ML18030A337

Forwards Explanation of Dose Assessment Procedure,Offsite Monitoring & Radiological Assessment Re Onsite Emergency Organization.Detailed Calculational Techniques Included in Emergency Plan Implementing Procedure

ML18030A337
Person / Time
Site:	Susquehanna
Issue date:	08/19/1981
From:	Curtis N PENNSYLVANIA POWER & LIGHT CO.
To:	Schwencer A Office of Nuclear Reactor Regulation
References
PLA-910, NUDOCS 8108250268
Download: ML18030A337 (4)

Text

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSIOV NBR:8108250268 DOC ~ DATE: 81/08/19 NOTARIZED:

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50 3BS Susquehanna Stean Electrtc Staticnt Unit t, pennsyI'va a~a AUTH',NAiHE AUTHOR AFFILIATION CURTISI V ~ ~ ~

Pennsyl,vania Power 8 Light'o ~

R EC I P ~ 4 A.4IK" RECIPIKNT AFFILIATION SCHWK4CKR/AD Licensing, Branch 2

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Pennsylvania Power 8 Light Company Two North Ninth Street

~ Allentown, PA 18101

~ 215/ 7705151 Norman W. Curtis Vice President-Engineering 6 Construction-Nuclear 21 5 / 770-5381 August 19, 1981 Mr, A. Schwencer, Chief Licensing Branch No.

2 Division of Project Management U.S. Nuclear Regulatory Commission Washington, D.C.

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-X~r.i'USQUEHANNA STEAM ELECTRIC STATION DOSE ASSESSMENT PROCEDURES ER 100450 FILE 841-2 PLA-910 DOCKET NOS.

50-387 AND 50-388

Dear Mr. Schwencer:

Attached is an explanation of the dose assessment procedure planned for Susquehanna SES.

This information supplements our previous letter, PLA-887.

Very truly yours, 4.L.O N.

W. Curtis Vice President&ngineering 6 Construction-Nuclear WEB/mks Attachment cc:

R.

M. Stark USNRC S. Chestnut USNRC pgS" 8l08250268 8i08i9 PDR ADOCK 05000387 F

PDR

Radiolo ical Assessment and Off-Site Monitorin Prior to the activation of the entire On-site Emergency Organization, the Emergency Director may dispatch off-site radiological monitoring teams.

These teams will consist of two persons per team, trained in the use of portable radiation monitoring equipment.

When dispatched, the teams will proceed to the Emergency Operations Facility where they will pick up emergency kits containing portable monitoring equipment and portable radios.

After an operatinal check of the equipment including a radio operations

check, they will pick up an emergency vehicle and proceed to their first, monitoring location.

They will be controlled by the Radiation Support Manager and will report all readings to him.

The plant has capability to dispatch two radiation monitoring teams within 30-60 minutes of the emergency declaration if necessary.

For gaseous

releases, the first step in the assessment process is to estimate the noble gas and iodine source release terms in microcuries per second.

These source release terms are input to the SSES computerized Emergency Radiation Dose Projection Service (RADOSE) or to a Manual backup system if the automatic system fails.

Effluent monitor readings are in ~Ci/sec~ ~Ci/10 minutes, or ~Ci/hour.

The SSES RADOSE operator receives ~Ci/10 minute values for each of the five SSES vents and converts these values to Ci/minute for input to the computer system.

Ten minute averaged meteorological data is automatically input to the computer from the primary meteorological tower.

Switchover to the backup meteoro-logical tower is automatic in cases of primary tower failure.

The RADOSE system output consists of whole body and thyroid dose rates at 9 distances along the centerline of each of the 16 Susquehanna EPZ sectors and at points cor-responding to population centers in the Susquehanna area.

Up to 15 additional distances and up to 21 points for dose calculation can be selected by the operator.

The RADOSE system outputs dose rate at a given time and accumulates doses when repeated RADOSE runs are made.

In addition, the code calculates and displays the time to reach Protective Action Guide levels at the calculated dose rates, plume dimensions, and travel times for the plume to reach specified locations.

RADOSE is programmed to repeat dose calculation runs automatically at frequencies not to exceed once every 10 minutes.

Real-time meteorological data is input for each separate run.

Radioactivity release rates are assumed to be constant until new values are substituted by the operator.

Once dose projections are made, the radiation monitoring teams can be directed to locations of interest to take readings and confirm the projections.

The RADOSE code and its backup manual system have the capability to back-calculate from offsite monitoring team readings to verify or update estimated source release terms.

This iterative process.is continued in order to determine the actual source release terms as accurately as possible.

If the instrumentation used for radiological assessment is off-scale or inoperative, the Radiation Support Manager must utilize contingency dose calculation procedures.

These conservative calculational methods utilize dose release factors which are based upon the expected plant source release terms for several accident classi-fications.

The Radiation Support Manager must first select the accident class which most closely fits the current plant conditions He must then input these expected

plant source release terms into the RADOSE or manual dose projection systems to project: whole body or thyroid doses.

Concurrently, radiation monitoring teams are sent to those locations of interest to take actual field measurements in order to refine the projections and to correlate projected versus actual results.

These detailed calculational techniques are included in an Emergency Plan Implementing Procedure.