ML19332D121

LER 89-009-00:on 891025,determined That Containment Purge in Operation W/O Operable Radiation Monitor Capable of Isolating Purge on High Radiation Signal.Caused by Personnel Error.Valve Opened,Restoring Sample flow.W/891122 Ltr

ML19332D121
Person / Time
Site:	Millstone
Issue date:	11/22/1989
From:	Deslandes K, Scace S NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-89-009-01, LER-89-9-1, MP-13772, NUDOCS 8911300039
Download: ML19332D121 (4)

Text

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g General Offices'$elden Street. Berhn Connecticut wYs ela's*.Iede'ttIYieWenS*n"y" P.O. Box 270 #

• $'.s7EtNECO*Mny No HARTFORD. CoNNECTiovT 06414-0270 No'tneast Nac6 eat Enrgy Comnemy (20$)$$$.6Q00 November 22, 1989 MP-13772 Re: 10CFR50.73(a)(2)(i)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555

Reference:

Facility Operating License No. DPR-65

, Docket No. 50-336 Licensee Event Report 89-009-00

, Gentlemen:

This letter forwards Licensee Event Report 89-009-00 required to be submitted within thirty (30) days pursuant to paragraph 50.73(a)(2)(i).

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY e

4A py Stephe E. cace Station Superintendent Millstone Nuclear Power Station SES/KDD:mo

Attachment:

LER 89-009-00 >

l- cc: W. T. Russell, Recion 1 Administrator W. J. Ravmond, S'enior Resident inspector, Millstone Unit Nos.1, 2 and 3 G. S. Vissing, NRC Project Manager, Millstone Unit No. 2 I

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Radiation Monitor RM 6262 Inlet Yahe f 2-AC-b2) Found Closed EVENT DATE @ t i n NUMPF A f f i PEDOAT D ATE m OTHF A F ACtfiW S INVOL vFD f t1 MONT> DAY YEAR YEAR MDNTH DAY YEAR F AOILIT V fvAME6 0]6l010l0] l l

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1 0 2l5 6 0 6 l9 0l0l9 0l 0 3l1 2l 2 8l9 0l 5l 010101 l l oPERAtsNa TH15 AEPORT IS BENa SUBM'TTED PUASUANT TO THE REQU14EMENTE or to cFR g genees one p. mor, et the tonowmout o 20 402(b) 20 402tel 60 73iaH2Hid 73. 71(b) ao aosianuto 60.3cic u n so 73 auln o 73 ruci AOq'm ~ ~ - ,

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ABSTRACT (Limit to 1600 spaces. i.e., apprommateiy fifteen singie-space typewritten imes) 06)

On October 25,1989 at 1649 hours0.0191 days <br />0.458 hours <br />0.00273 weeks <br />6.274445e-4 months <br /> uith the plant m cold shutdown Mode 5, Octpower, it was determined that Containment Purge was m operation without an operable radiation momtor capable of isolating the purge on a high radiation signal. The sample mlet isolation vah'e (2-AC-62) for the Facility 2 radiation monitor RM6262 was found closed.

At the time of occurrence the Facility I emergency power source (d esel generator) was taken out of service on October 23,1969 at 1426 hours0.0165 days <br />0.396 hours <br />0.00236 weeks <br />5.42593e-4 months <br /> rendenng the Facihty I radiation monitor RM6123 inoperable, howeser RM6123 remained in service without an emergency power source for its roots blower whenever Containment Purge was in service. Radiauon momtor RM6123 was taken out of service October 24, 1969 at 1310 hours0.0152 days <br />0.364 hours <br />0.00217 weeks <br />4.98455e-4 months <br /> for Instrument and Control calibration SP2404AL and returned to service October 25,19F9 at 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br />.

Subsequent review showed radiation monitor RM6262 was taken out of service on October 21,1969 for Instrument and Control calibrauon SP2404AL. Restoration from the procedure failed to open sample inlet isolation valve 2-AC-62.

l Therefore no operable Containment Atmosphere - Particle / Gaseous radiation monitor was available for 19 hours2.199074e-4 days <br />0.00528 hours <br />3.141534e-5 weeks <br />7.2295e-6 months <br />. Technical Specification Limitmg Condition for Operation 3.3.3.1 titled "Radiaticn Monitonng" was not entered which requires a grab sample at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or the use of a constant air monitor.

It should be noted that Health Physics conducted rouune outage grab samples of Containment atmosphere i with no unusual results dunng the tirae the sample inlet isolauon valve 2-AC-62 was closed. Also an area radiation monitor is located in Containment on the refuel bridge which conunuously monitors the containment area.

The sample inlet isolation valve 2-AC-F2 was opened and radiation monitor RM6262 was declared operable.

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1. Determnon of Es ent On October 25,1989 at 1649 hours0.0191 days <br />0.458 hours <br />0.00273 weeks <br />6.274445e-4 months <br /> with the plant in cold shutdown Niode 5. 0"t power, it was determined that Contamment Purge was in operation without an operable radiation morator capable of isolati .y the purge on a high radiation signal. The sample mlet isolation vahe (2-AC-82) for the Facihty 2 radiation monitor RN18262 was found closed.

At the time of occurrence the Facihty 1 emergency power source (diesel generator) was taken out of semce on October 23,1989 at 1428 hours0.0165 days <br />0.397 hours <br />0.00236 weeks <br />5.43354e-4 months <br /> renderms the Facihty 1 radiation monitor RN16123 inoperabic, however RN18123 remamed m service without an emergency power source for its roots blower whenever Containment Purge was m service. Radiation monitor RN18123 was taken out of service October 24,1989 at 1310 hours0.0152 days <br />0.364 hours <br />0.00217 weeks <br />4.98455e-4 months <br /> for Instrument and Control cahbration SP2404AL and returned to semce October 25,1989 at 1800 hours0.0208 days <br />0.5 hours <br />0.00298 weeks <br />6.849e-4 months <br />.

Subsequent review showed radiation monitor RN16262 was taken out of service on October 21, 1989 for Instrumentation and Control calibration SP2J04AL. Restoration from the procedure failed to open sample inlet isolation valve 0-AC-82.

Therefore no operable Containment Atmosphere - Particle / Gaseous radiation monitor was available for 19 hours2.199074e-4 days <br />0.00528 hours <br />3.141534e-5 weeks <br />7.2295e-6 months <br /> Technical Specification Limiting Condiuon for Operation 3.3.3.1 titled

• Radiation hionuoring" was not entered which requires a grab sample at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or the use of a constant air momtor.

it should be noted that Health Physics conducted routine outage grab samples of Containment atmosphere with no unusual results durms the time the sample intet isolation valve 2-AC-82 was closed. Also an area radiation monitor is located in Contamment on the refuel bndpe which contmuously monitors the Containment area.

The sample inlet isolation valve 2-AC-82 was opened and radiation monitor RN18262 was declared operable, ll. fame of Fvent During the performance of the calibration procedure SP24n4AL, valve 2-AC-62 was closed.

During the performance of the rest of the procedure, it was determineel by the person performing the calibration that a change to the way the radiation monitor was isolated was appropnate. The new isolation method provided in Change 1 to procedure SP2404AL called for the closure of the radiation monitor inlet valve. 2-AC-70, and radiation monitor outlet valve 2- AC-74, by Operations. This change moved the isolation boundary from the inside the recirculation line on the Skid to outside the recirculation line.

When the change was implemented anJ the isolation boundary moved, 2-AC-52 was not reopened.

The calibration activity was then completed by different personnel. They performed the procedure guidance provided by the change to have Operations re-open valve 2-AC-70 and 2-AC-74. This completed the activities required by the procedure but left the radiation momtor isolated by the closure of valve 2-AC-62.

The root' cause of this event is personnel error. Prior to makmp a procedure change, valve 2-AC-82 should have been opened, which would have restored the radiation monitor RN18262 vahe lineup to normal operation. Once restored and the procedure change approved, the surveillance could have been completed using thr new isolation boundary.

a NRC Form 366 A (6-89) '

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0l $l 0l 0l 0l3 l3 l6 bl9 0l0l9 0l0 0l 3 OF 0l3 Text vi mm. space is reauir o, use acomonai NRc Fem 366A o sin 111. Annheit of Event This event is bemp reported pursuant to the requirements of paragraph 50.72(a)(2)(i) which requires reporting of any operation prohibited by the plant's Technical Specifications. Dunnp the time radiation moniter RMS262 was isolated, radiation monitor RM8103 was in service without its ,

emergency power source and would have performed its safety function, which is to isolate Containment Purge on a high radiation signal.

Health Physics personnel conducted routine outore grab samples of Containment atmosphere during this period with no unusual results. Also, an area radiation monitor is located in Containment on the Refuel Bndre which continuously monitors the Containment area. ,

Therefore, there were no safety consequences as a result of this occurrence.

IV. Corrective Action immediate action taken was to open isolation valve 2-AC-F2, restoring sample flow, which restored radiation monitor RMS262 to operable' status. The error of making changes to procedures prior to i restoring the system to original conditions has been discussed with the personnel invohed, and as a [

topic for the entire Instrument and Control Department.

Also steps has been added to the restoration section of calibration procedure SP2404AL and r SP2404AM which will verify positive sample flow indication at the radiation monitor skid and verify no low flow or high flow alarms exist.

V. Additionn1 Inintrnntion No similar events.

Ells Codes ( )

IL - Radiation Monitoring System l

l NRO Form 366A (6-89)