05000285/LER-1980-009-99, /99T-0:on 800522,during Maint on Stack Iodine Process Monitor,New Sensitivity Calibr Was Required.Caused by Use of Wrong Calibr Procedure.Training Will Be Conducted to Ensure Familiarity W/Procedures

/99T-0:on 800522,during Maint on Stack Iodine Process Monitor,New Sensitivity Calibr Was Required.Caused by Use of Wrong Calibr Procedure.Training Will Be Conducted to Ensure Familiarity W/Procedures

ML19310A290
Person / Time
Site:	Fort Calhoun
Issue date:	05/29/1980
From:	Franco F, Nicholas J OMAHA PUBLIC POWER DISTRICT
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML19310A287	List: 05000285/LER-1980-009, Forwards LER 80-009/99T-0 05000285/LER-1980-009-99, /99T-0:on 800522,during Maint on Stack Iodine Process Monitor,New Sensitivity Calibr Was Required.Caused by Use of Wrong Calibr Procedure.Training Will Be Conducted to Ensure Familiarity W/Procedures
References
LER-80-009-99T, LER-80-9-99T, NUDOCS 8006110030
Download: ML19310A290 (4)

LER-1980-009, /99T-0:on 800522,during Maint on Stack Iodine Process Monitor,New Sensitivity Calibr Was Required.Caused by Use of Wrong Calibr Procedure.Training Will Be Conducted to Ensure Familiarity W/Procedures

Event date:
Report date:
2851980009R99 - NRC Website

text

'

(7 77)

LICENSEE EVENT REPORT h

CONTROL BLCCX: l l

l l

l l]h (PLEASE PRINT OR TYPE ALL REQUIRED INFOT,MATIONI t

la t il I N I E I F l C l S l 1 l@l 0 l0 l0 l 010 !010 IO l0 l0 l0 l@l 4! 11 il ll ll@l l

l@

7 3 3 LICENSEE CoCE 14 15 LICENSE NUMSER 25 26 LICENSE TYPE 40 57 CAT 58 CcN T a% l t @l 015 l 0 l 010 l 2 i 8 I 5 GI O is I2 1218 10 @l0 15 12 19 l8 10 l@

IoIiI s

?

4 60 61 CoCKET NUM8ER 68 69 EVENT QATE 74 75 REPORT DATE 30 EVENT CESCRIPTION AND PAOBA8LE CONSEQUENCES h IoI2l l During maintenance on stack iodine crocess monitor, RMO-60, a new sensitivity cali-l Ioi3l l bration was required. Upon conducting the calibration procedure, SCP-RM-060, it was l 1o i4 l l determined the previous calibration was conducted using an out of date procedure.

I Fo i 5 ! l Thus various incorrect numbers were used for the previous calibration.

Since the l

lc is l I plant was shutdown for refueling repairs, iodine sa=cles from contain=ent were very I

[oI7I l low and the erroneous setpoints had no adverse consequences.

j l)63l }

$0 7

3 9 SYSTEM

CAUSE

CAUSE COMP.

vAty g COCE CCOE SU8C00E COMPONENT CODE SU8 CODE SUSCOCE laial I 31 a l@ ID l@ lZ l@ l Xl Xl Xl Xl Xl Xl@ lZ l@ lZ l@

5 3

to 11 12 13 is 19 20 SEcVENTIAL OCCU R R ENCE REPORT

• EVISioN gga oc SVENTVEAR RE'CRT No.

C00E "vPE No.

@ aE= oar I sl 0l l_l l 0l 0l 9l lA l9l9l lT l l_l l0l 21 22 23 24 26 27 29 29 30 31 32

? KEN AC C C P NT ME woVRS S8 i SoR 8.

SUP8Li MANUFAC RER IZ l@l al@

l Z l@

l Zl@

l 0l0l 0l 0l l Yl@

lNj@

lZl@

lZj9l9l9l@

30 34 05 06 37 40 41 42 43 44 47 CAuSE cESCRIPTION AND CORRECTIVE ACTICNS h Ii io l l The wrong procedure was used by a health physics technician for this calibration.

Thd it ii I l old crocedure had been revised and the new values were not aoolied to the calibration J The setpoints for alert and alarm were set high due to the wrong values being used in j

ii,21 I the calibration procedure (see attached).

All process radiation monitor calibration l J

procedures will be reviewed for unifor=1ty and accuracy.

Training will be conducted

)

{it3l l for calibration technicians to ensure familiarity with procedures and their accomo-l i

tieA i i lishments to alleviate any further oroblems.

l so 7

s a SA

% POWER oTHER STATUS 01 RY DISCOVERY OESCRIPTloN NA l

lC l@l Recalibration Following Maintenance l,

lt 15 l W@ l0 l0 l0 l@l AC IVITY CO TENT RELEASED CFRELEASE AMOUNT oF ACTIVITY LOCATION oF RELEASE NA l

l NA l

l1 is l l Z l @ lZ l@l 7

3 3 10 tt 44 45 80 PERSCNNEL 1XPoSURES NLM8ER TYPE

DESCRIPTION

l i l 7 l [ 0 ] O l 0 l@l Z l@l NA l

PtRSoNNE k sNJURIES cESCRirTicN@

NUM8s.R li j a l l 0 l 0 l 0 l@l NA l

7 3 3 11 12 80 LOSS of CR oAMAGE To FACILITY Q TYPt C ESCRIPTf oN

%,,/

NA l

li t s ! I Z l@l 30 7

4 3 to CfQ 1 : i o l l N f@lo'ESRiPTroN @

NRC uss cNov 8006110 sSut

<As l

ll ll llIIIIIil{

NA F

4 3 to 1M 58 69 30 3 PHONE:

{

J.3. Nicholas /F. F. Franco 102 426-4011

.NAME OF PaEP ARER

LER 80-009 Omaha Public Power District Fort Calhoun Station Unit No. 1 Docket No. 05000285 Attachment No. 1 i

Safety Analysis

Fort Calhoun Station stack effluent monitor RM-060 contains set points which automatically terminate iodine release from the plant in order to maintain an iodine release rate within the quantities specified in Technical Specification 2.9(2)b. Technical Specification 2.9(2)e.(1);

Table 2-1, note (4) and Standing Orders T-3 and T-12 require that stack monitors be operable and capable of performing their design function prior to the initiation of either containment purge or waste gas batch discharge. During the period of May 12 through May 22, when 1980 the RM-060 set points were invalid, the stack particulate monitor (RM-061) and the stack gaseous monitor (RM-062) were in service and correctly performing their design functions.

In addition, no radioactive releases were performed by either contai= ment purge or waste gas discharge.

The official documentation for compliance to Technical Specif-ication 2.9(2)b that the iodine release rate is less than 9.4E-02 microcurie per second is derived by a weekly analysis of the charcoal filter cartridge. The analysis is performed in the radiochemistry laboratory using a Germanium-lithium detector for gamma isotopic identif-ication.

The isotopic concentrations of the charcoal filter cartridges from

^

the period in question, and the plant conditions during this period, confirm that release rates were not exceeded at any time.

Thus, no re-lease violation occurred while the invalid setpoints were in the monitor.

LER 80-009' Omaha Public Power District Fort Calhoun Station Unit No. 1 Docket No. 05000285 Attachment No. 2

Corrective Action

The alert and alarm set points based on the correct monitor sample flow rate and correct sensitivity factor were calculated and installed on May 22, 1980. These set points fully limit the release rate of iodine to 9.4E-02 microcuries per second. To prevent further occurrences of this type, all process radiation monitor calibration procedures are being reviewed for uniformity and accuracy of numerical parameters and calculational equations.

Current calibration procedures require a review and approval by the Plant Health Physicist, the Supervisor-Chemistry and Radiation Protection and a member of the Quality Control group prior to acceptance. A review by an NRC senior license PRC member is required prior to an actual change of the monitor set points.

t t

9 c7-

LER 80-009 Omaha Public Power District Fort Calhoun Station Unit No.1 Docket No. 05000285 Attachment No. 3 i

Failure Data This is the first procedural event at Fort Calhoun Station which has resulted in an invalid set point of a stack effluent :nonitor.

I 2

e i

I s

I e

5 ftr \\P J

4g.