IR 05000382/1988005

Insp Rept 50-382/88-05 on 880307-11.No Violations or Deviations Noted.Major Areas Inspected:Chemistry/ Radiochemistry Program & Water Chemistry & Radiochemistry Confirmatory Measurements

ML20151N612
Person / Time
Site:	Waterford
Issue date:	04/07/1988
From:	Murray B, Nicholas J, Wise R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20151N605	List: IR 05000382/1988005 ML20151N600
References
50-382-88-05, 50-382-88-5, NUDOCS 8804250336
Download: ML20151N612 (21)

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APPENDIX

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U.S. NUCLEAR REGULATORY COMMISSION

REGION IV

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NRC Inspection Report:

50-382/88-05 Operating License:

NPF-38 Dobket:

50-382!

Licensee:

Louisiana 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, Taft, St. Charles' Parish, Louisiana Inspection Conducted:

March 7-11, 1988

m Inspectors:

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4/-7/97 s

f./B. Nicholas,5eniorRadiationSpecialist

/acilities Radiologicai Protection Section

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R. Wise, Radiation Specialist, Facilities

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Radiological Protection Section Approved:

(1[1Ab WAbfMfv/

/M B. Murray, Chief, Facilitief Radiological Dhte'

Protection Section Insoection Summary Inspection Conducted March 7-11, 1988 (Report 50-382/88-05)

Areas Inspected:

Routine, unannounced inspection of the licensee's chemistry / radiochemistry program and water chemistry and radiochemistry confirmatory measurements.

~Results:

Within the areas inspected, no violations or deviations were identified.

One previously identified violation and one unresolved item were closed.

See paragraph 2.

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-2-DETAILS 1.

Persons Contacted LP&L

• R. P. Barkhurst, Vice President, Nuclear (Site Director)

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• N. S. Carns, Plant Manager

• R. E. Allen,, Senior Chemistry Engineer - Nuclear

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-K. P. Boudreaux, Senior Health Physics Technician

'C. E. Brannon, Senior Chemistry Technician M. J. Campo, Chemistry Technician

• G. L. Dolese, Radiochemistry Supervisor B. P. Falqoust, Senior Chemistry Technician

• C. R. Gaines, Events Analysis Supervisor W. L. Gilboy, Senior Chemistry Technician

• T. 0 Gray, Quality Assurance (QA) Supervisor, Operations

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M. L. Layton, Nuclear Operations and Support Assessment Engineer

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• H.

C.' Lesan, Radiological Engineer D. G. Marse, Senior Chemistry Technician D. L. McBride, Senior Chemistry Technician D. O. Medina, Chemistry Technician J. V. Messina, QA Auditor, Operations

• B. G. Morrison, Licensing Engineer

• J. M. O'Hern, Technical Training Superintendent P. V. Prasankumar, Assistant Plant Manager, Plant Technical Services

• S. Ramzy, Assistant Radiation Protection Superintendent

• D. A. Thorpe, Radiochemistry Engineer E. V. Wright, Senior Chemistry Technician

• G. E. Wuller, Operational Licensing Supervisor N'lC W. F. Smith, NRC Senior Resident Inspector, Wat-3 T. R. Staker, NRC Resident Inspector, Wat-3

• Denotes those present during the exit interview on March 11, 1988.

2.

Followup On Previously Identified Inspection Findings (92701/92702)

(Closed) Violation 382/8706-01:

Failure to Properly Store and Protect Quality Assurance Records - This violation was identified in NRC Inspection Report 50-382/87-06 and involved the failure to properly store original records of radioactive waste shipments performed during 1986 and 1987 and transmit these records in a timely manner to permanent plant

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records for final retention.

The NRC inspectors reviewed the licensee's response and corrective actions to the violation.

The licensee had purchased and placed in the Radwaste Supervi:.or's office in the reactor auxiliary building a lockable, one-hour rated fireproof file cabinet for

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-3-interim storage of radwaste shipping records.

The NRC inspector verified the use'of the fireproof file cabinet for interim storage and noted that l

all completed records of radioactive waste shipments had been transmitted to permanent plant records for final retention.

The NRC inspectors reviewed the procedure change to Radwaste Departmental Procedure, RW-1-200,

"Record Preparation, Filing, and. Storage," Revision 1, June 26, 1987, and determined that the procedure requirements for record storage and retention

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were being met.

(Closed) Unresolved Item 382/8706-02:

Procurement and Selection of Packaging - This item was identified in NRC Inspection Report 50-382/87-06'

and involved the licensee possibly not applying to the Director, Office of Nuclear Material Safety and Safeguards, in writing, to u p spccific certified shipping packages prior the licensee's first use.

The licensee was able to locate copies of the their application and the NRC approval letter licensing LP&L as a licensed user of specific certified shipping packages prior to their use by the licensee during 1986.

The NRC inspectors reviewed the required documents and determined that the licensee had made application and received approval to use specific certified shipping packages prior to their use.

3.

Followup On Licensee-Identified Problem (92705)

Contaminated Environmental Drinking / Surface Water Samples:

Environmental drinking / surface water samples composited between January 18 and February 15, 1988, were found to be potentially contaminated with Cs-134

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and Cs-137 by the licensee's environmental contractor laboratory.

The licensee has investigated the problem and determined that the source of

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the contamination was a contaminated bottle of 6N hydrochloric acid used l

l to acidify the environmental samples prior to shipping them to the offsite l.

laboratory for analysis.

The licensee self-identified the potential

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violation regarding the transfer of an unknown amount of licensed radioactive material to an offsite laboratory.

The NRC inspectors have reviewed the results of the licensee's investigation of this self-identified problem and find the licensee's evaluation, immediate corrective actions, and actions initiated to prevent a recurrence of the

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incident satisfactory to meet the requirements of 10 CFR Part 2,

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l Appendix C, and therefore, a Notice of Violation will not be issued.

4.

Open Items Identified During This Inspection An open item it a matter that requires further review and evaluation by i

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the NRC inspector.

Open items are used to document, track, and ensure

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adequate followup on matters of concern to the NRC inspector.

The following open item was identified:

Open Item Title Paragraph

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382/8805-01 Post Accident Sampling System

t (PASS)

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Inspector Observations The.following are observations.the NRC inspectors discussed with the licensee during the exit interview on March 11, 1988.

These observations are not violations, deviations, unresolved items, or open items.

These observations were-identified for licensee consideration for program improvement, but the observations have no specific regulatory requirements.

The following observations are identified in paragraphs 8 and 11 of this report.

The licensee stated that these observations would be evaluated.

a.

Quality Control Charts - The licensee had not established criteria to identify and evaluate data biases in daily or periodic quality control analyses of water chemical parameters (see paragraph 8).

b.

Quality Assurance of Contractor Laboratory - The licensee was not including in the audit of the licensee's contractor laboratory a detailed review of the laboratories quality control program for specific contract radioanalytical analyses (see paragraph 11).

6.

Organization and Management Controls (83722/83522)

The NRC inspectors reviewed the licensee's organization, staffing, identification and correction of program weaknesses, audits and appraisals, communication to employees, and documentation and implementation of the chemistry / radiochemistry section (C/RS) to determine adherence to commitments in Chapter 13 of the Final Safety Analysis Report (FSAR) and the requirements in Section 6.2 of the Technical Specifications (TS).

The NRC inspectors verified that the organizational structures of the corporate nuclear operations and support assessment (NOSA) organization and the Wat-3 C/RS were as defined in the FSAR and TS.

The N0SA and C/RS staff assignments and management controls were reviewed for the assignment of responsibilities for the management and implementation of the corporate t

N0SA chemistry / radiochemistry group and the Wat-3 chemistry / radiochemistry programs.

The NRC inspectors verified that the administrative control and program implementing responsibilities specified in the FSAR and Wat-3 procedures were being implemented.

The NRC inspectors reviewed the staffing of the corporate N0SA d emistry/ radiochemistry group and the Wat-3 C/RS.

It was noted that the staffing of the N0SA chemistry / radiochemistry group had been reduced to one position since the previous NRC inspection in this area in October 1986.

The N0SA chmistry/ radiochemistry group had lost both previous staff members and the Wat-3 C/RS had lost its secondary chemistry engineer, secondary chemistry supervisor, and six chemistry technicians.

The one N0SA chemist position had been filled by the former secondary chemistry supervisor, the secondary chemistry engineer position was filled by one of the former N0SA chemists, and the secondary chemistry supervisor position had been filled by one of the senior chemistry technicians.

The

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-5-six chemistry technician position vacancies had been filled with new personnel.

Four of the six new chemistry technicians had no prior nuclear power plant chemistry experience.

The NRC inspectors determined that the N05A chemistry / radiochemistry group had experienced a 100 percent turnover in personnel and the C/RS personnel turnover had been approximately 50 percent in the past 16 months.

The Wat-3 staffing of the N N A chemistry / radiochemistry group and C/RS was determined to be in accordance with licensee commitments.

No violations or deviations were identified.

7.

Training and Qualifications (83723/83523)

The NRC inspectors 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, new employees, Institute of Nuclear Power Operations (INP0) accreditation, and audits and appraisals to determine adherence to commitments in Chapter 13 of the FSAR and the requirements in Sections 6.3 and 6.4 of the TS.

The NRC inspector reviewed the education and experience of the present corporate N05A chemistry / radiochemistry personnel and Wat-3 C/RS staff and determined that all but four recently hired chemistry technicians met the experience qualification requirements of ANSI N18.1-1971.

The NRC inspectors also verified that all the C/RS personnel met the required qualifications specified in the FSAR, TS, and position 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.

l THe NRC inspectors reviewed the licensee's training program for C/RS

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personnel including a review of the chemistry training instructor's l

qualifications, training facilities, chemistry technician training l

procedure, chemistry technician training course descriptions, chemistry training schedules for 1987 and 1988, and C/RS personnel training records.

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The NRC inspectors found that the licensee's chemistry training program l

was being implemented and documented in accordance with Wat-3 procedures,.

It was determined that the Wat-3 nuclear training department had received INP0 accreditation.

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No violations or deviations were identified.

8.

Light Water Reactor Water Chemistry Control and Chemical Analysis (79701/79501)

The NRC inspectors reviewed the licensee's water chemistry program l

including establishment and implementation of a water chemistry control l

program, sampling, facilities and equipment, establishment and implementation of a quality control program for chemical measurements, and

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-6-water chemistry confirmatory measurements to determine adherence to.

commitments in Chapters 5, 9, 10, and 11 of the FSAR and the requirements in Sections 3/4.4.6, 6.8.1, and 6.8.4 of the TS.

The NRC inspectors' review of the water chemistry program found that the licensee had revised and approved administrative procedures, surveillance procedures, chemical control procedures, instrument calibration and quality control procedures, and analytical procedures.

A review of selected procedures revised and written since the previous NRC inspection in October 1986 indicated that the C/RS had established sufficient programmatic procedures to meet the requirements of the FSAR and TS.

The NRC inspectors inspected the facilities and equipment used by the C/RS staff.

The following facilities were inspected: water chemistry laboratory, radiochemistry laboratory, radiochemistry counting room, and health physics counting room.

The laboratories and counting rooms were equipped with the necessary chemicals, reagents, labware, and analytical instrumentation to perform the required analyses.

The NRC inspectors reviewed selected chemistry department procedures for operation, calibration, and quality control of the instrumentation used for analysis of the NRC water chemistry standards to determine the adequacy and effectiveness of the licensee's chemistry measurement quality control program.

It was observed that the licensee was using quality control charts to trend quality control data collected from daily or periodic quality control analyses of chemical parameters.

However, the licensee had not established, in the water chemistry quality control program, criteria to identify and evaluate data biases in calibration and quality control data and changes or trends in instrument performance.

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This observation was discussed with the licensee during the inspection and

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at the exit interview.

The licensee agreed to evaluate the NRC l

inspectors' observation and consider actions for program improvements.

t During the inspection, standard chemical solutions were provided to the i

l licensee for confirmatory measurements analyses.

The standards were analyzed by the licensee using routine methods and equipment.

The results of the measurement comparisons are summarized in Attachments 1, 2, and 3 to this report.

No violations or deviations were identified.

9.

Quality Assurance and Confirmatory Measurements for In-plant Radiochemical l

Analysis (84725/84525)

The NRC inspectors reviewed the licensee's radiochemical analysis program including procedures, facilities and equipment, implementation of a quality control program, PASS sample analyses, and radioanalytical confirmatory measurements to determine adherence to commitments in Chapters 5, 9, and 11 of the FSAR and the requirements in l

Sections 3/4.4.6, 6.8.1, and 6.8.4 of the TS.

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The NRC inspectors reviewed selected procedures and documents revised and approved since the previous NRC inspection in October 1986 and determined that the licensee had established and implemented sufficient programmatic procedures to meet the FSAR and TS requirements.

The NRC inspectors reviewed the licensee's records for the period January through December 1987 involving instrument calibration and quality control.

It was verified that the radiochemistry counting room instruments had been calibrated according to procedures and an instrument quality control program had been implemented.

The NRC inspectors verified that the PASS equipment and associated.

procedures satisfied the requirements of NUREG-0737, Item II.B.3, for representative sampling and analysis of reactor coolant and containment atmosphere following a reactor incident.

Since the previous NRC inspection of PASS in October 1986, the licensee has installed a newly designed PASS operating panel and has been performing a test program on the PASS modifications to demonstrate the proper functioning of all the PASS equipment.

The licensee demonstrated PASS operability by collecting several diluted samples of reactor coolant.

However, it was noted that the new modifications have not corrected the problem of being able to degas the reactor coolant sample and perform an accurate analysis of the reactor coolant dissolved hydrogen and radioactive gaseous isotopes.

The root cause of this sampling problem has been determined to be gas sample leakage past the solenoid sampling valves due to design defects which do l

not allow the sampling valves to seat properly.

The licensee is presently

having a valve manufacturer design a different type of valve for this specific sampling application.

The licensee has not been able to completely test and declare the PASS totally available for use.

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the NRC inspectors determined that the licensee had completed testing of all other functions of the PASS and could collect reactor coolant and containment atmosphere samples for analysis.

This item is considered an open item pending licensee completion of the modifications to the PASS and successful testing of the reactor coolant degasification portion of the PASS.

(382/8805-01)

During the inspection, radiological confirmatory measurements were l

performed on standards and split samples by the licensee and the NRC j

inspectors in the Region IV mobile laboratory.

The standards and samples l

were analyzed by the licensee using routine methods and equipment.

The results of the measurements comparisons are summarized in Attachments 1, t

4, and 5.

No violations or deviations were identified.

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10.

Quality Assurance Program (79701/79501; 84725/84525)

The NRC inspectors reviewed the licensee's N0SA surveillance and QA l

surveillance and audit programs regarding C/RS activities to determine l

adherence with commitments in Chapter 13.4 of the FSAR and the requirements in Section 6.5.2.8 of the TS.

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ATTACHMENT 1

2.

Rgdigiggigg[_Cggficegigty_dggsytgeggig Confirmatory measurements were performed on the following standards and samples in the Region IV mobile laboratory at Waterford-3 Steam Electric Station during the inspection:

(1)

Reactor Coolant Liquid Sample (20 ml Scintillation Vial)

(2)

Reactor Coolant Gas Sample (33 cc Gas Sphere)

(3)

Particulate Filter Standard (47 mm Filter 24838-109)

(4)

Scott Charcoal Cartridge Sample (5)

Liquid Waste Sample (1 liter Marinelli Beaker)

(6)

Waste Gas Tank

"C" Gas Sample (33 cc Gas Sphere)

(7)

Waste Gas Tank

"C" Gas Sample (33 cc Gas Sphere)

(8)

Reactor Coolant Tritium Sample (20 ml Scintillation Vial)

(9)

Charcoal Cartridge Sample F&J Type The confirmatory measurements tests consisted of comparing measurements made by the licensee and the NRC mobile laboratory.

The NRC's mobile laboratory measurements are referenced to the National Bureau of Standards (NBS) by laboratory intercomparisons.

Confirmatory measurements are made only for those nuclides identified by the NRC as being present in concentrations greater than 10 percent of the respective isotopic values for liquid and gas concentrations as stated in 10 CFR Part 20, Appendix B,

Table II.

Attachment 5 contains the criteria used to compare results.

At the time of the inspection, the licensee had three detectors in the radiochemistry counting room and two detectors in the health physics counting room.

One of the radiochemistry counting room detectors was out of service.

All five detectors are used for routine isotopic analysis of radioactive samples to demonstrate compliance with TS and j

regulatory requirements.

The detectors labeled (1) and (3) are located and maintained in the radiochemistry counting room and are primarily used for isotopic analysis of reactor coolant system samples.

The detectors labeled (0) and (H) are located and maintained in the health physics counting room and are used primarily for isotopic analysis of radioactive waste samples and building atmosphere.

The licensee performed the tritium analysis on their l i qui d scintillation counting system.

The individual sample analyses f

and comparison of analytical results of the confirmatory measurements are tabulated in Attachment 4 The licensee's chemistry section gamma isotopic results from the listed samples in Attachment 4 showed 100 percent agreement with the NRC's analysis results and the licensee's health physics section gamma isotopic results from the listed samples showed 94 percent agreement with the NRC's analysis results.

The licensee's tritium result was in agreement with the NRC's analysis result.

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BIIGCUDENI_1 enetyti cal _Meenuteeeeta 1.

Watec _Cheei nttr_Coc titeetoty _deanuteeno tn During the inspection, standard chemical solutions were provided to the licensee for analysis.

The standard solutions were prepared by the Brookhaven National Laboratory (BNL), Safety and Environmental Protection Division, for the NRC.

The standards were analyzed by the licensee using routine methods and equipment.

The analysis of chemical standards is used to verify the licensee's capability to monitor chemical parameters in various plant systems with respect to Technical Specification requirements and other industry standards.

In addition, the analyses of standards are used to evaluate the licensee's analytical procedures with respect to accuracy and precision.

The results of the measurements comparison are listed in Attachment 2.

Attachment 3 contains the criteria used to compare results.

All standards were analyzed in triplicate.

The licensee's original analytical results indicated that 21 of the 30 results were in agreement.

Two chloride results and one sulfate result were originally found in disagreement.

The licensee's chloride quality control standard read low and the sulfate quality control standard read high.

The licensee recalibrated the ion chromatograph and reran the chloride and sulfate standards.

The rerun result for the low chloride concentration remained in disagreement, but the rerun results for the sulfate c.oncentrations were all in agreement.

The licensee's original fluoride results were all in disagreement.

The licensee reconditiond the selective ion electrode and reran the fluoride standards.

The rerun result for the high fluoride concentration remained in disagreement.

The licensee's original high concentration result for iron was biased low and in disagreement.

There was not enough BNL standard to attempt a rerun.

The licensee's original low concentration result for ammonia was biased high as was the ammonia quality control standard.

The licensee prepared a new dilution of BNL standard 86M for the low concentration range and reran the ammonia analysis.

The rerun result for ammonia was in agreement.

The licensee's original mi d-r ange concentr at i on result for hydrazine was biased low as was the hydrazine quality control standard.

The licensee recalibrated the spectrometer for hydrazine and ceran the BNL hydrazine standards.

The rerun results for hydrazine were all in agreement.

The unresolved disagreements are not considered to indicate any significant programmatic problems.

The licensee's final analysis results showed 90 percent agreement with the DNL results based on 27 agreement results out of 30 total results compared.

As pa-t of the inspection, actual inplant samples were split between the licensee and the NRC in ordar to verify the licensee's measurement c apabi l i ti es on actual plant water samples.

The analyses will be performed by the licensee using their normal analytical methods and instrumentation and by BNL.

Upon completion of the analyses by b o t'h laboratories, the results will be documented in a subsequent NRC inspection repor.

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The NRC inspectors reviewed-the surveillance and audit schedules for 1987 and 1988, N0SA and QA surveillance and audit plans and checklists, and the qualifications of surveillance inspectors and auditors.

Surveillances and audit reports of N0SA and QA activities performed during 1987 in the areas of secondary chemistry, radiochemistry, chemistry training, and PASS were reviewed for scope to ensure thoroughness'of program evaluation.

The NRC inspectors noted that the N0SA surveillances and QA surveillances and audits were designed to determine compliance with the FSAR, TS, and Wat-3 procedures.

The NRC inspectors verified that surveillance and audit

' Ndings had been reviewed by licensee's management and that responses and 3riective actions to findings had been documented in accordance with QA oco.edures. The NRC inspectors determined that the surveillances and iadits were performed by qualified personnel knowledgeable in c;tmistry/ radiochemistry activities at nuclear power facilities.

No sfolations or deviations were identified.

11.

Contractor Activities (84725/84525)

The licensN uses a contractor laboratory to perform TS required radiochetistry analyses on several radioactive effluent composite samples.

The licensee's program for oversight of contractor laboratory activities and the quality control of analytical measurements by-the contractor laboratory were reviewed to verify adherence to the requirements in

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Sections 3/4.11 and 6.5.2.8 of the TS and agreement with the recommendations of Regulatory Guide (RG) 4.15.

The licensee performs vendor audits triannually with annual evaluations to retain current status on the qualified vendors list.

The NRC inspectors reviewed the audit performed on the licensee's contractor laboratory in April 1987 and verified that the contractor had been approved for the required analyses and placed on the current qualified vendors list.

It was observed that the area of quality control of radiological monitoring analyses was not addressed in sufficient detail to determine the scope and thoroughness of the audit in this area in regard to specific analyses requeated in the contract by the licensee.

The observation was discussed with the licensee's representatives at the exit interview.

The licensee agreed to evaluate the NRC inspectors' observation.

No violations or deviations were identified.

12.

Exit Interview The NRC inspectors met with the licensee representatives denoted in paragraph 1 at the conclusion of the inspection on March 11, 1988.

The NRC inspectors summarized the scope of the inspection and discussed the inspection findings, inspector observations, and the results of the water chemistry and radiochemistry confirmatory measurements as presented in this report.

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ATTAC51 MENT 1

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Confirmatory measurements were performed by the licensee and a contractor laboratory on two liquid radiochemistry samples prepared by the Radiological Environmental Sciences Laboratory (RESL) in Idaho Falls, Idaho.

The samples were provided to the licensee in July 1987.

The analytical results were compared to the known sample activities and the results of the comparisons are presented in Attachment 4,

sample 10.

The licensee's results were in 100 percent agreement with the certified activities.

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GIIBCbdENI_2 Watet_Cbemistty_Cooliteatoty_dessutements_Besults Waterford-3 SES NRC Inspection Report: 5J-382/88-05 1.

GhlgCi dg_6n glygtg (5-25 ppb)

WAT-3 Results NRC Results WAT-3/NRC Comparison Seente detand

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86A IC 8.4010.50 12.1011.60 0.6910.10 Disagreement 868 18.2010.30 18.7010.60 0.9710.04 Agreement 86C 4.9010.20 4.0310.11 1.22iO.06 Disagreement Rerun 86A 8.5020.60 12.1011.60 0.7110.11 Disagreement 868 18.9010.20 18.7010.60 1.0110.03 Agreement 86C 14.8010.30 16.1010.40 0.9210.04 Agreement 2.

ELU9 Cide _00alYELS (5J-500 ppb)

W'4T-3 Resul ts NRC Results WAT-3/NRC Comparison SaOQl2 UEtDQd (QGk)

(2Rel____

_BatLQ___

_QCGlHLQU_

86A SIE 39.7010.60 46.2011.00 0.8610.02 Disagreement 86B 149.3010.60 174.0018.00 0.8610.04 Di sagreement 86C 137.70!O.60 334.00 11.0 0.4110.10 Disagreement Rerun 86A 49.3011.20 46.2011.00 1.0710.04 Agreement 868 171.7012.90 174.00 8.00 0.9910.05 Agreement 86C 420.0010.00 334.00 11.0 1.2610.10 Disagreement 3.

SulidLE_004LYELE (5-25 ppb)

WAT-3 Results NRC Results WAT-3/NRC Comparison SGOQlt delb9d (Qgb)

(agbl____

_Batig___

_QetL5LgG_

86A IC 9.6010.70 10.0010.50 0.9610.08 Agreement 86B 17.90!O.30 20.5011.20 0.8710.05 D33 agreement 86C 4.8010.40 4.0410.15 1.1910.11 Agreement Rerun 86A 10.2010.70 10.0010.50 1.0210.09 Agreement 06B 19.7010.50 20.5011.20 0.9710.06 Agreement 86C 15.6010.30 16.2010.60 0.9710.04 Agreement

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ATTACHMENT 2

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4.

Ogtgn_Analygis (100-2000 ppm)

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WAT-3 Results NRC Results WAT-3/NRC Comparison Seente detund

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_RetinL90_

86F MT 99.4 0.5 98.911.20 1.0110.01 Agreement 86E 59o.e!2.5 604.819.20 0.99 0.02 Agreement 86F 994.8t2.6 989.4 12.2 1.01 0.01 Agreement 5.

Jtgo_Soglygig (0.5-20 ppm)

WAT-3 Results NRC Results WAT-3/NRC Comparison Saente dethod (aael_____

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_RetinL90_

86G AAF 5.13 0.02 4.8910.35 1.0510.08 Agreement 86H 9.4710.02 9.5510.34 0.99 0.04 Agreement 86I 13.3110.01 14.7010.42 0.9110.02 Disagreement 6.

Cggget_eoelysis (0.5-20 ppm)

WAT-3 Results NRC Results WAT-3/NRC Comparison Seente Methed

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_BetL9___

_ReEisL90_

86G AAF 4.6010.01 4.6810.24 0.98 0,05 Agreement 86H 9.4310.01 9.66!O.49 0.9810.05 Agreement 861 14.2210.03 14.50 0.60 0.98iO.05 Agreement 7.

Sgdium_9nalygig (0.5-5 ppm)

WAT-3 Results NRC Results WAT-3/NRC Comparison Seente dethod

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_RecLnL90_

86J AAF 5.0610.02 4.58 0.50 1.10to.12 Agreement 86K 2.5910.01 2.3110.20 1.1210.09 Agreement 86L 1.5510.01 1.4410.08 1.0810.06 Agreement 8.

9mmgoia_ecalysis (0.5-5 ppm)

WAT-3 Results NRC Results WAT-3/NRC Comparison Seente detugd

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_BatL9___

_RectsL90_

86M SPEC 2.1310.01 1.7510.11 1.2210.08 Disagreement 86N 3.0310.01 3.1410.26 0.9610.08 Agreement 860 5.0310.01 4.69 0.43 1.0710.10 Agreement Rerun 86M 1.94tO.02 1.7510.11 1.1110.07 Agreement

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ATTACHMENT 2

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9.

Hydrazine_ Analysis (5-250 ppb)

WAT-3 Results NRC Results WAT-3/NRC Comparison Samate dethod-

___loabl_____

__1Raul____

_Batio___

_Decistoc_

86P SPEC 21.010.0 22.3 1.4 0.9410.06 Agreement 860 52.310.6 56.910.7 0.9210.02 Disagreement 86R 100.011.0 104.011.0 0.9610.02 Agreement Rerun 86P 21.710.6 22.3 1.4 0.9710.07 Agreement 860 54.011.0 56.910.7 0.9510.03 Agreement 86R 108.010.0 104.011.0 1.0410.02 Agreement 10.

S LLi c a _Analygi s (10-500 ppb)

WAT-3 Results NRC Results WAT-3/NRC Comparison SamRLe dethgd

___1gghl_____

__1gghl____

_Batig___

_DgcLglgG_

865 SPEC 53.310.60 54.31 5.6 0.9810.10 Agreement 86T 109.010.00 109.0 7.0 1.0010.06 Agreement 86U 328.011.00 320.0110.0 1.0310.03 Agreement Analysis Method Definitions:

lon Chromatograph - IC Plazma Emission Spectroscopy - PES Atomic Absorption Graphite Furnace - AAGF Atomic Absorption Flame - AAF Selective Ion Electrode - SIE Manitol Titration - MT Spectroscopy - SPEC t

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OIIOCUDENI_3 CB1IEB10_EQB_CQUEBB10G_000LYIICBL_DEBSUSEdENIS This attachment provides criteria for comparing results of capability tests.

In these criteria the judgement limits are based on the uncertainty of the ratio of the licensee's value to the NRC value.

The following steps are performed the licensee's value to the NRC value is computed (1)

Tne ratio of L i C '"'" ' ' v*l"'

); and (ratio

=

NRC VALUE (2)

the uncertainty of the ratio is propagated.

If the absolute value of one minus the ratio is less than or equal to twice the ratio uncertainty, the results are in agreement.

uncertainty)

(l1-ratio l 1 2 x S

6!

N y

x

=

+

then Z=

,

x2 y2 y

1(From:

Bevington, P.

R., Data Reduction and Error Analysis f or tne Physical Sciences, McGraw-Hill, New York, 1969)

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BII6gdDEUI_4 Sad 19199iGal_C90fiCOa19CY_U2929CE50E01_8E29112 Waterford-3 SES NRC Inspection Report: 50-382/88-05 1.

BEaG19C C991aDt_Liguid_J20GG_SGiOtillati90_Viall (Sampled:

08:05, CST, March 9,

1988)

Sample analyzed by radiochemistry on detector (1).

WAT-3 Results NRC Results WAT-3/NRC Comparison NyGlide

_1gCLLsLL____

_ lu G L Le ll_ _ _ _

_BatLg___

_QggigigG_

1-131 4.428tO.042E-2 4.91710.029E-2 0.90 Agreement 4.54510.022E-2 0.92 Agreement 1-132 1.322tO.OO7E-1 1.39710.OO6E-1 0.95 Agreement 1.25310.OO6E-1 0.90 Agreement I-133 1.239tO.OO5E-1 1.38610.OO4E-1 0.89 Agreement 1.28410.OO3E-1 0.93 Agreement 1-134 1.893tO.025E-1 2.06710.019E-1 0.92 Agreemert 1.717iO.049E-1 0.83 Agreement I-135 1.63310.021E-1 1.75010.015E-1 0.93 Agreement 1.65310.014E-1 0.94 Agreement Cs-134 9.19310.351E-3 1.08910.027E-2 0.84 Agreement 9.449 0.197E-3 0.87 Agreement Cs-137 1.108 0.036E-2 1.138tO.026E-2 0.97 Agreement 1.096tO.018E-2 0.96 Agreement Cs-138 1.72110.039E-1 1.884 0.026E-1 0.91 Agreement 1.75210.181E-1 0.93 Agreement 2.

Reactor Coolant Gas Sample (33cc Gas Sphere)

(Sampled:

10:15, CST, March 9,

1988)

Sample analyzed by radiochemistry on detector (1).

WAT-3 Results NRC Results WAT-3/NRC Comparison UllGlidE

_IMCidGC)

( ttQ L LGGl_.

_64tL9___

_QEGinlOO_

Ar-41 1.31510.084E-2 1.12310.044E-2 1.17 Agreement Xe-133 1.98210.OO2E+0 1.73710.OO1E+0 1.14 Agreement Xe-133m 4.787to.239E-2 4.42010.094E-2 1.08 Agreement

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ATTACHMENT 4

RCS Gas Samole Contid WAT-3 Results NRC Results WAT-3/NRC Comparison NucLtde

_luCLLcci..___

_luCLLcct__

_Batio___

_ Decision _

j Xe-135 4.96410.OO9E-1 4.679 0 OOSE-1 1.06 Agreement Xe-135m 7.57210.169E-2 6.533 0.495E-2 1.16 Agreement Kr-85m 1.115 0.OO4E-1 1.026 0.OO2E-1 1.09 Agreement Kr-87 1.269to.012E-1 1.154 0.OO7E-1 1.10 Agreement Kr-88 2.215tO.014E-1 2.02010.OO7E-1 1.10 Agreement i

3.

eacticulaig_Eiltet_ Standard _ld2_ee_Eillet_24030:1021 (Standardized:

02:00, CST, March 10, 1988)

Standard analyzed by health physics on detectors (0) and (H).

WAT-3 Results NRC Results WAT-3/NRC Comparison Nygligg J.qQLL$dORlel_

19 Cide #Tg[gl

_RgtLg___

_DggisLge_

Cd-109 1.206tO.OO2E+0 1.02910.OO2E+0 1.17 Agreement 1.17810.OO2E+0 1.14 Agreement Co-57 2.768tO.OO7E-2 2. 32910. OO6E-2 1.19 Disagreement 2.694!O.OO9E-2 1.16 Agreement Ce-139 1.73110.OO7E-2 1.48210.OO5E-2 1.17 Agreement 1.67810.OOBE-2 1.13 Agreement Hg-203 9.106to.071E-3 7.994 0.057E-3 1.14 Agreement 8.89310.076E-3 1.11 Agreement Sn-113 2.62610.015E-2 2.21210.011E-2 1.19 Disagreement 2.53619.016E-2 1.15 Agreement Cs-137 5.67510.023E-2 4.574!O.017E-2 1.24 Disagreement 5.41510.023E-2 1.18 Agreement Y-88 3.05910.022E-2 2.53510.016E-2 1.21 Agreement 2.92710.021E-2 1.15 Agreement Co-60 4.510tO.025E-2 3.937to.021E-2 1.15 Agreement 4.3OO10.024E-2 1.09 Agreement

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ATTACHMENT 4

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Scott Charcoal Cartridae Samole (Sampled: 08:20, CST, March 10, 1988)

Sample analyzed by health physics on detectors (0) and (H).

WAT-3 Results NRC Results WAT-3/NRC Comparison Nggligg lygtfSgeglg)

(yQLLSgegLgl

_Battg___

_Qggigigg_

1-131 2.71710.037E-3 2.527 0.031E-3 1.08 Agreement 2.78010.043E-3 1.10 Agreement 1-133 1.52210.034E-3 1.32910.029E-3 1.15 Agreement 1.484dO.035E-3 1.12 Agreement 5.

Liguid_Wastg_Semntg_11_litgr_Mgrinellit (Sampled:

10:35, CGT, March 10, 1988)

Sample analyzed by radiochemistry and health physics on detectors (1),

(O), and (H).

WAT-3 Results NRC Results WAT-3/NRC Comparison NyqLtde

_1ggiLgLl____

_luqLLall__

_89tio___

_QeqLSigg_

Na-24 1.03210.107E-6 1.39710.119E-6 0.74 Agreement 1.503to.139E-6 1.08 Agreement 1.64910.156E-6 1.18 Agreement Mn-54 1.68010.170C-6 1.62510.113E-6 1.03 Agreement 1.73110.127E-4 1.07 Agreement 1.63910.155E-6 1.01 Agreement Cu-58 3.123dO.035E-5 2.99310.028E-5 1.04 Agreement 3.231do.035E-5 1.08 Agreement 3.59910.037E-5 1.20 Agreement Co-60 4.15710.179E-e 4.30720.133E-6 0.97 Agreement 4.47810.164E-6 1.04 Agreement 5.24010.166E-6 1.22 Agreement I-131 3.175tO.031E-5 3.31410.028E-5 0.96 Agreement 3.29610.035E-5 0.99 Agreement 3.34810.035E-5 1.01 Agreement 1-133 1.41110.025E-5 1.44810.025E-5 0.97 Agreement 1.509tO.041E-5 1.04 Agreement 1.502tO.042E-3 1.04 Agreement Cs-134 2.49220.036E-5 2.526tO.028E-5 0.99 Agreement 2.50910.032E-5 0.99 Agreement 2.528!O.032E-5 1.00 Agreement Cs-137 3.190tO.040E-5 3.319AO.032E-b O.96 Agreement 3.251tO.037E-5 0.98 Agreement 3.345tO.038E-S 1.01 Agreement

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ATTAdHMENT 4

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6.

Waste Gas Tank

"C" Gas Sample (33cc Gas Bulb)

(Sampled:

13:05, CST, March 9, 1988)

Sample analyzed by radlochemistry on detectors (1) and (3).

WAT-3 Results NRC Results WAT-3/NRC Comparison Nyg[(dg

_jyQifgg)

(yQifqq)

Rgtig___

_Qggigigg_

Kr-85m 9.74611.211E-5 9.502!O.681E-5 1.03 Agreement 1.060tO.138E-4 1.12 Agreement Kr-85 8.01911.334E-3 9.157 0.430E-3 0.88 Agreement 1.082tO.121E-2 1.18 Agreement Xe-131m 5.474tO.381E-3 6.336 0.167E-3 0.86 Agreement 7.113tO.371E-3 1.12 Agreement Xe-133m 2.15610.057E-3 2.19110.032E-3 0.98 Agreement 2.369tO.086E-3 1.08 Agreement Xe-133 3.602tO.OO3E-1 3.31110.OO1E-1 1.09 Agreement 3.759tO.OO3E-1 1.14 Agreement Xe-135 3.255to.020E-3 3.241!O.010E-3 1.00 Agreement 3.318!O.024E-3 1.02 Agreement 7.

Waste Gas Tank

"C" Gas Sample (33cc Gas Bulb)

(Sampled:

17:24, CST, March 10, 1988)

Sample analyzed by health physics on detectors (0) and (H).

WAT-3 Results NRC Results WAT-3/NRC Comparison Nygildg

_1gGidqcl____

_1gGLLqql__

_80tig___

_QggigLge_

Kr-85 1.14910.102E-2 9.26310.531E-3 1.24 Agre(ment 9.43311.129E-3 1.02 Agreement Xe-131m 5.930tO.454E-3 6.866tO.230E-3 0.86 Agreement 7.642!O.524E-3 1.11 Agreement Xe-133m 1.75510.070E-3 1.579tO.034E-3 1.11 Agreement 1.82510.079E-3 1.16 Agreement Xe-133 3.48410.OO5E-1 2.99810.OO2E-1 1.16 Agreement 3.49310.OO6E-1 1.17 Agreement Xe-135 4.207tO.112E-4 4.116tO.053E-4 1.02 Agreement 4.52810.153E-4 1.10 Agreement 8.

Rgqqtqt_Qgglen(_ItL(LgO_SqcgLg_12Q_OL_SGiOLLLlatLQG_YL4LL (Sampled:

08: 08, CST, March 9,

1988)

WAT-3 Results NRC Results WAT-3/NRC Comparison Nyt[Lde

_1gCtLOL)

(uCLLOLL.,_

_Rettg___

_Qqqlgtgg_

H-3 4.789E-2 5.59910.106E-2 0.86 Agreement i

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ATTACHMENT 4

9.

Charcoal Cartridae Sample F&J Type (Sampled: 14:05, CST, March 10, 1988)

Sample analyzed by health physics on detectors (0) and (H).

WAT-3 Results NRC Results WAT-3/NRC Comparison Nuclide luCilScTale)

(uCilSamalel

_Batic___

_Decis190_

1-131 2.10110.034E-3 1.744 0.059E-3 1.20 Agreement 2.083 0.037E-3 1.19 Agreement I-133 1.59110.038E-3 1.33110.068E-3 1.20 Agreement 1.70710.042E-3 1.28 Agreement 10.

RESL_Ugkagwg_Liguid_Sgmglg ( St andardi z ed :

12:00, MST, January 11, 1987)

WAT-3 Results NRC Results WAT-3/NRC Comparison NWGlide

_19Ci/01)

(9C12011__

_89119___

_DeGlDiDO_

Mn-54 2.60E-5 2.3710.05E-5 1.10 Agreement Co-60 2.08E-5 2.27 0.05E-5 0.92 Agreemenf Cs-137 3.55E-5 3.341>.10E-5 1.06 Agreement Fe-55 7.OO!O.50d-5 8.1610.16E-5 0.85 Agreement Sr-89 1.70to.10E-4 1.8310.05E-4 0.93 Agreement Sr-90 1.70 0.10E-5 1.65to.07E-5 1.03 Agreement H-3 1.22E-4 1.34!O.03E-4 0.91 Agreement Fe-59 5.6610.23E-6 NRC results were taken from the standard certification supplied to the NRC Region IV office as prepared by RESL and traceable to the National Bureau of Standard +..'

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GIIeCbdEUI_D CBIIEBle_EDB_CQ5EeBIND_eSeLyIICeL_DEe5UBEDEUIS The following are the criteria used in comparing the results of ccpability tests and verification measurements.

The criteria are based on an empirical r el at i onshi p established through prior cxperience and this program's analytical requirements.

In these criteria, the judgement limits vary in relation to the comparison of the resolution.

NRC VALUE Resolution

=

NRC UNCERTAINTY LICENSEE VALUE Ratio

=

NRC VALUE Comparisons are made by first determining the resolution and then The reading across the same line to the corresponding ratio.

f ollowing table shows the acceptance values.

AGREEMENT RATIO RESOLUTION 0.40 - 2.50

<4 0.50 - 2.00 4-7 0.60 - 1.66 8-

0.75 - 1.33 16 - 50 0.80 - 1.25 51 - 200 0.85 - 1.18

>200 The above criteria are applied to the f ollowing analyses:

,

(1) Gamma Spectrometry l

(2) Tritium in liquid samples I

(3) Iodine on adsorbers (4)

Sr and Sr determinations

.

Gross Bete where samples are counted on the same date using (5) the same reference nuclide.

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