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| {{Adams
| | #REDIRECT [[05000213/LER-1999-001]] |
| | number = ML20205F995
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| | issue date = 03/31/1999
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| | title = :on 990105,discovered That Main Stack RM R-14A Pressure Compensating Signal Had Not Been Calibr.Caused by Personnel Error.Revised Calibr Procedures to Include Calibr of Pressure Transmitter.With
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| | author name = Bouchard G, Flynn S
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| | author affiliation = CONNECTICUT YANKEE ATOMIC POWER CO.
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| | addressee name =
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| | addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
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| | docket = 05000213
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| | license number =
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| | contact person =
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| | document report number = CY-99-049, CY-99-49, LER-99-001, LER-99-1, NUDOCS 9904070079
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| | title reference date = 03-31-1999
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| | document type = LICENSEE EVENT REPORT (SEE ALSO AO RO), TEXT-SAFETY REPORT
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| | page count = 5
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| }}
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| {{LER
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| | Title = :on 990105,discovered That Main Stack RM R-14A Pressure Compensating Signal Had Not Been Calibr.Caused by Personnel Error.Revised Calibr Procedures to Include Calibr of Pressure Transmitter.With
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| | Plant =
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| | Reporting criterion = 10 CFR 50.73(a)(2)(i), 10 CFR 50.73(a)(2)(viii), 10 CFR 50.73(a)(2)(ii), 10 CFR 50.73(a)(2)(x), 10 CFR 50.73(a)(2)(iii), 10 CFR 50.73(a)(2), 10 CFR 50.73(a)(2)(v), 10 CFR 50.73(a)(2)(i)(B)
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| | Power level =
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| | Mode =
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| | Docket = 05000213
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| | LER year = 1999
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| | LER number = 1
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| | LER revision = 0
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| | Event date =
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| | Report date =
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| | ENS =
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| | abstract =
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| }}
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| =text=
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| {{#Wiki_filter:F 1
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| l CONNECTICUT YA N K EE AT O M IC POWER COMPANY HADDAM NECK PLANT 362 iNJUN HOLLOW ROAD e EAST HAMPTON, CT 06424-3099 March 31, 1999 CY-99-049
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| )
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| U.
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| S.
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| Nuclear Regulatory Commission Document Control Desk Washington, D.
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| C.
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| 20555
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| ==Reference:==
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| Facility Operating License Nc DPR-61 Docket No. 50-213 Reportable Occurrence LER 50-213/1999-001-01 l
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| 4 This letter forwards Supplemental Licensee Event Report 1999-001-01, required to be submitted, pursuant to the requirements of 10CFR50.73.
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| Very truly yours, j
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| .H.
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| B uchard
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| / Unit Director l
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| i GHB/ reb
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| ==Attachment:==
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| LER 50-213/1999-001-01 cc: | |
| Mr.
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| H.
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| J.
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| Miller Regional Administrator, Region I
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| < S#
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| N 475 Allendale Road King of Prussia, PA 19406 Dr.
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| R.R.
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| Bellamy
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| ] | |
| Chief, Decommissioning and Laboratcry Branch, Region I 475 Allendale Road King of Prussia, PA 19406 ojg011 iors-s nev e-ot 9904070079 990331 PDR ADOCK 05000213 S
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| PDR
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| p l
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| NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO.3160-0104 (4-95)
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| EXPtRES 04/30/9s IN OR ATION COLLE Y,0 R O ES 60 MRS EPO T D L S NS n'"??o'LMP."! ";!%30 'Es.n!NT4"Vo"fa'o ^=n "5
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| LICENSEE EVENT REPORT (LER) 1%'"UT '"glfnan"Ana' gags",^o",M"!,"!,,g^g"6'c
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| !?!'c'EMt,0 oE"r'la"n"r". Ofn72"J"?dlal'"' ''
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| (See reverse fOr required nurnber of l
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| digits / characters for each block)
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| FJ.CluTY NAME (1)
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| DOCKET NUMBER (2)
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| PAGE (3)
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| Haddam Neck 05000213 1 of 4 TIrLE 14)
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| Main Stack Radiation Monitor R-14A Pressure Compensating Signal Not Calibrated EVENT DATE (5)
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| LER NUMBER (6)
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| REPORT DATE (7)
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| OTHER FACILITIES INVOLVED (8)
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| MONTH DAY YEAR YEAR SEQUENTIAL REVISION MONTH DAY YEAR FACluTY NAME DOCKET NUMBER NUMBER 05000
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| ''' " "^"'
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| C"" """8'"
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| 01 05 1999 1999 001 01 03 31 1999 05000 OPERATING N
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| THIS REPORT IS SUBMITTED PU*SUANT TO THE REQUIREMENTS OF 10 CFR 5: (Check one or more) (11)
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| MODE (M 20.2201(b) 20.2203(a)''
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| <)
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| )( 50.73(a)(2)(i) 50.73(a)(2)(viii)
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| POWER 20.2203(a)(1) 20.2203(a)(3,;)
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| X' 50.73(a)(2)(ii) 50.73(a)(2)(x)
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| LEVEL (10) 000 20.2203(aH2Hi>
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| 20.2203(aH3Hii) 50.73(a)(2)(iii) 73.71 20.2203(aH2)(ii) 20.2203(aH4) 50.73(a)(2)0v)
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| OTHER U-
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| ~
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| 20.2203(a)(2)(iii) 50.36(cH1) 50.73(a)(2)(v)
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| Specify m Abstract below t()g;n n
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| ^e % eq f 20.2203(aH2)0v) 50.36(c)(2) 50.73(aH2)(vii) or in NRC Form 366A
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| ' 9 ::
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| - < < ~
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| LICENSEE CONTACT FOR THIS LER (12)
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| NAME TELEPHONE NUMBER linclude Area Codel Steven Flynn, Engineering (860)267-2556 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)
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| ==CAUSE==
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| SYSTEM COMPONENT M ANUF ACTURE R REPORTABLE q
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| ==CAUSE==
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| SYSTEM COMPONENT MANUFACTURER REPORTABLE TO NPRDS TO NPRDS SUPPLEMENTAL REPORT EXPECTED (14)
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| EXPECTED MONTH DAY YEAR SUBMISSION y
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| YES NO (If yes, complete EXPECTED SUBMISSION DATE).
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| ABSTRACT (Limit to 1400 spaces, i.e.,
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| approximately 15 single-spaced typewritten lines)
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| (16) 1 On January 5,
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| 1999, with the plant permanently defueled, while reviewing radiation i
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| monitoring system (RMS) design issues, it was determined that main stack radiation monitor R-14A utilizes a pressure compensating signal and that calibration of the pressure transmitter had not been included in the instrument calibration surveillance procedure from the time the monitor was installed in August 1996. The apparent cause is that perso.mel preparing the R-14A calibration and functional test procedure (s) did not identify the need for the pressure transmitter calibration. This event is believed to have low safety significance since the error introduced by the uncalibrated pressure transmitter is offset by conservative instrument setpoints.
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| Corrective action consisted of revising the calibration procedure to include calibration of the l
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| pressure transmitter and ensuring the pressure transmitter signal is bypassed during calibration of tne radiation detector. The pressure transmitter was calibrated on January 27, 1999.
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| The as-found data was within the min / max pressure range specified l
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| within the calibration procedure. This supplemental LER provides the results of the 1
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| calibration.
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| 1 i
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| i j
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| p i.
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| .U.S. NUCLEAR REGULATORY COMMISSIGN (4-96)
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| LICENSEE EVENT REPORT (LER)
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| TEXT CONTINUATION FACluTY NAME (1)
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| DOCKET NUMBER (2)
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| LER NUMBER (6)
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| PAGE (3)
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| YEAR SEQUENTIAL REVISION Haddam Neck NUMBER NUMBER 05000213 1999 001 01 2 of 4 TEXT (11more space is required, use additional copies of NRC Form 366A) (17)
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| ==BACKGROUND INFORMATION==
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| R-14A (EIIS Code:IL), monitors the noble gas effluents being discharged through the primary vent stack, which includes discharges from the Spent Fuel Building. This monitor is required to be operable in accordance with plant Technical Specification 3.3.3.8 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION.
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| Periodic calibration I
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| and functional testing is required to demonstrate operability.
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| Plant modification, PDCR 1550, replaced this monitor with a newer model in 1996. The purpose of PDCR 1550.was to replace radiation monitors that were obsolete or difficult to maintain. R-14A monitors gaseous effluent releases through the primary vent stack and provides indication and alarms for the plant operators. Neither the plant modification nor the purchase specification noted the requirement for a pressure compensation of the radiation signal.
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| During the development of the Licensing Basis / Design Basis Document for the defuelsd plant condition, a number of radiation monitoring system (RMS) design basis issues were idsntified.
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| This led to a continuing effort to clearly identify all RMS design bases.
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| This continuing effort has uncovered several. deficiencies identified in previous LERs (identified in " Previous Similar Events") and was instrumental in identifying this j
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| problem.
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| ==EVENT DESCRIPTION==
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| On January 5,
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| 1999, with the plant permanently defueled, while reviewing radiation monitoring system design issues, it was determined that main stack radiation monitor R-
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| .14A utilizes a pressure compensating signal and that calibration of the pressure transmitter was not included in the instrument calibration surveillance procedure from the time the monitor was installed in August 1996. The output signal of R-14A is a i
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| " compensated" signal based on the effects of the absolute pressure as measured at the detector. chamber.
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| If the pressure transmitter was outside its calibration specifications, an erroneous radiation signal could result.
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| By assuming that the pressure transmitter output may have drifted, it was assumed the indicated radiation signal could be below the actual radiation level.
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| It was. subsequently discovered that vendor factory testing included bypassing the pressure transmitter while calibrating the radiation detector.
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| Station surveillance procedures did not include bypassing the pressure transmitter during calibration of the radiation detector. This could introftce additional error in the final instrument calibration state.
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| It was concluded from the above that complete calibration of the radiation monitor had not been accomplished within the surveillance requirement interval.
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| R-14A was declared inoperable and grab sampling was initiated in accordance with the Technical Specification action statement.
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| ll L._.U.S. NUCLEAR REGULATORY COMMISSION W95)
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| LICENSEE EVENT REPORT (LER)
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| TEXT CONTINUATION iLCILITY NAME (1)
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| DOCKET NUMBER (2)
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| LER NUMBER (6)
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| PAGE 13)
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| YEAR SEQUENTIAL REVISION Haddam Neck NUMBER NUMBER 05000213 1999 001 01 3 of 4 TEXT (If more space is required, use additional copies of NRC Form 366A) i17)
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| ==CAUSE OF EVENT==
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| The apparent cause is that personnel preparing the R-14A calibration and functional test procedure (s). did not identify the need for the pressure transmitter calibration during the review of vendor-supplied technical manuals.
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| A contributing cause is that the engineer (s) responsible for the initial installation and acceptance testing did not assist in the preparation of the surveillance procedures.
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| A second contributing cause is that the vendor technical manuals do not clearly specify the existence of the pressure compensating signal, nor the need to calibrate the associated pressure transmitter.
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| ==SAFETY ASSESSMENT==
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| This event is reportable under 10CFR50.73 (a) (2) (i) (B) as a condition prohibited by the plant's Technical Specifications and as a condition beyond the design basis which is reportable under 10CFRSO.73 (a) (2) (ii) (B).
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| The event is believed to have Jow safety significance based on the following factors:
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| :- The monitor was placed in service after the plant shut down (last operated on July 22, 1996).
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| :- The lowest setpoint is based on State notification which is 1/400th of the Technical Specification limit.
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| JRRECTIVE ACTION The~ surveillance procedure was revised to include calibration of the pressure transmitter and to ensure the pressure transmitter signal is bypassed during calibration of the radiation detector.
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| Ths pressure transmitter was calibrated on January 27, 1999.
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| The as-found data was within the min / max pressure range specified within the calibration procedure.
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| No adjustments to the pressure transmitter were necessary to ensure the channel was within the. desired accuracy and intended range of operat3cn.
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| The reading obtained from R-14A was not affected by the fact that the pressure transmitter had not been calibrated since installation.
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| Therefore, the calculations associated with previous gaseous radioactive effluents are. unaffected by the lack of calibration of the pressure transmitter and no further evaluation of previous (1996 to 1999) gaseous releases is warranted.
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| 9_
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| .yU.S. NUCLEAR REGULATORY COMMISSION (4-93)
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| LICENSEE EVENT REPORT (LER)
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| TEXT CONTINUATION FACILITY NAME (1),
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| DOCKET NUMBER (2)
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| LER NUMBER (6)
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| PAGE (3)
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| YEAR SEQUENTIAL REVISION
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| ~
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| Haddam' Neck NUMBER NUMBER 05000213 1999 001 01 4 of 4 TEXT (11more space is required, use additional copies of NRC form 366A) (17l
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| ==ADDITIONAL INFORMATION==
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| This supplemental LER provides the results of the calibration.
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| PREVIOUS SIMILAR EVENTS-LER 97-009-00, Design Deficiency Found in Stack Radiation Monitor Isokinetic Nozzle RMS-14A LER 98-004-00, Design Deficiency Found in Stack Radiation Monitor RMS-14B Isokinetic Sampling
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| .LER 98-006-00, Design Deficiency Found in Stack Radiation Monitor RMS-14B Sampling Lines LER 98-008-00, Main' Stack Radiation Monitor RMS-14B Samples Not Analyzed to Required Detection LevelsL...
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| }}
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| {{LER-Nav}}
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