ML19224B729
| ML19224B729 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/17/1979 |
| From: | Limroth D Metropolitan Edison Co |
| To: | Metropolitan Edison Co |
| References | |
| NUDOCS 7906220145 | |
| Download: ML19224B729 (4) | |
Text
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M'ETROPO LIT AN EDISON C O M P A N Y see,,o.,, o, o.m.,,,
eme,.c ui.ni,,, cc,no,.,o, Subject REMOVAL OF MATERIAL FROM Location TMI fiuclear Station WITHIN THE PROTECTED AREA Middletown, PA Date May 17, 1979 To DEPARTMEt1T HEADS Tiil SECURITY PERSONNEL HEALTH PHYSICS CONTROL POINTS UNIT I & II i
My memo of 14 May, same subject, prescribed certain restrictions regarding the removal of material from within the protected area.
This memo cancels and supercedes tha't guidance.
A large trash container has been located immediately south of the south parking lot. All trash will be deposited in this container.
fio further trash may be dumped in the old landfill area.
Prior to any trash being removed from the protected area, Health Physics is to be notified in order that it may be surveyed to ensure that no radioactive material is present.
(Survey is to be done with an E-520 or RM-14 or ecuivalent with a frisker probe.
Maximum contact reading not to exceed 100 cpm above background for release cirteria.)
Radioa.tive waste may be removed from within the protected area only under the escort of Health Physics personnel.
Waste may not be stored outside the protected area except in sealed drums or sealed LSA boxes.
Any such material will be stored only in designated stowage areas.
The contents of all trucks will be surveyed prior to being released from the protected area. A Health Physics technician is on call in the process center for this purpose.
Radioactive samples being transferred to counting labs on the Island are exempt from this memorandum.
Prior to pick up of trash from the dumpsters, in the south landfill area, the dumpster will be surveyed. Arrangement for such survey should be scheduled through the Met-Ed HP foremen with as much notice as possible.
This memorandum does not apply to any trash collected outside the protected area, w
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W AA 7t93 7 9 0 6 2 20t4f INTER-OFFICE MEMORANDUM b ~ 3M f
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4 May 20, 1979 OUTLINE RADIOLOGICAL INVESTIGATION REPORT 1.
a.
Installed Plant Equipment - Describe pre-incident condition of
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equipment such as area monitors, process monitors, environmental monitoring equipment, radwaste systems, communications equipment etc.
i b.
Portable Health Physics Equipment and Supplies - Describe equipment and supplies available and evaluate their adequacy.
Include items such as radiation survey instruments, protective clothing, respirators etc.
c.
E=ergency Facilities and Eculpment - Describe facilities and equipment available such as emergency kits, decontamination facilities, special communications equipment, decisional aids such as maps and isopleths, etc. and evaluate for compliance with regulatory requirements.
d.
Training - Describe health physics and emergency training conducted and determine compliance with regulatory requirements.
e.
Drills - Describe drills conducted and datermine if problems identified during these drills were corrected.
2.
Initial Emergency Response a.
Detection - Describe indications of the incident provided by area' radiation monitors, process radiation monitors, containment pressure and sump level monitors, and instrumentation monitoring reactor coolant system parameters.
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b.
Classification _ - State when local, site, and general emergency made and determine if these classifications classifications wer?
were time.ly and appropriate.
Organization Activation _ - State when the emergency organization c.
was activated. Evaluate timeliness of this activation.
Compare the organization implemented with the one specified in the T
Emergency Plan and comment on its effectiveness.
List key 4
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personnel and team members by job title.
d.
Notifications - Describe initial notifications of off-site personnel by the licensee and determine compliance with notification requirements in his emergency plan and procedures.
3.
Assessment, Corrective and Protective Actions Ef fluent Monitorine and Corrective Actions - Describe the pathway a.
of radioactive material from the reactor coolant system to the Describe effluent controls such as isolation of environment.
the "B" OSTG, closing atmospheric main steam du=p valves, and stopping IVST system discharge. Describe process effluent
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monitoring and sample results.
Verify thd licensee's assessment r
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A fr of "the quantity of radioactivity released, and-compare is L'!
~rel a e 4.th regulatory release limits..
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In-Plant Assessment and Protective Actions - Describe general f
b.
Y, surveys made by the licensee. Describe smeys for specific g.
entr.ies into the Auxiliary Buildings. Describe protective I
measures taken such as protective clothing, respirators,. pre-y.
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y planning, mockup training, use of shieldirg, bioassays, etc..
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Include discussion of baron analyses performed on reactor coolant samples. Assess the adequacy of licensee surveys :nd
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protective actions based on reasonable application of regulatory d:.
i requirements and accepted health physics practices. Consider
.c-t use of survey maps.
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Environmental Assessment and Protective Actions - Describe censurements made by the Cc=monwealth of Pa. and the NRC for which results were provided to the licensee.
Include ceteorological monitoring performed. Evaluate the adequacy of licensee measurements.
Evaluate the appropriattness of licensee's assess =ent of and response to measurement results.
Summarine results of off-site surveys and cc= pare with 10 CFR 20.105, 10 CFR 50 Appendix I, 10 CFR 100 siting criteria, and FS AR accident predicticus.
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