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Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEAR05000354/LER-1990-0091990-07-0505 July 1990 LER 90-009-00:on 900607,HPCI Sys Oil Samples Indicated High Water Content & Traces of Sediment Contamination.Caused by Design Deficiency in HPCI Turbine Lube Oil Reservoir. Reservoir Cleaned,Flushed & Wiped down.W/900705 Ltr 05000354/LER-1990-0081990-07-0505 July 1990 LER 90-008-00:on 900604,reactor Bldg Exhaust Radiation Monitor Trip Setpoint Found Nonconservatively High.Caused by Personnel Error.Technicians Disciplined,Rept Reviewed W/All Personnel & Setpoint Included in procedure.W/900705 Ltr 1990-07-05
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217F1501999-10-12012 October 1999 Special Rept:On 990929,south Plant Vent (SPV) Range Ng Monitor Was Inoperable.Monitor Was Inoperable for More than 72 H.Caused by Electronic Noise Generated from Noise Suppression Circuit.Replaced Circuit ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML20217N6531999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Hope Creek Generating Station,Unit 1.With ML20217M0211999-09-20020 September 1999 Part 21 Rept Re Possible Deviation of NLI Dc Power Supply Over Voltage Protection Circuit Actuation.Caused by Electrical Circuit Conditions Unique to Remote Engine Panel. Travelled to Hope Creek to Witness Startup Sequence of DG ML20211N5531999-09-0808 September 1999 Safety Evaluation Supporting Amend 121 to License NPF-57 ML20211B3781999-08-13013 August 1999 Special Rept 99-002:on 990730,NPV Radiation Monitoring Sys Was Declared Inoperable.Caused by Voltage Induced in Detector Output by Power Cable to Low Range Sample Pump. Separated Cables & Secured in Place to Prevent Recurrence ML20210U4721999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Hope Creek Generating Station,Unit 1.With ML20216D8331999-07-26026 July 1999 Safety Evaluation Concluding That Licensee IPEEE Complete Re Info Requested by Suppl 4 to GL 88-20 & That IPEEE Results Reasonable Given HCGS Design,Operation & History ML20216D8721999-07-26026 July 1999 Review of Submittal in Response to USNRC GL 88-20,Suppl 4: 'Ipeees,' Fire Submittal Screening Review Technical Evaluation Rept:Hope Creek Rev 1:980518 ML20210F3331999-07-22022 July 1999 Safety Evaluation Granting Relief Requests RR-B1,RR-C1,RR-D1 & RR-B3.Finds That Proposed Alternative for RR-B3 Provides Acceptable Level of Quality & Safety & Authorizes Alternative Pursuant to 10CFR50.55a(a)(3)(i) ML20210C4731999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Hope Creek Generating Station,Unit 1.With ML20216D8901999-06-30030 June 1999 IPEEEs Technical Evaluation Rept High Winds,Floods & Other External Events ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML18107A3441999-06-0101 June 1999 Interim Part 21 Rept Re Premature Over Voltage Protection Actuation in Circuit Specific Application in Dc Power Supply.Testing & Evaluation Activities Will Be Completed on 990716 ML20196A1511999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Hope Creek Generating Station,Unit 1.With ML20206Q4731999-05-14014 May 1999 SER Accepting Response to GL 97-05, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Plant ML20206U1571999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Hope Creek Generating Station,Unit 1.With ML20216D8451999-04-30030 April 1999 Rev 1, Submittal-Only Screening Review of Hope Creek Unit 1 IPEEE (Seismic Portion). Finalized April 1999 ML20206C8481999-04-22022 April 1999 SER Authorizing Pse&G Proposed Relief Requests Associated with Changes Made to Repair Plan for Core Spray Nozzle Weld N5B Pursuant to 10CFR50.55a(a)(3)(i) LR-N990157, Special Rept 99-001:on 990315, C EDG Valid Failure Occurred During Surveillance Testing.Testing Resulted in Unsuccessful Loading Attempt,Due to Failure EDG Output Breaker to Close.Faulty Card Replaced1999-04-12012 April 1999 Special Rept 99-001:on 990315, C EDG Valid Failure Occurred During Surveillance Testing.Testing Resulted in Unsuccessful Loading Attempt,Due to Failure EDG Output Breaker to Close.Faulty Card Replaced ML20205R5901999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Hope Creek Generating Station,Unit 1.With ML20205G6051999-03-19019 March 1999 SER Accepting Relief Request Re Acme Code Case N-567, Alternate Requirements for Class 1,2 & 3 Replacement Components,Section Xi,Div 1 ML20205F8911999-03-18018 March 1999 Safety Evaluation Authorizing Licensee Requests for Second 10-year Interval for Pumps & Valves IST Program ML20204F7951999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Hope Creek Generating Station,Unit 1.With ML18106B0931999-02-25025 February 1999 Part 21 Rept Re Possible Defect in Swagelok Pipe Fitting Tee,Part Number SS-6-T.Caused by Crack Due to Improper Location of Heated Bar.Only One Part Out of 7396 Pieces in Forging Lot Was Found to Be Cracked.Affected Util,Notified ML18106B0551999-02-0101 February 1999 Part 21 Rept Re Possible Matl Defect in Swagelok Pipe Fitting Tee,Part Number SS-6-T.Defect Is Crack in Center of Forging.Analysis of Part Is Continuing & Further Details Will Be Provided IAW Ncr Timetables.Drawing of Part,Encl ML18106B0441999-01-29029 January 1999 Part 21 Rept Re Possible Defect in Swagelok Pipe Fitting Tee Part Number SS-6-T.Caused by Crack in Center of Forging. Continuing Analysis of Part & Will Provide Details in Acoordance with NRC Timetables ML20202F6861999-01-26026 January 1999 Engine Sys,Inc Part 21 (10CFR21-0078) Rept Re Degradation of Synchrostat Model ESSB-4AT Speed Switches Resulting in Heat Related Damage to Power Supply Card Components.Caused by Incorrect Sized Resistor.Notification Sent to Customers ML18107A1871998-12-31031 December 1998 PSEG Annual Rept for 1998. ML20199E7271998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Hope Creek Generating Station,Unit 1.With ML18107A1881998-12-31031 December 1998 PECO 1998 Annual Rept. LR-N980580, Monthly Operating Rept for Nov 1998 for Hope Creek Generating Station,Unit 1.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Hope Creek Generating Station,Unit 1.With ML20198N4161998-11-12012 November 1998 MSIV Alternate Leakage Treatment Pathway Seismic Evaluation LR-N980544, Monthly Operating Rept for Oct 1998 for Hcgs,Unit 1. with1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Hcgs,Unit 1. with ML20155J9861998-10-31031 October 1998 Non-proprietary TR NEDO-32511, Safety Review for HCGS SRVs Tolerance Analyses LR-N980491, Monthly Operating Rept for Sept 1998 for Hope Creek Generating Station,Unit 1.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Hope Creek Generating Station,Unit 1.With ML17354B0971998-09-0909 September 1998 Part 21 Rept Re Possible Machining Defect in Certain One Inch Stainless Steel Swagelok Front Ferrules,Part Number SS-1613-1.Caused by Tubing Slipping Out of Fitting at Three Times Working Pressure of Tubing.Notified Affected Utils LR-N980439, Monthly Operating Rept for Aug 1998 for Hope Creek Generating Station Unit 1.With1998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Hope Creek Generating Station Unit 1.With LR-N980401, Monthly Operating Rept for July 1998 for Hope Creek Generating Station,Unit 11998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Hope Creek Generating Station,Unit 1 ML20236N6751998-07-0909 July 1998 Part 21 & Deficiency Rept Re Notification of Potential Safety Hazard from Breakage of Cast Iron Suction Heads in Apkd Type Pumps.Caused by Migration of Suction Head Journal Sleeve Along Lower End of Pump Shaft.Will Inspect Pumps LR-N980354, Monthly Operating Rept for June 1998 for Hope Creek Generating Station,Unit 11998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Hope Creek Generating Station,Unit 1 ML20236E9491998-06-30030 June 1998 Rev 0 to non-proprietary Rept 24A5392AB, Lattice Dependent MAPLHGR Rept for Hope Creek Generating Station Reload 7 Cycle 8 ML18106A6821998-06-24024 June 1998 Revised Charting Our Future. ML18106A6681998-06-17017 June 1998 Charting the Future. LR-N980302, Monthly Operating Rept for May 1998 for Hope Creek Generating Station,Unit 11998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Hope Creek Generating Station,Unit 1 ML20248C7381998-05-22022 May 1998 Rev 0 to Safety Evaluation 98-015, Extension of Allowed Out of Service Time for B Emergency Diesel Generator LR-N980247, Monthly Operating Rept for Apr 1998 for Hope Creek Station, Unit 11998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Hope Creek Station, Unit 1 LR-N980196, Monthly Operating Rept for Mar 1998 for Hope Creek Generating Station,Unit 11998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Hope Creek Generating Station,Unit 1 ML20217D5701998-03-20020 March 1998 Part 21 Rept 40 Re Governor Valve Stems Made of Inconel 718 Matl Which Caused Loss of Governor Control.Control Problems Have Been Traced to Valve Stems Mfg by Bw/Ip.Id of Carbon Spacer Should Be Increased to at Least .5005/.5010 ML18106A5851998-03-0303 March 1998 Emergency Response Graded Exercise,S98-03. Nuclear Business Unit Salem,Hope Creek Emergency Preparedness, 980303 1999-09-08
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s Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 ,
' Hope Creek Generating Station L.
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July-5, 1990 i
[L U. S. Nuclear Regulatory Commission ,
Document Control Desk '
Washington, DC 20555 1
.i
Dear Sir:
HOPE CREEK GENERATING STATION DOCKET NO. 50-354 ,
UNIT NO. 1 j LICENSEE EVENT REPORT 90-008-00 -
- s Thic Licensee Event Report b,being submitted pursuant to- !,
. the requirements of 10CFR50.73(a) (2) (1) . $
1 Sincerely, k _- ~ '
t J.J. gan '
General Manager.- l Hope Creek Operations RBC/= ;
Attachment '
.SORC Mtg.90-062 l
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On 6/4/90 at 1108, a Radiation Protection Supervisor reported to the Nuclear Shift Supervisor (NSS, SRO licensed) that, during review of the Radiation Monitoring System (RMS) data base, the reactor building exhaust (RBE) radiation monitor trip setpoint had been found set non-conservatively high (2X10- 8 uci /cc) . Technical Specification Table 3.3.3-2 requires that the trip setpoint for the subject monitor be set less than or equal to 1X10- 8 uci/cc. Upon discovery, the setpoint was immediately reset to within Technical Specification required parameters.
Followup investigation determined that the trip setpoint had been
' incorrectly entered into the RMS computer during the performance of an I&C department functional test procedure which functionally checks the RBE rad monitor and refuel floor exhaust (RFE) radiation monitor. This occurred on S/29/90. Tho I&C technician who performed the procedure incorrectly ;
input the setpoint value for the RFE radiation monitor ( 2X10- 8 uci/cc) when }
inputting the RBE radiation monitor trip setpoint. This occurred due to !
improper recording of "as found" setpoint data when performing the l- procedure and inadequate verification of the data when the procedure was completed. The independent verifier (also an I&C technician) did not ,
catch the error when the "as found" data was recorded or during the 1 data verification process after inputting the setpoint. As such, the error went undetected. Corrective actions included disciplinary action for the technicians involved, reviewing appropriate I&C procedures for possible inclusion of static RMS data within the body of the procedure, and including a review of this incident in thu I&C department continuing training program.
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- ** RLY YlAR NLMD lEVE mlTX GDDATDKi CTATIm 05000354 i 90 -
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l PLANT AND SYSTEM IDENTIFICATION !
General Electric - Boiling Water Reactor (BWR/4)
Radiation Monitoring System (EIIS Designation: IL)
Reactor Building Ventilation System (EIIS Designation: VA)
)
1DENTIFICATION OF OCCURRENCE Technical Specification violation - Reactor Building Exhaust Radiation Monitor Set In Excess of Allowable Limits - Personnel Error Event-Date: 5/29/90 i Discovery Dates 6/4/90 Discovery Time: 1108 l This LER was initiated by Incident Report No.90-058 CONDITIONS PRIOR-TO OCCURRENCE i
Plant'in OPERATIONAL CONDITION 1 (Power Operation), Reactor Power 100%, Unit Load 1100MWo.
DESCRIPTION OF OCCURRENCE On 6/4/90 at 1108, a Radiation Protection Supervisor informed the Nuclear shift Supervisor (NSS, SRO licensed) that the trip setpoint for the reactor building exhaust (RBE) radiation '
l monitor had been discovered set in excess of Technical Specification allowable values. The setpoint was discovered set-at 2X10 e uCi/cc rather than .1X10- 8 uC1/cc as required by Technical Specification Table 3.3.2-2. The setpoint_ was immediately restored to the required value, and the NSS initiated an investigation to determine how and when the l setpoint had been incorrectly established in the Radiation l Monitoring System (RMS) computer.
APPARENT CAUSE OF OCCURRENCE
.. The primary cause of this occurrence was a non-cognitive i
personnel error on the part of two I&C technicians. The technicians incorrectly established the RBE radiation monitor .
trip setpoint in a non-conservative direction during the course '
of performing and verifying an I&C functional test procedure.
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z IJCunE ININr iO0Rr ulR) TEKT GWrIWATlaN FACILrIY NME (1) DET kMER (2) IIR NLMIER (6) PME (3)
YFAR \\ NUMER \\ RLY 10PI: CR11X GMRATDC mATIm 050003M 90 -
0 0 8 -
0 0 0 3 G' O 4 ANALYSIS OF OCCURRENCE On 5/29/90, two I&C technicians wore assigned to perform a-monthly functional test procedure on the Channel "A" RFE and RBE radiation monitoring system. The first portion of the procedure requires the technicians to test the RFE radiation monitoring circuitry. As an initial step to the test, the technician is required to record the 3 38 found" setpoints of the RFE in the procedure data table. The escond portion-of the procedure. requires the same steps for the RBE radiation monitor. When recording the RBE radiation monitor trip setpoint, the technician actually recorded the as-found trip setpoint for RFE. The independent verifier (second technician) did not recognize the error, as such, the error was carried through to the completion of the test.
At the completion of the test, the technicians were regiired to verify that the "as-left" trip netpoints agreed with the static data from a controlled hardcopy of the RMS database. Again, the error was not detected, and was carried through to test i completion. . The subject radiation monitors were returned to service and declared operable following test completion.
The RBE radiation monitor remained set unconservatively high until discovered during a scheduled RMS database review by a Radiation Protection Supervisor. ,
PREVIOUS OCCURRENCES One previous instance of entering incorrect trip setpoints into I the.RMS system has occurred at ilope Creek (reft LER 87-022).
That' incident resulted from a personnel error on the part of a Radiation Protection Technician in entering an incorrect trip
[" setpoint for the cooling tower blowdown radiation monitor. It-should be noted that the incident described in this report was discovered due to corrective actions implemonted in response to LER 87-022 (thrice weekly RMS database verification).
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HAR \\ NUPUR \\ RLY lut OsX GMRATDC 17tAnm 050003M j !- 90 -
0 0 8 -
0 0 0 4 3' 0 4 i
SAFETY SIGNIF_ICANCE This occurrence had minimal safety significance. During the period'of time that Channel "A" RBE radiation monitor was set unconservatively high, Channel "B" RBE radiation monitor was set appropriately and would have provided reactor building ventilation capability, if necessary.
CORRECTIVE ACTIONS
- 1. The technicians involved in this incident received disciplinary action with regard to the lack of attention to detail exhibited in this occurrence.
- 2. This report will be - reviewed with all I&C Department personnel an part of the station Operational Experience Feedback program and I&C department continuing training.
Training will stress the importance and need for thorough independent verification. Additionally, this report will be forwarded to the Chemistry / Radiation Protection. Manager and Operations Department Manager for inclusion in departmental training, as necessary.
- 3. The subject I&C procedure will be reviewed by I&C department with the intent of including permanent, static RMS setpoint data into this and similar I&C department RMS test procedures.
Since oly,
/
.J. agan General Manager -
Hope Creek Operations RBC/
SORC Mtg.90-061
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05000354/LER-1990-008 | LER 90-008-00:on 900604,reactor Bldg Exhaust Radiation Monitor Trip Setpoint Found Nonconservatively High.Caused by Personnel Error.Technicians Disciplined,Rept Reviewed W/All Personnel & Setpoint Included in procedure.W/900705 Ltr | | 05000354/LER-1990-009 | LER 90-009-00:on 900607,HPCI Sys Oil Samples Indicated High Water Content & Traces of Sediment Contamination.Caused by Design Deficiency in HPCI Turbine Lube Oil Reservoir. Reservoir Cleaned,Flushed & Wiped down.W/900705 Ltr | |
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