ML18044A961
| ML18044A961 | |
| Person / Time | |
|---|---|
| Site: | Palisades |
| 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~~-.,;....~~-