ML021340637
| ML021340637 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 05/07/2002 |
| From: | Barron H Duke Energy Corp |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML021340637 (68) | |
Text
Sk Duke Duke Energy Corporation McGuire Nuclear Station Energy.
12700 Hagers Ferry Road Huntersville, NC 28078-9340 H. B. Barron (704) 875-4800 OFFICE Vice President (704) 875-4809 FAX May 7, 2002 Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Re:
McGuire Nuclear Station Unit 1 Docket No.
50-369 McGuire Nuclear Station Unit 2 Docket No.
50-370 Changes to Emergency Plan Implementing Procedures Attached to this letter are a revised Emergency Plan Implementing Procedure (EPIP) Index and a notice of revision to five (5)
Emergency Plan Implementing Procedures.
These procedure revisions were evaluated pursuant to the requirements of 10 CFR 50.54 (q).
These changes do not constitute a reduction in the effectiveness of the emergency plan and the plan continues to meet the requirements of 10 CFR 50.47 (b) and 10 CFR 50 Appendix E.
Duke implemented these changes on April 10, 2002.
A copy of these changes is also being sent to the NRC Office of Nuclear Material Safety and Safeguards as per 10 CFR 72.44 (f).
Revision bars within the procedures indicate the revisions.
The following procedure index changes and procedure revisions have been implemented:
EPIP Index Page 1 Dated 4/10/2002 EPIP Index Page 2 Dated 4/10/2002 EPIP Index Page 3 Dated 4/10/2002 REVISION to the following procedures:
HP/0/B/1009/003 Dated 4/10/2002, Rev 004 HP/0/B/1009/006 Dated 4/10/2002, Rev 006 HP/0/B/1009/016 Dated 4/10/2002, Rev 003 HP/0/B/1009/024 Dated 4/10/2002, Rev 002 HP/0/B/1009/029 Dated 4/10/2002, Rev 006 There are no new regulatory commitments in this document.
Duke is also supplying two copies of this submittal to the Regional Administrator of Region II.
Questions on this document should be directed to Kevin Murray at (704) 875-4672.
Very truly yours, H.
B. Barron Attachments
U.S. Nuclear Regulatory Commission May 7, 2002 Page 2 xc:
(w/attachment)
Mr. Luis Reyes, Regional Administrator U.S. Nuclear Regulatory Commission Region II 61 Forsyth St.,
SW, Suite 23T85 Atlanta, Georgia 30303 (w/attachment)
Mr. Martin J.
Virgilio, Director Office of Nuclear Material Safety and Safeguards Mail Stop T-8A23 Washington, D.C. 20555-0001 (w/o attachment)
R.
E. Martin, USNRC U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D.C.
20555 NRC Resident Inspector McGuire Nuclear Station E.M. Kuhr (ECO50)
M.T. Cash, Manager NRIA (ECO50)
Electronic Licensing Library (EC050)
EP File I11
DUKE McGUIRE NUCLEAR SITE EMERGENCY PLAN IMPLEMENTING PROCEDURES APPROVED:
SAfE *4SSuRANCE MANAGER DATE APPROVED EPIP Index Page EPIP Index Page EPIP Index Page HP/0/B/1009/003 HP/0/B/1009/006 HP/0/B/1009/016 HP/0/B/1009/024 HP/0/B/1009/029 1
2 3
Dated Dated Dated Dated Dated Dated Dated Dated 4/10/2002 4/10/2002 4/10/2002 4/10/2002, 4/10/2002, 4/10/2002, 4/10/2002, 4/10/2002, Sr/i /,j -
Rev Rev Rev Rev Rev 004 006 003 002 006
EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX PROCEDURE #
RP/O/A15700/000 RP/O/A/5700/001 RP/0/A/5700/002 RP/0/A/5700/003 RP/0/A/5700/004 RP/O/A/5700/05 RP/0/A/5700/006 RP/O/A/5700/007 RP/O/A15700/008 RP/01A/5700/009 RP/O/A/5700/010 RP/0/A/5700/011 RP/0/A/5700/012 RP/O/A15700/0 13 RP/O/A/5700/14 RP/0/A/5700/015 RP/0/A/5700/16 RP/0/A15700/17 RP/O/A/5700/018 RP/O/A/5700/019 RP/O/A15700/020 RP/O/A/5700/21 RP/O/A/5700/022 RP/O/A/5700/024 RP/O/A/5700/026 RP/0/B/5700/023 OPO/OB/6200/090 TITLE Classification of Emergency Notification of Unusual Event Alert Site Area Emergency General Emergency Care and Transportation of Contaminated Injured Individual(s) From Site to Offsite Medical Facility Natural Disasters Earthquake Release of Toxic or Flammable Gases Collisions/Explosions NRC Immediate Notification Requirements Conducting a Site Assembly, Site Evacuation or Containment Evacuation Activation of the Technical Support Center (TSC)
Activation of the Emergency Operations Facility (EOF)
Emergency Telephone Directory Notifications to the State and Counties from the EOF EOF Commodities and Facilities Procedure Emergency Data Transmittal System Access Notifications to the State and Counties from the TSC Core Damage Assessment Activation of the Operations Support Center (OSC)
EOF Access Control Spill Response Procedure Recovery and Reentry Procedure Operations/Engineering Technical Evaluations in the Technical Support Center (TSC)
Community Relations Emergency Response Plan PALSS Operation for Accident Sampling April 10, 2002 Rev. 30 REVISION NUMBER Rev. 008 Rev. 016 Rev. 016 Rev. 016 Rev. 016 DELETE Rev. 009 Rev. 007 Rev. 004 Rev. 002 Rev. 013 Rev. 005 Rev. 019 DELETE DELETE DELETE DELETE DELETE Rev. 011 Rev. 004 Rev. 011 DELETE Rev. 009 Rev. 002 Rev. 002 Rev. 002 DELETED I
EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX PROCEDURE #
HP/0/B/1009/002 HP/0/B1/1009/003 HP/O/B/1009/05 HP/0/B/1009/006 HP/0/B/1009/010 HP/1/B/1009/015 HP/2/B/1009/015 HIP/O/B/1009/016 HP/0/B/1009/020 HP/0/B/1009/021 HPIO/B/11009/022 HP/0/B1/1009/023 HP/O/B/1009/024 HP/O/B/ 1009/029 SH/0/B/2005/001 SHIO/B/2005/002 SR/0/B/2000/01 SR/0/B/2000/002 SR/0/B/2000/003 SR/O/B/2000/004 TITLE Alternative Method for Determining Dose Rate Within the Reactor Building Recovery Plan Initial Evaluation of Protective Action Guides Due to Abnormal Plant Conditions Procedure for Quantifying High Level Radioactivity Releases During Accident Conditions Releases of Radioactive Effluents Exceeding Selected Licensee Commitments Unit 1 Nuclear Post-Accident Containment Air Sampling System Operating Procedure Unit 2 Nuclear Post-Accident Containment Air Sampling System Operating Procedure Distribution of Potassium Iodide Tablets in the Event of a Radioiodine Release Manual Procedure for Offsite Dose Projections Estimating Food Chain Doses Under Post-Accident Conditions Accident and Emergency Response Environmental Monitoring for Emergency Conditions Personnel Monitoring for Emergency Conditions Initial Response On-Shift Dose Assessment Emergency Response Offsite Dose Projections Protocol for the Field Monitoring Coordinator During Emergency Conditions Standard Procedure for Public Affairs Response to the Emergency Operations Facility Standard Procedure for EOF Commodities and Facilities Activation of the Emergency Operations Facility Notification to States and Counties from the Emergency Operations Facility April 10, 2002 Rev. 30 REVISION NUMBER Rev. 002 Rev. 004 DELETED Rev. 006 Rev. 006 DELETED DELETED Rev. 003 DELETED Rev. 001 Rev. 003 Rev. 004 Rev. 002 Rev. 006 Rev. 001 Rev. 002 Rev. 003 Rev. 002 Rev. 009 Rev. 005 2
EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX PROCEDURE #
McGuire Site Directive 280 EP Group Manual MNS RP Manual:
PT/0/A/4600/088 TITLE Site Assembly/Accountability and Evacuation/Containment Evacuation Section 1.1 Emergency Organization Section 18.1 Accident and Emergency Response Section 18.2 Environmental Monitoring for Emergency Conditions Section 18.3 Personnel Monitoring for Emergency Conditions Section 18.4 Planned Emergency Exposure Functional Check of Emergency Vehicle and Equipment April 10, 2002 Rev. 30 REVISION NUMBER DELETED Rev. 017 DELETED DELETED DELETED DELETED Rev. 007 3
(Ro4-01)
Duke Power Company PROCEDURE PROCESS RECORD (1) ID No. HPIOJBII0O9/003 Revision No.
00)4
"-REPARATION (2) Station McGuire Nuclear Station (3) Procedure Title Recovery Plan (4) Prepared By Grayton Cayton Date February 27, 2002 (5) Requires NSD 228 Applicability Determination?
[i Yes (New procedure or revision with major changes)
[
No (Revision with minor changes)
F] No (To incorporate reviously approved changes)
(6) Reviewed By (QR)
Date 3ý o o _
Cross-Disciplinary Review B (QR) NAGL-I Date e
Qiz2.
Reactivity Mgmt. Review By (QR) NA**Lý::
Date-h o2 Mgmt. Involvement Review By (OPS Supt.) N A z
Date 3
oz
- 2.
(7) Additional Reviews Reviewed By Date Reviewed By Date (8) Temporary Approval (if necessary)
By (OSM) Date By (QR) Date_
(9) Approved By Date 6e-xo-e PERFORMANCE (Compare with Control Copy every 14 calendar days while work is being performed.)
(10) Compared with Control Copy Date Compared with Control Copy Date Compared with Control Copy Date (11) Date(s) Performed Work Order Number (WO#)
COMPLETION (12) Procedure Completion Verification DI Yes El NA Check lists and/or blanks initialed, signed, dated, or filled in NA, as appropriate?
El Yes nI NA Required enclosures attached?
El Yes El NA Data sheets attached, completed, dated and signed?
El Yes El NA Charts, graphs, etc. attached, dated, identified, and marked?
E] Yes El NA Procedure requirements met?
Verified By Date (13) Procedure Completion Approved Date (14) Remarks (Attach additional pages, if necessary.)
Form based on NSD 703 App D (Procedure Process Record)
Duke Power Company McGuire Nuclear Station Recovery Plan Information Use Procedure No.
HP/O/B/1009/003 Revision No.
004 Electronic Reference No.
MC0045FW I
HP/O/B/1009/003 Page 2 of 6 Rev 004 (04/03/02) For documentation. This revision allows procedure to be accessed via NEDL.
HP/O/B/1009/003 Page 3 of 6 Recovery Plan
- 1. Purpose 1.1 To provide a plan for recovery from, and return to an operational status following a Notification of Unusual Event, Alert, Site Area Emergency, or a General Emergency 1.2 The level of use for this procedure is "Information Use".
- 2. References 2.1 Radiation Protection Policy Manual Policy Number 11-02, Planned Special Exposure and Emergency Dose Limits for Occupationally Exposed Personnel 2.2 Nuclear System Directive 201 - Reporting Requirements 2.3 SHIO/B/2000/005, Posting of Radiation Control Zones 2.4 SHI0/B/2000/004, Taking, Counting, and Recording Surveys
- 3. Limits and Precautions 3.1 Normal respiratory protection guidelines shall be followed.
3.2 Normal Radiation Protection dosimetry procedures shall be followed.
3.3 Protective clothing shall be used whenever loose contamination exists or is suspected to be greater than 1000 dpm/100cm2 Beta-Gamma or 20 dpmlOOcm2 Alpha.
3.4 Posting of radiation control zones shall follow guidelines in Reference 2.3.
3.5 Surveys shall be performed under guidelines in Reference 2.4.
- 4. Procedure 4.1 In any plant emergency involving radioactive contamination, the immediate action is directed to limiting the consequences of the incident in a manner that affords maximum protection to the public. Once the immediate protective actions have established an effective control over the incident, the emergency actions shall shift into the recovery phase.
HP/O/B/1009/003 Page 4 of 6 4.2 A recovery plan, from a practical standpoint, shall be flexible enough to adapt to existing conditions. It is not possible to anticipate in advance all of the conditions that may be encountered in an emergency situation, therefore this recovery plan is addressed to general principles that serve as a guide for developing a flexible plan of action.
Comprehensive plans for recovery from any major emergency are formulated on agreements between Duke Power and the NRC, the Radiation Protection Branch of the North Carolina Department of Human Resources, the North Carolina Department of Crime Control and Public Safety, and the Mecklenburg County Health Department.
4.3 In the recovery phase all station actions shall be carefully planned by Duke Power Company management. In the period immediately following an incident, initial radiation monitoring functions shall involve only gross hazard evaluations and isolation of radiological problem areas. These immediate radiation surveys are intended to provide the basic information necessary for the recovery operation.
4.4 The initial re-entry into the affected area shall be conducted by Radiation Protection personnel to evaluate radiological hazards and contamination levels.
4.5 Subsequent to the initial entry and after the radiological hazards have been identified the recovery operation may proceed in accordance with the following case examples:
4.5.1 CASE "A" - Unusual Events or Alert conditions that may have resulted in the spread of contamination, unsafe conditions, and/or evacuation of an area due to noxious gases being present.
4.5.1.1 The Station Manager, Station RPM, Station Safety Manager and Station Chemist shall make decisions related to their areas of responsibility to recover and normalize any affected areas.
Applicable paragraphs of CASE "C" may become pertinent in this case.
4.5.1.2 Follow all Limits and Precautions prescribed to ensure the safety of all recovery personnel.
4.5.2 CASE "B" - Site Area Emergencies that have resulted in the evacuation of a station area, the spread of contamination, and/or change in the operating status of the station.
4.5.2.1 The Station Manager, Group Superintendents and Station RPM shall make decisions related to their areas of responsibility to recover and normalize any affected areas. All paragraphs of CASE "C" may also be applicable.
4.5.2.2 Follow all Limits and Precautions prescribed to ensure the safety of all recovery personnel.
HP/0/BI/1009/003 Page 5 of 6 4.5.2.3 On completion of recovery operations ensure proper documentation of the accident and include all pertinent data involving the incident and the recovery operation.
4.5.3 CASE "C" - General emergencies that have resulted in the spread of contamination, evacuation of an area of the station, injured personnel, or a change in the operating status of the station.
4.5.3.1 The Station Manager, Station Group Superintendents, Station Radiation Protection Manager (RPM) and Staff, Emergency Operations Facility Director at the Emergency Operations Facility (EOF), and any other offsite agencies who may be involved shall decide what procedures and precautions shall be taken in the recovery plan.
4.5.3.2 Review all available radiation survey data. Determine station areas potentially affected by radiological hazards.
4.5.3.3 Review radiation exposure history of all personnel scheduled to participate in the recovery operations. Determine the need for additional personnel.
4.5.3.4 Review the adequacy of radiation survey equipment available.
Determine the need for additional equipment and a source of procurement.
4.5.3.5 Pre-plan survey team activities, including areas to be surveyed, anticipated radiation levels, survey equipment required, protective clothing requirements, access control procedures, exposure control procedures, and communication capabilities.
4.5.3.6 Conduct a comprehensive radiation survey or surveys of station facilities and define all radiological problem areas.
4.5.3.7 Post all appropriate areas following the guidelines in Reference 2.3.
4.5.3.8 Perform visual inspection of station areas and equipment.
4.5.3.9 All radiological conditions discovered and existing in the facility as determined by the re-entry survey shall be evaluated by station management and EOF Personnel.
4.5.3.10 Upon evaluation of the radiological conditions, the EOF Director at the EOF shall determine what procedures are required to restore the site to a normal status.
HP/0/BI/1009/003 Page 6 of 6 4.5.3.11 Personnel radiation exposure shall be closely controlled and documented per Reference 2.1.
4.5.3.12 Recovery coordinators shall take appropriate actions to ensure that emergency personnel and equipment leaving the radiation control area are not contaminated, that radiological conditions at the scene of the emergency are properly defined, barricaded, and posted with appropriate signs.
4.5.3.13 The EOF Director, Station Manager, Station Group Superintendents, and Station RPM shall make all necessary decisions to return the unit to normal status and to prevent a recurring problem.
4.6 Formal reporting of the emergency and recovery shall be completed as required by NSD 201 - Reporting Requirements (Reference 2.2).
- 5. Enclosures N/A
(R04-01)
(4) Prepared By Grayton Cayton Date February 27, 2002 (5) Requires NSD 228 Applicability Determination?
El Yes (New procedure or revision with major changes)
[
No (Revision with minor changes)
LI No (To incorporate previously approved changes)
(6) Reviewed By Cý C.C (OR)
Cross-Disciplinary Review By (QR) NA Reactivity Mgmt. Review By (OR) NA CV Mgmt. Involvement Review By (OPS Supt.) NA-'c (7) Additional Reviews Reviewed By Reviewed By (8) Temporary Approval (if necessary)
By (OSM)
By (OR)
- 9) Approved By z
Date 31 Date 31 I.J2 Date 3
10
- 02.
Date oz I
oZ.
Date Date Date Date Date-PERFORMANCE (Compare with Control Copy every 14 calendar days while work is being performed.)
(10) Compared with Control Copy Date Compared with Control Copy Date Compared with Control Copy Date (11) Date(s) Performed Work Order Number (WO#)
COMPLETION (12) Procedure Completion Verification El Yes D-NA Check lists and/or blanks initialed, signed, dated, or filled in NA, as appropriate?
El Yes El NA Required enclosures attached?
El Yes 13 NA Data sheets attached, completed, dated and signed?
El Yes El NA Charts, graphs, etc. attached, dated, identified, and marked?
E] Yes El NA Procedure requirements met?
Verified By Date (13) Procedure Completion Approved Date (14) Remarks (Attach additional pages, if necessary.)
Form based on NSD 703 App D (Procedure Process Record)
Duke Power Company PROCEDURE PROCESS RECORD (1) ID No. HP/OfB/1009/006 Revision No.
006 "ION McGuire Nuclear Station ure Title Procedure for Quantifying High Level Radioactivity Releases During Accident Conditions 1EPARAT A2) Station (3) Proced
Duke Power Company McGuire Nuclear Station Procedure for Quantifying High Level Radioactivity Releases During Accident Conditions Multiple Use I Procedure No.
HP/O/B/ 1009/006 Revision No.
006 Electronic Reference No.
MC0045FZ
HP/O/B/ 1009/006 Page 2 of 6
HP/O/B/ 1009/006 Page 3 of 6 Procedure for Quantifying High Level Radioactivity Releases During Accident Conditions
- 1. Purpose This procedure describes methods for collecting samples and taking radiation measurements for estimating noble gas, particulates, and radioiodine concentrations if the existing effluent instrumentation goes offscale during accident conditions. Enclosure 5.1 through 5.6 are designated as: REFERENCE USE, and must be at the sample location at all times during sampling. The remaining portions of this procedure are designated as: INFORMATION USE and are not required to be at sample locations during sampling.
- 2. References 2.1 NUREG-0737, Table 2.F.1-2 2.2 Remote Unit Vent Sampler Activity Buildup and Dose Assessment Calculations MCC 1229.00-33 and MCC 1227.00-23 2.3 HP/O[B/1004/019, Preparation of Samples for Count Room Analysis 2.4 HP/0B/1001/035, Operation of the Gamma Spectroscopy System 2.5 HPIO/B/10031036, Unit Vent 2.6 SH/OIB/2000/004, Taking, Counting and Recording Surveys.
- 3. Limits and Precautions 3.1 This procedure is written for use under abnormal conditions, which could involve extremely high radiation levels. Individuals collecting the samples shall be aware of the possibility of airborne contamination and high radiation levels in sampling areas.
3.2 When taking samples, as much as practical, keep individual exposures < 5 rem Total Effective Dose Equivalent and extremities < 50 rem Shallow Dose Equivalent per year.
Obtain dose extension through the OSC as appropriate.
3.3 Only the Station Radiation Protection Manager/designee shall authorize the use of this procedure when needed and shall ensure appropriate surveillance and control of people taking the samples.
3.4 All commitments are denoted at the end of the referenced section of this procedure by brackets { } with a number inside. They are specifically listed on Enclosure 5.8.
HP/0/B/ 1009/006 Page 4 of 6 3.5 Unless otherwise directed by RP Supervisor, or qualified designee, follow all steps of this procedure. All deviations from this procedure shall meet the intent of this procedure.
3.6 Do not dispose of silver zeolite cartridges in radioactive waste. Contact RP Staff for disposal of used silver zeolite cartridges.
- 4. Procedure 4.1 RWP 5020 is provided for performance of this task.
"* Read and logon to RWP 5020.
"* Comply with all RWP requirements.
4.2 Obtain the following equipment necessary for remote Unit Vent sampling:
4.2.1 Survey instrument, preferably an Ion Chamber.
4.2.2 Sample train equipment:
- 95cc gas bomb with two sections of small gauge tygon tubing 4.3 Using Enclosure 5.1, set up remote vent sampling. {16}
4.3.1 The actions described on Enclosure 5.1, steps 1.1.1.1 -1.1.1.5, are an effort to place equipment in a maximum safe condition. It is not mandatory and should only be performed if dose rates and manpower permit. Check with the OSC and check EMF23 (Unit Vent Area Monitor) to determine appropriate actions and travel path. If the normal unit vent cannot be secured, proceed to.1, step 1.1.2.
4.4 Using Enclosure 5.2, repeat sampling at 30 minute intervals or as directed by Station Radiation Protection Manager/designee. { 161 4.4.1 This interval will depend on the contact dose rates on the sample train and the severity of the accident.
4.4.2 If long term unit vent sampling using the remote sample train is to take place, consult supervision regarding channel checks, weekly requirements, inoperable requirements, etc.
HP/O/B/1009/006 Page 5 of 6 4.5 When remote sampling is no longer required, resume normal vent sampling using.3. { 16}
4.6 After each sample, transfer applicable data from Enclosure 5.1, 5.2, or 5.3 to Dose Rate Logsheet (Enclosure 5.5).
4.7 With the individual sample holders separated, obtain closed window contact dose rates from each holder; particulate, iodine cartridge and gas bomb. Record on Dose Rate Logsheet.
4.8 If samples can be counted in the Count Room (i.e. < 10 mr/hr), report analysis results to the TSC or EOF.
4.9 If samples cannot be counted in the Count Room, iodine, particulate, and noble gas concentrations will be determined by completion of Enclosure 5.6 as follows:
4.9.1 Using Enclosure 5.4, select DCF for the time after Reactor shutdown for the most recent sample off time and record on Enclosure 5.6.
4.9.2 Using Enclosure 5.5, subtract G/A readings from the return line readings and record on Enclosure 5.6 at DR(RL)-GA. Record the particulate housing reading, iodine housing reading, at DR(PH) and DR("l1) respectively.
4.9.3 Complete the calculations on Enclosure 5.6.
4.10 Report results from the Unit Vent Effluent Worksheet to the TSC or EOF.
4.11 Gas bombs not analyzed shall be purged unless otherwise directed by TSC.
4.12 All particulate filters shall be saved for compositing.
- If doserates >100 mr/hr at 12", store in a pig in the Source Room.
4.13 When remote sampling is terminated, assemble completed procedure package.
- 5. Enclosures 5.1 Unit Vent Normal to Remote Transfer 5.2 Unit Vent Remote Sampling 5.3 Unit Vent Remote to Normal Transfer 5.4 Dose Conversion Factors 5.5 Dose Rate Logsheet
HP/O/B/ 1009/006 Page 6 of 6 5.6 Unit Vent Effluent Worksheet 5.7 Unit 1 & 2 Vent Sampling Schematics 5.8 Commitments for HP/O/B/1009/006
Unit Vent Normal to Remote Transfer Page 1 of 2 COMPARED WITH CONTROL COPY BY DATE:
1.1 Notify the affected Unit's Reactor Operator that they should receive a loss of flow alarm on the Unit Vent P&C sampling device while remote unit vent sampling takes place. { 39}
CAUTION:
Steps 11.1.1 through 1.1.1.5 may be eliminated if dose rates in the area of the normal vent sample point are prohibitive.
1.1.1 While monitoring general area and contact dose rates, secure normal unit vent continuous P&C as follows:
1.1.1.1 Locate the normal vent sample point. Unit I or Unit 2 (circle affected unit).
1.1.1.2 Record flowrate
..., and vacuum on the sample bags.
1.1.1.3 Turn off vacuum pump and record time on the sample bags.
1.1.1.4 Close Sample Supply valve located on column JJ-51 (Unit 1) or JJ-61 (Unit 2) (Enclosure 5.5). Leave the Sample Return valve open.
1.1.1.5 Remove P&C filters and place in sample bags. Retain normal vent samples for Count Room analysis, if dose rates permit.
1.1.2 Locate Remote Vent sample point, 767 Elevation, Column HH-53 (Unit 1) or FF-58 (Unit 2). Unit 1 or Unit 2 (circle affected unit).
1.1.3 Connect the sample train.
1.1.4 Verify gas bomb isolation valves open, if applicable 1.1.5 Close valve From Normal Pump Discharge. This will isolate the normal sample flow.
1.1.6 Open Vent Remote Supply valve 1.1.7 Open Vent Return valve 1.1.8 Start Remote sample pump and record start time..1 HP/0/B3/1009/006
.1 HP/O/B/1009/006 Unit Vent Normal to Remote Transfer Page 2 of 2 NOTE:
The sample volume used in the calculations on Enclosure 5.4 are derived from a 25 1pm flow rate at 5" Hg for 30 minutes. If you change these variables you will need to recalculate the volume.
1.1.9 Adjust flowrate on sample pump to 25 +/-5 lpm. Vacuum should read 5 +/-1" Hg. If vacuum gauge reading is less than required, verify that there is not a restriction in the flowpath (i.e., closed sample valves). { 19) 1.1.9.1 Record flowrate and vacuum 1.1.10 Record "Sample Number" and Sample On Date/Time" on Dose Rate Logsheet (Enclosure 5.5).
Performed By Date Unit 1 & 2 Remote Vent Sample Train Schematics RASP PUMP WOMK D=*oNWCTS CARTRIDGE 96cC FILTER GAS BOMB HOUSING ON REMOTE SAMPLER StPPLY LOW
.2 HP/O/B/10091006 Unit Vent Remote Sampling Page 1 of 2 767 Elev, HH-53 (U-i) FF-58 (U-2) Circle One COMPARED WITH CONTROL COPY BY DATE:
WARNING: High dose may be encountered on sample media.
1.1 Transport shielded containers with initial sample collection and thereafter as needed.
1.2 Collect a 30 minute sample (+/-6 min) or as directed by the Station Radiation Protection Manager or qualified designee.
1.3 Turn Remote sample pump off, allow vacuum to return to 0.
1.4 Close Vent Remote Supply valve.
1.5 Close Vent Return valve.
1.6 Record off time 1.7 Isolate gas bomb.
1.8 Disconnect sample train.
1.9 Set sample train away from sample lines to minimize dose and prevent interference with general area and return line dose rates.
- Use of the shielded containers may be necessary.
1.10 Connect new sample train.
1.11 Verify gas bomb isolation valves open, if applicable.
1.12 Open Vent Remote Supply valve.
1.13 Open Vent Return valve.
1.14 Start Remote sample pump and record start time 1.15 Adjust flowrate on sample pump to 25 +/-5 1pm. Vacuum should read 5 +/-1" Hg.
1.16 If vacuum gauge reading is less than required, verify that there is not a restriction in the flowpath (i.e., closed sample valves). { 19}
1.17 Record flowrate and vacuum
.2 HPIO/B/1009/006 Unit Vent Remote Sampling Page 2 of 2 767 Elev, HH-53 (U-i) FF-58 (U-2) Circle One 1.18 After a short purge time, obtain return line dose rates at point marked "Return Line Sample Point". Return line dose rate 1.19 Obtain general area dose rate approximately three feet away from unit vent lines.
General Area dose rate 1.20 If contact dose rate on removed sample >100 mr/hr, evaluate transporting sample back to the lab in shielded container(s).
1.21 Transport sample train to the Shift Lab, place under hood.
1.22 Go to step 4.6 in the body of this procedure.
Performed by Date Unit 1 & 2 Remote Vent Sample Train Schematics RASP PUh4P RETURN I./NE (2)
FTTNG QUICK DISCONNECT
'ERMANENTLY MOUNTED ON REMOTE SAMPLER SUPPLY LINE CARTRVGE 95 cc FILTER GAS BOMB HOUSIWG
.3 HP/O/B/ 1009/006 Unit Vent Remote to Normal Transfer Page 1 of 2 COMPARED WITH CONTROL COPY BY DATE:
WARNING: High dose may be encountered on Remote and Normal sample media.
Normal Vent Sample Point 1.1 If normal vent composite sampler was left running, evaluate condition of sample apparatus.
"* Pump may be damaged.
"* Pump power source breakers may have tripped (Unit-i: Panel iLl 1, breaker 25 / Unit-2:
Panel 2L10, breaker 24).
"* Tygon may be contaminated.
"* Shielded containers may be needed for transport.
"* This list is not all inclusive.
1.1.1 Record flowrate
, and vacuum 1.1.2 Turn off the sample pump and record the time 1.1.3 Close Sample Supply valve.
1.1.4 Remove the P&C filters.
Remote Vent Sample Point 1.2 Turn Remote sample pump off, allow vacuum to return to 0.
1.3 Close Vent Remote Supply valve.
1.4 Close Vent Return valve.
1.5 Open From Normal Pump Discharge.
1.6 Record off time 1.7 Isolate gas bomb.
1.8 Disconnect sample train.
0 Evaluate the need for transport in shielded container(s).
.3 Unit Vent Remote to Normal Transfer HP/O/B/ 1009/006 Page 2 of 2 Normal Vent Sample Point 1.9 Place new P&C in holder.
1.10 Open the Sample Supply valve.
1.11 Ensure Sample Return valve is open.
1.12 Start the sample pump.
1.13 Acquire a sample using the flowrate of = 20 LPM.
1.14 Record the time
, flowrate
,and vacuum on the P&C sample bags and leave the bags at the sample location.
1.15 If the vacuum gauge reading is > 4.5 "Hg, verify that there is not a restriction in the flow path (i.e., closed sample valves, etc.) { 19}
1.16 Notify the affected unit's Reactor Operator that remote sampling is complete and sample is in normal vent sampling configuration.
1.17 Verify loss of flow alarm cleared.
1.18 Transport sample(s) to the Shift Lab.
1.19 Go to 4.6 in the body of this procedure.
Performed by:
Date
.4 Dose Conversion Factors (DCF)
HP/O/B/1009/006 Page 1 of 1 Time (hrs)
Iodine Housing Particulate Housing Return Line After
( uCi mR)
"LG
/ mR Ci mr)
Shutdown c
rc
-_r___--_-c hr cchr
.0 5.9E-03 3.1E-2 5.20E-I
.25 6.4E-03 3.1E-2 5.20E-1
.5 7.OE-03 3.2E-2 5.20E-1 1
8.lE-03 3.3E-2 5.20E-1 1.5 9.3E-03 3.5E-2 5.20E-1 2
1.OE-02 3.7E-2 5.201-1 3
1.2E-02 4.1E-2 5.20E-1 4
1.4E-02 4.3E-2 5.20E-1 5
1.6E-02 4.3E-2 5.20E-1 8
2.OE-02 4.4E-2 5.20E-1 12 2.5E-02 4.4E-2 5.20E-1 16 2.9E-02 4.4E-2 5.20E-1 24 3.7E-02 4.4E-2 5.20E-1 30 4.4E-02 4.7E-2 5.20E-1 50 6.3E-02 4.7E-2 5.20E-1 100 L.OE-01 4.8E-2 5.20E-1 250 1.2E-01 5.0E-2 5.20G-1 500 1.2E-01 5.5E-2 5.20E-I 720 1.2E-01 5.8E-2 5.20E-1 Use the higher DCF value for intervals between time after shutdown.
(
HP/O/B/1009/006 Page 1 of I.5 Dose Rate Logsheet DOSE RATES (mR/hr)
SAMPLE SAMPLE ON SAMPLE OFF RETURN LINE GENERAL IODINE PART.
GAS NUMBER DATE/TIME DATE/TIME READING AREA HOUSING HOUSING BOMB S(Step 4.7)
(Step 4.7)_
(Step 4.7)
I I _
I _
_III
(.6 Unit Vent Effluent Worksheet DCF(I-) = Dose Conversion Factor for Iodine Housing DCF(PH) - Dose Conversion Factor for Particulate Housing DCF(RL) = Dose Conversion Factor for Return Line
(
HPIO/B/ 1009/006 Page 1 of 1 DR(IH)
= Dose Rate on Iodine Housing DR(PH)
= Dose Rate on Particulate Housing DR(RL)-GA
= Dose Rate on Return Line minus General Area Unit Vent Concentration Calculations Time After Shutdown
.(hrs)
Sample #
/.aCi / mR Iodine Concentration (pLCi/cc) uCi
'-R DCF(IH) puCiI mR Particulate Concentration (xCi/cc) =
-'h'c [_'r DCF(PH)
,uCi / mR mR Return Line Concentration (giCi/cc) 0.52
-'/-
X hr ForNole hr hr For Noble Gas DCF(RL)
DR(RL)-GA X
9.6E-5'
=tCi/cc X
9.6E-5'
=tCi/cc IC i/cc Unit Vent Activity Based on Count Room Analysis Grand Total Activity: Particulate = _iCi/cc Iodine = __Ci/cc Noble Gas = __
Ci/cc Collection Media Volume (65cc) 9.6E-5"
=
Sampled Volume (6.8E5cc)
- Sampled Volume (6.8E5cc) is derived from 25 lpm flow rate at 5" Hg for 30 minutes.
If the flow rate, vacuum, and/or sampling time time varies, the sample volume must be corrected.
mR x
hr DR(IH) mR x
hr DR(PH)
.7 Unit 1 & 2 Vents Sampling Schematics HP/O/B/ 1009/006 Page 1 of 1 Unit 1 76r' Column JJ-51 U-1 Vent U-1 Sample Sam Returm Z-Sample Return Mil. Sample Flow Device U-I Vent Return From Normal Puni? Discharge U-2 Vent Sample sV" v
U-2 76r' FF-58 Remote supply
~1
~~ItýZI4 From Normal Pump Discharge z
z 4
Unit 2 767" Column JJ-6i U-2Vem Renum
- Minp, Roten San am l Flw.eyc I
I PR&
l
.8 Commitments for HP/0/B/1009/006 LER 369/90-03 LER 369/09-08 PIR 1-M92-0506 HP/O/B/ 1009/006 Page 1 of I Sampling enclosures required in the field.
Observe and correct higher than expected vacuum on sample trains.
Notify U-I and U-2 Control Room Operators separately for alarms during sample changeout.
{16}
{19}
{39}I
(R04-01)
Duke Power Company PROCEDURE PROCESS RECORD (1) ID No. HP/IOB/1009/016 Revision No.
003 REPARATION
-(2) Station McGuire Nuclear Station (3) Procedure Title Distribution of Potassium Iodide Tablets in the Event of a Radioiodine Release (4) Prepared By Grayton Cayton Date February 27, 2002 (5) Requires NSD 228 Applicability Determination?
F] Yes (New procedure or revision with major changes) 0 No (Revision with minor changes)
L] No (To incorporate previously approved changes)
(6) Reviewed By Q
C (QR)
Date
-1,1o2 Cross-Disciplinary Review By (eR) NAm*
Date 1
I `10 2 Reactivity Mgmt. Review By (eR) NA L
Date 3 la O Mgmt. Involvement Review By (OPS Supt.) NA Z
Date 3 1-10z.
(7) Additional Reviews Reviewed By Date_
Reviewed By Date (8) Temporary Approval (if necessarty By (OSM) Date By (QR) Date (9) Approved By Date 0 -o0 PERFORMANCE (Compare with Control Copy every 14 calendar days while work is being performed.)
(10) Compared with Control Copy Date Compared with Control Copy Date Compared with Control Copy Date (11) Date(s) Performed Work Order Number (WO#)
COMPLETION (12) Procedure Completion Verification Dl Yes 1i NA Check lists and/or blanks initialed, signed, dated, or filled in NA, as appropriate?
[I Yes [I NA Required enclosures attached?
El Yes El NA Data sheets attached, completed, dated and signed?
[] Yes [I NA Charts, graphs, etc. attached, dated, identified, and marked?
L] Yes [I NA Procedure requirements met?
Verified By Date (13) Procedure Completion Approved Date (14) Remarks (Attach additional pages, if necessary.)
Form based on NSD 703 App D (Procedure Process Record)
Duke Power Company McGuire Nuclear Station Distribution of Potassium Iodide Tablets in the Event of a Radioiodine Release Reference Use IProcedure No.
HP/O/B/ 1009/016 Revision No.
003 Electronic Reference No.
MC0045G9
HP/O/B/1009/016 Page 2 of 6 Revision History (significant issues, limited to one page)
Rev 003 (04103/02) For documentation. This revision allows procedure to be accessed via NEDL.
HP/0/B!/1009/016 Page 3 of 6 Distribution of Potassium Iodide Tablets in the Event of a Radioiodine Release
- 1. Purpose 1.1 This procedure provides information necessary to distribute Active Potassium Iodide (KI) tablets to personnel in the event of a release of radioiodine resulting from emergency conditions. Also, it outlines storage and supply information to assure sufficient quality and quantity of thyroid blocking material.
1.2 The level of use for this procedure is "Reference Use".
- 2. References 2.1 NCRP Report No. 55; Protection of the Thyroid Gland in the Event of Releases of Radioiodine 1977 2.2 NCRP Report No. 65; Management of Persons Accidentally Contaminated with Radioiodine 1980 2.3 BRH Report; Recommendations of Thyroid Blocking EKI, HHS Pub. FDA 81-8158 2.4 SHIO/B/2001/001, Internal Dose Assessment
- 3. Limits and Precautions 3.1 Persons who are known to be allergic to KI or iodine shall NOT receive these tablets.
3.2 Nursing mothers who receive KI tablets shall be advised to use nutrient substitutes (ex.
milk or a formula) for children for the duration of the ten-day tablet use period.
3.3 Personnel shall be advised NOT to deviate from prescribed dosages and dosage rates.
3.4 Best results shall be achieved when KI tablets are administered prior to an exposure or immediately after an exposure (within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />). Administration as late as 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the exposure is of less value but still significant enough to justify the administering.
3.5 Discolored or disfigured tablets and bottles of KI with loose tops shall be discarded.
3.6 Hands of personnel shall be free from contamination prior to taking KI tablets.
- 4. Procedure 4.1 Responsibilities for Distribution 4.1.1 The Radiation Protection Manager, in conjunction with available medical advice, shall control the distribution of KI tablets.
HP/0/B/ 1009/016 Page 4 of 6 4.1.2 Station personnel suspected of having been in the affected area prior to detection and during the release, personnel present in the affected area, and personnel who shall enter the area while radioiodine is present shall be instructed by the Radiation Protection Manager to report immediately and register at a KI distribution area.
4.1.3 KI shall be distributed only to prevent a significant uptake of radioiodine. A "significant uptake" is defined as follows:
4.1.3.1 A significant amount of radioiodine exposure (both in-plant and off-site) is that amount taken into the body that would result in a Committed Dose Equivalent (CDE) of 25 rem or more to the thyroid. 25 rem CDE to the thyroid is equal to 1000 DAC-hrs of iodine exposure. Use Enclosure 5.4 to document expected DAC-hrs of exposure. IF it is expected that there will be 1000 DAC-hrs or greater, the use of KI is recommended.
4.2 Registration of Personnel Exposed to Radioiodine 4.2.1 WHEN personnel that have been notified by Radiation Protection arrive at a distribution area, record appropriate data per Enclosure 5.1.
4.2.2 The Radiation Protection Manager or his designee shall give one (1) tablet to each affected person and shall give instructions concerning the use of the tablets. Then, each affected person shall be issued one bottle containing nine (9) KI tablets along with the package insert which describes the use of the KI tablets (see Enclosure 5.2).
4.2.2.1 A sufficient quantity of small sample bottles shall be in emergency kits to permit ample distribution of tablets.
4.2.2.2 Tablets are to be taken only as directed. One (1) tablet per day for ten (10) days is the recommended dosage.
4.2.2.3 After the initial dose of KI, subsequent doses shall be taken on a daily basis. Tablets shall be taken as close to a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> time period as possible.
4.2.3 Tablets removed from full bottles of KI shall be stored in small plastic sample bottles. The expiration date on the bottle from which the tablets were taken and the name of the Radiation Protection representative shall be recorded on the small bottles. Tablets stored in small plastic sample bottles shall then be distributed to affected personnel.
HP/0/B/ 1009/016 Page 5 of 6 4.3 Thyroid Burden Analysis Following Radioiodine Exposure 4.3.1 All employees receiving KI tablets should receive a thyroid burden analysis.
IF the number of people involved render this step impractical, then the Count Room Supervisor shall draw a representative sample of persons listed on.1 who have received KI tablets.
4.3.1.1 Subsequent action involving thyroid burden analysis shall follow guidelines established in the System Radiation Protection Manual.
4.3.2 Records of thyroid burden analyses shall be maintained.
4.3.3 Thyroid burden analyses immediately after an accident could lengthen KI distribution time and cause confusion among personnel. Distribute KI before analyzing thyroid concentration.
4.4 Storage Requirements for KI Tablets 4.4.1 There are three major storage requirements to be observed:
4.4.1.1 Store in a temperature range of 68 to 77 degrees F.
4.4.1.2 Store in a low humidity area (avoid direct exposure to liquids).
4.4.1.3 Store in an area protected from exposure to light.
4.4.2 Upon receiving a shipment of KI, boxes shall be opened as soon as possible and the bottles examined to ensure that an airtight seal has been maintained.
Bottles shall be returned to the boxes, and the boxes shall be sealed shut so as to avoid exposure to light.
4.5 Shelf Life and Changeout of KI Tablets 4.5.1 Thyro Block TM tablet bottles are labeled with an expiration date from the factory. As tablets reach the expiration dates, they shall be discarded, unless a shelf life extension is authorized by the FDA.
4.5.2 Replacement tablets shall be ordered at least three (3) months prior to the date of expiration listed on the bottles of KI.
4.5.3 Upon receiving a shipment of KI tablets, ensure that old tablets are used before new tablets.
4.5.4 After a radioiodine emergency, the tablets in the small plastic sample bottles that were NOT distributed shall be discarded.
HP/0/B/ 1009/016 Page 6 of 6
- 5. Enclosures 5.1 Potassium Iodide Tablet Distribution Data Sheet 5.2 Package Insert for Thyro-BlockTM Tablets 5.3 KI Storage Location List and Distribution 5.4 DAC-Hour Determination
.1 Potassium Iodide Tablet Distribution Data Sheet HP/O/B/1009/016 Page 1 of 1 RP Badge Name Department Date & Time of Date & Time of Initial Number Suspected Exposure Issuance I
I
.2 Package Insert for Thyro-BlockTM Tablets HP/0/BI/1009/016 Page 1 of 2 Patent Package Insert For INDICATIONS THYROID BLOCKING IN A RADIATION EMERGENCY ONLY DIRECTIONS FOR USE Use only as directed by State or local public health authorities in the event of a radiation emergency.
DOSE Tablets:
ADULTS AND CHILDREN 1 YEAR OF AGE OR OLDER: One (1) tablet once a day. Crush for small children.
BABIES UNDER 1 YEAR OF AGE: One-half (1/2) tablet once a day. Crush first.
Take for 10 days unless directed otherwise by State or local public health authorities.
Store at controlled room temperature between 200 and 25'C (68'- 77'F). Keep container tightly closed and protect from light.
WARNING Potassium iodide should NOT be used by people allergic to iodide.
Keep out o the reach of children. In case of overdose or allergic reaction, contact a physician or the public health authority.
DESCRIPTION Each THYRO-BLOCKTM TABLET contains 130mg of potassium iodide.
Other ingredients:
Magnesium stearate, microcrystalline cellulose, silica gel, and sodium thiosulfate THYRO-BLOCK TM (POTASSIUM IODIDE)
(pronounced poe-TASS-e-um EYE-oh-dyed)
(abbreviated: KI)
TABLETS U.S.P.
TAKE POTASSIUM IODIDE ONLY WHEN PUBLIC HEALTH OFFICIALS TELL YOU. IN A RADIATION EMERGENCY. RADIOACTIVE IODINE COULD BE RELEASED INTO THE AIR. POTASSIUM IODIDE (A FORM OF IODINE) CAN HELP PROTECT YOU.
IF YOU ARE TOLD TO TAKE THIS MEDICINE, TAKE IT ONE TIME EVERY 24 HOURS.
DO NOT TAKE IT MORE OFTEN. MORE WILL NOT HELP YOU AND MAY INCREASE THE RISK OF SIDE EFFECTS. DO NOT TAKE THIS DRUG IF YOU KNOW YOU ARE ALLERGIC TO IODIDE. (SEE SIDE EFFECTS BELOW.)
.2 HP/O/B/1009/016 Package Insert for Thyro-Block TM Tablets Page 2 of 2 HOW POTASSIUM IODIDE WORKS Certain forms of iodine help your thyroid gland work right. Most people get the iodine they need from foods, like iodized salts or fish. The thyroid can "store" or hold only a certain amount of iodine.
In a radiation emergency, radioactive iodine may be released in the air. This material may be breathed or swallowed. It may enter the thyroid gland and damage it. The damage would probably NOT show itself for years. Children are most likely to have thyroid damage.
IF you take potassium iodide, it will fill-up your thyroid gland. This reduces the chance that harmful radioactive iodine will enter the thyroid gland.
WHO SHOULD NOT TAKE POTASSIUM IODIDE The only people who should NOT take potassium iodide are people who know they are allergic to iodide. You may take potassium iodide even if you are taking medicines for a thyroid problem (for example, a thyroid hormone or antithyroid drug).
Pregnant and nursing women and babies and children may also take this drug.
HOW AND WHEN TO TAKE POTASSIUM IODIDE Potassium Iodide should be taken as soon as possible after public health officials tell you. You should take one dose every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. More will NOT help you because the thyroid can "hold" only limited amounts of iodine. Larger doses will increase the risk of side effects. You will probably be told NOT to take the drug for more than 10 days.
SIDE EFFECTS Usually, side effects of potassium iodide happen when people take higher doses for a long time. You should be careful NOT to take more than the recommended dose or take it for longer than you are told. Side effects are unlikely because of the low dose and the short time you will taking the drug.
Possible side effects include skin rashes, swelling of the salivary glands, and "iodism" (metallic taste, burning mouth and throat, sore teeth and gums, symptoms of a head cold, and sometimes stomach upset and diarrhea).
A few people have an allergic reaction with more serious symptoms. These could be fever and joint pains, or swelling of parts of the face and body and at times severe shortness of breath requiring immediate medical attention.
Taking iodide may rarely cause overactivity of the thyroid gland, underactivity of the thyroid gland, or enlargement of the thyroid gland (goiter).
WHAT TO DO IF SIDE EFFECTS OCCUR IF the side effects are severe or if you have an allergic reaction, stop taking potassium iodide. Then, if possible, call a doctor or public health authority for instructions.
HOW SUPPLIED THYRO-BLOCKTm TABLETS (Potassium Iodide. U.S.P) are white round tablets, one side scored, other debossed 472 Wallace, each containing 130 mg potassium iodide. Available in bottles of 14 tablets (NDC 0037-0472-20).
WALLACE LABORATORIES Division of CARTER-WALLACE, INC.
Cranbury, New Jersey 08512 IN-0472-04 Rev. 5/98
.3 Potassium Iodine Location and Distribution List HP/0/BI/1009/016 Page 1 of 1 Cowan's Ford Dam Recovery Kit Cowan's Ford Dam Personnel Survey Kit Control Room Training & Technology Center Recovery Kit Training & Technology Center Personnel Survey Kit Environmental Survey Kits (4 kits)
RP Instrument Cal Lab South PAP Technical Support Center Kit Operations Support Center Kit TOTAL:
979 bottles (1)
(2)
(3)
(4)
(5)
(6)
(7)
(8)
(9)
(10) 470 bottles 2 bottles 150 bottles 150 bottles 2 bottles 4 bottles 1 bottle 150 bottles 25 bottles 25 bottles
.4 DAC-Hour Determination DAC (4ci/mI) 2E-8 1E-7 7E-7 Expected Exposure Time Hrs HP/O/B/1009/016 Page 1 of 1 DAC Hours X
X X
Total DAC-Hrs -III IF total DAC-hrs is 1000 or greater, the use of KI is recommended.
Conc (L*C*nI)
Nuclide 1-131 1-133 1-135
(R04-01)
Duke Power Company PROCEDURE PROCESS RECORD (1) ID No. HP/O/B/1009/024 Revision No.
002 "REPARATION (2) Station McGuire Nuclear Station (3) Procedure Title Personnel Monitoring for Emergency Conditions (4) Prepared By Grayden Cayton Date February 28, 2002 (5) Requires NSD 228 Applicability Determination?
Li Yes (New procedure or revision with major changes)
[
No (Revision with minor changes)
[
No (To incorporate previously approved changes)
(6) Reviewed By Ca,*d C -,q-(QR)
Date 3 0z1 c
Cross-Disciplinary Review By (QR) N Date 3
01 2 Reactivity Mgmt. Review By (QR) NA
__ Date 3 1 jo2.
Mgmt. Involvement Review By (OPS Supt.) NA_ýr_-
Date 3 i o2.
(7) Additional Reviews Reviewed By Date_
Reviewed By Date (8) Temporary Approval (if necessary)
By (OSM) Date By (OR) Date (9) Approved By
.¢-
4 Date
_L--/o Z_.._
PERFORMANCE (Compare with Control Copy every 14 calendar days while work is being performed.)
(10) Compared with Control Copy Date Compared with Control Copy Date Compared with Control Copy Date (11) Date(s) Performed Work Order Number (WO#)
COMPLETION (12) Procedure Completion Verification LI Yes [L NA Check lists and/or blanks initialed, signed, dated, or filled in NA, as appropriate?
EL Yes EL NA Required enclosures attached?
DI Yes El NA Data sheets attached, completed, dated and signed?
EL Yes [0 NA Charts, graphs, etc. attached, dated, identified, and marked?
[] Yes EL NA Procedure requirements met?
Verified By Date (13) Procedure Completion Approved Date (14) Remarks (Attach additional pages, if necessary.)
Form based on NSD 703 App D (Procedure Process Record)
Duke Power Company McGuire Nuclear Station Personnel Monitoring for Emergency Conditions Information Use Procedure No.
HP/O/B/1009/024 Revision No.
002 Electronic Reference No.
MC0095LZ I
HP/O/B/1009/024 Page 2 of 6 Revision History (significant issues, limited to one page)
Rev 002 (04/03/02) For documentation. This revision allows procedure to be accessed via NEDL.
HP/O/B/1009/024 Page 3 of 6 Personnel Monitoring for Emergency Conditions
- 1. Purpose 1.1 To provide personnel monitoring during a Site Evacuation due to a radiological emergency.
- 2. References 2.1 Nuclear System Directive 114, Site Assembly/Evacuation Process 2.2 HP/0/B/1009/016, Distribution of Potassium Iodide Tablets in the Event of a Radioiodine Release 2.3 SH/0/B/2001/003, Investigation of Skin and Clothing Contaminations 2.4 HP/0/B/1009/022, Accident and Emergency Response 2.5 SH/0/B/2000/004, Taking, Counting and Recording Surveys
- 3. Precautions and Limitations 3.1 Survey teams can be advised to don appropriate respiratory equipment based on assessed conditions.
3.2 If survey teams are expected to be exposed to 113, consult Reference 2.2 for a determination of whether the survey team should ingest Potassium Iodide Tablets.
3.3 Survey teams shall don protective clothing when contamination levels are expected to be
> 1000 dpm/100 cm2 [3y, > 20 dpm/100 cm 2 (X.
3.4 Survey teams shall wear TLD's and ED's (electronic dosimeters).
- 4. Procedure 4.1 Upon initiation of a Site Evacuation (Reference 2.1) due to a radiological emergency, Radiation Protection shall dispatch emergency personnel survey teams to the following locations.
4.1.1 North VAP Area (as needed)
- Emergency kit for the North VAP is located in the RP Instrument Lab.
4.1.2 South PAP Area
- Emergency kit for the South PAP is located in Room 158.
HP/O/B/1009/024 Page 4 of 6 4.1.3 Evacuation Facility (Cowan's Ford Dam)
- Emergency kits for Cowan's Ford Dam is located on the first level to the right in a room labeled "MNS Emergency kits".
4.1.4 Evacuation Facility (Tech. Training Center)
"* Emergency kits for the TTC are located on the first floor in the stairwell across from the canteen.
"* Both Evacuation Facilities will not necessarily be activated simultaneously.
4.2 Each location is equipped with an emergency kit containing the following (in addition to various miscellaneous items):
4.2.1 One Eberline E-520 or E-120 with HP-260 probe or equivalent instrument (supplemental equipment is in service at each PAP).
4.2.2 Four (4) particulate respirators.
4.2.3 Electronic Dosimeters 4.2.4 Six (6) sets of protective clothing.
4.2.5 Radiation boundary ribbon or rope and cautions signs with inserts.
4.2.6 Potassium Iodide tablets.
4.2.7 A copy of SU/O/B/2001/003, Investigation of Skin and Clothing Contaminations (Reference 2.3).
4.2.8 A copy of HPIO/B/1009/024, Personnel Monitoring for Emergency Conditions.
4.2.9 A copy of HP/OIBI10091022, Accident and Emergency Response (Reference 2.4).
4.2.10 One (1) case of disposable coveralls at each of the four (4) locations.
4.3 Upon reaching their predesignated locations the survey teams shall verify communications with the Operation Support Center Radiation Protection Supervisor and maintain open communications.
4.4 The North VAP and South PAP Area survey teams shall monitor all personnel and vehicles leaving via this area to insure there is no spread of contamination outside of the protected area.
HP/O/B/1009/024 Page 5 of 6 4.4.1 In the event that a vehicle and/or its passengers are found to be contaminated, the survey team shall:
4.4.1.1 Notify the OSC RP Supervisor. The OSC RP Supervisor shall in turn notify the TSC Radiation Protection Manager.
4.4.1.2 Dress the contaminated individual(s) in the appropriate protective clothing and isolate that individual(s) until proper decontamination can be accomplished.
4.4.1.3 Escort the contaminated person(s) to the contaminated change room for decontamination. If unable to return to the station, proceed to the Evacuation Facility (Technical Training Center or Cowans Ford Dam) for decontamination. Personnel shall be decontaminated per Reference 2.3.
4.4.1.4 Prevent movement of the vehicle especially from leaving the protected area.
4.4.1.5 When all personnel have cleared the area notify the OSC RP Supervisor and await instructions, i.e., a) proceed to the evacuation facility to assist or b) report back to the OSC.
4.5 The Evacuation Facilities survey teams shall stand by at the designated evacuation facility in preparation for monitoring incoming personnel in the event of a subsequent Site Evacuation.
4.5.1 In the event that an individual(s) or vehicle(s) is found to be contaminated, the survey team shall:
4.5.1.1 Notify the OSC RP Supervisor. The OSC RP Supervisor shall in turn notify the TSC Radiation Protection Manager.
4.5.1.2 Dress the contaminated individual(s) in the appropriate protective clothing and isolate that individual(s) until proper decontamination can be accomplished.
4.5.1.3 Escort the contaminated person(s) to the contaminated change room at McGuire. If unable to return to the contaminated change room at McGuire, use the showers at the Evacuation Facility, i.e.
Technical Training Center or Cowans Ford Dam. Personnel shall be decontaminated per Reference 2.3.
4.5.1.4 Post a Radiation Control Zone around the contaminated vehicle.
HP/O/B/1009/024 Page 6 of 6 4.5.1.5 Survey the area to determine the existence of further contamination.
4.5.1.6 Document all surveys per Reference 2.5.
4.6 Survey teams shall be supplemented, relieved, or secured as directed by the Radiation Protection Manager.
- 5. Enclosures N/A
(R04-01)
Duke Power Company PROCEDURE PROCESS RECORD (1) ID No. HP/O/B/1009/029 Revision No.
006
'REPARATION (2) Station (3) Procedure Title McGuire Nuclear Station Initial Response On-Shift Dose Assessment (4) Prepared By Grayden Cayton Date February 28, 2002 (5) Requires NSD 228 Applicability Determination?
El Yes (New procedure or revision with major changes)
[
No (Revision with minor changes)
[
No (To incorporate previously approved changes)
(6) Reviewed By (QR)
Date
-/S-02 Cross-Disciplinary Review By (QR) NA.
Date
-/S/"-'-6z_
Reactivity Mgmt. Review By (OR) N Date 4-/J.".
Mgmt. Involvement Review By (OPS Supt.) N Date (7) Additional Reviews Reviewed By Date Reviewed By Date (8) Temporary Approval (if necessary)
By (OSM) Date_
By (OR) Date_
(9) Approved By Date 6'
Z.._
PERFORMANCE (Compare with Control Copy every 14 calendar days while work is being performed.)
(10) Compared with Control Copy Date Compared with Control Copy Date Compared with Control Copy Date (11) Date(s) Performed Work Order Number (WO#)
COMPLETION (12) Procedure Completion Verification LI Yes El NA Check lists and/or blanks initialed, signed, dated, or filled in NA, as appropriate?
[E Yes D] NA Required enclosures attached?
El Yes El NA Data sheets attached, completed, dated and signed?
LI Yes 1] NA Charts, graphs, etc. attached, dated, identified, and marked?
f] Yes F-NA Procedure requirements met?
Verified By Date (13) Procedure Completion Approved Date (14) Remarks (Attach additional pages, ff necessary.)
Form based on NSD 703 App D (Procedre Process Record)
Duke Power Company McGuire Nuclear Station Initial Response On-Shift Dose Assessment Reference Use Procedure No.
HP/O/B/ 1009/029 Revision No.
006 Electronic Reference No.
MC0095KW I
HP/O/B/1009/029 Page 2 of 13 Revision History (significant issues, limited to one page)
Rev 006 (04/03/02) For documentation. This revision allows procedure to be accessed via NEDL.
HP/O/B/ 1009/029 Page 3 of 13 Initial Response On-Shift Dose Assessment
- 1. Purpose The purpose of this procedure is to provide on-shift Radiation Protection personnel a method for determining offsite dose to the public, and completing items 11 through 15 on the Emergency notification form, using Raddose-V. {68)
The level of use for this procedure is "REFERENCE USE".
- 2. References 2.1 Earth Tech, Raddose-V Operator's Manual.
- 3. Limits and Precautions 3.1 This procedure shall be performed upon declaration of an emergency classification and at the request of the Operations Shift Manager / Emergency Coordinator.
3.2 Raddose-V considers all releases to be at ground level.
3.3 Dose projections should be performed within the time frame specified by the Operations Shift Manager / Emergency Coordinator in order to make the required emergency notification.
3.4 Raddose-V will print the Emergency Notification Form (green sheet) only after a Forecast dose projection has been completed.
3.5 Refer to Enclosure 5.2 concerning back-up method for performing dose assessment during a loss-of-power situation or a printer failure.
3.6 It is acceptable to perform steps 4.2, 4.3, 4.4, and 4.16 out of sequence to allow timely completion of Emergency Notification forms.
3.7 This procedure may be performed in the RP Shift Lab or the TSC as needed.
- 4. Procedure 4.1 Obtain the following relevant unit information from Operations, when it is available:
4.1.1 Affected unit:
1 / 2 (circle one).
4.1.2 Date and time of reactor trip (
I 4.1.3 Actual or best estimate of release start time (
).
HP/O/B/ 1009/029 Page 4 of 13 4.1.4 IF leak in Auxiliary Building, affected unit VA exhaust filtration (on / off I NA) (circle one).
If leak in containment or annulus, affected unit VE exhaust filtration (on / off /
NA) (circle one).
4.1.5 IF S/G tube leak/rupture, affected S/G (partitioned / not partitioned) (circle one).
- This determination is made based on knowledge of the Steam Generator secondary side water level in relation to the top of the tube bundle.
4.1.5.1 Steam release in progress (yes / no).
4.1.5.2 Release duration Use 1 hr. default if release duration is not available.
0 Raddose-V will allow 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> as the minimum forecast time.
4.1.6 IF fuel assembly accident, record reactor shutdown date for that assembly.
4.1.7 Current emergency classification 4.1.8 Next emergency notification due by (date/time).
4.2 Obtain the following equipment:
4.2.1 IF needed, key #17 from Shift key box (TSC).
4.2.2 Calculator.
4.3 Verify operability of meteorological instrumentation through TSAIL prior to obtaining data from Control Room modules.
4.4 At the designated computers in the RP Shift LabITSC, power up the Raddose computer, monitor and Data Acquisition computer and monitor.
4.4.1 On the Data Acquisition computer, select the McGuire Desktop icon, select McGuire Process Data, then SDS, then Unit 1, Unit 2, or Simulator.
4.4.2 Type GD ERO-2. IF SDS data is not available or IF the data is suspect for any reason, obtain all necessary information on Enclosure 5.1 (average meteorological data and relevant source term data) from the Control Room. IF meteorological data is not available, use one of the following sources in order of sequence:
"* DPC Meteorological Lab (8-594-0341)
"* National Weather Service (1-800-268-7785).
"* Catawba Nuclear Station Control Room (8-831-2338)
HP/O/B/1009/029 Page 5 of 13 4.5 On the Raddose computer, select the DAS/Raddose-V icon. A dialog box will appear stating "DAS Workstation configuration" (EOF or TSC). Click on "OK" to access the DAS (Dose Assessment Software) desktop.
4.5.1 IF the workstation was not configured TSC:
At the DAS Desktop, click on FILE.
Click on DAS Configuration.
Click on TSC for Work Station Type and Production Mode.
Restart Raddose V for changes to take effect.
4.5.2 Select the icon for the affected unit.
4.5.3 Select Accident Mode (actual emergency) or Drill Mode (drills/exercises).
4.5.4 At the prompt, "Do you want to use automatic data from the network or manual data entry?", select Auto. IF Manual selected, Met and EMF data will be entered by performer.
4.6 At the Start-up Menu, select Begin New Incident. A pop-up message will display, "This erases all previous data. Click Yes to continue or No to abort." Select Yes.
4.7 At the Accident Scenario definition screen, edit the reactor trip and release times. Current date and time from the computer will appear as the reactor trip and release date and time.
4.7.1 Edit the reactor trip time, if known. IF a reactor trip has not occurred or the reactor trip time is not known, no editing of the time is required.
4.7.2 Edit the release time. IF theactual release time is not known, input a time 15 minutes previous to the current time. Example: the current time is 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br />.
The correct input would be 0745.
4.7.3 Enter the operator's initials.
4.7.4 Select Accept to accept this data.
4.8 At the Main Menu screen, select Enter/Edit Meteorological Data.
4.8.1 The Meteorological Data Input screen will appear. IF AUTO was selected in step 4.5.4, data will be auto retrieved. IF MANUAL was selected in step 4.5.4, Raddose-V provides the following pop-up message: "No automatic meteorological data available. Enter data manually." Select OK.
4.8.2 IF AUTO was selected, use SDS to verify that the data on the Meteorological Input Screen is correct.
4.8.3 IF AUTO was selected, edit any fields which do not agree with SDS data. IF MANUAL was selected, enter Wind Speed, Wind Direction, Delta Temperature, Air Temperature and Precipitation from SDS or from Enclosure 5.1.
HP/0/B/1009/029 Page 6 of 13 4.8.3.1 Select the data field with a single mouse click.
4.8.3.2 Ensure the field is highlighted, (selected field turns gray).
4.8.3.3 Type in the correct data.
4.8.3.4 Ensure mixing height is not zero.
Default Values are:
Dec, Jan, Feb - 1000 Mar, Apr, May - 1700 Jun, Jul, Aug - 1800 Sept, Oct, Nov - 1400 4.8.4 Verify the data in the time step is correct. When editing is complete, select Accept at the bottom of the screen.
4.9 At the Main Menu, select Enter/Edit Source Term Data.
4.9.1 The Source Term Data Input screen will appear. ]F AUTO was selected in step 4.6.4, data will be auto retrieved. IF MANUAL was selected in step 4.5.4, Raddose-V provides the following pop-up message: "No automatic source term data available. Enter data manually." Select OK.
4.9.2 At the Source Term Data Input screen, select the Accident Type data field for Path 1. Click on the highlighted area to display the Accident Menu.
4.9.3 Using Enclosure 5.3 determine the accident type and select by placing the cursor on the accident type and double clicking.
IF LOCA selected, go to step 4.9.4 IF SGTR selected, go to step 4.9.5 IF LOCO selected, go to step 4.9.6 IF Fuel selected, enter Fuel Assembly age (Days): go to step 4.9.7 4.9.4 LOCA (G) (M): Select the NG Method data field. Click on the highlighted area to display the Noble Gas Release Rate Method Menu.
HP/O/B/1009/029 Page 7 of 13 4.9.4.1 Select unit vent EMF pathway from below with a double mouse click.
EMF36L: Select UVIL or UV2L EMF36H: Select UVIH or UV2H EMF36HH: Select UV1HH or UV2HH 4.9.4.2 A pop-up message requesting Filter Status will appear ON/OFF. IF VE exhaust filter status is not known or phase B isolation not initiated, select OFF. Click on OK.
4.9.4.3 IF AUTO was selected, use SDS to verify that the data on the Source Term Data Input Screen is correct.
4.9.4.4 IF AUTO was selected, edit any fields which do not agree with SDS.
IF MANUAL was selected, enter Monitor Reading and Unit Vent Flow Rate from SDS or from Enclosure 5.1.
Select the data field with a single mouse click.
Ensure the field is highlighted, (selected field turns gray).
Type in the correct data.
4.9.4.5 For Path 2 select the Accident Type data field and click on the highlighted area to display the Accident Type Menu. Select the same accident type as Path 1.
4.9.4.6 Select the NG Method data field and click on the highlighted area to display the Noble Gas Release Rate Method Menu.
A. Select containment EMF pathway from below with a double mouse click.
EMF39L: Select CONL EMF39H: Select CONH EMF51A or 51B: Select CONHH (Use if 391139H is isolated)
B.
A pop-up screen will appear to determine containment leakage.
Enter containment bypass fraction = 0.07 Select ice condenser = recire Select holdup time < 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Select sprays ON/OFF = ON if >3 psi or phase B initiated.
Select "Containment Pressure and Hole Size" Select "Design Basis Leakage (0.3%/day @ 15 psig)"
Enter containment pressure =
Use SDS to verify that containment pressure is correct.
Select OK.
HPIO/B/ 1009/029 Page 8 of 13 4.9.4.7 IF AUTO was selected, edit any fields which do not agree with SDS.
IF MANUAL was selected, enter Monitor Reading from SDS or from Enclosure 5.1.
4.9.4.8 Go to step 4.9.8.
4.9.5 SGTR (G) (M): Select the NG Method data field and click on the highlighted area to display the Noble Gas Release Rate Method Menu.
4.9.5.1 Select the affected steamline monitor (IEMF-24, 25, 26, 27 or 2EMF-10, 11, 12, 13) using a double mouse click.
4.9.5.2 A pop-up message requesting Steam Generator partitioned/not partitioned will appear. IF partitioning status is not known, select partitioned. Select OK.
4.9.5.3 IF AUTO was selected, use SDS to verify that the data on the Source Term Data Input Screen is correct.
A. IF AUTO was selected, edit any fields which do not agree with SDS. IF MANUAL was selected enter Monitor Reading and Flow Rate from SDS or from Enclosure 5.1.
Select the data field with a single mouse click.
Ensure the field is highlighted, (selected field turns gray).
Type in the correct data.
B.
Ensure the flow rate is not zero. IF the flow rate is zero, manually input the default value of 2.09E5 pounds mass steam per hour.
4.9.5.4 For Path 2 select the Accident Type data field and click on the highlighted area to display the Accident Menu. Select the same accident type as Path 1.
4.9.5.5 Select the NG Method data field and click on the highlighted area to display the Noble Gas Release Rate Method Menu.
A. Select unit vent EMF pathway from below EMF36L: Select UV1L or UV2L EMF36H: Select UV1H or UV2H EMF36HH: Select UV1HH or UV2HH B.
A pop up message requesting Steam Generator partitioned/not partitioned will appear. IF partitioning status is not known select Partitioned. Select OK.
HP/O/B/1009/029 Page 9 of 13 C. IF AUTO was selected, use SDS to verify that the data on the Source Term Data Input Screen is correct.
D. IF AUTO was selected, edit any fields which do not agree with SDS. IF MANUAL was selected, enter Monitor Reading and Flow Rate from SDS or from Enclosure 5.1.
Select the data field with a single mouse click.
Ensure the field is highlighted, (selected field turns gray).
Type in the correct data.
4.9.5.6 Go to step 4.9.8.
4.9.6 LOCO (G) (M): Select the NG Method data field and click on the highlighted field to display the Noble Gas Release Rate Menu.
4.9.6.1 Select unit vent EMF pathway from below by double click:
EMF36L: Select UVIL or UV2L EMF36H: Select UV1H or UV2H EMF36HH: Select UV1HH or UV2HH 4.9.6.2 A pop-up message requesting filter status will appear ON/OFF. IF VA exhaust filter status is not known, select OFF.
4.9.6.3 IF AUTO was selected, use SDS to verify that the data on the Source Term Data Input Screen is correct. IF MANUAL was selected in step 4.5.4, Raddose-V provides the following pop-up message: "No automatic monitor data available. Enter data manually." Select OK.
4.9.6.4 IF AUTO was selected, edit any fields which do not agree with SDS.
IF MANUAL was selected, enter Monitor Reading and Flow Rate from SDS or from Enclosure 5.1.
Select the data field with a single mouse click.
Ensure the field is highlighted, (selected field turns gray).
Type in the correct data.
4.9.6.5 Go to step 4.9.8.
4.9.7 FUEL: A Fuel Assembly Age Box will appear requiring the user to enter the fuel assembly age in days. Enter the Fuel Assembly Age in days.
Select the NG Method data field and click on the highlighted area to display the Noble Gas Release Rate Menu.
HP/OB/ 1009/029 Page 10 of 13 4.9.7.1 Select unit vent EMF pathway from below.
EMF36L: Select UVIL or UV2L EMF36H: Select UV IH or UV2H EMF36HH: Select UVIHH orUV2HH 4.9.7.2 A pop-up screen will appear requesting filter status ON/OFF and pool scrubbing. Select filter "ON" unless the VF filters are known to be bypassed and select "POOL".
4.9.7.3 IF AUTO was selected, use SDS to verify that the data on the Source Term Data Input Screen is correct.
4.9.7.4 IF AUTO was selected, edit any fields which do not agree with SDS.
IF MANUAL was selected, enter Monitor Reading and Flow Rate from SDS or from Enclosure 5.1.
Select the data field with a single mouse click.
Ensure the field is highlighted, (selected field turns gray).
Type in the correct data.
4.9.7.5 Go to step 4.9.8.
4.9.8 Review the data in the current time step. IF no fields require editing, or editing is complete, select Accept at the bottom of the screen.
4.10 At the Main Menu, select Emergency Classification.
4.10.1 Select the appropriate emergency classification.
4.10.2 Select Continue.
4.11 At the Main Menu, select Perform Calculations.
4.11.1 A 10-mile EPZ Map screen will be displayed after Raddose-V calculates the data in the current time step. IF the Emergency Classification selected in 4.10.1 was General Emergency, select GE PARs.
4.11.2 Select Continue at the bottom right of the screen.
4.12 At the Output Menu, select Continue Calculations.
4.13 At the Main Menu, select Perform Forecast.
4.13.1 A Forecast Mode screen will appear.
4.13.1.1 Select the applicable Status of the Emergency Release.
4.13.1.2 Select "New" for the Status of the Projected Offsite Dose.
HP/O/B/I1009/029 Page 11 of 13 4.13.1.3 A Forecast Period box will appear requiring the user to enter the forecast period in hours. IF the release duration is not known, delete the highlighted 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> default value and input 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> as the forecast period. Select OK.
4.13.2 A pop-up message will display, "Note: forecast will use the meteorological and source term data from current step. Continue?" Select OK.
4.13.3 Raddose-V will take 10 to 30 seconds to calculate the projection. The 10-mile EPZ Map screen will appear when calculations are complete.
4.13.3.1 IF the Emergency Classification selected in 4.10.1 was General Emergency, select GE PARs.
4.13.3.2 Select Continue at the bottom right of the screen.
4.13.4 A pop-up message will display, "Do you want to save PAZ's identified in Forecast Mode for evacuation?" Select No.
4.14 At the Output Menu, select Go to Report Menu.
4.15 At the Report Menu, select Print Emerg Notification, Summary Report.
4.15.1 Raddose will fill in items 10 through 15 on the "Emergency Notification (Green)
Form". Review items 10 through 15. If no recommended Protective Actions have been determined in item 15, place an "X" in box A.
0 Items B and C will be identified by Raddose if dose projections indicate evacuation or sheltering is necessary. The affected zones (PAZ' s) will also be listed in items B and C.
IF printer fails, go to Enclosure 5.2 and perform steps 1.8 through 1.10.
4.15.2 Deliver the printed Emergency notification form (including dose comparison sheet) to the Operations Shift Manager / Emergency Coordinator.
4.15.3 Retain the printed Summary Sheet.
4.15.4 Select Return to Output Menu.
4.15.5 Go to step 4.16 for additional projections. IF no other projections are necessary:
4.15.5.1 Select Return to Main Menu.
A pop-up message will display, "You just completed a forecast.
Remember to check meteorological and source term data." Select OK.
4.15.5.2 Select Go to Start-up Menu
HP/O/B/ 1009/029 Page 12 of 13 4.15.5.3 Select Exit Raddose-V at this point. Go to step 4.22.
4.16 IF SDS data is not available or if the data is suspect for any reason, obtain all necessary information on Enclosure 5.1 (average meteorological data and relevant source term data) from the Control Room.
4.17 At the Output Menu, select Continue Calculations.
4.17.1 A pop-up message will display, "You just completed a forecast. Remember to check the meteorological and source term data for current information." Select OK to acknowledge.
4.18 At the Main Menu, select Enter/Edit Meteorological Data.
NOTE:
Time steps should be added as needed to as close as possible to the ENF due time to ensure current dose projections are communicated.
4.18.1 The Meteorological Data Input screen will appear. IF AUTO was selected in step 4.5.4, Raddose provides the following pop-up message: "Do you want to add a new time step for [previous time step plus 15 minutes]?" Select Yes. Data will be auto retrieved. IF MANUAL was selected in step 4.5.4, Raddose-V provides the following pop-up message: "No automatic meteorological data available.
Enter data manually."
4.18.2 IF AUTO was selected, use SDS to verify that the data on the Meteorological Input Screen is correct. IF MANUAL was selected, a pop-up message will display, "Do you want to add a new time step by copying data from [previous time step plus 15 minutes]?" Select Yes.
4.18.3 IF AUTO was selected, edit any fields which do not agree with SDS date. IF MANUAL was selected, enter Wind Speed, Win Direction, Delta Temperature, Air Temperature and Precipitation from SDS or from Enclosure 5.1.
Select the data field with a single mouse click.
Ensure the field is highlighted, (selected field turns gray).
Type in the correct data.
4.18.4 Verify the data in the time step is correct. When editing is complete, select Accept at the bottom of the screen.
HP/O/B/ 1009/029 Page 13 of 13 4.19 At the Main Menu, select Enter/Edit Source Term Data.
NOTE:
Time steps should be added as needed to as close as possible to the ENF due time to ensure current dose projections are communicated.
4.19.1 The Source Term Data Input screen will appear. IF AUTO was selected in step 4.5.4, Raddose provides the following pop-up message: "Do you want to add a new time step for [previous time step plus 15 minutes]?" Select Yes. Data will be auto retrieved. IF MANUAL was selected in step 4.5.4, Raddose-V provides the following pop-up message: "No automatic source term data available. Enter data manually." Select OK.
4.19.2 IF AUTO was selected, use SDS to verify that the data on the Source Term Data Input Screen is correct. IF MANUAL was selected, a pop-up message will display, "Do you want to add a new step by copying data from the [previous time step plus 15 minutes]?" Select NO. Click on ADD NEW STEP.
4.19.3 Return to step 4.9.2.
4.20 Continue to Perform Dose Projections, as directed by OSM/EC or until Duty Dose Assessment personnel are on station in the TSC.
4.21 At the Main Menu, select Start-up Menu then select Exit Raddose-V to exit the program.
4.22 Complete all procedure sign-offs. Route the completed Procedure Process Record, printed Summary sheets from each Raddose-V run, if applicable, and Enclosure 5.1 to Radiation Protection Staff.
- 5. Enclosures 5.1 Manual Input Data Collection 5.2 Back-up Computer Operation (TSC) 5.3 Accident Type 5.4 Commitments for HP/O/B/1009/029
.1 Manual Input Data Collection METEOROLOGICAL DATA COLLECTION (Obtain Average Data)
HP/O/B/1009/029 Page 1 of I Upper Wind Lower Wind Speed Direction Delta Temp Air Temperature Precipitation (mph)
(deg from N)
(deg C)
(deg C)
(diff/1 hr)
Date I Time AVG LWS AVG UWD AVG D/T AVG AMB PRE DIF SOURCE TERM DATA COLLECTION
- Affected Unit Vent
Percent Flow Actual Date/Time Steamline (mR/hr)
(cpm) (R/Hr)
(R/Hr)
Rate Flow Rate 188,748 cf-n x percent unit vent flow = actual flow rate
- record EMF used in space provided Signature:
.2 HP/O/B/1009/029 Back Up Computer Operation Page 1 of I
- 1.
Operation of Backup Laptop Computer NOTE:
This computer shall be used only when no other dose assessment computers are functional.
1.1 In the TSC Dose Assessment area, open the wall cabinet containing the Raddose Back-up Computer. The key for the wall cabinet is in the Dose Assessment cabinet.
1.2 Remove the laptop and place on the desk under the cabinet. Do not attempt to remove the attached security cable.
1.3 Connect the laptop to the LAN (yellow cable to the right side of the computer).
1.4 Turn on the computer by pushing the power switch (on the left side) forward.
1.4.1 The computer will display the following message:
"Starting Windows 95 Windows cannot determine what configuration your computer is in.
Select on the following:....
1.4.2 IF the LAN is available, enter "2" for Lan connected.
1.4.3 IF the LAN is NOT available, disconnect the yellow Ian connection from the right side of the computer and enter 1 for not Lan connected.
1.5 When prompted, enter your user ID and personal domain password.
1.6 Select the Raddose-V icon.
1.7 Go to step 4.4 in HP/O/B/1009/029. Perform step 4.5 through 4.14. After performing the required steps, proceed to 1.8.
1.8 At the Report Menu, select Display Green Form.
1.8.1 Review items 10 through 15 on the screen.
1.9 Transfer information from screen to blank Emergency Notification Form (blank sheets located in dose assessment area cabinet) and deliver to the OSM/EC. Communicate the information by phone if physical delivery is not possible. Click on SAVE.
1.10 Perform 4.15.4 through 4.20, as necessary.
1.11 When does assessment is completed, turn off the back-up computer, disconnect the modem line and place the computer back in the cabinet. Lock the cabinet and return key to dose assessment cabinet.
.3 Accident Type HP/O/B/1009/029 Page 1 of 1 Pathways Accident Type Inside Containment LOCA
- LOCAG **
LOCAM
- Containment Bypass Leakage (EMF39L, 39H, 51A, 51B)
Unit Vent (EMF36L, 36H, 36HH)
Outside Containment or Annulus LOCO
- LOCOG **
LOCOM***
Unit Vent (EMF36L, 36H, 36HH)
S/G Tube Rupture SGTR*
SGTRG**
SGTRM ***
Fuel Unit Vent (EMF36L, 36H, 36HH)
Main Steam Lines (EMF24, 25, 26, 27 for Unit 1)
(EMF10, 11,12,13 for Unit 2)
Unit Vent (EMF36L, 36H, 36HH)
(Use the same pathway for Fuel accidents whether they occur in containment or in the Spent Fuel Pool.)
- Normal Activity
- Gap Activity Melt Activity
(
(
O-M-97-0019.4 Commitments for HP/O/B/1009/029 HP/0/B/ 1009/029 Page 1 of 1 P is required to maintain n-shift capability to assess otential does to the public om radiological releases iat may occur during an ccident 68