ML18096A615

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LER 92-007-00:on 920306,containment Particulate Monitor 1R11A Momentarily Spiked High,Resulting in Pressure Vacuum Relief Isolation Signal.Caused by Detector Failure.Channel Detector Will Be Replaced & Event reviewed.W/920406 Ltr
ML18096A615
Person / Time
Site: Salem PSEG icon.png
Issue date: 04/06/1992
From: Pollack M, Vondra C
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-92-007, LER-92-7, NUDOCS 9204090157
Download: ML18096A615 (6)
v • d • e


Text

e PS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 0803_8 Salem Generating Station_

April 6, 1992 U. S. Nuclear Regulatory Commis~ion Document Control Desk Washington, DC 20555

Dear "Sir:

SALEM GENERATING STATION LIC~NSE NO. DPR-70 DOtKET NO~ 50-272 UNIT NO. 1 LICENSEE EVENT REPORT 92-007-00 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 to be issued within thirty {30} days of -event discovery.

Sincerely yours, C. A Vondra General Manager Salem Operations MJP:pc Distribution

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NRC FORM 366 U.S. NUCLEAR REGULATORY*COMMISSION 16-891 APPROVED OMB N*O. 3150*0104

  • EXPIRES: 4/30/92

. . . ESTIMATED BURDEN PER. RESPONSE TO COMPLY WTH THIS INFORMATION COLl,ECTION .REQUEST: 50.0 .HRS. FORWARD LICENSEE EVENT REPORT (LERI. COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P-530); U.S. NUCLEAR

  • . THE PAPERWORK REDUCTION PROJECT 13150-01041, OFFICE OF MANAGEMENT AND BUDGET', WASHINGTON, DC 20503.

I FACILITY NAME (1 I DOCKET NUMBER (21 . * .I PAtiEl3l Salem*Generatinq Station*- Unit l o 1s 1 o 1o 1 o 12 17 1 2 1 IoF o 1s TITLE (41 ESF Signal Actuation; lRllA Channel spike Ca.using Cont. Vent *. Isolation Signal EVENT DATE (S) . LER NUMBER (61 REPORT DATE (71 OTHER FACILITIES INVOLVED Ult MONTH DAY YEAR *YEAR  :;::::} SEQUENTIAL I::;:;:;:; REVISION MONTH DAY YEAR FACI LITV NAMES DOCKET* NUMBER(S)

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. OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE RloQUIREMENTS OF 10 CFR §: (CMck ono or mo;o of tho following) (111*.

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LICENSEE CONTACT FOR THIS LER (121 NAME TELEPHONE NUMBER AREA CODE M. J. Pollack.- LER Coordinator

  • COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (131

. MANUFAC-CAUSE SYSTEM COMPONENT TURER I I I I . I I I I I I

  • 1 I I I I I I I I I I I I I I I I I I SUPPLEMENTAL REPORT EXPECTED (14) MONTH . DAY YEAR

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  • EXPECTED n YES !If. VII, comp/1t1 EXPECTED SUBMISSIO_N DATE)

ABSTRACT (Limit to 1400 spocos, i.o:, 1pproxim1to/y ..fiftoon sin11t..,poc1 typowritton /inss) (16) bxi NO SUBMISSION DATE (151 I I This LER addresses an Engineered Safety Feature (ESF) signal ini_tiated through the Radiation Monitoring System (RMS). This signal was for Containment Purge/Pressure-Vacuum Relief '<cP/P-VR) System isolation.

On 3/6/92, at 1926-hoursi the lRllA Containment Particul*te RMS Monitor channel momentarily spiked high resulting in a CP/P-VR System isolation signal. Ch~nnel indication returned to normal after the spike. The lRllA RMS channel was declared inoperable and an investigation to determine .the cause of. the event was ini tici,ted. The isolation valves were closed at the time and did not change position as a result of the isolation signal. The cause of this event is attributed to equipment failure.* - The detector ,cable was che.cked for insulation resistance {j.e.j *eggered the cable} and was check~d fbr cbntiriuity.. Results w~re satisfactory. Also, the cable was manipulated, at the detector and the ratemeter drawer, in an attempt to reproduce the channel spikirig; however, it could n~t be reprod~ced. The channel has been operatin~ for the past month without recurrence of a channel spike. The lRllA RMS channel was successfully channel checked and so~rce checked. ~ased on engineering assessrnerit.

of the results of the inv~stigatiori to date, the most likely cause of~

this event was a detector problem. Therefore, the detector will be replaced.

NRC Form 386 (6-89)

  • LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Sal*ern Generating Station DOCKET NUMBER LER NUMBER PAGE Un_i_t__l____ _ ____________?_Q_Q_Q_~.72___ -**-------~-~-::.O_Q?_::_Q_Q ________ 2___of ___?___ _

Westinghouse P~essurized Water Reactor Energy Industry Identificati~n Systsm (EIIS) codes are identified in the text as {xxl Engineered Safety Feature signal actuation; Radiation Monitoring Systeni channel spike Event Date: 3/06/92 Report Date: 4/06/92 This report was initiated by Incident Report No.92-167.

CONDITIONS

- PRIOR TO OCCURRENCE:

Mode 1 Reactor Power 100% - *Unit l'oad 1160. MWe DESCRIPTION OF OCCURRENCE:

This LER addresses an Engineered Safety Feature (ESF) signal initiated through the Radiation Monitoring System (RMS) {ILi. This signal was for Containment Purg~/Pres~ure~vacuum Relief (CP/P-VR)

System {BF} isolation.

On March 6, 1992, at 1926 hour0.0223 days <br />0.535 hours <br />0.00318 weeks <br />7.32843e-4 months <br />s*, the 1R11A Containment Particulate RMS Monitor channel momentarily spiked high resulting in a CP/P-VR System isolation sign~l. Ch~nnel indication returned to normal after the spike~ The 1R11A RMS ~hannel was declared inoperable artd an investigation to deter~ine the cause of the event* was initiated.

The isolation valves were closed at the time and did.not change position as a result of the isolation signal. Technical Specification 3.3.2.1, 3.3.3.1, 3.3.3.9 and 3.4.6.1 Ac~ion Statements were entered.

Technical Specification Table 3.3-6 Action 20 states:

"With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.6.1".

Technical Specification 3.4.6.1 states:

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

a. The con*tainment atmosphere particulate radioactivity monitoring system,

e LICENSEE EVENT REPORT ( LER) TEXT.* CONTINUATION

--.---* --------------------------- ---------'*-* -**** --**---. --*-- .*----~-----*----o.:-~---------------

S alem Generating Station DOCKET NUMBER LER NUMBER PAGE

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b. *The containment sump level monitoring system, and
c. Either the containment fan cooler condensate flow r~te or the containment atmosphere ~aseous radioactivity mdnitoring system."_

Technical Specification 3;4.6~1 Action Statement states:

dWith only t~o of the above required leakage detection systems OPERABLE, operation may continue for up to 30 days provided grab samples of the containment a*tniosphere 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 reqtiired gaseous and/or particulate radioactivity monitoring system is inoperable; 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 iri 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-VR System isolation signal is an Engineered Safety Feature (ESF). Therefore, the Nuclear Regulatory Commission was.notified in accordance with Code of Federal Regulations 10CFR 50.72{b) (2) (ii) oh March 6, 1992 at 1944 hours0.0225 days <br />0.54 hours <br />0.00321 weeks <br />7.39692e-4 months <br />.

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The cause of this. everit is attributed to equipment failure.

The detector cable was checked for itisulation resistaftce (i.e.,

meggered the cable) and was checked for continuity. Results were satisfactory. Also, the cable was m~nipulated, at the detector and the ratemeter drawer, in an attempt to reproduce the channel spiking; however, it could not be reproduced~ The channel ha$ been operating for the past month without recurrenc~ of a channel spike. Based on engineering assessment of the results of the investigation to date, the most likely cause of thii event ~as a detectoi problem.

Therefore, the detector will be replaced.

At about the time of this ~vent, a Chemistry technician *as obtaining a Containment grab sample using the lRllA 'sample piping. The Chemistry technician was interviewed and his work procedure reviewed; however, it coul~ n6t be shown that hi~ activities contribute~ to the cause of the channel spike.

ANALYSIS OF OCCURRENCE: --**------~--

Isolation of the CP/P-VR System is an ESF. It mitigates the release of-radioactive*material ~o the environment after a d~sign basis accident.

Air samples are pulled from the Containment through filter paper which continuously moves past the lRllA (Containment Particulate Radiation M6nitor) detector. The air sample then passes through a charcoal cartridge (monitored by the 1R12B det~ctor) and is mixed

-*--------*--------*--------------***-- -. ----*--- ------~-----*--**----- **--*----~----------* __ ..._ ___________________ - .

- LICENSEE EVENT REPORT {LER) TEXT CONTINUATION

*-*------------------ --*--------*----- -------*-* ----* . ---~--- - - - -*--*--*------------

Sslem Generating Station DOCKET NUMBER .LER NUMBER PAGE Unit 1

**-------*-*****- - - - - - - - - - -- ---'---!?_Q_Q_Q_~.7-~----------~--- ~-~--:_Q_Q_?_~_Q_Q _______ ~__QJ __;;__

into a fixed shielded volume where it is viewed by the 1R12A (Containment Noble Gas Radiation Monitor) detector~ The air sample is then returned to the Containment.

The 1R11A Containment Particulate Monitor, (a NaI scintillation type detector, model LFE MD5B) monitors air particulate gamma .radio-activity- in.the Containment atmosphere. It is used to id~ntify Reactor Coolant System (RCS) {ABI leakage in conjunction with the contairiment sump level monitoring system, and either the containment fan c~oler_ condensate flow _rate or the containment atmosphere gaseous (1R12A) radioactivity monitoring sy~tem.-

Both the 1R11A and 1R12A RMS channels ~rovide an alarm signal which will cause the automatic isolation of the CP/P-VR System.

During this event, RCS leakage within the Containment did not increase. Also, the isolation valves were- closed at the time.

Therefore, this event did not affect the health or safety of the public. However! d~e to the automatic ~ctuation sign~l of an ESF system, they are reportable in accordance *ith Code of Federal Regula~ions 10CFR 50.7j(a) [2)(iv).

A similar event occurred on November 14, 1991 du.ring cleaning of the 1~11A- RMS channel sample bo~ (refeience -L~R 272/91-032-00). That event also was tbought to have possibly been caused by movement of the subject lead blankets. However, in that everit and this event, the ch~nnel spike could not be recreated. Subsequent 1R11A channel events (reference LER 272/91-034-00), on November 26, 1991 and December 26, 1991, revealed that the field cable connector signal wire was shorting against the shield wire making the channel susceptible t6 spiking if the cable is manipulated. The spiking was duplicated by moving the cable. The cable connection w~s subsequently repaired.

CORRECTIVE ACTION:

The.detector cable was checked for insulation resistance (i.e.,

rneggered the cable) and was checked for contiriuity. Results were satisfactory. Also, the cable was manipulated, at the detector_and the ratemeter drawer, in an attempt to reproduce the channel spiking; however, it could not be reproduced. The channel has been operatin~

for the past month wi.thout recurrence of a channel spike.

The 1R11A RMS channel was successfully channe1 checked and source checked.

System Engineering has reviewed the results of the channel trouble~hooting and the actions taken by the Chemistry technician.

Based on this review, the 1R11A RMS channel detector will be replaced (see Apparent Cause of Occurrence Section).

LICENSEE EVENT REPORT (LER). TEXT CONTINUATION*

Sal~m Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 1 5~00272

  • --- 92~007-00

--- - ---------------*- --- -------------- ----------- ~--C?J___5_.,-

CO~RECTIV.JL~<;TJ_QJi__: _J <;_Q.!_l~g)_

The ~irc~mstances sar~oundin~ thi~ event will be reviewed with applicable Chemistry Department personnel.*

eneraL ~a ager -

Salem Operations MJP:pc*

SORC Mtg.92-041

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