05000316/LER-1981-001-04, No Apparent Flow Observed Through Radiation Monitor R-19 from Steam Generator 21. Caused by Bad Diaphragm in roto-meter Flow Regulator.Flow Meters to Radiation Monitor to Be Modified

No Apparent Flow Observed Through Radiation Monitor R-19 from Steam Generator 21. Caused by Bad Diaphragm in roto-meter Flow Regulator.Flow Meters to Radiation Monitor to Be Modified

ML17331A666
Person / Time
Site:	Cook
Issue date:	03/04/1981
From:	Rischling J INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML17331A667	List: 05000316/LER-1981-001-04, No Apparent Flow Observed Through Radiation Monitor R-19 from Steam Generator 21. Caused by Bad Diaphragm in roto-meter Flow Regulator.Flow Meters to Radiation Monitor to Be Modified
References
LER-81-001-04X, LER-81-1-4X, NUDOCS 8103100369
Download: ML17331A666 (9)

LER-1981-001, No Apparent Flow Observed Through Radiation Monitor R-19 from Steam Generator 21. Caused by Bad Diaphragm in roto-meter Flow Regulator.Flow Meters to Radiation Monitor to Be Modified

Event date:
Report date:
3161981001R04 - NRC Website

text

RESULATORN',NFORMATION DISTRIBUTION +TEN (RIDS)

~'0 419 ACCESSION NBR:8103100369 DOC ~ DATE: 81/03/M NOTARIZED:

NO DOCKETt ¹ FACIL:50 316 Donald C ~

Cook Nuclear Power PlantE Unit 2R Indiana 8

05000316'UTH BYNAME AUTHOR AFFILIATION RISCHLINGiR ~ L, Indiana 8 Michigan Electr ic Co ~

RECIP ~ NAME RECIPIENT AFFILIATION Region ?i Atlanta< Office of the Director SUBJECT'pdated LER 81 001/04X 1 $ on 810112) there was no appar ent flow through radiation monitor R

19 from -steam generator 21 ~

'aused by bad diaphragm in roto meter flow regulator

~ Flow meter s to r adiation moni'tor to be modified.

DISTRIBUTION CODE:

A002S COPIES RECEIVED:LTR ~ ENCL SIZE:

TITLE: Incident'eports NOTES:Send 3 copies of all material to I8E, 05000316'XTERNAL:

ACRS NSIC 46 05 RECIPIENT ID CODE/NAME ACT'ION!

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04 INTERNAL~

A/D COMPLSTRU06 A/D MATL 8 QU08 A/D PLANT SYS10, A/D SFTY ASSE12 AEOD AUX SYS BR 15 CONT SYS BR 17 DIR p ENGINEER I20 DIR,SYS INTEG22" EQUIP QUAL BR25.

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,t Iootr4o INDIANA& MICHIGANEIECTRIC COMPANIY DONALDC. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 (616) 465-5901 March 3, 1981 Mr. J.G. Keppler, Regional Director Office of Inspection and Enforcement United States Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137 woa 09 ~9Si 9

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Operating License DPR-74 Docket No. 50-316

Dear Mr. Keppler:

Pursuant to the requirements of the Appendix A Technical Specifications, the following report/s are submitted:

RO 81-001/04X-1.

Sincerely,

/or D.V. Shaller Plant Manager

/bab cc:

J.E.

Dolan R.S. Hunter R.W. Jurgensen R.F. Kroeger R.W. Kilburn E.

Swanson/N.

DuBry RO:III R.C. Callen MPSC G. Charnoff, Esq.

J.M. Hennigan W. Lavallee EPRI PNSRC J.F. Stietzel E.L. Townley Dir., IE (20 copies)

Dir., MIPC (2 copies)

Directorate of Licensing o>

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ATTACHMENT TO LER II81-001/04X-1 SUPPLEMENTAL TO CAUSE DESCRIPTION This incident was reported to Mr. E.

Swanson of the NRC on January 22, 1981.

On January 22, 1981, it was determined that on January 12, at approximately

2200, there was no apparent flow through radiation monitor R-19 from number 21 steam generator.

During normal operation, the blowdown effluent would also pass through the steam generator blowdown treatment demineralizers where radiation monitor R-24 is located between the second and thiid demineralizers.

However, while investiga-ting the flow meter problem, the steam generator startup blowdown flash tank was in service, thus making R-19 the only radiation monitor,'hat was monitoring the blowdown effluent.

The startup blowdown flash tank was in service to reduce secondary system chemical contamination from condenser inleakage.

As Unit 2 has been experiencing a primary to secondary leak, routine daily samples are taken for leak rate determination and effluent release quanti-fication.

The activity of the blowdown from the steam generator number 21 was known prior to the incident and the activity levels were lower then had been determined the previous several months.

The startup blowdown flash tank was in service for 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> and 18 minutes, during which time the blow--

down from only number 21 steam generator was unmonitored prior to release to the environment.

Flow from the other three steam generators continued to be monitored during this time period.

Releases were calculated based on data taken on January 12,

1981, and the following results obtained:

Parameter Gross beta gamma

~Activit (u Ci/cc)

- 5 1.94 x 10 Release Total Release (m Ci)

Concentration (u Ci/cc)

- 9 2.04 x 10 1.75 Tritium Iodine-131

- 6 5.62 x 10

- 7 4.82 x 10

- 10 6.07 x 10-ll 5.20 x 10 0.506 0.043

These results are considered conservative as the use of the startup blowdown flash tank has a dilution effect on all parameters by discharging larger blow-down volumes and replacing it via a high makeup flow.

This is evident by data taken at 0115 hours0.00133 days <br />0.0319 hours <br />1.901455e-4 weeks <br />4.37575e-5 months <br /> on January 13, 1981, during the release, which shows all activities had decreased.

These samples were part of the plants routine daily analysis program.

The results are listed below:

Parameter Gross beta-gamma Tritium Iodine - 131

~Activit (u Ci/cc)

- 5 1.94 x 10

- 6 5.62 x 10

- 7 4.82 x 10 1-12-81

~Activit (u Ci/cc) 1/13/81

- 5 1.33 x 10

- 6 5.37 x 10

- 7 3.13 x 10 During the release, no other alarms or indications of increased primary to secondary leakage were noted.

Radiation monitors R-15, steam jet air ejector, and R-33 gland seal

exhaust, gave no indication of increased activity.

Estimates or releases were made assuming a constant 500 gallons per day primary to secondary leak rate with coincident lX failed fuel in the core and using the worst case meteorological data.

It was also assumed that.all activity remains in solution until reaching the startup blowdown flash tank.

Under these hypo-thetical worst case conditions, the following exposure rates would exist at the site boundary:

- 7 8.0 x 10 R/hr whole body from noble gases

- 7 3.0 x 10 R/hr from iodines with a thyroid dose rate

- 4 of 2.5 x 10 R/hr.

These estimates would yeild an integrated whole body dose of 0.0047 mR and an integrated thyroid dose of 1 mR.

The estimated release under these hypothetical conditions would be 0.023K of technical specifications or noble gases and 135 of technical specifications for radioiodines.

The summation of all radioiodines in the liquid release would be 46.5X of technical specifications.

In an effort to prevent reoccurrence of this problem, a design change (RFC No.

12-1825) was initiated to modify the flow meters to the radiation monitor, R-19 to include a loss of flow alarm.

In addition, a departmental standing order, TS0-021, was written to provide accurate responses if the condition were to exist again prior to completion of the design change.

This information has been distributed to all plant departments.

Although the incident allowed unmonitored effluent to be released to the environment, sufficient data is available to indicate thatduring the release the levels of radioactivity were low enough not to pose a threat to the health of safety of the public.

The sole purpose in revising this LER is to correct a typographical error for the value stated as the whole body-dose rate -from iodines under hypothetical worst case conditions.

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