IR 05000382/1997023
| ML20212G374 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 11/04/1997 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20212G372 | List: |
| References | |
| 50-382-97-23, NUDOCS 9711060152 | |
| Download: ML20212G374 (21) | |
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U.S. NUCLEAR REGULATORY COMMISSION L
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, . REGION IV Docket No;: 50-3'82 License No.: NPF-38
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Report No.: -50-382/97-23 Licensee: Entergy Operations, In ,
'. Facility: Waterford Steam Electric Station, Unit 3 Location: Hwy.18 Killona, t.ouisiana Dates: . October 6-10,'1997 Inspector: Gilbert L. Guerra, Jr., Radiation Speclaust - Plant Support Brancit >
Approved By: Blaine Murray, Chief Plant Support Branch Division of Reactor Safety Attachments:: 1. Supplemental Inspection Information 2. Summary of Effluent Releases and Offsite Doses
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. 2-EXECUTIVE SUMMARY Waterford Steam Electric Station, Unit 3 NRC inspection Report 50-382/97-23 A routine, announced inspectioe of the liquid and gaseous radioactive effluent v aste management program including organization and management controls, radioactive effluent monitoring, and safety-related air cleaning systems were conducte ' BaDLSUDDDL1
* Overall, a very good liquid and gaseous radioactive effluent waste management program was implemented. Quantities of radionuclides released and offsite doses to the environment were within regulatory limits. Offsite doses from liquid and gaseous effluent releases for 1996 97 were reduced when compared to 1994 1995 do es. Goals for the reduction of radioactive effluent waste releases were established. Particulate filtration systems were installed ;n the component cooling water system and auxiliary component cooling water tower basins in 1996 to remove radioactive material in effluents discharged from the dry cooling tower sumps (Section R1.1).
- A very good safety-related air cleaning ventilation system surveillance program was implemented (Section R1.2).
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* The radiochemistry counting room was equipped with the appropriate analytical instrumentation to perform the required analyses (Section R2.1).
- Surveillance tests of the post-accident sampling system were performed by qualified chemistry technicians. Test results indicated that the system was maintained in a proper state of operational readiness (Section R2.2).
- All liquid and gaseous effluent radiation monitoring instrumentation was tested and calibrated as required. Out-of-service times were excessive for some radioactive effluent waste monitors in 1996, four monitors were declared out of service for greater than 30 days. In 1997, eight other effluent monitors had been declared out of service for greater than 30 days (Section R2.3).
- Revisions to the Of fsite Dose Calculation Manual were appropriately implemented and documented (Section R3.1).
- Chemistry personnel had a very good understanding of the radioactive liquid and gaseous effluent waste management procedures, Offsite Dose Calculation Manual, and regulatory requirements (Section R4).
- Chemistry personnei participating in the radioactive effluent waste management program were properly trained and qualified (Section RS 1).
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* The chemistry department organiiation and staffing met Technical Specification requirements and had experienced little change (Section R6.1). .
*- Quality assurance audits and surveillances of the radioactive effluent waste'-
management program activities were technically comprehensive and provided exce!!ent program evaluation and oversight. The licensee effectively identified, tracked, and implemented timely corrective actions for identified problems (Section R7.1).
- :: Good annual radioactive effluent release reports were written and submitted in a timely manner and contained the required information (Section R8.1).'
-* An abnormal / unplanned release of spent fuel pool water occurred on May 21,199 Licensee remediation actions were appropriate. No regulatory limits were exceeded - ' (Section R8.2).
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Summarv of Plent Status Waterford Unit 3 was at power operations during the inspection. There were no operational occurrences that impacted the results of the inspectio IV. Plant Suonort R1 Radioactive Protection and Chemistry Controls R1.1 Radiolooical Effluent Waste Managemert Proarams Inspgtjon Scoce (8475D1 The implementation of the radioactive effluent waste management program was reviewed. This review included: radioactive effluent waste processing, radioactive effluent waste sampling ar i analyses, analyses sensitivities and results, offsite dose results, and performance of required surveillance tests. The following activities were observed:
* The collection of samples from the fuel handling building ventilation system I'
for analyses of particulates and iodine and preparation of the updated release permit for this etiiuent release poin * The collection of a liquid waste sample fiom a waste condensate tank and performance of radiochemistry analvses on the sample and preparation of the release permit and valve lineup for discharg * Other samp!e collection points observed included the turbine building sump, component cooling water discharge, and a by cooling tower sump, Observations and Findinos The inspector noted titat iicensee personnel followed the appropriate sampling, waste release permit preparation, discharge valve lineup, and radiation monitor set point calculation procedures during the observed tasks. The analyses of radioactive liquid and gaseous waste effluents and the approve! and performance of waste discharges were conducted in accordance with licensee procedures. Chemistry technicians were careful when handling effluent waste samples. Gamma spectroscopy analyses of collected samples were properly performed. Offsite doses were calculated according to Offsite Dose Calculation Manual methodologies and were within regulatory limit ' Selected radioactive effluent waste release permits for releases performed in 1997 were reviewed. No problems were identifie . . -
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The inspector noted that a natural work team was chartered to reduce the number and volume of radioactive effluent waste releases and offsite doses. The natural work to'm was tasked with identifying action items to enhance the radioactive effluent waste management program. - Preliminary performance goals have been set to achieve top industry quartile perfctmance. Data for 1996 and 1997 to date, show that improvement was'made when compared with the doses reported in 1994 and'1995. This data is provided in Attachment 2 to this report.
The licensee made the following plant configuration changes to reduce doses to the public from radioac.ive liquid discharges:
* To obtain more accurate release data, check valves were installed in the dry cooling tower sump pump discharge lines to prevent back flow and reduce gomp run time * Particulate filtration systems were installed on the component cooling water system and auxiliary component ecoling water towcr basins to reduce activity concentration Component cooling water and auxiliary component cooling water leakage into the dry cooling tower sumps contributes to activity released from the dry cooling towers. A plant configuration change was in progress to route the dry cooling tower sump pump discharge to the circulation water discharge to the Mississippi river. With this modification, the licensee will be able to use dilution f actors in calculating effluent release doses from the d y cooling tower Conclusion Overall, a very good liquid and gaseous radioactive effluent waste management program was implemented. Quantities of radionue; ides released and offsite doses to the environment were within regulatory limits. Offsite doses from liquid and gaseous effluent releases for 1996-97 were reduced when compared with 1994-95 doses. Goals for the reduction of radioactive effluent waste releases were established. Particulate filtration systems were installed in the component cooling water system and cus:iliary component cooling water tower basins in 1996 to remove radioactive materialin effluents discharged from the dry cooling tower sump R t .2 Enoineered Safetv Feature Filtration and Control Room Habitabilitv Systems Insoection Secoe (84750)
Surveillance and test results for the safety related air cleaning ventilation systems testing program were reviewed to determine agreement with the commitments in the Updated Final Safety Analysis Report and compliance with the requirements in-the Technical Specifications. The inspector observed in-place filter testing of the control room emergency air filtration syste . _ - . _ _ ,. , . . , . . - . . . _ , - . . _ . , _ . _ - . . _ _ _ . . _ . _ _ .
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i bi - -- Observations and Findinas ... The'inspectcir and a system engineer performed a visualinspection of all the-Technical Specification required. ventilation filtration systems. Systems observed included the fuel handling building,: control room, controlled ventilation area, and the = shield building ventilation filtration systems. These systems contained high j efficiency particulate air filters and activated charcoal adsorbers. No problems were-
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identified during the visualinspection of the ventilation filtration systems. No external damage to the filtration knits was identified. All filter housings and ducts . were well maintained.: The areas surrounding the filtration units were clean, free of debris, and the filtration units were' adequately lighted to provide for visual , inspection of housings and component Surveillance of the control room emergency air filtration system was completed satisfactorily, and no problems were noted. The in place filter testing of the control
- room emergency air filtration system filters was performed la accordance with licensee procedures and Technical Specification requirement ,
The licensee's surveillance testing program included the periodic functional checking of safety-related air cleaning ventilation system components, evaluation of the high ,
~ efficiency particulate air filters and activated charcoal adsorbers, and in-place fittar L testing of the ventilation system filtets; Since some surveillance tests were only -
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required to be performed at 18 month frequencies, the inspector verified that the previous two surveillance tests were performed at the 18 month frequency. The , , activated charcoal removal efficiency tests were performed by an offsite contract laborator The inspector noted thr.t the Technical Specification requirement for testing the 1 activated charcoal adsorber material in various air cleaning ventilation systems after every 720 hours of operation was tracked.
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. Conclusion . 'A very good safety-related air cleaning ventilation system surveillance program was- ' implemented and conformed to the commitments in the Updated Final Safety-
' Analysis Report and met Technical Specification requirement , R2- Status of Radiological _ Protection and Chemistry Facilities and Equipment R Radiochemistrv Countino Room Insoection Scone (847501 -
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The inspector reviewed operations in the radiochemistry counting room.
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' 7 _ Qhservations and Findin2S The radiochemistry counting room maintained the appropriate analytical instrumentation to perform the required rad;ochemistry analytical measurements of the radioactive effluent waste samples. Instrumentation was operable and we!! ' maintained. Chemistry technicians assigned to the radiochemistry counting room were knowledgeable on the use of the instrumentatio Quality controlineficators were tracked and trended for the gamma spectroscopy counting systems. Data showed that tha instruments were properly maintaine ConclusiQD
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The radiochemistry counting room was equipped with the appropriate analytical instrumentation to perform the required analyse . H 2.2 Post-Accident Samolino System jnsoection Sgnoe (84750) Surveillance programs for the post-accident sampling system instrumentation were reviewe Observations and Findings The inspector noted that surveillance tests to obtain post-accident sampling systoni samples were usually performed quarterly. However, the licensee's commitment was only to test the system on a 6-month frequency. Thirteen chemistry technicians were qualified and trained on the use of the post-accident sampling system. The inspector verified that the testing of the post accident sampliny system was conducted according to the licensee's commitment ConcluniQD Surveillance tests of the post accident sampling system were performed by qualified chemistry technicians. Test results indicated that the system was maintaincd in a proper state of operational readines R2.3 Uould and Gaseous Effluent Radiation Monitors Insoection Scoce (847ED1 The liquid and gaseous effluent radiation monitors were inspected for operation, calibration, and reliability,
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b. Observations artd findmas The inspector noted in the Annual Radioactive Effluent Release Report for 1996 tha four monitors were declared out of service for greater than 30 days, two of which were out of service for greater than 100 days. The licensee declared the monitors out of service due to electronic spiking and clogged sample line problems. The inspector determined that appropriate alternate methods were implemented, and no violations of commitments or regulatory requirements were identified. However, the inspector noted that the out of service time for the monitors was excessiv Modifications were made to the inonitors that corrected problems. The annual report for 1996, states that delays in obtaining required parts and materials delayed getting the monitors returned to service within 30 day The inspector also noted that during 1997, eight other monitors were declared out of service for greater than 30 days. These monitors were different from those repo'ted in 1996 and were declared out of service for various problems, such as clogged umple lines and communication problems with the plant computer system The licensee informed the inspector th61 effluent monitor problems were on the plant priorities list and that actions to correct monitor problems are planned including replacing the RM11 computu. However, the licensee indicated that a high maintenance backlog contributed to the problem of retuming monitors to service in a timely manne The inspector noted that the condenser vacuum pump wide range gas monitor was out of service because of a temporary modification preventing calibration for greater than 30 days in 1997. The condenser vacuum pump wide range gas monitor was identified under the Maintenance Rule (10 CFR 50.65) as a component in a Category (a)(1) system. Based on information supplied after the inspection, the specific period of unavailability was not the result of a maintenance preventabie functional f ailure and unavailability was not a performance criterion for this syste No enforcement issues were identifie Although, performance was poor in returning out-of-service effluent monitors to service within 30 days, the licensee has complied with the required action statements of the Technical Requirements Manual for the affected monitors. This issue was discussed with chemistry management and with plant management at the exit meeting on October 10,1997. The licensee acknowledged the inspector's observatio Surveillances on etfluent radiation monitors including source checks and channel checks were preformed as required. Calibration records of liquid and gaseous effluent radiation monitors confirmed that the calibrations had been performed at the required intervals. These records indicated that the liquid and gaseous radioactive effluent waste monitoring instrumentation was tested and calibrated in agreement with the surveillance requirements specified in the Technical Requirements Manua _ _ _ _ _ _ - _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _
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Allliquid and gaseous effluent radiation monitoring instrumentation was tested and
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calibrated in compliance with the surveillanco requirements in the Technical ; Requirements Manual. Out of service timus were excessive for some radioactive effluent waste monitors. Specifically, in 1996, four monitors were declared out of service for greater than 30 days, two of which were for greater than 100 day ; Additionally, in 1997, eight other of fluent monitors have been declared out of t service for greater than 30 day R3 Radiological Protection and Chemistry Procedures and Liocumentation
. R Chanoen to ths Offsite Dose CalculatignA4anual and Proc 3dures y insoection Scone (847501 Revisions to the Offsite Oose Calculation Manual were reviewed for any changos to ,
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the radioactive effluent waste progiams arid the radweste system design and operatio Ohsstyitions and Findinos The radioactive effluent waste prograin's implementing procedures described the responsibilities for collection and ana!yses of liquid and gaseous radioactive effluent waste samples. Procedures governing radioactive effluent waste sampling contained appropriate detail and relied somewhat on " skill of the craf t" for chemistry technicians. These procedures provided for the following: sampling of the radioactive liquid and gaseous wastes, radionuclide analyses prior to release, calculation of effluent radiation monitor set points, projected offsite radionuclide concentrations, and offsite doses prior to release. No concerns were identified with the licensee's sample collection procedure Revisions 4 and 5 to the Offsite Dose Calculation Manual were issued since the last NRC inspection. The changes were documented in the appropriate annual radioactive effluent release reports as required by Technical Specifications. The
- inspector determined that the changes did not reduce the effectiveness of the radioactive effluent waste management program, Conclusion ,
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- Revisions to the Offsite Dose Calculation Manual were appropriately implemented l and documented. -
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. 10-R4 Staff Knowledge and Performance launctionScope (847601 Discussions . vere held with chemistry department personnel to evaluate their knowledge and performance of radioactive effluent waste activities, Qhations arid Findings The inspector observed chemistry technicians perform radioactive of fluent waste activities and determined that they were familiar with the requirements of the radioactive effluent waste management program, Chemistry personnel!ncluding supervisors and technicians maintained a high level of performance tad were knowledgeable of the liquid and gaseous effluent waste management procedures, Offsite Dose Calculation Manual recuirements, and segulatory requirements and Concluilon Chemistry personnel had a very good understanding of the radioactivo I; quid and gaseous effluent waste management procedures, Offsite Dose Calculation Manual, and regulatory requirament R5 Staff Training and Qualification R5.1 Trriining and Qualification of_Chemistrv Personnel insoection Scooe (84750) Training and qualifications for chemistry technicians involved with conducting the , radioet tive effluent waste managament program were reviewed, Dhmtions and Findings Using computerized training records of qualification tasks completed, the inspector verified that a high percentage of the personnelin the chemistry department were qualified to perform routine radioactive effluent waste management program activities. The training matrix of qualification cards completed showed 13 technicians were fully qualified to implement the radicactive effluent waste sampling and analysis programs. These technicians were also qualified to perform sampling of the post accident sampling system. Two new chemistry technicians were working toward comploting the appropriate task qualification The inspector observed chemistry pcysonnel performing assigned tasks and noted that they were knowledgeable and performed well. The inspector determined that proper training and qualification programs were being implemented for chemistry technician . - - ..- . , . - .- . . . - _ - . - . - . - -_- - -.. -. -.- --.. J
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11 I l Conclusiop Chemistry personnel participating in the radioactive effluent waste management , program were properly treined and qualifie I R6 Radiological Protection and Chemistry Organization and Administration
R6.1 01ganization an(Staisina 1
) I_nsnaction Scone 184750) 'The organization, staffing, and assignment of the radioactive effluent waste -
' management program responsibilities were reviewe . Observations and Findinas i The inspector noted that the responsibilities and staff for implementing the environmental monitoring and radioactive effluent waste management programs were transferred to the chemistry department from the radiation protection department in September 1996. The staff implementing the environmental !
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monitoring and radioactive effluent waste management programs has remained the essentially the sam , The inspector verified that the organizational structwo af the chemistry department
'was appropriate for implementing the liquid and gaseous radioactive effluent waste management program. The staffing level of the chemistry department was sufficient to perform the duties required by the radioactive effluent waste program The chemistry department was assigned the responsibility for prepasing radioactive waste release permits, evcluating the radioactive effluent waste releases, calculating the radiation doses resulting from the teleases to the environment, and maintaining radioactive effluent waste release data. Valve lineups and release activities were performed by the operations department. The inspector determined that the duties and responsibilities of the chemistry department were being effectively implemented, Conclusion The chemistry department organization and staffing met Technical Specification requirements. The technical staff had experienced little change since the last NRC inspection in January 1996, i
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O 12-R7 Quality Assurance in Radiological Protection and Chemistry Activities R7.1 RadiancliytEffluent Waste Quality Assurence Emgam IDsacetion Scone (8475Q1 The quality assurance audit and surveillance piograms regarding the radioactive effluent waste management program activities were reviewed for scope and thoroughness of program evaluation. The quality assurunce audit and evaluation program regarding contractors perfurming surveillance activities leivolving the radioactive effluent waste programs and safety-related air cleaning ventilation systems were reviewed. Specific audits and surveillances reviewed are listed in Attachment 1 to this repor The inspector evaluated the effectiveness of the licensea's controls in identifying, resolving, and preventing problems in the area of radwaste treatment and effluent monitoring, based on issues, events, or problems identified though the licensee's condition reporting syste . Ohsmyallons and Findinos Very good quality assurance audits and surveillances were performed. Biennial audits were conducted which properly assessed the activities involving the liquid and gaseous effluent waste managemer't program. Generally, audit teams included specialists from other utilities. The audits effectively identifind items for improvement. The condition reporting system was used by the licensee to track audit finding The audits and surveillances were of good quality, technically comprehensive, and provided excellent oversight and evaluation o' P.s beensee's performance in implementing the radioactive effluent waste management program and meeting the Technical Specification and Offsite Dose Calculation Manual requirements. The inspector noted that the audits included both performance and compliance based reviews. Audit team members had previous experience in the areas reviewed and were qualified to evaluate the performance of personne The licensee used a contractor laboratory to perform radiochemistry analyses on radioactive effluent waste composite samples. The licensee used another contractor to perform in place filter testing and it.boratory charcoal adsorber analyses on the station's safety related air cleaning ventilation systems. The licensee used audits performed by the Nuclear Procurement issues Committee (NUPlC) to evaluate the performance of the contractors in performing analytical functions and to retain tneir current status on the licensee's qualified suppliers lis No negative trends were noted in the review of condition reports. Correctiva actions taken for licensee-identified deficiencies or improvement requests were I appropriate and timely, l
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13- t J l CpHClutiQD Quality assurance audits and surveillances of the radioactive effluent waste i i management program activities were technically comprehensive and provided excellent program evaluation and oversight. Evaluations of the contractors used to 1 perform radioactive ef fluent waste program Technical Specification required j surveillance analyses were performed. The licensee effectively identified, tracked, ; and implemented timely corrective actions for identified problem j
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M8 - Miscellaneous Radiological Protection and Chemistry issues i P.8.1l Renorts-
! in&Racilon Scope 1847501 i
Annual reports cor.cerning radioactive effluent waste releases were reviewed for omissions, obvious mistakes, anomalous measurements, observed biases, and trends - in the dat i Observations and Findinos Good annual radioactive effluent release reports were issued which contained the required information concerning liquid and gaseous effluent releases and annual dose . calculation result >
-- - The inspector reviewed the licensee's annual effluent release repyts for 1995 and l 1996. The reports were written in the proper format and contained the required information.- No unplanned releases were reported during 1995 and 1900. Several -. monitors were reported out of service in excess of 30 days during the 1995 1996 c time period. ' The out of service monitors are discussed in Saction R Summaries of the quantities of radioactive liquid and gaseous effluents released to the environment, and their associated doses to members of the public for 1995 and :
1993 were properly documented in the annual reports. A summary of the l radioactive liquid and gaseous effluent releases and associated doses is presented in l Attachment 2 to this repor The annual reports included changes to the Offsite Dose Calculation Manual as zi require c.- Conclusion
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Good annual radioactive effluent release reports were submitted in a timely manner
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R8.2 Spent Fuel Pool Soill jnsagetion Scace (847501 The inspector reviewed the spent fuel pool spill to the environment that occurred on May 21,199 Observations and Findings On May 21,1997, at 2:41 a.m. the spent fuel pool overflowed and spilled radioactive water. Water eventually made its way outside the fuel handling building trsin bay. Water levels in the train bay were sufficient to cause water to flow from under the large metal exterior access doors and spread out onto the concrete and asphalt surf aces immediately outside the train bay doors. Water flowed omo the security isolation tone that is comprised of scil covered with a 12 inch layer of sea shells. Water that entered the isolathn zone did not travel past the protected area fence. Water also entered the storm drain syste Radiation protection and chemistry personnel responded to the area upon notification and took act!ans to prevent further spread of water and to block the storm drains. The area was surveyed, posted, and general access was blocke Absorbent materials were used to soak up the spilled water. The storm drain system was dammed to prevent releases to the drainage ditches. Extensive excavation and cleanup were performad by the licensee. Surveys and samples were taken to ensure cleanup efforts were sufficien Contaminated water in the storm drain system escaped from the licensee's control because of *,hundershowers that occurred at approximately 1:15 p.m. and 5:30 on May 21,1997. The contaminated storm drain system was repeatedly flushed with clean water until the radioactivity was less than the lower limit of detection for samples collected. Af ter flushing for several days, the storm drains were determined to be free of radioactivity on May 24,199 Calculated release concentrations and offsite doses were well within the Offsite Dose Calculation Manuallimits, An abnormal / unplanned release report was written which includes all actions taken because of the event, release and dose calculations, and sample and analysis results. The licensee willinclude this information in its decommissioning file, and a summary will be included in the 1997 Annual Radioactive Effluent Release Repor The inspector determined that the event did not involve any violations of regulatory requirement __._ ..._ ._ . . - _ _ ___ . ._ _ . _ _ _ _ _ .. _ _ _ _ _ _ . _ - -
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t Cnucluilon : An abnormal / unplanned release of spent fuel pool water occurred on May 21,199 Licensee remediation actions and release and dose calculations were appropriat , No regulatory limits.were exceade ; V. Menagement Moe.tlogs :
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X1 Exit Meeting Summery , The inspector presented the results of the inspection to members of licensee
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management at the conclusion of the inspection on October 10,1997. . The licensee ! acknowledged the findings presented. No proprietary information was' identifie !
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___ _ _ . . AIIACHMENI_1 . SUPPLEMENTAL INFORMATlON PARTIAL LIST OF PERSONS CONTACTED Licenses C. Dugger, Vice President Operations ' E. Beckendorf, Plant Security Superintendent
~ M. Brandon, Licensing Supervisor J. Brown, Training Instructor A. Cilluffa, HP/RW Training Supervisor F. Drummond, Director Site Support E. Ewing, Director Nuclear Safety & Hogulatory Af f airs T. Gaudet, Licensing Manager
_ C. Puy, Chemistry Technician G. Hood, Chemistry Supervisor T. Leonard, General Manager Plent Operations J, Lewis, Emergency Planning Manager D. Madere, Chemistry Superintendent D. Newman, Quality Specialist IV R. Prados, Senior Lead Engineer, Licensing D. Reider, Senior Engineer, Quality Assurance J. Soper, Senior Technical Instructor M. Touna, System Engineer C. Thomas, Licensing Supervisor J. Williams, Chemistry NRC T. Meadows, License Examiner, Division of Reactor Safety LIST OF INSPECTION PROCEDURES USED IP 84750 Radioactive Waste Treatment, and Effluent and Environmental Monitoring _ - . __
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2-LIST OF DOCUMENTS REVIEWED ' EBQCEDURES CE-001000 Organization and Responsibilities of the Chemistry Department, Revision 7 : CE 001004 Periodic Analysis Scheduling Program, Revision 11 CE-002 016 Maintaining Gaseous Waste Management System, Revision 5 - CE-002 018 Monitoring Liquid Waste Management, Revision 5
: CE 003 305 - Sampling of Veritilation and Gaseous Waste Management Systems for ;
Radioactive Effluents, Revision 10 ! CE 003 506 Sampling of GWMS and Containment Purge for Radioactive Effluents,
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CE 003 509 Routine Filter Replacement and Grab Sampling From Pig Monitors end
. WRGMS, Revision 0 CE 003 510 Technical Specification Action Statement Compliance, Revision 0 ! ~" '
CE-003 511 Liquid Effluent Sampling, Revision O CE 003 514 Liquid Radioactive Waste Release Permit (Computer), Revision 0 i CE 003 515 Gaseous Radioactive Waste Release Permit (Computer), Revision 0 ; CE 003 905 Testing and Maintenance of the Post Accident Sampling System, Revision 7 !
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PE-005 004 - Control Room Air Conditioning System Surveillance, Revision 7 i AUDITS AND SURVEILLANCES SA 95-002.1 Offsite Dose Calculation Manual, November 28 December 15,1995' SA 96-018,1 Health Physics Program -Instruments, Process, and Area Monitors, August 20 September 23,1996 SA 96-019,1 Water Chemistry, September 23 November 12,1996 SA 97 022.1 Radiological Environmental Monitoring Program, January 4 - February 21,1997 0S 96-061 Evaluation of Leakage from the Waste Gas Management System, March 27,1996 ; REPORTS Annual Radioactive Effluent Release Report - 1995 and 1996
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QIllEfs Abnormal \ Unplanned Release Report - Spent Fuel Pool Ef fluent Release Calculations Radioactive waste effluent trending data Condition Reports - 05 1297, 96-0030, 96-0662, 96-0689, 96-0904, 96 1218, 96-1272, 96-1371, 96 1379, 96 1952, 97-0157, 97-0301, 97 0765, 96 2004 97 2236 Offsite Dose Calculation Manual, Revisions 4 and 5 Chemistry Department Training Records Organizational Charts Air Cleaning Systems Surveillance Test Records Vendor \ Supplier Evaluations
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..o- s ATTACHMENT 2 ~~
SUMMATION OF ALL LIQUID EFFLUENT RFIFASES
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- L 1994" J- -1995 . 1996 1997* s Number of Batch g 180 136 253 261 138 128
_Releases Fission & Activation Products (Curies) 1.310 0.604 3.650 3.770 0.817 1.330 Tritium (Curies) 495 490 759 1180 518 317 ' Dissolved & Entrained Noble Gases (Curies) 1.180 1.600 6.860 10.400 0.136 1.250
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Gross Alpha (Curies) 0.000 0.000 0.000 0.000 0.000 0.000 Waste Volume , Released (liters) g 2.10E + 6 7.70E + 6 8.49E + 6 1.25E + 7 1.03E + 7 9.68E + 6 !
*1997 data as of the date of this inspection
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.-o a-2-ATTACHMENT 2 (cont.)
SUMM ATION OF ALL AIRBORNE EFFLUENT RELEASES
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T 399f2 2 1993 -' Ni994^ ~ei995~ - 199E' ' ~ unummuummmmmmeununumulumnislumemuummmuumummummamunummymmmmmme ================ 1997* I Number of Batch Releases 6 3 14 16- 21 0-Fission & Activation Products (Curies) . 693 914 2700 1740 80 535 I Total lodine-131 (Curies) I 1.76E-5 1.08E-6 1.08E-4 7.77E-4 4.74 E-7 5.36E-4
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Particulates with Half- ' Lives > 8 days ,
(Curies! 1.81 E-5 0.OOE-O 7.65E-5 1.39E-5 5.18E-6 1.28E-5
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' Gross Alpha (Curies) 1.95E-5 2.15E-5 1.53E-5 2.03E-5 1.95E-5 3.44E-6 Tritium (Curies) 311 102 151 122 90 57
*1997 data as of the date of this inspection
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-3-ATTACHMENT 2 (cont.)
MAXIMUM ANNUAL DOSES FROM GASEOUS AMD LIQUID EFFLUENT RELEASES
#
I h ] 91992 N I199hDose^ 1994 Dose 11995 Dose 1996 Dos'a - 1997 Dose , Liquid Effluents (mrem)
0.168 0.796 0.849 0.113 Whole Body Organ (Liver) l 0.161 0.218 0.229 1.050 1.600 2.190 1.180 0.159 Gaseous Effluents (mrad) Noble Gas Gamma (Air Dose} O.670 0.320 0.606 0.431 0.076 0.208 Beta (Air Dose) 0.830 0.740 1.610 1.190 0.071 0.156 lodine-131, lodine-133, , Tritium, and Particulates with Half-Lives > 8 days (mrem) 0.280 0.090 0.187 0.558 0.147 0.457 i
*1997 data as of the date of this inspection i
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E t _ _ _ _ _ . _ . . _ _ _ _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ . . _ _ . _ _ . _ _ _ _ . . . __ _ _ _ _ . }}