ML18096A808: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
Line 16: Line 16:


=Text=
=Text=
{{#Wiki_filter: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  
{{#Wiki_filter:OPS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey,08038 Salem Generating Station July 2, 1992
: u. _s. Nuclear Regulatory commission Document Control Desk Washington, DC                 20555


==Dear sir:==
==Dear sir:==
SALEM GENERATING STATION LICENSE NO. DPR-70 DOCKET NO. 50-272 UNIT NO. 1 LICENSEE EVENT REPORT 92-013-00 July 2, 1992 This Licensee Event Report is being submitted pursuant to the requirements of the Code of Federal Regulations lOCFR 50.73(a) (2) (iv). This report is required to be issued within *thirty (30) days of event discovery.
 
MJP:pc Distribution Since ely yours, c. A Vondra General Manager -Salem Operations Thi:: (,*,pr.nv PP.onl8 9207070382 920702 PDR ADOCK 05000272 ri:: a."2. ,, , 95-2189 (10M) 12-89 S . PDR NRC FORM366 16-891 U.S. NUCLEAR REGULATORY COMMISSION APPROVED OMB NO. 3150-0104 EKPIRES: 4/30/92 LICENSEE EVENT REPORT CLER) FACILITY NAME 111 Salem Generatina Station -Unit 1 TITLE l'I ESTIMATED BURDEN PER RESPONSE*
SALEM GENERATING STATION LICENSE NO. DPR-70 DOCKET NO. 50-272 UNIT NO. 1 LICENSEE EVENT REPORT 92-013-00 This Licensee Event Report is being submitted pursuant to the requirements of the Code of Federal Regulations lOCFR 50.73(a) (2) (iv). This report is required to be issued within
TO COMPLV WTH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P-6301. U.S. NUCLEAR REGULATORY COMMISSION.
*thirty (30) days of event discovery.
WASHINGTON.
Since ely yours,
DC 20555. AND TO . THE PAPERWORK REDUCTION PROJECT (3150-01041.
: c. A Vondra General Manager -
OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON.
Salem Operations MJP:pc Distribution Thi:: (,*,pr.nv PP.onl8 ri::,,a."2.
DC 20S03. I DOCKET NUMBER 121 I PAii!: 131 . o 1s101010121112l1loF 013 2 Enqineered Safety Feature actuation siqnals initiated from the Radiation Monitoring Syst. EVENT DATE 151 LER NUMBER Ill REPORT DATE (71 OTHER FACILITIES INVOLVED Ill MONTH DAY VEAR YEAR mr
                                                                                                ,
{?
9207070382 920702 PDR ADOCK 05000272                                                                    95-2189 (10M) 12-89 S                   . PDR
MONTH DAY YEAR FACILITY NAMES . DOCKET NUMBERISI 016012 929l2-ol1b-olo*oh cl2912 01s1010101 I I OPERATING THll REPORT IS SUBMITTED PURSUANT TO THE OF 10 CFR §: (Chtck on1 or mor1 (!f th* fo/lowinlJ}
 
1111 ___ MO_D_E...,11_1
NRC FORM366                                                                               U.S. NUCLEAR REGULATORY COMMISSION 16-891                                                                                                                                                  APPROVED OMB NO. 3150-0104 EKPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE* TO COMPLV WTH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD LICENSEE EVENT REPORT CLER)                                                                    COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P-6301. U.S. NUCLEAR REGULATORY COMMISSION. WASHINGTON. DC 20555. AND TO .
_ __,._6;;;.+--1 20.4021bl . POWER I 20.4051*1111111 LEVEL -1101 I I 20.4051111111111 NAME 20.40511111111111 20.40511111 lllvl . 20.4051*111 IM M i Coordinator 20.4051cl x ....._ -llCl.31(cll11  
THE PAPERWORK REDUCTION PROJECT (3150-01041. OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON. DC 20S03.
-.__ llCl.3111cll21
I FACILITY NAME 111                                                                                                                                DOCKET NUMBER 121                     I   PAii!: 131 Salem Generatina Station - Unit 1                                                                                                        . o 1s101010121112l1loF 013 TITLE l'I 2 Enqineered Safety Feature actuation siqnals initiated from the Radiation Monitoring Syst.
-.__ 50.731*1121111
EVENT DATE 151                             LER NUMBER Ill                               REPORT DATE (71                         OTHER FACILITIES INVOLVED Ill MONTH       DAY         VEAR       YEAR     mr   SE~~~~~~AL      {? :~~~~            MONTH         DAY YEAR               FACILITY NAMES .                   DOCKET NUMBERISI 016012                   929l2-ol1b-olo*oh                                                             cl2912                                                       01s1010101               I     I OPERATING                     THll REPORT IS SUBMITTED PURSUANT TO THE R~OUIREMENTI OF 10 CFR                   §: (Chtck on1 or mor1 (!f th* fo/lowinlJ} 1111
-.__ 5D.73lall211iil
___
....._ -5D.731111211iill LICENSEE CONTACT FOR THIS LER 1121 llD.731111211i*I 73.711bl -llD.73111121M 73.711cl 1--ll0.731*11211&#xa5;111 OTHER fS1><<ify in Ab1troct -IM/ow ind in Tur *. NRC Form ll0.7311112ll*lllllAI 366AI l50.731*112ll*llillBI ll0.731*11211*1 TELEPHONE NUMBER AREA CODE 6 1019 313191-12!01212 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 1131 CAUSE SYSTEM COMPONENT I I I I I I I I MANUFAC* TUR ER I. I I I I I SUPPLEMENTAL REPORT EKPECTED 1141 n YES (If y1r. comol1t1 EXPECTED SUBMISSION DATE} rx, N.0 ABSTRACT (Limir ro 1400 *J>>C**. i.* .. *pprOllim*t.ly fift11n 1inglt1*l1Jac*  
  . POWER LEVEL I
/in**} (111 I I I I I I I I MANUFAC* . TURER I I I I I I EXPECTED SUBMISSION DATE 1151 MONTH DAY VEAR I I I on 6/2/92, at 0043 hours, the iRlA Control Room General Area Monitor and the lRllA Containment Particulate Radiation Monitoring System (RMS) Monitor channels spiked into alarm*. The lRlA channel spike caused control.Room Ventilation to switch to the emergency mode of operation in both Units (by design) and the lRllA channel spike caused Containment Purge/Pressure-Vacuum Relief System isolation (both are ESF signals).
MO_D_E...,11_1_
At the time of the lRlA and lRllA RMS channel spikes a design change was being incorporated*to the lA Vital Instrument Inverter and the inverter was aligned to support preventive maintenance.
I
The cause of this event is attributed to an electrical perturbation on the lA 115 VAC system. Investigation to date has not identified the cause of the perturbation.
__,._6;;;.+--1
The following tests did not reveal any anomalies;
                                  -
: 1) inverter fan testing and 2) ESF manual safety injection testing where lA Vital Bus loads were shed and sequenced on. The lRllA and lRlA RMS channels were returned to service following resetting of their alarm interlock functions.
20.4021bl 20.4051*1111111
Investigation of the electrical perturbation is continuing.
                                                                                  ....._
NRC Form 366 (6-891 LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit 1 DOCKET NUMBER 5000272 PLANT AND SYSTEM IDENTIFICATION:
                                                                                  --
Westinghouse Pressurized Water Reactor LER NUMBER 92-013-00
20.4051cl llCl.31(cll11             -
*PAGE 2 of 3 Energy Industry Identification System (EIIS) codes are identified in the text as {xx} IDENTIFICATION OF OCCURRENCE:
                                                                                                                      .__
2 Engineered Safety Feature actuation signals initiated from the Radiation Monitoring System Event Dates: 6/02/92 .Report Date: 7/02/92 This report was initiated by Incident Report No. 92-353. CONDITIONS PRIOR TO OCCURRENCE:
                                                                                                                      .__
x  llD.731111211i*I llD.73111121M                        -
1--
73.711bl 73.711cl 1101                    I            20.4051111111111                                llCl.3111cll21                      ll0.731*11211&#xa5;111
                                                                                                                                                                    -    OTHER fS1><<ify in Ab1troct IM/ow ind in Tur* .NRC Form 20.40511111111111 20.40511111 lllvl .
20.4051*111 IM
                                                                                  -
                                                                                  ....._
50.731*1121111 5D.73lall211iil 5D.731111211iill          -
                                                                                                                      .__    ll0.7311112ll*lllllAI l50.731*112ll*llillBI ll0.731*11211*1 366AI LICENSEE CONTACT FOR THIS LER 1121 NAME                                                                                                                                                                TELEPHONE NUMBER AREA CODE M      i        >>~11~~~ ~* T.~~                  Coordinator                                                                                    6 1019           313191-12!01212 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 1131 MANUFAC*                                                                                        MANUFAC*
CAUSE     SYSTEM         COMPONENT TUR ER                                                                                        . TURER I          I    I    I           I. I       I                                                     I             I     I   I       I    I    I I          I    I    I            I    I    I                                                    I            I     I   I       I   I     I SUPPLEMENTAL REPORT EKPECTED 1141                                                                                     MONTH      DAY      VEAR rx, EXPECTED n     YES (If y1r. comol1t1 EXPECTED SUBMISSION DATE}                                                   N.0 SUBMISSION DATE 1151 I      I          I ABSTRACT (Limir ro 1400       *J>>C**. i.*.. *pprOllim*t.ly fift11n 1inglt1*l1Jac* ty~w;itr.n /in**} (111 on 6/2/92, at 0043 hours, the iRlA Control Room General Area Monitor and the lRllA Containment Particulate Radiation Monitoring System (RMS)
Monitor channels spiked into alarm*. The lRlA channel spike caused control.Room Ventilation to switch to the emergency mode of operation in both Units (by design) and the lRllA channel spike caused Containment Purge/Pressure-Vacuum Relief System isolation (both are ESF signals). At the time of the lRlA and lRllA RMS channel spikes a design change was being incorporated*to the lA Vital Instrument Inverter and the inverter was aligned to support preventive maintenance. The cause of this event is attributed to an electrical perturbation on the lA 115 VAC system.
Investigation to date has not identified the cause of the perturbation.
The following tests did not reveal any anomalies; 1) inverter fan a~sembly testing and 2) ESF manual safety injection testing where lA Vital Bus loads were shed and sequenced on. The lRllA and lRlA RMS channels were returned to service following resetting of their alarm interlock functions. Investigation of the electrical perturbation is continuing.
NRC Form 366 (6-891
 
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station         DOCKET NUMBER      LER NUMBER      *PAGE Unit 1                               5000272         92-013-00        2 of 3 PLANT AND SYSTEM IDENTIFICATION:
Westinghouse     Pressurized Water Reactor Energy Industry Identification System (EIIS) codes are identified in the text as {xx}
IDENTIFICATION OF OCCURRENCE:
2 Engineered Safety Feature actuation signals initiated from the Radiation Monitoring System Event Dates:   6/02/92
    .Report Date:     7/02/92 This report was initiated by Incident Report No. 92-353.
CONDITIONS PRIOR TO OCCURRENCE:
Mode 6 (Refueling) 10th Refueling Outage in progress DESCRIPTION OF OCCURRENCE:
Mode 6 (Refueling) 10th Refueling Outage in progress DESCRIPTION OF OCCURRENCE:
On June 2, 1992, at 0043 hours, the lRlA Control Room General Area Monitor .and *the 1R11A Containment Par.ticulate Radiation Monitoring System (RMS) Monitor channels {IL} spiked into alarm. The lRlA channel spike caused Control Room Ventilation to switch to the Emergency Mode of Operation in both Units (by design) and the 1Rl1A channel spike caused a Containment Purge/Pressure-Vacuum Relief* (CP/P-VR)
On June 2, 1992, at 0043 hours, the lRlA Control Room General Area Monitor .and *the 1R11A Containment Par.ticulate Radiation Monitoring System (RMS) Monitor channels {IL} spiked into alarm. The lRlA channel spike caused Control Room Ventilation to switch to the Emergency Mode of Operation in both Units (by design) and the 1Rl1A channel spike caused a Containment Purge/Pressure-Vacuum Relief*
System {BF} isolation signal. * . In addition to the RMS channel spikes., other equipment.
(CP/P-VR) System {BF} isolation signal.       *
fed by the 1A Vital Instrument Bus experienced electrical perturbation (e.g., failure of the Hydrogen Analyzer.).
    . In addition to the RMS channel spikes., other equipment. fed by the 1A Vital Instrument Bus experienced electrical perturbation (e.g.,
The 1R1A and 1Rl1A RMS channel spikes occurred while a design change was being incorporated to the lA Vital Instrument Inverter and the inverter was aligned to support preventive maintenance  
failure of the Hydrogen Analyzer.).
.. The AC line regulator was deenergized and the inverter was manually selected to supply power to the lA Vital Instrument Bus., During the design change, it was required to remove the AC line regulator cooling fan fuses to allow fan alarm relay replacement.
The 1R1A and 1Rl1A RMS channel spikes occurred while     a design change was being incorporated to the lA Vital Instrument Inverter and the inverter was aligned to support preventive maintenance .. The AC line regulator was deenergized and the inverter was manually selected to supply power to the lA Vital Instrument Bus.,
During the design change, it was required to remove the AC line regulator cooling fan fuses to allow fan alarm relay replacement.
When the first fan fuse was removed, the technician observed an audible change in the inverter's background noise. This noise change is related to an increase/decrease in the inverter load or 'input AC voltage changes. Concurrently, the Control Rooin operators observed RMS channel spiking (including the 1R1A* and 1RllA channels) and
When the first fan fuse was removed, the technician observed an audible change in the inverter's background noise. This noise change is related to an increase/decrease in the inverter load or 'input AC voltage changes. Concurrently, the Control Rooin operators observed RMS channel spiking (including the 1R1A* and 1RllA channels) and
* numerous overhead alarms. The affected equipment is powered.from lA . Vital Instrument  
* numerous overhead alarms. The affected equipment is powered.from lA
*Bus. *
  . Vital Instrument *Bus.
* LICENSEE EVENT REPORT *(LER) TEXT CONTINUATION Salem Generating Station Unit 1 . DOCKET NUMBER 5000272 DESCRIPTION OF OCCURRENCE: (cont'd) LER NUMBER 92-013-00 PAGE 3 of 3 The containment ventilation isolation valves were open at* the time of this event; i.e., Containment Purge was in progress.
* LICENSEE EVENT REPORT *(LER) TEXT CONTINUATION
The valves closed per design upon RMS actuation.
* Salem Generating Station         DOCKET NUMBER    LER NUMBER      PAGE Unit 1           .                 5000272       92-013-00      3 of 3 DESCRIPTION OF OCCURRENCE:     (cont'd)
Also, the equipment required to change state, as a result of the lRlA actuation, responded per design. Control Room ventilation switching to its emergency mode of operation and CP/P-VR System isolation are Engineered Safety Features (ESFs). Therefore, the Nuclear Regulatory Commission (NRC) was notified of these actuation signals in accordance with Code of Federal Regulations lOCFR 50.72(b) (2) (ii). on June 2, 1992, at 0209 hours. APPARENT CAUSE OF OCCURRENCE:
The containment ventilation isolation valves were open at* the time of this event; i.e., Containment Purge was in progress. The valves closed per design upon RMS actuation. Also, the equipment required to change state, as a result of the lRlA actuation, responded per design.
The cause of this event is attributed to an electrical perturbation on the lA 115 VAC system. Investigation to date has not identified the cause of the perturbation.
Control Room ventilation switching to its emergency mode of operation and CP/P-VR System isolation are Engineered Safety Features (ESFs).
The following tests did not reveal any anomalies:
Therefore, the Nuclear Regulatory Commission (NRC) was notified of these actuation signals in accordance with Code of Federal Regulations lOCFR 50.72(b) (2) (ii). on June 2, 1992, at 0209 hours.
: 1) inverter fan assembly testing and 2) ESF manual safety injection testing where lA Vital Bus loads were shed and sequenced on. ANALYSIS OF OCCURRENCE:
APPARENT CAUSE OF OCCURRENCE:
Isolation of the CP/P-VR System is an ESF. It mitigates the release of radioactive material to the environment after a design basis accident.
The cause of this event is attributed to an electrical perturbation on the lA 115 VAC system. Investigation to date has not identified the cause of the perturbation. The following tests did not reveal any anomalies:   1) inverter fan assembly testing and 2) ESF manual safety injection testing where lA Vital Bus loads were shed and sequenced on.
Switching of the Control Room ventilation to the accident mode of operation (100% recirculation) is also an ESF. .It allows continued Control Room habitability during accidents.
                                                                              *1 i
The two (2) ESF actuations did not result from an increase in Containment particulate activity or Control Room ventilation duct radiation levels. This event did not affect the health or safety of the public;* however,-it is reportable to the NRC in accordance with Code of Federal Regulations lOCFR 50.73(a) (2) (iv). CORRECTIVE ACTION: The lRllA and lRlA RMS channels were returned to service following resetting of their alarm interlock functions.
ANALYSIS OF OCCURRENCE:                                                       I I
Also, the other affected equipment were returned to service. Investigation of the electrical perturbation is continuing.
Isolation of the CP/P-VR System is an ESF. It mitigates the release of radioactive material to the environment after a design basis accident. Switching of the Control Room ventilation to the accident mode of operation (100% recirculation) is also an ESF. .It allows continued Control Room habitability during post~lated accidents.
The lA Vital Instrument Bus functioned as designed.
The two (2) ESF actuations did not result from an increase in Containment particulate activity or Control Room ventilation duct radiation levels. This event did not affect the health or safety of the public;* however,-it is reportable to the NRC in accordance with Code of Federal Regulations lOCFR 50.73(a) (2) (iv).
No MJP:pc SORC Mtg. 92-072 was found.to have *1 i I I}}
CORRECTIVE ACTION:
The lRllA and lRlA RMS channels were returned to service following resetting of their alarm interlock functions. Also, the other affected equipment were returned to service.
Investigation of the electrical perturbation is continuing.
The lA Vital Instrument Bus                           was found.to have functioned as designed. No MJP:pc SORC Mtg. 92-072}}

Revision as of 11:15, 21 October 2019

LER 92-013-00:on 920602,two ESF Actuation Signals Initiated from Radiation Monitoring Sys Causing Alarm.Cause Attributed to an Electrical Fault in Sys.Both Channels Returned to Service After Resetting Alarm functions.W/920702 Ltr
ML18096A808
Person / Time
Site: Salem PSEG icon.png
Issue date: 07/02/1992
From: Pollack M, Vondra C
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-92-013, LER-92-13, NUDOCS 9207070382
Download: ML18096A808 (4)
v • d • e


Text

OPS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey,08038 Salem Generating Station July 2, 1992

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 92-013-00 This Licensee Event Report is being submitted pursuant to the requirements of the Code of Federal Regulations lOCFR 50.73(a) (2) (iv). This report is required to be issued within

  • thirty (30) days of event discovery.

Since ely yours,

c. A Vondra General Manager -

Salem Operations MJP:pc Distribution Thi:: (,*,pr.nv PP.onl8 ri::,,a."2.

,

9207070382 920702 PDR ADOCK 05000272 95-2189 (10M) 12-89 S . PDR

NRC FORM366 U.S. NUCLEAR REGULATORY COMMISSION 16-891 APPROVED OMB NO. 3150-0104 EKPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE* TO COMPLV WTH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD LICENSEE EVENT REPORT CLER) COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P-6301. U.S. NUCLEAR REGULATORY COMMISSION. WASHINGTON. DC 20555. AND TO .

THE PAPERWORK REDUCTION PROJECT (3150-01041. OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON. DC 20S03.

I FACILITY NAME 111 DOCKET NUMBER 121 I PAii!: 131 Salem Generatina Station - Unit 1 . o 1s101010121112l1loF 013 TITLE l'I 2 Enqineered Safety Feature actuation siqnals initiated from the Radiation Monitoring Syst.

EVENT DATE 151 LER NUMBER Ill REPORT DATE (71 OTHER FACILITIES INVOLVED Ill MONTH DAY VEAR YEAR mr SE~~~~~~AL {? :~~~~ MONTH DAY YEAR FACILITY NAMES . DOCKET NUMBERISI 016012 929l2-ol1b-olo*oh cl2912 01s1010101 I I OPERATING THll REPORT IS SUBMITTED PURSUANT TO THE R~OUIREMENTI OF 10 CFR §: (Chtck on1 or mor1 (!f th* fo/lowinlJ} 1111

___

. POWER LEVEL I

MO_D_E...,11_1_

I

__,._6;;;.+--1

-

20.4021bl 20.4051*1111111

....._

--

20.4051cl llCl.31(cll11 -

.__

.__

x llD.731111211i*I llD.73111121M -

1--

73.711bl 73.711cl 1101 I 20.4051111111111 llCl.3111cll21 ll0.731*11211¥111

- OTHER fS1><<ify in Ab1troct IM/ow ind in Tur* .NRC Form 20.40511111111111 20.40511111 lllvl .

20.4051*111 IM

-

....._

50.731*1121111 5D.73lall211iil 5D.731111211iill -

.__ ll0.7311112ll*lllllAI l50.731*112ll*llillBI ll0.731*11211*1 366AI LICENSEE CONTACT FOR THIS LER 1121 NAME TELEPHONE NUMBER AREA CODE M i >>~11~~~ ~* T.~~ Coordinator 6 1019 313191-12!01212 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 1131 MANUFAC* MANUFAC*

CAUSE SYSTEM COMPONENT TUR ER . TURER I I I I I. I I I I I I I I I I I I I I I I I I I I I I I SUPPLEMENTAL REPORT EKPECTED 1141 MONTH DAY VEAR rx, EXPECTED n YES (If y1r. comol1t1 EXPECTED SUBMISSION DATE} N.0 SUBMISSION DATE 1151 I I I ABSTRACT (Limir ro 1400 *J>>C**. i.*.. *pprOllim*t.ly fift11n 1inglt1*l1Jac* ty~w;itr.n /in**} (111 on 6/2/92, at 0043 hours4.976852e-4 days <br />0.0119 hours <br />7.109788e-5 weeks <br />1.63615e-5 months <br />, the iRlA Control Room General Area Monitor and the lRllA Containment Particulate Radiation Monitoring System (RMS)

Monitor channels spiked into alarm*. The lRlA channel spike caused control.Room Ventilation to switch to the emergency mode of operation in both Units (by design) and the lRllA channel spike caused Containment Purge/Pressure-Vacuum Relief System isolation (both are ESF signals). At the time of the lRlA and lRllA RMS channel spikes a design change was being incorporated*to the lA Vital Instrument Inverter and the inverter was aligned to support preventive maintenance. The cause of this event is attributed to an electrical perturbation on the lA 115 VAC system.

Investigation to date has not identified the cause of the perturbation.

The following tests did not reveal any anomalies; 1) inverter fan a~sembly testing and 2) ESF manual safety injection testing where lA Vital Bus loads were shed and sequenced on. The lRllA and lRlA RMS channels were returned to service following resetting of their alarm interlock functions. Investigation of the electrical perturbation is continuing.

NRC Form 366 (6-891

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER *PAGE Unit 1 5000272 92-013-00 2 of 3 PLANT AND SYSTEM IDENTIFICATION:

Westinghouse Pressurized Water Reactor Energy Industry Identification System (EIIS) codes are identified in the text as {xx}

IDENTIFICATION OF OCCURRENCE:

2 Engineered Safety Feature actuation signals initiated from the Radiation Monitoring System Event Dates: 6/02/92

.Report Date: 7/02/92 This report was initiated by Incident Report No.92-353.

CONDITIONS PRIOR TO OCCURRENCE:

Mode 6 (Refueling) 10th Refueling Outage in progress DESCRIPTION OF OCCURRENCE:

On June 2, 1992, at 0043 hours4.976852e-4 days <br />0.0119 hours <br />7.109788e-5 weeks <br />1.63615e-5 months <br />, the lRlA Control Room General Area Monitor .and *the 1R11A Containment Par.ticulate Radiation Monitoring System (RMS) Monitor channels {IL} spiked into alarm. The lRlA channel spike caused Control Room Ventilation to switch to the Emergency Mode of Operation in both Units (by design) and the 1Rl1A channel spike caused a Containment Purge/Pressure-Vacuum Relief*

(CP/P-VR) System {BF} isolation signal. *

. In addition to the RMS channel spikes., other equipment. fed by the 1A Vital Instrument Bus experienced electrical perturbation (e.g.,

failure of the Hydrogen Analyzer.).

The 1R1A and 1Rl1A RMS channel spikes occurred while a design change was being incorporated to the lA Vital Instrument Inverter and the inverter was aligned to support preventive maintenance .. The AC line regulator was deenergized and the inverter was manually selected to supply power to the lA Vital Instrument Bus.,

During the design change, it was required to remove the AC line regulator cooling fan fuses to allow fan alarm relay replacement.

When the first fan fuse was removed, the technician observed an audible change in the inverter's background noise. This noise change is related to an increase/decrease in the inverter load or 'input AC voltage changes. Concurrently, the Control Rooin operators observed RMS channel spiking (including the 1R1A* and 1RllA channels) and

  • numerous overhead alarms. The affected equipment is powered.from lA

. Vital Instrument *Bus.

  • LICENSEE EVENT REPORT *(LER) TEXT CONTINUATION
  • Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 1 . 5000272 92-013-00 3 of 3 DESCRIPTION OF OCCURRENCE: (cont'd)

The containment ventilation isolation valves were open at* the time of this event; i.e., Containment Purge was in progress. The valves closed per design upon RMS actuation. Also, the equipment required to change state, as a result of the lRlA actuation, responded per design.

Control Room ventilation switching to its emergency mode of operation and CP/P-VR System isolation are Engineered Safety Features (ESFs).

Therefore, the Nuclear Regulatory Commission (NRC) was notified of these actuation signals in accordance with Code of Federal Regulations lOCFR 50.72(b) (2) (ii). on June 2, 1992, at 0209 hours0.00242 days <br />0.0581 hours <br />3.455688e-4 weeks <br />7.95245e-5 months <br />.

APPARENT CAUSE OF OCCURRENCE:

The cause of this event is attributed to an electrical perturbation on the lA 115 VAC system. Investigation to date has not identified the cause of the perturbation. The following tests did not reveal any anomalies: 1) inverter fan assembly testing and 2) ESF manual safety injection testing where lA Vital Bus loads were shed and sequenced on.

  • 1 i

ANALYSIS OF OCCURRENCE: I I

Isolation of the CP/P-VR System is an ESF. It mitigates the release of radioactive material to the environment after a design basis accident. Switching of the Control Room ventilation to the accident mode of operation (100% recirculation) is also an ESF. .It allows continued Control Room habitability during post~lated accidents.

The two (2) ESF actuations did not result from an increase in Containment particulate activity or Control Room ventilation duct radiation levels. This event did not affect the health or safety of the public;* however,-it is reportable to the NRC in accordance with Code of Federal Regulations lOCFR 50.73(a) (2) (iv).

CORRECTIVE ACTION:

The lRllA and lRlA RMS channels were returned to service following resetting of their alarm interlock functions. Also, the other affected equipment were returned to service.

Investigation of the electrical perturbation is continuing.

The lA Vital Instrument Bus was found.to have functioned as designed. No MJP:pc SORC Mtg.92-072

Retrieved from "https://kanterella.com/w/index.php?title=ML18096A808&oldid=1939655"