ML20058J884
| ML20058J884 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 07/01/1982 |
| From: | William Jones OMAHA PUBLIC POWER DISTRICT |
| To: | Jay Collins NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| Shared Package | |
| ML20058J878 | List: |
| References | |
| LIC-82-247, NUDOCS 8208120168 | |
| Download: ML20058J884 (5) | |
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1 Omaha Public Power District 1623 HARNEY e OMAHA, NEBRASMA 68102 S TELEPHONE S36 4000 ARE A CODE 402 July 1, 1982 LIC-82-247 m
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JUL 61982 I h Mr. J. T. Collins, Regional Administrator M
U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011
Reference:
Docket No. 50-285
Dear Mr. Collins:
Fort Calhoun Station 1982 Emergency Preparedness Exercise The Commission's letter to the Omaha Public Power District, dated January 14, 1982, requested the District provide a description of the scope of the annual emergency exercise and the objectives to be ful-filled by this exercise approximately 75 days prior to the exercise.
Accordingly, the subject information is provided in Attachments 1 and 2 for the Fort Calhoun Station's 1982 emergency exercise.
Sir cerely, f,
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W. C. Jones Division Manager Produ4tionOperations Attachments cc: Mr. Brian K. Grimes, Director Division of Emergency Preparedness Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D.C.
20555 l
LeBoeuf, Lamb, Leiby & MacRae l
1333 New Hampshire Avenue, N.W.
l Washington, D.C.
20036 8208120168 820809 l
PDR ADOCK 05000205 F
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FORT CALHOUN STATION 1982 EMERGENCY EXERCISE SCOPE SCTNARIO DESCRIPTION The 1982 annual rrcergency exercise at the Fort Calhoun Station will involve an inadvertent release of gaseous radioactivity from the-auxi-7 liary building, a rapid increase in the failed fuel monitor reading, and a large break LOCA, concurrent with a loss-of-offsite power. This sequence of events wi10 eventually result in a " General Errergency" classification, af ter sequentially attaining the other three emergency action levels. This sequence of cvents will also result in the mobili-zation of the complete Emergency Response and Recovery Organization.
The exercise will commence with the reactor operating at 100%
power, with one charging pump and one high pressure safety injection pump removed from service for maintenance.
Between midnight and 6:00 a.m., there will be a release of radioactive gas, due to equipment malfunction, from the auxiliary building to the environment which will be in excess of the Technical Specification limits. As required by the Fort Calhoun Station Radiological Emergency Response Plan and the Emergency Plan Implementing Procedures, the " Notification of Unusual Event" emergency classification will be declared and all necessary notifications and actions will be taken. A personnel injury will occur while attempting to isolate the malfunctioned equipment and will be treated accordingly.
Exercise Objectives 1, 4, 5, 9, 10, 11, 12, 13, and 20 of Attachment 2 will be addressed by this emergency classification.
Approximately one hour after.the " Notification of Unusual Event" classification is declared, the emergency exercise will escalate to the
" Alert" category, due to the failed fuel monitor indicating greater than a 1% fuel failure. All necessary notifications and actions associated with this classification will be taken. This emergency action level will address Exercise Objectives 1, 2, 9,10, and 11 of Attachment 2.
Approximately two hours into the event, a fire will be irdicated in the old maintenance shop by the fire det6ctor alarm, the fire will be visually verificd, and the Fort Calhoun Station fire brigade will be activated.
This event will address Exercise Objective 3 of Attachment 2.
During the pertod of two to four hours into the emergency, primary system parameters will indicate progressively higher leakage rates from the reactor coolant system. Approximately four hours into the emer-gency, the reactor coolant leakage rate will exceed the available charging pumps make-up capacity and the emergency will escalate to the
" Site Area Emergency" classification. All necessary notifications and actions associated with this classification will be taken. ~Af ter the
" Site Area Emergency" is declared and before the reactor is tripped, the reactor coolant system pressur@ill drop dramatically, indicating a large break LOCA. The reactor will shot down as a result of 'the reactor protective system and the engineered safeguards will initiate emergency core cooling and emergency AC power. One diesel generator will not start.
1 1
1 Approximately ten minutes after definite indication of the large break LOCA, offsite AC power will be lost.,, Because of the loss of offsite power, the loss of one diesel generator, the unavailability of one high pressure safety injection pump and one charging pump, and the indication of a large break LOCA, a " General Emergency" will then be declared due to the potential for core melt conditions.
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An operator will be dispatched to the diesel generator room to evaluate and determine the reason for the malfunction of the diesel j
genera tor.
Testing and repair of the disabled diesel generator will be planned and initiated. This action will demonstrate Exercise Objective 6 of Attachment 2.
I The gaseous fission product activity will be released to the environment at a containment leak rate of 0.2 percent of the free volume of containment per twenty-four hours.
It is anticipated that a significant number of fuel rods in the core will rupture and release fission products to the containment atmosphere.
Of the radioactivity released to containment, 100% of the noble gases and 25% of the iodine gases will be available for release to the environment.
Radiological monitoring teams will be dispatched to both onsite and offsite areas to track the plume of released activity and to verify dose / concentration projections and projected plume behavior.
Specific exercise objectives of Attachment 2 demonstrated by this sequence are items 1, 2, 4, 5, 8, 9, 10, 11, 12, 13, 14, 15, 16, 17, and 18.
Af ter the "Ceneral Emergency" classification is declared and all required notifications are completed and immediate actions taken, long term core coolino will be initiated, lhe monitoring teams will continue with the plume tracking and monitoring. The post-accident sampling system (PASS), if fully operational, will be operated to provide pertinent information to the Recovery Organization during recovery planning.
7 Output data from the PASS will also be used by the Technical Support Center staff to quantify core damage. Operation of the PASS will demonstrate Exercise Objective 7 of Attachment 2.
At the time the plant is considered to be in a stable condition, the emergency classification will be de-escalated based upon the dis-cretion of the Recovery Organization and offsite support agencies.
The emergency exercise will then be terminated. This action will demon-L strate Exercise Objective 19 of Attachment 2.
This scenario should F
provide for the demonstration of all Exercise Objectives as detailed in
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y FORT CALHOUN STATION 1982 EMERGENCY EXERCISE OBJECTIVES DESCRIPTION OF PERFORMANCE G0ALS The scenario was prepared in a manner to demonstrate specific pre-planned objectives. The following twenty (20) objectives have been incorporated into the 1982 emergency exercise for the Fort Calhoun Station and should be demonstrated:
1.
A capability to initiate the appropriate emergency classi-fication and commence necessary actions consistent with equipment status and instrument parameters.
2.
Notification methods of emergency response personnel and augmentation of the on-shift personnel.
3.
Fire brigade activation, practices, and communication.
4.
Initiation, direction, and control of radiological monitor teams.
5.
Plume tracking techniques by the radiological monitor teams, including equipment operation, radiological measurements, environmental sampling, and data reporting.
6.
The initiation, direction, and completion of damage control and emeroency repair capabilities by the onsite emergency organization.
7.
Operation of the reactor coolant post-accident sampling system, if fully operational, by the onsite emergency organi-zation group.
8.
Simulated evacuation of personnel from the site, including proper instruction to ensure evacuation to a safe offsite assembly area.
9.
Initial notification and follow-up status information for recovery organization personnel and offsite authorities.
10.
Coordinated communication between the control room, Operations Support Center, Technical Support Center, and Emergency Operations Facility.
11.
Coordinated communication with offsite authorities.
12.
Dose assessment, dose projection, and protective action methodology.
13.
Engineering evaluations of station conditions and proposed corrective action directives.
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14.
Public alert, notification, and information, including full siren sounding.
15.
Activation and operation of the fledia Release Center.
16.
Press release development and applicable press release is-suances.
17.
Accountability of personnel within the owner controlled area.
18.
Coordination of offsite radiological monitoring activities.
19.
De-escalation from the various emergency classifications and emergency termination decisions.
20.
Rescue of injured personnel, transport to medical facility, and radiological treatment.
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