IR 05000285/1996011
| ML20134L978 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 11/19/1996 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20134L972 | List: |
| References | |
| 50-285-96-11, NUDOCS 9611220140 | |
| Download: ML20134L978 (22) | |
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ENCLOSURE U.S. NUCLEAR REGULATORY COMMISSION REGION IV '
Docket No.: 50-285 License No.: DPR-40 Report No.: 50-285/96-11 Licensee: Omaha Public Power District Facility: Fort Calhoun Nuclear Station Location: Fort Calhoun Station P.O. Box 399, Hwy. 75 - North of Fort Calhoun Fort Calhoun, Nebraska Dates: October 21-25,1996 Inspector: J. Blair Nicholas, Ph.D., Senior Radiation Specialist Plant Support Branch Approved By: Blaine Murray, Chief, Plant Support Branch Division of Reactor Safety Attachment: Supplemental Information 9611220140 961119 PDR ADOCK 05000285 O PM
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EXECUTIVE SUMMARY
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Fort Calhoun Nuclear Station
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NRC Inspection Report 50-285/96-11
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This routine, announced inspection focused on the licensee's radiological waste effluent management progra I l
i Enaineerina l L * Reviewed practices, procedures, and parameters were consistent with commitments Updated Safety Analysis Report (Section E2.1).
Plant Support
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- The liquid and gaseous radioactive waste effluent management programs were
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properly implemented (Section R1.1).
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- Good sample handling techniques were used by the licensee while collecting and i handling the air particulate filter samples, iodine charcoal cartridge samples, and noble gas samples (Section R1.1).
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- The safety-related air cleaning ventilation systems were properly maintained and tested (Section R1.2). i l
- The radiochemistry counting room was equipped with state-of-the-art analytical instrumentation to perform the required analyses. The analytical instrumentation was properly maintained, tested, and calibrated (Section R2.1).
- Liquid and gaseous radioactive waste management systems were properly installed and operated (Section R2.1). ;
i e All liquid and gaseous effluent radiation monitoring instrumentation were operable ;
and properly maintained, tested, and calibrated (Section R2.2). i
- Implementing procedures for the liquid and gaseous radioactive waste effluent management programs provided proper guidance. A good Annual Radioactive Effluent Release Report for 1995 was submitted in a timely manner (Section R3.1).
- Chemistry personnel and nuclear equipment operators had an excellent understanding of the radioactive liquid and gaseous waste management procedures, i D'fsite Dose Calculation Manual requirements, and regulatory requirements (Sechon R4).
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- Training and qualification programs for the chemistry staff and the nuclear j equipment operators were properly implemented. A trained and qualified staff for l conducting radioactive waste effluent processing and release operations was I maintained (Section RS.1).
- The chemistry technical staff had experienced very little change during the past
.1 % years (Section R6).
- Oversight of the radioactive waste effluent management program was good (Section R7.1).
- A good self-assessment of the chemistry department's activities including radioactive waste effluent activities was performed (Section R7.1).
- The quality assurance audit of the contractor used to perform surveillance testing of the safety-related air cleaning ventilatinn systems was comprehensive and provided good evaluatio,n and oversight of the contractor's performance (Section R7.2).
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- Report Details '
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Summary of Plant Status
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The plant was shutdown for a refueling outage during the entire inspection period. There
, were no operational occurrences that impacted the inspection.
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Ill. Enaineerina
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E2 Engineering Support of Facilities and Equipment E Uodated Safety Analysis Report Review (USAR)
, Insoection Scope
i The inspector reviewed selected topics presented in the USAR to ensure agreement with any commitments contained therein that pertained to the inspection.
. Observations and Findinas t
While performing the inspection discussed in this report, the inspector reviewed the
, applicable portions of the USAR that related to the areas inspected. The inspector i did not note any discrepancy between the USAR wording and the observed plant j practices, procedures, and/or parameter ;
- Conclusion Reviewed practices, procedures, and parameters were consistent with USAR commitment IV. Plant Support R1 Radiological Protection and Chemistry Controls R Radioloaical Waste Effluent Manaaement Proarams Insoection Scoce (84750)
Implementation of the liquid and gaseous radioactive waste effluent management programs, as described in the Technical Specifications and the Offsite Dose Calculation Manual, including radioactive effluent waste processing, radioactive effluent waste sampling and analyses, analyses sensitivities, analytical results, offsite dose results, and performance of required surveillance tests, were reviewe The inspector reviewed approximately 20 batch radioactive liquid waste effluent release permits for the period January through September 199 _ _ -
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IV. Plant Support R1 Radiological Protection and Chemistry Controls i
R1.1 Radioloaical Waste Effluent Manaaement Proarams Inspection Scope (84750)
Implementation of the liquid and gaseous radioactive waste effluent management programs, as described in the Technical Specifications and the Offsite Dose Calculation Manual, including radioactive effluent waste processing, radioactive effluent waste sampling and analyses, analyses sensitivities, analytical results, offsite dose results, and performance of required surveillance tests, were reviewe The inspector reviewed approximately 20 batch radioactive liquid waste effluent release permits for the period January through September 199 Observations and Findinas The inspector determined that the processing, sampling, and analyses of radioactive liquid waste effluents and the approve! and performance of batch radioactive liquid waste discharges were conducted in accordance with Offsite Dose Calculation Manual requirement Quantities of radionuclides released in the radioactive liquid waste effluents were within the limits specified in the Offsite Dose Calculation Manual. Offsite doses were calculated according to Offsite Dose Calculation Manual methodologies and were within regulatory limits. Required analyses of composite samples of batch radioactive liquid waste effluent releases for gross alpha, tritium, strontium-89, and strontium-90 were performed in accordance with Offsite Dose Calculation Manual requirement Selected gaseous waste effluent sample analyses for samples from the auxiliary building exhaust stack and the laboratory and radwaste building exhaust stack continuous releases for the period January 1996 through September 1996 were reviewed. The inspector verified that the sampling, analyses, and monitoring of the continuous discharges of radioactive gaseous effluents were conducted in accordance with Offsite Dose Calculation Manual requirements and station procedure Quantities of gaseous and airborne particulate radionuclides released were within the limits specified in the Offsite Dose Calculation Manual. Offsite doses were calculated according to Offsite Dose Calculation Manual methodologies and were within regulatory limits. Noble gas samples were collected and analyzed for principle gamma emitters and tritium in compliance with Offsite Dose Calculation
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l Manual requirements. Particulate effluent composite sample analyses for gross alpha, strontium-89, and strontium-90 were performed for each vent pathway in accordance with Offsite Dose Calculation Manual requirement l The inspector observed a chemist collect air particulate filter samples, iodine charcoal cartridge samples, noble gas samples, and tritium sample of the containment atmosphere from the radiation monitor sample point (RM-052) and the auxiliary building exhaust stack radiatior monitor sample point (RM-062) on October 22,1996. The inspector noted that the chemist used the following good sample handling techniques when removing the air particulate filter samples and l iodine charcoal cartridge samples from the sample holder devices and while collecting the noble gas samples.
' * The chemist used gloves to handle the air particulate filter, iodine charcoal cartridge, noble gas, and tritium sample * The chemist placed the air particulate filter samples and the iodine charcoal cartridge samples into plastic bags and sealed the bags with a twist tie for transfer to the radiochemistry counting room for analyse The inspector observed a chemist perform the radiochemistry analyses (principal gamma emitters and tritium) on the samples in the radiochemistry counting roo The inspector noted that the chemistry technician used a poor sample counting geometry when analyzing the air particulate filter sample. The air particulate filter sample was too large in diameter to fit smoothly in the bottom of the stainless steel planchet used for the counting geometry for determining principal gamma emitter The inspector's concern was the reproducibility of the air particulate filter's counting geometry. The inspector discussed the observation with the licensee during the inspection, and the licensee stated that they were aware of the potential problem and had evaluated the counting geometry and determined that the present practice of placing the oversized air particulate filter paper in the stainless steel planchet did not introduce any significant errors in the analysis result The inspector observed a chemist prepare the containment purge permit. All aspects of the containment atmosphere sampling, analyses, and preparation of the containment purge permit were performed in accordance with approved procedure c. Conclusions The liquid and gaseous radioactive waste effluent management programs were properly implemented. Good sample handling techniques were used by the licensee while collecting and handling the air particulate filter samples, iodine charcoal cartridge samples, and noble gas samples from the containment atmosphere sampler and the auxiliary building vent sampler associated with the respective effluent radiation monitor _- - _
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R1. 2 Safetv-Related Air Cleanina Systems l
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l J Inspection Scope (84750) l Surveillance and test results for the safety-related air cleaning ventilation systems testing program were reviewed to determine agreement with the commitments in
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the Updated Safety Analysis Report and compliance with the requirements in the Technical Specifications.
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The inspector verified that the surveillance tests provided for the required periodic functional checking of the safety-related air cleaning ventilation l systems' components, evaluation of the high efficiency particulate air filters and l
- activated charcoal adsorbers, and the in-place filter testing of the control room
air treatment system (VA-64A and 64B), the spent fuel storage pool area ventilation system (VA-66), and the safety injection pump room ventilation system (VA-26A
- and 268). Since some of the surveillance tests were only required to be per'ermed i at an 18-month frequency, the inspector reviewed the last surveillance tests' results ,
for each of the safety-related air cleaning ventilation systems named above and j verif ted that the previous two surveillances were performed at the required j
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18-month frequency. The in-place filter testing and activated charcoal laboratory j
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surveillance tests were performed in accordance with approved procedures by a
- contmct laboratory, and all test results were verified to be within Technical l Specification limits. The inspector noted that the Technical Specification I requirement for testing the various air cleaning ventilation systems' activated
- charcoal adsorber material after every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of operation following previous laboratory testing was being tracked by the control room on Surveillance Test Procedure OP-ST-SHIFT-0001," Operations Technical Specification Shift Surveillance Log."
The inspector performed a walkdown visual inspection with the system engineer of the following ventilation systems: the control room air treatment system, the spent fuel storage pool area ventilation system, and the safety injection pump room ventilation system. The visual walkdown was performed in accordance with Section 5.5 of American Society of Mechanical Engineers ASME N510-1989. The walkdown externalinspection of the identified ventilation systems indicated no visual problems with the systems' housing and ducts, local instrumentation, and filter unit components visual from the outside of the ventilation units. All doors were bolted tightly closed and all gaskets were in place and not leaking. No external damage to the ventilation units was identified. All filter housings and ducts appeared to be well maintained. The areas surrounding the ventilation units were clean, free of debris, and adequately lighted to provide for visualinspection of housings and component .
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-8- Conclusions The safety-related air cleaning ventilation systems conformed to the commitments in the Updated Safety Analysis Report and met the Technical Specification requirements. The safety-related air cleaning systems were tested in accordance with Technical Specification requirements, and all test results were within Technical l
Specification limit '
R2 Status of Chemistry Facilities and Equipment R2.1 Radiochemistry Countino Room and Radioactive Waste Effluent Processina Systems Inspection Scope (84750)
The radiochemistry counting room and associated analyticalinstrumentation were inspected to verify if adequate calibration and quality control programs were implemented. The radioactive liquid and gaseous waste processing equipment were inspected to ensure agreement with the Updated Safety Analysis Repor Equipment inspected in the auxiliary building and the radwaste building included the waste monitor tanks and the liquid waste effluent processing equipment. The inspector reviewed the implementation of the calibration and quality control programs for the analytical instrumentatio Observations and Findinas The radiochemistry counting room maintained sufficient state-of-the-art analytical instrumentation to perform the required radiochemistry analytical measurements of the radioactive waste effluents. The analyticalinstrumentation was properly maintained and calibrate The liquid radioactive waste processing and storage systems were installed as described in the Updated Safety Analysis Report and were operated in accordance with station procedure The gaseous radioactive waste processing and storage system was installed as described in the Updated Safety Analysis Report and was operated in accordance with station procedure No raajor equipment or design modifications were made to the liquid or gaseous radioactive waste management systems during 1995 and the first half of 1996.
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-9- Conclusions The radiochemistry counting room was equipped with state-of-the-art analytical instrumentation to perform the required analyses. The analytical instrumentation was properly rnaintained, tested, and calibrated. Liquid and gaseous radioactive waste management systems were installed and operated properl R2.2 Liauid and Gaseous Effluent Radiation Monitors I Inspection Scope (84750)
The liquid and gaseous effluent radiation monitors were inspected for operation, calibration, and reliability. The containment atmosphere, auxiliary building exhaust stack ventilation system, and laboratory and radwaste building exhaust stack
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ventilation system process radiation monitors' local sample points were inspecte Observations and Findinas l
The inspector reviewed the liquid and gaseous radioactive waste effluent radiation monitor source check, channel check, channel functional test, and channel l calibration records, for the time period January 1995 through September 1996, to determine agreement with the surveillance requirements specified in Offsite Dose Calculation Manual Table 2- All records and surveillance tests reviewed indicated that the liquid and gaseous radioactive waste effluent monitoring instrumentation was properly maintained, tested, and calibrated in compliance with the surveillance requirements specified in j the Offsite Dose Calculation Manua Conclusion All liquid and gaseous effluent radiation monitoring instrumentation was operable and properly maintained, tested, and calibrated in compliance with the surveillance requirements specified in the Offsite Dose Calculation Manua R3 Radioactive Waste Effluent and Chemistry Procedures and Documentation
R3.1 Radioactive Waste Effluent Procedures, Offsite Dose Calculation Manual, and Annual Radioactive Effluent Release Reports Inspection Scope (84750)
Procedures for the sampling, analysis, and release of radioactive liquid and gaseous waste effluents were reviewed. Revisions to the Offsite Dose Calculation Manual were reviewed. Annual reports concerning radioactive waste effluent releases were reviewe . , . -- - .=._..-.. _- ~ - - _- -- _
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The inspector verified that the procedures for batch release of liquid and gaseous radioactive waste effluents provided proper guidance regarding sampling, tank recirculation, analyses, release limits, monitoring, and approval The radioactive waste effluent program's implementing procedures described the
- responsibilities for collection and analyses of liquid and gaseous radioactive waste 4 effluent samples. The procedures were written with sufficient detail to effectively
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conduct the required radioactive waste effluent program activities. The inspector ;
reviewed the licensee's sample collection procedures and identified no concern '
The Annual Radioactive Effluent Release Report for 1995 included a summary of the j quantities of radioactive liquid and gaseous waste effluents, a summary of j meteorological data concurrent with the release of airborne effluents, an assessment of the radiation doses from the radioactive liquid and gaseous effluents released to i the environment during each calendar quarter, and changes to the Offsite Dose Calculation Manual and the Process Control Program. The Annual Radioactive I Effluent Release Report was written in the format described in NRC Regulatory Guide 1.21, Revision 1, June 1974, and contained the information required by the Offsite Dose Calculation Manua No unplanned releases of radioactive liquid or gaseous waste were reported during ,
1995 and the first half of 199 I Conclusions implementing procedures for the liquid and gaseous radioactive waste effluent management programs provided proper guidance. Changes to the Offsite Dose Calculation Manual and Process Control Program were properly documented. A good Annual Radioactive Effluent Release Report for 1995 was submitted in a timely manner and contained the required information presented in the required forma R4 Staff Knowledge and Performance Insoection Scope (84750)
The chemistry manager, chemistry supervisors, chemists, chemistry technicians, and nuclear equipment operators were interviewed with regard to regulatory and Offsite Dose Calculation Manual requirements for the implementation of the liquid and gaseous radioactive waste effluent management program .
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Chemistry personnel and nuclear equipment operators were knowledgeable of the l programmatic procedures, Offsite Dose Calculation Manual requirements, and regulatory requirements and maintained a high level of performance. Batch radioactive liquid and gaseous waste effluent releases and continuous radioactive gaseous waste effluent releases were properly performed during the time period January 1995 through August 199 c, Conclusion Chemistry personnel and nuclear equipment operators had an excellent understanding of the radioactive liquid and gaseous waste management procedures, Offsite Dose Calculation Manual, and regulatory requirement R5 Staff Training and Qualification R 5.1 Trainina and Qualification of Chemistry Personnel and Nuclear Eauipment Ooerators Inspection Scope (84750)
Training and qualification programs for chemists, chemistry technicians, and nuclear equipment operators involved with conducting the radioactive waste effluent management programs were reviewed. Training and qualifications of the chemistry technical staff and the nuclear equipment operators were verified, Observations and Findinas The inspector verified that all chemists and all but one recently hired chemistry technician had completed all of the training required to perform radioactive waste management program activities and were shift qualifie The inspector verified that 16 nuclear equipment operators were trained and qualified to conduct radioactive waste effluent batch releases and operate radioactive waste processing equipmen Conclusions Training and qualification programs for chemists, chemistry technicians, and nuclear equipment operators were properly implemented. The chemistry department and the operations department had well trained and qualified staffs for conducting radioactive waste effluent processing and release operation ~.
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The organization, staffing, and assignment of the radioactive waste effluent management program responsibilities were reviewed. Administrative and chemistry dc,-artmental procedures were reviewed for the assignment of responsibilities for th management and implementation of the radioactive waste effluent management progra Observations and Findinos The inspector verified that the chemistry and operations organizations and staff were responsible for the implementation of the radioactive waste effluent management program. The inspector determined that the duties and responsibilities for implementing the radioactive waste effluent management program, rs specified in the procedures, were implemente The inspector reviewed the staffing of the chemistry and operations organizations and determined that they were adequately staffed. There had been very little change in the chemistry technical staff during the past 1 % years. The chemistry department lost one senior chemistry technician and gained a chemistry technicia i .C_o",clusions The chemistry and operations organizations and staffing met Technical Specification requirements. The chemistry technical staff had experienced very little change during the past 1 % year R7 Quality Assurance in Chemistry and Radiological Waste Effluents Activities R7.1 Radioactive Waste Effluent Quality Assurance Proaram Inspection Scope (84750)
) The quality assurance audit and surveillance programs regarding the radioactive l waste effluent management program activities were reviewed. The review included the audit, surveillances, and self-assessment performed during 1994-1996. The inspector reviewed a self-assessment of the chemistry department's activitie Observations and Findinas The review of the quality assurance audit schedule dated September 13,1996, indicated that the audit of the radioactive waste effluent management program was scheduled on a 24-month frequency and performed during even numbered years in compliance with Technical Specification 5.5.2. . ._ . _ _ _ .
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-13-Reports of the quality assurance audit and surveillances, performed during the period January 1994 through September 1996, of the areas related to the performance of the radioactive waste effluent management program were performed in accordance with the quality assurance procedures by qualified auditors and a misted by technical specialists. The audit and surveillances of the radioactive waste effluent management program were of good quality and provided satisfactory oversight and evaluation of the licensee's performance in implementing the radioactive waste effluent management program and met the Technical Specification requirement The inspector reviewed a self-assessment of the chemistry department's activities, Conclusions Oversight of the radioactive waste. effluent management program was good. The quality assurance audit and surveillances of the radiological waste effluent management program activities were technically comprehensive and provided good program evaluation and oversight. A good self-assessment of the chemistry department's activities including radioactive waste effluent activities was performe ,
R7.2 Quality Assurance Proaram for Contractors Inspection Scone (84750)
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The quality assurance audit program regarding contractors performing surveillance activities involving the radioactive waste effluent program and safety-related air cleaning ventilation systems was reviewe Observations and Findinos The licensee used a contractor laboratory to perform required radiochemistry analyses of radioactive waste effluent composite samples and another contractor to perform in-place filter testing and laboratory charcoal adsorber analyses on the station's safety-related air cleaning ventilation systems. An audit of the radiochemistry laboratory, used to perform radiochemistry analyses of radioactive waste effluent samples, had not been performed at the time of the inspection but was scheduled for January 1997. An audit of the safety-related air cleaning ventilation systems' filter testing contractor was performed by a Nuclear Procurement issues Committee audit team, led by Washington Public Power Supply System on November 15 17,1994. The licensee used the audit to evaluate the performance of the contractor in performing the surveillance testing requirements and to retain its current status on the licensee's routine suppliers list. The inspector reviewed the audit performed on the contractor and determined that the audit was satisfactory to evaluate the contractor's abilities to perform the Technical Specification required testing and surveillance activitie _ __. . ._ . . - . _ . . . _ ._ _ _ _ _ _ _ _ _ . _ . . _ . _ _. . .. . . _ _ . _ _ . . . .
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The quality assurance audit of the contractor used to perform surveillance testing of the safety-related air cleaning ventilation systems was comprehensive and provided j good evaluation and oversight of the contractor's performance.
V. Manaaement Meetinas
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X1 Exit Meeting Summary I
a The inspector presented the results of the inspection to members of licensee
! management at the conclusion of the inspection on October 25,1996. The j licensee acknowledged the findings presented.
!~ The inspector asked the licensee whether any materials examined during the inspection should be considered proprietary. No proprietary information was l identified.
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l ATTACHMENT SUPPLEMENTAL INFORMATION PARTIAL LIST OF PERSONS CONTACTED Licensee G. Cook, Supervisor, Nuclear Licensing J. Chase, Plant Manager T. Patterson, Division Manager, Nuc. ear Operations J. Tills, Manager, Nuclear Licensing R. Haug, Corporate Health Physicist S. Gebers, Manager, Radiation Prott ction D. Spires, Manager, Chemistry C. Brunnert, Manager, Quality Assurance / Quality Control R. Conner, Manager, Training J. Gasper, Manager, Nuclear Projects NRC K. Johnston, Visiting Senior Resident inspector l LIST OF INSPECTION PROCEDURES USED IP 84750 Radioactive Waste Systems: Water Chemistry; Confirmatory Measurements and Radiological Environmental Monitoring LIST OF DOCUMENTS REVIEWED Oraanization Charts l
Chemistry Department - May 1996 Quality Assurance Documents Quality Assurance / Safety Audit Review Committee Internal Audit Schedule - 1996, Revision 4, dated August 1996 Quality Assurance Surveillance Schedule - 1996
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Quality Assurance Plan Section 10.1, " Audit Program and Audits," Revision 7, dated July 10,1996
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Quality Assurance Audits Safety Audit Review Committee Audit Report #63A, " Radiological Effluent Technical Specifications," conducted November 8 through December 6,1994 i
i Safety Audit Review Committee Audit Report #49, " Chemistry Control," conducted ;
July 25 through August 16,1994 I Safety Audit Review Committee Audit Report #49, " Chemistry Control," conducted July 8 through July 22,1996 Safety Audit Review Committee Audit Report #62," Performance Training and Qualification of Facility Staff," conducted June 13-28,1995 Safety Audit Review Committee Audit Report #62, " Performance Training and Qualification j of Facility Staff," conducted April 15 through May 20,1996
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Quality Assurance Surveilhnces ,
Quality Assurance Surveillance Report, B1-95-1," Radiological Effluent Report,"
conducted July 13-21,1995 Quality Assurance Surveillance Report, B1-96-1, " Radiological Effluent Report,"
conducted August 23 through September 3,1996 Quality Assurance Surveillance Report, C-95-1, " Process Monitors," conducted August 23 through September 3,1996 Vendor Audits NUPIC Joint Quality Assurance Audit of NCS Corporation, conducted November 15-17,1994 ,
Self Assessment Chemistry Department Self Assessment CY-95-01, dated November 1995 Procedures Operations Procedures Ol-WOL-3 " Liquid Waste Disposal Release," Revision 12, July 18,1995 OI-WDG-2 " Waste Gas Disposal System Release," Revision 12, March 17,1995
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-3-Chemistrv Procedures CH-AD-0001 " Chemistry Program Plan," Revision 3, October 4,1996 ;
CH-AD-0003 " Plant Systems Chemical Limits and Corrective Actions," Revision 22, j October 4,1996 ,
CH-AD-0004 " Guidelines for Shutdown and Startup Primary Chemistry," Revision 6, j September 12,1996 i l
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CH-AD-0010 "Compositing Guidelines," Revision 6, June 22,1995 CH-AD-0011 " Sampling Guidelines," Revision 1, February 15,1995 CH-AD-0021 " Containment Release Permit and Summary," Revision 11, August 20,1996 CH-AD-0022 " Waste Liquid Release Permit and Summary," Revision 11, August 29,1996 CH-AD-0024 " Steam Generator Release Permit," Revision 7, August 29,1996 CH-AD-0025 " Steam Generator Release Summary," Revision 5, February 15,1995 CH-AD-0026 " Auxiliary Building Exhaust Stack Release Summary," Revision 5, February 15,1995 CH-AD-0027 " Waste Gas Decay Tank Release Permit and Summary," Revision 8, March 1,1995 CH-AD-0028 " Condenser Off-Gas Release Summary," Revision 3, February 15,1995 CH-AD-0029 " Quarterly Cumulative Dose Calculations from Radioactive Effluents,"
Revision 2, February 15,1995
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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 1, April 19,1996 CH-SMP-RE-0003 " Monitor Tank (WD-22A and WD-228) Sampling," Revision 0, January 7,1992 CH-SMP-RE-0004 " Containment Atmosphere Sampling Radioactive Gas Particulate and 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
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- . CH-SMP-RE-0013 " Auxiliary Building Exhaust Stack Sampling," Revision 8, 8 July 20,1995
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- CH-SMP-RE-0014 . " Condenser Off-Gas / Tritium Sampling," Revision 2, August 11,1994 ,
CH-SMP-RE-0015 " Condenser Off-Gas Sampling," Revision 3, August 11,1994 CH-SMP-RE-0018 " Laboratory and Radioactive Waste Processing Building Exhaust Stack ;
i Sampling," Revision 14, October 19,1995 ;
k CH-ANL-RA-0001 " Determination of Gamma Isotopic Activity," Revision 7, August 29,1996 l CH-ANL-RA-0007 " Determination of Tritium," Revision 3, June 8,1995
', CH-ANL-RA-0014 - " Determination of Gross Alpha and Beta Using the Abacus 560A-1
Sample Counter," Revision 1, June 19,1996 !
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Chemistrv Forms 1
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- FC-211 " Waste Liquid Tank Release Permit," Revision 21, August 29,1996 ;
- I FC-212 " Containment Release Permit," Revision 30, August 29,1996- 2
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j FC-213 " Waste Gas Decay Tank Release Permit," Revision 24, August 29,1996 -j i -
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i j FC-261 " Condenser Air Ejector Release Summary," Revision 5, July 1,1993
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j FC-287 " Steam Generator Release Summary," Revision 7, August 29,1996 I
i FC-293 " Auxiliary Bu;lding Exhaust Stack Release Summary," Revision 8,
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I FC-339 " Monitor Tank Releases Monthly Composite Data Sheet," Revision 12, August 29,1996 FC-341 " Steam Generator Blowdown and Secondary Releases Monthly Composite Data Sheet," Revision 12, August 29,1996 FC-421 " Quarterly Cumulative Dose Contributions from Radioactive Effluents,"
Revision 4, May 25,1993 FC-745 " Laboratory and Radioactive Waste Processing Building Exhaust Stack Release Summary," Revision 3, September 30,1996
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Trainino Documentation s
" Equipment Operator Nuclear - Auxiliary Qualification Manual," Revision 5, dated
December 1992 Training Program Manual Procedure - 13, Section 7.8, " Chemistry Shift Technician Qualification' Guide," Revision 23, dated September 13,1996
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Performance Evaluation Checklist, RE-AD-0002, " Steam Generator Release Permits,"
i Revision 1 Performance Evaluation Checklist, RE-AD-0004," Waste Liquid Release Permits,"
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Revision 1 Performance Evaluation Checklist, RE-AD-0005," Waste Gas Decay Tank Release Permits,"
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Revision 1 J
Performance Evaluation Checklist, RE-AD-0006," Containment Purge Release Permits,"
. Revision 1
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i Performance Evaluation Checklist, RE-AD-0007," Continuous Auxiliary Building Exhaust Stack Release Summary," Revision 1 Performance Evaluation Checklist, RE-AD-0008," Continuous Laboratory and Radioactive
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Waste Processing Building Exhaust Stack Release Summary," Revision 1 Performance Evaluation Checklist, RE-CP-0001, " Liquid Process Monitor Calibrations,"
Revision 1 Performance Evaluetion Checklist, RE-CP-0002," Gaseous Process Monitor Calibrations,"
Revision 1 Performance Evaluation Checklist, RE-SMP-0001," Waste Liquid Sampling," Revision 1 Performance Evaluation Checklist, RE-SMP-0002," Waste Gas Sampling," Revision 1 Performance Evaluation Checklist, RE-SMP-0003," Airborne Effluent Sampling," Revision 1 Performanco Ev::!uation Chacklist, RE-AD-0001," Plant Effluent Composite Sampling,"
Revision 1 Chemistry Department Qualification Matrix Non-Licensed Operator Qualification Matrix
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Surveillance Tests CH-ST-BD-0001 " Steam Generator Blowdown Weekly Gamma, Noble Gases,1-131, and DEI Activities," Revision 3, May 25,1993 I I
i CH-ST-BD-0003 " Steam Generator Blowdown Composite Tritium and Alpha," i Revision 4, August 30,1996 l CH-ST-BD-0004 " Steam Generator Blowdown Composite Strontium-89 and Strontium-90," Revision 3, May 25,1993 )
l CH-ST-CE-0001 " Condenser Air Ejector Sampling and Determination for Gamma
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Emitters," Revision 2, May 25,1993 -
CH-ST-CE-0002 " Condenser Air Ejector Sampling and Determination for Tritium," >
l Revision 3, May 25,1993 l
CH-ST-MM-0001 " Quarterly Determination of Doses from Liquid and Gaseous Releases," Revision 3, July 1,1993 CH-ST-RM-4300 " Laboratory and Radioactive Waste Processing Building Exhaust Stack Gas Radiation Monitor, RM-043, Primary Calibration," Revision 1, May 23,1995 CH-ST-RM-5000 " Containment Particulate Radiation Monitor, RM-050, Primary Calibration," Revision 10, July 15,1996 CH-ST-RM-5100 " Containment Gas Radiation Monitor, RM-051, Primary Calibration,"
Revision 6, June 19,1996 CH-ST-RM-5200 " Auxiliary Building Exhaust Stack / Containment Gas Radiation Monitor, RM-052, Primary Calibration," Revision 6, June 4,1996 CH-ST-RM-5400 " Steam Generator "A" Blowdown Liquid Radiation Monitor, RM-054A, Primary Calibration," Revision 2, June 26,1996 CH-ST-RM-5401 " Steam Generator "B" Blowdown Liquid Radiation Monitor, RM-054B, Primary Calibration," Revision 2, June 26,1996 CH-ST-RM-5500 " Overboard Waste Discharge Liquid Radiation Monitor, RM-055, Primary Calibration," Revision 0, April 21,1994 CH-ST-RM-5700 " Condenser Off-Gas Radiation Monitor, RM-057, Primary Calibration,"
Revision 3, June 21,1996
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-7-CH-ST-RM-6200 " Auxiliary Building Exhaust Stack Gas, NRC Radiation Monitor, RM-062, Primary Calibration," Revision 3, May 23,1995 CH-ST-VA-0001 " Auxiliary Building Exhaust Stack Sampling and Analysis," Revision 9, July 30,1996 CH-ST-VA-0002 " Laboratory and Radioactive Waste Processing Building Exhaust Stack Sampling and Analysis," Revision 5, July 30,1996 CH-ST-VA-0004 " Auxiliary Building Exhaust Stack Composite Strontium-89 and Strontium-90," Revision 5, July 26,1994 CH-ST-VA-0005 " Chemistry and Radioactive Waste Processing Building Exhaust Stack Composite Strontium-89 and Strontium-90," Revision 2, May 25,1993
CH ST-WDL-0001 " Hotel Waste and Monitor Tank Release Composite for Tritium and Alpha," Revision 3, July 30,1996 CH-ST-WDL-0004 " Liquid Release Composites for Strontium-89 and Strontium-90," l Revision 3, May 25,1993 !
IC-ST-RM-5001 " Quarterly Functional Test of Pcocess Radiation Monitors," Revision 4, October 17,1996 IC-ST-RM-5051 " Electronic and Secondary Calibration of Radiation Monitors, RM-050 and RM-051," Revision 5, October 11,1996 IC-ST-RM-5200 " Electronic and Secondary Calibration of Radiation Monitor RM-052,"
Revision 7, October 11,1996 IC-ST-RM-5400 " Electronic and Secondary Calibration of Radiation Monitor RM-054A," Revision 5, October 11,1996 IC-ST-RM-5401 " Electronic and Secondary Calibration of Radiation Monitor RM-054B," Revision 5, October 11,1996 IC-ST-RM-5500 " Electronic and Secondary Calibration of Radiation Monitor RM 055,"
Revision 4, October 11,1996 IC-ST-RM-5700 " Electronic and Secondary Calibration of Radiation Monitor RM-057,"
Revision 3, October 11,1996
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IC-ST-RM-6200 " Electronic and Secondary Calibration of Radiation Monitor RM-062," l Revision 7, October 11,1996 I OP-ST-SHIFT-0001 " Operations Technical Specification Shift Surveillance Log,"
Revision 49, October 15,1995
, i Miscellaneous Documents ;
Selected Liquid Radioactive Waste Batch Release Permits Annual Operating Radioactive Effluent Report - 1995
"Offsite Dose Calculation Manual," Revision 6, dated March 15,1995
"Offsite Dose Calculation Manual," devision 7, dated December 19,1995 j
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