05000412/LER-1990-001, :on 900107,high Radiation Alarm Received on Steam Generator Blowdown (SGBD) Sample Radiation Monitor, Causing SGBD Sys Isolation.Caused by Crud Particles Swept Into Monitor.Monitor Purged & Returned to Svc

:on 900107,high Radiation Alarm Received on Steam Generator Blowdown (SGBD) Sample Radiation Monitor, Causing SGBD Sys Isolation.Caused by Crud Particles Swept Into Monitor.Monitor Purged & Returned to Svc

ML20011E250
Person / Time
Site:	Beaver Valley
Issue date:	02/06/1990
From:	Noonan T DUQUESNE LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-90-001, LER-90-1, ND3MNO:2020, NUDOCS 9002120340
Download: ML20011E250 (6)

LER-1990-001, on 900107,high Radiation Alarm Received on Steam Generator Blowdown (SGBD) Sample Radiation Monitor, Causing SGBD Sys Isolation.Caused by Crud Particles Swept Into Monitor.Monitor Purged & Returned to Svc

Event date:
Report date:
4121990001R00 - NRC Website

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"l$lf0C Telephone (412) 393-6000 Nuclear Group I

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February 6, 1990 ND3MNO:2020 l

- i Beaver Valley Power Station, Unit No. 2 Docket No. 50-412, License No. NPF-73 LER 90-001-00 J

i United States Nuclear Regulatory Commission Document Control Desk j

Washington, DC 20555 j

Gentlemen:

In-accordance

.with Appendix A,

Beaver Valle Technical Specifications,-the following Licensee Event Report-is ysubmitted:

LER 90-001-00, 10 CFR 50.73.a.2.iv, " Engineered Safet Features Actuation - Staam Generator-Blowdown Isolation".y

.j Very truly yours, W

T.

P. N onan General Manager l

Nuclear Operations j

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February 6, 1990 ND3MNO 2020 Page two

'cc: Mr. William.T. Russell Regional Administrator United States Nuclear Regulatory Commission Region 1 475 Allendale Road King of Prussia, PA 19406 C. A. Roteck, Ohio Edison Mr. Peter Tam, BVPS Licensing Project Manager United States Nuclear Regulatory Commission Washington, DC 20555 J.

Beall, Nuclear Regulatory Commission, BVPS Senior Resident Inspector Dave Amerine Centerior Energy 6200 Oak Tree Blvd.

Independence, Ohio 44101 INPO Records Center Suite 1500 1100 Circle 75 Parkway Atlanta, GA 30339 G.

E. Muckle, Factory Mutual Engineering, Pittsburgh Mr. J.

N. Steinmetz, Operating Plant Projects Manager Mid Atlantic Area Westinghouse Electric Corporation Energy Systems Service Division Box 355 Pittsburgh, PA 15230 American Nuclear Insurers c/o Dottie Sherman, ANI Library The Exchange Suite 245 270 Farmington Avenue Farmington, CT 06032 Mr. Richard Janati Department of Environmental Resources P. O.

Box 2063 16th Floor, Fulton Building Harrisburg, PA 17120 Director, Safety Evaluation & Control Virginia Electric & Power Co.

P.O.

Box 26666 One James River Plaza Richmond, VA 23261

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1. 2 was in steady-state Power Operation (Operatin/90, g-Mode

1) at 85% reactor power.

At 1639 hours0.019 days <br />0.455 hours <br />0.00271 weeks <br />6.236395e-4 months <br />, a high radiation alarm was received on the Steam Generator Blowdown (SGBD)

Sample Radiation

Monitor, 2SSR-RQIl00..

No equipment operation or activity was.in progress.

This.high alarm caused an isolation of the SGBD system.

This isolation is an Engineered Safety Features system actuation and reportable in accordance with 10CFR50.72 and 50.73.

- The

cause

for this actuation was due to residual contaminated (crud) particles, remaining from a

prior SG tube leak, being swept into the SGBD Sample Radiation Monitor.

The SGBD Sample Radiation Monitor was purged and returned to service and the SG blowdown system was restored to normal system arrangement.

An Engineering evaluation has been performed to raise the setpoint on 2SSR-RQIl00.

There were no safety implications as a result of this event.

The radiation monitor actuated as designed to isolate the blowdown system in the event of any steam generator tube leakage.

The low level activity was only a momentary excursion due the residual activity in the piping.

This was less than 1 percent of the allowed limit for power operation.

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DESCRIPTION

On 1/07/90, Unit

1. 2 was in steady-state Power Operation (Operating Mode

1) at 85% reactor power.

At 1639 hours0.019 days <br />0.455 hours <br />0.00271 weeks <br />6.236395e-4 months <br />, a high radiation alarm was-received on the Steam Generator Blowdown

=c (SGBD)

Sample Radiation

Monitor, 2SSR-RQIl00.

No abnormal

- equipment operation or activity was in progress.

This high.

alarm caused an isolation of the SGBD system.

The liquid in the SGBD-Sample Radiation Monitor which was isolated was analyzed.

The activity level of the liquid was found to be 4.99 E-7 microcuries per milliliter.

The high alarm setpoint is 1.53 E-5 microcuries per milliliter.

Operations personnel verified that the Condenser Air Ejector Radiation Monitor was indicating normal levels.

The SGBD Sample Radiation Monitor was purged and placed back in service.

The radiation monitor indications stabilized at pre-event values and the SGBD system was returned to service.

CAUSE OF THE EVENT

1 The

cause

for this event was residual contaminated (crud) particles, remaining from a prior SG tube leak, being swept into i

the SGBD Sample Radiation Monitor.

Total blowdown flow had been i

increased from its normal 220 gallons per minute to 280 gallons l

per minute for the previous three days to adjust Steam Generator Chemistry.

The increased flow was postulated to have caused i

some-residual crud particles to be released into the-system and to the-radiation monitor.

The residual activity deposited within the steam generator blowdown and blowdown sample system results in a relatively low level activity spike which is swept q

into the radiation moniter.

The design basis of the previous high alarm setpoint on the SGBD sample radiation monitor allows i

for the detection of primary-to-secondary leakage while limiting the secondary liquid concentration to less than 1.0E-5 j

microcuries per milliliter minimizing the buildup of steam generator blowdown demineralizer activity.

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CORRECTIVE ACTIONS

The following corrective actions have been taken as a result o this event:

1.

The SGBD Sample Radiation Monitor and the Auxiliary Steam Condensate effluent was directed to the Primary Auxiliary Building Sump until the analysis of the effluent was completed.

2.

The SGBD Sample Radiation Monitor was purged and returned to service.

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The SGBD system was restored to normal system arrangement.

4.

An Engineering evaluation -has been performed to increase the setpoint for the High and Alert alarm setpoints for the SGBD Sample Radiation Monitor.

The ne*'

setpoints are less than 15% of the allowed limits fe' normal -Power Operation.

The new-setpoint is higaer than any previous observed crud induced spikes on this monitor.

These setpoints were approved for use on 1/19/90.

The setpoints were increased as follows:

Previous value New Value Alert 1.24 E-5 1.42 E-5 High 1.43 E-5 7.33 E-3 Setpoint values are microcuries per milliliter.

These setpoints are administrative limits which serve to minimize secondary contamination.

The Steam Generator Blowdown System has been constantly flushed during operation with clean secondary water at the rate of 200 to 300 gallons per minute since the Steam Generator Tube Leak event on 6/21/89 (reference:

LER 89-021).

The Llowdown Monitoring System has been flushed and purged on several occasions since then, however, due

.to the residual crud deposits within the systems, these actions were unsuccessful in - preventing an additional occurrence.

- REPORTABILITY

- This event was repporrted.as an Engineered Safety Features (ESP)

System Actuation, in accordance with 10CFR50.72.b.2.ii, at 1835 hour0.0212 days <br />0.51 hours <br />0.00303 weeks <br />6.982175e-4 months <br />s-on 1/07/90.

This written report is being-submitted in accordance with the requirements of 10CFR50.73.a.2.iv.

SAFETY IMPLICATIONS There were no. safety implications to the public as a result of this event because the radiation monitor actuated as designed to c

- isolate.-the blowdown system in the-event of any steam generator tube leakage.

The low level activity was only a momentary excursion due to the residual activity in the piping.

The monitor's new alarm setpoint is less than 15% of the allowed limits for normal Power Operation (Reference: Beaver Valley Unit 2

UFSAR Table 15-0.8).

The previous alarm setpoint was less than 10% of the allowed limits for normal Power Operation.

This is an administrative limit chosen to control the contamination to the uncontrolled secondary plant systems in the event of a

'4 steam generator tube leak.

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PREVIOUS OCCURRENCES

There have been two previously reported events (Reference: LERs 89-024-00.and 89-026-00),

involving Engineered Safety Features (ESP)

Actuations resulting from steam generator blowdown system

~isolations, I

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