em ergency Preparedness Staff ..................................................................                    5 4.2    Security and Operations Personnel ............................................................                      5 5.0    PREREQUISITES ............................................................................................              5 6.0    PRECAUTIO NS, LIM ITATIONS AND NOTES .................................................                                  5 7.0    SPECIAL TOO LS AND EQ UIPM ENT ..............................................................                          6 8.0    ACCEPTANCE CRITERIA ...............................................................................                    6 9.0    INSTRUCTIONS ...............................................................................................            6 9.1    Startup .......................................................................................................      6 9.2    Creating Emergency or Drill M essages ........................................................                      6 9.3    Create Scenario ..........................................................................................          8 9.4    Creating Polling Notifications ......................................................................                8 9.5    Scheduling Recurring Notifications ...........................................................                      10 9.6    Broadcast Report ......................................................................................            12 9.7    Deleting Emergency Notification Scenarios ...............................................                          13 9.8    Deleting Unscheduled M essages ..............................................................                      14 9.9    Updating Individual Member Contact Information in Emergency Notification Software .....................................................................................................      14 9.10 Removing Individual Members in Emergency Notification Software .............                                          15 9.11 Group Personnel Roster Additions/Changes .............................................                                15 9.12 Adding Groups and Mem bers to the Groups .............................................                                16 9.13 Deleting Groups ........................................................................................              17 9.14 Deleting Group M em bers ...........................................................................                  17 10.0    RECORDS ......................................................................................................        17 EMG-NGGC-0004                                            Rev. 3                                                    Page 2 of 21
 
TABLE OF CONTENTS SECTION                                                                                                                          PAGE ENCLOSURES 1      EverBridge Options - Telephone ..............................................................                          18 2      EverBridge Options - Upload Message .....................................................                              19 3      Message Delivery Options Definitions ......................................................                            20 S um m ary of C ha nges ...............................................................................................        . .21 EMG-NGGC-0004                        I                    Rev. 3                        1                            Page 3 of 21
 
1.0  PURPOSE This procedure provides instructions for performing routine updates, maintenance, and testing of the Emergency Response Organization Notification System.
 
==2.0  REFERENCES==
 
2.1  Developmental References None 2.2  Implementing References
: 1. CSP-NGGC-2505, Software Quality Assurance and Configuration Control of Business Computer Systems
: 2. EMG-NGGC-0005, Activation of the Emergency Response Organization Notification System.
: 3. Emergency Response Organization Notification Procedures
* EM-206 (EM0206), [CR3] Emergency Plan Roster Notification
            " PEP-310, [HNP] Notifications and Communications
* EPNOT-01, [RNP] CR/EOF Emergency Communicator
: 4. Site Emergency Plans
* OERP, (BNP) Radiological Emergency Response Plan
* RERP, [CR3] Radiological Emergency Response Plan
            "  PLP-201, [HNP] Emergency Plan
* PLP-007, [RNP] Robinson Emergency Plan 3.0  DEFINITIONS
: 1. EverBridge - Company that hosts the software and website used for notification
: 2. Group - Set of defined personnel to be notified
: 3. Interactive Voice Response (IVR) - One of the options EverBridge provides in the notification of ERO personnel. The system will provide a series of prompts for an individual to respond to via telephone. Once the responses are validated by EverBridge and the correct emergency notification scenario is provided, the notification will be transmitted as directed.
: 4. Live EverBridge Operator - One of the options EverBridge provides in the notification of ERO personnel. Using a telephone, site personnel will request an employee of EverBridge to activate the ERO. The EverBridge personnel will in turn request member I.D. and scenario information from the caller to initiate the notification process.
EMG-NGGC-0004                I          Rev. 3              1                Page 4 of 21
 
3.0 DEFINITIONS (continued)
: 5. Personnel Roster Excel Spreadsheet - Provides the data needed to create the ERO Notification System database within EverBridge. This data includes, but is not limited to Name, Telephone Number (s), Pager Number, ERO Team Designation, ERO Position, etc.
: 6. Polling - Set of pre-established questions, such as fitness for duty and response time, used for analysis when activating the ERO.
: 7. Pop-up window - Small window that will appear during the programming of the notification. The window will typically be used to confirm an action.
: 8. Scenario -A group of messages sent to the ERO to activate in an emergency.
: 9. Upload message - Program the EverBridge system to send a message.
4.0  RESPONSIBILITIES 4.1  Emergency Preparedness Staff
: 1. The Emergency Preparedness Staff is responsible for the maintenance and oversight of the Emergency Response Organization Notification System.
: 2. Pre-scripted messages will be developed and maintained by the Emergency Preparedness Staff to enable prompt notification of the Emergency Response Organization upon classification of an event.
4.2  Security and Operations Personnel Security and Operations personnel are primarily responsible for activation of the Emergency Response Organization Notification System.
5.0  PREREQUISITES None 6.0  PRECAUTIONS, LIMITATIONS AND NOTES
: 1. Security and Operations personnel should be notified each time the system is unavailable. Alternate methods to notify the ERO are in place at each site and will be initiated. Site procedures provide specific information on the actions to take if this should occur.
: 2. Changes to scenarios and messages may affect the performance of this system in the event of an emergency. Peer checks for changes such as these are recommended.
EMG-NGGC-0004                              Rev. 3                            Page 5 of 21
 
6.0  PRECAUTIONS, LIMITATIONS AND NOTES(continued)
: 3. Newly developed or significantly modified scenarios should be tested for operation prior to placing them in service. Use of these scenarios may begin immediately with procedure revision to follow in a timely manner.
* A procedure revision request should be initiated when a new scenario is created or a current scenario is modified.
: 4. The use of abbreviations should be avoided within the system. If this is not possible, use letters with the appropriate spacing. Abbreviations will be pronounced as a word if not input correctly. The words or letters will be pronounced as they are written.
: 5. Text boxes contain a limited amount of character spaces. There are approximately 40 in the Scenario Title and 31 in the Message Box.
: 6. Use the EverBridge menu items and tools to navigate within the website.
: 7. Use caution when making changes on any of the EverBridge screens.
Many of the screens do not ask for confirmation before changes are made. Use error reduction tools when adding or deleting information.
7.0  SPECIAL TOOLS AND EQUIPMENT None 8.0  ACCEPTANCE CRITERIA None 9.0    INSTRUCTIONS 9.1    Startup
: 1. LOG onto the Emergency Response Organization Notification System, EverBridge OR go to the internet and type "www.everbridge.net".                          0
: 2. ENTER your unique member ID and Password to access the system. 0 SNOTE:  References to Notifications and Messages may be interchangeable due to software application limitations 9.2    Creating Emergency or Drill Messages
: 1. SELECT "Send Notification... ...........................................................
: 2. SELECT "Send Notification" again, underneath "Send Notification".0....
: 3. SELECT "STANDARD MESSAGE" ................................................              0 IEMG-NGGC-0004                I            Rev. 3                  1                          Page 6 of 21
 
9.2 Creating Emergency or Drill Messages (continued)
: 4. SELECT "ADD" in the "message to be distributed to groups" or "message to be distributed to individuals" field ....................................                          0
: 5. CHOOSE a "Group Name" or "individual name" to send a message to. 0
: 6. SELECT "close window" once all selections have been made ...........
: 7. S E L EC T "N ext" ....................................................................................        E NOTE:    Textboxes contain a limited amount of character spaces
: 8. TYPE in the title of the message in the "Message Title" box ................. E
: 9. CHOOSE the desired option from the "Record message via:" field.
: a.      "Enter a text message". Proceed to Step 9.2.10 if choosing this optio n ...............................................................................        NA D El
: b.      "Telephone". See Enclosure 1 for instruction. Proceed to Step 9.2.11 once option is completed ....................................... NA 0] 0
: c.      "Upload message". See Enclosure 2 for instruction. Proceed to Step 9.2.11 once option is completed ..........................                                NA 0 0 CAUTION Use of abbreviations should be avoided whenever possible.
: 10. TYPE the appropriate text message in the "Type your message" field using m inim al abbreviations ..................................................................              I "1
: 11. S E L E C T "Next" ..........................................          ................................... . . E
: 12. SELECT "Create message to be scheduled later" on the "Schedule Message/Choose Delivery Methods" page ..........................................                              E"1
: 13. Under "Sender Identification", VERIFY the display shows your site's ERO notification email address and sender caller ID.......................                                    EJ
: a.      BNP: BNP EROEDpgnmail.com, 910-457-3000
: b.      HNP: HNP ERO(,paqnmail.com, 919-362-2447
: c.      RNP: RNP EROWpiqnmail.com, 843-857-1000
: d.      CR3: CR3 EROWpgnmail.com, 352-563-4987 NOTE:    Enclosure 3 contains information to determine which option is applicable for use.
: 14. CHANGE "message delivery options" as necessary .......................                                        0 EMG-NGGC-0004                    I                    Rev. 3                          1                        Page 7of21
 
9.2 Creating Emergency or Drill Messages (continued)
: 15. SELECT the message delivery devices based on the message attributes under "Delivery Methods". ................................................................
: 16. VERIFY email and fax number are correct under "broadcast results delivery method" and select checkboxes as necessary .......................                                              0
: 17. SELECT "Save Message" ....................................................................                              E 9.3  Create Scenario
: 1. SELECT "Scenario Manager" ..........................................................
: 2. SELECT "Create Scenario" ..............................................................
: 3. TYPE in a "scenario name" in the "add a scenario" field ......................                                          0l
: 4. S E L E C T "SA V E" ........................................                .......................................... E
: 5. S E L E C T "A D D" .........................................              ........................................... E
: 6. CHOOSE desired message from the "choose unscheduled messages" lis t . .......................................................................................................        E
: 7. SELECT "close window" once selection has been made .....................                                                0
: 8. S E L E C T "SA V E" ........................................                .......................................... E
: 9. SELECT "YES" from "pop-up" message ..............................................                                      E 9.4  Creating Polling Notifications
: 1. SELECT "Send Notification". ...........................................................                                E
: 2. SELECT "Polling Notification" ..............................................................                            E
: 3. SELECT "STANDARD POLLING MESSAGE" .....................                                                                  0l...
: 4. SELECT "ADD" in the "message to be distributed to groups" or "message to be distributed to individuals" field ....................................                                  E
: 5. CHOOSE "Group Names" or "individual names" from the "pop-up" list for the distribution of the message .............................................................                          E
: 6. SELECT "close window" once selections have been made .................. E
: 7. S E L E C T "NE XT" ..........................................                ........................................ E NOTE:    Text boxes contain a limited amount of character spaces.
: 8. TYPE the title of the message in the "Message Title" box ....................                                          E IEMG-NGGC-0004                            I                    Rev. 3                          1                          Page 8f21
 
9.4  Creating Polling Notifications (continued)
: 9. CHOOSE the desired option from the "Record message via:" field.
: a.      "Enter a text message". Proceed to Step 9.4.10 if choosing this o p tio n ...............................................................................        NA 0 0
: b.      "Telephone". See Enclosure 1 for instruction. Proceed to Step 9.4.11 once option is completed ..................................                                NA 0 0
: c.      "Upload message". Enclosure 2 for instruction. Proceed to Step 9.4.11 once option is completed ....................................... NA 0 0
: 10. TYPE the appropriate text message in the "Type your message" field. 0
: 11. S E L E C T "NE XT" ......................................            ............................................ 0
: 12. TYPE in the polling statements or questions requiring response .......... 0 NOTE:  Enclosure 3 contains information to determine which option is applicable for use.
: 13. If necessary, ENTER the "Data Input" and "Call Transfer" information needed for the poll as necessary using the check box and drop-down list on the "Create Polling Response" screen ..................................                                NA 0 0
: 14. S ELEC T "NEXT"..........................................                  .................................... 0
: 15. SELECT "Create message to be scheduled later" under "Schedule Message/Choose Delivery Methods" page ......................................                                        0
: 16. VERIFY the display shows your site's ERO notification email address and sender caller ID under "Sender Identification" .......................... 0
: a.      BNP: BNP ERO(Dpgnmail.com, 910-457-3000
: b.      HNP: HNP ERO(,paqnmail.com, 919-362-2447
: c.      RNP: RNP ERO(Wp-qnmail.com, 843-857-1000
: d.      CR3: CR3 ERO(a*,pnmail.com, 352-563-4987 NOTE:  Enclosure 3 contains information to determine which option is applicable for use.
: 17. CHANGE message delivery options as necessary ..........................                                            0
: 18. SELECT the message delivery devices based on the message attributes under "Delivery Methods". ...............................................................                          0
: 19. VERIFY fax number and email message are correct under "broadcast results delivery method" AND SELECT check boxes as necessary. ... 0
: 20. SELECT "Save Message" ................................................................                              0 EMG-NGGC-0004                                          Rev. 3                                                    Page 9 of 21
 
9.5  Scheduling Recurring Notifications
: 1. SELECT "Send Notification". ...........................................................                    0
: 2. SELECT "Send Notification" again, underneath "Send Notification".0....
: 3. SELECT "STANDARD MESSAGE" ................................................                                  0
: 4. SELECT "ADD" on the "message to be distributed to groups" or "message to be delivered to individuals" field .................................                            0
: 5. CHOOSE a "Group Name" or "individual name" to send a message to. 0
: 6. SELECT "close window" once all selections have been made ........... 0
: 7. S E LE C T "Next"........................................        ........................................ 0 NOTE:  Text boxes contain a limited amount of character spaces.
: 8. TYPE in the title of the message in the "Message Title" box ............. 0
: 9. CHOOSE the desired option from the "Record message via:" field.
: a.      "Enter a text message". Proceed to Step 9.5.10 if choosing this option .........................................................................            NA      0]
[]
: b.      "Telephone". See Enclosure 1 for instruction. Proceed to Step 9.5.11 once option is completed .......................................                      NA 0 0
: c.      "Upload message". See Enclosure 2 for instruction. Proceed to Step 9.5.11 once option is completed .............................. NA 0 0 CAUTION Use of abbreviations should be avoided whenever possible.
: 10. TYPE the appropriate text message in the "Type your message" field. 0
: 11. S E LE CT "NEX T" ..........................................        .................................. . .0
: 12. SELECT "Schedule Message" under "Schedule Message/Choose D elivery M ethod" page ..........................................................................          0]
: 13. CHOOSE the start date of the message ...............................................                        03
: 14. CHOOSE the start time of the message ...............................................                        03
: 15. SELECT the "-".. "send every" option and CHOOSE the time interval that you wish the message to be sent ..............................................                        0
: 16. CHOOSE ending date for message ..................................................                            0 I EMG-NGGC-0004                                    Rev. 3                        1                      Page 10 of21
 
9.5 Scheduling Recurring Notifications (Continued)
: 17. VERIFY the display shows your site's ERO notification email address and sender caller ID under "Sender Identification" ...........................              0
: a. BNP: BNP ERO(,pqPnmail.com, 910-457-3000
: b. HNP: HNP EROpqnmail.com, 919-362-2447
: c. RNP: RNP ERO-poqnmail.com, 843-857-1000
: d. CR3: CR3 ERO*,pqnmail.com, 352-563-4987 NOTE:  Enclosure 3 contains information to determine which option is applicable for use.
: 18. CHANGE message delivery options as necessary ...........................                    0
: 19. SELECT the message delivery devices based on the message attributes under "Delivery Methods". .............................................................. 0
: 20. VERIFY email and fax number are correct under "broadcast results delivery method" and select checkboxes as necessary ................... 0
: 21. SELECT "Schedule Message" .........................................................        0 IEMG-NGGC-0004                        Rev. 3                                                Page 11 of 21
 
NOTE: Use of the following steps to obtain a copy of the "Broadcast Results" from a LAN computer are optional.
9.6    Broadcast Report 9.6.1 Once the scenario has been broadcast using the LAN, you can access the Broadcast Results in three ways:
9.6.2 The direct method:                                                                                  NADQ
: 1. SELECT the "I.D." number (located on the left side) to display the "Broadcast Results" screen, once you have activated the scenario ...... 0
: 2. SCROLL to the bottom of the page to view the status as it unfolds. The status w ill be displayed as: ................................................................      0 confirmed            not confirmed                      unreachable
: 3. PRINT the report to determine the status of each member of the ERO as necessary by selecting "PRINT" located at the bottom of the screen... 0 9.6.3 The indirect method:                                                                                NAQ 0
: 1. ACCESS "Mange Broadcasts" on the left side of the page ................... 0]
: 2. ACCESS "Track Active Broadcasts........................"........................0
: 3. SELECT the "Active Broadcast:" I.D." number .................................. 0
: 4. SCROLL to the bottom of the page to view the status as it unfolds. The status will be displayed as: ................................................................... 01 confirmed            not confirmed                      unreachable
: 5. PRINT the report to determine the status of each member of the ERO as necessary by selecting "PRINT" located at the bottom of the screen... 0 9.6.4 The archived method:                                                                                  NA 0Q
: 1. ACCESS "Reports" on the left side of the page ................................ 0
: 2. ACCESS "Broadcast Report..............................".............................0
: 3. LOCATE the report by "I.D." number, Message Title, or "Start Date" from the dropdown list of pages listed in chronological order .................... 0
: 4. SELECT the appropriate "I.D." number .............................................                  0
: 5. PRINT the report as necessary by selecting "PRINT" located at the bottom of the screen .........................................................................      0 IEMG-NGGC-0004                  I            Rev. 3                        1                        Page 12 of21
 
9.7    Deleting Emergency Notification Scenarios
: 1. SELECT "Scenario Manager'. ........................................................      0
: 2. SELECT "Manage Scenario". ........................................................... 0
: 3. CHOOSE the Scenario you wish to delete ......................................... 0 4.
CAUTION The software will not display a prompt once "Delete Scenario" is selected.
SELECT "Delete Scenario" ..............................................................
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9.8  Deleting Unscheduled Messages
: 1. SELECT "Manage Broadcasts". .......................................................
: 2. SELECT "Manage Messages". .........................................................
: 3. SELECT "UNSCHEDULED MESSAGES" .......................                                                          El....
: 4. SELECT the "trash can" icon that corresponds with the message you wis h to d e le te ........................................................................................ E
: 5.      SELECT "OK" when asked "Are you sure you want to cancel this unscheduled broadcast?". ................................................................
NOTE:  You must be logged onto the system as an administrator to perform sub-sections 9.9 through 9.14.
9.9  Updating Individual Member Contact Information in Emergency Notification Software
: 1. SELECT "Members". ....................................................................... E
: 2. SELECT "Manage Members". ...........................................................
: 3. SEARCH for the individual by entering individual's first or last name in "first name" or "last name" field .............................................................              E
: 4. S E LE C T "Search" ......................................            ...................................... El
: 5. CHOOSE the individual name requiring contact info update ................                                    E
: 6. MAKE updates to profile information as appropriate ............................                              E
: 7. S E LEC T "S ave". ..............................................................................            E
: 8. UPDATE additional information as needed using the available options on the bottom of the screen ..................................................................                E
: 9. SAVE any changes made within the options ........................................                            E IEMG-NGGC-0004              _                        Rev. 3                                                    Page 14 of 21
 
9.10  Removing Individual Members in Emergency Notification Software
: 1. S E LECT "Mem bers". ........................................................................
: 2. SELECT "Manage Members... ........................................................                          0
: 3. SEARCH for the individual by entering individual's first or last name in "first nam e" or "last nam e" field ......................................................... 0
: 4. S E LEC T "Search"......................................            ...................................... 0
: 5. SELECT the "trash can" icon that corresponds with the member you wish to d e lete ..................................................................................      .. 0
: 6. SELECT "End Mem bership". ............................................................. 0
: 7. S E LE C T "O K". .................................................................................      . .0 9.11  Group Personnel Roster Additions/Changes NOTE:  This section will provide the basic information needed to update the Personnel Roster Excel Spreadsheet, which is maintained outside the EverBridge system. This database will be maintained and updated as necessary.                                                                                                      I
: 1. ADD the appropriate "Action" in the first column: .............................. 0
: a.      A - Add
: b.      U - Update
: c.      D - Delete
: d.      C - Replace Data Value
: e.      B - Add if not in system, update if in system (preferred)
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9.11 Group Personnel Roster Additions/Changes (continued)
CAUTION Partial entry is not allowed for personnel information.
NOTE:  Columns with the headings "User Attribute Field Name" and "User Attribute" are linked. If one of the fields is not known, then leave both columns empty.
: 2. ENSURE the last column contains "END" ........................................                            0
: 3. SAVE Personnel Roster Spreadsheet as a ".csv" file .......................                                0
: 4. Logon to EverBridge website ..........................................................                    0
: 5. SELECT "Mem bers". .......................................................................                0
: 6. SELECT "Add Mem bers". ................................................................. 0
: 7. SELECT "Upload List of Members". ................................................. 0
: 8. OPEN Browser AND SELECT the appropriate Personnel Roster Excel Spreadsheet file that was previously revised .................................... 0
: 9. S E LEC T "Upload" ......................................          ...................................... 0
: 10. IF any errors are identified, THEN RESOLVE the errors on the spreadsheet AND UPLOAD the file again by following Steps 9.11.4 through 9 .11.9 ............................................................................      NA D 0 9.12 Adding Groups and Members to the Groups
: 1. SELECT "Groups and Filters"..........................................................                    0
: 2. SELECT "Add G roups".....................................................................                0
: 3. ENTER "G roup nam e".......................................................................              0
: 4. S E LE C T "Save"...............................................................................          0
: 5. ADD members by SELECTING "Add"............................................. 0
: 6. SEARCH for individual by entering individual's first name or last name in "first nam e" or "last nam e" field . ..................................................... 0
: 7. S E LE C T "Search"..............................................................................
: 8. SEARCH for groups by selecting "Search Group" button ................. 0 EMG-NGGC-0004                                    Rev. 3                                                Page 16 of 21
 
9.12  Adding Groups and Members to the Groups(continued)
: 9. CHOOSE individual or group requiring addition to the members list.... 0
: 10. REPEAT Steps 9.12.6 through 9.12.9 for each individual or group need ing placem e nt...............................................................................                    E
: 11. SELECT "close window"...................................................................                                  0
: 12. S E LEC T "Save"..............................................................................                          0
: 13. SELECT "Yes" or "No" on the pop-up window to accept or decline requested individual or group name ......................................................                              E 9.13  Deleting Groups NOTE:  There is not a "save" option for this action.                                                                              I
: 1. SELECT "Groups and Filters"..........................................................
: 2. SELECT "Manage Groups"..............................................................                                      l
: 3. SELECT the appropriate "Group Name" by clicking the appropriate "".0
: 4. SELECT the Trashcan icon or "DELETE SELECTED" ........................                                                    E
: 5. SELECT "OK" on pop-up window to accept or decline requested group n a m e .....................................................................................................            E 9.14  Deleting Group Members
: 1. SELECT "Groups and Filters" ..............................................................                              E
: 2. SELECT "Manage Groups" ..................................................................                                E
: 3. SELECT the appropriate "Group Name" by clicking on the group name.
            ..............................................................................................................          0
: 4. SELECT "Individual" to be deleted from the "Members" field ................ 0
: 5. S E L E C T "R em ove" .......................................                  ....................................... E
: 6. S ELEC T "Save".......................................                      .......................................      E
: 7. SELECT "Yes" or "No" on pop-up window to accept or decline requested ind ivid u a l's na m e ................................................................................                  E 10.0  RECORDS No Records are generated by this procedure.
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ENCLOSURE 1 Page 1 of 1 EverBridge Options - Telephone
: 1. CLICK on the telephone button .......................................................                                0
: 2. FOLLOW instructions provided in the "pop-up" window to record a message.
        ..............................................................................................................        0
: 3. RETURN to the web application to continue creating the message by selecting "READY" ..........................................................................                        0 IEMG-NGGC-0004                                            Rev. 3                                                    Page 18 of 21
 
ENCLOSURE 2 Page 1 of 1 EverBridge Options - Upload Message
: 1. CLICK on the "Upload Message" button ...........................................                      0
: 2. CLICK on "Browse"..........................................................................            0
: 3. SELECT the appropriate .wav file from the "Choose file" window by double clicking on file nam e .........................................................................      0
: 4. SELECT "UPLOAD" ........................................................................              0 I EMG-NGGC-0004            I                Rev. 3                                                  Page 19 of 21
 
ENCLOSURE 3 Page 1 of 1 Message Delivery Options Definitions Confirm - By default the message will be delivered with confirmation required. Un-checking the confirm box delivers a message without request for confirmation to all selected contact paths and eliminates the 10-digit call back number from being displayed to recipient.
Escalate - Checking this box delivers a message with Escalation to additional members as defined in the chosen member's profile.
Broadcast Duration - Member can choose duration for the broadcast. Emergency broadcast defaults to 30 minutes, Standard broadcast defaults to two hours.
Contact Cycles - Select the number of times you would like the message to cycle through each delivery method. The message will cycle through all the delivery methods selected until the message has been confirmed, all the cycles have been exhausted, or when the duration time ends.
Interval Between Delivery Methods - Select the interval (up to three min) that you choose to occur between the chosen delivery methods.
Interval Between Cycles - Select the interval (up to one hr) that you choose to occur between contact cycles.
Require PIN to hear Message - Checking this option will require the member input PIN # to hear the message. (Note: The PIN # is defined by the organization leader at the member level. The option is viewable when turned on.)
Voice Mail Preference - Select: No Message, Message Only, or Message with Confirmation Info to be included with Voice Mail option.
Send Attachment(s) to - If attachments have been added to message, choose where you would like the attachments sent: E-mail and Fax, E-mail only, or Fax Only.
Delivery Methods - Select the message delivery methods for your broadcast. When a text message is created with no recorded voice, only the text path checkboxes will be checked. To convert your text to speech you must select the desired voice paths, when sending your notification you will be prompted to convert text to voice. (Note: A recorded message without any text will only display voice devices.)
Broadcast Results Delivery Method - Broadcast results can be delivered via E-mail and/or fax by checking the appropriate checkbox, entering the desired E-mail address, and/or Fax number. (You have the option to send the broadcast results to any E-mail and/or fax #. Note:
Broadcast results via fax will show a summary of the broadcast.)
Call Transfer - When a recipient chooses call transfer, the recipient is forwarded to another phone number that has been programmed into the polling response.
Data Input - This allows the recipient to respond with numeric only data to the questions that are being polled such as; phone #, date, time.
I EMG-NGGC-0004                            Rev. 3                          Page 20 of 21
 
Summary of Changes PRR 617154 SECTIONISTEP                          CHANGES 9.1.1    Removed program location description for WIN7 implementation. (Editorial)
I EMG-NGGC-0004                Rev. 3                        Page 21 of 21
 
Enclosure 2d EMG-NGGC-0004, Maintenance of the Emergency Response Organization, Revision 4
 
            *
*!Progress Eu.y R
Reference Use NUCLEAR GENERATION GROUP STANDARD PROCEDURE VOLUME 99 BOOK/PART 99 EMG-NGGC-0004 MAINTENANCE OF THE EMERGENCY RESPONSE ORGANIZATION NOTIFICATION SYSTEM REVISION 4
 
TABLE OF CONTENTS SECTION.                                                                                                                                                      PAGE 1.0-      *PURPOSE U1.0R. PO S E .................
                              ..... .... ..... .. .... ......  . . ...... ...........-..-..........
                                                                            .        ..            .      ...... ....... .. .... :........... *........ ,.......
                                                                                                          .        .        ..          .        .      .        4
 
==2.0        REFERENCES==
....................                                    .......            . ..........................                                      .4 2.1        Developm ental R eferences .........................................................................                                                4 2.2        Implementing References .............................                                                                                    ...        .4
*3 .0      D E F IN IT IO NS..............................                                .............        ... .............            .... .... ........... 4 4.0        RESPO NSIBILITIES .......                          ............................ .              ........................................          .... 5 4.1        Emergency Preparedness Staff ........................                                                                                                5 4.2        Security and Operations Personnel..............................                                                                                      5 5.0        PREREQUISITES ...........                                                . ...
                                                                                          ..................
                                                                                                    ...                          ...................                5
.6.0        PRECAUTIONSI LIMITATIONS AND NOTES.                                                                      ..............                  ....... 5... 5 7.0      SPECIAL TOOLS AND EQUIPMENT...                                                    .... ...      .....      ....................                          6 8.0      ACCEPTANCE CRITERIA ........                                        ....      ........................................... 6 9.0        INSTRUCTIONS......... ' ....................................                                                                                              7 9 .1      S ta rtu p . .........................................        .. . .................................. .. ........... ....................            7.
9.2,      Creating Emergency or Drill Messages .......... .........                                                  ....... ......................          7 9 .3      C reate S ce na rio ............................... ............... ......................................... . . .                                  9 9.4        Creating Polling Notifications*.....                                  ..                                              ... ...        ........... 9
* 9.5        Scheduling.Recurring Notifications*............................                                                                      ........ 11 9.6        Broadcast Report ......................................                                                                                            13 9.7        Deleting Emergency Notification Scenarios .....                                                                                    s                14 9.8        Deleting Unscheduled Messages                                                                                                                      15 9.9        Updating IndividualMember Contact Information in Emergency Notification
                  ....    ".......Software.....      ....                ..............................................                                              15.
9.10      Removing Individual Members in Emergency Notification Software ...........                                                                          16 9.11      Group Personnel Roster Additions/Changes .........                                                        . ........... ... .......                16.
9.12      Adding Groups and Members to the Groups...                                                                  ....................                  17 9.13      Deleting G roups ...                ...............        ............................................................                            18
      . 914      Deleting Group Members...                                        .........................                                                        18 10.0      RECORDS. ....................                                                p .........................                                              18 EMG-NGGC-0004""                                                            Rev. 4                                                            Page 2 Qf 22
 
TABLE OF CONTENTS SECTION                                                                                                    PAGE ENCLOSURES 1    EverBridge Options - Telephone ...........................................                    ... 18 2    EverBridge O ptions - Upload Message ........................................................      19 3    Message Delivery Options Definitions ............................                            . 20 Summary of Changes ...................................                                    .............. 21
.MG-NGGC-0004.                                        Rev. 4                              Page 3 of 22
 
1.0  PURPOSE This procedure provides instructions for performing routine updates, maintenance, and testing of the Emergency Response Organization Notification System.
2.0 -REFERENCES 2.1  Developmental References None 2.2  Implementing References
: 1. CSP-NGGC-2505, Software Quality Assurance and Configuration Control of Business Computer Systems
: 2.      EMG-NGGC-0005, Activation of the Emergency Response Organization Notification System.
: 3.      Emergency Response Organization Notification Procedures
* EM-206 (EM0206), [CR3] Emergency Plan Roster Notification
* PEP-310, [HNP] Notifications and Communications
* EPNOT-01, [RNP] CR/EOF Emergency Communicator
: 4. Site Emergency Plans
* OERP, (BNP) Radiological Emergency Response Plan
            '    RERP, [CR3] Radiological Emergency Response Plan.
* PLP-201, [HNP] Emergency Plan
            . PLP-007, [RNP] Robinson Emergency Plan 3.0  DEFINITIONS
: 1.      EverBridge - Company that hosts the software and website used for notification
: 2. Group    - Set Of defined'personnel to be notified'
: 3.      Interactive Voice Response (IVR) - One of the options EverBridge provides in the notification of ERO personnel. The system will provide a series of prompts for an individual to respond. to via telephone. Once the..
responses are validated by EverBridge and the correctemergency notification scenario is provided, the notification will be transmitted as directed.
: 4.      Live EverBridge Operator - One of the options EverBridge provides in the notification of ERO personnel. Using a telephone, site personnel' will request an employee of EverBridge to activate the ERO. The EverBridge personnelwill.in turn requestrmember l:D. and scenario information from the caler to initiate the notification process. -
EMG-NGGC-0004                            Rev. 4                              Page4 of 22
 
*3.0 DEFINITIONS (continued)
: 5. Personnel Roster Excel Spreadsheet - Provides the data needed to create the ERO Notification System database within EverBridge. This data includes, but is not limited to Name, Telephone Number (s), Pager Number, ERO Team Designation, ERO Position, etc.
: 6. Polling - Set of pre-established questions, such as fitness for duty and response time, used for analysis when activating the ERO.
: 7. Pop-up window - Small window that will appear during the programming of the notification. The window will typically be used to confirm an action.
: 8. Scenario -A group of messages sent to the ERO to activate in an emergency.
      .9. Upload message - Program the EverBridge system to send a message.
4.0    RESPONSIBILITIES 4.1    Emergency Preparedness Staff
: 1. The Emergency Preparedness Staff is responsible for the maintenance and oversight of the Emergency Response Organization Notification System.
: 2. Pre-scripted messages will be developed and maintained by the Emergency Preparedness Staff to enable prompt notification of the Emergency Response Organization upon classification of an event.
*4.2. Security and Operations Personnel.
Security and Operations personnel are primarily responsible for activation of the Emergency. Response Organization Notification System.
5;0  PREREQUISITES
      ..None S"6:0  PRECAUTIONS; LIMITATIONS AND NOTES 1    Security and Operations personnel should be notified each time the system is unavailable. Alternate methods to notify the ERO are in place at each site and will be initiated. Site procedures provide specific information on the actions to take if this should occur.
: 2. Changes to scenarios and messages may affect the performance of this system in the event of an emergency... Peer checks for changes such. as these are recommended...
EMG-NGGC-0004.                            Rev..4                            Page 5 of 22
 
6.0  PRECAUTIONS, LIMITATIONS and notes.0                PRECAUTIONS, LIMITATIONS AND NOTES 5(continued)
: 3. Newly developed or significantly modified scenarios should be tested for operation prior to.plac ing them in service. Use of these scenarios may begin immediately with procedure revision to follow in a timely manner.
* A procedure revision request should be initiated when a. new scenario is created-ora current scenario is modified.
: 4. The use of abbreviations should be avoided within the system. If this is not possible, use letters with the appropriate spacing. Abbreviations will be pronounced as a word if not input correctly. The words or letters will be pronounced as they are written.
      .5. Text.boxes con.tain.a limited.amount of character spaces.. There are approximately 40 in the Scenario Title and 31 in the Message Box.
: 6. Use the EverBridge menu items and tools to navigate within the website.
: 7. Use caution when making changes on any of the EverBridge screens.
Many of the screens do not ask for confirmation before changes are made. Use error reduction tools when adding or deleting information.
7.0    SPECIAL TOOLS AND EQUIPMENT
      ..None-8.0    ACCEPTANCE CRITERIA None 4                          Page6of22j Rev.
I.EMG NGGC-.0004 EMG-NGGC-0004              Rev. 4                          Page 6 of.22
 
9.0  INSTRUCTIONS 9.1  Startup
: 1. LOG onto the Emergency Response Organization Notification System, EverBridge using one of the following options:
            ,        Go to the internet and type "www.everbridge. net'".                                          *.*                  l
            *
* IF using a Windows XP Desktop, THEN SELECT Start>Programs>Emergency Preparedness >EverBridge .......... El
            *o      IF using a.Windows 7 Desktop, THEN SELECT Start>All Programs>DAE>Shortcuts Tab>Search EverBri.dge>Select EverBridge and Run Application ..............
: 2. ENTER your unique member ID and Password to access the system. E NOTE:    References to Notifications and Messages may be interchangeable due to software application limitations 9.2  Creating Emergency or Drill Messages
: 1. SELECT "Send Notification.". ...............................
: 2. SELECT "Send Notification" again, underneath "Send Notification".                                                        E
: 3. SELECT "STANDARD MESSAGE"...........................El
: 4. SELECT "ADD" in the "message to be distributed to groups" or "message to be distributed to individuals" field. ............................... El                                      0
:5. CHOOSE a "Group Name" or "individual name" to send a message to.E
    *6. SELECT "close window" once all selections have been made..........E
: 7. SELECT "Next".....                                ........................                                              E 7S . L C    N  x  .... ........................                .......    ..... ... ...... .........
                                                                                                        ,...      -..............
                                                                                                                              .. . . . 0 NOTE:    Textboxes contain a limited amount of character spaces
: 8. TYPE in the title of the message inthe "Message Title" box                                                  ....          El EMG-NGGC-0004                                              Rev. 4                                                Page 7 of 22
 
9.2    Creating Emergency or Drill Messages (continued)
: 9. CHOOSE the desired option from the "Record message via:" field.
              *      "Enter a text message". Proceed to Step 9.2.10 if choosing this option.      .....................................                                  NAD 0
              *.    "Telephone". See Enclosure 1 for instruction. Proceed to Step 9.2.11 once option is com pleted .......................................            NA El El "Upload message". See Enclosure 2 for instruction. Proceed to Step 9.2.1.1 once option is completed ..............                              NA El El CAUTION Use of abbreviations should be avoided whenever possible.
: 10. TYPE the appropriate text message in the "Type your message" field using minimal abbreviations ...............................
: 11. SELECT "Next"..............................                                                .......... E
: 12. SELECT."Create message to be scheduled later" on the "Schedule Message/Choose Delivery Methods" page                      .................................... El
: 13.    :Under "Sender Identification", VERIFY the display shows your site's ERO notification email address and sender caller ID ........                                    "
BNP: BNP ERO(pgqnmail.com, 910-457-3000 HNP: HNP ERO~a~pqnrmaiLcom, 919'362-2447 S    .RNP:. RNP. ERO(ppqnmail.com, 843-857-1000
* CR3: CR3 ERO(cpqnmail.com, 352-563-4987 NOTE:      Enclosure 3 contains informnation to determine which option is applicable for use.
    . 14. CHANGE "message delivery options" as necessary .................-............                        ]
: 15. SELECT the message delivery devices based on the message attributes Under "Delivery Methods"... ........................ ......      ................. ..........:.D..
    .16.      VERIFY email and fax number are correct under "broadcast results.
          . delivery method" and select checkboxes as necessary.                              ............
: 17. SELECT "Save Message"....*........                                                  ............
EMG-NGGC-0004.                                    Rev. 4.                                          Page 8 of 22
 
9.3  Create Scenario 1    SELECT "Scenario Manager".. .......................... .                            .      ......... E.
: 2. SELECT "Create Scenario" ...........................................................
: 3. TYPE in a "scenario name" in the "add a scenario" field .E.....................                                  l
: 4. S E LE C T "SAV E .................................................................................            El
: 5. S E LECT "A D D" .......        ......... ...........      .....                .      .    ............... El
: 6. CHOOSE desired message from the "choose unscheduled messages" list:                    .......................        ... ... .....................                        El
: 7. SELECT "close window" once selection has been made .....................                                        E
: 8. SELECT            ......        . .......      .....      ........... "          ..............            .El
: 9. SELECT "YES" from "pop-up" m essage .E.............................................                              l 9.4  Creating Polling Notifications
: 1. SELECT "Send Notification"... ................                                      ......................      l
: 2. SELECT "Polling Notification"..... .....                                .....................
: 3. SELECT "STANDARD POLLING MESSAGE"..                                                                            El
: 4. SELECT "ADD" in the "message to be distributed to groups" or "message to be distributed to individuals" field.                                                              E
: 5. CHOOSE "Group Names" or "individual names" from the "pop-up" list for the distribution of the m essage .E.........l....... .............                        . ...        ... . 0l....
: 6. SELECT "close window" once selections have been made                                              ...        El
: 7. SELECT"NEXT".........              ........ ......................
                                                                            .                                                l NOTE:*  Text boxes contain a limited amount of character spaces.
: 8. TYPE the title of the message in the "Message Title." box .                                                    E..............
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9.4  Creating Polling Notifications (continued.)
: 9. CHOOSE the desired option from the "Record message via:" field.
            *      "Enter a text message". Proceed to Step 9.4.10 if choosing this option.....................................                                              NADE
            *      "Telephone". See Enclosure 1 for instruction. Proceed to Step 9.4.11 once option is com pleted .....................                    .............. NA El El
            *      "Upload message". Enclosure 2 for instruction. Proceed to Step 9.4.11 once option is completed ..................                                        NA E. E
: 10. TYPE the appropriate text message in the "Type your message" field. E
: 11. SELECT"NEXT"..... ...................................                                                ..
: 12. TYPE in the polling statements or questions requiring response......
NOTE:    Enclosure 3 contains information to determine which option is applicable for use.
: 13. If necessary, ENTER .the "Data Input". and "Call Transfer" information needed for the poll as necessary using the check box and drop-down list on the "Create Polling Response" screen.. .................                                      NA El El
: 14. SELECT "NEXT" ...................              " ."  .............................. ........... El
: 15. SELECT "Create message to be scheduled later" under "Schedule Message/Choose Delivery. Methods".page. .....                      .....................:              El..........
16.. VERIFY the display shows your site's ERO notification email address and sender caller ID under "Sender Identification".......... ......
* BNP: ..BNP EROQ(hpqnmail.com, 910-457-3000
* HNP: HNP ERO(Dp~qnmaiI.com, 919-362-2447
* RNP: RNP ERO(a-pnmail.com, 843-857-1000
            . ':CR3:      CR3 ERO(apqnmailicom, 352-563-4987 NOTE:    Enclosure 3 contains information to determine which option is applicable. for use.
: 17. CHANGE message delivery options as necessary..............E
    .18. SELECT the message delivery devices based on the message attributes under "Delivery Methods"... ...............................                                            El
: 19. VERIFY fax number and email message are correct under "broadcast results delivery method" AND SELECT check boxes as necessary ... El
: 20. SELECT Save Message".................                              ...............                      l EMG-NGGC-0004                                        Rev. 4    "                                        Page. 0 of 22
 
9.5  Scheduling Recurring Notifications
: 1. SELECT "Send Notification".                                                        ............................ 0
: 2. SELECT "Send Notification" again, underneath "Send Notification"..... El
: 3. SELECT "STANDARD MESSAGE .......................................................                                  0
: 4. SELECT "ADD" on the "message to be distributed to groups" or "m essage to be delivered to individuals" field . .............................. ;....... 0
: 5. CHOOSE a "Group Name" or "individual name" to send a message to. E
: 6. SELECT. "close window" once all *selections have been made.......*
: 7. SELECT "Next".....................                                            ...................
NOTE:    Text boxes contain a limited amount of character spaces.
: 8. TYPE in the title of the message in the "Message.Title" box.......E.
: 9. CHOOSE the desired option from the "Record message via:" field.
                  * "Enter a text message". Proceed to Step 9.5.10 if choosing this o p tio n . ............................................ .................................. NA El El "Telephone". See Enclosure 1 for instruction. Proceed to Step 9.5.11 once option is completed ....................                                            NA E E
            *      "Upload message". See Enclosure 2 for instruction. Proceed to Step 9.5.11 once option is completed.. ...... ........                                  ...... NA E E CAUTION Use of abbreviations should be avoided whenever possible.
: 10. TYPE the appropriate text. message in the "Type your message" field. El 11:. SELECT"NEXT".........* ..                                    .  .......            ...              ...        E
: 12. SELECT "ScheduleMessage" under "Schedule Message/Choose.
Delivery Method" page .........................................................                                    l......
: 13. CHOOSE the start date of the message ....... ......................                                                l......
    .14. CHOOSE thestart time of the message ......................                                                    .. El...
115'  SELECT'the "0-" "Send every" option and CHOOSE the time interval that you wish the message to be sent ......................                                          .. ..... El....
: 16. CHOOSE ending date for message.......,..; .............                                                          El....
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9.5 Scheduling Recurring. Notifications (Continued).
: 17. VERIFY the display shows your site's ERO notification email address and sender caller ID under "Sender Identification".                                                "      l
* BNP: BNP ERO(pcqnmail.com, 910-457-3000
* HNP: HNP ERO(pgqnmaii.com, 919-362-2447
* RNP:. RNP ERO(ap.qnmail.com,..843-857-1.000
* CR3: CR3 ERO(opqnmail.com, 352-563-4987 NOTE:    Enclosure 3 contains information to determine which option is applicable for use.
: 18. CHANGE message delivery options as.necessary                                                          .. 0
: 19. SELECT the message delivery devices based on the message attributes under "Delivery Methods".      ........................        ........ .................... E
: 20. VERIFY email and fax number are correct under "broadcast results delivery method" and select .checkboxes as necessary. ..............                        'l 2 1. S E L E C T "S ched ule Message" ................    ................................................. El 7T
.EMG-NGGC-.0004                          'Rev. 4                                                      Page 12.0f
 
NOTE: Use of the following steps to obtain a copy of the "Broadcast Results" from a LAN computer are optional.
9.6    Broadcast Report 9.6.1  Once the scenario has been broadcast using the LAN, you can access the Broadcast Results. in three ways:
9.6.2 The direct method:                                                                              NAD [
        .1. SELECT the "I.D." number (located on the left side) to display the "Broadcast Results" screen, once you have activated the scenario ...... E
: 2.      SCROLL to the bottom of the page to view the status as it unfolds. The status will be displayed as: ...............................
confirmed              not confirmed                      unreachable
: 3.      PRINT the report to determine the status of each member of the ERO as necessary by selecting "PRINT" located at the bottom of the screen... E' 9.6.3 The indirect method:                                                                            NAQ O
      .1..      ACCESS "Mange Broadcasts" on the left side of the page .........."..]
: 2.      ACCESS "Track Active Broadcasts."...............................E..
                                                                  .................                                l
: 3.      SELECT the "Active Broadcast:" I.D.' number...................
: 4.      SCROLL to the bottom of the page to.view the status as it unfolds. The status will be displayed as- ..................................                              .
confirmed              not confirmed                      unreachable.
: 5.      PRINT the report to determine the status of each member of the ERO as.
necessary by-selecting "PRINT" located at.the bottom of the screen.... E 9.6.4 The archived method:                                                                            NA          -.
: 1.      ACCESS "Reports" on the left side of the.page .................                                  0
: 2.      ACCESS "Broadcast Report "..................
                                                  ...............                        .    ...........      E 31      LOCATE the report by "I.D." number, Message Title, or "Start Date" from the dropdown list of pages listed in chronological order.....                          ....... E
: 4.      SELECT the'appropriate "'.D."number ..........                          ..............          El. .
: 5.      PRINT the report as necessary by selecting "PRINT" located at the bottom of the screen. .............................                                      .......
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9.7  Deleting Emergency Notification Scenarios
: 1. SELECT "Scenario Manager".................                                            . El
: 2. S ELECT "Manage Scenario". ........................................................... l
: 3. CHOOSE the Scenario you wish to delete........................................... E CAUTION The software will not display a prompt once "Delete Scenario" is selected.
: 4. SELECT "Delete Scenario"............      ..............  .................
IE
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.9.8  Deleting Unscheduled Messages
: 1. SELECT "Manage Broadcasts..............................                                            E
: 2.      S ELEC T "Manage Messages". ...............................................................        E
: 3.      SELECT "UNSCHEDULED MESSAGES". ..........................................                          El 4;      SELECT the "trash can" icon that corresponds with the message you wish to delete.........................................
: 5.      SELECT "OK" when asked "Are you sure you want to cancel this unscheduled broadcast?" ........................                                                    l........
                                                                                                                          .
NOTE:    You must be logged onto the system as an administrator to perform sub-sections 9.9 through 9.14.
9.9  Updating Individual Member Contact Information in Emergency Notification Software.
: 1. SELECT "Members".....................................l....
: 2. SELECT "Manage Members". ..............................                                              l
: 3. SEARCH for the individual by entering individual's first or last name in "first name" or "last name" field..............................
: 4.      SELECT "Search"......................................                                    .          l
: 5. CHOOSE the individual name requiring contact info update. .........                                E......
: 6.      MAKE updates to profile information as appropriate.                                                E
: 7. S ELECT '"Save...          .    .... ..............    ..... ..... ...................          E
: 8. UPDATE additional information as needed using the available options on the.bottom of the screen.                            ...............................            El
: 9.    :SAVE any changes made within the options .......... ..............................
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9.10 Removing Individual Members in Emergency Notification Software
: 1. SELECT "Members".                                                      .0
: 2. SELECT "Manage Mem bers .... .......................                        ..............................
: 3. SEARCH for the individual by entering individual's first or last name in "first nam e" or "last nam e" field.. ............. ;....... ...........                                          C............................
0
: 4. SELECT "Search"......                    ...................................................
I                                                            .......
: 5. SELECT the "trash can" icon that corresponds with the member you w is h to d e le te ....................    ................ ......... .......................................... 0
: 6. SELECT "End Membership"                                      ...............................                      E
: 7. SELECT "OK" .......................                                                                                0 9.11 Group Personnel Roster AdditionslChanges NOTE:  This section will provide the basic information needed to update the Personnel Roster Excel Spreadsheet, which is maintained outside the EverBridge system. This database will be maintained and updated as necessary.
: 1. ADD the appropriate "Action" in the first column: .............                                                    0 S      A -"Add S      U - Update
            . D-Delete
* C - Replace Data Value
* B  -  Add if not in system, update if in system (preferred)
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9.11 Group Personnel Roster Additions/Changes (continued)
CAUTION                                .
Partial entry is not allowed for personnel information.
NOTE:  Columns with the headings "User Attribute Field Name" and "User Attribute" are linked. If one of the fields is not known, then leave both columns empty.
: 2. ENSURE the last column contains "END".........................................                                E
: 3. SAVE Personnel Roster Spreadsheet as a ".csv" file. ..
: 4. Logon to EverBridge website.. ...............................                                              .
: 5. S E L E C T "Me m be rs" ............................................................................        E
: 6. SELECT "Add Members" ...                                          ....    ..........          .      . .... El
: 7. SELECT "Upload List of Mem bers"'.. ....................................................                      0
: 8. OPEN Browser AND SELECT the appropriate Personnel Roster Excel Spreadsheet file that was previously revised.                                                                  El
: 9. SELECT "Upload            ...................................................
: 10. IF any errors are identified, THEN RESOLVE the errors on the spreadsheet AND UPLOAD the file again by following Steps 9.11.4 through 9.11.9.        ....................................                                          NAO El 9.12 Adding Groups and Members to the. Groups 1.. SELECT '.'Groups and Filters" ....                                        "..........................l.....
: 2. SELECT "Add Groups" ........                                                ........    ,.....      ..... El..
: 3. E NT E R "G roup- nam e .....................................        ...................................... E
: 4. SELECT "Save"...          ...........                          ..                                            El...........
1-
: 5. ADD members by SELECTING "Add"..................................................                              E
: 6. SEARCH for individual by entering individual's first name or last name in "first nam e" or "last nam e" field. ...................                          .......................        l........
El.
: 7. S E LEC T "Search ...............................................................................              El
: 8. SEARCH for groups by selecting "Search Group" button.. ....... ........                                        E.
EMG-NGGC-0004                                    Rev. 4                                                  Page 17of 22
 
9.12  Adding Groups and Members to the Groups(continued)
: 9. CHOOSE individual or group requiring addition to the members list, .
: 10. REPEAT Steps 9.12.6 through 9.12.9 for each individual or group needing placement.                                    ............                        ......
                                                                                                            ..........
: 11. SELECT 'close window". ....... s
: 12. SELECT "Save".......................................                                                                  E
: 13. SELECT "Yes" or "No" on the pop-up window to accept or decline requested individual or group name ..........................                                                        .
913  Deleting Groups NOTE:    There is not a "save" option for this action.
: 1. SELECT "Groups and Filters"                                          ..............................
: 2. SELECT "Manage Groups"                            ..      ..................                      .............
: 3. SELECT the appropriate "Group Name" by clicking the appropriate *
: 4. SELECT the Trashcan icon or "DELETE SELECTED ........................                                                  0
: 5. SELECT "OK" on pop-up window to accept or decline requested group name.............................................................El
*.9.14  Deleting Group Members
: 1. SELECT "Groups and. Filters"...............                                .        ...        ................... D ..
2.. SELECT "Manage Groups".. .............................................
: 3. SELECT the appropriate "Group Name" by clicking on the group name.
: 4. SELECT "Individual"' to be deleted from the:"Members". field                                                "          E'l"..". -
: 5. SELECT "Remove"........................................l...
: 6. SELECT "Save"                    ...............................                                    ............ 0
: 7. SELECT "Yes" or "No" on pop-up window to accept or decline requested individu al's n a m e .. ..................... ............        .......................          ....... ......... El 10.0  RECORDS No Records are generated by this procedure.
EMG.-NGGC-0004.                                          Rev. 4                                                    Page.1.8 of
 
ENCLOSURE 1 Page 1 of 1 EverBridge Options - Telephone 1  CLICK on the telephone button............................                                                                                    D
: 2. FOLLOW instructions provided in the "pop-up" window to record a message.
        .. ..... .. .... ... .... ... .. .. .... ... ... .....  ...... ...... ... .... ... .. ..... 7.......................................
: 3. RETURN to the web application to continuecreating the message by se lecting "R E A D Y" .............I ............... .... .............................. ...... . .C EMG-NGGC-0004                                                  ..Rev. 4                                                                      Page 19 of 22
 
ENCLOSURE 2 Page 1 of 1 EverBridge Options - Upload Message
: 1. CLICK on the "Upload Message" button                                        ......            .          E.........
: 2. C L IC K o n "B ro wse".........................................      ....................................  -
: 3. SELECT the appropriate .wav file from the "Choose file" window by double clicking on file name..............                                  ......................
: 4. S E L E C T "UP LO A D".......................        ........... ..................................... 0 EMG-N.G.GC-0004                                .Rev. 4                                  GG OR.Page 20 of 22
 
ENCLOSURE 3 Page .1 of 1 Message. Delivery Options Definitions..          .. .  .    ......
Confirm - By default the message will be delivered with confirmation required. Un-checking the confirm box delivers a message without request for confirmation to all selected contact paths and eliminates the 10-digit call back number from being displayed to recipient.
Escalate - Checking this box delivers a message with Escalation to additional members as defined in the chosen member's profile.
Broadcast Duration - Member can.choose duration for the broadcast. Emergency broadcast defaults to 30 minutes, Standard broadcast defaults to two hours.
Contact Cycles - Select the number of times you would like the message to cycle through each delivery method. The message will cycle through all the delivery methods selected until the message has been confirmed, all the cycles have been exhausted,. or when the duration time ends.
Interval Between Delivery Methods - Select the interval (up to three min) that you choose
  .to occur between the chosen delivery methods.
Interval Between Cycles - Select the interval (up to one hr) that you choose to occur between contact cycles.
Require PIN to hear Message - Checking this option will require the member input PIN # to hear the message. (Note*: The PIN # is defined by the organization leader at the member level.. The option is viewable when turned on.)..
Voice Mail Preference - Select: No Message, Message Only, or Message with Confirmation Info to be included with Voice Mail option.
.Send Attachment(s) to - If attachments have. been added to. message, choose where you would like the attachments sent: E-mail and Fax, E-mail only, or Fax Only.
Delivery Methods - Select the message delivery methods for your broadcast. When a text message is created with no recorded voice, only the text path checkboxes will be checked. To convert.your text to speech you must select the desired voice paths, when sending your notification you will be prompted to convert teext to voice. (Note: A recorded message witho0ut
. any text-will only display voice devices.)
Broadcast Results Delivery Method - Broadcast results can be delivered via E-mail and/or fax by checking the appropriate checkbox, entering the desired E-mail address., and/or. Fax number. (You have the option to send. the broadcastresults to any E-mail and/or fax #. Note:
Broadcast results.via fax will show a summary of the broadcast.)
Call Transfer - When a recipient chooses call transfer, the recipient.is forwarded to another phone number that has been programmed into the polling response.
Data Input - This allows the recipient to respond with numeric only data to the questions that are. being.po.lled. such as.;. phone.#, date,.time.
EMG-NGGC-0004          "                    Rev. 4                      ..Page 21 of 22
 
Summary of Changes EMG-NGGC-0004 Rev. 3 PRR 617154 SECTION/STEP                          CHANGES 9.1.1    Removed program location description for WIN7 implementation. (Editorial)
EMG-NGGC-0004 Rev. 4 PRR 615736, CR 619320 SECTION/STEP                          CHANGES 9.1.1    Added removed EverBridge program instructions from previous revision and added location description for Windows 7 Desktop for WIN7 implementation. (Editorial)
EMG-NGGC-0004                Rev. 4                          Page 22 of 22,
 
Enclosure 2e EMG-NGGC-0005, Activation of the Emergency Response Organization Notification System, Revision 3
 
R
    *.Progress Energy                          Reference Use NUCLEAR GENERATION GROUP STANDARD PROCEDURE VOLUME 99 BOOK/PART 99 EMG-NGGC-0005 ACTIVATION OF THE EMERGENCY RESPONSE ORGA NIZA TION NO TIFICA TION SYSTEM REVISION 3 I EMG-NGGC-0005                Rev. 3          Page 1 of 27 1
 
TABLE OF CONTENTS Section                                                                                                                Page 1.0    PURPOSE ....................................................................................................        3
 
==2.0    REFERENCES==
.................................................................................................        3 3.0    RESPONSIBILITIES ........................................................................................            4 4.0    DEFINITIONS ...................................................................................................      5 5.0    PREREQUISITES ............................................................................................          5 6.0    PRECAUTIONS AND LIMITATIONS ..............................................................                          6 7.0    SPECIAL TOOLS AND EQUIPMENT ...............................................................                          6 8.0    ACCEPTANCE CRITERIA ................................................................................                6 9.0    INSTRUCTIONS ...............................................................................................        7 10.0  RECORDS .....................................................................................................        7 11.0 ATTACHMENTS ..............................................................................................            7
: 1. BNP Emergency Notification Scenarios .....................................................                        8
: 2. CR3 Emergency Notification Scenarios ...................................................                        10
: 3. HNP Emergency Notification Scenarios ....................................................                        13
: 4. RNP Emergency Notification Scenarios ....................................................                        18
: 5. Using a LAN Computer to Activate the ERO .............................................                          24
: 6. Using the EverBridge Interactive Voice Response to Activate the ERO .......                                      25
: 7. Using the Live EverBridge Operator to Activate the ERO .........................                                26 REVISION
 
==SUMMARY==
...............................................................................................          27 I EMG-NGGC-0005                                      Rev. 3                                                    Page 2 of 27
 
1.0    PURPOSE This procedure provides guidance for activating the Emergency Response Organization Notification System for the Nuclear Generation Group. The Emergency Notification System will be used to notify the Emergency Response Organization during an emergency, drill, exercise, or test.
 
==2.0    REFERENCES==
 
2.1    EMG-NGGC-0004, Maintenance of the Emergency Response Organization Notification System 2.2    EMG-NGGC-1 000, Fleet Conduct of Emergency Preparedness 2.3    EPNOT-01, [RNP] CR/EOF Emergency Communicator 2.4    EPPRO-02, [RNP] Maintenance and Testing 2.5    PEP-310, [HNP] Notifications and Communications 2.6    EPM-410, [HNP] Communication and Facility Performance Test 2.7    EM-206,(EM0206) (CR3] Emergency Plan Roster Notification 2.8    OPEP-02.6.21, [BNP] Emergency Communicator 2.9    OPEP-03.1.3, [BNP] Use of Communication Equipment 2.10  OPEP-02.1.1, [BNP] Emergency Control - Notification of Unusual Event, Alert, Site Area Emergency, and General Emergency 2.11  [RI] NOCS 100521, Emergency Preparedness On-Site and Off-site communications 2.12  [R2] NOCS 100533, Automated Dialing Capability for Fire Brigade Responders I EMG-NGGC-0005                          Rev. 3                          Page 3 of 27
 
3.0    RESPONSIBILITIES 3.1    The Site Emergency Coordinator (SEC) is responsible for determining:
3.1.1    When the Emergency Response Organization (ERO) is to be notified, 3.1.2    Which facilities are to be activated, unless decision is made by EOF Director.
3.1.3    The preferred methods of notification:
: 1.      LAN/Computer
: 2.      Interactive Voice Response (IVR)
: 3.      Live EverBridge Operator 3.2    The emergency notification scenario title and number to be provided as part of the notification.
3.3    Security is responsible for activating the ERO Notification System as directed by the SEC, unless the event is related to a security condition.
3.3.1 If security is unable to activate the ERO Notification System due to the nature of the event, responsibility of activation shall be returned to Operations.
3.4    In the event of a security condition, Operations will perform the necessary ERO notifications.
3.5    The Emergency Preparedness staff is responsible for:
3.5.1    Interface with the vendor(s) providing the notification service.
3.5.2    Maintaining the Emergency Response Organization contact information.
3.5.3    Maintaining the scenario and message contents.
I EMG-NGGC-0005                              Rev. 3                              Page 4of27
 
4.0    DEFINITIONS 4.1  Aware - Notification software application used by EverBridge.
4.2  EverBridge - Company that hosts the software and website used for notification.
4.3  Group - Set of defined personnel to be notified.
4.4  Interactive Voice Response (IVR) - One of the options EverBridge provides in the notification of ERO personnel. The system will provide a series of prompts for an individual to respond to via telephone. Once the responses are validated by EverBridge and the correct emergency notification scenario is provided, the notification will be transmitted as directed.
4.5  Live EverBridge Operator - One of the options EverBridge provides in the notification of ERO personnel. Using a telephone, site personnel will request an employee of EverBridge to activate the ERO. The EverBridge personnel will in turn request member I.D. and scenario information from the caller to initiate the notification process.
4.6  Password Card - Document which contains the site specific member I.D.'s and passwords required to activate the ERO using the EverBridge notification system.
4.7  Scenario - collection of message combinations used to notify ERO. A group of messages sent to the ERO to activate in an emergency.
4.8  Site Emergency Coordinator (SEC) - used as a generic term to represent the ERO position acting as the emergency coordinator for the site.
5.0    PREREQUISITES 5.1  An emergency event requiring activation of the ERO.
5.2  A drill, exercise, or test is being conducted which involves notification of the ERO.
I EMG-NGGC-0005                              Rev. 3                            Page 5o27
 
6.0      PRECAUTIONS AND LIMITATIONS 6.1    The Emergency Response Organization Notification System (EverBridge) uses pre-programmed messages to contact pre-established ERO personnel groups. These messages cannot be modified without the permission of the site Emergency Preparedness organization.
6.2    EverBridge is the preferred method of ERO notification. If this system is unavailable, site specific procedures and equipment should be used to provide notification. A list of these procedures is provided in the Reference Section (Section 2.0).
6.3    A LAN or wireless internet connection is required only if notification is made via the EverBridge website. It is NOT needed if IVR or a Live EverBridge Operator is used.
6.4    If notification occurs using a Live EverBridge Operator, the operator will ask a series of questions concerning the notification. These questions may vary from the script provided in Attachment 7. However, the intent and the critical responses will remain consistent.
6.5    Passwords will NOT be provided in this procedure to ensure the information cannot be accessed inappropriately. Instead, passwords are located on password cards provided to responsible personnel.
6.6    The  SEC should indicate the preferred method of notification. The options are:
                "  LAN Computer Activation
                "  EverBridge Interactive Voice Response (IVR) Telephone Activation
                "  Live EverBridge Operator Telephone Activation 6.7    Acronyms and abbreviations will be spoken as words by the IVR. Listen closely to ensure the correct option is selected.
7.0    SPECIAL TOOLS AND EQUIPMENT N/A 8.0    ACCEPTANCE CRITERIA N/A IEMG-NGGC-0005                    I          Rev. 3            1                Page 6 of 27 1
 
9.0    INSTRUCTIONS 9.1    Use of the EverBridge Notification System CAUTION The Scenario Title must correspond to the Scenario Number Provided by the SEC, otherwise the incorrect notification will be activated.
9.2    The SEC will direct activation of the ERO using the Emergency Response Organization Notification System. The Scenario number and preferred method for notification will be provided. Scenario numbers are identified in the following attachments.
* Attachment 1 -  BNP
* Attachment 2 -  CR3
* Attachment 3-  HNP
* Attachment 4-  RNP 9.3    IF the system is locked, THEN INITIATE system using alternate notification methods described in this procedure (LAN/Computer, Interactive Voice Response, or Live Operator) or immediately transition to back up ERO notification methods.
9.4    REFER to Attachment 5, to activate the ERO using a LAN computer.
9.5    REFER to Attachment 6, to activate the ERO using the EverBridge Interactive Voice Response (IVR) method.
9.6    REFER to Attachment 7, to activate the ERO using a Live EverBridge Operator.
10.0    RECORDS Documents generated by this procedure are NOT required to be retained.
11.0  ATTACHMENTS
: 1. BNP Emergency Notification Scenarios
: 2. CR3 Emergency Notification Scenarios
: 3. HNP Emergency Notification Scenarios
: 4. RNP Emergency Notification Scenarios
: 5. Using a LAN Computer to Activate the ERO
: 6. Using the EverBridge Interactive Voice Response to Activate the ERO
: 7.      Using the Live EverBridge Operator to Activate the ERO IEMG-NGGC-0005                  I            Rev. 3                        Page 7 of 27
 
ATTACHMENT 1 Sheet 1 of 2 BNP Emergency Notification Scenarios EMERGENCY CONDITIONS SCENARIO TITLE                SCENARIO NUMBER APPLICABILITY Unusual Event 1 U E Standby                                          31      EMERGENCY Unusual Event 2 U E Activate All. No JIC                              44      EMERGENCY Unusual Event 3 U E Activate All Facilities                          24      EMERGENCY Alert 4 Alert Activate All Facilities. No JIC                34      EMERGENCY Alert 5 Alert Activate All Facilities                        33      EMERGENCY Site Area Emergency 6 Site Area Emergency Activate All                      35      EMERGENCY General Emergency 7 General Emergency Activate All                        36      EMERGENCY Security Event 8 Security Event Activate A E F and J I C              43      EMERGENCY If wrong scenario 9 Notification Error                                    46      was sent Activate the Joint Information 10 Activate JIC                                          50      Center (JIC) Only EMG-NGGC-0005                              Rev. 3                    Page 8 of 27
 
ATTACHMENT 1 Sheet 2 of 2 BNP Emergency Notification Scenarios Drill Conditions & Information SCENARIO TITLE                  SCENARIO NUMBER        APPLICABILITY 9.0 Drill U E Standby                                  32    Drill 9.1 Drill U E Activate All. No JIC                      4    Drill 9.2 Drill U E Activate All Facilities                  23    Drill 9.3 Drill Alert Activate All Facilities                37    Drill 9.4 Drill Alert Activate All. No JIC                  38    Drill 9.5 Drill S A E Activate All Facilities                39    Drill 9.6 Drill G E Activate All Facilities                  40    Drill 9.7 Drill Security Event Act A E F and JIC                                                    6    Drill 9.8 Threat Level Increase (Orange)                      8    Information 9.9 Threat Level Increase (Red)                        42    Information Forced Outage                                          30    Information Post Storm Staffing                                    20    Information Test                                                  41    Information ERO Notification Drill 2                              52    Drill Ifwrong scenario was Notification Error                                    46    sent Drill Activate JIC                                    49    Drill Drill Alert Activate All No JIC 01                    51    Drill I EMG-NGGC-0005                          Rev. 3                    Page 9 of 27
 
ATTACHMENT 2 Sheet 1 of 3 CR3 Emergency Notification Scenarios
[RI] [R2]
SCENARIO NO.        SCENARIO TITLE                              APPLICABILITY Notification Error                  Retraction of any activation message sent
: 1.                                        in error Unusual Event    - ERO              Unusual Event declared.        Notify ERO to
: 2. Standby                            assume a heightened state of awareness in anticipation of emergency escalation.
Discretionary - TSC/OSC            At the discretion of the Emergency Coordinator, activate the following facilities:
3.
* Technical Support Center
* Operational Support Center Discretionary -                    At the discretion of the Emergency TSC/OSC/EOF/ENC                    Coordinator, activate the following facilities:
: 4.                                        a      Technical Support Center
* Operational Support Center
* Emergency Operations Facility
* Emergency News Center Alert                              Alert declared. Activate the following facilities:
(Refer to Scenario 8 if
: 5. activation of remote facilities    0      Technical Support Center is required.)                      0      Operational Support Center
* Emergency Operations Facility
* Emergency News Center I EMG-NGGC-0005            I            Rev. 3              1              Page 10of27
 
ATTACHMENT 2 Sheet 2 of 3 CR3 Emergency Notification Scenarios SCENARIO NO.        SCENARIO TITLE            [                APPLICABILITY Site Area Emergency                Site Area Emergency declared. Activate the following facilities:
(Refer to Scenario 9 if
: 6. activation of remote facilities    0      Technical Support Center is required.)                      0      Operational Support Center
* Emergency Operations Facility
* Emergency News Center General Emergency                  General Emergency declared. Activate the following facilities:
(Refer to Scenario 10 if
: 7.      activation of remote facilities
* Technical Support Center is required.)                      9      Operational Support Center
* Emergency Operations Facility I      Emergency News Center Alert (Remote Facilities)          Alert declared. Activate the following facilities:
: 8.
* Remote Technical Support Center
* Remote Operational Support Center
* Emergency Operations Facility
* Emergency News Center Site Area Emergency                Site Area Emergency declared. Activate (Remote Facilities)                the following facilities:
: 9.                                        0      Remote Technical Support Center
* Remote Operational Support Center
* Emergency Operations Facility
* Emergency News Center IEMG-NGGC-0005            I              Rev. 3                          Page 11 of 271
 
ATTACHMENT 2 Sheet 3 of 3 CR3 Emergency Notification Scenarios SCENARIO NO.        SCENARIO TITLE                          APPLICABILITY General Emergency              General Emergency declared. Activate the following facilities:
(Remote Facilities)
: 10.
* Remote Technical Support Center
* Remote Operational Support Center
* Emergency Operations Facility
* Emergency News Center Fire Brigade Support to SAB    Event requiring off-shift Fire Brigade
: 11.                                      support to report to the Site Admin Building.
(Example: Large-area fire)
Fire Brigade Support to EOF    Event requiring off-shift Fire Brigade support to report to the Emergency
: 12.                                      Operations Facility. (Example: Large-area fire)
Event Termination              Plant conditions no longer require ERO to
: 13.                                      stand by or to report as determined by Emergency Coordinator or EOF Director.
IEMG-NGGC-0005            I          Rev. 3                            Page 12 of 27
 
ATTACHMENT 3 Sheet 1 of 5 HNP Emergency Notification Scenarios NON-SECURITY EVENTS SCENARIO NO.              SCENARIO TITLE              APPLICABILITY            EXAMPLE UNUSUAL EVENT - Notification        EMERGENCY / ALL 20      Only                                      CALL                Unusual Event UNUSUAL EVENT - Pre Staffing        EMERGENCY / ALL 21      Facilities                                CALL                Unusual Event EMERGENCY / ALL 22    ALERT                                      CALL                    Alert EMERGENCY / ALL 23    SITE AREA EMERGENCY                        CALL            Site Area Emergency EMERGENCY / ALL 24    GENERAL EMERGENCY                          CALL            General Emergency Event Termination I All 25      EVENT TERMINATION                          Call                Any Event I EMG-NGGC-0005                      Rev. 3            1            Page 13 of 27
 
ATTACHMENT 3 Sheet 2 of 5 HNP Emergency Notification Scenarios SECURITY EVENTS SCENARIO NO.              SCENARIO TITLE              APPLICABILITY            EXAMPLE SEC UNUSUAL EVENT -                Security Emergency /
30    Notification Only                        All Call            Unusual Event SEC UNUSUAL EVENT - Pre            Security Emergency /
31      Staffing Facilities                      All Call            Unusual Event Security Emergency /
32      SEC ALERT                                All Call                Alert Security Emergency /
33      SEC SITE AREA EMERGENCY                  All Call        Site Area Emergency Security Emergency /
34      SEC GENERAL EMERGENCY                    All Call        General Emergency Security Event 35      SEC EVENT TERMINATION              Termination / All Call      Any Event I EMG-NGGC-0005                    Rev. 3                          Page 14 of 27
 
ATTACHMENT 3 Sheet 3 of 5 HNP Emergency Notification Scenarios Drill - Non Security Events SCENARIO NO.                SCENARIO TITLE                APPLICABILITY              EXAMPLE Drill - UNUSUAL EVENT  -
40      Notification Only                          Drill / All Call      Unusual Event Drill - UNUSUAL EVENT - Pre 41      Staffing Facilities                        Drill / All Call      Unusual Event 42      Drill - ALERT                              Drill / All Call          Alert 43      Drill - SITE AREA EMERGENCY                Drill / All Call  Site Area Emergency 44      Drill - GENERAL EMERGENCY                  Drill / All Call  General Emergency Drill Event Termination /
45      Drill - EVENT TERMINATION                      All Call            Any Event I EMG-NGGC-0005                        Rev. 3                          Page 15 of 27
 
ATTACHMENT 3 Sheet 4 of 5 HNP Emergency Notification Scenarios Drill - Security Events SCENARIO NO.              SCENARIO TITLE                    APPLICABILITY            EXAMPLE Drill Security Emergency 50    SEC Drill - UE - Notification Only              / All Call          Unusual Event SEC Drill - UE - Pre Staffing          Drill Security Emergency 51    Facilities                                      / All Call          Unusual Event Drill Security Emergency 52    SEC Drill - ALERT                                / All Call              Alert SEC Drill - SITE AREA                  Drill Security Emergency 53    EMERGENCY                                        / All Call      Site Area Emergency Drill Security Emergency 54    SEC Drill - GENERAL EMERGENCY                    / All Call      General Emergency Drill Security Emergency 55    SEC Drill - EVENT TERMINATION                    / All Call            Any Event IEMG-NGGC-0005              I            Rev. 3              1        Page 16 of 27
 
ATTACHMENT 3 Sheet 5 of 5 HNP Emergency Notification Scenarios Administrative and Testing SCENARIO NO.              SCENARIO TITLE                    APPLICABILITY          EXAMPLE Testing of EverBridge Notification          System Testing /
60    System                                    Selective Individuals      Testing Emergency Response Facility              Response Staffing / All 61    Staffing                                          Call            ERF Staffing System Testing /
62    Security EverBridge Training Exercise    Selective Individuals      Testing IEMG-NGGC-0005              I            Rev. 3              1        Page 17 of 27
* ATTACHMENT 4 Sheet 1 of 6 RNP Emergency Notification Scenarios EMERGENCY CONDITIONS SCENARIO NO.            SCENARIO TITLE              APPLICABILITY  EXAMPLE UNUSUAL EVENT -                  EMERGENCY I ALL I      ACTIVATION * (ALL CALL)                  CALL    Unusual Event UNUSUAL EVENT - NO                EMERGENCY / ALL 2      ACTIVATION * (ALL CALL)                  CALL    Unusual Event UNUSUAL EVENT -
ACTIVATION - R E R F              EMERGENCY / ALL 3      * (ALL CALL)                            CALL    Unusual Event UNUSUAL EVENT -                      EMERGENCY I 4      ACTIVATION                            PAGER ONLY  Unusual Event UNUSUAL EVENT - NO                  EMERGENCY /
5      ACTIVATION                          PAGER ONLY  Unusual Event UNUSUAL EVENT -                      EMERGENCY I 6      ACTIVATION - R E R F                PAGER ONLY  Unusual Event ALERT - ACTIVATION                EMERGENCY I ALL 7      * (ALL CALL)                            CALL          Alert ALERT - ACTIVATION - R E R F      EMERGENCY I ALL 8      * (ALL CALL)                            CALL          Alert I EMG-NGGC-0005        I          Rev. 3          1    Page 18of27
 
ATTACHMENT 4 Sheet 2 of 6 RNP Emergency Notification Scenarios EMERGENCY CONDITIONS SCENARIO NO.          SCENARIO TITLE              APPLICABILITY    EXAMPLE EMERGENCY /
9    ALERT - ACTIVATION                  PAGER ONLY          Alert EMERGENCY /
10    ALERT - ACTIVATION - R E R F        PAGER ONLY          Alert SITE AREA EMERGENCY-              EMERGENCY I ALL    Site Area 11    ACTIVATION * (ALL CALL)                CALL        Emergency SITE AREA EMERGENCY -
ACTIVATION - R E R F              EMERGENCY I ALL    Site Area 12    * (ALL CALL)                            CALL        Emergency SITE AREA EMERGENCY -                EMERGENCY I      Site Area 13    ACTIVATION                          PAGER ONLY      Emergency SITE AREA EMERGENCY -                EMERGENCY /      Site Area 14    ACTIVATION - R E R F                PAGER ONLY      Emergency GENERAL EMERGENCY -              EMERGENCY I ALL 15    ACTIVATION * (ALL CALL)                CALL      General Emergency GENERAL EMERGENCY    -
ACTIVATION - R E R F              EMERGENCY / ALL 16    * (ALL CALL)                            CALL      General Emergency GENERAL EMERGENCY -                  EMERGENCY /
17    ACTIVATION                          PAGER ONLY  General Emergency GENERAL EMERGENCY-                  EMERGENCY I 18    ACTIVATION - R E R F                PAGER ONLY  General Emergency EMG-NGGC-0005        F          Rev. 3                  Page 19 of 27
 
ATTACHMENT 4 Sheet 3 of 6 RNP Emergency Notification Scenarios EMERGENCY CONDITIONS SCENARIO NO.          SCENARIO TITLE            APPLICABILITY          EXAMPLE EMERGENCY I 19    PAGER FAILURE    * (ALL CALL)        ALL CALL        Pager Failure PAGERS RETURNEDTO                    EMERGENCY/    Pagers Returned 20    SERVICE * (ALL CALL)                ALL CALL          To Service FIRE BRIGADE - REPORT TO              EMERGENCY I 21    STATION 8                            SELECTIVE CALL  Fire Brigade FIRE BRIGADE - REPORT TO              EMERGENCY I 22    R NP                                SELECTIVE CALL  Fire Brigade EMERGENCY /    Termination Of 23    TERMINATION OF EVENT                  PAGER ONLY          Event IEMG-NGGC-0005          I        Rev. 3            1      Page 20 of27
 
ATTACHMENT 4 Sheet 4 of 6 RNP Emergency Notification Scenario Drill Conditions SCENARIO NO.              SCENARIO TITLE                  APPLICABILITY        EXAMPLE Drill - UNUSUAL EVENT -
24      ACTIVATION    * (ALL  CALL)              Drill / All Call  Unusual Event DRILL - UNUSUAL EVENT        -
25      NO ACTIVATION      * (ALL  CALL)          Drill / All Call  Unusual Event DRILL - UNUSUAL EVENT          -
ACTIVATION - R E R F 26      * (ALL  CALL)                            Drill / All Call  Unusual Event DRILL - UNUSUAL EVENT -
27      ACTIVATION                              Drill / Pager Only  Unusual Event DRILL - UNUSUAL EVENT -
28      NO ACTIVATION                            Drill / Pager Only  Unusual Event DRILL - UNUSUAL EVENT -
29      ACTIVATION - R E R F                    Drill / Pager Only  Unusual Event DRILL - ALERT - ACTIVATION 30      * (ALL  CALL)                              Drill / All Call      Alert DRILL - ALERT - ACTIVATION -
31      R E R F * (ALL CALL)                      Drill / All Call      Alert I EMG-NGGC-0005                          Rev. 3                    Page 21 of 27
 
ATTACHMENT 4 Sheet 5 of 6 RNP Emergency Notification Scenario Drill Conditions SCENARIO NO.          SCENARIO TITLE              APPLICABILITY          EXAMPLE 32    DRILL - ALERT - ACTIVATION          Drill / Pager Only        Alert DRILL - ALERT - ACTIVATION -
33    RE R F                            Drill / Pager Only        Alert DRILL - SITE AREA EMERGENCY - ACTIVATION                                      Site Area 34    * (ALL CALL)                          Drill / All Call    Emergency DRILL - SITE AREA EMERGENCY - ACTIVATION -                                    Site Area 35    R E R F * (ALL CALL)                  Drill / All Call    Emergency DRILL - SITE AREA                                          Site Area 36    EMERGENCY - ACTIVATION              Drill / Pager Only    Emergency DRILL - SITE AREA EMERGENCY - ACTIVATION -                                    Site Area 37    RE RF                              Drill/ Pager Only      Emergency DRILL - GENERAL EMERGENCY - ACTIVATION 38    * (ALL CALL)                          Drill / All Call General Emergency DRILL - GENERAL EMERGENCY - ACTIVATION -
39    R E R F * (ALL CALL)                  Drill / All Call General Emergency DRILL - GENERAL 40    EMERGENCY - ACTIVATION              Drill / Pager Only General Emergency IEMG-NGGC-0005                    Rev. 3              1      Page 22 of27
 
ATTACHMENT 4 Sheet 6 of 6 RNP Emergency Notification Scenario Drill Conditions SCENARIO NO.                  SCENARIO TITLE                        APPLICABILITY                      EXAMPLE DRILL - GENERAL EMERGENCY - ACTIVATION -
41        R E RF                                        Drill / Pager Only          General Emergency DRILL - AUGMENTATION 42        * (ALL CALL)                                      Drill / All Call          Augmentation Drill DRILL - QUARTERLY 43        COMMUNICATION * (ALL CALL)                        Drill / All Call              Quarterly Test DRILL - ERO TRAINING (EP 44        USE ONLY) * (ALL CALL)                            Drill / All Call              ERO Training DRILL - CONTROL ROOM 45        PRACTICE * (ALL CALL)                            Drill / All Call              CR Practice DRILL - SIMULATOR 46        PRACTICE      * (ALL CALL)                      Drill / All Call          Simulator Practice 47        DRILL - TERMINATION                            Drill / Pager Only          Termination Of Drill Notice to Emergency                National Terror E P - THREAT LEVEL                          Preparedness / Pager                Threat Level 48        INCREASE - ORANGE                                      Only                      Increase Notice to Emergency                National Terror E P - THREAT LEVEL                          Preparedness / Pager                Threat Level 49        INCREASE - RED                                          Only                      Increase
: 1) The Remote Emergency Response Facility (RERF) should be activated for the following events:
a) A security condition has made the site inaccessible.
b) The EOFITSC facilities are NOT habitable due to flooding, fire, loss of power, etc.
c) Ifan extended evacuation is made as part of the initial Protective Action Recommendation (PAR).
d) As directed by the SEC or ERM.
: 2) (*)Denotes (ALL CALL) in EverBridge Scenario Titles located in EverBridge database.
EMG-NGGC-0005                                Rev. 3                                  Page 23 of27
 
ATTACHMENT 5 Sheet 1 of 1 Using a LAN Computer to Activate the ERO NOTE: This method is used to activate the ERO using the EverBridge website and any available LAN computer.
: 1)  LOG onto the Emergency Response Organization Notification System, EverBridge OR OPEN an internet browser and type "www.everbridge.net".
: 2)  TYPE the site identification from the list below (NOT case sensitive) in the "Member ID" field of the initial login screen.
: a. For BNP, TYPE in "BNPactivation"
: b. For CR3, TYPE in "CR3activation"
: c. For HNP, TYPE in "HNPactivation"
: d. For RNP, TYPE in "RNPactivation"
: 3)  ENTER site specific Password from the "Password Card."
: 4)  SELECT "GO"OR PRESS "Enter" on the keyboard.
: 5)  SELECT "Scenario Manager" from left side of the screen.
: 6)  SELECT "Send Scenario" under "Scenario Manager."
: 7)  LOCATE AND CONFIRM the "Scenario Number" and "Scenario Title" provided by the SEC on the "Send Scenarios" screen, use the "Previous" and "Next" cursors to scroll through the scenario list as needed.
: 8)  CLICK the desired "Scenario Title" in EverBridge once you have located and confirmed that the "Scenario Number" and "Scenario Title" provided by the SEC are in alignment.
NOTE:    A satellite dish animation will appear on the screen to indicate transmission of the message.
: 9)  SELECT "Send Message" at bottom of the "list unscheduled messages" screen.
IEMG-NGGC-0005                I            Rev. 3          1              Page 24 of27
 
ATTACHMENT 6 Sheet 1 of 1 Using the EverBridge Interactive Voice Response to Activate the ERO NOTE: The following steps can be used to activate EverBridge mass communications system via telephone. The automated system will require the following information to activate and ask for responses to the following queries.
: 1) DIAL EverBridge at 9-1-888-440-4911
: 2) LISTEN to the IVR command AND FOLLOW the instructions:
a) "Pleaseenteryour Member ID followed by the "#"sign."
i) For BNP, ENTER "132508351 .#"
ii) For CR3, ENTER "132528221 .#"
iii) For HNP, ENTER "132508331 .#"
iv) For RNP, ENTER "132508341 .#"
b) "Pleaseenter your Passwordfollowed by the "#" sign."
i) ENTER site specific password. See Password Card for site password.
CAUTION Upon completion of the following steps, activation of the ERO will occur.
: 3) To launch a broadcast scenario now, PRESS the number "3".
: 4) To select your scenario by number, PRESS the number "1".
: 5) "Pleaseenteryour scenario number followed by the "#"sign."
a) For example; "10" "if'.
: 6) Voice will state title of the scenario. VERIFY this is the correct entry.
: 7) To select this scenario, PRESS "#" key, otherwise press
: 8) "To launch this scenario now, PRESS the number "1"."
: 9) END call I EMG-NGGC-0005                              Rev. 3          1              Page 25 of 27
 
ATTACHMENT 7 Sheet 1 of 1 Using the Live EverBridge Operator to Activate the ERO NOTE: The following steps can be used to activate the EverBridge mass communications system via telephone and the Live EverBridge Operator.
1.) CALL the live EverBridge operator at 9-1-877-220-4911. You will hear, "Thank you, an EverBridge Operatorwill be with you momentarily."
NOTE: The EverBridge Operator may use variations of the questions below.
2.) QUESTION:        The agent will ask for your Organization Name:
ANSWER:      SEE PASSWORD INFORMATION 3.) QUESTION:      The agent will ask for your Member ID:
ANSWER:      SEE PASSWORD INFORMATION 4.) QUESTION:      For authentication purposes, the agent will ask you your Hint Question: "What is your city of birth?"
ANSWER:      SEE PASSWORD INFORMATION 5.) QUESTION:      The agent should then ask, "How may I help you?"
NOTE: Ensure that the scenario number provided by the SEC and scenario name listed in EMG-NGGC-0005 are in alignment.
ANSWER:      "I WOULD LIKE TO SEND AN EMERGENCY SCENARIO USING THE FOLLOWING SCENARIO NUMBER:" Provide the Live EverBridge Operator with the scenario number that has been provided to you by the SEC.
6.) QUESTION:      The Live EverBridge Operator will then CONFIRM the Scenario Number (and Scenario Name) provided, "Is this the correct Scenario Number?"
ANSWER:      If the Scenario Number and Name are correct - "YES."
If the scenario number and name are incorrect - "NO."
Provide the Live EverBridge Operator with the correct scenario number that has been provided to you by the SEC before proceeding.
7.) QUESTION:      The Live EverBridge Operator will then confirm, "Would you like to send the notification now?"
ANSWER:      "SEND NOTIFICATION NOW." The Live EverBridge Operator will then provide you with the Message Broadcast ID number for tracking purposes.
I EMG-NGGC-0005                          Rev. 3                          Page 26 of 27
 
REVISION
 
==SUMMARY==
 
PRR 617154 IEMG-NGGC-0005 I        Rev. 3    1 Page 27 of 27
 
Enclosure 2f EMG-NGGC-0005, Activation of the Emergency Response OrganizationNotification System, Revision 4
 
w    -
  ,%*Progress Energy                              R Reference
* Use NUCLEAR GENERATION GROUP STANDARD PROCEDURE VOLUME 99 BOOK/PART 99 EMG-NGGC-0005.
ACTIVATION. OF.THE EMERGENCY RESPONSE ORGANIZATION NOTIFICATION SYSTEM REVISION 4
[EMG-NGGC-0005                Rev. 4          Page 1 of 27
 
                                                                                                                -
TABLE OF CONTENTS Section                                                                                                                          Page 1.0    P UR P O S E ......................................................................................................                3
 
==2.0    REFERENCES==
.....................................                ...................................                                3 3.0    RESPONSIBILITIES ...............................................                                                                  4 4.0    DEFINITIONS ................................................................                                                      5 5.0    PREREQ UISITES ..........................................................................                      ................. 5 6.0    PRECAUTIONS AND LIMITATIONS ..............................................................                                        6 7.0    SPECIAL TOOLS AND EQUIPMENT .....                                          .................................                      6 8.0    ACCEPTANCE CRITERIA ..............................................................................                                6 9.0    INSTRUCTIONS ...............................................                                                                      7 10.0  R EC O R D S .....................................................          ................................................... 7 11.0 ATTACHMENTS ..............................................                                                                          7
: 1. BNP Emergency Notification Scenarios ...........................                                                                8
: 2. CR3 Emergency Notification Scenarios............................                                                      ....... 10
: 3. HNP Emergency Notification Scenarios ................................... ............                                          13
: 4. RNP Emergency Notification Scenarios ..... w..........................                                                        18
: 5. Using a LAN Computer to Activate the ERO ..........................                                                ......      24 6    Using the EverBridge Interactive Voice Response to Activate the ERO .                                                          25
: 7. Using the Live EverBridge Operator to Activate the ERO .                                            .............            26 REVISION
 
==SUMMARY==
.... ...............................                                  .......................... ....... 27 EMG-N.GGC-0005                                            Rev. 4                                                    Page2 of 27
 
1.0    PURPOSE This procedure provides guidance for, activating the Emergency Response Organization Notification System for the Nuclear Generation Group. The Emergency Notification System will be used.to notify the Emergency Response Organization during an emergency, drill, exercise, or test.
 
==2.0    REFERENCES==
 
2.1    EMG-NGGC-0004, Maintenance of the Emergency Response Organization Notification System 2.2    EMG-NGGC-1 000, Fleet Conduct of.Emergency Preparedness 2.3    EPNOT-01, [RNP] CR/EOF Emergency Communicator 2.4    EPPRO-02, [RNP] Maintenance and Testing 2.5    PEP-310, .[HNP].Notifications.and Communications 2.6    EPM-410, [HNP] Communication and Facility Performance Test 2.7    EM-206,(EM0206) [CR3] Emergency Plan Roster Notification 2.8    OPEP-02.6.21, [BNP] Emergency Communicator 2.9    OPEP-03.1.3, [BNP] Use of Communication Equipment 2.10  OPEP-02.1.1, [BNP] Emergency Control - Notification of Unusual Event, Alert, Site.Area Emergency, and General Emergency 2.11  [RI] NOCS 100521, Emergency Preparedness On-Site and Off-site communications 2.12    [R2] NOCS 100533, Automated Dialing Capability for Fire Brigade Responders EMG-NGGC-0005                          Rev. 4                          Page 3 of 27
 
3.0      RESPONSIBILITIES 3.1      The Site Emergency Coordinator (SEC) is responsible for determining:
3.1.1    When the Emergency Response Organization (ERO) is to be notified, 3.1.2    Which facilities are to be activated, unless decision is made by EOF Director.
3.1.3    The preferred methods of notification:
: 1.      LAN/Computer
: 2.      Interactive Voice Response (IVR)
: 3.      Live EverBridge Operator 3.2      The emergency notification scenario title and number to be provided as part of the notification.
3.3      Security is responsible for activating the ERO Notification System as directed by the SEC, unless the event is related to a security condition..
3.3.1 If security is unable to activate the ERO Notification System due to the nature of the event, responsibility of activation shall be returned-to Operations.
3.4      In the.event of a security condition, Operations will perform the necessary ERO notifications..
3.5      The Emergency Preparedness staff is responsible. for:
3.5.1    Interface with the vendor(s) providing the notification service.
3.5.2    Maintaining the Emergency Response Organization contact information.
3.5.3    Maintaining the scenario and message contents.
EMG-NGGC-0005                                Rev. 4                              Page4of27
 
4.0      DEFINITIONS 4.1  Aware - Notification software application used by EverBridge.
4.2  EverBridge -. Company that hosts. the software and website used for notification.
    *4.3  Group - Set of defined personnel to be notified.
4.4  Interactive Voice Response (IVR) - One of the options EverBridge provides in the notification of ERO personnel. The system will provide a series of prompts for an individual to respond to via telephone. Once the responses are validated by EverBridge and the correct emergency notification scenario is provided, the notification will be transmitted as directed.
4.5  Live EverBridge Operator. - One.of the options EverBridge provides in the notification of ERO personnel. Using a telephone, site personnel will request an employee of EverBridge to activate the ERO. The EverBridge personnel will in turn request member I.D. and scenario information from the caller to initiate the notification process.
4.6    Password Card - Document which contains the site specific member ID's and passwords required to activate the ERO using the EverBridge notification system.
4.7  :Scenario - collection of message combinations used to notify ERO. A group of messages sent to the ERO to activate in an emergency.
4.8  Site Emergency Coordinator (SEC) - used as a generic term to represent the ERO position acting as the emergency coordinatorfor the site.
5.0      PREREQUISITES 5.1  An emergency event requiring activation of the ERO.
5.2  A drill, exercise, or test is being conducted which invOlves notification of the ERO.
EMG-NGGC-0005                                Rev. 4                            Page 5 of 27
 
6.0    PRECAUTIONS AND LIMITATIONS 6.1    The Emergency Response Organization Notification System (EverBridge) uses pre-programmed messages to contact pre-established ERO personnel groups.. These messages cannot .be modified. without.the permission of the site Emergency Preparedness organization.
6.2    EverBridge is the preferred method of ERO notification. If this system is unavailable, site specific procedures and equipment should be used to provide notification. A.list of these procedures is provided in the Reference Section (Section 2.0).
6.3    A LAN or wireless internet connection is required only if notification is made via the EverBridge website. It is NOT needed if IVR or a Live EverBridge Operator is used.
6.4    If notification occurs using a Live EverBridge Operator, the operatorwill ask a series of questions concerning the notification. These questions may vary from the script provided in Attachment 7. However, the-intent and the critical.
responses will remainconsistent.
6.5    Passwords will NOT be provided in this procedure to ensure the information cannot be accessed inappropriately. Instead, passwords are located on password cards provided to responsible personnel.
6.6    The SEC should indicate the preferred method of notification. The options are:
* LAN Computer Activation
* EverBridge Interactive Voice Response (IVR) Telephone Activation
* Live EverBridge Operator Telephone Activation 6.7    Acronyms and abbreviations will be spoken as words by the IVR. Listen closely to ensure the correct option is selected.
7.0    SPECIAL TOOLS AND EQUIPMENT
      *N/A.
8.0    ACCEPTANCE CRITERIA N/A EMG-NGGC-0005                                Rev. 4                            Page 6 of 27
 
9.0    INSTRUCTIONS 9.1      Use of the EverBridge Notification System CAUTION
*The Scenario Title must correspond to the Scenario Number Provided by the SEC, otherwise the incorrect notification will be activated.
9.2      The SEC will direct activation of the ERO using the Emergency Response Organization Notification System. The Scenario number and preferred method for notification.will be provided. Scenario numbers are identified in the following attachments.
* Attachment  1 - BNP
* Attachment  2 - CR3
* Attachment  3-HNP Attachment  4- RNP 9.3.      IF the system is locked, THEN INITIATE system using alternate notification methods described in this procedure (LAN/Computer, Interactive Voice Response, or Live Operator) or immediately transition to back up ERO notification methods.
9.4      REFER to Attachment 5, to activate the EROusing a LAN computer..
9.5      REFER to Attachment 6, to activate the ERO. using the EverBridcqe Interactive Voice Response (IVR) method.
9.6      REFER to Attachment 7, to activate the ERO using a Live EverBridqe Operator.
*10.0    RECORDS Documents generated by this procedure are NOT required to be retained.
11.0  ATTACHMENTS
: 1. BNP Emergency Notification Scenarios
: 2. CR3 Emergency Notification*Scenarios
: 3. HNP Emergency Notification Scenarios
: 4. RNP Emergency Notification Scenarios
: 5. Using a LAN Computer to Activate the ERO
: 6. Using the EverBridge Interactive Voice Response to Activate the ERO
          ..7. Using the Live EverBri.dge Operator to Activate the- ERO EMG-NGGC-0005                                Rev. 4                          Page 7 of 27
 
ATTACHMENT 1 Sheet 1 of 2 BNP Emergency Notification Scenarios EMERGENCY CONDITIONS SCENARIO TITLE                  SCENARIO NUMBER  APPLICABILITY Unusual Event 1 U E Standby                                            .31      EMERGENCY Unusual Event 2 U E Activate All. No JIC                                44    EMERGENCY Unusual Event 3 U E Activate All Facilities                              24    EMERGENCY Alert 4 Alert Activate All Facilities. No JIC                    34    EMERGENCY Alert
*5 Alert Activate All Facilities                            33    EMERGENCY Site Area Emergency 6 Site Area Emergency Activate All                        35    EMERGENCY General Emergency 7 General Emergency.Activate All        '36                      EMERGENCY Security Event
...8 Security Event Activate A E F and JlC                *.43      EMERGENCY If wrong scenario 9 Notification Error
* 46    was sent Activate the Joint Information
.10 Activate JIC                                              50 . . Center (JIG),Only EMG-NGGC-0u005                              Rev, 4                    Page8 of 27
 
ATTACHMENT 1 Sheet 2 of 2 BNP Emergency Notification Scenarios Drill Conditions.& Information SCENARIO TITLE                  SCENARIO NUMBER          APPLICABILITY 9.0 Drill U E Standby                                    32    Drill 9.1 Drill U E Activate All. No JIC                        4    Drill 9.2 Drill U E Activate All Facilities                    23    Drill 9.3 Drill Alert Activate All Facilities                  37    Drill 9.4 Drill Alert Activate All. No JI.                      38    Drill 9.5 Drill S A E Activate All Facilities                  39    Drill 9.6 Drill G. E Activate All Facilities                    40    Drill.
9.7 Drill Security Event Act A E F and JIG                                                        6    Drill 9.8 Threat Level Increase (orange)                        8    information 9.9 Threat Level Increase (Red)                            842  Information Forced Outage                                            30    Information
'Post Storm Staffing                                      20    Information Test                                                    ..41    Information ERO Notification Drill 2                                  52. Drill If wrong scenario was Notification Error                                        46    sent Drill Activate JIC                                        49. Drill Drill Alert Activate All. No JIc 01                      51  . Drill EI[G.-NGGC-0005                        Rev.4                        Page 9 of 7
 
ATTACHMENT 2 Sheet 1 of 3 CR3 Emergency Notification Scenarios
[R1] [R2]
SCENARIO NO.          SCENARIO TITLE          ].APPLICABILITY Notification Error                  Retraction of any activation message sent
: 1.          ..                              in error Unusual Event - ERO                Unusual Event declared.        Notify ERO to
: 2.      Standby                            assume a heightened state of awareness in anticipation of emergency escalation..
Discretionary - TSC/OSC            At the discretion of the Emergency Coordinator. activate the following facilities:
3.
* Technical Support Center
* Operational Support Center Discretionary -                    At the discretion of the Emergency TSC/OSC/EOF/ENC                    Coordinator, activate the following facilities:
    .4.                                                  Technical Support Center.
                                                  *    .Operational Support Center
                                                  .      Emergency Operations Facility
                                                  . .Emergency        News Center Alert .                            Alert declared. Activate the following facilities:
(Refer to Scenario 8 if
: 5.      activation of remote facilities
* Technical:Support Center
            . is required.)                              operational Support Cente.r O
* Emergency Operations Facility
                                                  ...    .Emergency News Center            .
EMG-NGGC-0005
* T              Rev. 4                            Page 10 of.27
 
ATTACHMENT 2 Sheet 2 of 3 CR3 Emergency Notification Scenarios SCENARIO NO. j        .SCENARIO TITLE                                APPLICABILITY Site Area Emergency                  Site Area Emergency declared. Activate the following facilities.
(Refer to Scenario 9 if
      *6.      activation of remote facilities
* Technical Support Center is required.)
* Operational Support Center
* Emergency Operations Facility
                                                    -.      Emergency News Center General Emergency                    General Emergency declared.. Activate the following facilities:..
(Refer to Scenario 10 if
    *7.        activation of.remote facilities
* Technical Support Center is required.).                              Operational Support Center
* Emergency Operations Facility
                                                    .      Emergency News Center Alert (Remote Facilities)            Alert declared. Activate the following facilities:
: 8.          '                                        Remote Technical Support Center
                                                    * .Remote          Operational Support Center
                                                    *.      Emergency Operations Facility
                                                    .        Emergency News Center Site Area Emergency                  Site Area Emergency declared. Activate
              '(Remote Facilities)                  the following facilities:
    .9.
* Remote Technical. Support Center
                                                    . .Remote          Operational Support Center
* Emergency Operations Facility
                                                    -*      Emergency News Center EMG-NGGC-0005                              Rev. 4                              Page.11of27
 
ATTACHMENT 2 Sheet 3 of 3 CR3 Emergency Notification Scenarios SCENARIO NO.          SCENARIO TITLE                            APPLICABILITY General Emergency              General Emergency declared. Activate the following facilities:.
(Remote Facilities)
: 10.                                                Remote Technical. Support Center
* Remote Operational Support Center
* Emergency Operations Facility
                                              *. Emergency News Center Fire Brigade Support to SAB    Event requiring off-shift Fire Brigade
: 11. 'support                                        to report to the Site.Admin. Building.
(Example: Large-area fire)
Fire Brigade Support to EOF    Event requiring off-shift Fire Brigade support to report to the Emergency
: 12.                                          Operations Facility. (Example: Large-area fire)
Event Termination              Plant conditions no longer require ERO to
: 13.                                          stand by or to report as determined by Emergency Coordinator or EOF Director.
EMG-NGGC-0005                          Rev. 4.                        ... Page 1
 
ATTACHMENT 3 Sheet 1 of 5 HNP Emergency Notification Scenarios NON-SECURITY EVENTS SCENARIO NO.              SCENARIO TITLE I    APPLICABILITY          EXAMPLE UNUSUAL EVENT - Notification        EMERGENCY / ALL 20    Only                                      CALL              Unusual Event UNUSUAL EVENT - Pre Staffing        EMERGENCY / ALL 21    Facilities                                CALL              Unusual Event EMERGENCY / ALL
  .. 22    ALERT                                    CALL                  Alert EMERGENCY I ALL 23    SITE AREA EMERGENCY                      CALL          Site Area Emergency EMERGENCY I ALL 24    GENERAL EMERGENCY                        CALL.        General Emergency.
Event Termination All 25    EVENT TERMINATION                          Call              Any Event EMG-NGGC-0005                      Rev. 4                      Page 13
 
ATTACHMENT 3 Sheet 2 of 5 HNP Emergency Notification Scenarios SECURITY EVENTS SCENARIO NO.              SCENARIO TITLE              APPLICABILITY            EXAMPLE SEC UNUSUAL EVENT -                Security Emergency /
30    Notification Only                        All Call            Unusual Event SEC UNUSUAL EVENT - Pre            Security Emergency I 31    Staffing Facilities                      All Call            Unusual Event Security Emergency I 32    SEC ALERT                                All Call                Alert Security Emergency /
33    SEC SITE AREA EMERGENCY                  All Call        Site Area Emergency Security Emergency /
. 34    SEC GENERAL EMERGENCY                    All Call.        General Emergency.
Security Event 35    SEC EVENT TERMINATION              Termination / All Call      Any Event EMG-NGGC-0005                    Rev. 4.                        Page 14 of 27
 
ATTACHMENT 3 Sheet 3 of 5 HNP Emergency Notification Scenarios Drill - Non Security Events SCENARIO NO.              SCENARIO TITLE                  APPLICABILITY.            EXAMPLE Drill - UNUSUAL EVENT      -
40    Notification Only  .Drill                          / All. Call    Unusual Event Drill - UNUSUAL EVENT - Pre
: 41. Staffing Facilities                            Drill / All Call      Unusual Event 42    Drill - ALERT                                  Drill / All Call          Alert
  *43    Drill - SITE AREA EMERGENCY                    Drill / All Call  Site Area Emergency 44    Drill - GENERAL EMERGENCY                      Drill / All Call  General Emergency Drill Event Termination, 45    Drill - EVENT TERMINATION                        All Call            Any Event EMG-NGGC-0005                          ..Rev. 4                        Page 15 of.27
 
ATTACHMENT 3 Sheet 4 of 5 HNP Emergency Notification Scenarios Drill - Security Events SCENARIO NO...            SCENARIO TITLE                      APPLICABILITY            EXAMPLE Drill Security Emergency 50    SEC.Drill - U.E - Notification Only                /All Call          Unusual Event SEC Drill - UE -Pre Staffing              Drill Security Emergency 51    Facilities                                        / All Call          Unusual Event Drill Security Emergency 52    SEC Drill - ALERT                                  / All Call              Alert SEC Drill - SITE AREA                    Drill Security Emergency 53    EMERGENCY                                          / All Call      Site Area Emergency Drill Security Emergency 54    SEC Drill - GENERAL EMERGENCY                    i  All Call      General Emergency Drill Security Emergency 55    SEC Drill - EVENT TERMINATION                        AII.Call            Any Event EMG-NGGC-0005                              Rev. 4.                        Page 16of 27
 
ATTACHMENT 3 Sheet 5 of 5 HNP Emergency Notification Scenarios Administrative and Testing SCENARIO NO.              SCENARIO TITLE                    APPLICABILITY          EXAMPLE Testing of EverBridge Notification          System Testing /
60      System                                  Selective Individuals      Testing Emergency Response Facility              Response Staffing / All
: 61. Staffing                                          Call.          ERF Staffing.
System Testing I 62    Security EverBridge Training Exercise. Selective Individuals      Testing EMG.-NGGC-0005            I            Rev. 4                        Page 17
 
ATTACHMENT 4 Sheet 1 of 6 RNP Emergency Notification Scenarios EMERGENCY CONDITIONS SCENARIO NO.            SCENARIO TITLE            APPLICABILITY    EXAMPLE UNUSUAL EVENT -                  EMERGENCY / ALL 1      ACTIVATION * (ALL CALL)                CALL    Unusual Event UNUSUAL EVENT - NO              EMERGENCY/-ALL.
2      ACTIVATION * (ALL CALL)                CALL    Unusual Event UNUSUAL EVENT -.
ACTIVATION - R E R F            EMERGENCY! ALL 3      * (ALL CALL)                          CALL    Unusual Event UNUSUAL EVENT -                    EMERGENCY /
4      ACTIVATION                          PAGER ONLY  Unusual Event UNUSUAL EVENT - NO                  EMERGENCY/
:5      ACTIVATION                          PAGER ONLY  Unusual. Event' UNUSUAL EVENT -                    EMERGENCY I
    *6      ACTIVATION - R E R F                PAGER ONLY  Unusual Event ALERT - ACTIVATION              EMERGENCY IALL
            * (ALL CALL) 7                                            CALL          Alert ALERT ACTIVATION - R E R F      EMERGENCY /ALL 8      *(ALL CALL)                            CALL          Alert EMaG-NGGC-0005                  Rev 4                  Page 1    7
 
ATTACHMENT 4 Sheet 2 of 6 RNP Emergency Notification Scenarios EMERGENCY CONDITIONS SCENARIO NO.            SCENARIO TITLE              APPLICABILITY      EXAMPLE EMERGENCY /
9    ALERT - ACTIVATION                  PAGER ONLY          Alert EMERGENCY I 10    ALERT - ACTIVATION - R E R F        PAGER ONLY          Alert SITE AREA EMERGENCY-              EMERGENCY / ALL      Site Area 11    ACTIVATION * (ALL CALL)                CALL          Emergency SITE AREA EMERGENCY    -
ACTIVATION - R E R F              EMERGENCY I ALL      Site Area 12    * (ALL CALL)                            CALL          Emergency SITE AREA EMERGENCY    -            EMERGENCY /      Site Area 13    ACTIVATION                          PAGER ONLY      Emergency SITE AREA EMERGENCY-                EMERGENCY]        Site Area
  .14      ACTIVATION - R E R F                PAGER ONLY      Emergency GENERAL EMERGENCY-                EMERGENCY /ALL
  .15      ACTIVATION *.(ALL CALL)                CALL      General Emergency GENERAL EMERGENCY    -
ACTIVATION - R E R F              EMERGENCY / ALL 16    *(ALL CALL)                            CALL      General Emergency GENERAL EMERGENCY    -              EMERGENCY/
17    ACTIVATION                          PAGER ONLY.. General Emergency GENERAL EMERGENCY-                  EMERGENCY/
18    ACTIVATION.- R E R F.....            PAGER ONLY  General Emergency
    . EMG-NGGC-0005                    Rev. 4                  Page 19 of 27
 
ATTACHMENT 4 Sheet 3 of 6 RNP Emergency Notification Scenarios EMERGENCY CONDITIONS SCENARIO NO.              SCENARIO TITLE            APPLICABILITY          EXAMPLE EMERGENCY /
19      PAGER FAILURE      * (ALL CALL)        ALL CALL        Pager Failure PAGERS RETURNEDTO                        EMERGENCY /    Pagers Returned 20      SERVICE * (ALL CALL)                    ALL CALL          To Service FIRE BRIGADE    -*REPORT. TO          EMERGENCY /
21      STATION 8.                              SELECTIVE CALL    Fire Brigade FIRE BRIGADE - REPORT TO                EMERGENCY/
22      R NP                                    SELECTIVE CALL    Fire Brigade
:EMERGENCY/      Termination Of
: 23. TERMINATION OF EVENT                    PAGER ONLY            Event EMG-NGGC-0005                        Rev.A..                  Page 2.0..of 27
    *MG    IG-005IRv.4                                            Pge    0Io 2
 
ATTACHMENT 4 Sheet 4 of 6 RNP Emergency Notification Scenario Drill Conditions SCENARIO NO.              SCENARIO TITLE                APPLICABILITY          EXAMPLE Drill - UNUSUAL EVENT -
24    ACTIVATION * (ALL CALL)                    Drill /All*Call    Unusual Event DRILL - UNUSUAL EVENT-25    NO ACTIVATION *.(ALL CALL)                Drill / All Call .Unusual    Event DRILL  -  UNUSUAL EVENT      -
ACTIVATION      - RERF
    .26    * (ALL CALL)                              Drill.. All Call  Unusual Event DRILL - UNUSUAL EVENT        -
  .27      ACTIVATION                              Drill / Pager Only  Unusual Event DRILL - UNUSUAL EVENT          -
28    NO ACTIVATION                            Drill / Pager Only  Unusual Event DRILL - UNUSUAL .EVENT        -
29    ACTIVATION - R E R F                    Drill /Pager Only    Unusual Event.
DRILL - ALERT      - ACTIVATION 30      (ALL CALL)                              Drill / All Call        Alert DRILL - ALERT - ACTIVATION        -
  .31      R E R F    * (ALL CALL)                    Drill/ All Call        Alert EMG-NGGC-0005        . . I          Rev. 4                      Page 21 of 27
 
ATTACHMENT 4 Sheet 5 of 6 RNP Emergency Notification Scenario.
Drill Conditions SCENARIO NO.                SCENARIO TITLE              APPLICABILITY            EXAMPLE 32      DRILL - ALERT - ACTIVATION          Drill /Pager Only            Alert DRILL - ALERT -. ACTIVATION -
  .33        RE R F                              Drill /Pager Only.          Alert.
DRILL - SITE AREA EMERGENCY - ACTIVATION                                          Site Area
:34      * (ALL CALL)                          Drill / All Call        Emergency DRILL - SITE AREA
            . EMERGENCY- ACTIVATION -                                        Site Area 35      R E R F * (ALL CALL)                  Drill / All Call        Emergency DRILL  -  SITE AREA                                            Site Area 36        EMERGENCY - ACTIVATION              Drill]/ Pager Only.      Emergency DRILL - SITE AREA EMERGENCY - ACTIVATION -                                        Site Area 37    .RERF                                  Drill /Pager Only        Emergency DRILL.- GENERAL.
EMERGENCY - ACTIVATION 38          (ALL CALL)                          Drill All Call      General Emergency DRILL - GENERAL EMERGENCY - ACTIVATION*.
39        R E R F (ALL CALL)                    Drill /All Call    General Emergency DRILL-GENERAL                                            '
40        EMERGENCY - ACTIVATION.              Drill/ Pager Only    General Emergency EMG-NGGC-0005.                      Rev. 4                        Page 22 of 27
 
ATTACHMENT 4 Sheet 6 of 6 RNP Emergency Notification Scenario Drill Conditions SCENARIO NO.        j          SCENARIO TITLE.                      APPLICABILITY                      EXAMPLE DRILL - GENERAL EMERGENCY - ACTIVATION -
41          R ER F                                        Drill    Pager Only          General Emergency DRILL.- AUGMENTATION 42          * (ALL CALL)                                      Drill / All Call          Augmentation Drill DRILL - QUARTERLY 43          COMMUNICATION * (ALL CALL)                        Drill /All Call              Quarterly Test DRILL - ERO TRAINING (EP 44          USE ONLY) * (ALL CALL)                            Drill /All Call              ERO Training DRILL - CONTROL ROOM 45          PRACTICE * (ALL CALL)                              Drill / All Call              CR Practice DRILL - SIMULATOR 46          PRACTICE * (ALL CALL)                              Drill / All Call          Simulator Practice 47          DRILL - TERMINATION                            Drill /Pager Only            Termination Of Drill Notice to Emergency                National Terror E P - THREAT LEVEL                          Preparedness Pager                  Threat Level 48          INCREASE - ORANGE                                      Only.                      Increase.
Notice to Emergency                National Terror E P - THREAT LEVEL                          Preparedness /Pager                  Threat Level 49          INCREASE- RED..                                        Only                      Increase
: 1)  The  Remote Emergency Response Facility (RERF) should be activated for the following events:
a)  A security condition has made the site inaccessible.
b)  The EOF/TSC facilities are NOT habitable due to flooding, fire, loss of power, etc.
c)  ifan extended evacuation is made as part of the initial Protective Action Recommendation (PAR).
d)  As directed by the SEC or ERM.
: 2) (*)Denotes-(ALLCALL) in EverBridge Scenario Titles located in EverBridge database.
Rev4        .                          Page 23 of 27 EM*GC00 EMG-N.GGC-000.5                                Rev. 4                                  Page 23 of.27 I.
 
ATTACHMENT 5 Sheet 1 of 1 Using a LAN Computer to Activate the ERO NOTE: This method is used to activate the ERO using the EverBridge website and any available LAN computer.
1). LOG onto the Emergency Response. Organization Notification System, EverBridge using one of the following options:
      ..    .. Go to the internet and type* "www.everbridge.net".
I using a Windows XP Desktop, THEN SELECT Start>Programs>Emergency iF Preparedness >EverBridge.
      .*        IF using a Windows 7 Desktop, THEN SELECT Start>All Programs>DAE>Shortcuts Tab>Search EverBridge>Select EverBridge and Run Application.
: 2)  TYPE the site identification from the list below (NOT case sensitive) in the "Member ID" field of the initial login screen.
: a. For BNP, TYPE in "BNPactivation"
: b. For CR3, TYPE in "CR3activation"
: c. For HNP, TYPE in "HNPactivation"
: d. For RNP, TYPE in "RNPactivation"
: 3)  ENTER site specific Password from the "Password Card:"
  *4) SELECT "GO" OR PRESS "Enter" on the keyboard.
: 5)  SELECT "Scenario. Manager" from left side of the screen.
: 6)  SELECT "Send Scenario" under "Scenario Manager."
*7)  LOCATE AND CONFIRM.the "Scenario Number"and "Scenario Title" provided by the SEC on the "Send Scenarios" screen, use the "Previous" and "Next" cursors to scroll through the scenario list as needed..                      .
: 8)  CLICK the desired "ScenarioTitle" in EverBridge once you have located and confirmed that the "Scenario. Number" and "Scenario Title" provided by the SEC are in alignment.
NOTE:    Asatellite dish animation will appear. on the screen to indicate transmission of the
        *m essage.**    *.  ..                ..            .    ..
: 9)  SELECT "Send Message" at bottom of the "list unscheduled messages" screen.
E.MG-NGGC-0005                                Rev. 4                              Page 24 of27
 
ATTACHMENT 6 Sheet 1 of 1 Using the EverBridge Interactive Voice Response to Activate the ERO NOTE. The following steps can be used to activate EverBridge mass communications system via telephone. The automated system will require the following information to activate and ask for responses to the following queries.
: 1) DIAL EverBridge at 9-1-888-440-4911
: 2) LISTEN to the IVR command AND FOLLOW the instructions:
a) "Pleaseenter your Member ID followed by the "#" sign."
i.) For BNP, ENTER "132508351"        "#"
ii) For CR3, ENTER "132528221        "#"
iii) For HNP, ENTER "132508331."      "#"
iv) For RNP, ENTER "13250834"          "#.V" b) "Pleaseenter your Passwordfollowed by the          "#" sign."
i) ENTER site specific password. See Password Card for site password.
CAUTION Upon completion of the following steps, activation of the ERO will occur.
: 3) To launch a broadcast scenario now, PRESS the number "3".
: 4) To select your scenario by number, PRESS the number "1".
: 5) "Pleaseenter your scenario number followed by&#xfd; the "#"sign."
a) For example; "10" "1#'.
: 6) Voice will state title of the scenario. VERIFY this is the correct entry.
: 7) To select this scenario, PRESS"#" key; otherwise press
: 8) *"To launch this scenario now,-PRESS the number"1"."
: 9) END call EMG-NGGC-0005                              Rev.      .                      Page 25 of2
 
ATTACHMENT 7 Sheet 1 of 1 Using the Live EverBridge Operator to Activate the: ERO NOTE: The following steps can be used to activate the EverBridge mass communications system via telephone and the Live EverBridge Operator.
1.) CALL the live EverBridge operator at 9-1-877-220-491 1. You will. hear, "Thank you, an EverBridge Operatorwill be with you momentarily."
NOTE: The. EverBridge Operator may use variations of the questions below.
2.) QUESTION:          The agent will ask for your Organization Name:
ANSWER:      SEE PASSWORD INFORMATION 3.) QUESTION:        The agent will ask for your Member ID:
ANSWER-      SEE PASSWORD INFORMATION 4.) .QUESTION:        For authentication purposes, the agent will ask you your Hint Question: "What is your city of birth?"
ANSWER:      SEE PASSWORD INFORMATION 5.) QUESTION:        The agent should then ask, "How may /help you?"
NOTE: Ensure that the scenario number provided by the SEC and scenario name listed in EMG-NGGC-0005 are in alignment.
ANSWER:.. "I WOULD LIKE TO SEND AN EMERGENCY SCENARIO USING THE FOLLOWING SCENARIO NUMBER:" Provide the Live EverBridge Operator with the scenario number that has been.
provided to you by the SEC.
*6.) QUESTION:        The Live EverBridge Operator will. then CONFIRM the Scenario Number (and Scenario -Name). provided, "Is this the correct Scenario Number?"
        ..ANSWER:      If the.Scenario Number and Name are correct.- "YES."
If the scenario number and name are incorrect - "NO."
Provide the Live EverBridge Operator with the correct scenario number that has been provided to"you by the SEC before proceeding.
7.). QUESTIO.N::      The Live EverBridge. Operator will.then confirm, "Would you like to send the notification now?"
ANSWER:      "SEND NOTIFICATION NOW." The Live EverBridge Operator will then provide you With the MessageB1roadcast ID number for'.
tracking purposes.
EMG-NGGC-0005                              Rev. 4                          Page 26 of 27
 
REVISION
 
==SUMMARY==
 
EMG-NGGC-0005 Rev. 3 SECTION                    REVISION COMMENTS.
implementation.        Removed program location description for WIN7 step 1).          (Editorial)
EMG-NGGC-0005 Rev. 4 PRR 615736, CR 619320 SECTION                    REVISION COMMENTS Added removed EverBridge program instructions from previous        revision and added location description for Windows 7 Desktop for step 1).          WIN7 implementation. (Editorial)
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