ML17262B109
| ML17262B109 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 10/08/1992 |
| From: | Backus W, Polfleit P ROCHESTER GAS & ELECTRIC CORP. |
| To: | |
| Shared Package | |
| ML17262B108 | List: |
| References | |
| NUDOCS 9212220177 | |
| Download: ML17262B109 (42) | |
Text
THE ROCHESTER GAS AND ELECTRIC CORPORATION GZNNA STATION EMERGENCY PREPAREDNESS EXERCISE MANUAL 1992 PLUME EXPOSURE EMERGENCY PREPAREDNESS EXERCISE October 8, 1992 Pre ared By:
Pete S. Polfleit We y H. Backus Reviewed By:
Richard J. Watts Approved By:
R ar J. Beldue (Emergency Pl nning Milestone Committee)
COIROLLRD COPY KO ~
9212220177 920722 PDR ADOCK 05000244 F PDR I-1
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1~0 SCOPE AND ONSITE OBJECTIVES PLUME EXPOSURE PATHWAY'
~ 1 ~8ao e The 1992 Emergency Preparedness Plume Exposure Pathway Exercise will simulate accident events culminating in a radiological accident resulting in the activation of onsite and offsite facilities. The Exercise will involve events that test the effectiveness of the Ginna Station Emergency Preparedness Program and t integrated capabilities of certain elements of the h e State of New York, Wayne County and Monroe County emergency organizations. The Exercise will include the partial mobilization of state and local resources adequately verify their capability to respond to an t o accident at the Ginna Nuclear Power Plant.
1~2 Onsite Ob'ectives for the 1992 Ginna Evaluated Plume Ex osure Pathwa Exercise The major objective of the Exercise is to demonstrate the response capabilities of the Rochester Gas and Electric Corporation Emergency Organization. With n this overall objective, numerous individual objectives i
are specified as follows:
1~2~1 Demonstrate the ability to mobilize, staff and activate Emergency Response Facilities promptly.
1~2~2 Demonstrate the ability to fully staff facilities and to maintain staffing on an around-the-clock basis gf-$
through the use of relief shift rosters (limited shift changes may occur to allow for operational restrictions).
1~2 ~3 Demonstrate the ability to make decisions and to coordinate emergency activities.
1 '+4 Demonstrate the adequacy of facilities and displays and the utilization of procedures to support emergency operations.
1 ~ 2~5 Demonstrate the ability to communicate with all appropriate locations, organizations, and field personnel.
1~2~6 Demonstrate the ability to mobilize and deploy Radiation Survey Teams.
1~2~7 Demonstrate the appropriate equipment and procedures for the determination of ambient radiation levels.
1~2~8 Demonstrate the proper use of appropriate equipment and procedures for measurement of airborne radioiodine concentrations as low as 1.0 E-7 uCi/cc in the presence of noble gases.
1~2~9 Demonstrate the ability to project dosage to the public via plume exposure, based on Plant and field data, and to determine appropriate protective measures, Action based on Guidelines, plant conditions, Protective time estimates, expected available shelter, evacuation factors.
release duration, and other appropriate 1 ~ 2 ~ 10 Demonstrate the ability to notify offsite officials and agencies within 15 minutes of declaration of an emergency.
1 ~ 2 ~ 11 Demonstrate the ability to periodically update offsite officials and agencies of the status of the emergency based on data available at Ginna Station.
1 ~ 2 ~ 12 Demonstrate the ability to notify emergency support pools as appropriate (i.e., INPO, ANI, etc.).
1+2 13 Demonstrate the ability to notify onsite personnel using plant alarms and public address systems.
1 2 ~ 14 Demonstrate the organization's ability to assess plant parameters and symptoms indicative of degrading plant conditions, and relate such symptoms to prescribed Emergency Action Levels.
1 ~ 2 ~ 15 Demonstrate the organization's ability to properly classify emergency conditions.
1 ~ 2 16 Demonstrate the organizational ability and resources necessary to manage an accountability of personnel within the restricted area.
1 ~ 2 ~ 17 Demonstrate the organizational ability and resources necessary to control access to the site.
1 ~ 2 18 Demonstrate the ability to continuously monitor and control emergency workers'xposure.
1 ~ 2 19 Demonstrate the adequacy of facilities and displays to support the Joint Emergency News Center operations.
/
1 ~ 2 ~ 20 Demonstrate the ability to brief the media in a clear, accurate, and timely manner.
1 ~ 2.21 Demonstrate the ability to provide advanced coordination of information released to the public.
1 ~ 2 ~ 22 Demonstrate the ability to establish and operate rumor control in a coordinated fashion.
1 ' '3 Demonstrate the adequacy of in-plant post-accident sampling techniques and analysis.
1 ~ 2 ~ 24 Demonstrate the ability to develop preliminary short-term and long-term actions to support plant recovery.
1 ~ 2 ~ 25 Demonstrate the proper use of back-up communications in the event of selected communications e q u i p m e n t malfunction.
1 ~ 2 ~ 26 Demonstrate the ability to mobilize principal portions of the licensee emergency organization on an off-hours, unannounced basis. To be erformed as a musterin drill durin November 1992 1' '7 Demonstrate the ability to conduct a post-exercise critique which adequately characterizes licensee performance based upon controller and observer assessments.
1 3 Summar of Pro pseud Activities Table 1.1 provides a list of proposed RGEE activities.
TABLE 1 ~ 1 1992 GINNA STATION EMERGENCY PREPAREDNESS EXERCISE PLUME EXPOSURE PROPOSED ONSITE ACTIVITIES RGSE Notification of Agencies Actual Call Up of Personnel Actual*
Activate Organization Actual>>
Maintain Security Actual Conduct. Dose Assessment Actual protective Action Recommendations Actual Operate Joint News Center Actual Dispatch Field Survey Teams Actual-3**
Obtain PASS Sample Actual Call up of personnel and facility activation will be performed in sequence. A separate, off-hours mustering drill will be November 9, 1992.
conducted during the week of Field teams will be deployed and will demonstrate appropriate field monitoring techniques and communications with respective emergency response facilities. A minimum of 1 onsite and 2 offsite teams will be deployed.
SIMULATIONS o Respiratory protection and protective clothing will be simulated by onsite/offsite survey teams. In-Plant team-will don respiratory protection and protective clothing prescribed by Health Physics and Chemistry p e r s on n e 1 according to postulated scenario plant conditions.
o In general, Exercise participants should follow applied&
plant procedures as closely as possible, and will be stopped by Controllers before actual equipment is manipulated (except PASS). Simulated repairs and other corrective actions should be described to Controller-
/Evaluators as fully as possible.
SUMMARY
OF PROPOSED OFFSITE ACTIVITIES It is anticipated that Wayne and Monroe Counties and New York State personnel will participate to perform the following minimum functions:
- 1. Command and Control
- 2. Dose Assessment
- 3. Joint New Center Staffing
- 4. Protective Action Decisionmaking
- 5. Communications
EXERCISE SCENARIO GINNA STATION 1992 EMERGENCY PREPAREDNESS EXERCISE INITIAL CONDITIONS 1~ The R. E. Ginna Nuclear Power Plant is operating at approximately 974 rated thermal power. The Plant has been operating at this power level continuously for approximately 150 days.
2 ~ The "A" Steam Generator (S/G) primary to secondary leak rate increased approximately 5 days ago to a calculated 60cc/min. At approximately 0630 hours0.00729 days <br />0.175 hours <br />0.00104 weeks <br />2.39715e-4 months <br /> this morning the primary to secondary leak rate has again increased significantly as indicated by a substantial increase in radiation monitor R-15 (Air Ejector). Radiation monitor R-19 (S/G Blowdown) has also indicated an increase in activity. The Health Physics/ Chemistry Department is in the process of analyzing samples to determine the calculated leak rate.
3 ~ Equilibrium Primary Coolant Isotopic activity as of 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> (10/8/92 is provided in table 9.2 of scenario Section 9.3. Total activity is 2.56 microcuries/gram.
Chemistry Log Sheet, available from the Controller.
4 ~ The Reactor Coolant System (RCS) total leakage is 0.361 GPM as of 0400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br /> this morning and has been increasing.
Identified RCS Leakage is 0.073 GPM.
- 5. General weather conditions are partly cloudy with no current precipitation. For purposes of the Exercise, additional meteorological information in the Simulator Control Room should be obtained from the Plant Process Computer System (PPCS).
- 6. The Primary Water Treatment Plant is secured for major maintenance that will take approximately 3 days. the 100,000 Gallon Outside Condensate Storage Tank is at 20%
Level. A Demineralizer Trailer has been ordered and is scheduled to arrive at 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br /> today.
7~ The House Heating Boiler is in service and Nuclear Steam is secured.
GINNA STATION 1992 EMERGENCY PREPAREDNESS EXERCISE ONSITE SEQUENCE OF EVENTS APPROPRIATE SCENARIO TIME TIME EVENT DESCRIPTION 0700 -00/15 Initial Conditions established 0715 00/00 Announcement to Commence Annual Emergency Exercise 0730 00/15 The Health Physics/Chemistry Department informs the Control Room that the "A" S/G UNUSUAL calculated leak rate is approximately EVENT 450cc/min (i.e., = 0.125 gpm).
ANTICIPATED RESULTS Control Room Operators should begin performing the applicable actions of Operating Procedure 0-6.10 (Plant Operations with Steam Generator Tube Leak Indication).
An orderly Plant shutdown should commence to be in Hot Shutdown within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and to be less than 350'F in the RCS within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> as required by Plant, Technical Specification.
An Unusual Event should be declared in accordance with EPIP 1-0, "Ginna Station Event Evaluation and Classification," EAL:
Steam Generator Tube Rupture (SGTR); Steam Generator Tube Leakage >
.1 GPM as identified by sampling.
Appropriate offsite notifications should be made per EPIP 1-5.
If an Unusual Event not declared in approximately 15 minutes, a contingency message should be given out to declare it.
APPROPRIATE SCENARIO TIME TIME EVENT DESCRIPTION 0755 00/40 The "A" S/G ARV pops open and cannot be closed from the Control Room.
ANTICIPATED RESULTS Control Room Should send an Auxiliary Operator to the Steam Header Area to close the Isolation Valve on the "A" S/G ARV.
Operators performing the applicable actions of 0-2.1.
Technical Su ort Center The Plant Manager, Operations Assessment Manager, and Duty Engineer should be manning the TSC for Offsite Communications Assistance per EPIP 1-5.
0810 00/55 The Auxiliary Operator sent to isolate the "A" S/G ARV reports to the Control Room that the "A" S/G ARV is isolated, but he has noticed a steam leak on the "B" S/G ARV, between the ARV and the ARV Isolation Valve.
ANTICIPATED RESULTS Control Room Should inform people manning the TSC of the "B" S/G ARV Line steam leak.
May request Auxiliary Operator to isolate the "B" S/G ARV.
Operators performing the applicable actions of 0-2.1.
Should inform the people manning the TSC of the "A" S/G ARV problem and isolation.
APPROPRIATE SCENARIO TIME TIME EVENT DESCRIPTION Technical Su ort Center May request that the "B" S/G ARV be isolated or may wait until Maintenance personnel have inspected it.
May inform Control Room that they will take actions to have Maintenance personnel inspect for the "A" And "B" S/G ARV problems.
0815 01/00 Annunciator G-22 (ADFCS System Trouble) alarms.
ANTICIPATED RESULTS Control Room Operators perform the applicable actions of AR-G.22.
Operators should check the S/G levels to ensure proper level control.
Operators should inform the people manning the TSC and I & C Department of the ADFCS problem.
The CCW Surge Tank Lo Level Alarm (AR-A-13) 0840 01/25 annunciates and the CCW level indicates it is decreasing.
ANTICIPATED RESULTS Control Room Operators perform the applicable actions of Alarm Response Procedure AR-A-13 (CCW Surge Tank Lo Level 41.24).
Operators should send an Auxiliary Operator into the Auxiliary Building to identify the CCW Leak.
Should inform the people manning the TSC of the CCW leak.
APPROPRIATE SCENARIO TIME TIME EVENT DESCRIPTION 0850 Ol/35 Auxiliary Operator checking the CCW leak in Auxiliary Building informs Control Room that the lA CCW Pump Mechanical Seal is leaking and spraying on the pump motor.
The running 1A CCW Pump trips out on overcurrent and annunciator (AR-A-17) alarms. The standby 1B CCW pump starts automatically and deliverers required flow.
ANTICIPATED RESULTS Control Room Operators perform the applicable actions of abnormal procedure AP-CCW.2 (Loss of CCW during power operation).
Operators request the Auxiliary Operator sent to identify the CCW leak in the Auxiliary Building, to isolate the suction and discharge of the 1A CCW Pump and rack out its electrical breaker.
Operators should inform the people manning the TSC of the 1A CCW Pump problems.
0855 01/40 The ADFCS problem with the MFW Regulating Valves is repaired.
ANTICIPATED RESULTS Control Room Operators continue shutting Plant down per 0-2.1.
0905 01/45 Auxiliary Operator isolating the 1A CCW Pump informs Control Room that the Suction and Discharge Valves are closed and the electrical breaker is racked out.
NTICIPATED RESULTS Control Room Operators should ensure that 1A CCW Pump Control Switch is in pull stop and CCW Surge Tank level has returned to normal.
APPROPRIATE SCENARIO TIME TIME EVENT DESCRIPTION 0915 02/00 The following events occur simultaneously:
~ Pressurizer level and pressure decreases ALERT uncontrollably.
~ A reactor trip occurs automatically from low pressurizer pressure or is manually activated by the operator.
~ A safety injection occurs automatically from low pressurizer pressure or is manually activated by the operator.
~ The <<A" S/G water level increases uncontrollably.
~ All safeguards equipment required is operating.
ANTICIPATED RESULTS Control Room Operators performing the immediate actions of E-0 (Reactor trip or safety injection).
An ALERT should be declared in accordance with EPIP 1-0, "Ginna Station Event Evaluation and Classification," EAL: Steam Generator Tube Rupture (SGTR): SGRT >
100 GPM. Appropriate onsite and offsite notifications should be made per EPIP 1-5.
If and ALERT is not declared in approximately 15 minutes, a contingency message should be given out to declare it.
Operators transition to E-3 (Steam Generator Tube Rupture) and start performing its applicable actions.
0945 02/30 Accident Response and Evaluation continues.
ANTICIPATED RESULTS Control Room Operators performing the applicable actions of E-3 (Steam Generator Tube Rupture) to stabilize the Plant.
0
APPROPRIATE SCENARIO TIME TIME EVENT DESCRIPTION Technical Su ort Cente The TSC should be nearing operational readiness of the Emergency Response Organization.
The TSC, when operational, should send repair teams into the Auxiliary Building to evaluate the 1A CCW Pump and motor problems.
The TSC, when operational should send repair teams out to evaluate the >>A>> and >>B>> S/G ARV problems if not already done.
Emer enc 0 erations Facilit EOF may be activating at this time due to Plant conditions.
1000 02/45 Accident response and evaluation continues.
TICIPATED RESULTS Control Room Operators performing the applicable actions of E-3 (Steam Generator Tube Rupture) to stabilize the Plant.
Technical Su ort Center The TSC should be assuming command and control.
1015 03/00 Annunciator J-9 (Safeguard Breaker Trip)
Alarms.
ANTICIPATED RESULTS Control Room When operators check the Board, the >>A>> SW Pump Switch indicates a white disagreement light and the >>A>> SW Pump indicates tripped.
Operators/TSC should send an Auxiliary Operator to the Screen House to check on >>A>>
SW pump.
Operators should inform the TSC of the >>A>>
SW Pump problem.
APPROPRIATE SCENARIO TIME TIME EVENT DESCRIPTION 1030 03/15 The Auxiliary Operator sent to the Screen House to check the "A" SW Pump reports to SITE AREA the Control Room/TSC that he can find EMERGENCY nothing wrong with the "A" SW Pump but he has smelled the strong odor of gas through-out the building with the strongest odor in the Basement.
ANTICIPATED RESULTS Control Room Should request that the Auxiliary Operator find the shutoff valves for the natural gas and propane gas to the Screen House and close them.
Should inform the TSC of the gas problem in the Screen House.
If not already isolated, should send Auxiliary Operator to isolate the "B" an S/G ARV when requested to do.
Technical Su ort Center The TSC, after assessing Plant conditions, should:
Declare a SITE AREA EMERGENCY in accordance with EPIP 1-0, "Ginna Station Event Evaluation 'and Classification," EAL:
Hazards being experienced or projected; entry of uncontrolled flammable gases into vital areas.
Appropriate notifications of offsite agencies should be made per EPIP 1-5.
If a Site Area Emergency is not declared in approximately 15 minutes, a contingency message should be given to declare it.
TSC should inform the EOF of Plant conditions and the Site Area Emergency Declaration.
A is Site Evacuation should determined necessary.
be commenced if it
APPROPRIATE SCENARIO TIME TIME EVENT DESCRIPTION Re air Teams Repair team sent out to check the CCW Pump should report that the 1A CCW Pump Mechanical seal needs replacing and that the 1A CCW Pump motor needs to be cleaned and dried. They report this will take approximately 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. They also report that the 1B CCW Pump Mechanical Seal is leaking a small amount.
Repair Team sent out to check the "A" S/G ARV control problem should report that the ARV's Mercoid controller needs to be replaced. They report that approximately 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to do.
it will take If not done earlier, the Repair Team sent out to check the "B" S/G ARV Steam leak request that it be isolated.
1045 03/30 Accident response and evaluation continues.
If not done earlier, the Auxiliary Operator sent out to isolate the "B" S/G ARV steam leak reports back that it is isolated.
ANTICIPATED RESULTS Co trol Room Operators performing the actions of E-3 (Steam Generator Tub Rupture) should have stabilized the Plant at approximately this time and be awaiting determination by the TSC as to what post SGTR cooldown procedure to use.
If not of the done earlier, should inform the TSC "B" S/G ARV steam leak isolation.
Technical Su ort Center The TSC should be evaluating the flammable gas problem in the Screen House and be taking corrective actions required to return the Screen House to a safe condition.
The TSC Dose Assessment should calculate and quantify any release paths to the environment.
TSC should have determined and informed the Control Room to use ES-3.1 (Post-SGTR Cooldown using Backfill).
APPROPRIATE SCENARIO TIME TIME EVENT DESCRIPTION Re air Teams Repair sent out to check the "B" S/G Team ARV steam leak reports that it the steam leak was from a >-inch hole appears that drilled almost through the pipe, and also that a flange is leaking.
They report that one and a half it hours will take approximately to repair the leak.
1100 03/45 Condensate Storage Tank (CST) levels decrease to 5 feet.
ANTICIPATED RESULTS Control Room Operators should refer to ER-AFW.1 (Alternate Water Supply to AFW Pumps) per foldout page of ES-3.1, Statement 4, which states, "If CST level decreases to less than 5 feet, then switch to alternate AFW supply (Refer to ER-AFW.1, Alternate Water Supply to AFW Pumps) and perform applicable actions.
Should inform TSC of the low level in the CSTs.
TECHNICAL SUPPORT CENTER TSC evaluating Plant conditions and taking action where required.
TSC should inform security of the as found condition of the "B" S/G ARV steam leak.
TSC Dose Assessment performing offsite dose calculations as required.
TSC should be expediting the repair of the S/G ARVs because of their use during such events as loss of condenser and Plant cooldown.
TSC should send a Repair Team to check out the "A" SW Pump problem when the Screen House is declared safe for entry.
TSC should inform EOF of Plant status and problems.
APPROPRIATE SCENARIO TIME . TIME EVENT DESCRIPTION
~eecurit Should be evaluating the drilled hole in the "B" S/G ARV pipe.
Emer enc 0 eration Facilit The EOF, assessing after it is manned, should Plant conditions and take start action as required.
1120 04/05 The "A" S/G ARV Mercoid is repaired and ready for return to service.
ANTICIPATED RESULTS Control Room Operators performing applicable actions of ES-3.1 (Post-SGTR Cooldown using Backfill).
Operators performing applicable actions ER-AFW.1.
Operators should return the "A" S/G ARV to service if requested by the TSC.
Technical Su ort Center TSC evaluating Plant conditions and taking actions where required.
TSC Dose Assessment performing offsite dose calculations as required.
TSC may request the Control Room to return the "A" S/G ARV to service.
~Secur it Should be evaluating the nB" S/G ARV drilled hole in the pipe.
Emer enc 0 erations Facilit EOF should be assessing Plant conditions and taking action as required.
APPROPRIATE SCENARIO TIME TIME EVENT DESCRIPTION EOF Dose Assessment should be performing offsite Dose Assessment, as required, in parallel with the TSC Dose Assessment.
The EOF should be assuming command and control at approximately this time.
Re air Teams Performing actions as required to return equipment to service as soon as possible.
1145 04/30 The >>B>> S/G ARV steam leak is repaired and ready for return to service.
ANTICIPATED RESULTS Control Roo Operators should be performing the applicable actions of the ES-3.1 (Post-SGTR Cooldown using Backfill).
Technical Su ort Center TSC evaluating Plant conditions and taking action as required.
EOF evaluating Plant conditions and taking action as required.
TSC should request Control Room to return the >>B>> S/G ARV to service.
=1230 05/15 Recover/Re-entry discussions should commence. This should include preliminary discussions about short term and intermediate term concerns, including preliminary designation of the Recovery Organization.
State and counties may also conduct parallel discussions. Recovery/Re-entry interface between TSC/EOF and offsite agencies should be demonstrated as time allows.
<<1315 06/00 After all Exercise Objectives have been demonstrated, the Exercise will be terminated.
RADIOLOGICALS RY 9.1 Radiolo ical Summar A Source Term The radiological source term assumed for this scenario was selected to include appropriate quantities of noble gas and radioiodine resulting from the postulated accident scenario.
Protective action recommendations i.e., sheltering or evacuation for certain Emergency Response Planning Areas (ERPAs) will not be required based upon the anticipated declaration of a Site Area Emergency and plant conditions. As a result of accident release rates, the projected whole body and thyroid doses will not exceed EPA Protective Action Guides beyond the Site Boundary.
The assumed noble gas and radioiodine release quantities are shown in Figure 9.1 as a function of time. The scenario involves two release points which is from the Air Ejector and the "A" Atmospheric Relief Valve (ARV). This occurs as follows:
Pre-Steam Generator Tube Rupture Time Release Point Release Rate C'ec 0700- Air Ejector 1.77 E-3 (Noble Gas) 0915 2.24 E-8 (Radioiodine)
The noble gas-to-radioiodine ratio assumed is 7.89 E4:1 during this period of release.
Time Release Point Release Rate Ci sec 0755- 8.32 E-3 (Noble Gas) 0810 1.76 E-9 (Radioiodine)
The noble gas-to-radioiodine ratio assumed is 7.89 E4:1 during this period of release.
Steam Generator Tube Rupture Time 8 Release Rate Ci sec 0915- Air Ejector 5.24 E-1 (Noble Gas) 0935 2.55 E-4 (Radioiodine)
The noble gas-to-radioiodine ratio assumed is 2000:1 during this period of release. Isotopic breakdowns of assumed noble gas, radioiodine and particulate release quantities are provided in Table 9.1.
Time Release Point Release Rate Ci sec 0935- Air Ejector 6.23 E-2 (Noble Gas) 0955 3.12 E-5 (Radioiodine)
The noble gas-to-radioiodine ratio assumed is 2000:1 during this period of release. Isotopic breakdowns of assumed noble gas, radioiodine and particulate release quantities are provided in Table 9.1.
B. Inte rated Offsite Doses Due to Plume E osure The downwind integrated doses from the scenario release are as follows:
Time Release Point Inte rated Dose Rem 0700- Air Ejector 1.25 E-4 (Whole Body) 0915 8.75 E-7 (Child Thyroid) 0755- 6.S2 E-5 (Whole Body) 0810 7.63 E-9 (Child Thyroid)
F 0915- Air Ejector 5.34 E-3 (Whole Body) 0935 1.48 E-3 (Child Thyroid) 0936- Air Ejector 6.S1 E-4 (Whole Body) 0955 1.81 E-4 (Child Thyroid)
Total Whole Body Dose (at 8ite Boundary) = 6.13 E-3 Rem Total Child Thyroid Dose (at 8ite Boundary) = 1.66 E-3 Rem C. Princi al Plant Radiolo ical Indications Figures 9.1 through 9.3 provide trend plots for key plant radiological indications, including plant vent concentration, letdown monitor level, containment radiation level and reactor coolant concentration.
TABLE 9 The assumed release quantities for the Ginna Exercise Scenario are summarized as follovs:
Time: 0915-0935 hr Nuclide Curie Sec Total Curies Released Kr-85 4. 0 E-04 4.8 E-01 Kr-85m 1.3 E-02 1.7 E+01 Kr-87 1' E-02 2.3 E+01 Kr-88 2 ' E-02 2.5 E+01 Xe-131m 4.9 E-03 5.9 E+00 Xe-133 3' E-01 4.0 E+02 Xe-133m 4.9 E-02 5.9 E+01 Xe-135 4.9 E-02 5.9 E+01 Xe-135m 1.6 E-02 1.9 E+01 Xe-138 6' E-02 7.6 E+01 Total Noble Gas 5~2 E-01 6 ' E+02 I-131 7.5 E-05 9 ' E-02 I-132 4.9 E-05 5' E-02 I-133 4.6 E-05 5.5 E-02 I-134 4' E-05 5.0 E-02 I-135 4' E-05 5' E-02 Total Radioiodine 2~6 E-04 3~1 E-01 Long-Lived Particulate 1+2 E-09 1~5 E-06
TABLE 9.1 (continued)
The assumed release quantities for the Ginna Exercise Scenario are summarized as follows:
Time : 0936 0955 hr Nuclide Curie Sec Total Curies Released Kr-85 4.8 E-05 5' E-02 Kr-85m 1.5 E-03 1.8 E+00 Kr-87 2.1 E-03 2.5 E+00 Kr-88 2.5 E-03 3.0 E+00 Xe-131m 5.8 E-04 7.0 E-01 Xe-133 3.9 E-02 4.7 E+01 Xe-133m 5.8 E-03 7.0 E+00 Xe-135 5.8 E-03 7.0 E+00 Xe-135m 1.9 E-03 2.3 E+00 Xe-138 7.5 E-03 9.0 E+00 Total Noble Gas 6 ' E 02 7 ~ 5 E+01 I-131 8.9 E-06 F 1 E-02 I-132 5.8 E-06 7.0 E-03 I-133 5.5 E-06 6' E-03 l-134 5.0 E-06 6' E-03 I-135 5.1 E-06 6' E-03 Total Radioiodine 3~1 E-05 3 ' E-02 Long-Lived Particulate 1 ~ 4 E-10 i+7 E 07
FIGURE 9.1 ASSUMED SOURCE TERMS C I/SEC 1.0E+00 - -; .
1.0E -01 1.0E -02 1.0E-03 1.0E -04 1.0E-05 1.0E-06 1.0E -07 1.0E-08 1.0E-09 1.0E-10 1.0E-11 77788888999999000011112222 1 1 1 1 1 1 1 1 1 1 1 1 34501134013345013401340134 0 5 5 0 0 5 0 5 0 5 0 6 5 6 0 5 0 5 0 5 0 5 0 5 0 5 CLOCK TIME
~ NOBLE GAS CI/SEC ~ RADIOIODINE CI/SEC
FIGURE 9.2 AIR EJECTOR VENT CONCENTRATIONS U CI/CC 1.0E+01 1.0E+00 1.0E -01 1.0E -02 1.0E -03 1.0E -04 1.0E -05 1.0E -06 1.0E -07 1.0E -08 1.0E -09 1.0E -10 1.0E-11 1 1 1 1 1 1 1 1 1 1 1 1 7 7 8 8 8 8 9 9 9 9 9 9 0 0 0 0 1 1 1 1 2 2 2 2 3 4 0 1 3 4 0 1 3 3 4 5 0 1 3 4 0 1 3 4 0 1 3 4 0 5 0 5 0 5 0 5 0 5 5 5 0 5 0 5 0 5 0 5 0 5 0 5 OLOCK TIME NOBLE GAS ~ RADIOIODINE
FIGURE 9.3 RCS CONCENTRATIONS VS TIME UCI/GM 1.0E +02 1.0E+01 1.0E+00 1.0E -01 1 1 1 1 1 1 1 1 1 1 1 1 7 7 8 8 8 8 9 9 9 9 0 0 0 0 1 1 1 1 2 2 2 2 3 4 0 1 3 4 0 1 3 4 0 1 3 4 0 1 3 4 0 1 3 4 0 5 0 5 0 5 0 5 0 5 0 5 0 5 0 5 0 5 0 5 0 5 CLOCK TIME TOTAL GAS ~ TOTAL IODINE
METEOROLOGICAL ASSUMPTIONS
Meteorolo ica Conditions Basis The meteorological conditions for this scenario were based upon historical meteorological data recorded by the Ginna primary weather tower and the National Weather Service on Au ust 22 1988. Minor editting was performed on the data to provide the wind direction and atmospheric stability conditions required by the scenario during the period of release.
National Weather Service and other Exercise controllers will provide Exercise participants weather forecast summaries based on the meteorological data and other supporting information available from the historical record.
The goal of this approach is to provide participants with more realistic forecast information.
Scenario Assum tions The scenario begins with light, southerly winds which shift and become northeasterly by mid-morning.
During the period of release due to the Steam Generator Tube Rupture (0915-0955 hr), the average meteorological conditions are as follows:
Wind Speed 5 mph (at 33 ft)
Wind Direction 50 degrees (at 33 ft; wind from)
Pasquill Stability = E
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