05000272/LER-1990-001, :on 900106,containment purge/pressure-vacuum Relief Sys Isolation Signal Actuated as Result of Channel Spike on Particulate Radiation Monitor 1R11A.Caused by Dirty Pc Cards.Cards Cleaned & Connectors Checked

:on 900106,containment purge/pressure-vacuum Relief Sys Isolation Signal Actuated as Result of Channel Spike on Particulate Radiation Monitor 1R11A.Caused by Dirty Pc Cards.Cards Cleaned & Connectors Checked

ML18094B283
Person / Time
Site:	Salem
Issue date:	01/31/1990
From:	Miller L, Pollack M Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-90-001, LER-90-1, NUDOCS 9002090313
Download: ML18094B283 (5)

LER-1990-001, on 900106,containment purge/pressure-vacuum Relief Sys Isolation Signal Actuated as Result of Channel Spike on Particulate Radiation Monitor 1R11A.Caused by Dirty Pc Cards.Cards Cleaned & Connectors Checked

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(iv), System Actuation
2721990001R00 - NRC Website

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PS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Dear Sir:

SALEM GENERATING STATION LICENSE NO. DPR-70 DOCKET NO. 50-272 UNIT NO. 1 LICENSEE EVENT REPORT 90-001-00 January 31, 1990 This Licensee Event Report is being submitted pursuant to the requirements of the Code of Federal Regulations 10CFR 50.73(a} (2) (iv).

This report is required within thirty (30) days of discovery.

MJP:pc Distribution Q00?090~1~ 900131

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PDC Sincerely yours, L. K. Miller General Manager -

Salem Operations 95-2189 (SM) 12-88

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On 1/6/90 at 0204 hours0.00236 days <br />0.0567 hours <br />3.373016e-4 weeks <br />7.7622e-5 months <br />, a Containment Purge/Pressure-Vacuum Relief System (CP/P-VRS) isolation signal actuated as a result of a channel spike on the Radiation Monitoring System (RMS) Containment Particutate Radiation Monitor, lRllA.

Subsequently, Technical Specification 3.4.6.1 Action Statement was entered.

A second spike and subsequent CP/P-VRS isolation signal occurred the same day at 1011 hours0.0117 days <br />0.281 hours <br />0.00167 weeks <br />3.846855e-4 months <br />.

The root cause of the channel spikes has been attributed to an equipment failure.

The channel drawer PC cards were found dirty.

The lRllA RMS is a NaI scintillation type detector, model LFE MDSB.

The lRllA channel drawer PC cards were cleaned and the channel connectors were checked and found satisfactory.

A channel functional test was successfully completed and, at 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br /> on January 9, 1990, the channel was declared operable and Technical Specification 3.4.6.1 Action Statement was exited.

The preventive maintenance program for the lRllA RMS channel will be reviewed and revised as applicable to prevent recurrence of this event.

NllCF.--

IM31

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit 1 DOCKET NUMBER 5000272

PLANT AND SYSTEM IDENTIFICATION

Westinghouse Pressurized Water Reactor LER NUMBER 90-001-00 PAGE 2 of 4 Energy Industry Identification System (EIIS} codes are identified in the text as {xxJ IDENTIFICATION OF OCCURRENCE:

Engineered Safety Feature Actuation -

Containment Ventilation Isolation Due To Equipment Concerns Event Date:

1/06/90 Report Date:

1/31/90 This report was initiated by Incident Report Nos.90-014, and 90-016.

CONDITIONS PRIOR TO OCCURRENCE:

Mode 1 Reactor Power 100% - Unit Load 1155 MWe DESCRIPTION OF OCCURRENCE:

On January 6, 1990 at 0204 hours0.00236 days <br />0.0567 hours <br />3.373016e-4 weeks <br />7.7622e-5 months <br />, a Containment Purge/Pressure-Vacuum Relief System (CP/P-VRS) isolation signal actuated as a result of a channel spike on the Radiation Monitoring System (RMS) {ILi Containment Particulate Radiation Monitor, lRllA.

Subsequently, Technical Specification 3.4.6.1 Action Statement was entered.

A second spike and subsequent CP/P-VRS isolation signal occurred the same_ day at 1011 hours0.0117 days <br />0.281 hours <br />0.00167 weeks <br />3.846855e-4 months <br />.

Technical Specification 3.4.6.1 states:

"The following Reactor Coolant System leakage detection systems shall be OPERABLE:

a.

The containment atmosphere particulate radioactivity monitoring system, b.

The containment pocket sump level monitoring system, and c.

Either the containment fan cooler condensate flow rate or the containment atmosphere gaseous radioactivity monitoring system."

Technical Specification 3.4.6.1 Action Statement states:

"With only two of the above required leakage detection systems OPERABLE, operation may continue for up to 30 days provided grab samples of the containment atmosphere are obtained and analyzed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the required gaseous and/or particulate radioactivity monitoring system is inoperable;

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit 1 DOCKET NUMBER 5000272 DESCRIPTION OF OCCURRENCE:

(cont'd)

LER NUMBER 90-001-00 PAGE 3 of 4 otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />."

The CP/P-VRS is considered an Engineered Safety System (ESF).

Subsequently, on January 6, 1990 at 0315 hours0.00365 days <br />0.0875 hours <br />5.208333e-4 weeks <br />1.198575e-4 months <br />, and again at 1151 hours0.0133 days <br />0.32 hours <br />0.0019 weeks <br />4.379555e-4 months <br />, the Nuclear Regulatory Commission was notified of the*

automatic actuation signal for CP/P-VRS isolation in accordance with Code of Federal Regulations 10CFR 50.72(b) (2) (ii).

APPARENT CAUSE OF OCCURRENCE:

The cause of the lRllA channel spikes has been attributed to an equipment failure.

The channel drawer PC cards were found dirty.

The lRllA RMS is a NaI scintillation type detector, model LFE MD5B.

ANALYSIS OF OCCURRENCE:

The lRllA, Containment Particulate Monitor, monitor's the air particulate gamma radioactivity in the Containment atmosphere.

It is used identification of Reactor Coolant System {ABJ leakage in conjunction with the containment pocket sump level monitoring system, the containment fan cooler condensate flow rate monitors, and the containment atmosphere gaseous radioactivity ( 1R12A) RMS.channel.

An alarm signal will cause the automatic isolation of the CP/P-VRS.

Air samples are pulled directly from the Containment atmosphere through a filter paper which continuously moves past the lRllA scintillation detector.

After the air sample passes through the filter paper, it passes through a charcoal cartridge (monitored by the 1R12B monitor) and is then mixed into a fixed shielded volume where it is viewed by the 1Rl2A noble gas monitor.

The air sample is then returned to the Containment.

Several area radiation monitors, in addition to the 1R12A monitor*,

are used to corroborate the lRllA channel's indications.

The corroborating area radiation monitors do not have isolation capabilities.

They only have alarm capability.

The 1R41A Plant Vent Particulate monitor also corroborates the lRllA channel indications during Containment purge or pressure-vacuum relief operations.

It also has the capability of automatic isolation of the CP/P-VRS.

During the inoperable period for the lRllA channel, Containment pressure relief was conducted.

The 1R41A channel remained operable during the pressure relief.

During this event, RCS leakage within Containment did not increase.

Additionally, a Containment purge or pressure-vacuum relief was not performed.

Therefore, this event did not affect the health or safety of the public.

However, due to the automatic actuation signal of an ESF system, this event is reportable in accordance with Code of Federal Regulations 10CFR 50.73(a) (2) (iv).

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit 1

CORRECTIVE ACTION

DOCKET NUMBER 5000272 LER NUMBER 90-001-00 PAGE 4 of 4 The lRllA channel drawer PC cards were cleaned and the channel connectors were checked and found satisfactory.

A channel functional test was successfully completed and, at 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br /> on January 9, 1990, the channel was declared operable and Technical Specification 3.4.6.1 Action Statement was exited.

The preventive maintenance program for the lRllA RMS channel will be reviewed and revised as applicable to prevent recurrence of this event.

MJP:pc SORC Mtg.90-008

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General Manager -

Salem Operations

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