ML20195F622
| ML20195F622 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 11/10/1988 |
| From: | Callan L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Goldberg J HOUSTON LIGHTING & POWER CO. |
| Shared Package | |
| ML20195F624 | List: |
| References | |
| NUDOCS 8811220083 | |
| Download: ML20195F622 (3) | |
See also: IR 05000498/1988066
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D;tr:lt Edisan - Fermi 2
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,RERP Plan implementing Prscedure
R::visicn 3
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RAPID ESTIMATE OF CORE / FUEL DAMAGE BASED
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ON CONTAINMENT HIGH RANGE RADIATION MONITOR
Revision Summary
1) Human factors upgrade and reformat to conform with RAP-PR1-01.
2) Removed Figure 1.1 from Attachment 1 and made it Enclosure B.
3) Provided step-by-step procedure for completing Attachment 1.
4) Deleted normal Drywell Radiation levels from Enclosure A.
5) Deleted Enclosures 2 through 7
Implementation Plan
[X] Revision effective immediately - ongoing work impacted
[ ] Ongoing work may proceed using previous revision
Attachments
1
110488
Rapid Estimate of Core / Fuel Damage based on Actual or Estimated
CHRRf,1 Reading
Enclosures
A
110488
Calculated Core / Fuel Damage Based on CHRRM Reading, Rad /hr, Fermi 2
Specific Accident,10-minute Post Shutdown
B
110488
CHRRf.1 Reading Versus Time
CONTROLLEQ
ARMS - INFORMATION SERVIC
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Date approved: /f /[
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Release authorized by:-771- CdM
Change numbers incorporated
88-3212
NOV 2 9 W
DSN
E P-5d7
Rev
3
Date
TPEPT
Fife 170310
Recipient
8b
O'tS
8812070083 881129
ADOCK 05000341
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Revision 3
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1.0
PURPOSE
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To provide a rapid quantitative estimate of core / fuel damage based on the Containment High
Range Radiation Monitor (CHRRM) reading prior to the availability of the drywell air
Post-Accident Sampling System (PASS) sample analysis.
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2.0
USE REFEF.ENCES
2.1
EP-546, Calculation of F.stimated Containment High Range Radiation Monitor or SGTS/AXM
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Monitor Readings if Instruments are Inoperable or Offscale
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3.0
ENTRY CONDITIONS
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3.1
The RERP Plan and its implementing procedures have been activated, and
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Annuncletor 3D43, OlV I/ll CONTAINMENT AREA RADIATION MONI10R TROUBLE,is
3.2
received in the Control Room, and
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3.3
Drywell air PASS sample analysis is not yet available.
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4.0
GENERAL INFORMATION
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4.1
The responsibility for implementing this procedure is assl0ned to the Emergency
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Director / designee. The estimate of core / fuel damage is reported to the Emergency
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Director / designee for use at the discretion of the Emergency Director /designea.
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4.2
This procedure provides a rapid gross method of estimating core / fuel damage based on
the CHRRf,1 reading and the quantity of radioactivity released to the containment that will
become airborne during a loss-of-Coolant Accident (LOCA).
4.3
Core / fuel damage estimates are based on calculations for three Fermi 2 specific
accidents. Calculation results are shown on Enclosures A and B. The three specific
accidents are:
4.3.1
100% fuel cladding gap release (10% of available noble gas,10% of available
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lodine 'eleased to the containment)
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4.3.2
Fermi 2 upper bound LOCA (100% noble gas. 2% lodine)
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4.3.3
Regulatory Guide 1.3 LOCA (100% noble gas,25% lodine)
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Revision 3
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5.0
IMMEDIATE ACTIONS
5.1
Obtain CHRRM readings from H11-P812 (H11-P602 back panet) or relay room pg.1els
H21-P914 (OlV I) and H21-P915 (DIV ll).
5.2
If DIV l and DIV 11 CHRRM are inoperable or offscale, estimate containment radiation using
6.0
PRGCEDURE
6.1
Perfctm the following steps using Rapid Estimate of Core / Fuel Damage based on Actual
or Estimated CHRRM Reading (Attachment 1)
6.1.1
Enter the date and time of reactor shutdown on Line A.
6.1.2
Enter the date and time of CHRRM Read;ng on Line B..
6.1.3
Calculate the number of hours after shutdown the monitor was read, and enter
on Line C.
6.1.4
Enter the CHRRM Reading on Line D.
1.
Select the highest actual reading from DIV I and OlV ll monitors.
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2.
If OlV I and OlV ll CHRRM are inoperable or offscale, use the estimated
value from EP-546.
6.1.5
Using the time atter shutdown entered on Line C and Enclosure B. enter the
anticipated CHRRM Reading for the three separate analyzed accidents on Lines
E.F.and G
6.1.6
Calculate the percentage of core / fuel damage by dividing the actual (or
estimated) CHRRM Reading from Line D, by the anticipated values (Lines E, F.
and G) for the three analyzed accidents.
1.
Enter the values on lines H. J. and K.
6,2
Report the results to the Emerge icy Director.
6.2.1
Report to the % Gap Release (H), unless H > 100%
6.2.2
If H > 100%, report % of Fermi 2 Upper Bound LOCA (J), unless J > 100%.
6.2.3
If J > 100% report % of Regulatory Guide 1.3 LOCA (K).
6.2.4
If K is greater than 100% the results should be reported as having exceeded the
Regulatory Guide 1.3 design basis for Fermi 2 by
% (K-100). The additional
activity is associated with release of iodines and other fission products to
containment.
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Revision 3
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7.0
FOLLOW-UP ACTIONS
7.1
Forward completed Rapid Estimate of Core / Fuel Damage based on actual or estimated
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CHRRM Reading (Attachment 1) to the Supervisor, RERP,164 NOC.
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8.0
RECORDS
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8.1
The following are required records and shall be retained or dispositioned in accordance
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with established procedures:
1
8.1.1
Rapid estimate of Core / Fuel Damage based on actual or estimated CHRRM
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Reading (Attachment 1).
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END OF TEXT
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RAPID ESTIMATE OF CORE / FUEL DAMAGE
BASED ON ACTUAL OR ESTIMATED CHRRM READING
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1.
Reactor Shutdown Date and Time
(A)
2.
Monitor Reading Date and Time
(B)
3.
Time After Shutdown [(B)-(A))
Hours (C)
4.
CHRRM Reading
Rad /hr (D)
DIV I
. DIV 11
. (Select Highest)
Estimated
(From EP 546)
5.
Using (C) and the CHRRM Reading Versus Time (Enclosure B)
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Curve 1 (100% Gap Release)
Rad /hr (E)
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Curve 2 (Fermi 2 Upper Bound LOCA)
Raa/hr (F)
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Curve 3 (Reg Guide 1.3 LOCA)
Rad /hr (G)
6.
(D)
Divided By (E)
x 100 =
(H)
% Gap Release
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(D)
Divided By (F)
x 100 =
(J)
% of Fermi 2
Upper Bound LOCA
(D)
Divided by (F)
x 100 =
(K)
% of Regulatory
Guide 1.3 LOCA
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l Forward original to Supervisor. RERP.164 NOC
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Form EP-547 Atti P1/1 1104S8
DTC: TPEMER File:
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Enclosure A, Page 1 of 1
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110488
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CALCULATED CORE / FUEL DAMAGE BASED ON CHRRM READING, RAD /HR
FERMI 2 SPECIFIC ACCIDENT,10-MINUTE POST SHUTDOWN
Airborne Release,
10-min Post LOCA
Percentage of
CHRRM Reading
inventory
R/hr
Accident Description
Nobles
lodines
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1.
Gap release,100%* (Curve 1,
10
10
3.6 x 10
Enclosure B)
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2.
Fermi 2 upper bound LOCA
l 100
2
1.02 x 10
(Curve 2. Enclosure B)
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3.
l 100
25
1.6 x 10
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sufficient core temperature
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to dnve out all noble
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gases from fuel pellets
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(Curve 3, Enclosure B)
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Release of all reactor
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coolant-no core damage
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0.01
- Since the curve ij linear any percentage less than 100% would be a direct multiplier; e g.,20% gap
release = 7.2 x 10
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Enclosure B, Page 1 of 1
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CHRRM READING VERSUS TIME
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TIME AFTER SHUTDOWN (HOURS)
Curve 1: 100% Gap Release (10% Noble Gas /10% fodine)
Curve 2: Fermi 2 Upper Bound LOCA (100% Noble Gas /2% todine)
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Curve 3: Reg. Guide 1-3 LOCA (100% Noble Gas /25% lodine)
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END
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D[taJII EDISON-f[RMI 2
Aul0nAIED AfCORD MANAG[MENI
DISIRI6u!!04 C04 TROL LISI
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11/90/88
fo: 00935
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00Cuntet CNIRL Otsa
ma5MIkGION, DC 20555
neJ1e; 17522/19424 wH1tf LIh[
Number Cnt
Issue
Doc. Serial Number
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Rev C9ples Lv1 Date
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[P-547
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11/29/US
AFC
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I certify that all revised, supersedeJ. or concelled documents have been
returneJ to information Services for dispostiton have Deen destroyed, or have
had their 004340tLED stamp vulded by lining through and initiating the stamp.
acceipt must De ackno.nedged through Aans or for off-site recipients by
retura to Information services. 140 [f2 NOC Dy 12/15/US
Received By
Date
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Ref: Pf.h!S$lG
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