ML18044A961

Determination of Extent of Core Damage.

ML18044A961
Person / Time
Site:	Palisades
Issue date:	04/29/1980
From:	CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML18044A959	List: ML18044A958 ML18044A960 ML18044A961 ML18044A962 ML18044A963 ML18044A964 ML18044A965 ML18044A966 ML18044A967
References
EI8-3, NUDOCS 8006040315
Download: ML18044A961 (8)

Text

PALISADES NUCLEAR PLANT PROC HO EIB-3 EMERGENCY IMPLEMENTATION PROCEDURE PAGE 1 OF 8

• TITLE. DETERMINATION .OF EXTE~T OF CORE REVISION O

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

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 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.

5.0 PROCEDURE 5.1 Determining Damage From 0 to 24 Hours After:Accident 5.1.l 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).

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

s~1.3* Use~cunres in Figure 1 to determine percent failed fuel. I f the point determined is between two curves,, state results *as range between those*

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

~

5.1.4 Record results on data shee*t.

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. PALISADES NUCLEAR PLANT PROC tlO EI8-3 EMERGENCY IMPLEMENTATION PROCEDURE

. . . PAGE 2 OF 8 Tl TLE ..I DETERMINATION OF EXTENT OF CORE DAMAGE REVISION o consumers Power .

DATE 4/29/80 5.2 Determining Damage.for Greater*thari 24 Hours Determine dosa. rate from monitors RIA 1805, 1806, 1807 and 1808. These monitors appear as follows On strip chart recorder RR-3202:

RIA No. Recorder Point No

• 1805 19 1806 20

. 1807 21 1808 22 Absolute dose rate is found by subtracting normal background (see 5.1.2).

5.2.2 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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EI8-3 Rev. 0 Page 8 4/29/80 DATA. SHEET FOR DETERMINING EXTENT OF CORE DANAGE .

• Time (Post'-Accident) Noni tor Dose  % Failed Hours, Days Location* Rate Fuel Technician I

• ~****

Reviewed by Health. Physicist~~~~~~~-

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