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Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEAR05000333/LER-1993-0171993-08-30030 August 1993 LER 93-017-00:on 930729,declared APRM Downscale,Companion IRM Upscale Inoperable Due to Misinterpretation of Sr. Initiated Plant Shutdown & Declared Unusual Event Until Trip Was corrected.W/930830 Ltr 05000333/LER-1993-0161993-08-23023 August 1993 LER 93-016-00:on 930722,missed Source Check of Radwaste Discharge Monitor Prior to Discharge of Waste Sample Tank a Due to Failure to Follow Procedures.Performed Source Check & Counseled Involved indiviuals.W/930823 Ltr 05000333/LER-1991-0321993-05-0101 May 1993 LER 91-032-01:on 911226,determined That During Postulated CR Fire,Existing Design of Circulating Water Sys Intake Structure Deicing Heaters Outside Design Basis.Caused by Omission of Heaters in Analyses.Fsar revised.W/930501 Ltr 05000333/LER-1983-060, Updated LER 83-060/03X-1:on 831130,incorrect Motor Actuator Installed on RHR Suppression Pool Outboard Isolation Valve During Maint Activities.Cause Not Stated.Replacement Actuator Installed on 840119.W/840203 Ltr1984-02-0303 February 1984 Updated LER 83-060/03X-1:on 831130,incorrect Motor Actuator Installed on RHR Suppression Pool Outboard Isolation Valve During Maint Activities.Cause Not Stated.Replacement Actuator Installed on 840119.W/840203 Ltr ML20071G2541978-12-20020 December 1978 /03L-0 on 781122:during Shutdown & Surveillance Test,A Number of Battery Cells Were Found W/Specific Gravity &/Or Individual Cell Voltage Variations(High or Low) Greater than Allowed by Test Acceptance Criteria ML20071G1391978-12-18018 December 1978 /04X-1 on 781006:3rd Quarter Release of Halogens & Particulates Greater than Tech Specs.Caused by Steam Leaks & Fuel Pin Clad Performance ML20071F9161978-11-28028 November 1978 /03L-0 on 781101:during Refueling & Maint Shutdown It Was Found That Surveillance Test Had Not Been Performed for Combustion Ionization Products Smoke Detectors Installed in Diesel Fire Pump Room on 780310,due to Oversight ML20071F8651978-11-17017 November 1978 /04L-0 on 781024:excess Solute Release from Makeup Water Treatment Waste Neutralizer Tanks to Circulating Water Discharge Tunnel Detected.Caused by Unsound Sampling & Method of Determining Concentrations & Dissolved Solids ML20148F2461978-11-0101 November 1978 /04T-0 on 781018:Environ Radiological Monitoring Sample of Periphyton Samples Pci/Gm(Wet)Does Not Meet Subj Facil Tech Spec Append B,Paragraph 5.6.2.6 ML20071F4241978-10-0303 October 1978 /04L-0 on 780914:An Apparent Excessive Solute Release from Makeup Water Treatment Waste Neutralizer Tanks to Circulating Water Discharge Tunnel Was Detected While Performing Aug 78 24-hour Complete Sample Analysis 1993-08-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARJAFP-99-0277, Monthly Operating Rept for Sept 1999 Fpr Ja FitzPatrick Nuclear Power Plant.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 Fpr Ja FitzPatrick Nuclear Power Plant.With ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data JAFP-99-0261, Monthly Operating Rept for Aug 1999 for Jafnpp.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Jafnpp.With JAFP-99-0236, Monthly Operating Rept for July 1999 for Ja FitzPatrick Npp. with1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Ja FitzPatrick Npp. with ML20216D9541999-07-28028 July 1999 Safety Evaluation Authorizing Proposed Alternatives for Second 10-year Interval Pursuant to 10CFR50.55a(a)(3)(ii) ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept JAFP-99-0211, Monthly Operating Rept for June 1999 for Ja FitzPatrick Nuclear Power Plant.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Ja FitzPatrick Nuclear Power Plant.With JAFP-99-0175, Annual Summary of Changes,Tests & Experiments for 1997/1998. with1999-06-0202 June 1999 Annual Summary of Changes,Tests & Experiments for 1997/1998. with JAFP-99-0181, Monthly Operating Rept for May 1999 for Jafnpp.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Jafnpp.With JAFP-99-0166, Monthly Operating Rept for Apr 1999 for Ja FitzPatrick Nuclear Plant.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Ja FitzPatrick Nuclear Plant.With JAFP-99-0142, Monthly Operating Rept for Mar 1999 for Ja FitzPatrick Nuclear Power Plant.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Ja FitzPatrick Nuclear Power Plant.With JAFP-99-0092, Monthly Operating Rept for Feb 1999 for Ja FitzPatrick Nuclear Power Plant.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Ja FitzPatrick Nuclear Power Plant.With ML20207E9311999-02-26026 February 1999 Part 21 Rept Re Sprague Model TE1302 Aluminum Electrolytic Capacitors with Date Code of 9322H.Caused by Aluminum Electrolytic Capacitors.Affected Capacitors Replaced ML20202J0891999-02-0303 February 1999 Safety Evaluation Accepting Rev 2 of Third Interval Inservice Testing Program for Pumps & Valves for James a FitzPatrick Nuclear Power Plant ML20199M0891999-01-22022 January 1999 Part 21 Rept Re Failure of Square Root Converters.Caused by Failed Aluminum Electrolytic Capacitory Spargue Electric Co (Model Number TE1302 with Mfg Date Code 9322H).Sent Square Root Converters Back to Mfg,Barker Microfarads,Inc JAFP-99-0011, Monthly Operating Rept for Dec 1998 for Ja FitzPatrick Nuclear Power Plant.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Ja FitzPatrick Nuclear Power Plant.With ML20198F9991998-12-0404 December 1998 Assessment of Licensing Basis for Use of Containment Overpressure Credit for Net Positive Suction Head Analyses Power Authority of State of New York,James a Fitzpatrick Nuclear Power Plant ML20196J3501998-12-0404 December 1998 SER Accepting License Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves JAFP-98-0396, Monthly Operating Rept for Nov 1998 for Ja FitzPatrick Npp. with1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Ja FitzPatrick Npp. with ML20196F9251998-11-25025 November 1998 Safety Evaluation Re Thrid 10-year Interval Inservice Insp Program Relief Requests for Plant ML20195J7521998-11-18018 November 1998 Rev 7 to Jaf Colr ML20195K4211998-11-17017 November 1998 Safety Evaluation Authorizing Proposed Alternative in Relief Request VRR-05 Per 10CFR50.55a(a)(3)(i) & PRR-01,PRR-02R1, PRR-03,PRR-04,VRR-02,VRR-03 & VRR-04 Per 10CFR50.55a(a)(3)(ii) ML20195E1051998-11-13013 November 1998 Safety Evaluation Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves, Issued 950817 ML20197G6221998-11-0606 November 1998 Non-proprietary Rev 7 to HI-971661, Licensing Rept for Reracking of Ja FitzPatrick Sfp ML20155H5321998-11-0303 November 1998 Safety Evaluation Authorizing Alternative to ASME Code Requirements for CRD Bolting ML20155H5801998-11-0303 November 1998 Safety Evaluation Authorizing Postponement of Beginning of Augmented Exam Requirements of 10CFR50.55a(g)(6)(ii)(A)(2) Re ASME Code,Section XI JAFP-98-0360, Monthly Operating Rept for Oct 1998 for Ja FitzPatrick Nuclear Power Plant.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Ja FitzPatrick Nuclear Power Plant.With ML20155C2821998-10-30030 October 1998 Non-proprietary Rev 0 to GENE-187-30-1598 Np, CRD Bolting Flaw Evaluation for Ja FitzPatrick Nuclear Power Plant ML20154L6591998-10-14014 October 1998 Safety Evaluation Accepting Licensee Proposed Alternative to Snubber Visual Inservice Exam Intervals & Sampling Rates Requirements Contained in ASME Code,Section Xi,Subsection Iwf,Article IWF-5000 JAFP-98-0322, Monthly Operating Rept for Sept 1998 for Ja Fitzpatrick Nuclear Power Plant.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Ja Fitzpatrick Nuclear Power Plant.With ML20153D2591998-09-21021 September 1998 SER Accepting Proposed Alternative Testing of Containment Following ECCS Suction Strainer Replacement ML20153B5611998-09-0101 September 1998 Rev 1 to JAF-SE-98-013, RHR & Core Spray Suppression Pool Suction Strainer Replacement ML20151X6891998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Ja FitzPatrick Nuclear Power Plant ML20237E8361998-08-25025 August 1998 Rev 6 to Colr ML20237E9471998-08-0808 August 1998 Rev 6 to Colr JAFP-98-0264, Monthly Operating Rept for July 1998 for Ja FitzPatrick Nuclear Plant1998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Ja FitzPatrick Nuclear Plant ML20236X5881998-07-29029 July 1998 Safety Evaluation Supporting Amend 245 to License DPR-59 ML20236V8181998-07-29029 July 1998 Safety Evaluation Accepting Request for Relief from Implementation of Requirements of 10CFR50.55a Related to Containment Repair & Replacement Activities for James a FitzPatrick Nuclear Power Plant ML20153B5781998-07-28028 July 1998 Rev 0 to JAF-SE-98-025, HPCI & RCIC Suppression Pool Suction Strainer Replacement ML20236X3831998-07-14014 July 1998 Rev 2 to JAF-RPT-MULTI-02671, Summary of Detailed Evaluation for NRC Generic Ltr 96-06 ML20154L9201998-07-10010 July 1998 SER Accepting Rev to Reactor Vessel Surveillance Capsule Withdrawal Schedule for James a Fitzpatrick Nuclear Power Plant JAFP-98-0222, Monthly Operating Rept for June 1998 for Ja FitzPatrick Nuclear Power Plant1998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Ja FitzPatrick Nuclear Power Plant JAFP-98-0193, Monthly Operating Rept for May 1998 for Ja FitzPatrick Nuclear Plant1998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Ja FitzPatrick Nuclear Plant ML20248F3531998-05-21021 May 1998 Part 21 Rept Re Electronic Equipment Repaired or Reworked by Integrated Resources,Inc from Approx 930101-980501.Caused by 1 Capacitor in Each Unit Being Installed W/Reverse Polarity. Policy of Second Checking All Capacitors Is Being Adopted JAFP-98-0168, Monthly Operating Rept for Apr 1998 for Ja FitzPatrick Nuclear Power Plant1998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Ja FitzPatrick Nuclear Power Plant JAFP-98-0128, Monthly Operating Rept for Mar 1998 for Ja FitzPatrick Nuclear Power Plant1998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Ja FitzPatrick Nuclear Power Plant ML20217A4631998-03-23023 March 1998 Safety Evaluation Accepting Use of Three Heats/Lots of Hot Rolled XM-19 Matl in Core Shroud Repair Assemblies Re Licenses DPR-16 & DPR-59,respectively JAFP-98-0091, Monthly Operating Rept for Feb 1998 for JAFNPP1998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for JAFNPP ML20202G9081998-02-0606 February 1998 Safety Evaluation Re Amend to License DPR-59 to Revise TS Tables 3.2-2 & 4.2-2 JAFP-98-0058, Monthly Operating Rept for Jan 1998 for Ja FitzPatrick Nuclear Power Plant1998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Ja FitzPatrick Nuclear Power Plant 1999-09-30
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Janos A.FihR3 rick i Nuclear Power Plant P.O Box 41
. Lycoming New York 130M 1 315 M2-3MD l
p A NewYorkPower so,ry P. Saimon, ar.
t
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W Authority nesideat uaoaaer August 23, 1993 JAFP-93-0457 l
I United States Nuclear Regulatory Commission ,
Document Control Desk Mail Station P1-137 Washington, D.C. 20555 l
SUBJECT:
DOCKET NO. 50-333 4 LICENSEE EVENT REPORT: 93-01f. Liquid Radioactive !
Waste Discharge Without Testing the ,
Radwaste Discharge ,
t Monitor
Dear Sir:
l This report is submitted in accordance with 10CFR50.73 ,
I (a) (2) (i) (B) . Questions concerning this report may be addressed '
to Mr. Eric Mulcahey at (315) 349-6458.
t Very truly yours, i
RRY P.' SALMON, JR /
MGLf" HPS:EM: tid l Enclosure l cc: USNRC, Region 1 [
USNRC Resident Inspector !
INPO Records Center 1
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i i
I f?
I f . ,;
i 1 S- il kokB310040930823 ADDCK 05000333 3 PDR i(d s ,
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WRC FOAM 366 - U.S. 88UCLEAR REGULATORY C0feelSS10N APPRWED BY CNB E0. 3150-0104
- (542) E'XPIRES 5/31/95
, LICENSEE EVENT REPORT (LER) ESTIMATED BURDEN PER RESPONSE 10 COMPLY WITH THl$ INf0RMATION COLLECTION REQUEST: 50.0 HRS.
(See reverse f or reovired ruter of digits / characters for each block) FORWARD COMMENTS REGARDING BURDEN ESilMATE 10 l THE INFORMATION AND RECORDS MAkAGEMENT BRANCH a
(MNBB 7714), U.S. NUCLEAR REGULATORY COMMIS$10N, WASHINGTON, DC 20555 0001, AND TO THE PAPERWORK i REDUCT!DN PROJECT (3150 0104), OFFICE OF q MANAGEMENT AND BUDGET, WASHINGTON, DC 20503. i FACILITY KAME (1) DOCKET IAMBER (2) PAGE (3) .
1 James A. FitzPatrick Nuclear Power Plant 05000333 01 OF 04 TITLE (4)
Liquid Radioactive Waste Discharge Without Testing the Radwaste Discharge IVINT DATE (5) ifR trMBER (6) REPORY DATE (T) OTHER FACit1 TIES INVotVtV (8)
MONTH DAY YEAR YEAR MONTH DAY YEAR 1 NuMatR NumsER 05000 FACILITY NAME DOCKET NUMBER l
07 22 93 93 016 00 08 23 93 05000 .
OPERATlWG N THn nr RT n m m muanT Tur m u m N n or 10 CrR u m ck om or w e) m BK1DE (9) 20.402(b) 20.405(c) 50.73(a)(2)(iv) 73.71(b)
POWER 20.405(a)(1)(i) 50.36(c)(1) 50. 73(a)(2)(v) 73.71(c) 100 LEVE L (10) 20.405(a)(1)(ii) 50.36(c)(2) 50.73(a)(2)(vii) OTHER 20.405(a)(1)(iii) X 50.73(a)(2)(i) 50.73(a)(2)(viii)(A>
20.405(a)(1)(iv) 50.73(a)(2)(ii) 50.73(a)(2)(viii)(B) 20.405(a)(1)(v) 50.73(a)(2)(i t i) 50.73(a)(2)(x) I t ICE NSE E CON T ACT IOR T HIS L E R (12) d NAME TELEPHONE NUMSER (include Area Code)
Mr. Eric Mulcahey, Senior Licensing Engineer (315) 349-6458 i
j COMPLFTE ONE LINE FOR E ACH COMMWINT F AlltRE DESCRIBED IN THIS REPORT (13) k CAUSE SYSTEM COMP 0hENT MANUFACTURER CAUSS SYSTEM COMPONENT MANUFACTURER p g f 1
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SLPPtfMINYAL RFPORT EXPECTED (14) , , _ _ _ - EXPECTED MONTH DAY YEAR ;
TES X susMISSION i (If yes, conplete EXPECTED SUBMISSION DATE). No DATE (15) !
ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten Lines) (16)
]
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EIIS Codes are in []
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On July 22, 1993, with the plant operating at 100% power, a source check was not performed of the Radwaste Discharge Monitor prior to discharge of Waste Sample Tank A [WD] to Lake Ontario. The failure to perform the source check was discovered after che tank had been discharged (later that
- day). A source check was performed satisfactorily immediately upon discovery. The Radwaste Discharge Monitor alarm and trip settings were completed prior to discharge and operability verification after-the-fact i proved that this was not an unmonitored release. Subsequent discharges to
- Lake Ontario were immediately suspended pending resolution and initiation of corrective actions to prevent recurrence.
t 1
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t NRC 70RM 366 (542)
NRC FDEM 366A U.S. EUCLEAR REGULATOY CDe(IS$10 APPROVED B7 deb NO. 3150-0104 (5-92, EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS.
FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO LICENSEE EVENT REPORT (LER) THE INFORMAil0N AND RECORDS MANAGEMENT BRANCH TEXT CONTINUATION (MNas m 4), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555-0001, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT AND BUDGET WASHINGTON, DC 20503.
FACILITY NAME (1) DOCKET NUMBER (2) LER NtMBER (6? PAT (3)
James A. FitzPatrick Nuclear YEAR SEQUENTIAL REVISION Power Plant 05000333 02 OF 04 93 016 0 TEXT (if more space is reauired. use additional copies of NRC Form 366A) (17)
Event Description Contrary to the requirements of the Radiological Effluent Technical Specifications Table 3.10-2 note (c), on July 22, 1993 at 1314, with the plant operating at 100% power, a source check was not performed on the Radwaste Discharge Monitor [IL] prior to discharge of Waste Sample Tank A
[WD] to Lake Ontario.
On the morning of July 22, 1993, the Chemistry Technician provided the
, Shift Supervisor (SS) with a Liquid Radioactiva Waste Discharge Permit
'(discharge permit), Batch No.93-019 for Waste: Sample Tank A. Section A of the discharge permit containing the chemistry and radiochemistry parameters including the required dilution factors was complete. Section B of the discharge permit is required to be completed by the Shift Supervisor. The Shift Supervisor (SS) computed and set the Radwaste Discharge Monitor alarm and trip setpoints and authorized release of the tank by signing the discharge permit. The SS then notified a radwaste operator to pick up the discharge permit and the key to the discharge flow control valve. The discharge permit and the key were picked up at about 1245 and discharge of the Waste Sample Tank A started at 1314 on July 22, 1993.
On that same day, shortly after the tank was discharged, a Chemistry Technician went to the Radwaste Control Room to pick up the discharge permit. Upon review of the discharge permit, it was discovered that the Flow Rate Instrument Daily Check and Monitor Source Check areas in Section B were not completed. The Radwaste Operator informed the Chemistry Technician that the discharge instrument flow check was logged in the Radwaste Operator Log book. The Chemistry Technician reported these omissions to the SS and arranged for an after-the-fact radwaste monitor source check by a second chemistry technician. The radwaste monitor source checked satisfactory.
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NQC FORM 366A (5-72) l
NRC FORQ 3664 U.S. MUCLEAR REGULATORY CDMISSION APPROVED BY OMB No. 3150-0104 (5-92) EXPIRES 5/31/95 N PER R$ L LICENSEE EVENT REPORT (LER)
I
$""3,E,Dog eo t(eTI QUEST Oj TEXT CONTINUATION FORWARD COMMENTE PEGARDING BURDEE ESTIMATE TO THE INFORMATION AND RECOPDS MANAGEMENT BRANCH (MNBB 7714), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGT0*f, DC 20555-0001, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT AND BUDGET, WASHlWGTON, DC 20503.
FACILITY KAME (1) DOCKET NLMBER (2) lER WUMBER (6) PAGF (3)
James A. FitzPatrick Nuclear YEAR SEQUENTIAL REVISION Power Plant 05000333 03 OF 04 93 016 0 IEKT (If mnre space is reauired, use additionet copies of NRC form 366A) (17)
Event Causes The cause of this event was the failure to follow procedures and instructions (Cause Code A). The Liquid Radioactive Waste Discharge Permit clearly required a Flow Rate Instrument Daily Check and Monitor Source Check in Section B. The SS signed the authorization for discharge of Waste Sample Tank A without the Flow Rate Instrument Daily Check and Monitor Source Check areas in Section B being complete contrary to instructions contained in OP-49. Those areas of the discharge permit remained blank when the radwaste operator picked it up. There was no discussion between the SS and radwaste operator regarding the e crformance of these tests prior to discharging the tank. The SS assumed that the Radwaste Operator would perform these tests and enter the results prior to discharging the tank.
In addition, the radwaste operator proceeded to discharge Waste Sample Tank A without questioning the blanks at the Flow Rate Instrument Daily Check and Monitor Source Check areas in Section B of the discharge permit. The radwaste operator did perform the flow check but did not enter the test results on the permit, instead it was entered in the Radwaste Operator Log.
Event Analysis The Radwaste Discharge Monitor functions to alert operators to a higher than planned activity (High Alarm Setpoint) or to isolate the discharge path (High Setpoint) in the event of a significant non-conservative error in determining tank activity such as analysis error, unrepresentative sample, or selection of the wrong tank. Waste Sample Tank A contained domineralized water with an activity of 1.11E-7 microcurie / milliliter and was being discharged because of high inventory. The highest calculated dose to the public from consuming water at the nearest intake was 5.03E-8 mrem to the lower gastrointestinal tract. If the radwaste discharge monitor had been inoperative and an unrepresentative sample had been obtained due to improper mixing or the activity analysis been in error by a factor of 10 non-conservatively, the highest dose to the public would be insignificant as compared to that allowed for the quarterly dose to the public of less than or equal to 1.5 mrem to the whole body or less than or equal to 5 mrem to any organ by this pathway.
If Waste Sample Tank B had been selected erroneously, the activity contained in that tank was analyzed at 8.46E-8 microcurie / milliliter at that time and the highest calculated dose to the public woul' have been less than from the A tank.
NRC FORM 366A (5-92)
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ORC FORM 366A ' U.S. CUCLEAR REGULATOY CupMISSIC APPROVED BY OMB 100. 3150-0104 '
(5-92) EXPIRES 5/31/95 l l
ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH j LICENSEE EVENT REPORT (LER) THIS INFORMATION COLLECTION REQUEST: 50.0 HRS. <
TEXT CONTINUATION FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO I
THE INFORMATION AND RECORDS MAkACEMENT SRANCH !
(MNBB 7714), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555-0001 AND TO THE PAPERWORK REDUCTION PROJECT (31$0-0104), OFFICE OF MANAGEME NT AND BUDGET, WASHINGTON, DC 20503. .
FACILITT NAMC (1) DOCKET NtMSFR (?) LFR NLMBER (6) PAGE (3) !
James A. FitzPatrick Nuclear YEAR SEouENTIAL REVISION Power Plant 05000333 04 OF 04 93 016 0 TEXT (if more s.nace is reavired, use additional copies of hRC Form 366A) (17)
A satisfactory source check was performed after the discharge, which proved that the monitor would have functioned as designed. There was, therefore, no safety significance to the event.
The failure to perform the source check required by Table 3.10-2 note (c) was a violation of Radiological Effluent Technical Specifications. As a result, the event requires a report under 10 CFR 50.73 (a) (2) (i) (B) , that is, an operation prohibited by Technical Specifications.
Corrective Actions
- 1. The immediate corrective actions were: a) to perform a source check for the Radwaste Discharge Monitor and b) prohibit liquid radwaste discharges until the event was critiqued, corrective actions identified, and appropriate steps taken to prevent recurrence. !
- 2. The Shift Supervisor and operator involved were counstled. These individuals were also assigned to perform a critique of the event.
- 3. PSP-4, Wastewater Sampling and Analysis and OP-49, Liquid Radioactive Waste System have been revised to require the Chemistry Technician to perform the source check of the Radwaste Discharge Monitor prior to discharge of each tank. The Shift Supervisor is required to verify that this has been performed prior to authorizing the discharge of each tank. This change will ensure that the source check is performed l and logged on the form prior to authorization for discharge by the Shift Supervisor.
- 4. All operators have been briefed on the event and the corrective actions taken.
Additional Information !
Failed Components: None Previous similar Events: No previous LERs involving release of a liquid ,
radwaste tank and failure to follow procedures have been submitted. j l
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05000333/LER-1993-009, Forwards LER 93-009-02 Re Low Rwl Scram Due to FW Transient. Replacement of Reactor Feed Discharge Valves W/Improved Design Scheduled So That One Valve Will Be Replaced During 1994 Refueling Outage | Forwards LER 93-009-02 Re Low Rwl Scram Due to FW Transient. Replacement of Reactor Feed Discharge Valves W/Improved Design Scheduled So That One Valve Will Be Replaced During 1994 Refueling Outage | | 05000333/LER-1993-016 | LER 93-016-00:on 930722,missed Source Check of Radwaste Discharge Monitor Prior to Discharge of Waste Sample Tank a Due to Failure to Follow Procedures.Performed Source Check & Counseled Involved indiviuals.W/930823 Ltr | | 05000333/LER-1993-017 | LER 93-017-00:on 930729,declared APRM Downscale,Companion IRM Upscale Inoperable Due to Misinterpretation of Sr. Initiated Plant Shutdown & Declared Unusual Event Until Trip Was corrected.W/930830 Ltr | | 05000333/LER-1993-018, Forwards Rev 1 to LER 93-018,identifying That Increase in Min Carbon Dioxide Storage Tank Level Specified in TS Required to Provide Single Full Discharge of Carbon Dioxide Into North Emergency Switchgear Room | Forwards Rev 1 to LER 93-018,identifying That Increase in Min Carbon Dioxide Storage Tank Level Specified in TS Required to Provide Single Full Discharge of Carbon Dioxide Into North Emergency Switchgear Room | | 05000333/LER-1993-019, Forwards Updated CR Habitability Rept, Response to NUREG-0737,III.D.3.4 CR Habitability for JAFNPP, Per Commitment to Submit Rept as Corrective Action Associated W/ LER-93-019-02 | Forwards Updated CR Habitability Rept, Response to NUREG-0737,III.D.3.4 CR Habitability for JAFNPP, Per Commitment to Submit Rept as Corrective Action Associated W/ LER-93-019-02 | | 05000333/LER-1993-027, Reissues LER-93-027 Re Fire Protection Sys Functional Test Procedure Weaknesses Due to Incorrect Date on Block 7 of Form NRC 366.Rept Text Remains as Issued on 940120 | Reissues LER-93-027 Re Fire Protection Sys Functional Test Procedure Weaknesses Due to Incorrect Date on Block 7 of Form NRC 366.Rept Text Remains as Issued on 940120 | |
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