ML031960127
| ML031960127 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 06/24/2003 |
| From: | Susquehanna |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML031960127 (115) | |
Text
Jun. 24, 2003 Page 1 of 1 MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2003-29394 rhz INFORMATIO 0 ame:> C XOSE M E2MPL#:28401 CA#:0363 A 2 Pho 254-3194 TRANSMITTAL INFORMATION:
TO: L rev_ lo 06/24/2003 LOCATION: DOCUMENT CONTROL DESK FROM: NUCLEAR RECORDS DOCUMENT CONTROL CENTER (NUCSA-2)
THE FOLLOWING CHANGES HAVE OCCURRED TO THE HARDCOPY OR ELECTRONIC MANUAL ASSIGNED TO YOU:
105 - 105 - TSC DOSE CALCULATOR: EMERGENCY PLAN-POSITION SPECIFIC PROCEDURE REMOVE MANUAL TABLE OF CONTENTS DATE: 04/16/2003 ADD MANUAL TABLE OF CONTENTS DATE: 06/23/2003 CATEGORY: PROCEDURES TYPE: EP ID: EP-PS-105 REPLACE: REV:15 REPLACE: REV:15 UPDATES FOR HARD COPY MANUALS WILL BE DISTRIBUTED WITHIN 5 DAYS IN ACCORDANCE WITH DEPARTMENT PROCEDURES. PLEASE MAKE ALL CHANGES AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX UPON RECEIPT OF HARD COPY. FOR ELECTRONIC MANUAL USERS, ELECTRONICALLY REVIEW THE APPROPRIATE DOCUMENTS AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX.
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Tab 2 EP-PS-1 05-2 EMERGENCY ORGANIZATION CONTROL ROOM EMERGENCY DIRECTOR (SHIFT MANAGER) l l l l~~~~~~~~~
EMERGENCY PLAN SHIFT TECHNICAL NRC OPERATORS COMMUNICATOR(S)
COMMUNICATOR ADVISOR (STA)
EP-AD-000-406, Revision 16, Page 1 of 3
(: (; (
Tab 2 EP-PS-1 05-2 TSC ORGANIZATION EMERGENCY DIRECTOR*
l . .~~~~~~~~~~~~~~~~~~~~~
Operations 3 >litr RadProtl Coordinator AdminStaff oordiator*Coordinator*
I I I I HPN TSC Severe Accident Damage Control Shift Manager Communicator Communicators Management Team Coord.*
1Communicator* Coordinator TSC Dose Calculator l
I TSC Radio Communicator F-H HP Specialist Rad Assess Staff I L I, Additional:
I IMaintenance I Coordinators F-H Tech Support Coordinator I I.
Rad Staff, l Chemistry I OSC Coordinator I Coordinator Proposed NRC Rev. 5-02 Susquehanna Steam Electric Station Non-Operations Core Thermal Units I and 2 Support Personnel (9) H Hydraulic Engineer Emergency Plan Ref. Sec. 6.2.12 TSC ORGANIZATION 9 report @ 60 minutes FIGURE 8.2 Non-Operations Support Personnel Mechanical Ref. Sec. 6.2.12 l1 Engineer I 5 report @ 90 minutes HI -Engineering Designates minimum requirements In accordance with Table 6.1 for 60-minute response. -d Support I
-- Individuals
- may be located Inthe OSC, TSC, or Field.
- Designates positions required for TSC activation.
EP-AD-000-406, Revision 16, Page 2 of 3
( (
Tab 2 EP-PS-1 05-2 EOF ORGANIZATION EOF SUPPORT SUPERVISOR*
ENVIRONMENTAL SAMPLING TEAM Proposed NRC Rev. 5-02 Susquehanna Steam Electric Station Units 1 and 2 Emergency Plan EOF ORGANIZATION MOC Designates minimum requirements in accordance with Table 6.1 for 90 minute response. ADMINISTRATIVE FIGURE 6.3 COORDINATOR
- Designates positions required for EOF activation.
EP-AD-000-406, Revision 16, Page 3 of 3
Tab 3 EP-PS-1 05-3 RADIOLOGICAL DOSE ASSESSMENT PHONE LOG This form is intended for communication of dose assessment results from the TSC to the EOF (or EOF to TSC) when a facility is unable to transmit a copy of the MIDAS DOSE ASSESSMENT
SUMMARY
SHEET. HIGH PRIORITY items (1-6) are required inputs for the dose assessments. LOW PRIORITY items (7-10) are highly desired but not essential. The LOW PRIORITY items may be omitted if time constraints exist.
HIGHPRIORITY
- 1. CURRENT (15) MINUTE CALCULATION TIME PERIOD DATE TIME 1 -1 1
- 2. I .-UNITS, ['l EPB(MREM)Y- .- 2MILE MREM)X; l: 10MILE REM)
I TEDE I _. I THYCDE l
- 3. j :DATE l TIME - j- REACTOR SHUTDOWN START OF RELEASE
- 4. ACCIDENT MENU SELECTION o MENU B: FORWARD CALCULATIONS OR 0 MENU G: BLOWOUT PANEL CALCULATIONS (MONITORED RELEASE or BLOWOUT PANEL CALCULATION) o MENU E-W: BACK CALCULATIONS FIELD MONITOR PARAMETER SELECTION l FIELD MONITOR READING (MR/HR)
DISTANCE FROM PLANT (MILES)
IODINE CARTRIDGE I ] NET CPM l lLCi/cc l J lDEFAULT MIX
- 5. SOURCE TERM CHARACTERIZATION BLOWOUT PANEL LIFTED:
o ATWS O NORMAL RX COOLANT ACTIVITY 13 RCIC PUMP ROOM o LOCA (RX DP-NO FD) HPCI PUMP ROOM o LOCA (CLAD FAILURE) 0 HPCI/RCIC ROUTING AREA O LOCA (FUEL MELT) RWCU PENETRATION ROOM O FUEL HANDLING ACCIDENT 0 RB/TB MAIN STEAM TUNNEL
- 6. (REMAINING) DURATION OF RELEASE I J (MINUTES)
EP-AD-000-099, Revision 1, Page 1 of 2
Tab 3 EP-PS-105-3 LOW PRIORITY
- 7. :G-:uTE-TOTALRELEASERFATES ~-:- Measured or Default SITE
- / TOT : -h RATES. . ~
- iAL RELEASE NOBLE GAS 1-131 PARTICULATES
- 8. PROJECTION TIME (IF OTHER THAN 6 HOURS)
- 9. ^--- ! 1. >fi I<
- ETIDATA --i < i . I 10mWINDSPEED l l(MPH) 10 m WIND DIRECTION (DEG FROM1-STABILITY CLASS (DEG C)
RAIN (N/15 MINUTES)
- 10. - -M. - ::EPB DOSE RATES 5 : : -0 C - -
MREM/HR SECTOR EDE I CDE EP-AD-000-099, Revision 1, Page 2 of 2
Tab 6 EP-PS-105-6 EMERGENCY CLASSIFICATION CHECK E 1.0 TIMING OF CLASSIFICATION 0 1.1 UNUSUAL EVENT An UNUSUAL EVENT shall be declared within 15 minutes of having information necessary to make a declaration.
1 1.2 ALERT An ALERT shall be declared within 15 minutes of having Sformation necessary to make a declaration.
0 1.3 SITE AREA EMERGENCY A SITE AREA EMERGENCY shall be declared within 15 minutes of having information necessary to make a declaration.
0 1.4 GENERAL EMERGENCY A GENERAL EMERGENCY. shall be declared within 15 minutes of having information necessary to make a declaration.
EP-AD-000-200, Revision 19, Page 1 of 38
Tab 6 EP-PS-105-6 CLASSIFICATION OF EMERGENCY CONDITIONS USE OF EMERGENCY CLASSIFICATION MATRIX NOTE: CONFIRM THAT INDICATORS AND/OR ALARMS REFLECT ACTUAL CONDITIONS PRIOR TO TAKING ACTION BASED ON THE INDICATOR OR ALARM.
The matrix is worded in a manner that assumes parameter values indicated are the actual conditions present in the plant.
The matrix is designed to make it possible to precisely classify an abnormal occurrence into the proper emergency classification based on detailed Emergency Action Level (EAL) descriptions.
It is impossible to anticipate every abnormal occurrence. Therefore, before classifying any abnormal occurrence based on the EALs in the matrix, one should verify that the general conditions prevalent in-plant and offsite meet the general class description of the emergency classification. In addition, prior to classification, one should be aware of the ramifications in-plant and particularly offsite of that classification. Special consideration of offsite consequences should be made prior to declaring a GENERAL EMERGENCY.
EP-AD-000-200, Revision 19, Page 2 of 38
Tab 6 EP-PS-105-6 CLASS DESCRIPTIONS UNUSUAL EVENT - Events that are occurring or have occurred which indicate a potential degradation of the level of safety of the plant.
No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety systems occurs.
ALERT - Events that are occurring or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant. Any releases are expected to be limited to small fractions of the EPA Protective Action Guideline exposure levels.
SITE AREA EMERGENCY - Events that are occurring or have occurred which involve actual or imminent major failures of plant functions needed for protection of the public. Any releases are not expected to exceed EPA Protective Action Guideline exposure levels except inside the emergency planning boundary.
GENERAL EMERGENCY - Events that are occurring or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity. Expectation is that releases will exceed EPA Protective Action Guideline exposure levels beyond the emergency planning boundary.
EP-AD-000-200, Revision 19, Page 3 of 38
Tab 6 EP-PS-1 05-6 CATEGORY INDEX TO THE MATRIX FOR THE CLASSIFICATION OF EMERGENCY CONDITIONS TABLE OF CONTENTS CATEGORY EVENT PAGE I AIRCRAFT/TRAIN ACTIVITY ............................................. 5 2 CONTROL ROOM EVACUATION ............... .............................. 6 3 FUEL CLADDING DEGRADATION ................. ............................ 7 4 GENERAL.................................................................................................... 10 5 INJURED/CONTAMINATED PERSONNEL ............................................. 11 6 IN-PLANT HIGH RADIATION ............................................. 12 7 LOSS OF AC POWER ............................................. 13 8 LOSS OF CONTROL ROOM ALARMS AND ANNUNCIATORS ................... 14 9 LOSS OF DC POWER ............................................. 15 10 LOSS OF DECAY HEAT REMOVAL CAPABILITY .................................... ;.16 11 LOSS OF REACTIVITY CONTROL ................................... 17 12 LOSS OF REACTOR VESSEL INVENTORY ................................... 19 13 NATURAL PHENOMENA ................................... 21 14 ONSITE FIRE/EXPLOSION ................................... 23 15 RADIOLOGICAL EFFLUENT ................................... 25 16 SECURITY EVENT ............ 29 17 SPENT FUEL RELATED INCIDENT ................................ 31 18 STEAM LINE BREAK ................................ 33 19 TOXIC/FLAMMABLE GASES ................................. 36 20 TECHNICAL SPECIFICATION SAFETY LIMIT ................................ 37 21 DRY FUEL STORAGE ................................. 38 EP-AD-000-200, Revision 19, Page 4 of 38
Tab 6 EP-PS-1 05-6 I - AIRCRAFT/TRAIN ACTIVITY UNUSUAL EVENT EAL# 1.1 Aircraft crash or train derailment onsite as indicated by:
Visual observation or notification received by control room operator.
ALERT EAL# 1.2 Aircraft or missile strikes a station structure as indicated by:
Direct observation or notification received by control room operator.
SITE AREA EMERGENCY EAL# 1.3 Severe damage to safe shutdown equipment from aircraft crash or missile impact when not in cold shutdown, determined by:
(A and B and C)
A. Direct observation or notification received by control room operator.
and B. Shift Supervisor evaluation.
and C. Reactor Coolant temperature greater than 2000 F as indicated on Panel 1C651 (2C651).
GENERAL EMERGENCY EAL# 1.4 None.
EP-AD-000-200, Revision 19, Page 5 of 38
Tab 6 EP-PS-1 05-6 2 - CONTROL ROOM EVACUATION UNUSUAL EVENT EAL# 2.1 None.
ALERT EAL# 2.2 Control Room evacuation as indicated by:
(A and B)
A. Initiation of control room evacuation procedures.
and B. Establishment of control of shutdown systems from local stations.
SITE AREA EMERGENCY EAL# 2.3 Delayed Control Room Evacuation as indicated by:
(A and B)
A. Initiation of control room evacuation procedures.
and B. Shutdown systems control at local stations not established within 15 minutes.
GENERAL EMERGENCY EAL# 2.4 None.
EP-AD-000-200, Revision 19, Page 6 of 38
Tab 6 EP-PS-105-6 3- FUEL CLADDING DEGRADATION UNUSUAL EVENT EAL# 3.1 Core degradation as indicated by:
(A or B)
A. Valid Off-gas Pre-treatment Monitor high radiation alarm annunciation on Panel 1C651 (2C651) or indication on Panel 1C600 (2C600).
or B. Reactor coolant activity, determined by sample analysis greater than or equal to 2
,1Ci/cc of 1-131 equivalent.
ALERT EAL# 3.2 Severe fuel cladding degradation as indicated by:
(A or B or C or D)
A. Valid Off-gas Pre-treatment monitor High-High radiation alarm annunciation on Panel lC651 (2C651) or indication on Panel lC600 (2C600).
or B. Valid Reactor coolant activity greater than 300 Ci/cc of equivalent P131, as
- determined by sample analysis.
or C. Valid Main Steam Line High radiation trip annunciation or indication on Panel 1C651 (2C651).
or D. Valid containment post accident monitor indication on Panel 1C601 (2C601) greater than 200 R/hr. (An 8R/hr correction factor must be added manually to the indication to offset a downscale error Kprimary containment temperature exceeds 225 degrees Fahrenheit. Reference EC-079-0521.)
(CONTINUED ON NEXT PAGE)
EP-AD-000-200, Revision 19, Page 7 of 38
Tab 6 EP-PS-1 05-6 3 - FUEL CLADDING DEGRADATION (continued)
SITE AREA EMERGENCY EAL# 3.3 Severely degraded core as indicated by:
(A or B)
A. Reactor coolant activity greater than 1,000 j+/-Ci/cc of equivalent 1-131 as determined by sample analysis.
or B. Valid containment post accident monitor indication on Panel 1C601 (2C601) greater than 400 R/hr. (An 8 R/hr correction factor must be added manually to the indication to offset a downscale error if primary containment temperature exceeds 225 degrees Fahrenheit. Reference EC-079-0521.)
(CONTINUED ON NEXT PAGE)
EP-AD-000-200, Revision 19, Page 8 of 38
Tab 6 EP-PS-105-6 3 - FUEL CLADDING DEGRADATION (continued)
GENERAL EMERGENCY EAL# 3.4.a Fuel cladding degradation. Loss of 2 out of 3 fission product barriers (fuel cladding and reactor coolant pressure boundary) with potential loss of the third barrier (primary containment) as indicated by:
(A or B)
A. (1 and 2)
- 1. Valid containment post accident monitor indication on Panel 1C601 (2C601) greater than 400 Rhr. (An 8 R/hr correction factor must be added manually to the indication to offset a downscale error if primary containment temperature exceeds 225 degrees Fahrenheit. Reference EC-079-0521.)
and
- 2. (a or b or c)
- a. Containment pressure greater than 40.4 PSIG, indicated on Panel C601 (2C601).
or
- b. A visual inspection of the containment indicates a potential for loss of containment (e.g. anchorage or penetration failure, a crack in containment concrete at tendon).
or
- c. Other indications of potential or actual loss of primary containment.
or B. (1 and 2)
- 1. Reactor coolant activity greater than 1,000 j+/-Ci/cc of.equivalent 1-131 as determined by sample analysis.
and
- 2. Actual or potential failure of reactor coolant isolation valves to isolate a coolant leak outside containment as determined by valve position indication on Panel 1C601 (2C601) or visual inspection.
OR EAL# 3.4.b Core melt as indicated by (A and B)
A. Valid containment post accident monitor indication on Panel 1C601 (2C601) greater than 2000 Rhr. (An 8 R/hr correction factor must be added manually to the indication to offset a downscale error if primary containment temperature exceeds 225 degrees Fahrenheit. Reference EC-079-0521.)
and B. Containment high pressure indication or annunciation on Panel 1C601 (2C601).
EP-AD-000-200, Revision 19, Page 9 of 38
Tab 6 EP-PS-1 05-6 4- GENERAL UNUSUAL EVENT EAL# 4.1 Plant conditions exist that warrant increased awareness on the part of plant operating staff or state and/or local offsite authorities as indicated by:
Events that are occurring or have occurred which indicate a potential degradation of the level of safety of the plant No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety systems occurs.
ALERT EAL# 4.2 Other plant conditions exist that warrant precautionaryctivation of PPL, State, County, and local emergency centers as indicated by:
Events that are occurring or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant. Any releases are expected to be limited to small fractions of the EPA Protective Action Guideline exposure levels.
SITE AREA EMERGENCY EAL# 4.3 Other plant conditions exist that warrant activation of emergency centers and monitoring teams or a precautionary notification to the public near the site as indicated by:
Events that are occurring or have occurred which involve actual or imminent major failures of plant functions needed for protection of the public. Any releases are not expected to exceed EPA Protective Action Guideline exposure levels except inside the emergency planning boundary.
GENERAL EMERGENCY EAL# 4.4 Other plant conditions exist, from whatever, source, that make release of large amounts of radioactivity in a short time period available as indicated by:
Events that are occurring or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity. Expectation is that releases will exceed EPA Protective Action Guideline exposure levels beyond the emergency planning boundary.
EP-AD-000-200, Revision 19, Page 10 of 38
Tab 6 EP-PS-1 05-6 5.- INJUREDICONTAMINATED PERSONNEL UNUSUAL EVENT EAL# 5.1 Transportation of externally contaminated injured individual from site to offsite medical facility as deemed appropriate by Shift Supervisor.
ALERT EAL# 5.2 None.
SITE AREA EMERGENCY EAL# 5.3 None.
GENERAL EMERGENCY EAL# 5.4 None.
EP-AD-000-200, Revision 19, Page 11 of 38
Tab 6 EP-PS-105-6 6 - IN-PLANT HIGH RADIATION UNUSUAL EVENT EAL# 6.1 Unanticipated or unplanned concentrations of arborne activity exist in normally accessible areas, which are not due to planned maintenance activities, as indicated by:
Concentrations exceed 500 times the DAC values of IOCFR20 Appendix B, Table I values for a single isotope, or for multiple isotopes where CA
+ CB C Ce+ CC Cc CN 2500 DA C DA CB DA Cc DACNv ALERT EAL# 6.2 Unexpected in-plant high radiation levels or airborne contamination which indicates a severe degradation in the control of radioactive material as indicated by:
Area Radiation Monitor reading 1000 times normal annunciation on Panel 1C601 (2C601) or indication on Panel 1C600 (2C600).
SITE AREA EMERGENCY EAL# 6.3 None.
GENERAL EMERGENCY EAL# 6.4 None.
EP-AD-000-200, Revision 19, Page 12 of 38
Tab 6 EP-PS-1 05-6 7 - LOSS OF AC POWER UNUSUAL EVENT EAL# 7.1 Loss of offsite power or loss of all onsite AC power supplies as indicated by-(A or B)
A. Loss of power to Startup Transformer 10 and 20 annunciation or indication on Panel OC653.
or B. Failure of all diesel generators to start or synchronize to the emergency buses by indication or annunciation on Panel OC653.
ALERT _
EAL# 7.2 Loss of all offsite power and all onsite AC power supplies as indicated by:
(A and B)
A. Loss of power to Startup Transformer 10 and 20 annunciation or indication on Panel OC653.
and B. Failure of all diesel generators to start or synchronize to the emergency buses by annunciation or indication on Panel OC653.
SITE AREA EMERGENCY EAL# 7.3 Loss of all offsite power and loss of all onsite AC power supplies for greater than 15 minutes as indicated by:
(A and B and C)
A. Loss of offsite power.
and B. Failure of all diesel generators to startup or synchronize to the emergency buses by indication or annunciation on OC653.
and C. The above conditions exist for greater than 15 minutes.
GENERAL EMERGENCY EAL# 7.4 None.
EP-AD-000-200, Revision 19, Page 13 of 38
Tab 6 EP-PS-105-6 8 - LOSS OF CONTROL ROOM ALARMS AND ANNUNCIATORS UNUSUAL EVENT EAL# 8.1 None.
ALERT EAL# 8.2 Loss of all control room annunciators as indicated by:
In the opinion of the Shift Supervisor, all Control Room annunciators and the Plant Process Computer are lost, or insufficient annunciators are available to safely operate the unit(s) without supplemental observation of plant systems.
SITE AREA EMERGENCY EAL# 8.3 All annunciators lost and plant transient initiated while annunciators are lost as indicated by:
(A and B)
A. In the opinion of the Shift Supervisor, all Control Room annunciators and the Plant Process Computer are lost, or insufficient annunciators are available to safely operate the unit(s) without supplemental observation of plant systems.
and B. (1 or2 or3 or4)
- 1. Low-Low reactor water level indication on Panel 1C651 -(2C651) followed by ECCS initiation on Panel I C601 (2C601).
or
- 2. Reactor coolant temperature change greater than 1000F per hour indication on recorder TR-1 R006 on Panel 1C007 (2C007) (Reactor Building elevation 683').
or
- 3. High reactor pressure indication on Panel 1C651 (2C651) and followed by scram indication on Panel C651 (2C651).
or
- 4. Any indication that transient has occurred or is in progress.
GENERAL EMERGENCY EAL# 8.4 None.
EP-AD-000-200, Revision 19, Page 14 of 38
Tab 6 EP-PS-10-6 9 - LOSS OF DC POWER UNUSUAL EVENT EAL# 9.1 None.
ALERT EAL# 9.2 Loss of onsite vital DC power as indicated by:
(A and B)
A. Less than 210 volts on the 250 VDC main distribution Panel buses, D652 (2D652) and D662 (2D662) as indicated by trouble alarms on Panel 1C651 (2C651).
and B. Less than 105volts on the 125VDC main distribution buses ID61 2(2D612),1D622 (2D622), 1D632 (2D632), and 1D642 (2D642) as indicated by trouble alarms on Panel 1C651 (2C651).
NOTE: Buses are not tripped on undervoltage condition.
SITE AREA EMERGENCY EAL 9.3 Loss of all vital onsite DC power sustained for greater than 15 minutes as indicated by:
(A and B and C)
A. Less than 210 volts on the 250 VDC main distribution Panel buses, 1D652 (2D652) and D662 (2D662) as indicated by trouble alarms on Panel 1C651(2C651).
and B. Less than 105 volts on the 125 VDC main distribution buses 1D612 (2D612), D622 (2D622), 1D632 (2D632), and 1D642 (2D642) as indicated by trouble alarms on Panel 1C651(2C651).
and C. The above condition exists for greater than 15 minutes.
NOTE: Buses are not tripped on undervoltage condition.
GENERAL EMERGENCY EAL# 9.4 None.
EP-AD-000-200, Revision 19, Page 15 of 38
Tab 6 EP-PS-105-6 10 - LOSS OF DECAY HEAT REMOVAL CAPABILITY UNUSUAL EVENT EAL# 10.1 None.
ALERT EAL# 10.2 Inability to remove decay heat while in plant condition 4, inability to maintain the plant in cold shutdown as indicated by:
Inability to maintain reactor coolant temperature less than 200OF with the reactor mode switch in shutdown; exception is when testing per Special Test Exception TS 3.10.1 which allows maximum temperature of 21 2 0F.
SITE AREA EMERGENCY EAL# 10.3 Inability to remove decay heat while the plant is shutdown as indicated by:
(A and B and C)
A. Reactor Mode switch in shutdown.
and B. Reactor Coolant System temperature greater than 2000 F and rising.
and C. Suppression Pool temperature greater than 1200 F and rising.
GENERAL EMERGENCY EAL# 10.4 Inability to remove decay heat while the plant is shutdown with possible release of large amounts of radioactivity as indicated by:
(A and B and C)
A. Reactor mode switch in shutdown.
and B. Reactor coolant system temperature greater than 200OF and rising.
and C. Suppression pool temperature greater than 2900F indicated on the computer output (MAT 12,13,14,15 or 16).
EP-AD-000-200, Revision 19, Page 16 of 38
Tab 6 EP-PS-105-6 11 - LOSS OF REACTIVITY CONTROL UNUSUAL EVENT EAL# 11.1 Inadvertent Criticality as indicated by:
Unexpected increasing neutron flux indication on Panel 1C651 (2C651).
ALERT EAL# 11.2 Failure of the Reactor Protection System or the Alternate Rod Insertion System to initiate and complete a scram that brings the reactor subcritical as indicated by:
(A or B) and (C and D and E)
A. Trip of at least one sub-channel in each trip system (RPS A and RPS B) as indicated by annunciators and trip status lights on Panel 1C651 (2C651).
or B. Trip of both trip systems (ARI A and ARI B) as indicated by annunciators on Panel 1C601 (2C601).
and C. Failure of control rods to insert, confirmed by the full core display indication on Panel 1C651 (2C651) or process computer indications.
and D. Failure to bring the reactor subcritical confirmed by neutron count rate on the neutron monitoring indication on Panel 1C651 (2C651).
and E. Reactor power >5% as indicated on Panel 1C651 (2C651).
(CONTINUED ON NEXT PAGE)
EP-AD-000-200, Revision 19, Page 17 of 38
Tab 6 EP-PS-105-6 11 - LOSS OF REACTIVITY CONTROL (continued)
SITE AREA EMERGENCY EAL# 11.3 Loss of functions needed to bring the reactor subcritical and loss of ability to bring the reactor to cold shutdown as indicated by:
(A and B and C and D)
A. Inability to insert sufficient control rods to bring the reactor subcritical as indicated by count rate on the neutron monitoring instrumentation on Panel 1C651 (2C651).
and B. ( or2)
Failure of both loops of standby liquid control to inject into the vessel indicated by:
- 1. Low pump discharge pressure indication on Panel 1C601 (2C601).
or
- 2. Low flow indication on Panel 1C601 (2C601).
and C. Reactor coolant temperature greater than 2000 F, indicated on Panel 1C651 (2C651).
and D. Reactor power >5% indicated on Panel 1C651 (2C651).
GENERAL EMERGENCY EAL# 11.A Loss of functions needed to bring the reactor subcritical and transient in progress that makes release of large amounts of radioactivity in a short period possible as indicated by:
(A or B) and (C and D)
A. Trip of at least one sub-channel in each trip system (RPS A and RPS B), indicated by annunciation or trip status lights on Panel 1C651 (2C651).
or B. Trip of both systems (ARI A and ARI B) as indicated by annunciators on Panel 1C601(2C601).
and C. Loss of SLC system capability to inject, indicated by instrumentation on Panel 1C601 (2C601).
and D. Reactor power greater than 25% of rated, indicated on Panel 1C651 (2C651).
EP-AD-000-200, Revision 19, Page 18 of 38
Tab 6 EP-PS-105-6 12 - LOSS OF REACTOR VESSEL INVENTORY UNUSUAL EVENT EAL# 12.1 Valid initiation of an Emergency Core Cooling System (ECCS) System as indicated by:
(A or B)
A. Initiation of an ECCS System and low, low, low reactor water level (-129) annunciation or indication on Panel 1C651 (2C651).
or B. Initiation of an ECCS System and High Drywell Pressure annunciation or indication on Panel 1C601 (2C601).
ALERT EAL# 12.2 Reactor coolant system leak rate greater than 50 gpm as indicated by:
(A or B)
A. Drywell floor drain sump A or B Hi-Hi alarm on Panel 1C601 (2C601) and 2 or more drywell floor drain pumps continuously running as indicated on Panel 1C601 (2C601).
or B. Other estimates of Reactor coolant system leakage indicating greater than 50 gpm.
SITE AREA EMERGENCY EAL# 12.3 Known loss of coolant accident greater than make-up capacity as indicated by:
Water level below (and failure to return to) top of active fuel for greater than three minutes as indicated on fuel zone level indicator on Panel 1C601 (2C601).
(CONTINUED ON NEXT PAGE)
EP-AD-000-200, Revision 19, Page 19 of 38
Tab 6 EP-PS-1 05-6 12 - LOSS OF REACTOR VESSEL INVENTORY (continued)
GENERAL EMERGENCY EAL# 12.4.a Loss of coolant accident with possibility of imminent release of large amounts of radioactivity as indicated by:
Water level below (and failure to return to) top of active fuel for greater than 20 minutes as indicated on fuel zone level indicator on Panel 1C601 (2C601).
OR EAL# 12.4.b Loss of Reactor Vessel inventory. Loss of 2 out of 3 fission product barriers (fuel cladding & reactor coolant pressure boundary) with potential loss of the third barrier (primary containment), as indicated by:
(A or B)
A. (1 and 2 and 3)
- 1. High drywell pressure annunciation or indication on Panel 1C601 (2C601).
and
- 2. (a orb or c)
- a. Containment pressure exceeds 40.4 PSIG as indicated on Panel C601 (2C601).
or
- b. A visual inspection of the containment indicates a potential or actual loss of containment (e.g. anchorage or penetration failure).
or
- c. Containment isolation valve(s) fail to close as indicated by valve position indication on Panel 1C601 (2C601).
and
- 3. Reactor Vessel level drops below (and fails to return to) top of active fuel for greater than three minutes as indicated on fuel zone level indicator on Panel 1C601 (2C601).
or B. (1 and 2)
- 1. Failure of reactor pressure vessel isolation valves to isolate coolant break outside containment as indicated by valve position indication on Panel 1C601 (2C601) or visual inspection.
and
- 2. Reactor vessel level drops below (and fails to return to) top of active fuel for greater than three minutes as indicated on fuel zone level indicator on Panel 1C601 (2C601).
EP-AD-000-200, Revision 19, Page 20 of 38
Tab 6 EP-PS-1 05-6 13- NATURAL PHENOMENA UNUSUAL EVENT EAL# 13.1 Natural phenomenon occurrence as indicated by:
(A or B or C)
A. Tornado impact on site.
or B. Hurricane impact on site.
or C. Earthquake detected by seismic instrumentation systems on Panel 0C696.
ALERT EAL# 13.2 Natural Phenomenon Occurrence as indicated by:
(A or B orC)
A. Tornado with reported wind velocities greater than 200 mph impacting on site.*
or B. Reported hurricane or sustained winds greater than 70 mph.*
or C. Earthquake at greater than operating basis earthquake (OBE) levels as indicated on Panel 0C696.
- Telephone numbers for the National Weather Bureau are located in the Emergency Telephone Directory.
(CONTINUED ON NEXT PAGE)
EP-AD-000-200, Revision 19, Page 21 of 38
Tab 6 EP-PS-1 05-6 13 - NATURAL PHENOMENA (continued)
SITE AREA EMERGENCY EAL# 13.3 Severe natural phenomenon occurrence, with plant not in cold shutdown, as indicated by:
(A and 3)
A. Reactor Coolant Temperature greater than 200OF as indicated on Panel 1C651 (2C651).
and B. (1 or2or3)
- 1. Reported hurricane or sustained winds greater than 80 mph.*
or
- 2. Earthquake with greater than Safe Shutdown Earthquake (SSE) levels as indicated on Panel OC696.
or
- 3. Tornado with reported wind velocities greater than 220 mph impacting on site.*
GENERAL EMERGENCY EAL# 13.4 None.
- Telephone numbers for the National Weather Bureau are located in the Emergency Telephone Directory.
EP-AD-000-200, Revision 19, Page 22 of 38
Tab 6 EP-PS-1 05-6 14 - ONSITE FIRE/EXPLOSION UNUSUAL EVENT EAL# 14.1 Significant fire within the plant as indicated by:
(A and B)
A. Activation of fire brigade by Shift Supervisor.
and B. Duration of fire longer than 15 minutes after time of notification.
OR Explosion inside security protected area, with no significant damage to station facilities, as indicated by:
Visual observation or notification received by control room operator and Shift Supervisor evaluation.
ALERT EAL# 14.2 On-site Fire/Explosion as indicated by:
(A or B)
A. Fire lasting more than 15 minutes and fire is in the vicinity of equipment required for safe shutdown of the plant and the fire is damaging or is threatening to damage the equipment due to heat, smoke, flame, or other hazard.
or B. (1 and 2)
Explosion damage to facility affecting plant operation as determined by:
- 1. Direct observation or notification received by control room operator.
and
- 2. Shift Supervisor observation.
(CONTINUED ON NEXT PAGE)
EP-AD-000-200, Revision 19, Page 23 of 38
Tab 6 EP-PS-1 05-6 14 - ONSITE FIRE/EXPLOSION (continued)
SITE AREA EMERGENCY EAL# 14.3 Damage to safe shutdown equipment due to fire or explosion has occurred when plant is not in cold shutdown, and damage is causing or threatens malfunction of equipment required for safe shutdown of the plant as determined by:
(A and B and C)
A. Direct observation or notification received by control room operator.
and B. Shift Supervisor evaluation.
and C. Reactor Coolant Temperature greater than 2000 F as indicated on Panel 1C651 (2C651).
GENERAL EMERGENCY EA# 14.4 None.
EP-AD-000-200, Revision 19, Page 24 of 38
Tab 6 EP-PS-1 056 15 - RADIOLOGICAL EFFLUENT UNUSUAL EVENT EAL# 15.1 Any unplanned release of gaseous or liquid radioactivity to the environment that exceeds 2 times the Technical Requirements Manual limits for 60 minutes or longer.
EAL# 15.1 (1 or 2 or 3)
- 1. Valid Noble Gas vent stack monitor reading(s) that exceeds a total site release rate of 2.OE+6 igCi/min and that is sustained for 60 minutes or longer.
- 2. Confirmed sample analyses for airborne releases indicates total site release rates at the site boundary with a release duration of 60 minutes or longer resulting in dose rates of:
a) Noble gases >1000 mrem/year whole body, or b) Noble gases >6000 mrem/year skin, or c) 1-131, 1-133, H-3, and particulates with half lives >8 days >3000 mrem/year to any organ (inhalation pathways only).
- 3. Confirmed sample analyses for liquid releases indicates concentrations with a release duration of 60 minutes or longer in excess of two timfe the Technical Requirements Manual liquid effluent limits.
(CONTINUED ON NEXT PAGE)
EP-AD-000-200, Revision 19, Page 25 of 38
Tab 6 EP-PS-1 05-6 15 - RADIOLOGICAL EFFLUENT (continued)
ALERT EAL# 15.2 Any unplanned release of gaseous or liquid radioactivity to the environment that exceeds 200 times Technical Requirement Manual limits for 15 minutes or longer.
EAL# 15.2 (1 or 2 or 3)
- 1. Valid Noble Gas vent stack monitor reading(s) that exceeds a total site release-rate of 2E+8 igCi/min and that is sustained for 15 minutes or longer.
OR 2 Confirmed sample analyses for airborne releases indicates total site release rates at the site boundary for 15 minutes or longer resulting in dose rates of:
a) Noble gases >1.0E+5 mrem/year whole body, or b) Noble gases >6.OE+5 mremlyear skin, or c) 1-131, 1-133, H-3, and particulates with half-lives >8 days >3.OE+5 mrem/year to any organ (inhalation pathways only).
- 3. Confirmed sample analyses for liquid releases indicates concentrations in excess of 200 times the Technical Requirements Manual liquid effluent limits for 15 minutes or longer.
(CONTINUED ON NEXT PAGE)
EP-AD-000-200, Revision 19, Page 26 of 38
Tab 6 EP-PS-1 05-6 15 - RADIOLOGICAL EFFLUENT (continued)
SITE AREA EMERGENCY EAL# 15.3 Dose at the Emergency Plan boundary resulting from an actual or imminent release of gaseous radioactivity exceeds 100 mrem whole body TEDE or 500 mrem child thyroid CDE for the actual or projected duration of release.
EAL# 15.3(1 or2or3or4or5)
- 1. Valid Noble Gas vent stack monitor readings(s) that exceeds a total release rate 6.2E8 gCi/min for greater than 15 minutes and Dose Projections are not available.
Note: If the required dose projection cannot be complete within the 15 minute period, then the declaration must be made based on a valid sustained monitor reading(s).
- 2. Valid dose assessment using actual meteorology indicates projected doses greater than 100 mrem whole body TEDE or 500 mrem child thyroid CDE at or beyond the EPB.
- 3. A valid reading sustained for 15 minutes or longer on the RMS perimeter radiation monitoring system greater than 100 mR/hr.
- 4. Field survey results indicate Emergency Planning boundary dose rates exceeding 100 mR/hr expected to continue for more than one hour.
- 5. Analyses of field survey samples indicate child thyroid dose commitment at the Emergency Planning Boundary of 500 mrem for one hour of inhalation.
(CONTINUED ON NEXT PAGE)
EP-AD-000-200, Revision 19, Page 27 of 38
Tab 6 EP-PS-1 05-6 15 - RADIOLOGICAL EFFLUENT (continued)
GENERAL EMERGENCY EAL# 15.4 Dose at the Emergency Planning Boundary resulting from an actual or imminent release of gaseous radioactivity exceeds 1000 mrem whole body TEDE or 5000 mrem child thyroid CDE for the actual or projected duration of the release using actual meteorology.
EAL# 15.4 (1 or2or3or4or5)
- 1. Valid Noble Gas vent stack monitor readings(s) that exceed a total release rate of 6.2E9 gCi/min for greater that 15 minutes and Dose Projections are not available.
Note: If the required dose projection cannot be completed within the 15 minute period, then the declaration must be made based on a valid sustained monitor reading(s).
- 2. Valid dose assessment using actual meteorology indicates projected doses greater than 1000 mrem whole body TEDE or 5000 mrem child thyroid CDE at or beyond the EPB.
- 3. A valid reading sustained for 15 minutes or longer on the RMS perimeter radiation monitoring system greater than 1000 mR/hr.
- 4. Field survey results indicate Emergency Planning Boundary dose rates exceeding 1000 mR/hr expected to continue for more than one hour.
- 5. Analyses of field survey samples indicate child thyroid dose commitment at the Emergency Planning Boundary of 5000 mrem for one hour of inhalation.
EP-AD-000-200, Revision 19, Page 28 of 38
Tab 6 EP-PS-1 05-6 16 - SECURITY EVENT UNUSUAL EVENT EAL# 16.1 Security threat or attempted entry or attempted sabotage as indicated by:
(A or B or C)
A. A report from Security of a security threat, attempted entry, or attempted sabotage of the owner controlled area adjacent to the site.
or B. Any attempted act of sabotage which is deemed legitimate in the judgment of the SHIFT SUPERVISOR/EMERGENCY DIRECTOR, and affects plant operation.
or C. A site specific credible security threat notification.
ALERT EAL# 16.2 Ongoing Security Compromise as indicated by:
(A or B)
A. A report from Security that a security compromise is at the site but no penetration of protected areas has occurred.
or B. Any act of sabotage which results in an actual or potential substantial degradation of the level of safety of the plant as judged by the SHIFT SUPERVISOR/EMERGENCY DIRECTOR.
SITE AREA EMERGENCY EAL# 16.3 An ongoing adversary event threatens imminent loss of physical control of plant as indicated by-(A or B)
A. Report from Security that the security of the plant vital area is threatened by unauthorized (forcible) entry into the protected area.
or B. Any act of sabotage which results in actual or likely major failures of plant functions needed for protection of the public as judged by the SHIFT SUPERVISOR/EMERGENCY DIRECTOR.
(CONTINUED ON NEXT PAGE)
EP-AD-000-200, Revision 19, Page 29 of 38
Tab 6 EP-PS-105-6 16 - SECURITY EVENT (continued)
GENERAL EMERGENCY EAL# 16.4 Loss of physical control of facilities as indicated by:
(A or B)
A. Report from Security that a loss of physical control of plant vital areas has occurred.
or B. Any act of sabotage which results in imminent significant cladding failure or fuel melting with a potential for loss of containment integrity or the potential for release of significant amounts of radioactivity in a short time as judged by the SHIFT SUPERVISOR/EMERGENCY DIRECTOR.
EP-AD-000-200, Revision 19, Page 30 of 38
Tab 6 EP-PS-1 05-6 17 - SPENT FUEL RELATED INCIDENT UNUSUAL EVENT EAL# 17.1 Unanticipated or unplanned concentrations of airborne activity exist in normally accessible areas, which is not due to planned maintenance activities, as indicated by:
Concentrations exceed 500 times the DAC values of 10CFR20 Appendix B, Table I values for a single isotope, or full multiple isotopes where CA + CB + CC -CN > 500 DACA DAC. DACC DACN ALERT EAL# 17.2 Unexpected in-plant high radiation levels or airborne contamination which indicates a severe fuel handling accident as indicated by:
Refuel floor area radiation monitor reading 1000 times normal annunciation on Panel 1C601 (2C601) or indication on Panel 1C600 (2C600).
(CONTINUED ON NEXT PAGE)
EP-AD-000-200, Revision 19, Page 31 of 38
Tab 6 EP-PS-105-6 17 - SPENT FUEL RELATED INCIDENT (continued)
SITE AREA EMERGENCY EAL# 17.3.a Major damage to irradiated fuel with actual or clear potential for significant release of radioactive material to the environment as indicated by:
(A and B)
A. Dropping, bumping, or otherwise rough handling of a new OR irradiated fuel bundle with irradiated fuel in the pool.
and B. (I or2)
- 1. Refueling floor area radiation monitor reading 1000 times normal annunciation on Panel 1C601 (2C601) or indication on Panel 1C600 (2C600).
or
- 2. Reactor Building vent stack monitoring system high radiation annunciation or indication on Panel 0C630 or 0C677.
OR EAL# 17.3.b Damage to irradiated fuel due to uncontrolled decrease in the fuel pool level to below the level of the fuel as indicated by:
(A and B)
A. (1 or2)
- 1. Uncovering of irradiated fuel confirmation by verification of significant leakage from spent fuel pool.
or
- 2. Visual observation of water level below irradiated fuel in the pool.
and B. (1 or2)
- 1. Refueling floor area radiation monitor annunciation on Panel 1C651 (2C651) or indication on Panel I C600 (2C600).
or
- 2. Reactor Building vent stack monitoring system high radiation annunciation or indication on Panel 0C630 or 0C677.
GENERAL EMERGENCY EAL# 17A None.
EP-AD-000-200, Revision 19, Page 32 of 38
Tab 6 EP-PS-1 05-6 18 - STEAM LINE BREAK UNUSUAL EVENT EAL# 18.1 None.
ALERT EAL# 18.2 MSIV malfunction causing leakage as indicated by:
(A and B)
A. Valid MSIV closure signal or indication on Panel 1C601 (2C601).
and B. (1 or2)
- 1. Valid Main Steam Line flow indicabon on Panel 1C652 (2C652).
or
- 2. Valid Main Steam Line radiation indication on Panel 1C600 (2C600).
(CONTINUED ON NEXT PAGE)
EP-AD-000-200, Revision 19, Page 33 of 38
Tab 6 EP-PS-1 05-6 18 - STEAM LINE BREAK (continued)
SITE AREA EMERGENCY EAL# 18.3 Steam line break occurs outside of containment without isolation as indicated by:
(A or Bor C or D)
A. (1 and 2)
- 1. Failure of both MSIVs in the line with the leak to close as indicated by position indication on Panel 1C601 (2C601).
and
- 2. (a orb)
- a. High MSL flow annunciation on Panel C601 (2C601) or indication on Panel I C652 (2C652).
or
- b. Other indication of main steam leakage outside containment or B. (1 and 2)
- 1. Failure of RCIC steam isolation valves HV-F008 and HV-F007 to close as indicated on Panel 1C601 (2C601).
and
- 2. (a orb orc ord ore orf)
- a. RCIC steamline pipe routing area high temperature annunciation on Panel 1C601 (2C601), or indication on Panel 1C614 (2C614).
or
- b. RCIC equipment area high temperature annunciation on Panel 1601 (2C601) or indication on Panel 1C614 (2C614).
or
- c. RCIC steamline high flow annunciation on Panel 1C601 (2C601).
or
- d. RCIC steamline tunnel ventilation high delta temperature annunciation on Panel 1C601 (2C601).
or
or
- f. Other indication of steam leakage from the RCIC system.
(CONTINUED ON NEXT PAGE)
EP-AD-000-200, Revision 19, Page 34 of 38
Tab 6 EP-PS-105-6 18 - STEAM LINE BREAK (continued)
SITE AREA EMERGENCY (continued) or C. (1 and 2)
- 1. Failure of HPCI steam isolation valves HV-F002 and HV-F003 to close as indicated by position indicator on Panel 1601 (2C601).
and
- 2. (aorborcordoreorf)
- a. HPCI steamline pipe routing area high temperature annunciation on Panel 1C601 (2C601), or indication on Panel 1C614 (2C614).
or
- b. HPCI equipment area high temperature annunciation on Panel 1C601 (2C601) or indication on Panel 1C614 (2C614).
or
- c. HPCI steamline high flow annunciation on Panel 1C601 (2C601).
or
- d. HPCI steamline tunnel ventilation high delta temperature annunciation on Panel 1C601 (2C601).
or
or
- f. Other indication of steam leakage from the HPCI system.
or D. Any other un-isolatable steam line breaks.
GENERAL EMERGENCY EAL# 18.4 None.
EP-AD-000-200, Revision 19, Page 35 of 38
Tab 6 EP-PS-1 05-6 19 - TOXIC/FLAMMABLE GASES UNUSUAL EVENT EAL# 19.1 Nearby or onsite release of potentially harmful quantifies of toxic or flammable material as indicated by:
Visual observation or notification received by the control room operator.
ALERT EAL# 19.2 Entry of toxic or flammable gases into the facility, with subsequent habitability problem as indicated by:
Visual observation, direct measurement, or notification received by the control room operator.
SITE AREA EMERGENCY EAL# 19.3 Toxic or flammable gases enter vital areas, restricting access and restricted access constitutes a safety problem, as determined by:
(A and B)
A. Shift Supervisor's evaluation.
and B. Visual observation, direct measurement, or notification received by control room operator.
GENERAL EMERGENCY EAL# 19.4 None.
EP-AD-000-200, Revision 19, Page 36 of 38
Tab 6 EP-PS-105-6 20 - TECHNICAL SPECIFICATION SAFETY LIMIT UNUSUAL EVENT EAL# 20.1 Abnormal occurrences which result in operator complying with any of the Technical Specification SAFETY LIMIT ACTION statements indicated by:
(A or B or C or D)
A. Exceeding THERMAL POWER, low pressure or low flow safety limit 2.1.1.1.
or B. Exceeding THERMAL POWER, high pressure and high flow safety limit 2.1.1.2.
or C. Exceeding REACTOR VESSEL WATER LEVEL safety limit 2.1.1.3.
or D. Exceeding REACTOR COOLANT SYSTEM PRESSURE saffy limit 2.1'.2.
ALERT EAL# 20.2 None.
SITE AREA EMERGENCY EAL# 20.3 None.
GENERAL EMERGENCY EAL# 20.4 None.
EP-AD-000-200, Revision 19, Page 37 of 38
Tab 6 EP-PS-1 05-6 21 - DRY FUEL STORAGE UNUSUAL EVENT EAL# 21.1.a. Situations are occurring or have occurred during the transport of the irradiated spent fuel to the onsite storage facility, which jeopardize the integrity of the spent fuel or its container as indicated by:
(A or B)
A. Radiological readings exceed 2 Rlhour at the external surface of any transfer cask or horizontal storage module.
or B. Radiological readings exceed 1 Rhour one foot away from the external surface of any transfer cask or horizontal storage module.
OR EAL# 21.1.b. Situations are occurring or have occurred at the irradiated spent fuel storage facility, which jeopardize the integrity of the dry cask storage system as indicated by:
(A or B)
A. Radiological readings exceed 2 Rlhour at the external surface of any transfer cask or horizontal storage module.
or B. Radiological readings exceed 1 R/hour one foot away from the external surface of any transfer cask or horizontal storage module.
ALERT EAL# 21.2 None.
SITE AREA EMERGENCY EAL# 21.3 None.
GENERAL EMERGENCY EAL# 21.4 None EP-AD-000-200, Revision 19, Page 38 of 38
Tab 7 EP-PS-1 05-7 PAR AIRBORNE RELEASES EP ENTERED MONITOR CONDITIONS:
- PLANT STATUSIPROCEDURES
- ONSITE RAD CONDITIONS ASSESSMENT
- STATUS OF RELEASE
- DOSE PROJECTIONS PA-1 O RENCY EEN NO REMECLARED PPA.
YES 2DOSES OF JEREM TEDE OR YESDOEC AL D RIE.
\25 REM THYROID CDEAA/ 10MLS
- 3. TANCE OF 2 2 MS
\ / ~~~~~~~~PA-5 NO OR UNKNOWN INFRMTION NTHACTONTOB TAE. MN VAUTO RECOMMEND EVACUATING COMME 02 ILEAND DSSHELTERING 2-10 MILES. kASSMN PA-1 PA-4
. PA-# CAN BE USED TO REFER TO PROCEDURE STEPS FOR MORE DETAILED INFORMATION ON THE ACTION TO BE TAKEN.
- 2. DOSE PROJECTIONS DO NOT INCLUDE DOSE ALREADY RECEIVED.
- 3. TEDE - WHOLE BODY (TEDE) IS THE SUM OF EFFECTIVE DOSE EQUIVALEFNT RESULTING FROM EXPOSURE TO EXTERNAL SOURCES. THE COMMITTED EFFECTIVE DOSE EQUIVALENT (CEDE) FROM ALL SIGNIFICANT INHALATION PATHWAYS AND THE DOSE DUE TO GROUND DEPOSITION.
- 4. CDE - COMMITTED DOSE EQUIVALENT TO THE CHILD THYROID.
EP-AD-000-126, Revision 10, Page 1 of 6
Tab 7 EP-PS-1 05-7 PAR LIQUID RELEASES INDICATIONS OF A POTENTIAL LIQUID RELEASE
- UNISOLABLE RADWASTE TANK RELEASE
- LEAK TO COOLING TOWER BASIN
-LEAK TO SPRAY POND PL-1 ENSURE CHEMIESD TAKES AND ANALYZES SAMPLES PL-2 i NPANDRLA NO ACINCNIUE TO THE RIVER No RENI EC Values RADIONUCLIDE (pCUmI)
Co-60 3E 4 Yes Sr-S1 2E' Mo-" 2E4 RAD PERSONNEL NOTIFY Te-132 9E4 DEPIBRP THAT A RELEASE 1-131 1E 4 HAS OCCURRED 1-133 7E 4 1-134 4E 4 PL-4 t No 1-135 3E-6 Cs-134 SE- 7 TEC RELEASE REURMET . OR- _A I Cs-136 GE4 -<TECH RECIUMEME S Cs-137 1E 4 RLEASE PN Ba-139 2E4 Ba-140 SE 4 PL-5 Ba-141 3E`
Yes Np-239 2E4 RAD PERSONNEL NOTIFY DANVILLE THAT A RELEASE HAS OCCURRED PL-6
- CHEMIFTD EVALUATES RELEASE vs PAG PL-7 NOTES:
- 1. PL4 CAN BE USED TO REFER TO ES RELEASE EXCE RAD PERSONNEL PROCEDURE STEPS FOR MORE ANY OF THE SINGLE-NUCLIDE NOTIFY DEPIBRP DETAILED INFORMATION ON THE EC VALUES OR DOES THE ACTION TO BE TAKEN. SM OF EC FRACTIONS
,THAT NO PAR IS
- 2. CALLS TO DANVILLE ARE COURTESY EXCEED 0.5/ REQUIRED INFORMATION CALLS ONLY. AT DANVILLE? PL-10 PROTECTIVE ACTION RECOMMENDATION CALLS MUST BE PLt MADE BY DEPIBRP.
Yes w
RAD PERSONNEL NOTIFY DEPIBRP FOR DOWNSTREAM USERS TO DIVERT WATER SUPPLY &ESTIMATED TIME OF ARRIVAL OF RELEASE AT DANVILLE PL-9 EP-AD-000-126, Revision 10, Page 2 of 6
Tab 7 EP-PS-105-7 PUBLIC PROTECTIVE ACTION RECOMMENDATION GUIDE AIRBORNE RELEASES 0 PA-1 MONITOR CONDITIONS FOR PAR APPLICATION The following conditions should be continuously evaluated to determine if a PAR should be implemented or changed:
- Plant status and prognosis for changes in conditions
- Onsite radiological conditions
- Status of actual or potential radioactive releases
- Offsite dose projections or actual offsite radiological conditions
- Escalation in Emergency Classification (i.e., General)
(Go to PA-2)
PA-2 HAS A GENERAL EMERGENCY BEEN DECtARED?
o YES - If a GENERAL EMERGENCY has been declared, a PAR must be made within 15 minutes of the emergency declaration. The PAR requirement is found in NUREG-0654. (Go to PA-3) ol NO- If a GENERAL EMERGENCY has not been declared, continue to monitor plant status, parameter trends, and prognosis for termination or escalation of the event. (Go to PA-1)
PA-3 IS THERE A VALID DOSE PROJECTION INDICATING DOSES OF > I REM TEDE OR 5 REM CDE CHILD THYROID AT A DISTANCE OF > 2 MILES?
O YES - If the projected doses at 2 miles are 2 1 REM TEDE or > 5 REM CDE child thyroid, then full evacuation (0-10 miles) is recommended.
(Go to PA-5) o NOIUNKNOWN - (Go to PA-4) o PA-4 RECOMMEND EVACUATION 0-2 MILES; SHELTER 2-10 MILES Limited Evacuation (0-2 miles) and sheltering is appropriate for events that are significant enough to cause a General Emergency classification and dose projections are low, unknown, or below full evacuation guidelines.
O PA-5 EVACUATE 0-10 MILES Full evacuation of members of the general public is recommended at this point based on the emergency classification and dose projections.
EP-AD-000-1 26, Revision 10, Page 3 of 6
Tab 7 EP-PS-1 05-7 LIQUID 0 PL-1 ENTRY This section is entered when there are indications of a potential unplanned radioactive liquid release.
Indications of potential unplanned releases include:
- an unisolable radwaste tank release
- leaks to cooling tower basin
- leak to spray pond (Go to PL-2)
O PL-2 CHEMISTRYIENVIRONMENTAL SAMPLINGDIRECTOR (ESD)
TAKES AND ANALYZES SAMPLE (Go to PL-3)
PL-3 IS THERE AN UNPLANNED RELEASE TO THE RIVER?
0 YES - An unplanned release to the river has occurred when event-related radioactive materials are released to the river that are not controlled by the release methodologies described in the ODCM and applicable Chemistry procedures.
(Go to PL-4) 0 NO- If there is no unplanned release to the river, then no notifications are required and monitoring should continue.
O PL-4 RAD PERSONNEL NOTIFY DEPIBRP THAT A RELEASE HAS OCCURRED Depending on which facility is activated, the notification to BRP will be made by the RPC (TSC), Dose Assessment Supervisor, or Radiological Liaison at the EOF.
DO NOT MAKE ANY PROTECTIVE ACTION RECOMMENDATIONS AT THIS TIME.
(Go to PL-5)
EP-AD-000-1 26, Revision 10, Page 4 of 6
Tab 7 EP-PS-1 05-7 LIQUID (CONT'D)
PL-5 IS RELEASE > TECHNICAL REQUIREMENTS.LIMITS (AT THE RELEASE POINT)?
0 YES- Releases are at or greater than Technical Requirements limits when Chemistry determines that the limits are exceeded based on methodologies described in the ODCM and applicable Chemistry procedures.
(Go to PL-6) 0 NO- If the release is < Technical Requirements limits, then no further notifications are required and monitoring should continue.
O PL-6 RAD PERSONNEL NOTIFY DANVILLE THAT A RELEASE HAS OCCURRED Depending on which facility is activated, the notification to Danville will be made by the RPC (TSC), Dose Assessment Supervisor, or Radiological Liaison at the EOF.
DO NOT MAKE ANY PROTECTIVE ACTION RECOMMENDATIONS AT THIS TIME.
(Go to PL-7) o PL-7 CHEM/FTD EVALUATES RELEASE VERSUS PAGs The results of the sample analysis are compared to the PAGs for radionuclides in drinking water. The analysis calculates the expected concentration at Danville, taking into account the dilution afforded by the river.
PL-8 DOES RELEASE EXCEED PAGs (AT DANVILLE)?
o YES - If a single isotope exceeds its effluent concentration (EC) value or the sum of EC fractions exceeds 0.85, then a protective action recommendation should be made for downstream water users (e.g.,
Danville) to DIVERT DRINKING WATER supply to a backup supply or terminate user intake until the release has passed.
(Go to PL-9)
O NO- If the PAGs are not exceeded, monitoring should continue and the State should be notified that no PAR for the liquid release is required.
(Go to PL-10)
EP-AD-000-1 26, Revision 10, Page 5 of 6
Tab 7 EP-PS-1 05-7 LIQUID (CONT'D) 0 PL-9 RAD PERSONNEL NOTIFY DEP/BRP OF PAR Depending on which facility is activated, the PAR notification to DEP/BRP will be made by the RPC (TSC), Dose Assessment Supervisor, or Radiological Liaison at the EOF. The PAR FORM shall be used to document the PAR.
DO NOT COMMUNICATE THE PROTECTIVE ACTION RECOMMENDATION TO DANVILLE. THE DEP/BRP IS RESPONSIBLE FOR THIS COMMUNICATION AND ANY COMMUNICATION TO OTHER DRINKING WATER SUPPLIERS OR WATER USERS.
0 PL-10 RAD PERSONNEL NOTIFY DEPIBRP No PAR is required. Depending on which facility is activated, the RPC (TSC), Dose Assessment Supervisor, or Radiological Liaison at the EOF shall notify DEP/BRP that no PAR is required.
EP-AD-000-126, Revision 10, Page 6 of 6
Tab 8 EP-PS-1 05-8 PPL EMERGENCY PERSONNEL DOSE ASSESSMENT AND PROTECTIVE ACTION RECOMMENDATION (PAR) GUIDE TABLE OF CONTENTS SECTION PAGE 1.0 EMERGENCY DOSE LIMITS 2 2.0 EMERGENCY EXPOSURE/ACCIDENTAL OVEREXPOSURE 3 3.0 PROTECTIVE ACTIONS 3 4.0 EMERGENCY EXPOSURE NOTIFICATION AND HEALTH CONSEQUENCE INVESTIGATION 7 EMERGENCY EXPOSURE EXTENSIONS 8 HEALTH PHYSICS AND ALARA CONSIDERATIONS DURING AN EMERGENCY 12 NOTE: EMERGENCY EXPOSURE EXTENSION REQUEST FORM and POTASSIUM IODIDE TRACKING FORM can be found as Forms EP-AD-000-135 and EP-AD-000-141, respectively.
EP-AD-000-125, Revision 9, Page 1 of 13
Tab 8 EP-PS-1 05-8 PPL EMERGENCY PERSONNEL DOSE ASSESSMENT AND PROTECTIVE ACTION RECOMMENDATION (PAR) GUIDE CHECK 0 1.0 Limits for EMERGENCY doses.
D 1.1 An EMERGENCY DOSE AUTHORIZATION (see EMERGENCY EXPOSURE EXTENSIONS) may be granted in order to protect facilities, and or equipment to substantially limit the escape of radioactive effluents or control fires. The maximum planned doses are:
1.1.1 Whole body (TEDE)(1) dose shall not exceed 10 rem.
1.1.2 Dose to any organ (CDE)(2), including the skin and extremity (SDE)(3), shall not exceed 100 rem.
1.1.3 Dose to the lens of the eye shall not exceed 30 rem (LDE)(4).
O 1.2 An EMERGENCY dose authorization may be granted for life-saving actions or protection of large populations. The maximum doses are:
1.2.1 Planned whole body (TEDE)(') doses shall not exceed 25 rem.
1.2.2 Planned dose to any organ (CDE)(2), including skin and extremity doses, shall not exceed 250 rem.
1.2.3 Dose to the lens of the eye shall not exceed 75 rem (LDE)(4).
1.3 RARE situations may occur in which a dose GREATER THAN those specified in SECTION 1.2 above for emergency dose would be unavoidable to carry out a lifesaving operation or to avoid extensive exposure of large populations. It is not possible to prejudge the risk that one should be allowed to take to save lives of others, therefore no upper limit has been established.
The sum of the Effective Dose Equivalent resulting from the exposure to external sources and the Committed Effective Dose Equivalent incurred from all significant inhalation pathways during the early phase.
(2) The Committed Dose Equivalent to the thyroid from radioiodine.
(3) Shallow Dose Equivalent.
(4) Lens Dose Equivalent.
EP-AD-000-125, Revision 9, Page 2 of 13
Tab 8 EP-PS-1 05-8 PPL EMERGENCY PERSONNEL DOSE ASSESSMENT AND PROTECTIVE ACTION RECOMMENDATION (PAR) GUIDE CHECK0 2.0 For any EMERGENCY EXPOSURE OR ACCIDENTAL OVEREXPOSURE, the assessment actions in step 2 of the EMERGENCY EXPOSURE EXTENSIONS must be performed.
3.0 PROTECTIVE ACTIONS Q 3.1 Potassium Iodide 3.1.1 For thyroid doses that are strongly expected to exceed 10 rem (CDE) (2), ingestion of a KI dose of 130 mg (100mg - iodine) should be recommended, except as noted in pairagraph 3.1.2, to personnel whose emergency assignment or qualifications do not allow other protective measures to be taken (e.g. respiratory protection, evacuation, relocation, etc.) to maintain the dose to the thyroid at less than 10 rem.
NOTE: HHS/FDA guidance is that adults over 40 years of age need take KI only in the case of a projected large internal radiation dose to the thyroid ( > 500 rem) to prevent hypothyroidism; the guidance is 10 rem for adults over age 18 to age 40.
3.1.2 KI should not be administered to any emergency worker who:
- a. does not concur with its use, or
- c. has been directed by their Physician or Pharmacist to avoid ingestion of iodine and/or foods containing iodine such as shellfish.
°2) The Committed Dose Equivalent to the thyroid from radioiodine.
EP-AD-000-125, Revision 9, Page 3 of 13
Tab 8 EP-PS-1 05-8 PPL EMERGENCY PERSONNEL DOSE ASSESSMENT AND PROTECTIVE ACTION RECOMMENDATION (PAR) GUIDE CHECK0 3.1.3 Onsite issuance of KI for iodine prophylaxis requires the approval of the EMERGENCY DIRECTOR. Issuance to EOF and FIELD EMERGENCY MONITORING/SAMPLING TEAM personnel requires the approval of the RECOVERY MANAGER when the EOF has relieved the TSC of emergency management activities.
The EMERGENCY DIRECTOR will approve issuance prior to that time. These approvals must be documented on the POTASSIUM IODIDE (KI) TRACKING FORM.
3.1.4 Unless the EMERGENCY DIRECTOR or RECOVERY MANAGER instructs personnel to do otherwise, the Ftablets should generally be taken as soon as possible after thyroid dose exceeding 10 rem CDE (2)is projected.
NOTE: Stable iodine (KI) is most effective when administered immediately prior to exposure to radioiodine. Significant blockage of the thyroid dose can be provided by administration within a few hours after uptake of radioiodine.
3.15 In the event a significant exposure to the thyroid is projected to continue over a period of several days the CONSULTING RADIOLOGICAL PHYSICIAN should be re quested to provide a recommended KI dosage for subsequent KI usage. (See Emergency Telephone Directory for telephone number.)
3.16 Until input/advice from the CONSULTING RADIOLOGICAL PHYSICIAN is available, a quarter of a tablet should be taken on days of exposure that follow the day on which the initial full tablet dose (130 mg) was taken.
3.17 If a worker expresses concern with the use of KI and/or is unsure if it will interact with his/her current medication,
- a. the CONSULTING RADIOLOGICAL PHYSICIAN should be requested to provide inputladvice to the individual concerning the administration and cessation of KI use prior to its ingestion by the individual. (See Emergency Telephone Directory for telephone number.)
(2) The Committed Dose Equivalent to the thyroid from radioiodine.
EP-AD-00-125, Revision 9, Page 4 of 13
Tab 8 EP-PS-1 05-8 PPL EMERGENCY PERSONNEL DOSE ASSESSMENT AND PROTECTIVE ACTION RECOMMENDATION (PAR) GUIDE CHECK 0
- b. control and track workers' dose, to limit their projected thyroid dose to 40 rem total organ dose. As warranted, ensure adjusted RWP controls and dose extensions are in place.
3.1.8 Should the projected dose to the thyroid not exceed 10 rem CDE (2)but the worker expresses the strong desire to use KI, the worker may do so at his/her own risk. In such case, the RPC or DASU as appropriate will inform the worker of the potential risks and benefits as described below and will recommend the person contact the CONSULTING RADIOLOGICAL PHYSICIAN for further guidance.
NOTE: Radiation exposure to the thyroid glands of adults does not appear to lead to cancer but has been shown to cause other deterministic effects (such as hypothyroidism resulting from thyroid ablation) from very high radiation doses to the thyroid.
For persons over 40 years of age, HHS/FDA recommends KI only for projected doses to the thyroid of above 500 rem, to prevent hypothyroidism.
The National Council on Radiation Protection and Measurement (NCRP Report No. 55) concludes that the risk of adverse effects from use of KI is on the order of 5 in 10 million.
In some cases, hyperthyroidism (excessive functional activity of the thyroid gland) is possible.
Those most at risk are patients with thyroid pathologies. This is most common in patients with goiter. This complication can be serious when the person also has heart disease. The risk of adverse effects is higher in adults of age 45 years and older, due to the frequency of diagnosed and sub-clinical thyroid disease and the use of certain prescription pharmaceuticals that would lead to a drug interaction.
The Committed Dose Equivalent to the thyroid from radioiodine.
EP-AD-000-1 25, Revision 9, Page 5 of 13
Tab 8 EP-PS-1 05-8 PPL EMERGENCY PERSONNEL DOSE ASSESSMENT AND PROTECTIVE ACTION RECOMMENDATION (PAR) GUIDE CHECK 0 HHS/FDA observes that short-term administration of KI at thyroid blocking doses is safe. The risks of stable iodine administration include sialadenitis (an inflammation of the salivary gland), gastrointestinal disturbances, allergic reactions, and minor rashes.
Other risks may apply if repeated doses of KI are ingested.
3.1.9 If the individual states the intent to take KI absent a projected dose of 10 rem (CDE)(2) or more, the RPC or DASU will document in his/her logbook that individual's intent, that information on risks and benefits was described to the individual, and the statement that the individual was notified that ingestion was at the individual's own risk.
3.1.10 For an injured and/or contaminated worker sent to a hospital for treatment, the patient will be under the care of the attending physician. As such, plant procedures no longer apply and KI issuance will be at the discretion of the attending physician. The physician can rely on a senior Health Physics Technician Level II or Health Physics Management to provide the in-plant radiological data on which to base their decision.
3 3.2 Protective measures should be implemented for EOF personnel at the direction of the DOSE ASSESSMENT SUPERVISOR, within the bounds of RWPs #8001 and #8002. Consultation with and approval by the RPC is needed for RWP revisions.
O 3.3 Exposures to members of local offsite support groups, (ambulance workers, fire fighters) shall not exceed 500 mrem (TEDE)(1) for the performance of support duties on the site of the Susquehanna SES.
(2) The Committed Dose Equivalent to the thyroid from radioiodine.
(1) The sum of the Effective Dose Equivalent resulting from the exposure to external sources and the Committed Effective Dose Equivalent incurred from all significant inhalation pathways during the early phase.
EP-AD-000-1 25, Revision 9, Page 6 of 13
Tab 8 EP-PS-105-8 PPL EMERGENCY PERSONNEL DOSE ASSESSMENT AND PROTECTIVE ACTION RECOMMENDATION (PAR) GUIDE CHECK O 4.0 EMERGENCY EXPOSURE NOTIFICATIONS AND A HEALTH CONSEQUENCE INVESTIGATION must be conducted for any emergency exposure as outlined in step 6 of the Emergency Exposure Extensions.
NOTE: Reference for section 3.1 are as follows:
- 1. HHS/FDA Guidance-Potassium Iodide as a Thyroid Blocking Agent in Radiation Emergencies, December 2001.
- 2. LeGuen, B. et.al., French Approach for the Distribution of Iodine Tablets in the Vicinity of Nuclear Power PKants, Health Physics 2002.
EP-AD-000-125, Revision 9, Page 7 of 13
Tab 8 EP-PS-1 05-8 EMERGENCY EXPOSURE EXTENSIONS CHECK Cl
- 1. Fill out the attached EMERGENCY EXPOSURE EXTENSION REQUEST Form.
- 2. Review the following factors:
D Rescue personnel should be volunteers or professional rescuers.
O Other considerations being equal (e.g., skill, potential need for person on another mission) personnel above the age of 45 are preferred.
o Rescue personnel should be familiar and briefed with the consequences of exposure.
D Women capable of reproduction should not take part in an effort requiring EMERGENCY exposure.
o Use of personnel with high lifetime cumulative exposure should be discouraged.
D All reasonable measures must be taken to control contamination and internal exposure.
Dl Exposure under these conditions shall be limited to once in a lifetime.
Dl For exposures greater than 25 rem whole body (TEDE), the persons undertaking any emergency operation in which the dose will exceed 25 rem to the whole body (TEDE) should do so only on a voluntary basis and with full awareness of the risks involved, including the numerical levels of dose at which acute effects of radiation will be incurred and numerical estimates of the risk of delayed effects.
See the following two tables for general information concerning Health Effects &
Cancer Risks.
EP-AD-000-125, Revision 9, Page 8 of 13
Tab 8 EP-PS-1 05-8 EMERGENCY EXPOSURE EXTENSIONS CHECK 0 Health Effects Associated with Whole Body Absorbed Doses Received Within a Few Hours(a)
Whole Body Absorbed Early Fatalities(b) Whole Body Absorbed Prodromal Effects(c)
Dose (rad) (percent) Dose (rad) (percent affected) 140 5 50 2 200 15 100 15 300 50 150 50 400 85 200 85 460 95 250 98 (a) Risks will be lower for protracted exposure periods.
° Supportive medical treatment may increase the dose at wfiich these frequencies occur by approximately 50 percent.
(C) Symptoms (nausea, vomiting) which occur within a few hours after exposure to large doses of radiation and which usually precede more serious health effects.
Approximate Cancer Risk to Average Individuals from 25 Rem Effective Dose Equivalent Delivered Promptly Average Years of Life Lost If Age at Exposure Approximate Risk of Premature Death Premature Death Occurs (years) (deaths per 1,000 persons exposed) (years) 20 to 30 9.1 24 30 to 40 7.2 19 40 to 50 5.3 15 50 to 60 3.5 11
- 3. Review the HEALTH PHYSICS AND ALARA CONSIDERATIONS DURING EMERGENCIES which is attached.
- 4. Obtain appropriate approval signatures as outlined in the table below.
EXTENSION FROM I TO mrem (TEDE) mrem (TEDE) APPROVAL ACTIONS 4000 <25000 (ED or RM) and RPC ALARA REVIEW AND APPLY EMERGENCY EXPOSURE CONSIDERATIONS
>25000 (ED or RM) and RPC ALL OF ABOVE AND BRIEFING ON RISKS EP-AD-000-1 25, Revision 9, Page 9 of 13
Tab 8 EP-PS-1 05-8 EMERGENCY EXPOSURE EXTENSIONS CHECK O
- 5. If the Emergency Dose Extension is for greater that 4 rem (TEDE), have the volunteer sign the EMERGENCY EXPOSURE REQUEST Form acknowledging that they are a volunteer and are fully aware of the radiological risks of acute and delayed effects.
- 6. Upon completion of the activity requiring the Emergency Exposure perform the following:
oLI Collect, process, and evaluate personnel dosimetry devices when technically appropriate.
o Investigate the circumstances of all emergency exposures and confirm the dose received.
o Notify the NRC of emergency exposure as follows:
Immediate notification of the NRC is required for:
Notification of the NRC within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is required for:
o Assess the health consequences of all emergency exposures. Consult with a physician to determine the need for and extent of physical and biochemical examinations.
o Whole body greater than 25 rem (TEDE) should result in an examination of the exposed person by a physician.
o If internal exposure is suspected, quantitative measurements should be made as soon as reasonably feasible. Bioassays are required based on the following:
- Nasal smear or facial contamination greater than 1,000 cpm above background.
- Greater than 4 DAC-HRS in a day or less, or 20 DAC-HRS in a week or less.
EP-AD-000-1 25, Revision 9, Page 10 of 13
Tab 8 EP-PS-1 05-8 HEALTH PHYSICS AND ALARA CONSIDERATIONS DURING EMERGENCIES CHECK 0 1.0 Evaluate radiological conditions.
1.1 Obtain detailed survey data to ascertain:
1.1.1 Beta-Gamma radiation levels 1.1.2 Need for neutron measurements 1.1.3 Contamination levels and protective clothing requirements 1.1.4 Airborne radioactive materials 1.1.5 Variability of conditions over space and time 1.2 Evaluate personnel status.
1.2.1 Determine available dose under normal administrative dose objectives.
1.2.2 If essential, obtain approval from RADIATION PROTECTION COORDINATOR/EMERGENCY DIRECTOR for persons expected to exceed administrative objectives.
1.2.3 Follow criteria in PPL Emergency Personnel Dose Assessment and Protective Action Recommendation Guide when emergency exposures are deemed appropriate by EMERGENCY DIRECTOR.
1.2.4 Assess individual's history of exposure to airborne materials.
1.2.5 Assess individual's skills in relation to proposed task.
1.2.6 Assess individual's lifetime exposure history.
EP-AD-000-1 25, Revision 9, Page 11 of 13
Tab 8 EP-PS-1 05-8 HEALTH PHYSICS AND ALARA CONSIDERATIONS DURING EMERGENCIES CHECK 0 1.3 Determine proper type and placement of dosimeters.
1.3.1 Evaluate need for additional whole body dosimeters.
NOTE: For emergency exposures above 4 rem, the placement of several dosimeters on an Individual is recommended to determine spatial distribution of dose to the ndividual.
1.3.2 Evaluate need and placement of extremity dosimeters.
1.3.3 Evaluate need for additional dosimetry devices such as high range self-reading dosimeters, electronic dosimeters, and neutron dosimeters.
1.3.4 Evaluate need for time keeping.
1.4 Determine proper respirator equipment required to perform task.
NOTE: For tasks expected to last more than several hours, consider need for relief of team members.
1.5 Review the following ALARA items:
NOTE: The detail and scope of ALARA reviews are to be commensurate with the magnitude of doses expected, numbers of people involved, and urgency of required task.
1.5.1 Consider the trend of exposures vs. the importance of the task:
- a. Important and critical task with rising exposure rates will require the dispatch of teams as quickly as possible to reduce exposures.
- b. Unimportant or less critical task could be delayed until exposure rates begin to trend downward.
EP-AD-000-125, Revision 9, Page 12 of 13
Tab 8 EP-PS-1 05-8 HEALTH PHYSICS AND ALARA CONSIDERATIONS DURING EMERGENCIES CHECKE 1.5.2 When time permits the following should be included in the ALARA review:
- a. Consider the use of remote handling devices or other special tools.
- b. Consider the use of portable shielding.
- c. Consider the need for mock-ups or other practice exercises.
- d. Assess the number of people required to assure all have essential productive roles.
- e. Consider the magnitude of doses received by team members in transit to work location.
EP-AD-000-125, Revision 9, Page 13 of 13
Tab 9 EP-PS-105-9 METNENT DATA ACQUISITION OPTIONS The following are sources of meteorological and ventilation data at Susquehanna SES:
A. ACQUISmON OF METNENT DATA FROM THE PICSY TERMINAL
- 2. All required meteorological and ventilation (METNENT) inputs for the MIDAS dose projections can be obtained by selecting the METNENT DATA display option on the E-PLAN menu.
- a. Vent and Primary Met Tower Data is displayed on page 1 of this display.
- b. Use the PAGE FORWARD command if the Back-up Tower data is required.
- c. Should neither the Primary or Back-up Tower be available, obtain the Downriver Tower data as follows:
- 1) At the command line, type GDVMS05B and [ENTER] for Downriver Tower wind speed.
- 2) At the command line, type GDVMX09B and [ENTER] for Downriver Tower wind direction.
- 3) At the command line, type GDVMX10B and [ENTER] for Downriver Tower sigma theta.
- 4) Press Escape [ESC] to return to the SSES Logo display.
- d. Other options - see Step 6 below.
- 3. If the Primary Met Tower AT data is not available, determine the wind speed corrected stability class as follows:
- a. Determine the initial (uncorrected) stability class using the measured value of sigma theta and the Supplemental Meteorological Information Table 1 (or page 2 of the PICSY screen).
- b. Determine the wind speed corrected stability classification using the initial classification, the measured wind speed, and, as appropriate, either Table 2 or Table 3.
EP-AD-000-124, Revision 21, Page 1 of 8
Tab 9 EP-PS-1 05-9
- 4. The PICSY QUALITY CODES for the display colors are as follows:
YELLOW: DATA ACCEPTABLE RED: DATA EXCEEDS WARNING LIMIT MAGENTA: DATA EXCEEDS ALARM SETPOINT WHITE: DATA SUSPECT
- 5. If a hard copy printout of the information is required you may either
- a. Select the PRINT option using the pull down menu (screen copy takes approximately 3 minutes to complete); or
- b. Initiate the METNENT DATA LOG option as follows:
- 1) On the E-PLAN menu, select the FREE FORMAT LOG MENU.
- 2) To activate the TSC log, press Fl], [22], and [ENTER].
To activate the EOF log, press [Fl], 9], and [ENTER].
NOTE: Be sure to read the log description because there are 2 logs for the TSC and 2 logs for the EOF.
- 3) The log will start printing at the next quarter hour.
- 4) To deactivate the TSC log, press [F3], 122, and [ENTER]..
To deactivate the EOF log, press [F3], [9], and [ENTER].
- 6. If historical METNENT information is required, refer to the following instructions:
- a. At the command line, type. GD_AMET1ENT1 and [ENTER].
- b. Group point display for that display file will come up. Press the [F3] key for history.
(See bottom of screen for F key menu.) A dialog box will appear.
- c. The work file name to be used is ARCHIVE.D, which is the default for that field.
- d. Enter the desired retrieval time. Click on OK.
- e. Group point display will return with values for the specified retrieval time.
- f. Press the [F4] key to step through data points from the specified retrieval time to the current time.
NOTE: Not all desired data Is likely to be available for any one particular point In time.
EP-ADO00-124, Revision 21, Page 2 of 8
Tab 9 EP-PS-105-9
- g. Press the [F4] key if you want to step slowly through the data. Press the [F5] key if you want to step quickly through the data. (See bottom of screen for F key menu for more options.)
- h. The group point display will return to real time when history is complete. A message at the top of the screen will alert you that it is returning to real time.
- 6. To exit the menu, select the [ESC] key.
B. Site-specific meteorological information can be obtained by contacting either ABS Consulting or the National Weather Service (NWS).
- 1. ABS Consulting ABS Consulting is the primary meteorological contractor for the Susquehanna Steam Electric Station (SSES). ABS Consulting has the ability to integogate the primary and backup meteorological towers on a real-time basis and provide short and long-term weather forecasts for the site and surrounding area.
ABS Consulting provides this emergency service to PPL ONLY during normal working hours. The SSES Project Manager's name, phone number and mailing address are as follows:
ABS Consulting Mark Abrams (301) 907-9100
-(301) 921-2362 (Fax)
ABS Consulting Suite 200 4 Research Place Rockville, MD 20850 EP-AD-000-124, Revision 21, Page 3 of 8
Tab 9 EP-PS-1 05-9
- 2. NATIONAL WEATHER SERVICE The National Weather Service's (NWS) primary meteorological support responsibility for a radiological emergency at SSES resides with the NWS office at Binghamton, New York. Inthe event the Binghamton office is unable to provide this support, the designated backup is the NWS office in State College, Pennsylvania.
The role of the local NWS office is to provide weather information and forecasts in support of emergency response activities at SSES. The !1WS can be consulted over the telephone if data interpretations, assessment, or forecasting assistance are needed.
This information will include the following:
- Forecasts at current time and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> of:
- a. 10-meter and 60-meter wind speed and wind direction,_
- b. Precipitation rate in inches per 15 minutes, and,
- c. Boundary layer atmospheric stability described as STABLE, UNSTABLE, or NEUTRAL.
- Estimates of current 10-meter and 60-meter wind speed and wind direction in the event of complete loss of onsite and offsite meteorological instrumentation.-
- General weather forecast from current time to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> with special emphasis on significant weather occurrences such as major changes in wind speed, wind direction or synoptic weather patterns.
- Periodic weather updates at time intervals dictated by the on-going weather and emergency situation.
NOTE: The NWS should ONLY be contacted when meteorological support from ABS Consultinq Is not available (i.e., weekends, holidays, and during the overnight hours).
Whenever contacting the NWS, be sure to provide the following information:
- Name, Title, Facility, and Location
- Reason for the call
- Status of the Emergency
- Retum telephone number EP-AD-000-1 24, Revision 21, Page 4 of 8
Tab 9 EP-PS-105-9 The following telephone numbers are UNLISTED and should only be used for EMERGENCY situations.
PRIMARY CONTACT NWS EMERGENCY METEOROLOGICAL SUPPORT OFFICE National Weather Service Office Binghamton Regional Airport 32 Dawes Drive Johnson City, NY 13795 (607) 798-6625 (607) 729-7629 (607) 798-6624 (Fax)
BACKUP CONTACT NWS EMERGENCY METEOROLOGICAL SUPPORT OFFICE National Weather Service Office 227 W. Beaver Avenue, Suite 402 State College, PA 16801 (814) 237-1152 (814) 237-1153 (814) 234-9703 (Fax)
EP-AD-000-124, Revision 21, Page 5 of 8
Tab 9 EP-PS-105-9 PLANT COMPUTER METEOROLOGICAL DATA POINT IDENTIFIERS METEOROLOGICAL AVERAGING PARAMETER POINT ID* UNITS PERIOD PRIMARY TOWER-eastofthe art,300'high 1whitetower.
1Dm Wind Direction vmaO3 degrees 15 minutes 1Om Wind Speed vmaO6 mph 15 minutes Delta T'A vma0l 'C/50m 15 minutes Delta T B vmaO2 0C/50m 15 minutes 60m Wind Direction vmaO4 degrees 15 minutes 60m Wind Speed vmaO7 mph 15 minutes 1Dm Sigma Theta vmalO degrees 15 minutes 60m Sigma Theta vmx24 degrees 15 minutes Precipitation Rate vmaO9 in/hr 15 minutes Ambient Temperature vmtO8b O1 hour BACKUP TOWER - across from the SSES Learn ng Center. _ _
1Dm Wind Direction vmaO5 l degrees 15 minutes 1Dm Wind Speed vmaO8 l mph 15 minutes 1Dm Sigma Theta vmal2 degrees - 15 minutes DOWNRIVER TOWER - n Ro ust east of Nescopeck.
1Dm Wind Direction I vmxO9b degrees . 2 minutes**-
1Om Wind Speed vmsO5b mph 2 minutes**
1Om Sigma Theta vmx1 Ob degrees 2 minutes**
- Letters are given here in lower case to differentiate the letter o from the number 0.
EP-AD-000-1 24, Revision 21, Page 6 of 8
Tab 9 EP-PS-1 05-9 SUPPLEMENTARY METEOROLOGICAL INFORMATION TABLES TABLE 1 ATMOSPHERIC STABILITY CLASSIFICATION Stability Class Delta (Alternate) Plume Width Temperature Sigma Theta @ 10 miles % of Hrs at Code Title (VC150m) (degrees) (miles) SSES A Very Unstable _ _-.95 >22.5 5.7 6 B Unstable -. 94 to -.85 17.5 to 22.4 4.3 3 C Slightly Unstable -. 84 to -.75 12.5 to 17.4 3.3 4 D Neutral -. 74 to -.25 7.5 to 12.4 2.3 35 E Slightly Stable -.24 to .75 3.8 to 7.4 1.6 32 F Stable .76 to 2.0 2.1 to 3.7 1.1 12 G Very Stable >2.0 <2.1 .75 8 TABLE 2 TABE 3 DAYTIME NIGHTTIME (08:00 to 18:00) _(18:00 to 08:00) __
Initial Stability Class/ FINAL Initial Stability Class/ FINAL Wind Speed (MPH) VALUE Wind Speed (MPH) VALUE A A Wind Speed < 7 A Wind Speed < 6 F 7 sWind Speed < 9 B 65 Wind Speed<8 E_ _
9 SWind Speed < 13 C Wind Speed 2 8 D Wind Speed 2 13 D B B Wind Speed < 9 B Wind Speed <5 F 9< Wind Speed < 13 C 5 Wind Speed < 7 E Wind Speed 2 13 D Wind Speed 7 D C C Wind Speed < 13 C Wind Speed < 5 E Wind Speed 2 13 D Wind Speed > 5 D D,E, F, G D Any wind speed. D Any wind speed. D E
Wind Speed < 11 E Wind Speed 2 11 D Example: If wind speed is 9 mph and sigma F,G theta is 18 degrees @ 10 a.m., the initial Wind Speed <7 F stability class from Table 1 is B' and the wind speed corrected stability class from Table 2 is 7 Wind Speed < 11 E BC". Wind Speed 11 D EP-AD-000-124, Revision 21, Page 7 of 8
Tab 9 EP-PS-1 05-9 TABLE 4 WIND SECTORS AND DISTANCES _
Wind From Affected Affected EPB* On-Site Team Site Boundary % of Hrs Sector Degrees lSector Sector Distance (ml) Distance(mi) Distance(mi) Affected SSES 348 -11 N S 0.34 0.25 0.38 6 12 - 33 NNE SSW 0.34 0.37 0.39 9 34 - 56 NE SW 0.34 0.33 0.61 12 57 - 78 ENE WSW 0.34 0.39 1.22 11 79-101 E W 0.34 0.37 1.03 6 102 - 123 ESE WNW 0.34 0.41 0.61 4 124 - 146 SE NW 0.34 0.35 0.66 4 147 - 168 SSE NNW 0.34 0.29 0.59 4 169-191 S N 0.34 0.29 0.59 5 192 - 213 SSW NNE 0.34 0.39 0.78 7 214 - 236 SW NE 0.34 0.42 0.58 11 237 - 258 WSW ENE 0.34 0.52 0.49 7 259 -281 W E 0.34 0.45 0.48 4 282 - 303 WNW ESE 0.34 0.18 0.50 3 304 - 326 NW SE 0.34 0.20 0.43 3 326 - 348 NNW SSE 0.34 0.20 0.41 5
- EPB distances established at Exclusion Area Boundary distance of 1800 ft.
EP-AD-000-124, Revision 21, Page 8 of 8
Tab 10 EP-PS-1 05-1 0 VENT MONITOR DATA ACQUISITION
- 1. Determine which Channel is alarming on the SPING Control Terminal.
- 2. Press [PRINT] 6 [ENTER] to obtain a printout of all channels in Hi Alarm.
- 3. Determine Alarming Unit and Channel numbers from Printout.
DESCRIPTION UNIT # DESCRIPTION CHANNEL #
RB1 3 NOBLE GAS (LO) 5 RB2 4 NOBLE GAS (MID) 7 TB1 5 NOBLE GAS (HI) 9 SBGT 6 PAVSS N.G. (MID)1 TB2 7 PAVSS N.G. (HI) 2 PAVSS TB1 8 PAVSS SBGT 9 PAVSS TB2 10
- 4. Obtain Noble Gas concentrations in gCimin for each Alarming Unit and Channel as follows:
- a. Press [HIST 10 MIN] UNIT # [-] CHANNEL # [ENTER].
- b. Press [PRINT] [FILE] [ENTER].
- c. Examine the last full 10-minute data period (next to last concentration value).
- 1. If LO range <2.2E 2 Ccc, proceed to step 4d to obtain release rates in the ttCicc/min.
- 3. If MID range >7.8E+' I.LCIcc, repeat steps 4a and 4b using the Hi range detector.
- d. After the concentration history file is printed out, press [-] to scroll to "RELEASE RATE" and press [ENTER]. Wait for the panel display to change, press [PRINT]
[FILE] [ENTER] to print corresponding release rates in +/-lCiminute.
- e. Repeat steps 4a through 4d for all alarming noble gas channels.
- 5. Sum the release rates for Noble Gas channels in alarm and use this value for the MIDAS dose calculations.
EP-AD-000-183, Revision 6, Page 1 of 1
Tab 11 EP-PS-105-1 1 MIDAS OPERATING PROCEDURE TABLE OF CONTENTS SECTION PAGE A. INTRODUCTION/SYSTEM STARTUP 2 B. MENU B: FORWARD CALCULATIONS 4 C. MENU C: EVENT TREE NUREG-1228 CALCULATIONS 10 D. MENU D: DEFAULT ACCIDENT CALCULATIONS 14 E. MENU E-W: BACK CALCULATIONS 17 F. MENU G: BLOWOUT PANEL CALCULATIONS 23 G. DESCRIPTION OF INFORMATION PROVIDED ON THE MIDAS DOSE
SUMMARY
REPORT 29 H. INFORMATION FOR DISTANCES BETWEEN 10 AND 50 MILES 33 I. ACCIDENT DESCRIPTIONS 34 EP-AD-000-1 12, Revision 21, Page 1 of 40
Tab 11 EP-PS-1 05-11 A. INTRODUCTIONISYSTEM STARTUP
- 1. The following conventions are used in this procedure to describe computer operations:
- a. Bold, upper case text (i.e., CURRENT DATE), denotes text which appears on the screen.
- b. Underlined, uppercase text (i.e., LOGIN) denotes text to be typed.
- c. Bracketed, upper case text (i.e., [ENTER]), denotes special keys which are to be pressed.
- d. Most mouse selections can be made with a single click.
Single click RESET to cancel previous screemselections.
Double click RESET to back out of present menu.
- Double click to EXIT menu.
- 2. The met and vent spreadsheet will appear with all of the meteorological and ventilaion release rate parameters across the top of the page. The current time period is highlighted in the left-hand column. The first time interval is 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> before the current time and the last time interval is 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> after the current time.
- 3. All required meteorological and ventilation data for MIDAS can be obtained using the METNENT DATA ACQUISITION OPTIONS tab.
- 4. To start MIDAS on a DOS computer
- a. Tum ON each component (monitor, computer, and printer) of the computer system on which MIDAS is loaded.
- b. At the MIDAS logon screen, enter the password MIDAS and [ENTER].
- c. At the MIDAS MAIN MENU screen, select A: MIDAS (Dose Calculator) and [ENTER].
- d. The system will then display the CURRENT DATE. If the date is correct, press [ENTER]. If this date is incorrect, type the correct date using the format which is illustrated in the prompt and press [ENTER].
- e. The system will then display the CURRENT TIME, which is stored in the computer system's clock (24-hour clock format). If the time is correct, press [ENTER]. If this time is incorrect, type the correct time using the format which is illustrated in the prompt and press [ENTER].
EP-AD-00-1 12, Revision 21, Page 2 of 40
Tab 11 EP-PS-1 05-11
- f. The MIDAS logon screen will now appear for 20 seconds.
- 9. The ACCIDENT MENU SELECTION screen will appear. Select the appropriate calculation option and CONFIRM your selection.
- 5. To exit MIDAS on a DOS computer, double-click EXIT on each menu screen that appears. At the SECURITY MENU, press [F8] to log off.
- 6. To start MIDAS on a Windows computer:
- a. Turn on each component (monitor, computer, and printer) of the computer system on which MIDAS is loaded.
- b. At the WINDOWS LOGIN Screen, press [CANCEL].
- c. On the System Desktop, double click on the MIDAS Icon.
- d. The system will then display the CURRENT DATE. If the date is correct, press [ENTER]. If the date is incorrect, type the correct date using the format which is illustrated in the prompt and press [ENTER].
- e. The system will then display the CURRENT TIME, which is stored in the computer system's clock (24-hour dock format). If the date is correct, press [ENTER]. If the date is incorrect, type the correct time using the format which is illustrated in the prompt and press [ENTER].
- f. The MIDAS logon screen will now appear for a short time.
- 9. The ACCIDENT MENU SELECTION screen will appear. Select the appropriate calculation option and CONFIRM your selection.
- 7. To exit MIDAS on a Windows computer, double-clock EXIT on each menu screen that appears until you return to the System Desktop.
- a. On the System Desktop, select START, SHUTDOWN, SHUTDOWN THE COMPUTER, and press [YES].
EP-AD-000-1 12, Revision 21, Page 3 of 40
Tab 11 EP-PS-105-1 1 B. MENU B: FORWARD CALCULATIONS REQUIRED INPUTS ENGINEERING OR OPERATIONS SUPPORT IS REQUESTED FOR THESE CALCULATIONS.
PLANT CONDITIONS
- TIME OF REACTOR SHUTDOWN
- RELEASE START TIME
- DURATION OF RELEASE PROJECTION TIME ACCIDENT SOURCE TERM SELECTION MET DATA
- 10 M WIND SPEED
- 10 M WIND DIRECTION
- STABILITY CLASS
- PRECIPITATION RATE VENT DATA
- SITE TOTAL NOBLE GAS RELEASE RATES
- SITE TOTAL 1-131 RELEASE RATES (if available from Chemistry or as directed by RPC/DASU)
- SITE TOTAL PARTICULATE RELEASE RATES (if available from Chemistry or as directed by RPC/DASU)
- 1. The METNENT DATA CONTROL TABLE screen will appear.
- a. Select START NEW SCENARIO and then CONFIRM, OR
- b. If you have already initiated calculations and wish to modify either the existing met spreadsheet file or vent spreadsheet, select CURRENT SCENARIO EDIT and CONFIRM.
NOTE: CURRENT SCENARIO EDIT will include releases/doses from previous time steps, if applicable.
- c. Other options are available in the lower right hand section of the display if you wish to RESET or change your initial selection or EXIT the screen.
EP-AD-000-1 12, Revision 21, Page 4 of 40
Tab 11 EP-PS-1 05-11
- 2. The METEOROLOGICAL DATA spreadsheet will appear with all of the required meteorological parameters across the top of the page. Place the cursor on the data period corresponding to the start of release. Input the following met data:
NOTE 1: If the met data remains the same for successive time periods, the operator need only enter the met data once. MIDAS will persist the data to future time periods automatically.
NOTE 2: If a value is to be repeated in a field it can still be manually copied down the spreadsheet using the K (copy last) key while that value is highlighted.
- a. In the column labeled IOM SPD, enter the wind speed from the 10 meter onsite (primary) meteorological tower in MILES PER HOUR (MPH).
NOTE: If the primary meteorological tower-data is not available, refer to the Met Vent Data Acquisition Options tab for other options.
If the primary meteorological tower wind speed remains at "zero" during freezing and/or other inclement weather, that data point is likely invalid, and the backup tower wind speed should be used if available.
- b. In the column labeled 10M WD, enter the wind direction from the 10-meter onsite (primary) meteorological tower in DEGREES FROM (DEG FM).
- c. In the column labeled STAB CLS, enter the actual value for AT in DEGREES CENTIGRADE (preferred method) or the wind speed corrected stability class (Letter Code) if the primary tower data is not available. MIDAS will convert the letter entry to a numerical value.
- d. In the column labeled RAIN-LMH, enter the precipitation rate in INCHES PER 15 MINUTES (IN/15M). Divide the PICSY precipitation rate (inches/hr) by 4. If the precipitation rate is not available, estimation may be made by using the following table:
NO PRECIPITATION l (zero)
DRIZZLE or MIST LIGHT STEADY RAIN MEDIUM HEAVY DOWNPOUR HEAVY
- e. Type X when all data has been entered to save the data and exit out of the meteorological spreadsheet.
EP-AD-000-1 12, Revision 21, Page 5 of 40
Tab 11 EP-PS-105-1 1
- 3. A WEATHER SELECTION screen will appear if any of the meteorological data inputs are missing from the spreadsheet.
- a. If this screen appears, select RESET until you have returned to the METNENT DATA CONTROL TABLE screen.
- b. Select CURRENT SCENARIO EDIT and enter any missing meteorological values on the spreadsheet.
- c. Type X when all data has been entered to save the data and exit out of the meteorological spreadsheet.
- 4. The vent (GASEOUS VENT AND FLOW) spreadsheet will appear next. Enter current vent data. The data entry for each 15-minute period is as follows:
NOTE: Vent data may be entered in a regular numerical presentation (10000) or in scientific notation (1.OE+04).
- a. In the column labeled TOT NG RELEASE, enter the site total noble gas release rate in gCi/min.
- b. In the column labeled TOT 1-131 RELEASE, enter the site total 1-131 release rate in gCi/min. Unless valid data is available from Chemistry or data is authorized for use by the RPC/DASU, the 1-131 release rate should be calculated as follows:
TOT NG RELEASE (CVmin)/1 000 = TOT 1-131 RELEASE (Ci/min)
- c. In the column labeled TOT P RELEASE, enter the site total particulate release rate in giCi/min. Unless valid data is available from Chemistry or data is authorized for use by the RPC/DASU, the particulate release rate should be calculated as follows:
TOT NG RELEASE (l/Cmin)/10,000 = TOT P RELEASE (Ci/min)
- d. When the data entry is complete, press the X key to save the information and exit the spreadsheet.
EP-AD-000-1 12, Revision 21, Page 6 of 40
Tab 11 EP-PS-1 05-11
- 5. From the ACCIDENT SOURCE TERM SELECTION screen, select an appropriate accident source term, then CONFIRM. Select RESET if you wish to change your previous selection.
If no specific information on the type of release is available from Engineering, use the following as a guide in the selection of appropriate accident source term.
- a. Obtain Reactor Power from Engineering, Operations, or as follows:
- 1) From PICSY, select Unit #1 or Unit #2 formats to view affected unit.
- 2) Type STA and press [ENTER].
- 3) 'Reactor Power' is in the top left section.
- 4) Click on MET VENT to return to the MetNent data display.
- b. If the reactor is operating at or greater than 10% power, select the ATWS source term.
- c. If reactor power is at less than 10%, select the LOCA (Clad Failure) source term.
- d. If conditions indicate a fuel handling incident and a release from the refueling floor (Reactor Building floor 818'), select Fuel Handling Accident.
- 6. The RELEASE TIMING SELECTION screen will appear next. There are three lines to the screen.
- a. On Line 1, select TRI P DATE (date and time of reactor trip). Using the calendar wheel, enter the appropriate date and time of reactor trip.
CONFIRM to close the calendar wheel.
- 1) The time of reactor trip must be equal to or earlier than the START OF RELEASE.
- 2) The time of reactor trip can be set up to roughly one year (8,190 hours0.0022 days <br />0.0528 hours <br />3.141534e-4 weeks <br />7.2295e-5 months <br />) prior to the START OF RELEASE.
EP-AD-000-1 12, Revision 21, Page 7 of 40
Tab 11 EP-PS-1 05-11 NOTE (1): MIDAS assumes the reactor must be shutdown before a release can occur. The TRIP DATE triggers the start of decay for the accident mix.
NOTE (2): Even during an ATWS, where a release is in progress and the reactor has not shut down, a TRIP DATE must be entered to run MIDAS. It is recommended the same date and time for the START OF RELEASE be used for the TRIP DATE. Entering a date and time for reactor trip has no impact on decay of the ATWS mix.
- b. On Line 2, select START OF RELEASE. Using the calendar wheel, enter the appropriate date and time of the start of release. CONFIRM to close the calendar wheel.
- 1) If START NEW SCENARIO was selected,4e START OF RELEASE date/time entered should be the current date/time at which you are starting the calculation.
- 2) If CURRENT SCENARIO EDIT was selected, the previously entered START OF RELEASE should still be used, if met/vent date have been entered for each 15-minute period since that START OF RELEASE. Otherwise, select RESET until START NEW SCENARIO is selected.
NOTE: The START OF RELEASE is defined as the date and time of the first vent data entry.
- c. On Line 3, select REMAINING DURATION of the release. Using the numpad enter the duration of release, in minutes, and select EN or press
[ENTER] to close the numpad. If the duration of release is not known, use the default of 360 minutes.
NOTE: The REMAINING DURATION (DURATION OF RELEASE) can use forecasted or persisted data for up to 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> into the future.
- d. Select CONFIRM to continue with the calculation or RESET to change any of your previous choices.
EP-AD-000-1 12, Revision 21, Page 8 of 40
Tab 11 EP-PS-1 05-1 1
- 7. The PPL
SUMMARY
DATA SELECTION screen allows the user to select different options for the MIDAS DOSE ASSESSMENT
SUMMARY
SHEET.
- a. Select the projection time from the left-hand column if other than the default of six hours is needed.
NOTE: The 0.25-hour projection time should be used with extreme caution. Projected doses can be substantially underestimated.
- b. Select the PEAK SECTOR dose rate option; then CONFIRM. If you wish to change any of your previous choices, select RESET.
NOTE: The PEAK SECTOR is used to determine the highest dose rate in all 16 sectors. The alternate selection (CURRENT AFFECTED SECTOR) is applicable only when estimated dose rates from the current release period alone are requested by the RPC/DASU.
- 8. After the calculations have completed, the MIDAS DOSE ASSESSMENT
SUMMARY
SHEET will be displayed on the screen.
- a. If you want to select a different projection time or sector designation from the PPL
SUMMARY
DATA SELECTION screen, select RESTART REPORT.
- b. If you wish to view additional report options, select CONTINUE and, on the next page, MORE REPORTS.
- c. If you wish to continue with the next calculation, double click EXIT. This will return you to the ACCIDENT MENU SELECTION screen where the dose calculation process can be repeated using updated input values.
- d. If a hard copy is desired of any printout or plot displayed on the screen, press [PRINT SCRN].
NOTE: If a hard-copy printout is made of the MIDAS DOSE ASSESSMENT
SUMMARY
SHEET, be sure to fill in the required Information documenting the name of the dose calculator and approver.
EP-AD-000-1 12, Revision 21, Page 9 of 40
Tab 11 EP-PS-1 05-11 C. MENU C: EVENT TREE NUREG-1228 CALCULATIONS REQUIRED INPUTS ENGINEERING OR OPERATIONS SUPPORT IS REQUESTED FOR THESE CALCULATIONS.
PLANT CONDITIONS
- RELEASE PATHWAY
- CONTAINMENT CONDITIONS
- FILTRATION PROJECTION TIME MET DATA
- 10 M WIND SPEED
- 10 M WIND DIRECTION
- STABILITY CLASS
- PRECIPITATION RATE
- 1. The EVENT TREE NUREG-1228 SELECTION screen will appear.
- a. Using information provided by Engineering Support or Operations, select one cell in each row of the menu. When a cell in the current row is selected, the next row then appears.
NOTE: Event tree menu selections, which include a definition of plant release parameters, are included (Section I) for each NUREG-1228 accident release scenario.
- b. Using information provided by Engineering Support, select percent clad failure or percent fuel melt as follows:
(1) Left-click on percent clad failure (fuel melt).
(2) Using the numpad on the screen, input the percent clad failure (fuel melt) provided by Engineering Support, the EN (ENTER).
(3) CONFIRM your entry if correct. If incorrect, re-perform steps (1) and (2).
- c. CONFIRM entries to continue with the calculation or RESET if you wish to change any of your selections. You may also double-click EXIT to return to the ACCIDENT MENU SELECTION screen.
EP-AD-000-1 12, Revision 21, Page 10 of 40
Tab 11 EP-PS-1 05-11
- 2. The METNENT DATA CONTROL TABLE screen will appear.
- a. Select START NEW SCENARIO and then CONFIRM.
- b. Other options are available in the lower right hand section of the display if you wish to RESET your initial entries or EXIT the screen.
- 3. The METEOROLOGICAL DATA spreadsheet will appear with all of the required meteorological parameters across the top of the page.
NOTE: Ensure met data is entered for the current time. MIDAS will persist the data to future time periods automatically.
- a. In the column labeled 10M SPD, enter the wind speed from the 10-meter onsite (primary) meteorological tower in MILES PER HOUR (MPH).
NOTE: If the primary meteorological tower data is not available, refer to the Met Vent Data Acquisition Options tab for other options.
If the primary meteorological tower wind speed remains at "zero" during freezing and/or other inclement weather, that data point is likely invalid, and the backup tower wind speed should be used if available.
- b. In the column labeled 10M WD, enter the wind direction from the 10-meter onsite (primary) meteorological tower in DEGREES FROM (DEG FM).
- c. In the column labeled STAB CLS, enter the actual value for AT in DEGREES CENTIGRADE (preferred method) or the wind speed corrected stability class (Letter Code) if the primary tower data is not available. MIDAS will convert the letter entry to a numerical value.
- d. In the column labeled RAIN-LMH, enter the precipitation rate in INCHES PER 15 MINUTES (IN/i15M). Divide the PICSY precipitation rate (incheslhr) by 4. If the precipitation rate is not available, estimation may be made by using the following table:
NO PRECIPITATION R(zero)
DRIZZLE or MIST LIGHT STEADY RAIN MEDIUM HEAVY DOWNPOUR HEAVY EP-AD-000-1 12, Revision 21, Page 11 of 40
Tab 11 EP-PS-105-1 1
- e. Type X when all data has been entered to save the data and exit out of the meteorological spreadsheet.
- 4. A WEATHER SELECTION screen will appear if any of the meteorological data inputs are missing from the spreadsheet.
- a. If this screen appears, select RESET until you have returned to the MET/VENT DATA CONTROL TABLE screen.
- b. Select CURRENT SCENARIO EDIT and enter any missing meteorological values on the spreadsheet.
- c. Type X when all data has been entered to save the data and exit out of the meteorological spreadsheet.
- 5. The PPL
SUMMARY
DATA SELECTION screen allows-the user to-select different options for the MIDAS DOSE ASSESSMENT
SUMMARY
SHEET.
- a. Select the projection time from the left-hand column if other than the default of six hours is needed.
NOTE: The 1-hour projection time should be used with caution.
Projected doses can be underestimated.
- b. Select the PEAK SECTOR dose rate option; then CONFIRM. If you wish to change any of your previous choices, select RESET.
NOTE: The PEAK SECTOR is used to deter mine the highest dose rate in all 16 sectors. The alternate selection (CURRENT AFFECTED SECTOR) is applicable only when estimated dose rates from the current release period alone are requested by the RPC/DASU.
- 6. After the calculations have completed, the MIDAS DOSE ASSESSMENT
SUMMARY
SHEET will be displayed on the screen.
- a. If you want to select a different projection time or sector designation from the PPL
SUMMARY
DATA SELECTION screen, select RESTART PROGRAM.
- b. If you wish to view additional report options, select CONTINUE and, on the next page, MORE REPORTS.
- c. If you wish to continue with the next calculation, double click EXIT. This will return you to the ACCIDENT MENU SELECTION screen where the dose calculation process can be repeated using updated input values.
EP-AD-000-112, Revision 21, Page 12 of 40
Tab 11 EP-PS-1 05-11
- d. If a hard copy is desired of any printout or plot displayed on the screen, press [PRINT SCRN].
NOTE (1): If a hard-copy printout is made of the MIDAS DOSE ASSESSMENT
SUMMARY
SHEET, be sure to fill in the required information documenting the name of the dose calculator and approver.
NOTE (2): Engineering Support or Operations concurrence with the selections may be documented by their representatives' signatures on the printout.
EP-AD-000-1 12, Revision 21, Page 13 of 40
Tab 11 EP-PS-1 05-11 D. MENU D: DEFAULT ACCIDENT CALCULATIONS REQUIRED INPUTS ENGINEERING OR OPERATIONS SUPPORT IS REQUESTED FOR THESE CALCULATIONS.
MET DATA
- 10 M WIND SPEED
- 10 M WIND DIRECTION STABILITY CLASS
- PRECIPITATION RATE SOURCE TERM
- ACCIDENT SOURCE TERM SELECTION
- PROJECTION TIME
- 1. The METNENT DATA CONTROL TABLE screen will appear.
- a. Select START NEW SCENARIO and then CONFIRM.
- b. Other options are available in the lower right hand section of the display if you wish to RESET your initial entries or E)T the screen.
- 2. The METEOROLOGICAL DATA spreadsheet will appear with all of the required meteorological parameters across the top of the page.
NOTE: Ensure met data is entered for the current time. MIDAS will persist the data to future time periods automatically.
- a. In the column labeled 10M SPD, enter the wind speed from the 10-meter onsite (primary) meteorological tower in MILES PER HOUR (MPH).
NOTE: If the primary meteorological tower data is not available, refer to the Met Vent Data Acquisition Options tab for other options.
If the primary meteorological tower wind speed remains at "zero" during freezing and/or other inclement weather, that data point is likely invalid, and the backup tower wind speed should be used if available.
EP-AD-000-1 12, Revision 21, Page 14 of 40
Tab 11 EP-PS-1 05-11
- b. In the column labeled 10M WD, enter the wind direction from the 10-meter onsite (primary) meteorological tower in DEGREES FROM (DEG FM).
- c. In the column labeled STAB CLS, enter the actual value for AT in DEGREES CENTIGRADE (preferred method) or the wind speed corrected stability class (Letter Code) if the primary tower data is not available. MIDAS will convert the letter entry to a numerical value.
- d. In the column labeled RAIN-LMH, enter the precipitation rate in INCHES PER 15 MINUTES (IN/15M). Divide the PICSY precipitation rate (inches/hr) by 4. If the precipitation rate is not available, estimation may be made by using the following table:
NO PRECIPITATION Q(zero)
DRIZZLE or MIST LIGHT STEADY RAIN MEDIUM HEAVY DOWNPOUR I HEAVY
- e. Type X when all data has been entered to save the data and exit out of the meteorological spreadsheet.
- 3. A WEATHER SELECTION screen will appear if any of the meteorological data inputs are missing from the spreadsheet.
- a. If this screen appears, select RESET until you have returned to the METNENT DATA CONTROL TABLE screen.
- b. Select CURRENT SCENARIO EDIT and enter any missing meteorological values on the spreadsheet.
- c. Type X when all data has been entered to save the data and exit out of the meteorological spreadsheet.
- 4. From the ACCIDENT SOURCE TERM SELECTION screen, select an appropriate accident source term, then CONFIRM.
- 5. A PERCENT FAILURE FOR LOCA screen will appear if the clad failure or fuel melt accident source term is selected. Input the percent of clad failure or fuel melt using the numpad and CONFIRM.
EP-AD-000-1 12, Revision 21, Page 15 of 40
Tab 11 EP-PS-105-1 1
- 6. The PPL
SUMMARY
DATA SELECTION screen allows the user to select different options for the MIDAS DOSE ASSESSMENT
SUMMARY
SHEET.
- a. Select the projection time from the left-hand column if other than the default of six hours is needed.
NOTE: The 1-hour projection time should be used with caution.
Projected doses can be underestimated.
- b. Select the PEAK SECTOR dose rate option; then CONFIRM. If you wish to change any of your previous choices, select RESET.
NOTE: The PEAK SECTOR is used to determine the highest dose rate in all 16 sectors. The alternate selection (CURRENT AFFECTED SECTOR) is applicable only when estimated dose rates from the current releaseperiod alone are requested by the RPC/DASU.
- 7. After the calculations have completed, the MIDAS DOSE ASSESSMENT
SUMMARY
SHEET will be displayed on the screen.
- a. If you want to select a different projection time .or sector designation from the PPL
SUMMARY
DATA SELECTION screen, select RESTART PROGRAM.
- b. If you wish to view additional report options, select CONTINUE and, on the next page, MORE REPORTS.
- c. If you wish to continue with the next calculation, double click EXIT. This will return you to the ACCIDENT MENU SELECTION screen where the dose calculation process can be repeated using updated input values.
- d. If a hard copy is desired of any printout or plot displayed on the screen, press [PRINT SCRN].
NOTE: If a hard-copy printout is made of the MIDAS DOSE ASSESSMENT
SUMMARY
SHEET, be sure to fill in the required information documenting the name of the dose calculator and approver.
EP-AD-00-1 12, Revision 21, Page 16 of 40
Tab 11 EP-PS-105-1 1 E. MENU E-W: BACK CALCULATIONS REQUIRED INPUTS ENGINEERING OR OPERATIONS SUPPORT IS REQUESTED FOR THESE CALCULATIONS.
PLANT CONDITIONS
- TIME OF REACTOR SHUTDOWN
- RELEASE START TIME
- DURATION OF RELEASE
- ACCIDENT SOURCE TERM SELECTION
- PROJECTION TIME MET DATA 10 M WIND SPEED
- 10 M WIND DIRECTION
- STABILITY CLASS
- PRECIPITATION RATE FIELD DATA
. 3 FT (CW) SURVEY METER READING
- DISTANCE FROM PLANT
- 1. The MET/VENT DATA CONTROL TABLE screen will appear.
- a. Select START NEW SCENARIO and then CONFIRM.
- b. If you have already initiated calculations and wish to modify the existing met spreadsheet file, select CURRENT SCENARIO EDIT and CONFIRM.
- c. Other options are available in the lower right hand section of the display f you wish to RESET your initial entries or EXIT the screen.
EP-AD-000-1 12, Revision 21, Page 17 of 40
Tab 11 EP-PS-1 05-11
- 2. The METEOROLOGICAL DATA spreadsheet will appear with all of the required meteorological parameters across the top of the page.
NOTE: Ensure met data is entered for the current time. MIDAS will persist the data to future time periods automatically.
- a. In the column labeled IOM SPD, enter the wind speed from the 10-meter onsite (primary) meteorological tower in MILES PER HOUR (MPH).
NOTE: If the primary meteorological tower data is not available, refer to the Met Vent Data Acquisition Options tab for other options.
If the primary meteorological tower wind speed remains at uzerow during freezing and/or other inclement weather, that data point is likely invalid, and the backup tower wind speed should be used if available.
- b. In the column labeled IOM WD, enter the wind direction from the 10-meter onsite (primary) meteorological tower in DEGREES FROM (DEG FM).
- c. In the column labeled STAB CLS, enter the actual value for AT in DEGREES CENTIGRADE (preferred method) or the wind speed corrected stability class (Letter Code) if the prima'y tower data is not available. MIDAS will convert the letter entry to a numerical value.
- d. In the column labeled- RAIN-LMH, enter the precipitation rate in INCHES PER 15 MINUTES (IN/15M). Divide the PICSY precipitation rate (inches/hr) by 4. If the precipitation rate is not available, estimation may be made by using the following table:
NO PRECIPITATION l(zero)
DRIZZLE or MIST lIGHT STEADY RAIN MEDIUM HEAVY DOWNPOUR I HEAVY I
- e. Type X when all data has been entered to save the data and exit out of the meteorological spreadsheet.
EP-AD-000-1 12, Revision 21, Page 18 of 40
Tab 11 EP-PS-1 05-11
- 3. A WEATHER SELECTION screen will appear if any of the meteorological data inputs are missing from the spreadsheet.
- a. If this screen appears, select RESET until you have returned to the METNENT DATA CONTROL TABLE screen.
- b. Select CURRENT SCENARIO EDIT and enter any missing meteorological values on the spreadsheet.
- c. Type X when all data has been entered to save the data and exit out of the meteorological spreadsheet.
- 4. From the ACCIDENT SOURCE TERM SELECTION screen, select an appropriate accident source term, then CONFIRM.
If no specific information on the type of release is available from Engineering, use the following as a guide in the selection of an appropriate accident source term:
- a. Obtain Reactor Power from Engineering, Operations, or as follows:
- 1) From PICSY, select Unit #1 or Unit #2 formats to view affected unit.
- 2) Type STA and press [ENTER].
- 3) "Reactor Power" is in the top left section.
- 4) Click on MET VENT to return to the Metlent data display.
- b. If the reactor is operating at or greater than 10% power, select the ATWS source term.
- c. If reactor power is at less than 10%, select the LOCA (Clad Failure) source term.
- d. If conditions indicate a fuel handling incident and a release from the refueling floor (Reactor Building floor 818'), select Fuel Handling Accident.
EP-AD-000-1 12, Revision 21, Page 19 of 40
Tab 11 EP-PS-1 05-11
- 5. The next screen is the FIELD MONITOR PARAMETER SELECTION screen.
Select the appropriate cells and input the information requested using the numpad on the screen or enter the data using the computer keyboard. Once the data entry is complete, CONFIRM to continue with the calculation.
- a. Enter Field Team or ERMS Fixed Monitor gamma (EDE) dose rate whichever is appropriate.
- b. Enter the distance of the Field Team or Fixed Monitor from the plant as noted on the RMS Report or for the on-site team as noted on Table 4 of EP-AD000-1 24.
- c. If iodine air sample data is available, enter either the IODINE CARTRIDGE reading in net counts per minute or an IODINE CONCENTRATION value in p.Ci/cc. A zero (0) value may be entered for the net count per minute or P1Cicc measurementif indicated.
- d. If iodine data is not available, select the DEFAULT MIX option to characterize the iodine source term.
- 6. On the RELEASE TIMING SELECTION screen, enter the estimated remaining duration for the release, then CONFIRM. If the duration of release is not known, use the default of 360 minutes.
- 7. The PPL
SUMMARY
DATA SELECTION screen allows the user to select different options for the MIDAS DOSE ASSESSMENT
SUMMARY
SHEET.
- a. Select the projection time from the left-hand column if other than the default of six hours is needed.
NOTE: The 1-hour projection time should be used with caution.
Projected doses can be underestimated.
- b. Select the PEAK SECTOR dose rate option; then CONFIRM. If you wish to change any of your previous choices, select RESET.
NOTE: The PEAK SECTOR is used to determine the highest dose rate in all 16 sectors. The alternate selection (CURRENT AFFECTED SECTOR) is applicable only when estimated dose rates from the current release period alone are requested by the RPC/DASU.
EP-AD-000-1 12, Revision 21, Page 20 of 40
Tab 11 EP-PS-1 05-11
- 8. After the calculations have completed, the MIDAS DOSE ASSESSMENT
SUMMARY
SHEET will be displayed on the screen.
- a. If you want to select a different projection time or sector designation from the PPL
SUMMARY
DATA SELECTION screen, select RESTART PROGRAM.
- b. If you wish to view additional report options, select CONTINUE and, on the next page, MORE REPORTS.
- c. If you wish to continue with the next calculation, double click EXIT. This will return you to the ACCIDENT MENU SELECTION screen where the dose calculation process can be repeated using updated input values.
- d. If a hard copy is desired of any printout or plot displayed on the screen, press [PRINT SCRNI.
NOTE: If a hard-copy printout is made of the MIDAS DOSE ASSESSMENT
SUMMARY
SHEET, be sure to fill in the required information documenting the name of the dose calculator and approver.
- e. Remote Monitoring System perimeter monitoring location dose rates can be displayed by MIDAS using the perimeter monitoring dose rate screen option.
NOTE: The displayed values are only numeric dose estimates based on MIDAS calculations. They are not "real-timer readings from the perimeter monitor system.
Directions for accessing the MIDAS perimeter monitor dose rate screen option are as follows:
- 1) At the MIDAS DOSE ASSESSMENT
SUMMARY
SHEET screen, select CONTINUE.
- 2) On the next screen select MORE REPORTS.
- 3) From the MORE REPORTS SELECTION screen, select FM GAMMA DOSE RATE PLOT and CONFIRM.
- 4) From the REPORT PARAMETER SELECTION screen, choose the appropriate projection time and CONFIRM.
- 5) From the MAP SELECTION screen, select MAP SCALE and input 1.25 miles, then CONFIRM.
EP-AD-000-1 12, Revision 21, Page 21 of 40
Tab 11 EP-PS-1 05-11
- 6) On the next screen, select MAP FEATURES.
- 7) On the next screen, select CALCULATED PERIMETER MON DOSE RATES and CONFIRM.
- 8) To exit, select CONTINUE, MORE REPORTS, and EXIT.
EP-AD-000-1 12, Revision 21, Page 22 of 40
Tab 11 EP-PS-1 05-11 F. MENU G: BLOWOUT PANEL CALCULATIONS REQUIRED INPUTS ENGINEERING OR OPERATIONS SUPPORT IS REQUESTED FOR THESE CALCULATIONS.
PLANT CONDITIONS
- TIME OF REACTOR SHUTDOWN RELEASE START TIME
- PROJECTION TIME
- BLOWOUT PANEL ASSUMED TO HAVE LIFTED (RELEASE PATHWAY)
- 10 M WIND DIRECTION
- STABILITY CLASS
- PRECIPITATION RATE
- 1. The METNENT DATA CONTROL TABLE screen will appear.
- a. Select START NEW SCENARIO and then CONFIRM, OR
- b. If you have already initiated calculations and wish to modify the existing met spreadsheet file, select CURRENT SCENARIO-EDIT and CONFIRM.
NOTE: CURRENT SCENARIO EDIT will include releases/doses from previous time steps, if applicable.
- c. Other options are available in the lower right hand section of the display if you wish to RESET or change your initial selection or EXIT the screen.
EP-AD-000-1 12, Revision 21, Page 23 of 40
Tab 11 EP-PS-1 05-11
- 2. The METEOROLOGICAL DATA spreadsheet will appear with all of the required meteorological parameters across the top of the page. Place the cursor on the data period corresponding to the start of release. Input the following met data:
NOTE 1: If the met data remains the same for successive time periods, the operator need only enter the met data once. MIDAS will persist the data to future time periods automatically.
NOTE 2: If a value is to be repeated in a field it can still be manually copied down the spreadsheet using the K (copy last) key while that value is highlighted.
- a. In the column labeled 10M SPD, enter the wind speed from the 10 meter onsite (primary) meteorological tower in MILES PER HOUR (MPH).
NOTE: If the primary meteorological tower-data is not available, refer to the Met Vent Data Acquisition Options tab for other options.
If the primary meteorological tower wind speed remains at Nzero" during freezing and/or other inclement weather, that data point is likely invalid, and the backup tower wind speed should be used if available.
- b. In the column labeled 1M WD, enter the wind direction from the 10-meter onsite (primary) meteorological tower in DEGREES FROM (DEG FM).
- c. In the column labeled STAB CLS, enter the actual value for AT in DEGREES CENTIGRADE (preferred method) or the wind speed corrected stability class (Letter Code) if the primary tower data is not available. MIDAS will convert the letter entry to a numerical value.
- d. In the column labeled RAIN-LMH, enter the precipitation rate in INCHES PER 15 MINUTES (N/15M). Divide the PICSY precipitation rate (inches/hr) by 4. If the precipitation rate is not available, estimation may be made by using the following table:
NO PRECIPITATION Q(zero)
DRIZZLE or MIST LIGHT STEADY RAIN MEDIUM HEAVY DOWNPOUR HEAVY
- e. Type A when all data has been entered to save the data and exit out of the meteorological spreadsheet.
EP-AD-000-1 12, Revision 21, Page 24 of 40
Tab 11 EP-PS-105-1 1
- 3. The BLOWOUT PANEL SELECTION screen will appear.
NOTE: Blowout panel locations are shown on Figure 1 of this procedure tab.
- a. Using information provided by Engineering Support or Operations, select one cell in each row of the menu. When a cell in the current row is selected, the next row then appears.
- b. CONFIRM entries to continue with the calculation or RESET if you wish to change any of your selections. You may also double-click EXIT to return to the ACCIDENT MENU SELECTION screen.
- c. On the PERCENT CLAD FAILURE (or PERCENT FUEL MELT) screen, using information provided by Engineering Support, select percent clad failure or percent fuel melt as follows:
(1) Left-dick on percent clad failure (fuel melt).
(2) Using the numpad on the screen, input the percent clad failure (fuel melt) provided by Engineering Support, then EN (ENTER).
(3) CONFIRM your entry fcorrect. If incorrect, re-perform steps (1) and (2).
NOTE: Release rates used by MIDAS are those shown in Table 1 of this procedure tab, multiplied by the percent clad failure (fuel melt).entered, expressed as a fraction (e.g., the multiplier for 50% fuel melt would be 0.5).
- 4. A WEATHER SELECTION screen will appear if any of the meteorological data inputs are missing from the spreadsheet.
- a. Missing information will be indicated by a black box (with white lettering) in the left-hand column.
(1) Left-click on the black box in the left column.
(2) Using the numpad on the screen, input the response to the missing data.
(3) Repeat steps (1) and (2) to supply any other required information.
(4) CONFIRM your entry if correct. If incorrect, re-perform steps (1) and (2) for the data in error.
EP-AD-000-1 12, Revision 21, Page 25 of 40
Tab 11 EP-PS-1 05-11
- 5. The PPL
SUMMARY
DATA SELECTION screen allows the user to select different options for the MIDAS DOSE ASSESSMENT
SUMMARY
SHEET.
- a. Select the projection time from the left-hand column if other than the default of six hours is needed.
NOTE: The 0.25-hour projection time should be used with extreme caution. Projected doses can be substantially underestimated.
- b. Select the PEAK SECTOR dose rate option; then CONFIRM. If you wish to change any of your previous choices, select RESET.
NOTE: The PEAK SECTOR is used to determine the highest dose rate in all 16 sectors. The alternate selection (CURRENT AFFECTED SECTOR) is applicable-only when estimated dose rates from the current release period alone are requested by the RPC/DASU.
- 6. After the calculations have completed, the MIDAS DOSE ASSESSMENT
SUMMARY
SHEET will be displayed on the screen.
- a. If you want to select a different projection time or sector designation from the PPL
SUMMARY
DATA SELECTION screen, select RESTART PROGRAM.
- b. If you wish to view additional report options, select CONTINUE and, on the next page, MORE REPORTS.
- c. If you wish to continue with the next calculation, double click EXIT. This will return you to the ACCIDENT MENU SELECTION screen where the dose calculation process can be repeated using updated input values.
- d. If a hard copy is desired of any printout or plot displayed on the screen, press [PRINT SCRN].
NOTE: If a hard-copy printout is made of the MIDAS DOSE ASSESSMENT
SUMMARY
SHEET, be sure to fill in the required information documenting the name of the dose calculator and approver.
EP-AD-000-112, Revision 21, Page 26 of 40
Tab 11 EP-PS-1 05-11 FIGURE 1 I
I II EP-AD-0O-1 12, Revision 21, Page 27 of 40
Tab 11 EP-PS-105-1 1 TABLE I EVALUATION OF UNMONITORED RELEASES FROM STATION BLOWOUT PANELS DIRECTIONS
- 1. Select the appropriate station blowout panel location.
- 2. Select an appropriate accident source term mix.
- 3. Use the corresponding design base release rates for input into MENU B.
- 4. Enter the release rates for one (1) fifteen-minute time period.
NOTE: If Clad Failure or Fuel Melt mixes are selected, multiply the site total noble gas, 1-131, and particulate release rates by the appropriate fraction of clad failure or fuel melt prior to entering the values onto the vent spreadsheet (e.g., the multiplier for 50% FUEL MELT would be 0.5).
11 BLOWOUT PANEL LOCATION 131 ESIGN BASIS (SITE TOTAL) RELEASE RATES NOBLE GAS 1-131 PARTICULATE RCIC PUMP ROOM (MCVmin) (lCimin) f(jCi/min)
[2 ACCIDENT SOURCE TERM _
Normal Reactor Coolant Activity 1.2E+02* 1.8E+02 1.1 E+03 (LOCA) Reactor Depressurization-No FD 2.6E+06 8.4E+04 2.2E+04 (LOCA) 100% Clad Failure 2.IE+09 2.4E+08 9.1E+07 (LOCA) 100% Fuel Melt 4.3E+10 1.3E+09 1.7E+09 HPCI PUMP ROOM l (pCimin) (pCi/min) (pCi/min)
Normal Reactor Coolant Activity 2.IE+03* 3.2E+03 1.9E+04 (LOCA) Reactor Depressurization-No FD 4.6E+07 1.5E+06 3.8E+05 (LOCA) 100% Clad Failure 3.7E+10 4.3E+09 1.6E+09 (LOCA) 100% Fuel Melt 7.5E+1 I 2.3E+10 3.OE+10 HPCIIRCIC ROUTING AREA l (pCVmin) l Cimin) (plCilmin)
Normal Reactor Coolant Activity 3.2E+03* 4.9E+03 2.9E+04 (LOCA) Reactor Depressurization-No FD 7.OE+07 2.2E+06 5.8E+05 (LOCA) 100% Clad Failure 5.7E+10 6.5E+09 2.4E+09 (LOCA) 100% Fuel Melt 1.IE+12 3.5E+10 4.6E+10 RWCU PENETRATION ROOM -J (Ci/min) (pCi/min) (uCI/min) l Normal Reactor Coolant Activity 7.3E+03* 5.8E+03 6.6E+04 (LOCA) Reactor Depressurization-No FD 1.6E+08 2.6E+06 1.3E+06 (LOCA) 100% Clad Failure 1.3E+11 7.6E+09 5.5E+09 j (LOCA) 100% Fuel Melt 2.6E+12 4.1E+10 1.0E+1 I RBITB MAIN STEAM TUNNEL ] (pCimin) l (pCimin) (pCtmin)
Normal Reactor Coolant Activity 2.6E+04* l 3.9E+04 l 2.3E+05 (LOCA) Reactor Depressurization-No FD 5.6E+08 1.8E+07 4.7E+06 (LOCA) 100% Clad Failure 4.6E+11 5.2E+10 1.9E+10 (LOCA) 100% Fuel Melt 9.1E+12 2.8E+1 1 3.7E+1 1 FD = FUEL DAMAGE Value less than the TRM limit for noble gas release rate.
REFERENCE:
EC-RADN-1018, Evaluation of Unmonitored Releases from Station Blowout Panels, Revision 1, File R2-1.
EP-AD-000-1 12, Revision 21, Page 28 of 40
Tab 11 EP-PS-105-1 1 G. DESCRIPTION OF INFORMATION PROVIDED ON THE MIDAS DOSE ASSESSMENT
SUMMARY
SHEET
- 1. CALCULATION TYPE Menu option chosen for the calculation. Examples are Forward Calculation or Event Tree Calculation.
- 2. CURRENT TIME PERIOD Current meteorological time period used for dose projections provided on quarter hour increments to match met spreadsheet entries.
- 3. WEATHER CONDITIONS Meteorological data (wind speed, wind direction, affected-sector, stability class, and precipitation rate) used for the summary report dose projections.
- 4. REACTOR SHUTDOWN TIME Date and time of reactor shutdown.
- 5. RELEASE START TIME This is the date and time of first dose calculation as indicated by the first positive vent release rate value entered on the vent data spreadsheet or if the vent spreadsheet is not used, the date and time of the calculation..
NOTE: For MENU C: EVENT TREE NUREG-1228 CALCULATIONS, MENU D: DEFAULT CALCULATIONS, and MENU E-W: BACK CALCULATIONS, it is conservatively assumed that the date and time of reactor shutdown is concurrent with the start of release.
- 6. PROJECTION TIME This is the time X hours into the future, starting from the beginning of the current meteorological time period. X" is the number of hours the user chooses as the projection time (e.g., 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />).
- 7. REMAINING DURATION This is the remaining duration of the release for the calculation type chosen. For Event Tree calculations, that is always 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and for Blowout Panel calculations, 0.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br />.
EP-AD-000-1 12, Revision 21, Page 29 of 40
Tab 11 EP-PS-1 05-11
- 8. SOURCE TERM (for Forward and Back Calculations)
Identifies the source term used for the current dose projection summary report calculations. Choice of six options:
ATWS-Normal Reactor Coolant Activity (UNDECAYED)
Normal Reactor Coolant Activity (DECAYED)
- (LOCA) Coolant Activity Leak with Depressurization Spike-No Fuel Damage (LOCA) Cladding Failure-Gap Release
- (LOCA) Fuel Melt-Early In-Vessel Release
- Fuel Handling Accident
- 9. RELEASE CONDITIONS This section lists the release rates used in the calculation. The values are taken from user input for Forward calculations, inferred from ustr input of event conditions (Event Tree, Default, and Blowout Panel calculations, or inferred from user input of measured data in the field (Back calculations).
- 10. Content of this section varies by Calculation Type. The objective is to provide information about the assumptions used to infer the Release Conditions for the calculation or to provide additional information about the Release Conditions.
For Forward Calculations, isotopic release ratios are provided. These may be compared to default ratios and used to infer plant conditions, for example, status of filtration.
For Event Tree, Default, and Blowout Panel Calculations, event or default conditions are listed. From those conditions, Release Conditions are inferred.
For Back Calculations, measured field data are listed. From those data, Release Conditions are inferred.
- 11. DOSE RATE PROJECTIONS This table provides the TEDE, EDE, and THYROID CDE dose rates calculated at the OSCAR and EPB distances. These rate calculations are based on a variable projection/integration period for the current affected sector or peak sector (the usual user selection).
EP-AD-000-1 12, Revision 21, Page 30 of 40
Tab 11 EP-PS-1 05-11
- 12. INTEGRATED DOSE PROJECTIONS This table provides a TEDE and THYROID CDE dose projection calculated at the EPB, 2-mile, and 10-mile distances for varying projection times. The projection time will appear in the header line e.g., 4 HOUR INTEGRATED DOSE PROJECTION. The sector designation for this dose projection is based on the maximum calculated dose determined from all sixteen sectors for the given projection time (peak sector option, usually the users choice) or the calculated dose for the current affected sector. Information for distances between 10 and 50 miles is available using the More Reports' feature.
- 13. PERFORMEDIAPPROVED The sign-off for calculation results is done for documentation purposes. The intended approval" does not necessarily mean an independent verification of each input to the calculation but more an interactive discussion between the RPC/HP Level II Dose Calculator and/or DASU/DAST (or dose calculator) to ensure the calculated results are reasonable based on current plant and environmental information.
This sign-off process should occur before the calculated results are used for any emergency classification determinations or protective action recommendations.
EP-AD-000-1 12, Revision 21, Page 31 of 40
Tab 11 EP-PS-1 05-11 a'
us0WO90a I I3M ~ T-EP-AD-000-1 12, Revision 21, Page 32 of 40
Tab 11 EP-PS-105-1 1 H. INFORMATION FOR DISTANCES BETWEEN 10 AND 50 MILES
- 1. From the MIDAS DOSE ASSESSMENT
SUMMARY
SHEET screen, select CONTINUE and, on the next page, MORE REPORTS.
- 2. Select TEDE 4-DAY DOSE REPORT or THYROID CDE DOSE REPORT, depending on which PAR guide has been exceeded at the 10-mile distance.
- 3. On the REPORT PARAMETER SELECTION screen, select PROJECTION TIME until the appropriate PROJECTION TIME (0.25,4, 6, or 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />) is displayed on the screen; then select CONFIRM.
NOTE: The 0.25-hour projection time should be used with extreme caution. Projected doses can be substantially underestimated.
- 4. The screen will now display projected doses at the EPB and at 2, 5, 10, 25, and 50 miles. To obtain finer increments of distance, select CONTINUE until the desired range of distances is displayed.
NOTE: An objective is to determine the approximate distance from the plant at which dose projections are less than 1 rem TEDE and 5 rem THYROID CDE. A PAR is then likely to be issued to the next furthest 5-mile distance increment from the plant.
Example: A PAR for distances to 30 miles may be selected if projected doses become less than the PAG values (1 rem TEDE, 5 rem THYROID CDE) between 25 and 30 miles from the plant EP-AD-000-1 12, Revision 21, Page 33 of 40
Tab 11 EP-PS-1 05-11 ACCIDENT DESCRIPTIONS DEFAULT ACCIDENT DESCRIPTIONS (MENU B AND MENU D)
- 1. NORMAL REACTOR COOLANT ACTIVITY This accident scenario is defined as the release of reactor coolant system liquid and steam activity from the primary coolant system with no damage to the fuel and no activity spiking. The source term for this accident is normal reactor coolant system liquid and steam activity.
This accident scenario is defined as the release of reactor coolant system liquid and steam activity from the primary coolant system. Depressurization of the primary coolant system is assumed, resulting in an activity spike in the reactor coolant. The source term for this accident is normal reactor coolant liquid and steam activity plus the depressurization activity spike. There is no fuel damage.
- 3. LOCA (CLAD FAILURE)
This accident scenario is defined as a Loss-of-Coolant Accident which results in damage to the reactor fuel cladding. The source term for this accident is normal reactor coolant liquid and steam activity and a percentage of the activity in the fuel clad gap. For Menu D calculations, that percentage is entered as part of the calculation process. For Menu B calculations, the valid vent data entered define the severity of the event.
This accident scenario is defined as a Loss-of-Coolant Accident which results in damage to the reactor fuel. The source term for this accident is normal reactor coolant liquid and steam activity and a percentage of the activity in the reactor fuel. For Menu D calculations, that percentage is entered as part of the calculation process. For Menu B calculations, the valid vent data entered define the severity of the event.
- 5. FUEL HANDLING ACCIDENT This accident scenario is defined as a fuel handling accident which results in the release of spent fuel activity. The source term for this accident is spent fuel gap activity assuming a decay time after shutdown of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
EP-AD-000-1 12, Revision 21, Page 34 of 40
Tab 11 EP-PS-1 05-11
- 6. ATWS This accident scenario is used for releases from a reactor unit continuing to operate at or greater than 10% power. The source term for this accident is normal reactor coolant system liquid and steam activity. The source term is undecayed; that is, no reactor trip is assumed to have occurred.
NOTE (1): For Menu D calculations, design basis assumptions are utilized.
For example, design basis leakage rates are assumed and iodine filtration efficiency of 99% is assumed in those pathways for which filters are in place.
NOTE (2): The source term for Menu D accident types is fixed. Release rate is calculated by MIDAS by dividing the total activity released by a predetermined release duration (6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for all but fuel handling accidents, for which release duration is 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />).
NUREG 1228 EVENT TREE ACCIDENT TYPES (MENU C)
- 1. LOCA - DRYWELL RELEASE This accident is a Loss-of-Coolant Accident with an activity release into the drywell which bypasses the suppression pool for which filtration of activity by the Standby Gas Treatment System takes place before release to the environment.
- 2. LOCA - WETWELL RELEASE This accident is a Loss-of-Coolant Accident with an activity release through the suppression pool for which filtration of activity by the Standby Gas Treatment System takes place before release to the environment.
- 3. LOCA - CONTAINMENT BYPASS RELEASE This accident is a Loss-of-Coolant Accident with an activity release to the environment that bypasses the containment and the Standby Gas Treatment System.
- 4. ZIRCALLOY FIRE IN ONE THREE MONTH OLD BATCH This accident is a zircalloy fire in spent fuel that results in an activity release similar to a core melt. It assumes that the activity is filtered by the Standby Gas Treatment System prior to release.
EP-AD-000-1 12, Revision 21, Page 35 of 40
Tab 11 EP-PS-105-1 1
- 5. SPENT FUEL GAP RELEASE This accident is a release of fuel gap activity from the spent fuel pool with treatment by the Standby Gas Treatment System prior to release.
NOTE: Menu C (from NUREG-1 228 Event Tree Analyses) is used to relatively quickly provide a bounding estimate of offsite dose, for situations where there are substantial uncertainties in prediction of source term and any resultant doses.
EP-AD-000-1 12, Revision 21, Page 36 of 40
Tab 11 EP-PS-1 05-11 NUREG 1228 MENU STRUCTURE FOR DRYWELL RELEASE CONTAINMENT DRYWELL WETWELL BYPASS SPENT FUEL RELEASE RELEASE RELEASE POOL RELEASE (Clad Failure) (Fuel Melt) (Fuel Melt) Core Condition GAP RELEASE IN-VESSEL VESSEL MELT UNCOVERED SEVERE THROUGH 15-30 MIN DAMAGE UNCOVERED
> 30 MIN SPRAY ON
[ SPRAY OFF I Status of Drywell Containment Spray HOLDUP TIME HOLDUP TIME HOLDUP TIME Drywell Holdup Time:
<1 HOUR 2-12 HOURS 24 HOURS I Time from Release CATASTROPHIC DELAYED (DEFAULT) into Containment to CONTAINMENT RELEASE
- Start of Release into FAILURE -Environment(')
I LEAK RATE 100%/HOUR LEAK RATE 100%/DAY LEAK RATE 100%/DAY DESIGN LEAK RATE DESIGN LEAK RATE UNFILTERED FILTERED UNFILTERED FILTERED Catastrophic Failure to Isolate Containment 1%/Day Containment Failure (1) HOLDUP TIME is defined as drywell holdup time prior to release to the environment.
During this time period, credit is taken for drywell airborne activity removal due to plateout by natural processes and water sprays prior to release to the environment.
EP-AD-000-1 12, Revision 21, Page 37 of 40
Tab 11 EP-PS-1 05-11 NUREG 1228 MENU STRUCTURE FOR WETWELL RELEASE
[ DRYWELL RELEASE WETWELL RELEASE CONTAINMENT BYPASS SPENT FUEL POOL RELEASE RELEASE (Clad Failure) (Fuel Melt) (Fuel Melt) Core Condition GAP RELEASE IN-VESSEL VESSEL MELT UNCOVERED SEVERE THROUGH 15-30 MIN DAMAGE UNCOVERED
> 30 MIN
[ SATURATED
[ SUB-COOLED
] Conditions in Suppression Pool HOLDUP TIME HOLDUP TIME HOLDUP TIME Wetwell Holdup Time:
<1 HOUR 2-12 HOURS 24 HOURS Time from Release CATASTROPHIC DELAYED (DEFAULT) into Wetwell to Start CONTAINMENT RELEASE of Release into FAILURE Environment<')
LEAK RATE l LEAK RATE DESIGN DESIGN LEAK RATE LEAK RATE LEAK RATE 100%/DAY 100%/DAY 100%1HOUR FILTERED UNFILTERED FILTERED UNFILTERED Catastrophic Failure to Isolate Containment 1%/Day Containment Failure (1) HOLDUP TIME is defined as wetwell holdup time prior to release to the environment.
During this time period, credit is taken for wetwell airborne activity removal due to plateout by natural processes and water sprays prior to release to the environment.
EP-AD-000-1 12, Revision 21, Page 38 of 40
Tab 11 EP-PS-1 05-11 NUREG 1228 MENU STRUCTURE FOR CONTAINMENT BYPASS RELEASE CONTAINMENT DRY WELL WETWELL BYPASS RELEASE RELEASE RELEASE (Clad Failure) (Fuel Melt) (Fuel Melt) Core Condition GAP RELEASE IN-VESSEL VESSEL MELT UNCOVERED SEVERE THROUGH 15-30 MIN DAMAGE UNCOVERED
> 30 MIN I UNFILTERED I FILTERED Is Release Filtered?
RELEASE RATE RELEASE RATE TYPICAL DESIGN Release Rate, in 100%/HOUR 100%1DAY RELEASE RATE Terms of Percent of Core Inventory Catastrophic Failure to Isolate 1%IDay Containment Failure Containment EP-AD-000-1 12, Revision 21, Page 39 of 40
Tab 11 EP-PS-105-1 1 NUREG 1228 MENU STRUCTURE FOR SPENT FUEL POOL RELEASE CONTAINMENT WETWELL SPENT FUEL DRYWELL RELEASE BYPASS RELEASE POOL RELEASE RELEASE ZIRCALLOY FIRE GAP RELEASE GAP RELEASE Condition of Spent IN ONE 3 MONTH FROM ONE FROM 15 Fuel OLD BATCH 3 MONTH OLD BATCHES BATCH (TOTAL POOL)
SPRAY ON SPRAY OFF Status of Containment Spray (Default) into Pool HOLDUP TIME HOLDUP TIME Time from Release
<1 HOUR 2-12 HOURS from Fuel to Start of Release into CATASTROPHIC (DEFAULT) Environment(')
FAILURE OF REACTOR BUILDING LEAK RATE LEAK RATE LEAK RATE Release Rate, in 100%/HOUR 100%/DAY 100%/DAY Terms of Percent of UNFILTERED FILTERED Source Inventory Catastrophic Failure of Secondary Containment (1) HOLDUP TIME for a spent fuel pool release is defined as reactor building holdup time prior to release to the environment. During this time period, credit is taken for reactor building airborne activity removal due to plateout by natural processes and water sprays prior to release to the environment.
EP-AD-000-1 12, Revision 21, Page 40 of 40
Tab 13 EP-PS-1 05-13 ONSITE EMERGENCY MONITORING LOCATONS To Shi&")hny
- Remote Monitoring Station Locations
- OSCAR Monitoring Team Locations EP-AD-000-177, Revision 4, Page 1 of 1 (File R36-9)