ML20093K157
| ML20093K157 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 06/01/1984 |
| From: | PUBLIC SERVICE CO. OF COLORADO |
| To: | |
| Shared Package | |
| ML20093K156 | List: |
| References | |
| TASK-2.B.3, TASK-TM RERP-CORE, TAC-44443, NUDOCS 8407300467 | |
| Download: ML20093K157 (7) | |
Text
RERP-CORE g
PUBLIC SERVICE COMPANY OF COLORADO Issue 1 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 1 of 3 g
TITLE:
CORE DAMAGE EVALUATION ISSUANCE AUTHORIZED BY H '$/ @),A l k /- L M.em k.,,
/
8 EFFECTIVE R EVIEW PORc 5 71 MAY 301984 DATE b-I* b TABLE OF CONTENTS Section Description Page 1.0 Criteria for Implementation.............................
1 2.0 Procedure....................................
.......... 2 3.0 Responsibilities....................................... 3 1
4.0 References............................................. 3 Worksheet 1 Failed Fuel Evaluation...........................
1 Work /Datasheet/Checkli st Control Li st............................. 1 Forms Use Reporting Sheet *........................................ 2 ANYTIME A WORKSHEET, DATASHEET, OR CHECKLIST HAS BEEN WRITTEN ON, COMPLETE THE REPORTING SHEET ATTACHED IN THE TABBED WORKSHEET SECTION AND FORWARD IT TO THE NUCLEAR DOCUMENTS SPECIALIST, FORT ST. VRAIN. DO NOT WRITE ON ANY WORKSHEETS, DATASHEETS, CHECKLISTS, OR REPORTING SHEETS IN THE PROCEDURE ITSELF. ALL WORKSHEETS/DATASHEETS/ CHECKLISTS ARE TO BE TAKEN FROM THE TABBED SECTION FOLLOWING EACH PROCEDURE.
PDR ADOCK8407300467 840716 05000267 F
PDR FORM 372 22 3642
PUBLIC SERVICE COMPANY OF COLORADO ue FORT ST. VRAIN NUCLE AR GENERATING STATION Page 2 of 3 GENERAL This procedure provides guidance for estimating core damage (failed fuel fraction) following a LOFC accident. The procedure utilizes the tu!ts of a PCRV volume calculation and radiochemical analyses of primary coolant. The following assumptions are made:
1.) The PCRV is depressurized to 5 PSIG within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> after a LOFC event, and there is no failed fuel during this time period; 2.) Previous reactor power history is used to establish the quantities of radionuclides available for release from the fuel; 3.) The expected R/B values for noble gases in primary coolant are in the range of IE-6; therefore the initial PCRV inventory of noble gases during reactor depressurization is ignored; 4.) The purification system is not operating during the LOFC condition; and 5.) The release fraction of noble gases is directly proportional to the failed fuel fraction.
1.0 Criteria for Implementation This procedure is intended to be used following a LOFC accident; however the basic methodology may be applied in other cases where fuel failure is suspected.
Other cases of this sort will be handled on a case by case basis.
2.0 Procedure Worksheet 1 is utilized to calculate the failed fuel fraction.
The failed fuel fraction is simply the ratio of the observed (circulating) activity of 133Xe to the total (available for release from the fuel) activity of 133Xe.
core damage ' evaluation, primary 2.1 In nrder to perform a coolant analyses must be obtained in units of pCi/sec.
The PCRV volume must also be calculated. Using this information, the circulating activity of 133Xe is obtained.
2.2 The total quantity of 133Xe present in the fuel prior to shutdown, including the 133I precursor, is calculated.
2.3 Utilizing the results of steps 2.1 and 2.2, Worksheet 1 is completed.
FORM 372 22 3643
((, CORE PUBLIC SERVICE COMPANY OF COLORADO o
FORT ST. VR AIN NUCLEAR GENERATING STATION Page 3 of 3 4
3.0 Responsibilities 3.1 Health Physics Supervisor or Designee The Health Physics Supervisor or his designee is responsible for ensuring that primary coolant samples are collected as required for analysis.
3.2 Radiochemistry Supervisor or Designee The Radiochemistry Supervisor or his designee is responsible for ensuring that primary coolant samples are analyzed in accordance with procedures.
The Radiochemistry Supervisor or his designee is also responsible for calculating PCRV volume.
3.3 Radiological Assessment Cocrdinator The Radiological Assessment Coordinator is responsible for completing Worksheet I and reporting the results of the failed fuel evaluation to the Corporate Emergency Director and, as directed, to the TSC Director.
4.0 References 4.1 HPP-14, Analytical Instrumentation Room 4.2 RCP-22, Primary Coolant Radioactivity Surveillance for Technical Specification SR 5.2.11W 4.3 R.
D. Burnette, " Measurement of Fuel Failed in FSV During LOFC" 4.4
" VOLUME" Computer Program I
FORM 372 22. M43
RERP-CORE PUBLIC SERVICE COMPANY OF COLORADO i
Workshoeg 1 FORT ST. VRAIN NUCLEAR GENERATING STATION lssue 1 Page 1 of 1 WORKSHEET 1 FAILED FUEL EVALUATION 1.
Primary Coolant 133Xe inventory (curies)
(Xei) 2.
Reactor Power at shutdown, MW(th) 3.
Time since Reactor shutdown, hours 4.
Failed Fraction =
Xe 1, ( e -l t - e-1 t} 1 -X
+ Xe, e-X t A i i
2 2
where Xei = total curies of 133Xe in helium (PCRV) at sample isolation time (1 above) i I, = total curies of 133I at shutdown (fuel)
MW(th)
- FY
- 3.15E16 f/s/MW
- 1/3.7E10 dps/C1 133I 1 = decay constant for 133I, 3.41E-02 hr2 2
1 = decay constant for 133Xe, 5.46E-03 hr 2
t = time since reactor shutdown, hours (3 above)
Xe, = total curies of 133Xe at shutdown, (fuel)
MW(th)
- FY
- 3.15E16 f/s/MW
FY133I = 6.69E-02 FY133Xe = 6.69E-02 FAILED FRACTION =
F ORM 313
- 23
- 3643
RE E
PUBLIC SERVICE COMPANY OF COLORADO g,
y FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 Page 1 of 3 Work /Datasheet/ Checklist Control List NOTE:
Extra attachments as listed are found in the working copy of this procedure in the Forward Command Post and the Technical Support Center.
Worksheet No.
Title Number of Copies 1
Failed Fuel Evaluation 10 i
Datasheet No.
None N/A N/A Checklist No.
(
None N/A N/A i
i Attachment No.
None N/A N/A J
l 4
i i
~
f i
PORM 372 22 3643
- l..
R
-C0 E PUBLIC SERVICE COMPANY. OF COLORADO g,
,}
FORT ST. VRAIN NUCLEAR GENERATING ST ATION y$$ye 1 Page 2 of 3 s
FORMS 'JSE REPORTING SHEET Nuclear Documents Specialist:
This sheet is being transmitted to report use of forms from a controlled copy of the Radiological Emergency
Response
Plan Implementing Procedures, BOOK NO.
located at The following forms have been utilized from this copy:
Worksheet Numbers Copies Used Datasheet Numbers Copies Used Checklist Numbers Copies lised The procedure affected by this sheet is shown in the header to this page, unless otherwise noted below in the comments to this reporting form.
When this form is received, it will be necessary to replace the noted number of forms, as well as this " Forms Use Reporting Sheet" for the affected procedure in the affected book.
FORM 3F2 22 364
' f'
,~
R E
PUBLIC SERVICE " COMPANY' OF COLORADO 4
g, FORT ST. VRAIN NUCLEAR GENERATING STATIOM lssue 3 Page 3 of 3 t
,v FORMS USE REPORTING $HEET (Continued)
COMMENTS.:
\\
v ReportediByt.
Date:
\\'
Nuclear Documents Specialist Date Received Date Replaced i
(
I.
Nuclear Documents Specialist will transmit this form to the originating individual / department upon completion of this form to notify users that the procedure has been updated and that all worksheets, checklists, and datasheets are present in the required number of copies.
I l
i J
l s
]
l l
POHM 372 22 3643
-- ~
~
- ~ ~:
.