IR 05000382/1990006
| ML20042F245 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 04/13/1990 |
| From: | Murray B, Nicholas J, Wilborn L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20042F244 | List: |
| References | |
| 50-382-90-06, 50-382-90-6, NUDOCS 9005080039 | |
| Download: ML20042F245 (30) | |
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APPENDIX U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
NRC Inspection Report:
50-382/90-06 Operating License: NPF-38
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Docket: 50-382 Licensee:
Louiciana Power & Light Company (LP&L)
317 Baronne Street New Orleans, Louisiana 70160 Facility Name: Waterford Steam Electric Station, Unit 3-(Wat-3)
Inspection At: Wat-3 site, Killona, St. Charles Parish, Louisiana Inspection Conducted: March 26-30, 1990 Inspectors:
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+' > 90 J/B. Nicholas,SenibrRadiationSpecialist Dat'e
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Facilities Radiological Protection Section
/uunDhau eahe
. Wilbor//, Radiation Specialist Date Facilit9es Radiological Protection Section Approved:
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B.Murray,Chf'ef, Fact /1tiesRadiological 06te Protection Section (/
Inspection Summary Inspection Conducted March 26-30,1990 (Report 50-382/90-06)
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Areas Inspected:
Routine, unannounced inspection of the licensee's water l
chemistry and radiochemistry programs, including water chemistry and radiochemistry confirmatory measurements, and certain aspects of the
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l radioactive waste management and effluent control programs.
Results: The licensee had implemented a water chemistry program and radiochemistry program in accordance with NRC requirements. The water
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chemistry and radiochemistry programs were being conducted in accordance with Technical Specification (TS) requirements.
The licensee's chemistry staff had experienced a personnel turnover of approximately 30 percent during the past 24 months.
The licensee had performed comprehensive quality assurance (QA)
audits in the chemistry / radiochemistry area. The licensee's chemistry 9005080039 900427 PDR ADOCK 0D000382 O
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staffing, training, and qualification programs were adequate to support plant operations. The radiological confirmatory measurements results for the radiochemistry counting room indicated 100 percent agreement and for the health physics (HP) counting room showed 99 percent agreement which were consistent with the radiochemistry 100 percent agreement and the HP 94 percent agreement achieved during the last NRC inspection of this area in March 1988.
The results of the nonradiological water chemistry confirmatory measurements showed 100 percent agreement which indicated an improvement over the 90 percent agreement achieved during the previous NRC chemistry confirmatory measurements inspection in March 1988.
The licensee had implemented the radioactive waste management and effluent control programs in accordance with the Radiological Effluent Technical Specifications (RETS) and Offsite Dose Calculation Manual (ODCM).
The quantities of radionuclides released in liquid and gaseous effluents were within the limits specified in the RETS. Offsite doses had been calculated according to the ODCM and were within TS limits.
QA surveillances and audits had been performed as required and were technically comprehensive. The licensee had submitted their Semiannual Effluent Release Reports as per TS requirements.
Within the areas inspected, no violations or deviations were identified.
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Persons Contacted LP&L s
- J. R. McGaha, Plant Manager, Nuclear
- R. E. Allen, Plant Chemist
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D. E. Baker, Manager, Nuclear Operations Support and Assessments. (NOSA)
- T. P. Brennan, Manager, Design Engineering
- W. E. Day, Technical Compliance and Reporting / Event Analysis Reporting and Response Supervisor
- G. L. Dolese, Chemistry Supervisor T. J. Gaudet, Site Licensing Engineer
- P. M. Kelly, HP Supervisor
- W. T. LaBonte, Radiation Protection Superintendent
- L. W. Laughlin, Site Licensing Supervisor
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l all. C. Lesan, Radiological Engineer i
A. S. Lockhart, Manager, QA-Nuclear
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B. R. Loetzerich, Site Licensing Engineer l
- D. C. Madere, Chemistry Supervisor
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- M. L. Marler, HP Training Instructor l
- J. V. Messina, Secondary Chemistry Engineer
- D. F. Packer, Assistant Plant Manager, Operations and Maintenance i
R. J. Pollock, Acting QA Audit Supervisor l
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l P. V. Prasankumar, Assistant Plant Manager, Technical Services
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- S. Ramzy, HP Assistant Superintendent, Technical Support
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J. A. Ridgel, HP Assistant Superintendent, Operations i
- T. H. Smith, Plant Engineering Superintendent
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R. L. Stanley, Chemistry Training Instructor i
K. T. Walsh, Events Analysis Reporting and Response Engineer l
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- W. F. Smith, Senior Resident Inspector
- Denotes those present during the exit meeting on March 30, 1990.
2.
Followup on Previously Identified Inspection Findings (92701)
(Closed) Open Item (382/8914-01): NRC/NRR Review of DC-3000 10 CFR Part 50.59 Evaluation - This item was discussed in NRC Inspection Report 50-382/89-14 and involved the Office of Nuclear Reactor Regulation (NRR) review of the licensee's safety evaluation and accident analysis performed in compliance to 10 CFR Part 50.59 requirements in
conjunction with design changes (DC) -3000 and DC-3026 to the Gaseous l
Waste Management System. The inspectors discussed the DC's safety evaluation and accident analysis performed by the licensee with the facility's NRR project manager and determined that NRR had no concerns and '
the DC's 10 CFR Part 50.59 review had been performed in a_ proper manner.
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(Closed) Open item (382/8914-02):
NRC Review of Licensee Event Report
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(LER)89-011 - This item was discussed in_NRC Inspection
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Report 50-382/89-14 and involved the circumstances described in Potential Reportable Eient 89-065 and LER 89-011. The LER reported that the fuel handling building (FHB) normal ventilation radiation monitor "B" indicated zero process flow at 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> on May.16, 1989.
The licensee determined
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the root cause of this event to be an intermittent equipment failure, isolated to this monitor. The data base information items affecting sample and process flow readout from the monitor had been erased resulting
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in a zero process flow signal. The licensee tested the FHB normal'
ventilation exhaust radiation monitor "B" and did not find any problems.
The licensee reloaded the radiation monitor's data base and attempted to duplicate the original problem. The original problem could not be
duplicated. The licensee did not discover any hardware or software-problems. The inspectors reviewed the results of the licensee's testing of the monitor and determined that the licensee had performed their investigation of the problem satisfactorily as described in the LER The
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resident inspecters had closed the LER in NRC Inspection Report 50-382/50-34, 3.
Organization and Management Controls (84750)
The inspectors reviewed the licensee's organization, staffing, and staff functional assignments related to the water chemistry and radiochemistry programs and the radioactive liquid and gaseous effluent programs to determine agreement with commitments in Chapter 13 of the Updated Final Safety Analysis Report (UFSAR) and the requirements in Section 6.2 of the
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l The inspectors verified that the organizational structure of the Wat-3
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chemistry / radiochemistry section (C/RS) was as defined in the UFSAR and
TS. The C/RS staff assignments and management controls were reviewed for the assignment of responsibilities for the management and implementation of the Wat-3 chemistry / radiochemistry programs.
The-inspectors verified that the administrative control and program implementing responsibilities specified in the UFSAR and Wat-3 procedures were being implemented.
The inspectors reviewed the staffing of the Wat-3 C/RS and noted, since the previous NRC chemistry / radiochemistry inspection in March 1988, the secondary chemistry engineer and the radiochemistry engineer had left.
The secondary chemistry engineer had been replaced by an individual from the QA Division, but the radiochemistry engineer position remained vacant.
The licensee was actively recruiting to fill the vacancy.
The secondary chemistry section consisted of seven chemistry technician positions.
Six of these positions were occupied and one was vacant.
The licensee was actively recruiting to fill the vacancy.
The radiochemistry section consisted of seven chemistry technician positions. All of these positions were occupied; however, three had been recently filled with new personnel.
The inspectors determined that the vacant positions had not significantly affected the quality of performance of the C/RS.
The inspectors determined that the C/RS personnel turnover had been approximately
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30 percent in the past 24 months. The Wat-3 staffing appeared adequate to support the licensee's chemistry / radiochemistry program and was -determined.
to be in accordance with licensee commitments.
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No violations or deviations were identified.
4.
Training and Qualifications (84750)
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The inspecturs reviewed the licensee's training and qualification program for C/RS personnel including education and experience, adequacy and quality of training, employee knowledge, qualification requirements, and Institute of Nuclear Power Operations (INPO) accreditation to determine agreement with commitments in Chapter 13 of the UFSAR and compliance with the requirements in Sections 6.3 and 6.4 of the TS.
The-inspectors reviewed the education and experience of the present Wat-3 C/RS staff and determined that all but the three recently hired chemistry technicians met the experience qualification requirements of ANSI N18.1-1971. The inspectors also verified that all the C/RS personnel met the required qualifications specified in the UFSAR, TS, and position
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descriptions.
A review of shift staffing for the C/RS indicated that all shifts had a lead technician meeting the qualification requirements of ANSI N18,1-1971.
It was determined that the licensee had an adequate, qualified staff to meet shift staffing requirements.
The inspectors noted that of the 4 exempt and 13 nonexempt positions that were occupied, 7 were occupied with personnel who possessed a college degree in chemistry or a science-related field.
The inspectors reviewed the licensee's training program for C/RS personnel including a review of the chemistry training instructor's qualifications, training facilities, chemistry technician training procedure, chemistry.
technician training course descriptions, chemistry training schedules for i
1989 and 1990, and C/RS personnel training records.
The inspectors found that the licensee's chemistry training program was being implemented and documented in accordance with Wat-3 procedures.
It was determined that the Wat-3 nuclear training department had received INPO accreditation.
No violations or deviations were identified.
5.
Light Water Reactor Chemistry Control, Chemical Analysis, and
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Confirmatory Measurements (84750)
The inspectors reviewed the licensee's water chemistry control and analysis program including implementation of a water chemistry control
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program, water sampling, facilities and equipment, implementation of a quality control (QC) program for chemical measurements, and water chemistry confirmatory measurements to determine agreement with commitments in Chapters 5, 9, 10, and 11 of the UFSAR and compliance with the requirements in Sections 3/4.4.6, 6.8.1 and 6.8.4 of the TS.
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The. inspectors' review of the water cheralstry program found that the licensee had revised and approved administrative procedures, surveillance procedures, chemistry control procedures, instrument calibration and QC procedures, and analytical procedures. A review of selected procedures revised since the previous NRC water chemistry inspection in March 1988 indicated that the C/RS had sufficient programmatic procedures to meet the commitments of the UFSAR and TS requirements.
The procedures reviewed are listed in Attachment 6 to this report.
The inspectors inspected the secondary chemistry. laboratory and laboratory equipment. The secondary chemistry laboratory was equipped with the necessary chemicals, standards, reagents, labware, and analytical instrumentation to perform the required chemistry analyses to support
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plant operation. The licensee had installed new digital process conductivity meters on the various plant water systems to better monitor water chemical conditions and maintain a more accurate control of water purity. The licensee was in the process of installing in-line ion chromatography instrumentation on the secondary water systems.
The inspectors reviewed selected chemistry department procedures for operation, calibration, and QC of the laboratory analytical instrumentation used for analysis of the NRC water chemistry standards to
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determine adequacy and accuracy of the licensee's water chemistry measurements program. The secondary chemistry and primary chemistry nonradiological laboratory analytical instruments had been calibrated H accordance with approved procedures and an instrument QC program had been implemented.
The licensee was using QC charts to trend QC data and I
instrument performance. The licensee had established criteria to identify l
end evaluate data biases in QC data and changes or trends in instrument performance. The licensee had implemented a program of using independent chemical standards for calibration and QC measurements of chemistry analytical instrumentation.
The inspectors reviewed second ry and primary water chemistry data to determine compliance with TS requirements.
It was verified that TS-required nonradiological water chemistry sampling and analyses had been performed. The review included inspection of the recorded trends of the secondary water quality data and reactor coolant chemistry parameters.
The inspectors reviewed the records of out-of-specification chemical parameters and the licensee's corrective actions taken when chemical parameters did not meet established chemical control limits. The inspectors reviewed the effectiveness of the water chemistry control program and determined that the licensee's chemical limits were established according to the Combustion Engineering chemistry specifications and the Electric Power Research Institute (EPRI) owner's group guidelines for pressurized water reactor secondary and primary water chemi stry.
Operation action levels had been defined in plant chemistry
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control procedures for the various plant operating modes and plant operation was controlled by chemistry parameter specifications. The i
licensee had implemented a strong chemistry control program which was substantiated by the results of the sludge lancing performed on the two
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i steam generators during the last refueling in the fall of 1989. The i
sludge lancing results showed approximately 28 pounds of sludge recovered
.from the cleaning process.of the two steam generators. Data supplied by the Steam Generators Owner Group indicated.that tnis type of steam generator tube cleaning had produced sludge quantities in the range of
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25-1000 pounds per steam generator depending on the life of the plant and adherence to good secondary chemistry controls.
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Standard chemical solutions were provided to the licensee for nonradiological confirmatory measurements analyses..The chemical standards were analyzed by the licensee in both the secondary.and primary chemistry laboratories using routine methods and equipment. The final results of the nonradiological water chemistry confirmatory measurements
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showed 100 percent agreement or qualified agreement with the NRC certified standard values. These results indicated an improvement in t
nonradiological water chemistry analytical performance over the 90 percent t
agreement during the previous NRC chemistry confirmatory measurements inspection in March 1988.
The results of the measurements comparisons are summarized in Attachments 1, 2, and 3 to this report.
No violations or deviations were identified.
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Radiological Chemistry Control. Radiochemical Analysis, and Confirmatory Measurements (84750. 84725)
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The inspectors reviewed the licensee's radiochemistry control and analysis program including analytical procedures, facilities and equipment, implementation of chemistry control of the reactor coolant system and
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plant borated water systems, implementation of an instrument QC program, postaccident sampling system (PASS) sample analyses, and radioanalytical confirmatory measurements to determine agreement with the commitments in
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Chapters 5, 9, and 11 of the UFSAR and compliance with the. requirements in Sections 3/4.1.2.7, 3/4.1.2.8, 3/4.4.6, 3/4.4.7 3/4.5.1, 3/4.5,4, 3/4.7.1.4, 3/4.9.1.1, 6.8.1, and 6.8.4 of the TS.
The inspectors reviewed selected radiochemistry laboratory analytical procedures revised and approved since the previous NRC inspection of radiochemistry activities in March 1988 and determined that the licensee had established and implemented satisfactory radioanalytical procedures to meet UFSAR and TS requirements.
The inspectors reviewed the licensee's records for 1989 to determine compliance with TS requirements for sampling and analyses of the reactor coolant system, steam generators, boric acid makeup tanks, refueling water storage pool, and safety injection tanks. The E-Bar data for July 1989 and March 1990 were also reviewed. The inspectors verified that all
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TS-required chemistry sampling and analyses of the above listed systems and components had been performed.
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Radiochemistry and HP procedures for the operation, calibration, and QC of.
the radiochemistry counting room and HP counting room instrumentation used U
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for analysis of the radiological confirmatory measurements were reviewed.
The inspectors reviewed the licensee's records.for 1989 and 1990 involving-
- r instrument calibrations and QC in both. counting rooms ~.
It.was verified
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that the analytical instruments had been calibrated in accordance with approved procedures and an instrument QC program had been implemented.-
The licensee was using'QC charts to trend QC data and instrument performance.
The inspectors.verifled that the PASS-equipment af.d associated procedures
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satisfied the requirements of NUREG-0737, Item II B.-3, for representative t
sampling and analysis of reactor coolant and containment atmosphere
following a reactor incident. The licensee had completed PASS operator
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training for C/RS technicians as part of:their shift qualification training and had implemented a requalification training program for PASS-
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operators which was being conducted annually as a required aspect of-the-l chemistry continuing training program. The licensee had installed ~a new
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PASS operating panel and several design modifications and had completed
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testing of the system modifications since'the last PASS inspection in March 1988.
In conjuncti.c.? with an; emergency exercise conducted at the.
time of the inspection the licensee demonstrated for the inspectors.the s
s operability of the PASS by collecting a diluted sample'from the reactor coolant system. The licensee performed a boron analysis and gross.
activity analysis on the PASS reactor coolant sample..The analytical
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n uits from the PASS, sample were compared with~the results-from a reactor M ant grab sample.
The results comparison was satisfactory.
Radiological confirmatory measurements were performed on stan.dards and I
split samples by the licensee and the inspectors in the Region'IV mobile laboratory onsite.
The standards and samples were analyzed by the
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licensee.using routine methods and equipment.
The radiological confirmatory measurements included analyses performed in the radiochemistry and HP counting rooms..This involved comparisons of analytical results from five detectors.
The licensee's radiological confirmatory measurements results for theLradiochemistry counting room indicated 100 percent agreement and for the HP counting room showed
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99 percent. agreement with the NRC analyses results. These results were consistent with the radiochemistry 100 percent agreement and the HP J
94 percent agreement during the previous NRC radiological confirmatory i
measurements inspection conducted in March 1988.
The results of'the e
l measurements comparisons are summarized in Attachments 1, 4, and 5 to this report.
No violations or deviations were identified.
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Radioactive Liquids and Gaseous Waste Effluent Releases (84750, 84723,
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84724)
L The inspectors reviewed the licensee's liquid and gaseous radwaste l
processing systems and procedures and records associated with liquid and
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l gaseous effluent releases to determine agreement with commitments in
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Chapter 11 of the UFSAR'and compliance with the requirements in Section 3/4.11 of the TS and the ODCM.
The inspectors-reviewed the licensee's' implement 6 tion of the'RETS and ODCM to ensure agreement with analysis sensitivities,_ reporting limits, analytical results, sampling requirements, surveillance' tests, radioactive waste effluent procedures, and offsite dose results from liquid and-gaseous effluents'.
Selected documents and records listed in Attachment 6-to this report were reviewed.
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The inspectors reviewed selected liquid and gaseous release permits for the period January 1989 through Marchj990.
The release permits included -
j batch liquid releases, plant stack and;FHB ventilation continuous releases, and gaseous batch releases from waste gas decay tanks Land containment purges. The processing, sampling and analyses, approvals, and-performance of the radioactive waste effluent releases _were conducted in
accordance with Wat-3 procedures. -Quantities of-radionuclides released in liquid and gaseous effluents were within the limits specified-in the RETS.
'Offsite doses had been calculated according-to the ODCM and were within TS limits.
l No violations or deviations were identified.
8.
Reports of Radioactive Effluents' (84750)
The inspectors reviewed the licensee's reports concerning' radioactive waste effluent releases to' determine compliance with the requirements of 10 CFR Part 50.36(a)(2) and Sections 6.9.1.8, 6.13, 6.14, and 6.1S of the
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TS.
The inspectors reviewed the licensee's semiannual effluent release _ reports for the periods July 1 through December 31, 1988; January 1:through June 30, 1989; and July I through December 31, 1989.
These' reports were written in the format described in NRC Regulatory Guide 1.21 and contained
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the information required by TS. During-the period July 1,1988, through December 31, 1989, the licensee had performed 237 liquid batch releases and 14 gaseous batch releases.
It was noted that the first report filed each year contained a summary of radiation doses due to radiological effluents during the previous calendar vear calculated in'accordance with the methodology specified in the ODCM. The inspectorr reviewed the licensee's changes to the ODCM as described in the appropriate semiannual effluent release reports as per TS requirements.
No violations or deviations were identified.
9.
QA Program The inspectors reviewed the licensee's N0SA surveillance and QA surveillance and audit programs regarding C/RS activities to determine agreement with commitments in Chapter 13.4 of the UFSAR and the I
requirements in Section 6.5.2.8 of the T.;
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The inspectors reviewed the surveillance and audit schedules for 1988,
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1989, and 1990; N0SA and QA surveillance and audit plans and-checklists; a n the. qualifications of surveillance inspectors and auditors.
Surveillances and audit reports of N0SA and QA activities performed during-1988' and '1989 in the areas of secondary chemistry,; radiochemistry,-
chemistry training, and PASS were reviewed for scope to ensure
- thoroughness of. program evaluation.
The inspectors noted that the N0SA surveillances and QA surveillances and audits were designed to. determine compliance'with the UFSAR, _TS, and Wat-3 procedures. The-inspectors verified that surveillance and audit findings had.been reviewed by licensee's management and that responses and corrective actions'to findings had been documented in a~ccordance with QA-procedures.. The
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inspectors determined that the surveillances and audits were performed by^
qualified personnel knowledgeable 'in' chemistry / radiochemistry activities at nuclear power. facilities..The inspectors reviewed the surveillance and audit reports listed-in Attachment 6 to this report, a
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10. Contractor Activities j
'The. licensee used a contractor-laboratory'to. perform TS required
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radiochemistry analyses on several radioactive effluent composite samples.
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The licensee's program for oversight of contractor. laboratory activities j
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and the QC' of analytical measurements by the contractor laboratory were reviewed to verify compliance with the requirements in Sections 3/4_.11 and 6.5.2.8 of the TS and agreement'with the recommendations ofLRegulatory Guide 4.15.
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a The licensee performs vendor-audits triannually with annual evaluations to i
retain current status on the qualified suppliers. list.. The inspectors reviewed the audit performed on the licensee's contractor. laboratory in August 1988 and verified that the contractor had been approved for the required analyses and placed on the current qualified suppliers list. The
inspectors found that the: licensee's supplier QA audit / surveillance program appeared to be adequate.
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No violations or deviations were identified.
11.
Exit Meeting The inspectors met with the senior resident inspector and the licensee representatives identified in paragraph 1 of'this report at the conclusion of the inspection on March 30, 1990. The inspectors summarized the scope and findings of the inspection and the results of the water chemistry and radiochemistry confirmatory measurements as presented in this report. The licensee did not identify as proprietary any of the materials provided to,
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or reviewed by, the inspectors during the inspection.
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ATTACHMENT 1 Analvtical Measurements Waterford-3 Steam El ectri c - St ati on
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NRC Inspection Report 50-382/90-06
1.
Water Chemistry Confirmatory Measurements
.During the inspection, standard chemical solut1'ons were provided'to'
f the. li censee f or anal ysi s.
The standard solutions were -prepared by the Brookhaven - Nati onal. Laboratory,(BNL), Safety and. Environmental.
a Protecti on Di vi si on, for the NRC.-
The standards were analyzediby the licensee using routine methods and equipment The anal ysis. of chemical standards is used to. verif y the licensee's r.apability to monitor chemical - parameters in various plant systems with respect to Technical Speci f i cati on (TS) ' requirements and other industry-
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In addition, the analyses of standards ~are used to evaluate the licensee's analytica1L procedures with respect to accuracy and precision.
The results of the measurements comparisons ar*
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Attachment 3 describes the criteria.used t e the results.
All standards were analyzed in triplicate at
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The -licensee's original analytical results' indicated' problems with the.
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analyses for iron, copper, 'ammoni a, and hydrazine.
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results chowed 25 of the 35 results were in agreement or cualified agreement using the criteria presented in Attachment 3.
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The licensee's original iron.results were all i n -'di sagreement.
The licensee prepared new iron calibration stendards, adjusted the instrument lamp alignment, and.recalibrated the atomic absorption instrument.
The licensee prepared new dilutions of
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the BNL iron standards (88G, 88H, and 881) and reran the iron
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The retest results for the iron analyses were all in l:
agreement.
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The licensee's original copper results were all in disagreement.
The li censee prepared 'nnw copper calibration standards, replaced the sample tube, and.recalibrated the atomic absorption instrument.
The licensee prepared new dilutions of the BNL copper standards (BBG, 88H, and BBI) and reran the copper analyses.
The retest results for the copper analyses were all in agreement.
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ATTACHMENT 1
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The licensee's original ammoni a low range' concentration result was in disagreement and biased high.
The licensee prepared a new dilution of BNL standt.rd BBM and reran the ammonia analysis.
The retest result for the ammonia low range concentration was in agreement.
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The licensee's original hydrazine result's were in qualified
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agreement or disagreement.. The licensee prepared new dilutions of the BNL hydrazine standards-(88P, BBQ, and BBR) Land reran.the hydrazine analyses.
The retest'results for-the hydrazine concentrations were in agreement or qualified. agreement.
The licensee's final anal yti c al results, after the retests to resolve the original disagreements, indicated'100 percent agreement;or qualified agreement with the. BNL results based on 35 results compared.
The licensee's chemistry section perf ormance in the area of non-radiological water chemistry confirmatory measurements showed an improvement over the 90 percent agreement achieved during the last NRC inspection of this area in March 1988.
2.
Radi ol ool c al Confirmatory Measurements The radiochemistry confirmatory measurements were performed on the f ollowing standards and samples in the NRC Region 'IV mobile laboratory at Waterf ord-3 Steam Electric Station 'during the inspection.
(1) NRC Air Particulate Filter Standard (34118-109)
(2) Scott Charcoal Cartridge Sample (3) Waste Liquid Sample - Tank
"B" (1 Liter Marinelli Beaker)
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(4) Containment Atmosphere Sample (1 Liter Gas Marinelli Beaker)
(5) Reactor Coolant System Li quid Sample (20ml Scintillation Vi al)
(6) Reactor Coolant System Gas Sample (15cc Gas Serum Vial)
(7) Reactor Coolant System Tritium Sample
The radiological confirmatory measurement tests consisted of comparing l-the analysis results of the licensee and the NRC-Region IV mobile.
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The NRC's mobile laboratory measurements are ref erenced
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to the National Institute of Standards and Technology by laboratory intercomparisons.
Confirmatory measurements.are made only for those i
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nuclides identified by the NRC as being present in concentrations greater than 10 percent of the respective isotopic values f or liquid and gas concentrations as stated in 10 CFR Part 20, Appendix B, Table
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ATTACHMENT i
The licensee maintains three high-purity germanium detectors in the radiochemistry counting room and three high purity germanium detectors in the health physics counting room for a total-of six detectors.
One of the radiochemistry counting room detectors was out of service at the time of the inspection.
These detectors are used routinely for isotopic analysis of radioactive samples to demonstrate compliance with TS and regul atory requirements.
The analytical results from the five detectors in service during the inspection were compared with the NRC results.
The detectors' labeled (1) and (2).are lo:ated and maintained in the radiochemistry counting room and are primarily used for isotopic anal ysis of reactor coolant system samples.
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detectors label ed (G),
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and (D) are located and maintained in the-health physics counting room and are primarily used for isotopic
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analysis of radioactive waste samples and building atmosphere.
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respective analytical-results are reported for each detector in the order listed above.. The licensee perf ormed the reactor coolant system tritium analysis on their liquid scintillation counting system in the radiochemistry counting room.
The individual sample analyses and comparison of analytical results of the radiological confirmatory measurements are tabulated in Attachment 4.
Attachment 5 describes the criteria used to compare the analytical results.
The licensee's radiochemistry section gamma isotopic results from the samples listed in Attachment 4 showed 100 percent agreement with the NRC analysis results based on 52 agreement results out of 52 total results compared.
The -licensee's tritium result of the reactor coolant sample was in agreement with the NRC analysis result.
The licensee's radiochemistry section performance in the area of r adi ol ogi c al confirmatory measurements demonstrated the.same high quality of performance of 100 percent agreement achieved during the last NRC inspection of this area in Marcn 1988.
,,
The licensee's health physics section gamma isotopic results from the samples listed in Attachment 4 showed 99 percent agreement with the
.
NRC analysis results based on 65 agreement results out of 66 total
'
results compared.
The licensee's health physics section performance in the area of radiological confirmatory measurements showed an improvement over the 94 percent agreement achieved during the last NRC inspection of this area in March 198 _.
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ATTACHMENT 2
i Water Chemistry Confirmatory Measurements Results j
j Waterf ord-3 Steam Electric Station i
NRC Inspection Reports 50-382/90-06 l
1.
Chl ori de Anal ysi s (1-10 ppb)
Ion Chromatography Wat-3 Results NRC Results Comparison Sample (pob).
(pob)-
Decision-88A 2.910.8 3.010.2 Agreement BBB 5.910.1 6.20.4-Agreement'
88C 8.8 0.1 9.510.5 Agreement 2.
Fluoride Anal ysis (50-500_ ppb)
Selective Ion Electrode Wat-3 Results NRC Results Comparisen Sample (pob)
(pob)
Decision BBA 92.312.5 96.011.0 Agreement
888 191.712.9 192.018.0 Agreement BOC 295.015.0 296.0112.0 Agreement
,
3.
Sulfate Analysis (1-10 ppb)
Ion Chromatography
.
Wat-3 Results NRC Results Comparison Sample (pob)
(pob)
Deci si on 88A 2.liO.2 1.9 0.3 Agreement 888 3.910.1 3. bio.4 Agreement BBC 5.5io.2 6.010.4 Agreement
.
4.
Baron Analysis (100-2000 ppm)
Manital Titration Wat-3 Results NRC Results Comparison Sample (nom)
(opm)
Deci si on 88D 203.710.6 205.014.0 Agreement BOE 611.3i4.2 598.018.0 Agreement BBF 1020.4 1.1 1020.0120.0 Agreement r
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ATTACHMENT 2
5.
Iron Analysis (1-60 ppb)
Atomic Absorption Graphite Furnace Wat-3 Results NRC Results Comparison Sample (oob)
(pob)
Deci si on 88G 10.310.4 19.8 0.3 Disagreement 88H 49.610.6 39.211.0 Disagreement 88I 20.710.9 50.011.0 Disagreement Retest - prepared new iron calibration standards, adjusted lamp alignment, and recalibrated the instrument; prepared new BNL standard dilutions and performed retest analayses-88G 20.4 1.O'
19. bio.3 Agreement OOH 39.810.5 39.211.0 Agreement 881 61.210.7 58.011.0 Agreement
- 6.
Cooper Anal ysi s (1-50 ppb) Atomic Absorption Graphite Furnace I
Wat-3 Results NRC Results Comparison Sample (oob)
(pob)
Decision
,
88G 16.710.1 19.9iO.4 Disagreement 88H 32.SiO.4-40.510.3 Diwagreement
'
881 47.8io.9 59.5 0.5-Disagreement Retest - prepared new copper calibration standards and recalibrated the atomic absorption instrument; prepared new BNL standard dilutions and performed retest analyses 88G
,20.3 0.8 19.9 0.4 Agreement
88H 40.710.8 40.5 0.3 Agreement j
BOI 61.3 0.6 59.510.5 Agreement 7.
Sodium Analysis (0-5 ppm)
Flame Atomic Absorption Wat-3 Results NRC Results Comparison Sample (pob)
(oob)
Decision
-
88J 0.5010.02 0.5110.02 Agreement 88K 1.04 0.06 0.9910.02 Agreement
,
88L 1.72 0.02 1.52 0.04 Agreement
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ATTACHMENT 2
C.
Lithium Analysis ~(0.5-5.0 ppm)
Flame Atomic Absorption Wat-3 Results NRC Results Comparison Sample (oom)
(oom)
Decision 88J 2.0110.02 1.98 0.03 Agreement 88K 3.0210.08 2.9310.08 Agreement BOL 4.1710.02 3.9510.06 Agreement
,
9.
Ammont a Analysis (0.1-2. ppm)
Spectroscopy
.
Wat-3 Results NRC Results Comparison Sample (oom)-
(com)
Decision BOM O.16410.010 0.10210.005 Disagreement BBN O.62810.027 0.620iO.020 Agreement 880 1.92810.061 2.00010.080 Agreement Retest - prepared new BNL standard dilution and performed retest analysis c
88M O.09210.004 0.102 0.005 Agreement 10.
Hydrazine Analysis (1-100 ppb)
Spectroscopy Wat-3 Results NRC Results Comparison Sample (pob)
(oob)
' Decision
,
'
88P 12.0 3.0 10.2 0.3 Qual. Agree.
BBQ 38.316.7 42.310.9 Qual. Agree.
l 88R 71.1 4.7 84.410.6-Disagreement l
.
l Retest - prepared new ENL standard dilutions and performed retest analyses 88P 12.011.0 10.2io.3 Qual. Agree.
'
880 40.310.6 42.3 0.9 Agreement 88R 83.011.0 84.4iO.6 Agreement 11.
Silica Analysis (1-500 ppb)
Spectroscopy Wat-3 Results NRC Results Comparison Sample (pob)
inpb)
Decision 87S 47.313.2 52.812.0 Agreement 87T 94.016.0 104.Oi4.0 Agreement
l D6U 142.015.0 157.012.0 Agreement
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ATTACHMENT 7
12.-
Post Accident Sampl e -
.
Boron Anal ysi s Manital Titration.
Wat-3 Results
' NRC Results Comparison Sample (com)
(com)
Decision AA18 200017 2060140 Agreement Chl ori de Anal ysi s Ion Chromatography
,
Wat-3 Results NRC Results-Comparison Sample (opm)
(opm)
Decision AA18 9.2510.05 11.3iO.3 Agreement
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ATTACHMENT 3 i
CRITERIA FOR COMPARING WATER CHEMISTRY ANALYTICAL MEASUREMENTS The following are_the criteria used in comparing the results of
~
the capability tests and verification measurements.
The rriteria j
for the judgement limits are based on the data from Table 2.1 of NUREG/CR-5244, " Evaluation of Non-Radiological Water Chemistry at Power Reactors."
Licensee values within the plus or minus two stadnard deviations range of the BNL known values are considered to be in agreement. ' Licensee values outside the plus or minus two standard deviationa range but within the plus or minus three standard deviations range of the BNL known values are considered to be in qualified agreement.
Retest results which are in qualified agreement will receive additional attention.
Licensee values greater than the plus or minus three standard deviations range of the BNL known values are in disagreement.
The standard deviations were computed using the average percent standard deviation values of each analyte in Table 2.1.
The ranges f or the-data in Attachment 2 are as follows:
Agreement Qualified Areement Amoule Analvte Ranoe Ranoe i
88A F
B4 - 108 80 - 112
C1 2.8 - 3.2 2.7 - 3.3 SO -
1.7 - 2.1 1.6 -'2.2
888 F
168 - 216 160 - 224 I
C1 5.7 - 6.7 5.5 - 6.9 SO 3.4 - 4.2 3.3 - 4.3
88C F
260 - 332 244 - 348 C1 8.8 - 10.2 8.5 - 10.5 SO 5.4 - 6.6 5.2 - 6.8
88D
202 - 210 199 - 213 88E
585 - 611 579 - 617 88F
998 - 1042 987 - 1053 88G Fe 17.9 - 21.7 16.9 - 22.7 Cu 18.0 - 21.8 17.1 - 22.7 88H Fe 35.4 - 43.0 33.6 - 44.8 Cu 36.6 - 44.4 234.7 - 46.3
-
.
.
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.
ATTACHMENT 3
L Agreement Qualified Areement j
Amou(r'
Analvte Ranoe Ranae i
l g
881 Fe 52.4 - 63.6 49.6 - 66.4 Cu 53.8 - 65.2 51.0 - 68.0-l BBJ
.Na 0.44 - 0.58 0.40 - 0.62 Li 1.70 - 2.26 1.57 - 2.39 88K Na 0.85 - 1.13 0.78 - 1.20 l
.
Li
- 2.52 - 3.34 2.30 - 3.56 i
1.73 1.20 - 1.84
!
88L Na 1.31
-
Li 3.40 - 4.50 3.-12 - 4.78 88M N!!
0.092 - O.112 0.087 - 0.117
4 88N NH 0.56 - 0.68 0.53 - 0.71
880 NH 1.81 - 2.19 1.71 - 2.29
88P NH 9.4 - 11.0 8.5 - 12.0
39.0 - 45.6 37.4 - 47.2 l
88Q NyH4 88R'
NH 77.9 - 90.9 74.6 - 94.2
87S SiO 44.3 - 53.6 42.1 - 55.9
2-
!
87T SiO 100 -- 120 94.6 - 125
!
87U SiO 142 - 172 134 - 180
AA18
1957 - 2163 1945 - 2175 C1 9.0 - 12.4 8.6 - 13.0 I
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- ~n ww m-
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ATTACHMENT 4 i
Radi oloaical Confirmatory Measuresment Reaulta Waterf ord-3 Steam Electric Stati on NRC Inspection Reports 50-382/90-06
!
1.
NRC Air Pprticulate Filter Standard (34118-109)
(Standardized:
11:00, CST, January 1, 1990)
Standard was analyzed by radiochemistry on detectors (1) and (2) and by health physics on detectors-(G),
(H), and (D). The results of thel analyses.are reported for'each detector in the above stated order.
.
Wat-3.Results NRC Results'
Wat-3/NRC Comparison Nuclide (uCi/ sample)
(uCi/ sample)
Ratio Decision
<
Hg-203 8.8710.05E-2 7.98 0.06E-2 1.11 Agreement B.9010.04E-2 1.12 Agreement
'
8.3OiO.04E-2 1.04 Agreement
8.5010.04E-2 1.07 Agreement
8.56 0.04E-2 1.07 Agreement Co-60 9.01tO.D5E-2 8.36iO.04E-2 1.08 Agreement 9.50iO.04E-2 1.14 Agreement 8.8810.04E-2 1.06 Agreement 8.86 0.04E-2 1.06 Agreement
'
9.1210.04E-2 1.09 Agreement L
i Cd-109 1.24iO.01E+O 1.10iO.01E+O-1.13 Agreement L
1.3410.01E+0 1.22 Agreement 1.2310.01E+O 1.12 Agreement 1.2SiO.01E+0 11.14 Agreement
,
'
1.2710.01E+0 1.15 Agreement i
Co-57 3.3610.01E-2 2.8910.02E-2 1.16
' Agreement
,'
3.45 0.01E-2 1.19
' Agreement 3.2710.01E-2 1.13 Agreement 3.35tO.01E-2 1.16 Agreement 3.3110.01E-2 1.15 Agreement Ce-139 4.60 0.01E-2 3.95iO.02E-2 1.16 Agreement 4.7210.02E-2 1.19 Agreement 4.41 0.01E-2 1.12 Agreement 4.45 0.02E-2 1.13 Agreement
.
4.4510.01E-2 1.13 Agreement
.
Sn-113 9.62 0.05E-2 8.53io.05E-2 1.13 Agreement 9.93iO.04E-2 1.16 Agreement
<
9.2410.04E-2 1.08 Agreement 9.50tO.04E-2 1.11 Agreement
'
9.55io.03E-2 1.12 Agreement
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ATTACHMENT 4
a Wat-3 Results NRC Results
.Wat-3/NRC Comparison-
'
Nuclide igCi /sampl e)
(uC1/sampl e)-
Ratio Deci si on
!
Cs-137 8.3810.04E-2 7.60iO.04E-2 1.10 Agreement j
8.69iO.03E-2 1.14 Agreement j
i 8.34tO.03E-2 1.10 Agreement (
B.5710.03E-2 1.13'
Agreement dn72iO.03E-2 1.15 Agreement
I Y-88 1.5410.01E-1 1.4510.01E-1 1.06 Agreement I
L 1.5910.01E-1 1 ~.10 Agreement 1.49tO.01E-1 1.031 Agreement 1.4910.01E-1 1.03 Agreement 1.5310.01E-1 1.06 Agreement 2.
Scott Charcoal Cartridae Samole (Wat-3 51A)
(Sampled:
17:40, CST, March 27, 1990)'
Sample was analyzed by health physics on detectors (G),
(H), and (D).
i The results of the analyses are reported for each detector in the above stated order.
'
Wat-3 Results NRC Results Wat-3/NRC
. Comparison Nuclide (uCi/ sample)
(uCi/samo)w5-Ratio _
Decision I-131 1.2510.01E-1 1.1610.01E-1 1.08 Agreement 1.3110.01E-1 1.13 Agreement 1.3110.01E-1 1.13 Agreement I-133 1.0510.03E-2 0.8710.01E-2-1.21 Agreement
,
1.0410.01E-2 1,20 Agreement
-
1.0510.02E-2
~1. 21 Agreement
$
3.
Waste Li quid Sampl e - Tank
"b" (1 Liter Marinelli Beaker) Wat-3 44A (Sampled:
16:15, CST, March 26, 1990)
Sample was analyzed by health physics on detectors (G),
(H), and (D).
-
The results of the analyses are reported for each detector in the above stated order.
.
Wat-3 Results NRC Results Wat-3/NRC Comparison Nuclide (uCi /ml )
(uCi /ml )
Ratio Deci si on Co-58 1.2110.02E-5 1.2310.01E-5 0.98 Agreement 1.17 0.02E-5 0.95 Agreement 1.14 0.02E-5 0.93 Agreement Co-60 9.1410.71E-7 9.8810.56E-7 0.93 Agreement 8.82 0.85E-7 0.89 Agreement 8.41 0.70E-7 0.85 Agreement
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l ATTACHMENT 4
Wat-3 Results NRC Results'
Wat-3/NRC Comparison Nuclide (uCi/ml)
(uCi/ml)
Ratio Decision Sb-124 2.92io.20E-6 3.23iO.14E-6 0.90 Agreement 2.7410.19E-6 0.85 Agreement 2.7210.19E-6 0.84 Agreement Sb-125 3.9410.06E-5 3.95 0.04E-5 1.00 Agreement 3.9310.06E-5 0.99 Agreement 3.67iO.06E-5 0.93 Agreement Cs-134 8.07iO.18E-6 7.77 0.13E-6 1.04 Agreement 7.9410.19E-6 1.02 Agreement 7.4710.17E-6 0.96
~Agruement Cs-137 1.14tO.02E-5 1.1610.02E-5 0.98 Agreement 1.1810.02E-5 1.02
. Agreement 1.14tO.02E-5 0.98 Agreement 4.
Containment Atmosphere Samole (1 Liter' Gas Merinelli-Beaker) Wat-3 SOB (Sampled:
13:30, CST, March 27, 1990)
,
I Sample was analyzed by health physics on detectors (G),
(H), and (O).
,
l The results of th= analyses are reported'for each detector in the above stated order.
Wat-3 Results NRC Results Wat-3/NRC Comparison
!
Nuclide (uC1/sampl e)
(uCi /samol e)
Rati_o Decision Ar-41 1.6110.22E-3 0.7710.22E-3 2.09 Agreement
.
1.41tO.14E-3 1.83 Agreement 1.40iO.16E-3 1.81 Agreement
-
Kr-85m 2.9510.50E-4 2.50 0.37E-4 1.18 Agreement 2.19tO.32E-4 0.88 Agreement 3.6610.39E-4 1.46 Agreement
>
Xe-131m 1.28 0.47E-3 2.1110.35E-3 0.61 Agreement 2.4110.66E-3 1. l t, Agreement 2.4110.66E-3 1.14 Agreement Xe-133 1.79io.01E-1 1.6510.01E-1 1.08 Agreement-1.79iO.01E-1 1.08 Agreement-2.12iO.01E-1 1.28 Disagreement-Xe-133m 1.78iO.20E-3 1.57 0.14E-3 1.13 Agreement 1.5110.20E-3 0.96 Agreement 2.14 0.20E-3 1.36 Agreement Xe-135 2.7810.07E-3 2.7810.05E-3 1.00 Agreement 2.8710.06E-3 1.03 Agreement 3.47 0.07E-3 1.25 Agreement
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ATTACHMENT 4
.4 5.
RCS Li oul d Sampl e (4m1 in 20ml Scintillation Vial) Wet-3 45A
,
(Sampled:
9:45, CST, March 27, 1990)
Sample was analyzed by radiochemistry on detectors (1) and (2).
The results of the analyses are reported for each detector in-the-above stated order.
Wat-3 Results NRC Results Wat-3/NRC Comparison Nuclide (uCi/ml)
(uCi/ml)
Ratio Decision i
Na-24 4.19 0.04E-2 4.5910.02E-2 0.91 Agreenent I
4.1110.03E-2 0.90 Agreement i
Mo-99 2.92iO.80E-3 4.80 0.57E-3 0.61 Agreement 5.1110.73E-3 1.06 Agreement I-131
.1.29iO.02E-2 1.48 0.01E-2 0.87-Agreement 1.30iO.02E-2 0.88 Agreement I-132 2.9110.03E-2 3.21tO.02E-2 0.91 Agreement 3.01 0.02E-2 0.94 Agreement
.
I-133'
2.3510.02E-2 2.70io.01E-2 0.87 Agreement-l 2.43 0.02E-2 0.90
' Agreement i
1-134 5.95iO.20E-2 6.5910.07E-2 0.90 Agreement 6.10 0.06E-2 0.93
' Agreement I-135 4.03 0.10E-2 4.3910.05E-2 0.92-Agreement-3.96 0.07E-2-O.90 Agreement l
Cs-134 2.1210.15E-3 2.1410.11E-3 0.99 Agreement l
1.86iO.13E-3 0.87'
Agreement Cs-137 2.7810.13E-3 3.0610.10E-3 0.91 Agreement 2.81 0.12E-3 0.92 Agreement Cs-138 6.2110.51E-2 6.04 0.09E-2 1.03 Agreement 5.5710.06E-2 0.92 Agreement Ba-139 4.95 0.85E-3 5.7210.57E-3 0.87 Agreement 4.78 0.55E-3 0.84 Agreement
'
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ATTACHMENT 4
6.
RCD Gas Ssmole (4.7ec in 15cc Gas Vial) Wat-3 47A
_
(Sampled:
11:30, CST, March 27, 1990)
Sample was analyzed by radiochemistry on detectors (1) and (2).
The results of the analyses are reported f or each detector in the above stated order.
m Wat-3 Results NRC Results Wat-3/NRC Comparison NucLtdg (uCi/cc)
(uCi/cc)
Ratio Decisien Ar-41 2.1410.30E-3 1.73 0.09E-3 1.24 Agreement 1.7310.00E-3 1.00 Agreement Kr-85m 3.32iO.01E-2 3.15io.01E-2 1.05 Agreement 3.4510.01E-2 1.10 Agreement Kr-87 3.66iO.06E-2 3.96 0.02E-2 0.92 Agreement 3.88tO.02E-2 0.98 Agreement Kr-88 5.5710.03E-2 5.57 0.07E-2 1.00 Agreement
,
5.7710.02E-2 1.04 Agreement
'
Xe-133 4.06tO.01E-1 3.60iO.01E-1 1.13-Agreement
!
4.19iO.01E-1 1.16 Agreement
-
s Xe-133m 7.85 0.32E-3 8.64 0.48E-3 0.91 Agreement 8.33 0.39E-3 0.96 Agreement Xe-135 1.70iO.01E-1 1.7710.01E-1 0.96 Agreement 1.73tO.01E-1 0.98 Agreement 7.
Reactor Coolant System Tritium Sample
-
(Sampled:
9:05, CST, March 26, 1990)
Wat-3 Results NRC Results Wat-3/NRC Comparison Nuclide (uCi/ml)
(uCi/ml)
Ratio Decision H-3 2.4710.02E-1 2.52iO.02E-1 0.98 Agreement
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ATTACHMENT 5
>
o l
CRITERIA FOR COMPARING RADIOCHEMISTRY ANALYTICAL MEASUREMENTS
.
The f ollowing are the criteria' used in comparing the results of
.
capability tests and verification measurements.
.The criteria are-based on an empirical relationship. established through prior experience and this program's analytical requirements.
In these criteria, the judgement limits vary in relation to the
'
comparison of the resolution.
Resoluti on
NRC UNCERTAINTY LICENSEE VALUE Ratio
=
NRC VALUE
~
Comparisons are made by first determining the resolution and then reading across the same line to the corresponding ratio.
The following table shows the acceptance values.
'
- ~.
RESOLUTION AGREEMENT RATIO f
<4 0.40 - 2.50
'
4-7 HO.50 - 2.00 8-15 0.60 - 1.66
!
16 - 50 0.75 - 1.33 j
51 - 200 0.80 - 1.25
!
>200 0.85 - 1.18'
l l
The above criteria are applied to the following analyses:
,
(1). Gamma Spectrometry (2) Tritium in l i qui d samples (3) Iodine on adsorbers
,
(4)
Sr and Sr determinations (5) Gross Beta where samples are counted on the same date using the same reference nuclid }
q
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.
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!
ATTACHMENT 6-
'
Waterford-3, Steam' Electric Station:
,
NRC-Inspection Report 50-382/90-06
' Documents Reviewed
Title:
, Revision ;Date 1.
~ Chemistry Department' Procedures'(CE) '
,
i CE-001-000, Organization and Responsib111 ties-3^
12/12/87
-
of the Chemistry Department
,
CE-001-001, Training-and' Qualification of Chemistry-3 ~
09/11/87
'
Department Personnel CE-001-002, Log Keeping, Filing, and Record Storage
05/09/89
_
-CE-001-003,- Reporting. Chemistry Data
'06/28/88
.
'
CE-001-004, Periodic Analysis Scheduling Program-
08/04/89-CE-001-005,- Test Stand Calibration Scheduling Program-
07/15/89
CE-001-006, Analytical and Process. Equipment
-06/12/89
'
Calibration Schtduling Program CE-001-016, Control of Measuring and Test Equipment.
04/14/89'
'l CE-001-020, Chemistry. Department-Quality Control
07/10/89 Program a
CE-001-021, Verification of Analytical Performance
06/23/89 CE-002-001, Maintaining Steam Generator Chemistry 6-10/06/89
-
'
CE-002-002, Maintaining Condensate and Feedwater-
01/20/89 Chemistry CE-002-006, Maintaining Reactor Coolant Chemistry
11/11/89 CE-002-009, Maintaining Boron Managenent System
10/20/89 Chemistry CE-002-010, Maintaining Sefety Injection Tank Chemistry 4-01/28/88-
.
's f. a
.,
....
.
.
-2-CE-002 011, Maintaining Spent Fuel Pool Chemistry.
09/14/89 CE-002-016, Maintaining Gaseous Waste Management'
05/20/88 System CE-002-018, Monitoring Liquid Waste Management
09/18/89-CE-002-020, Maintaining Primary Water Storage Tank 6.
07/09/89
- Chemi stry CE-002-025,-Maintaining Refueling Water Storage' Pool 5=
09/14/89 Chemistry CE-002-031, Maintaining Secondary Chemistry Monitoring
11/12/86-System CE-002-200,. Chemistry Technical-Specifications'
11/28/88 Surveillance Performance Coordination
'
CE-002-101, Secondary Chemistry Control Study
09/30/88 j
CE-003-103, Determination of Chlorides-Specific Ion.
07/09/89 Electrode Method
,
..i CE-003-108,- Determination of Hydrazine'(0-80 ppb)
-12/06/88
<
CE-003-109, Determination of Hydrazine-
07/20/88 CE-003-111, Determination of Ammonia
12/05/87 CE-003-113, Determination of Silica
11/21/88 CE-003-121, Boron Determination (Autotitration Method)
10/06/86'
l CE-003-122, Determination of Boron (Titration Method)
06/12/88 CE-03-300, Preparation of Liquid Sample-for
01/18/88
Radiological Chemical Analysis i
!
CE-03-302, Determination of Gross Beta-Gamma
07/25/88 Radioactivity
CE-03-303, Gross Alpha Measurement
07/09/89
,
CE-03-305, Sampling of Ventilation and Gaseous Waste
02/17/89
!
Management Systems for Radioactive Effluents CE-03-306, Determination of the Average Beta-Gamma
06/06/88 Energy of Reactor' Coolant
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co.,,. * -
G
'*:
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,
-3-
CE-03-313, Tritium Analysis
07/20/88'
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CE-03-314, Use of.Beckman LS5801
,12/06/88 i
CE-03-320, Use of the ND-6700 for Radiochemistry
05/02/88
'
CE-03-325, Determination of Nitrogen, Hydrogen, '
'
07/09/89-0xygen, and Gaseous Activities CE-03-327, Operation of' the Primary Sample Panel
09/14/8P CE-03-329, Operation of the Liquid Scintillation
09/21/88 System Beckman LS7000 CE-03-400, Operation of the Plasma Emission
09/01/88
,
Spectrometer CE-03-401, Operation of the Atomic Absorption
08/27/88:
Spectrophotometer CE-03-700, General Grab Sampling Techniques
08/08/88 CE-03-800,-Operation of the Ion Chromatograph
05/26/89 CE-03-900, Operation of the-Post Accider,t' Sampling
L10/11/88 System o
CE-03-902, Post Accident Boron Analysis (Plasma Method)'
2-06/16/86 CE-03-905, Testing and Maintenance of the Post
12/05/89 Accident Sampling System 2.
Health Physics (HP) Group Procedures HP-001-169, Compositing Effluent Samples
12/06/85 HP-001-170, Sampling of GWMS and Containment Purge for 2'
02/16/90 Radioactive Effluents HP-001-171, General Grab Sampling Techniques
12/04/87-
,
HP-001-172, Quality Control of the ND Gamma
09/14/86 Spectroscopy System HP-001-174, Grab Sampling from PIG Monitors and WRGM
01/26/89 HD-001-175, Routine Filter Replacement on PIG Monitors
01/26/89 and WRGM i
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,
-4 '-
HP-001-230,'Offsite Dose Calculat' ion' Manual
07/07/87-HP-001-233, Liquid Radioactive Waste Release Permit
01/16/90--
,
(Computer)
HP-001-234,- Gaseous Radioactive Waste Release Permit
06/11/88'
(Computer)
HP-001-235, Cal'eulation and Adjustment of Radiation
'7 12/29/89
.
Monitoring Setpoints HP-001-238, Radiological Eff.luents Sampling Schedule
.1 02/09/88
,
HP-001-239, Quality Assurance Program for Radiological
07/21/87-Effluents'and Environmental Monitoring
[
-HP-002-307, Operation of the Gamma Spectroscopy System.
09/22/86 i
HP-002-474, Calibration of the Gamma Spectroscopy,
09/14/86
,
System ND-66/76
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3.
Quality Assurance (QA) Audits and Surveillances i
QA Audit Schedules 1988-1990 QA Audit Report:
SA-89-003 J, " Performance, Training, and Qualification,"
performed June 21 through July 28, 1989 QA Audit Report:
SA-88-033.1, " Primary Water Chemistry," performed February 29 through March 18, 1988 QA Audit Report:
SA-89-033.1, " Primary Water Chemistry," performed November 27 through December 26, 1989
QA Audit Report:
SA-89-020.1, " Post Accident Sampling System," performed
"
February 20 through March 22, 1989 QA Audit Report:
SA-89-019.1, " Secondary Chemistry,"' performed April 17 through May 10, 1989
}
QA Audit Report:
AP0-88/0428, " Grand Gulf Nuclear Station Unit 1 Transmit tal of Audit Report SCAI-88/01 (SERI) Q-3-A35.39-233-88.1 '(LP&L),"
perforrr,ad April 21-22, 1988 QA Audit Report: A39.234-88.1, "Waterford III SES QA Audit of Teledyne Isotopes," performed August 15, 1989 Surveillance Report: QS-88-075, " Chemistry / Plant Engineering /QA-Diesel Fuel Oil Analysis (PRE 88-77)," performed July 6 to July 13, 1988
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Surveillance Report:.QS-89-047, " Chemistry-Waste Condensate Chemistry.
Analysis," performed October 3, 1989 Surveillance Report: QS-88-030, " Chemistry-Lay-up Chem'istry," performed '
Mty-16, 1988 i
Surveillance Report: QS-88-051, " Chemistry Volume Control System (CVCS),"-
,
performed May 26, 1988
!
Surveillance' Report: QS-88-057, " Chemistry Department-Verification =of-
!
Chemistry Prerequisites Required for Plant Startup," performed May 26 through June 7,1988-
'
Surveillance Report: QS-88-072, " Nuclear Operations Engineering-Post.
Accident Sampling System (PASS) Acceptance Testing of Gas Portion,"-
performed June 25, 1988
)
Surveillance Report:
305-89, " Auxiliary System Chemistry," performed'
November 28, 1989
-
i 4.
Waterford-3-Steam Electric Station Semiannual Radioactive Effluent Release Reports
!
July 1 through December -31, 1988 l
January 1 through June 30, 1989 July 1 through December-31, 1989
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