IR 05000285/1998013
| ML20198G764 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 12/16/1998 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20198G749 | List: |
| References | |
| 50-285-98-13, NUDOCS 9812290166 | |
| Download: ML20198G764 (18) | |
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ENCLOSURE U.S. NUCLEAR REGULATORY COMMISSION
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REGION IV
Docket No.: 50-285- ,
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' License No.: DPR-40
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Report No.: 50-285/98-13 Licensee: Omaha Public Power District Facility: Fort Calhoun Station Location: Fort Calhoun Station FC-2-4 Adm., P.O. Box 399, Hwy. 75 - North of I Fort Calhoun i
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Fort Calhoun, Nebraska Dates: November 30 through December 4,1998 '
Inspector: J. Blair Nicholas, Ph.D., Senior Radiation Specialist !
Plant Support Branch l
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Approved By: Blaine Murray, Chief, Plant Support Branch Division of Reactor Safety i
Attachment: Supplemental Information
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2-EXECUTIVE SUMMARY Fort Calhoun Station NRC inspection Report 50-285/9813 This announced, routine inspection reviewed the implementation of the liquid and gaseous radioactive waste effluent management program. Training and qualifications, quality assurance oversight,- facilities and equipment, and ennual reports were also reviewe Plant Support
- Overall, a good liquid and gaseous radioactive waste effluent management program was implemented which included proper implementing procedures, a qualified and experienced staff, and good analytical instrumentatio * The liquid and gaseous radioactive waste effluent management program was properly implemented. The volume of liquid waste effluent discharged remained relatively constant since 1993. The station's curie amount of liquid effluent discharged showed a slight decreasing trend since 1993, but the liquid tritium released showed some increase. Since 1994, the gaseous effluent activity relear,ed showed a significant increase due to the influence from the failed fuel (Section R1.1).
- 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 instruments were properly maintained and calibrated (Section R2.1).
- Three liquid and four gaseous effluent radiation monitors were operable and properly maintained, tested, and calibrated (Section R2.2).
- 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 and 1997 annual radioactive effluents release reports were submitted in a timely manner and contained the required information (Section R3.1).
- Chemistry personnel had a very good understanding of the radioactive waste effluent program procedures, Offsite Dose Calculation Manual requirements, and dose
calculation methodologies (Section R4).
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- The chemistry and operations departments maintained well trained, qualified, and
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experienced staffs for conducting sampling, analyses, processing, and release operations of radioactive waste effluents (Section RS).
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Oversight of the radioactive waste effluent program was good. The quality assurance audit and surveillance program along with the chemistry department self-assessments ,
provided management with a good assessment of the radioactive waste effluent >
program. Timely, effective corrective actions were implemented in response to assessment findings. Contractor laboratories used to perform in-place filter testing and charcoal analyses on the engineered-safety-related ventilation filter systems and radiochemistry analyses of the radioactive waste effluent composite samples were properly evaluated (Section R7).
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-4-Report Details
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IV, Plant Support R1 Radiological Protection and Chemistry Controls R1.1 _lmolementation of the Radioactive Waste Effluent Manaaement Proarams Insoection Scope (84750)
Implementation of the liquid and gaseous radioactive waste effluent management programs, as described in the Offsite Dose Calculation Manual, was reviewe l The inspector interviewed licensee personnel and reviewed the following:
= Ten batch radioactive liquid waste effluent release permits for the period January 1997 through November 1998 from the monitor tanks
. Twelve batch radioactive gaseous waste effluent release permits for the period January 1997 through November 1998 from the waste gas decay tanks and containment
!- . Selected liquid waste effluent sample analyses of continuous release samples from the steam generators for the period January 1997 through November 1998
= Selected gaseous waste effluent sample analyses of continuous release samples from the condenser off gas, auxiliary building exhaust stack, and laboratory and radwaste building exhaust stack for the period January 1997 through November 1998
= Quarterly dose results calculated from liquid and gaseous waste effluent releases for 1997 and 1998 l The inspector observed the fol!owing acdvities:
l l = The collection of gaseous effluent sample from the condenser off gas radiation monitor and the performance of the radiochemistry analysis for noble gases
- The collection of gascous effluent samples from the auxiliary building exhaust stack radiation monitor and the performance of radiochemistry analyses for airborne particulates, iodine, and noble gas
! * The collection of gaseous effluent samples from the auxiliary building exhaust stack radiation monitor and the performance of radiochemistry analyses for
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airborne particulates, iodine, and noble gas
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b. Observations and Findinas
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On December 1,1998, the inspector observed chemistry personnel perform the above listed sample collectioris and sample analyses. The inspector noted that the chemistry personnel carried and referred to the appropriate sampling procedures while performing the sample collections. Proper sample handling techniques were used when collecting and analyzing the samples. All aspects of the sample collections and analyses were properly performe The radioactive liquid and gaseous waste effluent releases were performed in accordance with approved procedures and the Offsite Dose Calculation Manual requirements. Quantities of radionuclides released in the liquid ano 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 within regulatory limits. Required analyses of monthly and quarterly composite samples of liquid and gaseous radioactive waste effluents were 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 had remained relatively constant. Through a review of data supplied by the licensee that related to radinave effluent releases from pressurized
, water reactors, the inspector determined that the curie amount of radioactive liquid effluent mixed fission and activation products released between 1993 and 1997 showed a declining trend but still remained high compared to similar facilities. The curie amount of liquid tritiurn released between 1993 and 1995 remained relatively constant and low compared to other pressurized water reactor facilities, but increased in 1996 to near the median amount released by pressurized water reactors due to multiple reactor shutdowns and poor fuel integrity and has since remained near the median industry valu Since 1993, the gaseous effluent data showed a significant increase in the amount of activity discharged due to the failed fuel experienced during the period 1994 through 1997. However, in 1997, the amount of airborne activity released showed a decline and improvemen Conclusions The liquid and gaseous radioactive waste effluent management program was properly implemented. The volume of liquid waste effluent discharged remained relatively constant since 1993. The station's curie amount of liquid effluent discharged showed a slight decreasing trend since 1993, but the liquid tritium released showed some increase. Since 1994, the gaseous effluent activity released showed a significant l increase due to the influence from the failed fuel.
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6-R1.2 Enaineered-Safetv-Feature Ventilation Filter Systems Inspection Scope (84750)
The inspector performed visual inspections of the control room air treatment system, the spent fuel storage ventilation system, and the safety injection pump room ventilation system and interviewed the system engineer assigned to the system The inspector reviewed the following:
- Records of in-place filter testing of high efficiency particulate filters and charcoal adsorbers
- Records of laboratory tests of charcoal adsorbers Observations and Findinas The inspector noted during visual inspection 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 in-place filter testing were installed and easily accessible. The areas surrounding the filtration units were clean, free of debris, and adequate lighting was provided for inspection of housings and components. The inspection of the ventilation filter systems indicated no problem The inspector verified that the surveillance tests for the three safety-related ventilation filter systems provided for the required periodic functional testing of the filtration systems' components, evaluation of the high efficiency particulate air filters and activated charcoal, and the in-place filter testing. The inspector reviewed the results of the last performed surveillance tests for each of the three safety-related air 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 procedures by an off-site contractor laboratory. The surveillance test results met Technical Specification Table 3-5 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 systems.
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-7-R2 Status of Radiological Protection and Chemistry Facilities and Equipment R Radiochemistry Countina Room a .- Inspection Scoce (84750)
The radiochemistry counting room's analytical instrumentation was inspected to verify *
that adequate calibration and quality control programs were in plac Observations and Findinas The radiochemistry counting room maintained the appropriate analytical instrumentation to perform the required radiochemistry analytical measurements of the radioactive waste effluent samples. Quality control indicators were tracked and trended for the gamma spectroscopy and gross alpha counting systems. Data showed that the instruments were operable, well maintained, and calibrate Conclusion i
The radiochemistry counting room's analytical instruments were properly maintained and calibrate R2.2 Liauid and Gaseous Effluent Radiation Monitors Insoection Scoce (84750)
The inspector interviewed licensee personnel and reviewed the following:
a Effluent radiation monitor operability
- Effluent radiation monitor checks and calibration a Effluent .adiation monitor alarm setpoints Observations and Findinas During walkdowns of the effluent radiation monitors, the inspector found all monitors operable. Source checks, channel checks, channel functional tests, and calibrations were properly performed on the liquid and gaseous effluent radiation monitor Surveillance test records documented that the effluent monitoring instrumentation was properly maintained, tested, and calibrated in compliance with Offsite Dose Calculation Manual Tables 2.1.2 and 2.2.2 requirement The inspector checked the setpoint calculations of selected effluent radiation monitors and determined that the alarm setpoints were properly calculated using Offsite Dose Calculation Manual methodologies. The inspector verified that the calculated alarm setpoints were properly installed in the effluent radiation monitor m . .._
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! Conclusions The liquid and gaseous effluent radiation monitors were operable and properly maintained, tested, and calibrated. Effluent radiation monitor alarm setpoints 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 Inspection Scoce (84750)
The inspector reviewed the following: ;
- Procedures for the sampling, analysis, and release of radioactive liquid and gaseous waste effluents
- Revisions to the Offsite Dose Calculation Manual were reviewed for any changes to the radioactive waste effluent program
= Annual radioactive effluent release reports for 1996 and 1997 Observations and Findinas Chemistry procedures described the responsibilities for collection and analyses of liquid and gaseous radioactiva effluent waste samples. Procedures for batch and continuous j release of liquid and gaseous radioactive waste effluents provided proper instruction for sampling, analyses, release permit generation, release limits, monitoring, and approvals. Chemistry procedures also provided proper guidance in the use of the quality controlled computer software to perform dose calculations in accordance with the dose c iculation methodologies described in the Offsite Dose Calculation Manual. The chemis,9 orocedures were written with sufficient detail to effectively :onduct the required radioactive waste effluent program activitie Revisions 8 and 9 to the Offsite Dose Calculation Manual were issued since the last NRC inspection in October 1996. The inspector determined that the revision changes to the, Offsite Dose Calculation Manualincorporated the format of NUREG-0472, ,
" Radiological Effluent Technical Specifications for Pressurized Water Reactors," and did )
not reduce the effectiveness of the radioactive waste effluent management progra The details of the changes will be documented in the 1998 annual radioactive effluent release repor 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 informatio I
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. 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 program. The 1996 and 1997 annual radioactive effluent release reports were submitted in a timely manner and contained the required informatio R4 Staff Knowledge and Performance a. Insoection Scope (84750)
Chemistry personnel were interviewed and observed to evaluate their knowledge and performance of radioactive waste effluent activitie b. Observations and Findinas The inspector interviewed and observed chemistry personnel while performing radioactive waste effluent activities and determined that they were familiar with the radioactive waste effluent management program requirements. Chemistry personnel including supervisors, chemists, and senior 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 ,
requirements. Batch and continuous radioactive liquid and gaseous waste effluent releases were properly performed during the period January 1997 through November 199 i
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trained and qualifie c. Conclusions l
Chemistry personnel had a very good understanding of the radioactive waste effluent program procedures, Offsite Dose Calculation Manual requirements, and dose l calculation methodologie l R5 Staff Training and Qualification l Insoection Scope (84750)
The inspector interviewed licensee personnel and reviewed the following:
- Training and qualification programs for the chemistry technical staff and auxiliary building nuclear equipment operators
- Training program procedures
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- Selected lesson plans
- Selected performance evaluation checklists
Qualification manuals for the chemistry personnel and auxiliary building nuclear equipment operators
. Observations and Findings Based on a review of training and qualification records, the inspector verified that seven chemists and five senior chemistry technicians were trained and qualified to independently perform routine radioactive waste effluent program activities and met shift qualification requirements. Two recently hired chemistry technicians were in the process of completing the required training and task qualifications to be shift qualifie The inspector also verified that each of the six operating shifts was staffed with at least one qualified and experienced auxiliary building nuclear equipment ope rator, who routinely performed waste effluent release activitie Conclusions
, Training and qualification programs for the chemistry technical staff and auxiliary building nuclear equipment operators were properly implemented. The chemistry and 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 Inspection Scope (84750)
The organization, staffing, and assignment of the radioactive waste effluent management program responsibilities were reviewed. Chemistry departmental procedures were reviewed for the assignment of responsibilities for the management and implementation of the radioactive waste effluent progra Observations and Findinas The chemistry department was responsible for implementing the radioactive waste effluent program with support from the auxiliary building nuclear equipment operators and control room operators when performing liquid and gaseous radioactive waste l effluent batch releases. The staffing levels of the chemistry and operations departments were sufficient to perform the duties required by the radioactive waste effluent progra The chemistry staff implementing the radioactive waste effluent program had remained essentially the same with the addition of two recently hired chemistry technicians. The system chemistry supervisor responsible for the radioactive waste effluent program had remained the same since the last NRC inspection of this area conducted in October
1996. The previous chemistry manager was replaced as a result of staff reassignment !
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The inspector verified that the qualifications and experience of the new chemistry manager met Technical Specification requirement The operations shift crews were adequately staffed, and the auxiliary building nuclear equipment operators had not changed significantly during the past 2 years. The organization and staffing of the chemistry department and the operations shift crews were appropriate for implementing the radioactive waste effluent progra Conclusion An appropriate chemistry technical staff and operations staff were maintaine R7 Quality Assurance in Radiological Protection and Chemistry Activities Inspection Scoce (84750)
The quality assurance program of the radioactive waste effluent program and Offsite Dose Calculation Manual were reviewed. The following items were reviewed:
- Qualifications of personnel who performed the quality assurance audit and ,
surveillance
- Biennial quality assurance audit of the radiological effluent program perfo :'ried in January 1997
- Quality assurance surveillance of the 1997 annual radiological effluent release report performed in May 1998
- Chemistry department self assessment performed in July 1997 )
- Quality assurance audits of the contractor laboratories used to perform surveillance tests and sample analyses required by the radioactive waste effluent l
program and the engineered-safety-related ventilation filter systems' testing program
! O_bfervations and Findinas The biennial quality assurance audit of the radiological effluent program was a combined audit of three program areas including the radiological waste treatment program, radiological effluent monitoring program, and radiological environmental i monitoring program. Based on the inspector's review of the audit report, the audit of the I radiological effluent program appeared to be not as comprehensive as observed in previous audits when only the radiological effluent monitoring program was audite This observation was discussed with the quality assurance manager, who stated that he would evaluate the inspector's observation. No condition reports were issued as a result of the radiological effluent monitoring program audi ,
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- 12-A quality assurance surveillance of the 1997 annual radiological effluent release report was performed to supplement the quality assurance audit program. No condition reports were issued as a result of this surveillanc During July 1997, the chemistry department performed a comprehensive self assessment which included several program activities related to the radioactive waste effluent program. Condition reports generated in the radioactive waste effluent program area were properly addressed, and the problems were corrected in a timely manner. The self-assessment was performed by technical personnel who had work experience in the areas assesse The reviewed quality assurance audit and surveillance were performed by qualified auditors and technical specialists, who had previous operational experience in radiological effluent activities. The quality assurance program and chemistry department self-assessment provided good oversight of radioactive waste effluent program activitie 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 laboratories 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 l audits performed of the two contractor laboratories met the requirements to properly l evaluate the contractors' abilities to perform their respective Technical Specification and !
Offsite Dose Calculation Manual required analyses and surveillance activitie c. Conclusions Oversight of the radioactive waste effluent program was good. The quality ascurance audit and surveillance and chemistry department self-assessment provided management with a good assessment of the radioactive waste effluent progra Timely, effective corrective actions were implemented in response to assessment findings. Contractor laboratories used to perform in-place filter testing and charcoal analyses on the engineered-safety-related ventilation filter systems and radiochemistry analyses of the radioactive waste effluent composite samples were properly evaluate V. Manaaement Meetinq2 X1 Exit Meeting Summary The inspector presented the results of the inspection to members of licensee management at the conclusion of the inspection on December 4,1998. The licemee acknowledged the findings presented. No proprietary information was identifi< >
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SUPl EMENTALINFORMATION l
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P 4RTIAL LIST OF PERSONS CONTACTED j i
Licensee l
' O. Bannister, Supervisor, Operations R. Beck, Chemist, Chemistry G. Cavanaugh, Licensing Engineer, Licensing ;
C. Crawford, Supervi.sor, Chemistry / Radiation Protection Training l T. Durkarski, Supervisor System Chemistry, Chemistry I
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W. Gates, Vice President, Nuclear R. Hamilton,-Manager, Chemistry B. Hansher, Supervisor, Licensing l R. Haug, Corporate Health Physics j J. Hoffman, Chemist, Chemistry j B. Mierzejewski, System Engineer, Safety Ventilation Systems i R. Phelps, Acting Division Manager, Nuclear Engineering M. Puckett, Manager, Radiation Protection C. Schaffer, System Engineer, Radiation Monitoring
. J. Shipman, Chemist, Chemistry C. Simons, Specialist, Nuclear Safety Review Group I J. Solymossy, Plant Manager D. Spires,~ Manager, Quality Assurance M.Tesar, Division Manager, Nuclear Support )
J. Tills, Assistant Plant Manager j l
NRC ;
- W. Walker, Senior Resident inspector I
LIST OF INSPECTION PROCEDURES USED IP 84750 Radioactive Waste Treatment and Effluent and Environmental Monitoring
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LIST OF DOCUMENTS REVIEWED ORGANIZATION CHARTS Chemistry Department October 1998 CHEMISTRY TRAINING DOCUMENTATION Chemistry department training records Training Program Master Plan - 13, Section 7.3, " Chemistry Shift Technician Qualification Guide," Revision 29, dated August 29,1998 Performance Evaluation Checklists RE-AD-0002 " Steam Generator Release Permits," Revision 4 RE-AD-0004 " Waste LiquM Release Permits," Revision 3
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RE-AD-0005 " Waste Gas Decay Tank Release Permits," Revision 3 RE-AD-0006 " Containment Purge Release Permits," Revision 4 RE-AD-0007 " Continuous Auxiliary Building Exhaust Stack Release Summary,"
Revision 3
' RE-AD-0008 " Continuous Laboratory and Radioactive Waste Processing Building Exhaust Stack Release Summary," Revision 3 RE-CP-0001 " Liquid Process Monitor Calibrations," Revision 3
' RE-CP-0002 " Gaseous Process Monitor Calibrations," Revision 3 RE-SMP-0001 ' Waste Liquid Sampling," Revision 4
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RE-SMP-0002 ' Waste Gas Sampling," Revision 4 l RE SMP-0003 " Airborne Effluent Sampling," Revision 3 SE-AD-0001 " Plant Effluent Composite Sampling," Revision 3 l
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-3-OPERATIONS TRAINING DOCUMENTATION Operations department training records Equipment Operator Nuclear Auxiliary Qualification Manual, Revision 2, dated April 1996 Lesson Plan (0443-12) " Waste Disposal Gas System," Revision 5 Lesson Plan (0443-13) " Liquid Radioactive Waste Disposal System," Revision 8 Lesson Plan (1920-40) " Radiation Detection and Measurement" Revision 3 OUALITY ASSURANCE DOCUMENTS Quality Assurance Internal Audit Schedules for 1997,1998, and 1999 Quality Assurance Surveillance Schedules for 1997,1998, and 1999 Ouality Assurance Plan Section 10.1," Audit Program and Audits," Revision 8 Safety Audit Review Committee Audit Report #63A," Radiological Effluent Program," performed '
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January 7-21,1997 Ouality Assurance Surveillance Report B1-98-01, " Radiological Effluent Report," performed May 25 through June 1,1998 Self Assessment i
" Chemistry Department Self Assessment," performed July 14-18,1997 l Vendor Audits ,
l NUPIC Joint Quality Assuraace Audit of Teledyne Brown Engineering-Environmental Services, l conducted April 21-24,1997 ;
NUPIC Joint Quality Assurance Audit of NCS Corporation, performed November 18-22,1996 PROCEDURES l l
Operations Procedures OI-WDL-3 " Liquid Waste Disposal Release," Revision 13, June 8,1998 l OI WDG-2 " Waste Gas Disposal System Release," Revision 14, March 27,1997
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Chemistry Administrative Procedures l l
CH-AD-0010 "Compositing Guidelines," Revision 7, August 12,1997 CH-AD-0021 " Containment Release Permit and Summary," Revision 17, August 6,1998 j CH-AD-0022 " Waste Liquid Release Permit and Summary," Revision 14, April 1,1998 CH-AD-0024 " Steam Generator Release Permit," Revision 10, April 17,1998
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CH AD-0026 " Auxiliary Building Exhaust Stack Release Summary," Revision 6, :
January 15,1998 I l
CH-AD-0027 " Waste Gas Decay Tank Release Permit and Summary," Revision 9, April 1,1998 CH-AD-0028 " Condenser Off-Gas Release Summary," Revision 3, February 15,1995 CH-AD-0029 " Quarterly Cumulative Dose Calculations from Radioactive Effluents," '
l Revision 3, October 25,1996 CH-AD-0045 " Laboratory and Radioactive Waste Processing Building Exhaust Stack Release Summary," Revision 4, February 15,1995 CH-AD-0050 " Annual Radioactive Effluent Release Report," Revision 3, April 1,1998
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Chemistry Samolino Procedures CH-SMP-RE-0003 " Monitor Tank (WD-22A and WD-22B) Sampling," Revision 0, January 7,1992 CH-SMP-RE-0004 " Containment Atmosphere Sampling Radioactive Gas Particulate and I
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lodine Using Either RM-050/051 or RM-052," Revision 8, July 20,1995
. CH-SMP-RE-0008 " Waste Gas System (Al-110) Sampling," Revision 5, April 25,1995 CH-SMP-RE-0013 " Auxiliary Building Exhaust Stack Sampling," Revision 10, April 22,1997 I CH-SMP-RE-0015 " Condenser Off-Gas Sampling," Revision 4, November 7,1997 CH-SMP-RE-0018 " Laboratory and Radioactive Waste Processing Building Exhaust Stack Sampling," Revision 15, January 21,1997 Chemistry Analvtical Procedures CH-ANL-RA-0001 " Determination of Gamma isotopic Activity," Revision 9, April 1,1998 CH-ANL-RA-0014 " Determination of Gross Alpha and Beta Using the Abacus 560A-1 i Sample Counter," Revision 1, June 19,1996 l
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l l FC-211 " Waste Liquid Tank Release Permit " Revision 23 January 6, 1998
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FC 212 " Containment Release Permit," Revision 32, July 30,1998 ( FC 213 " Waste Gas Decay Tank Release Permit," P.evision 26, July 30,1998
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t FC-261 " Condenser Air Ejector Release Summary," Revision 6, September 4,1997 FC-287 " Steam Generator Release Summary," Revision 7, August 29,1996 FC-293 " Auxiliary Building Exhaust Stack Release Summary," Revision 9, September 4,1997 FC-339 " Monitor Tank Releases Monthly Composite Data Sheet," Revision 13, l
September 4,1997 FC-341 " Steam Generator Blowdown and Secondary Releases Monthly Composite Data Sheet," Revision 13, September 4,1997 l FC-421 " Quarterly Cumulative Dose Contributions from Radioactive Effluents,"
Revision 5, September 4,1997 FC-745 " Laboratory and Radioactive Waste Processing Building Exhaust Stack Release Summary," Revision 4, September 4,1997 l
SURVEILLANCE TESTS CH-ST-RM-5400 " Steam Generator "A" Blowdown Liquid Radiation Monitor, RM-054A, Primary Calibration," Revision 3, January 15,1998 CH-ST-RM-5401 " Steam Generator "B" Blowdown Liquid Radiation Monitor, RM-054B, Primary Calibration," Revision 3, January 15,1998 CH-ST-RM-5500 " Overboard Waste Discharge Liquid Radiation Monitor, RM-055, Primary Calibratien," Revision 1, January 15,1998 IC-ST-RM-5001 " Quarterly Functional Test of Process Radiation Monitors," Revision 4,
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October 17,1996 IC-ST-RM-5200 " Electronic and Secondary Calibration of Radiation Monitor RM-052,"
Revision 7, October 11,1996 l IC-ST-RM-5400 " Electronic and Secondary Calibration of Radiation Monitor RM-054A,"
l Revision 7, August 14,1998 IC-ST-RM-5401 " Electronic and Secondary Calibration of Radiation Monitor RM-054B,"
f Revision 7, August 14,1998 l
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-6-IC-ST-RM-5500 " Electronic and Secondary Calibration of Radiation Monitor RM-055," ,
Revision 5, February 6,1997 1
' IC-ST-RM-5700 " Electronic and Secondary Calibration of Radiation Monitor RM-057,"
- Revision 3, October 11,1996 IC-ST-RM-6200 " Electronic and Secondary Calibration of Radiation Monitor RM-062," [
Revision 7, October 11,1996 MISCELLANEOUS DOCUMENTS Selected liquid radioactive waste batch release permits Selected waste gas decay and containment release permits Effluent radiation monitor surveillance test records .
. Engineered-safety-feature ventilation filter systerns surveillance test records .
t Annual Radioactive Effluent Release Reports - 1996 and 1997 l "Offsite Dose Calculation Manual," Revision 8, January 15,1998 :
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"Offsite Dose Calculation Manual," Revision 9, June 12,1998 !
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