ML19331D400

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Procedure to Determine Extent of Core Damage (for 0% to 100% Core Meltdown)
ML19331D400
Person / Time
Site: Big Rock Point File:Consumers Energy icon.png
Issue date: 06/10/1980
From:
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML19331D399 List:
References
5D, NUDOCS 8009020343
Download: ML19331D400 (6)
v • d • e


Text

.

ENCLOSURE 2 VOLUME 9A IMPLEMENTING PROCEDURES-5D m

BIG ROCK PGINT NUCLEAR PLAST

(,)

SITE EMERGENCY PLAN i

PROCEDURE TO DETERMINE ENTENT OF CORE DAMAGE (FOR O*. TC 130". CORE MELTD0'n'N)

Procedure 3D 1.0 PURPOSE J

1.1 To provide a method for estimating the degree of core damage during accident conditions.

If radiation levels are low enough, sampling of core spray heat exchanger water may be performed (per EPIP SE) for determining up to 10?. core meltdown.

2.0 METFOD 2.1 The degree of core dsmage will be estimated using the ionization chamber readout (in the air compressor room) and the attached graphs (Attachments 1 and 2) of dose rate versus time.

3.0 TECHNICAL SPECIFICATIONS AND CTHER REQUIREMENTS 3.1 Letter from D P Hoffman to D K Eiemann, dated December 27, 1979; Big Rock Point Plant - Recuirements Resulting from Review of Three Mile Island 2 Accident. Actions taken in response to Sec-s tion 2.1.8.a, Page 21.

3.2 The containment monitor sh:11 be calibrated at least quarterly.

4.0 SPECIAL EQUIPMENT 4.1 A high range ionizat' ion chamber (located in the cable penetration room, approximately fo r feet off the floor and six feet from the containment).

4.2 A local readout with range switch (located in the air compressor room).

June 10, 1980 3D-1 Rev 0 pr048G-0053d-97 8009020%

---,n-VOLUME 9A IMPLE'!ESTING PROCEDURES-5D BIG ROCK POINT NUCLEAR PLANT SITE EMERCENCY PLAN 4.3 Graphs of ionization chamber readout for 100% fuel failure in R/h versus ti=e (Attachments 1 and 2).

'I 5.0 PRECAUTIONS AND LIMITATIONS 5.1 Radiological surveys shall be conducted as necessary to ensure the radiatien limits of 10 CFR 20 are not exceeded during the performance of this procedure.

6.0 PROCIDURE 6.1 In the air ccepressor room, record the following ionization chamber infor=ation on the Extent of Core Damage Data Sheet (Attachment 3):

6.1.1.

Date (Location 1).

6.1.2.

Time (Location 2).

c.1.3.

Initials of person obtaining information (Location 3).

6.1.4 Reading of ionization chamber (Location 4).

NOTE: This instrument reads in KR/h. Multiply KK/h by 1,000 to obtain R/h.

l 6.1.5.

Time elapsed from t=0 (time elapsed since reactor trip)

(Locatien 5).

6.2 Using the appropriate graph of R/h with 100% fuel failure versus time - post accident (Attachment 1 or 2), record on Attachment 3 (Location 6) the R/h value at the time elapsed since reactor trip (t=0 at reactor trip).

6.3 Divide Step 6.1.4 by Step 6.2 and multiply by 100 te determine the percent of core damage. Record this on Attachment 3 (Location 7).

June 10, 1980 SD-2 Rev 0 pr0480-0053d-97 h

VOLCME 9A IMPLEMT. STING PRCOEDURES-5D BIG ROOK POINT NUCLEAR PL.BT SITE EMER3 NCY PLAN I

6.4 Exa=ple:

An acciden: has occurred tha: requires an estimation of the percentage of core da= age.

a.

The ioni=atica cha=ber reados: is 1 x 10' Rd 'a cne hour after J

=0 (Step 6.14).

The attach,ed graphs give a value of 1.7 x 10' R/h at one hour b.

from :=0 (S:ep 6.2).

c.

1.0 x 104 Rih = 0.59 1.7 x 10- R/h (0.59)(100) = 59*. (Step 6.3)

The extent of core da= age is 59*..

June 10, 1980 TD-3 Rev 0 p:0430-0053d-97

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