ML18044A961

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Determination of Extent of Core Damage
ML18044A961
Person / Time
Site: Palisades Entergy icon.png
Issue date: 04/29/1980
From:
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML18044A959 List:
References
EI8-3, NUDOCS 8006040315
Download: ML18044A961 (8)


Text

PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTATION PROCEDURE PROC HO EIB-3 PAGE 1

OF 8 REVISION O

  • consumers Power
  • TITLE. DETERMINATION.OF EXTE~T OF CORE I DAMAGE DATE 4/29/80 REVIEWED BY PRC - DATE 4/28/80 QA-05 1.0 PURPOSE To provide a method of estimating the degree of core damage during accident conditions.

DATE

2. 0
REFERENCES 2.2 2.1 Palisades Nuclear Plant, FSAR Table 11-1.

3.0 P~EREQUISITES

    • N/A.
4. 0 PRECAUTIONS AND LIMITATIONS 5.0 5.1 5.1.l 5.1.2 s~1.3*

~

5.1.4 The.attached tables are based.on equilibrium core activities and Reg Guide

i. 4 (Reference 2 ~ 2) release rates.

Depending on core J.if e at time of accident these tables may.giv~ erroneous results.

PROCEDURE Determining Damage From 0 to 24 Hours After:Accident Determine tne dose rate from the Control Room entrance radiation mon:ttor.

This monitor appears as 1111 on the area radiation monitor strip chart recorder (RR".'"2302).

Absolute dose rate is obtained by subtracting normal.background (#11 reading before t=O) from the dose rate after accident occurs.

Use~cunres in Figure 1 to determine percent failed fuel. If the point determined is between two curves,, state results *as range between those*

curves. (ie, 10%-50%, etc.).

Record results on data shee*t.

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PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTATION PROCEDURE Tl T LE.. DETERMINATION OF EXTENT OF CORE DAMAGE PROC tlO EI8-3 PAGE 2

OF 8 REVISION o DATE 4/29/80 I

consumers Power 5.2 Determining Damage.for Greater*thari 24 Hours 5.2.2 Determine dosa. rate from monitors RIA 1805, 1806, 1807 and 1808.

These monitors appear as follows On strip chart recorder RR-3202:

RIA No.

1805 1806

. 1807 1808 Recorder Point No

  • 19 20 21 22 Absolute dose rate is found by subtracting normal background (see 5.1.2).

If four readings are 0btained> use appropriate curves in Figures 2-5 and find an average value.

Record __ r.esults on data sheet and submit for review by Health Physicist

.and Site Emergency Director.

6.0 ACCEPr:ANCE CRI~IA N/A.

7.0 ATTACHMENTS AND RECORDS 7.1 Figure 1 - Dose. Rc;i.te V?. Time for Control Rcom Entrance Monitor.

7.2

. l'igure.2 - Dos.e Rate vs. Time for Containment ~onitor /}1805 ~

7 *. 3 Figure 3 - Dose Rate vs. Ti~e for Containment Monitor #1806~

7.4 Figure 4 -:-.Dose Rate vs. Time for Containment Monitor #1807.

. 7.5 Figure 5 - Dose Rate vs. Time for Containment Monitor-ffl808

  • 7.6.

. Data sheet. for determining extent of core damage *..

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DATA. SHEET FOR DETERMINING EXTENT OF CORE DANAGE..

  • EI8-3 Rev. 0 Page 8 4/29/80 Time (Post'-Accident)

Hours, Days I

Noni tor Location*

  • ~****. - - -..

Dose Rate

% Failed Fuel Technician Reviewed by Health. Physicist~~~~~~~-

Reviewed by Site Ernerg. Director~~-.,;....~~-