ML17262A747

LER 92-001-01:on 920105,containment Ventilation Isolation Occurred Due to Actuation Signal from Containment Particulate Radiation Monitor R-11.Root Cause Undetermined. Sys Returned to Preevent status.W/920214 Ltr

ML17262A747
Person / Time
Site:	Ginna
Issue date:	02/14/1992
From:	Backus W, Mecredy R ROCHESTER GAS & ELECTRIC CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-92-001, LER-92-1, NUDOCS 9202190337
Download: ML17262A747 (18)

Text

ACCELERATED DRIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9202190337 DOC.DATE: 92/02/14 NOTARIZED: NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION BACKUS,W.H. Rochester Gas & Electric Corp.

MECREDY,R.C. Rochester Gas & Electric Corp.

RECIP.NAME RECIPIENT AFFILIATION R

SUBJECT:

LER 92-001-01:on 920105,failure of containment radiation monitor. Cause unknown. Return containment ventilation isolation sys to pre-event normal status.W/920214 ltr.

D DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR ENCL SIZE: .s TITLE: 50.73/50.9 Licensee Event Report (LER), ncident Rpt, etc.

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NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 A

RECIPIENT COPIES RECIPIENT COPIES D ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-3 LA 1 1 PD1-3 PD 1 1 D JOHNSON,A 1 1 INTERNAL: ACNW 2 2 AEOD/DOA 1 1 AEOD/DS P/TPAB 1 1 AEOD/ROAB/DS P 2 2 NRR/DET/ECMB 9H 1 1 NRR/DET/EMEB 7E 1 1 NRR/DLPQ/LHFB10 1 1 NRR/DLPQ/LPEB10 1 '1 NRR/DOEA/OEAB 1 1 NRR/DREP/PRPB11 2 2 NRR/DST/SELB SD 1 1 NRR/DST/SICBSH3 1 1 N ~~SPLBSD1 ~

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D NOTE TO ALL "RIDS" RECIPIENTS'LEASE S

HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 31 ENCL 31

J>> r' 10>>K ss>>rr ROCHESTER GAS AND ELECTRIC CORPORATION ~ 89 EAST AVENUE, ROCHESTER N.Y. 14649-0001 ROBERT C MECREOY TELEPHONE Vice President AREA CODE 716 546 2700 Clnna Nuclear Prssducrinn February 14, 1992 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Subject:

LER 92-001, (Revision 1) Failure of Containment Radiation . Monitor Due To Unknown Cause, Causes Containment Ventilation Isolation (i.e. ESF Actuation)

R.E. Ginna Nuclear Power Plant Docket No. 50-244 In accordance with 10CFR50.73, Licensee Event Report System, item (a)(2)(iv), which requires a report of, "any event or condition that resulted in manual or automatic actuation of any Engineered Safety Feature (ESF), including the Reactor Protection System (RPS)", the attached event report LER 92-001 (Revision 1) is hereby submitted. This revision is necessary to add an expected submission date of a supplemental report.

This event has in no way affected the public's health and safety.

Very truly yours, Robert C. Mecredy XC>> U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna USNRC Senior Resident Inspector

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SVFFLCNCNTAL 1CFO1f CXSCCTCO CSSCCTCO WCNISCION Tt c hs ttt. txstcrto tvtNitstow CArll 08 0492 AACTAACT ILAIVIN I SOS Wee, I ~ ., SSSrlsNNNtt ATNsA ISVN~S ttSSvNINA Noel IISI On January 5, 1992 at approximately 0240 EST, with the reactor at approximately 98% full power, a containment ventilation isolation occurred due to an actuation signal from the containment particu-late radiation monitor (R-ll).

All containment isolation valves that were open, closed as designed.

Immediate operator action was to perform the applicable alarm response procedures actions. This included verifying automatic actions, determining the cause of the containment ventilation isolation, and making appropriate notifications.

The immediate cause of the event. was determined to be the failure of R-ll.

Corrective action taken was to return the containment ventilation isolation system to pre-event normal status, sequentially followed by a troubleshooting effort by the Instrument and Control Depart-ment, and then changeout of the R-11 drawer with a qualified spare. Further investigation to determine the root cause is continuing.

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R.E. Ginna Nuclear Power Plant: o o 244 92 001 01 0205:0 TKXT '<<<<<<T$ WA$ << ~. <<V VWV<<V<<ACA<<V ~$ 1 IIW o s o PRE-EVENT PLANT CONDITIONS The plant was at approximately 984 steady state reactor power with no major activities in progress.

DESCRIPTION OP A. DATES AND APPROXIMATE TIMES OP MAJOR OCCURRENCES:

0 January 5, 1992, 0240 EST: Event date and time.

I 0 January 5, 1992, 0240 EST: Discovery date and time.

o January 5, 1992, 0252 EST: Control Room operators restore R-11 (Containment Particulate Radiation Monitor and reset containment ventilation isolation).

B EVENT On January 5, 1992 at approximately 0240 EST, with the reactor at approximately 984 full power, the following control board alarms were received, E-16 (RMS Process Monitor High Activity) and A-25 (Contain-ment Ventilation Isolation). The Control Room operators, responding to the above alarms, observed that R-11 (Containment Particulate Radiation Monitor) had the light indicating failure illuminated. The Control Room operators immediately referred to alarm response procedures AR-A-25 and AR-RMS, and verified that all containment ventilation isolation valves that were open, closed as designed and performed the applicable actions of the alarm response procedures.

Subsecpxently, at approximately 0242 EST, Control Board alarm E-20 (CNMT Or Plant Vent Rad Mon Pump Trip) was received. This alarm was due to isolation the trip of the containment radiation monitor pump and of the containment valves to and from the pump. other The Control Room operators also verified that the containment process radiation monitors were reading normal prior to the radiation monitor pump trip.

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0 5 0 0 0 2 4 4 9 2 P 0 ] p 0 30'. 0 7 After the above immediate actions were completed, the Control Room operators addressed plant Technical Specifications and declared R-11 inoperable.

At approximately 0252 EST, January 5, 1992, the Control Room operators reset R-11 by cycling its AC power supply off and on, reset the containment ventilation isolation signal; and restarted the containment radiation monitor pump. All containment process radiation monitor readings returned to approximately pre-event values, indicating that R-11 was now operating properly. Subsequently, at 0324 EST, the Control Room operators performed periodic testprocedure PT-17.2 (Process Radiation Monitors R-11 R-22 Iodine Monitors R-10A and R-10B) on R-11 only and'emonstrated that R-11 was operating as required.

C INOPERABLZ STRUCTURES~ COMPONENTST OR SYSTEMS THAT CONTRIBUTED TO THE EVENT.

None.

D OKH94 SYSTEMS OR SECONDARY FUNCTIONS AFFECTED:

With the containment ventilation isolation, the following major components were isolated:

o R-10A, Containment Iodine RMS Monitor o R-11, Containment Particulate RMS Monitor o R-12, Containment Gas RMS Monitor METHOD OF DISCOVERY The event was immediately apparent due to Control Board annunciator alarms and containment ventilation isolation valve position indication on the Control Board. Also, Radiation Monitor R-11 digital readout indicated an invalid error code.

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Control Room operators responded to .the event by performing the applicable actions of alarm response procedures E-16, A-25, RMS, and E-20 and other actions as they deemed necessary. This included the following: ~

0 Verifying that all containment ventilation isolation valves that were open, closed as designed.

0 Addressing the plant Technical Specifications to ensure the plant was operating within these specifications.

0 Declaring R-11 inoperable per administrative procedure A-52.4 (Control of Limiting Conditions for Operating Equipment).

0 Resetting R-11, resetting the containment ventilation isolation signal and restarting R-10A, R-11, and R-12 sample pump and verifying sample flow was re-established.

0 Verifying that R-10A, R-11, R-12 RMS monitor readings returned to normal.

0 Notifying the NRC and higher supervision of the ESF actuation.

G SAFETY SYSTEM RESPONSES:

The containment ventilation isolation valves that were open, closed automatically from the containment ventilation isolation signal.

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The containment ventilation isolation was due to an R-11 failure.

B ROOT CAUSE:

After the following troubleshooting, the root cause still remains undetermined at this time:

o The Instrument and Control (I&C) Department calibrated the R-11 drawer with no adjustments required.

o Victoreen Inc., the manufacturer of the instrument was called. Victoreen Inc. concluded that, the probable cause was the micro-processor "locking-up" and its AC it was reset by the operators cycling power supply off and on. They suspect it

'ay be a "one time" event.

ALYSIS OF EV19FV This event is reportable in accordance with 10CFR50.73, Licensee Event Report system, item (a)(2)(iv), which requires reporting of, "any event or condition that resulted in manual or automatic actuation of any Engineered Safety Feature (ESF) including the Reactor Protection System (RPS)". The containment ventilation isolation due to the R-11 failure, was an automatic actuation of an ESF subsystem.

An assessment was performed considering both the safety consequences and implicati,ons of this event .with the following results and conclusions:

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U ~a 1 R.E. Ginna Nuclear Power Plant o2 44 92 001 01 060~0 TeTT lIs ~ we A ervea ~e oeeeew eAc seA w4'sI IITI o 5 o o 7 There were no operational or safety consequences or implications attributed to the containment. ventilation isolation because:

o The containment ventilation isolation system operated as designed.

o The components affected were capable of withstanding the isolation.

o The containment ventilation isolation was in the conservative direction.

Based on the above', it can be concluded that the public's health and safety was assured at all times.

CORRECTIVE ACTION A. ACTION TAKEN TO RETURN AFFECTED SYSTEMS TO PRE-EVENT NORMAL STATUS:

o The Control Room operators, after determining that the containment ventilation isolation was due to the R-11 failure, reset R-11, reset the containment ventilation isolation signal and restored the system to pre-event status.

B ACTION TAKEN OR PLANNED TO PREVENT RECURRENCE:

The following corrective action was taken:

0 The R-11 drawer was replaced with a qualified spare and the removed R-11 drawer will be sent to Victoreen, Inc., so that. they can attempt to duplicate the failure and determine the root cause.

o Engineering has been involved in assessing the situation and will provide guidance for any desirable follow-up actions.

No other corrective action is planned until a root cause determination is accomplished. After a root cause determination is completed, a supplemental report to this LER will be submitted. Expected submittal date is approximately August 4, 1992.

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R.E. Ginna Nuclear Power Plant: Q 70F TTXT w ~ ~ ~. << iv orooaev <<&'vv~'v <ill 0 5 0 0 0 2 4 4 9 2 Q ] Q ] Pi P 7 ADDITIONAL INPORMA ON A. FAILED COMPONENTS The R-11 drawer was a model g942A, manufactured by Victoreen, Inc.

B. PREVIOUS LERs ON SIMILAR EVENTS:

A similar LER event historical search was conducted with the following results: LERs87-005, 88-007,89-011, 89-013, and 89-014 were similar events with known causes that appear much different than this event.

No other documentation of similar events could be identified.

C SPECIAL COMKKTS:

None.

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