IR 05000445/1999009
| ML20206P609 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 05/12/1999 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20206P601 | List: |
| References | |
| 50-445-99-09, 50-445-99-9, 50-446-99-09, 50-446-99-9, NUDOCS 9905180267 | |
| Download: ML20206P609 (17) | |
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ENCLOSURE U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
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Docket Nos.: 50-445 50-446 License Nos.: NPF-87 NPF-89 Report No.: 50-445/99-09
, 50-446/99-09
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l Licensee: TU Electric Facility: Comanche Peak Steam Electric Station, Units 1 and 2 Location: FM-56 Glen Rose, Texas Dates: April 19-23,1999 Inspector: J. Blair Nicholas, Ph.D., Senior Radiation Specialist Plant Support Branch Approved By: Gail M. Good, Chief, Plant Support Branch
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Division of Reactor Safety Attachment: Supplemental Information i
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-2- i E.XECUTIVE SUMMARY Comanche Peak Steam Electric Station,' Units 1 and 2 1 NRC Inspection Report No. 50-445/99-09; 50-446/99-09 This announced, routine inspection reviewed the implementation of the liquid and gaseous radioactive waste effluent management program; status of the effluent radiation monitors and radiochemistry counting room instruments; and implementation of the engineered-safety-feature filtered ventilation systems design, maintenance, and in-place filter testing progra Training and qualifications of personnel, quality assurance oversight, and annual radiological effluent release reports were also reviewed.-
Plant Suooort
- An excellent liquid and gaseous radioactive waste effluent management program was implemented. The processing, sampling, and analyses of radioactive liquid and gaseous waste effluents and the approval and performance of waste discharges were conducted in accordance with Offsite Dose Calculation Manual requirements. Excellent performance was noted in the reduction of liquid effluent volume, gamma radionuclide curies released, and offsite dose. Since 1993, the volume of liquid radioactive waste discharged was reduced approximately 80 percent, and the curie amount of radioactive liquid effluent mixed fission and activation products released showed a 74 percent reduction resulting in a dose reduction of approximately 99. 6 percent. Since 1994, the -
gaseous effluent activity released decreased approximately 99.4 percent (Section RI.1).
- An effective maintenance and testing program was implemented for the in-place filter '
and laboratory charcoal testing of the engineered-safety-feature ventilation filter systems-(Section R1.2).
- The radiochemistry counting room's analytical instrumentation was properly maintained,
! tested, and calibrated in accordance with station procedures (Section R2.1).
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' * The' liquid and gaseous effluent radiation monitors were operable and properly maintained, tested, and calibrated in accordance with Offsite Dose Calculation Manual requirements. Effluent radiation monitor alarm set points were properly calculated and installed (Section R2.2).
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- Implementing procedures for the radioactive waste effluent program provided proper guidance. Revisions to the Offsite Dose Calculation Manual were appropriately-implemented and did not reduce the effectiveness of the radioactive waste effluent program. The 1996,1997, and 1998 annual radioactive effluent release reports were submitted in a timely manner and contained the required information and inc!uded a comprehensive executive summary that provided liquid and gaseous effluent performance trends relative to previous years (Section R3.1).
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- Chemistry and radiation protection personnel had a very good understanding of the l radioactive waste effluent program procedures, Offsite Dose Calculation Manual requirernents, and dose calculation methodologies. Experienced radwaste plant equipment operators performed radioactive waste batch effluent releases (Section R4).
- Training and qualification programs for the chemistry technical staff, radiation protection technical support staff, and radwaste plant equipment operators' were properly implemented. The chemistry, radiation protection, and radwaste operations departments maintained well trained, qualified, and experienced staffs for conducting l sampling, analyses, processing, and release operations for radioactive waste effluents (Section RS).
l * The licensee's assessment program of the radioactive waste effluent program was good. The auditors assigned to perform the assessment of the radioactive waste effluent program were well qualified to perform the radioactive waste effluent program evaluations. The annual nuclear over/iew evaluations provided management with a
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good perspective to assess the radioactive waste effluent program. The contractor l laboratories used to perform surveillance testing of the engineered-safety-related ventilation filter systems and the radioactive waste effluent samples were properly evaluated (Section R7).
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L-4- l Report Details IV. Plant Support-R1 Radiological Protection and Chemistry Controls R Imolementation of the Radioactive Waste Effluent Manaaement Proarams lnsoection Scope (84750)
~ Implementation of the liquid and gaseous radioactive waste effluent management programs, as described in the Offsite Dose Calculation Manual, was reviewe . The inspector interviewed licensee personnel and reviewed the following: l
- Ten batch radioactive liquid waste' effluent release permits for the period February 1997 through April 1999 from the monitor tanks
. Nine batch radioactive gaseous waste effluent release permits for the period
< February 1997 through April 1999 from the waste gas decay tanks and containment )
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= Selected liquid waste effluent sample analyses of continuous release samples from the low volume waste pond and turbine building sumps for the period February 1997 through April 1999
- Selected gaseous waste effluent sample analyses of continuous release samples from the north and south plant vent stacks for the period February 1997 through April 1999
= Quarterly dose results calculated from liquid and gaseous waste effluent !
releases for 1997,1998, and the first quarter of 1999 The inspector observed the following activities:
- The collection of gaseous effluent samples from the north and south plant vent exhaust stack radiation monitors and the performance of radiochemistry analyses for airborne particulates, iodine, tritium, and noble gas
- The collection of gaseous effluent samples from the Unit 1 containment for a containment vent batch release and the performance of radiochemistry analyses
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for airborne particulates, iodine, and noble gas -
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The collection of liquid effluent samples from plant effluent tank No.1 for
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preparation of a batch radioactive waste effluent release and the performance of i chemistry analysis for pH and radiochemistry analysis for principal gamma j emitting radionuclides, including iodine-131 and dissolved and entrained noble j gases 1
b. Observations and Findinas On April 20,1999, the inspector observed chemistry technicians perform the Unit 1
- containment vent and north and south plant vent sample collections and analyses. The inspector also observed the preparation of the Unit 1 containment vent release permit including the required approval authorizations and the verification of the effluent monitor set points prior to initiating the containment vent. On April 21,1999, the inspector observed a chemistry technician perform the sample collection and analyses of samples collected from plant effluent tank No.1. The inspector observed the preparation of the batch radioactive liquid effluent release permit by a chemistry technician. Prior to initiating the batch liquid effluent release, the liquid waste effluent radiation monitor set points were verified by the lead chemistry technician, and the proper valve lineup for the release of the plant effluent tank was performed and independently verified by two radwaste operator The inspector noted that the chemistry technicians carried and referred to the proper sampling procedures while performing the sample collections. Very good sample handling techniques were used when collecting and analyzing the samples. All aspects i of the airborne and liquid sample collections and analyses were properly performe i The radioactive liquid and gaseous waste effluent releases were performed in i accordance with approved procedures and the Offsite Dose Calculation Manual l requirements. Quantities of radionuclides released in the liquid and gaseous radioactive waste effluents were within the limits specified in the Offsite Dose Calculation Manua Offsite doses were calculated according to Offsite Dose Calculation Manual methodologies and were well within regulatory limits. Required analyses of monthly and quarterly composite samples of liquid and gaseous radioactive waste effluents were l properly performed as specified in the Offsite Dose Calculation Manua The radioactive liquid effluent data showed that the volume of liquid radioactive waste discharged since 1993 has been reduced significantly from 5.5 million gallons released in 1993 to 1.1 million gallons in 1998, an 80 percent decrease. From a review of data supplied by the licensee, the inspector determined that the curie amount of radioactive l liquid effluent mixed fission and activation products released between 1993 and 1997 showed a declining trend from 0.42 curies released in 1993 to 0.11 curies released in 1997, a 74 percent reduction. However, the curie amount of liquid effluent mixed fissio'n arid activation products increased in 1998 to 0.23 curies due to sub-micron particles in the liquid effluent resulting from the axial offset anomaly experienced during the 1998 fuel cycle. Even though the liquid effluent curies discharged increased in 1998, the dose remained low and the solid radwaste generated continued to decrease. The inspector noted that this occurred because the licensee used selective processing techniques to reduce the amount of high dose contributor radionuclides from the liquid l
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6-effluents discharged. From 1993 through 1998, the liquid effluent dose from mixed fission and activation products decreased from 0.046 millirems to 0.0002 millirems, a 99.6 percent reduction. This liquid effluent performance was among the best for 2-unit pressurized water reactor stations. The curie amount of liquid tritium released between 1993 and 1998 remained relatively constant and greater than the median industry valu Since 1993, the gaseous effluent data showed a significant decrease in the amount of airborne fission and activation radioactivity gases discharged. From 1993 through 1998, the curie amount of airborne fission and activation radioactive gasas released decreased from 245 curies to 1.59 curies, a 99.4 percent reduction. This gaseous effluent performance was among the best for 2-unit pressurized water reactor station Conclusions An excellent liquid and gaseous radioactive waste effluent management program was implemented. The processing, sampling, and analyses of radioactive liquid and gaseous waste effluents and the approval and performance of waste discharges were conducted in accordance with Offsite Dose Calculation Manual requirements. Excellent performance was noted in the reduction of liquid effluent volume, gamma radionuclide curies released, and offsite dose. Since 1993, the volume of liquid radioactive waste discharged was reduced approximately 80 percent, and the curie amount of radioactive liquid effluent mixed fission and activation products released showed a 74 percent reduction resulting in a dose reduction of approximately 99.6 percent. Since 1994, the gaseous effluent activity released decreased approximately 99.4 percen R1.2 Enaineered-Safetv-Feature Ventilation Filter Systems Insoection Scope (84750}
The inspector performed visualinspections of the control room emergency fil? ration / pressurization system and the primary plant ventilation system and interviewed the system engineer assigned to the system Tho inspector reviewed the following items:
Records of in-place filter testing of high efficiency particulate filters and clacoal adsorbers
- Records of laboratory tests of charcoal adsorWrs Observations and Findinas The inspector noted during visua inspections of the air cleaning systems that the filtration units and ventilation ducts were properly maintained. All filter housing doors were tightly closed, and the door gaskets were not leaking. Permanent test ports for t
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' in-place filter testing were installed and easily accessible. The areas surrounding the
, : filtration units were clean and free of debris.- Adequate lighting was provided for visual j inspection of housings and components. No problems were identified during the visual i
' inspection of the ventilation filter systems.-
l: . The inspector verified that the' surveillance tests provided for the' required periodic l functional testing of the filtration systems' components, evaluation of the high efficiency
! l particulate air filters and activated charcoal, and the in-place filter testing. The inspector
! reviewed the results of the last surveillance tests for each of the two safety-related air L cleaning ventilation filter systems and verified that previous surveillance tests were performed at the required 18-month frequency. The in-place filter testing and activated charcoal iodine removal efficiency tests were performed in accordance with approved I procedures by an_off-site contractor laboratory. The surveillance test results met Technical Specification acceptance criteri Conclusion An effective maintenance and testing program was implemented for the in-place filter
' and laboratory charcoal testing of the engineered-safety-feature ventilation filter l
system R2 Status of Radiological Protection and Chemistry Facilities and Equipment R Radiochemistry Countina Room i Inspection Scooe (84750)
l - The radiochemistry counting room's analytical instrumentation was inspected to verify i _ that adequate calibration and quality control programs were in plac Observations and Findinas i.
l The radiochemistry counting room maintained appropriate state-of-the-art analytical I = instrumentation to perform the required radiochemistry analytical measurements of the radioactive waste effluent samples. Quality control indicators were tracked and trended i
' for the gamma spectroscopy and gross alpha counting systems. Data showed that the ;
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instruments were operable, well maintained, and calibrated. Chemistry technicians j assigned to the radiochemistry counting room were trained and knowledgeable on the use of the instrumentatio Conclusion
- The radiochemistry counting room's analytical instrurnentation was maintained, tested, and calibrated in accordance with station procedures.
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-8-R2.2 Liauid and Gaseous Effluent Radiation Monitors Inspection Scoce (84750)
The inspector interviewed licensee personnel and reviewed the following:
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Effluent radiation monitor operability
- Effluent radiation monitor checks and calibration
- Effluent radiation monitor alarm set points Observations and Findinas During walkdowns of the effluent radiation monitors, the inspector determined that all i Offsite Dose Calculation Manual required effluent monitors were operable. Source )
checks, channel checks, channel functional tests, and calibrations were properly j performed on the liquid and gaseous effluent radiation monitors. Surveillance test i records documented that the effluent monitoring instrumentation was properly j maintained, tested, and calibrated in compliance with Offsite Dose Calculation Manual ,
I requirements (Tables 4.3 3 and 4.3-4).
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The inspector checked the set point calculations of selected effluent radiation monitors
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Calculation Manual methodologies. The inspector verified that the calculated alarm set points were properly installed in the effluent radiation monitor Conclusions The liquid and gaseoits effluent radiation monitors were operable and properly maintained, tested, and calibrated in accordance with Offsite Dose Calculation Manual requirements. Effluent radiation monitor alarm set points were properly calculated and installe R3- Radiological Protection and Chemistry Procedures and Documentation R Radioactive Waste Effluent Procedures. Offsite Dose Calculation Manual. and Annual Radioactive Effluent Release Reports Insoection Scoce (84750)
The inspector reviewed the following items:
i l * Procedures for the sampling, analysis, and release of radioactive liquid and l gaseous waste effluents
- Revisions to the Offsite Dose Calculation Manual involving changes to the radioactive waste effluent program e
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. *- Annual radioactive effluent release reports for 1996,1997, and 1998 b. Observations and Findinas Chemistry procedures described the responsibilities for collection and analyses of liquid and gaseous radioactive effluent waste samples. Procedures for batch and continuous release of liquid and gaseous radioactive waste effluents provided proper instruction for sampling, analyses, release permit generation, release limits, monitoring, and approvals. Chemistry and radiation protection procedures provided proper guidance in j the use of the quality controlled computer software to perform pre- and post-release dose calculations in accordance with the dose calculation methodologies described in the Offsite Dose Calculation Manual. The chemistry and radiation protection procedures provided sufficient instruction to effectively conduct the required radioactive waste effluent program activitie Revision 15 to the Offsite Dose Calculation Manual was issued on March 15,199 The inspector determined that the revision changes which involved the station service water effluent radiation monitors and the determination of the monitors' alert set point !
did not reduce the effectiveness of the radioactive waste effluent radiation monitoring progra i The annual radioactive effluent release reports were written in the format described in NRC Regulatory Guide 1.21, Revision 1, June 1974, and contained the required information. The executive summaries provided a comprehensive summary of the year's effluent data and included liquid and gaseous effluent performance trends relative ,
to previous years; c. Conclusions implementing procedures for the radioactive waste effluent program provided proper guidance. Revisions to the Offsite Dose Calculation Manual were appropriately - .
implemented and did not reduce the effectiveness of the radioactive waste effluent i program. The 1996,1997, and 1998 annual radioactive effluent release reports were j submitted in a timely manner and contained the required information and included a comprehensive executive summary that provided liquid and gaseous effluent l performance trends relative to previous year I R4 Staff Knowledge and Performance Insoection Scooe (84750)
Chemistry, radiation protection, and radwaste operations personnel were interviewed and observed to evaluate their knowledge and performance of radioactive waste effluent activities.
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l -10-b. Observations and Findinas The inspector interviewed and observed chemistry, radiation protection, and radwaste operations personnel while performing radioactive waste effluent activities and determined that the staff was familiar with the radioactive waste effluent management program requirements. Chemistry personnelincluding chemists, lead chemistry technicians, and chemistry technicians were knowledgeable and experienced in the performance of the liquid and gaseous radioactive waste effluent program procedures and implementation of the Offsite Dose Calculation Manual sampling and analyses requirements. Batch and continuous radioactive liquid and gaseous waste effluent releases were properly performed during the period February 1997 through April 199 Radiation protection personnel assigned to perform the effluent dose calculations were well trained and qualified. Radwaste operators were experienced and qualified to perform radioactive waste batch effluent release c. Conclusions Chemistry and radiation protection personnel had a very good understanding of the l radioactive wa'ste effluent program procedures, Offsite Dose Calculation Manual l requirements, and dose calculation methodologies. Experienced radwaste plant equipment operators performed radioactive waste batch effluent release R5 Staff Training and Qualification a. Insoection Scope (84750)
I The inspector interviewed licensee personnel and reviewed the following: l
Training and qualification programs for the chemistry technical staff, radiation ,
protection technical support staff, and radwaste plant equipment operators
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- Training program procedures
Selected training records for chemistry technicians, radiation protection technical support personnel, radwaste plant equipment operators
Selected on-the-job training qualification cards l
Technician qualification matrix for chemistry personnel ;
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-11-t Observations and Findinos Based on a review of training and qualification records, the inspector verified that the i five lead chemistry technicians and the three chemistry technicians assigned to the
, radiochemistry counting room were trained and qualified to independently perform
! routine radioactive waste effluent program activities. The two individuals in the radiatiori i
[ protection technical support group assigned the responsibility to perform and track p
. effluent doses were trained, qualified, and very experienced in performing dose calculations. The inspector also verified that all 12 radwaste plant equipment operators
. were fully trained and qualified to perform radioactive waste effluent program release activitie ~ Conclusions Training and qualification programs for the chemistry technical staff, radiation protection i
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technical support staff, and radwaste plant equipment operators were properly implemented. The chemistry, radiation protection, and radwaste operations departments maintained well trained, qualified, and experienced staffs for conducting sampling, analyses, processing, and release operations for radioactive waste effluent 'R6 Radiological Protection and Chemistry Organization and Administration insoection Scope (84750)
The organization, staffing, and assignment of the radioactive waste effluent management program responsibilities were reviewed.' Chemistry procedures were reviewed to ensure that responsibilities were assigned for the program management and implementatio Observations and Findinas The chemistry, radiation protection, and radwaste operations departments were, through a combined effort, responsible for implementation and control of the radioactive waste effluent program. No major organizational and staffing changes were noted in the three departments since the last inspection in February 1997. The staffing levels of the chemistry department, radiation protection technical support group, and radwaste l
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. operations department were sufficient to perform the duties required by the radioactive waste effluent program. Personnel changes represented a very low turnover and had no negative effect on the performance of the radioactive waste effluent progra Conclusions The licensee's radioactive waste effluent management program organization remained stable. An appropriate chemistry technical staff, radiation protection technical support staff, and radwaste plant equipment operations staff were maintaine m
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I-12-R7 Quality Assurance in Radiological Protection and Chemistry Activities - l Inspection Scooe (84750) '
The quality assurance program for the radioactive waste effluent program was reviewe The following items were reviewed:
- Qualifications of personnel who performed the nuclear overview evaluations
Annual nuclear overview evaluations of the radwaste and effluent / environmental monitoring programs performed in August 1997 and August 1998
- Quality assurance audits of the contractor laboratories used to perform surveillance tests and sample analyses required by the radioactive waste effluent program and the engineered-safety related ventilation filter systems' testing program Observations and Findinas
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The annual nuclear overview evaluations of the radioactive waste effluent program were -
a combined audit of three program areas including the ' solid radwaste treatment
- program, radioactive waste effluent monitoring program, and radiological environmental monitoring program. The reviewed evaluations were performed by qualified auditors, ,
who had previous operational experience in radioactive waste effluent activities. Based j on the inspector's review of the 1997 and 1998 annual evaluation reports, the evaluation
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of the radioactive waste effluent program provided management with a good perspective to assess the program. No SMART forms were issued as a result of the radioactive-waste effluent monitoring program evaluation Audits'of contractor laboratories used to perform radiochemistry analyses of radioactive waste effluent composite samples and in-place filter testing and charcoal analyses on the station's engineered-safety-related ventilation filter systems were used to evaluate
- the contractors' performance and to maintain the two contractor it.boratories as qualified
. suppliers on the licensee's routine suppliers list. These audits were performed by Nuclear Procurement issues Committee audit teams led by utilities with interest in the services provided by the contractor laboratories. The inspector determined that the audits performed of the two contractor laboratories met the requirements to properly j
- evaluate the contractors' abilities to perform respective Technical Specification and '
Offsite Dose Calculation Manual required ar'alyses and surveillance activitie Conclusions
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The licensee's assessment program of the radioactive waste effluent program was good. The auditors assigned to perform the assessment of the radioactive waste ;
effluent program were well qualified to perform the radioactive waste effluent program j evaluations. The annual nuclear overview evaluations provided management with a 1 good perspective to assess the radioactive waste effluent program. The contractor l
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-13-laboratories used to perform surveillance testing of the engineered-safety-related ventilation filter systems and the radioactive waste effluent composite samples were properly evaluate V. Manacement Meetinas X1 Exit Meeting Summary The inspector presented the results of the inspection to members of licensee management at the conclusion of the inspection on April 23,1999. The licensee acknowledged the findings presented. No proprietary information was identifie j j
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ATTACHMENT SUPPLEMENTAL INFORMATION .
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PARTIAL LIST OF PERSONS CONTACTED l
Licensee l l
C.L. Terry, Senior Vice President and Principal Nuclear Officer M. Blevins, Vice President, Nuclear Operations
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S. Bradley, Radiation Protection Supervisor -
P. Camerlin, Chemistry Technician C. Carella, Chemist
. J. Curtis, Radiation Protection Manager D. Davis, Nuclear Overview Manager L. Edwards, Radwaste Operations Supervisor T. Edwards, Radwaste Engineering Technician R. Flores, System Engineering Manager E. Floyd, Radiation Protection Technician l
H. Fossum, Chemistry T echnician D. Goodwin, Operations Support Manager T. Hope, Regulatory Affairs Manager B. Knowles, Health Physicist D. Moore, Operations Manager T. Nesbit, Radwaste Engineering Technician
- B. Pineda, Radwaste Engineering Technician )
T. Spalding, Lead Chemistry Technician i M. Syed, System Engineer, Radiation Monitoring R. Theimer, Chemistry Manager ,
C. Welch, Senior Nuclear Specialist, Nuclear Overview Department C. Wilkerson, Senior Licensing Engineer NRC A. Gody, Jr., Senior Resident Inspector LIST OF INSPECTION PROCEDURES USED i
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IP 84750 Radioactive Waste Treatment and Effluent and Environmental Monitoring l l
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-2-LIST OF DOCUMENTS REVIEWED ORGANIZATION CHARTS Chemistry Department - April 1999 l
Radiation Protection Department - April 1999 l Radwaste Operations Department - April 1999 CHEMISTRY TRAINING DOCUMENTATION -
Chemistry department training records Technician Qualification Matrix for Chemistry Personnel Radioactive Gaseous Effluents Pre-release Calculations OJT Card Radioactive Liquid Effluents Pre release Calculations OJT Card PC-11 Operations for Routine Releases OJT Card RADIATION PROTECTION TRAINING DOC 8JMENTATION Radiation protection department training records '
TRA-301, " Radiation Protection Training," Revision 12 Perform Pre-Release Calculations OJT Card Adjust DRMS Alarm Set points OJT Card Perform Post-Release Calculations OJT Card Produce Dose Summation Reports OJT Card RADWASTE OPERATIONS TRAINING DOCUMENTATION Radwaste operations department training records
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3-QUALITY ASSURANCE DOCUMENTS
. Nuclear Overview Evaluation Schedules for 1997,1998, and 1999 Quality Assurance Manual Section 18.0, " Evaluations,". Revision 5 Nuclear Overview Evaluatica Report EVAL-97-000093, "Radwaste and Effluent / Environmental Monitoring Programs," performed July 31 through August 15,1997
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Nuclear Overview Evaluation Report EVAL-98-000047,"Radwaste and Effluent / Environmental-Monitoring Programs," performed July 31 through August 25,1998 Vendor Audits -
NUPIC Joint Quality Assurance Audit of Teledyne Brown Engineering-Environmental Services, conducted August 31 through September 4,1998 NUPIC Joint Quality Assurance Audit of NUCON International, performed July 15-18,1997 PROCEDURES Radwaste Operations Procedures RWS-102 ' " Drain Channel A," Revision 8, July 7,1998 -
RWS 103 " Drain Channel B," Revision 11, February 12,1999 RWS-104 " Drain Channel C," Revision 10, April 8,1997 RWS-201 " Gaseous Waste Processing System," Revision 11, March 12,1999 Radiation Protection Procedures j l
' STA-603 " Control of Station Radioactive Effluents," Revision 15, October 1,1996 l RPl-705 " Post-Release Processing for Radioactive Effluent Releases," Revision 4, February 13,1998 RPI 706 Radioactive Effluent Tracking, Revision 4, July 19,1994 j Chemistrv Procedures CHM-616 " Sampling and Analysis of Gaseous Waste Systems," Revision 4, April 29,1992 !
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CHM-517 " Chemistry Control of Liquid Waste Systems," Revision 5, September 30, 1993 CLI740 " Effluent Pre Release Processing," Revision 0, October 9,1996 CLI-741 "Setpoint Modification and DRMS Pre-Release Surveillance," Revision 0, l May 3,1997 l CLl-774 "WRGM Filter Replacement," Revision 3, October 7,1992 CLI-777 "Use of Gaseous Waste Sampling Equipment," December 5,1991 MISCELLANEOUS DOCUMENTS Selected liquid radioactive waste batch release permits j I
Selected waste gas decay tank and containment batch release permits i
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Effluent radiation monitor surveillance test records Engineered-safety-feature ventilation filter systems surveillance test records Annual Radioactive Effluent Release Reports - 1996,1997, and 1998
"Offsite Dose Calculation Manual," Revision 15, February 26,1999 l
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