ML18044A961: Difference between revisions
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curves. (ie, 10%-50%, etc.). * | 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 . | |||
. 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: | 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 * | RIA No. Recorder Point No | ||
* 1805 19 1806 20 | |||
1805 19 1806 20 | |||
. 1807 21 1808 22 Absolute dose rate is found by subtracting normal background (see 5.1.2). | . 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. | 5.2.2 If four readings are 0btained> use appropriate curves in Figures 2-5 and find an average value. | ||
| Line 68: | Line 57: | ||
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EI8-3 Rev. 0 Page 8 4/29/80 DATA. SHEET FOR DETERMINING EXTENT OF CORE DANAGE . | 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 | * Time (Post'-Accident) Noni tor Dose % Failed Hours, Days Location* Rate Fuel Technician I | ||
*~**** | *~**** | ||
Reviewed by Health. Physicist~~~~~~~- | Reviewed by Health. Physicist~~~~~~~- | ||
Reviewed by Site Ernerg. Director~~-.,;....~~-}} | Reviewed by Site Ernerg. Director~~-.,;....~~-}} | ||
Revision as of 14:31, 3 February 2020
| 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
{{#Wiki_filter: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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;;t,~t g
. 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~~-.,;....~~-}}