IR 05000382/1986020

Insp Rept 50-382/86-20 on 861027-31.No Violations or Deviations Noted.Major Areas Inspected:Chemistry/ Radiochemistry Program,Including Review of Corporate & Onsite Organizations & Mgt Controls

ML20215D848
Person / Time
Site:	Waterford
Issue date:	11/26/1986
From:	Murray B, Nicholas J, Wise R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20215D828	List: IR 05000382/1986020 ML20215D826
References
50-382-86-20, NUDOCS 8612170065
Download: ML20215D848 (16)

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APPENDIX $

. U.S. NUCLEAR REGULATORY COMMISSION s

[ REGION IV  ;

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NRC Inspection Report

50-382/86-20 License: NPF-38

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Docket: 50-382 -

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, Licensee: Louisiana Power and Light Company (LP&L) I g 317 Baronne Street  ;

w br n L uisiana 70160 b

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Facility Name: Waterford Steam Electric Station, Unit 3 (Wat-3) 1 l c Inspection At: Taft, St. Charles Parish, Louisiana l

l Inspection Conducted: October 27-31, 1986

{ A I Inspectors: //M4/M J'

ff B. Nicholas, Sdnior Radiation Specialist Date I L gacilities Radiological Protection Section I

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p R. Wise, Radiation Specialist, Facilities Date 2 g Radiological Protection Section  :

b Approved: , aM4/d a B.flurray, Chief, Facilities Radiological Date '5 E (#rotection Section -

E I Inspection Summary

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i Inspection Conducted October 27-31, 1986 (Report 50-382/86-20) e

! i j Areas Inspected: Routine, unannounced inspection of the licensee's 5 l chemistry / radiochemistry program including review of corporate and onsite '

g organizations and management controls, staffing and staff qualifications, ;

training program, chemistry / radiochemistry program, facilities and equipment, -

F postaccident sampling system (PASS), quality assurance (QA) program of j

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chemistry / radiochemistry activities, quality control of analytical 3

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measurements, and radiochemistry confirmatory measurement L -

i Results: Within the areas inspected, no violations or deviations were j

? identifie r PDR ADOCK 05000382 3 G PDR _'

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-2- l DETAILS

.1.- Persons Contacted LP&L

• R._P. Barkhurst, Vice~ President-Nuclear, Nuclear Operations

• N. S. Carns, Plant Manager

• D. E. Adams, Chemistry / Radiochemistry Unit Coordinator, Nuclear Support

• S. A. Alleman, Assistant Plant Manager

• R. E. Allen, Chemistry Engineer C. R. Booth, Chemist

• K. L. Brewster, Licensing Engineer

^ L. Dolese, Radiochemistry Supervisor L. J. Dauzat, Health Physics Technician D. W. Gamble, Instruments and Controls Engineer, Project Engineering

• T. O. Gray, QA Supervisor, Operations

• R. B. Herrington, Chemistry Technician

• D. L. Hoel, Health Physics Supervisor M. L. Layton, Secondary Chemistry Supervisor

• A. S. Lockhart, Site Quality Manager D. C. Madere, Chemistry Technician

• J. V. Messina, QA Representative,- Operations J. M. O'Hern, Technical Training Superintendent W. N. Perry, Chemistry Training

• P. V. Prasankumar, Acting Radiation Protection Superintendent R. L. Stanley, Chemistry Technician Others

• J. G. Luehman, NRC Senior Resident Inspector

• Denotes those present during the exit briefing on October 31, 198 . Inspector Observations The following are observations the NRC inspectors discussed with the licensee during the inspection and at the exit briefing on October 31, 1986. These observations are neither violations nor unresolved item These items were recommended for licensee consideration for program improvement, but they have no specific regulatory requirement. The licensee stated these items would be reviewe Chemistry / Radiochemistry Training Records - The initial training / qualification cards for all Wat-3 chemistry technicians and current contractor chemistry technicians had not been completed and transmitted to the nuclear training department for permanent record storage (see paragraph 5).

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b .' Postaccident Sam >1ina System - The leaks and equipment malfunctions:

associated with > ASS had not been repaired and a frequent surveillance program had not been established to ensure system reliability (see-paragraph 8). ' Confirmatory Measurements - The licensee was unable to analyze an NRC prepared radioactive charcoal cartridge standard for quantitative isotopic content with satisfactory agreement to certified values (see paragraph-10.b). Contractor Laboratory Analytical Results - The licensee had not reviewed contractor laboratory analytical results which were in disagreement with known isotopic concentrations (see paragraph 11).

3. Chemistry / Radiochemistry Organization-and Management Controls The NRC inspectors reviewed the licensee's corporate and Wat-3 organizations and staffing regarding chemistry / radiochemistry activities to determine adherence to commitments in Chapter 13 of the Final Safety Analysis Report (FSAR) and requirements in Section 6.2 of the Technical Specifications (TS).

The NRC. inspectors verified that the organizational structures of the corporate' nuclear support organization and the Wat-3 chemistry / radiochemistry section.(C/RS) were as defined in the FSAR and TS and unchanged from previous NRC inspections. The corporate and C/RS staff assignments and management controls were reviewed for the assignment of responsibilities for the management and implementation of the corporate nuclear support chemistry section and the Wat-3 chemistry / radiochemistry programs. It was verified that the administrative control responsibilities specified by the Wat-3 procedures were being implemente The NRC inspectors reviewed the staffing of the corporate nuclear support chemistry section and the Wat-3 C/RS and noted that the corporate nuclear chemistry section was fully staffed and the two staff members were the same as reported in previous NRC inspection reports. Since the previous NRC inspection in December 1985, the Wat-3 C/RS had lost its radiochemist and two chemistry technicians. The two chemistry technician positions had been filled and the radiochemist position is to be filled in November 198 The corporate nuclear support chemistry section and Wat-3 C/RS organizational structures and staffing were determined to be in accordance with licensee commitment No violations or deviations were identifie . Chemistry / Radiochemistry Personnel Qualifications The NRC inspectors reviewed the qualifications of the corporate nuclear support chemistry personnel and Wat-3 C/RS personnel to determine adherence to commitments in Chapter 13 of the FSAR and requirements in Section 6.3 of the T ,

-4-The NRC inspectors reviewed the education and experience backgrounds of the present corporate nuclear support chemistry personnel and Wat-3 C/R personnel and verified that they met the required qualifications specified in the FSAR, TS, and position descriptions. It was determined that all of the present corporate and Wat-3 C/RS staff satisfied the ANSI N18.1-1971 qualifications. .The NRC. inspectors also verified that the four contractor personnel used to support chemistry / radiochemistry activities were qualified in accordance with FSAR and TS requirements. The licensee appeared to have an adequate qualified staff to meet shift staffing requirement No violations or deviations were identifie . Chemistry / Radiochemistry Training Program The NRC inspectors reviewed the licensee's chemistry / radiochemistry training program to determine adherence to commitments in Chapter 13 of the FSAR and the requirements in Section 6.4 of the T The NRC inspectors reviewed the training department organization, chemistry training instructor qualifications, training facilities, implementing procedures, C/RS training schedule, annual requalification training, and the continuing training program. The topics for the 1986 continuing training program were reviewed including lesson plans and course examinations. The licensee's chemistry training and qualification program was being implemented in accordance with the Wat-3 Administrative Procedure CE-01-001, " Training and Qualification of Chemistry Department Personnel," Revision 2, August 15, 198 The NRC inspectors reviewed the C/RS individual staff training records and determined that the 1986 continuing training and qualification training were being completed and documented in accordance with procedur The licensee had conducted PASS annual requalification training for all C/RS staff onsite prior to April 198 A review of the C/RS staff qualification cards indicated that the initial qualification cards for chemistry technicians hired prior to January 1985 had been transmitted to the nuclear training department for permanent record. The initial qualification cards for five Wat-3 chemistry technicians and three contractor chemistry technicians hired since January 1985 have not been completed. The NRC inspectors discussed this observation with the licensee during the inspection and at the exit briefing. The licensee stated that they would review the eight initial qualification cards which had not been completed at the time of the inspectio No violations or deviations were identifie . Chemistry / Radiochemistry Program The NRC inspectors reviewed the licensee's chemistry / radiochemistry program to determine adherence to commitments in Chapters 5, 9, 10, and 11 of the FSAR and in Section 3/4.4.6 of the T ,cm y ~

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The NRC . inspectors' review of the chemistry / radiochemistry 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 Lreview of selected procedures revised since the previous'NRC inspection in December 1985 indicated that the C/RS had established sufficient programmatic procedures to meet the requirements of the FSAR and T No violations or: deviations were-identifie . Facilities and Equipment The NRC inspectors. inspected the facilities and equipment used by the C/RS staf The facilities and equipment inspected had not been changed since the previous NRC inspection of these areas in December 198 The NRC inspectors noted that the hydrogen and oxygen gas analyzer has been out of service since. March 22, 1985. There have been many attempts to fix and modify the system and put it back in service. -The gas analyzer and its function are required to satisfy TS 3.3.3.11 and surveillance i requirement 4.3.3.11 for waste gas holdup system explosive. gas monitorin ~The out-of-service gas analyzer has resulted in one NRC violation, one licensee event report, and several QA findings as a result of internal audits. The NRC inspectors were informed that the problem was receiving high priority evaluation and that the gas analyzer was expected to be modified and repaired during the plant outage in November 198 No violations or deviations were identifie . Postaccident Sampling System The NRC inspectors reviewed the licensee's PASS to determine adherence to requirements of NUREG-0737, Item II.B.3 and Section 6.8.4.d of the TS.

The NRC inspectors verified that the PASS equipment and operating procedures met the requirements of NUREG-0737, Item II.B.3, and TS for representative sampling and analysis of reactor coolant and containment

. atmosphere following a reactor incident. The licensee had completed PASS

! operator training for eight chemistry technicians as part of their shift qualification training and established an annual requalification training

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program on PASS.

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The NRC inspectors verified the licensee had implemented an in-line instrument calibration and preventative maintenance program in compliance

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with TS requirements. The licensee's PASS calibration and maintenance

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program is administered by the issuance of task cards semiannually. The NRC inspectors reviewed the in-line instrument calibration record The licensee demonstrated PASS operability by collecting a diluted sample of reactor coolant and performing analyses including pH, dissolved oxygen, boron, and gamma isotopic and comparing the results of these analyses with

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-6-reactor coolant grab sample analysis results. The results which were compared were in satisfactory agreemen The licensee attempted to collect an undiluted reactor coolant sample in the cask sampling device for shipment offsite for chloride analysi A leak developed at the lower quick disconnect on.the sampler and sampling activities were suspended due to airborne and liquid contamination of the PASS sampling area. A Condition Identification Work Authorization was written to investigate, repair, and test the leaking connection. The licensee also collected and analyzed a containment atmosphere sample for gamma isotopic conten During the sampling of containment atmosphere, several problems were noted concerning light . indicators for valve operation and positio These observed problems of leakage and equipment malfunction were discussed with the licensee during the inspection and at the exit briefing. These problems indicate that a more frequent surveillance and preventative maintenance program.may be required to demonstrate reliability of the PASS equipment to operate successfully on deman The NRC inspectors discussed with the licensee the major modifications to be made to the PASS during the November 1986 plant outag These modifications are a result of determining, during testing and operation of the PASS in December 1985, that the phase separator for hydrogen stripping from the reactor coolant sample was not operating correctly. Several major components of the PASS are to be modified or replaced which will require new operating procedures, complete acceptance testing of the PASS, and requalification operator training of the chemistry technicians prior to exceeding 5 percent power following plant restart after the plant outag No violations or deviations were identifie . Quality Assurance Program The NRC inspectors reviewed the licensee's QA audit program regarding chemistry / radiochemistry activities to determine adherence to commitments in Chapter 17 of the FSAR and the requirements in Section 6.5.2.8 of the T The NRC inspectors reviewed the QA department organization and recent changes in personnel and their responsibilities, audit schedule for 1986 and 1987, QA auditor qualifications, and audit reports. Audit reports generated from QA activities during 1986 in the areas of primary water chemistry and secondary water chemistry were reviewed for scope to ensure thoroughness of chemistry / radiochemistry program evaluation and timely followup of identified deficiencies. The NRC inspectors determined that the audit plans and checklists were comprehensive and that the responses and corrective actions to audit findings were timel The NRC inspectors found that the QA audit program appeared to be adequat No violations or deviations were identifie l

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-7-10. Analytical Measurements Confirmatory Measurements Confirmatory measurements were performed on the following standards and samples in the NRC Region IV mobile laboratory at the Wat-3 site during the inspection:

(1) NRC Particulate Filter Standard (SRS-21478-109)

(2) NRC Cesco Charcoal Cartridge Standard (SRS-21421-109)

(3) NRC Scott Charcoal Cartridge Standard (SRS-21420-109)

(4) Waste Gas Sample (1 Liter Gas Marinelli Beaker)

(5) Waste Liquid Tank "B" (1 Liter Liquid Marinelli Beaker)

(6) -Reactor Coolant System Gas (30 cc gas bulb)

(7) Reactor Coolant System Degassed Liquid (20 ml Scintillation Vial)

(8) Reactor Coolant System Tritium Sample The confirmatory measurements test 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 intercomparison 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 I Attachment 1 contains the criteria used to compare result 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 roo 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 regulatory requirement The detectors labeled (1) and (2) 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

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-8-their liquid scintillation counting syste The individual sample analyses and comparison of analytical results_of the confirmatory measurements are tabulated in Attachmen The licensee's chemistry section gamma isotopic results from the listed samples in Attachment 2 showed 98 percent agreement with the NRC analysis results and the licensee's health physics section gamma isotopic results from the listed samples showed 82 percent agreement with the NRC analysis results. The highest percentage of disagreements was with the health physics results on the NRC Cesco charcoal cartridge standard analyzed on detector (0). The NRC inspectors discussed these analysis disagreements with the licensee during the inspection and at the exit briefin The licensee agreed to evaluate the calibration of this detector for the charcoal cartridge geometry and take corrective action as necessary. The licensee's tritium result was in agreement with the NRC analysis resul Confirmatory measurements were performed by the licensee on a liquid sample prepared by the Radiological Environmental Sciences Laboratory (RESL) in Idaho Falls, Idaho. The licensee's analytical results were compared to the known sample activities and the results of the comparisons are presented in Attachment 2, sample 9. The licensee's results were in agreement with the certified activities in the sample except for the tritium analysis performed by the Wat-3 C/RS and the 89Sr analysis performed by the licensee's contract laborator No violations or deviations were identifie . Contractor Activities The NRC inspectors determined that the licensee was using four contractor personnel onsite to perform chemical and radiochemical analyses. The licensee had imph aented a program to ensure the qualifications of these contract chemistry technicians. The training / qualification card for each contract chemistry technician was reviewe The licensee was using a contract laboratory to perform the 893p, 903p, and 55Fe analyses on radioactive waste effluent samples required by T The licensee uses the results of the annual RESL confirmatory measurements sample as a quality control check on the contractor laboratory. The NRC inspectors discussed the 89Sr analysis disagreement with the licensee as

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shown in Attachment 2, sample 9, and the licensee agreed to investigate the contract laboratory's analysis result in an attempt to resolve the disagreement.

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No violations or deviations were identified.

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_ . Exit Briefin The NRC inspectors met with the Wat-3 NRC senior. resident inspector and~

the licensee representatives identified in paragraph 1 of this report at

'the conclusion of the inspection on October 31, 1986. The lead NRC

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inspector summarized the scope of the inspection, discussed the inspection

. findings, and presented the results of the confirmatory measurements. The licensee agreed to review the NRC inspectors' observations listed in paragraph . .. . . . . . .. . . . . .. . . . . . . . . . . . . . . . . .. . . . . .

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ATTACHMENT 1

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Criteria for Comparing Analytical Measurements The following 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 requirement In these criteria, the judgement limits vary in relation to the comparison of the resolutio " ^

Resolution =

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 value RESOLUTION AGREEMENT RATIO

<4 0.4 - .5 - .6 - 1.66 .

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

>200 0.85 - 1.18 The above criteria are applied to the following a'halyses:

(1) Gamma Spectrometr (2) Tritium analyses of liquid sample (3) Iodine on adsorber (4) asSr and 80Sr determination (5) Gross Beta where samples are counted on the same date using the same reference nuclid . .

ATTACHMENT 2 CONFIRMATORY MEASUREMENTS RESULTS 1. NRC Particulate Filter Standard (SRS-21478-109)

(Standardized 11:00 CST, October 1, 1986)

Wat-3 Wat-3 Results NRC Results Wat-3/NRC Comparison Nuclide De (uCi/ sample) (uCi/ sample) Ratio Decision s7Co' (1) 4.2110.01E-02 4.0610.01E-02 1.04 Agreement (2) 4.3610.01E-02 1.07 Agreement (0) 5.0210.02E-02 1.24 Disagreement-(H) 4.0610.02E-02 1.00 Agreement 60C0 (1) 3.6310.03E-02 3.5010.02E-02 1.04 Agreement (2) 3.8610.04E-02 1.10 Agreement (0) 3.7710.04E-02 1.08 Agreement (H) 3.4110.04E-02 0.97 Agreement 88Y (1) 1.0110.01E-01 9.6710.03E-02 1.04 Agreement (2) 1.0510.01E-01 1.09 Agreement (0) 1.0310.07E-01 1.07 Agreement (H) 9.4810.07E-02 0.98 Agreement 109Cd (1) 1.6010.01E+00 1.5010.01E+00 1.07 Agreement (2) 1.7010.01E+00 1.13 Agreement (0) 1.9010.01E+00 1.27 Disagreement (H) 1.5510.01E+00 1.03 Agreement 113Sn (1) 7.9110.03E-02 7.1110.02E-02 1.11 Agreement (2) 7.9310.03E-02 1.12 Agreement (0) 8.6010.05E-02 1.21 Disagreement (H) 7.6010.05E-02 1.07 Agreement 137Cs (1) 5.8910.03E-02 5.3010.02E-02 1.11 Agreement (2) 5.8310.03E-02 1.10 Agreement (0) 6.2410.05E-02 1.18 Agreement (H) 5.5710.05E-02 1.05 Agreement 139Ce (1) 4.1510.02E-02 3.8010.01E-02 1.09 Agreement (2) 4.2510.02E-02 1.12 Agreement (0) 4.6510.02E-02 1.22 Disagreement (H) 3.8010.02E-02 1.00 Agreement sosHg (1) 1.1010.01E-01 1.1110.01E-01 0.99 Agreement (2) 1.1110.01E-01 1.00 Agreement (0) 1.2010.05E-01 1.08 Agreement (H) 1.0310.01E-01 0.93 Agreement

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2.- NRC Ce'sco-Charcoal Cartridae-Standard (SRS-21421-109)

.(Standardized 11:00 CST, October 1, 1986)

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Wat-3 Wak.-3' Results' ' NRC Results' Wat-3/NRC; Comparison 7- Nuclide -De (uci/ sample) (uC1/ sample) Ratio Decision s7Co (0) '4.6710.02E-02 . 3.57*0.01E-02 .1.31 Disagreement

.(H)- 3.9410.02E-02 1.11 Agreement-soCo (0) 3.7010.05E-02 - 3.1110.02E-02' 1.19 Disagreement (H)- 3.3410.04E-02 1.07 Agreement asY (0) 9.7810.07E-02 8.5410.04E-02 1.15- Agreement (H) 9.1010.07E-02 1.07 Agreement

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108Cd (0) 1.7310.01E+00 1.3210.01E+00 1.31- Disagreement (H) 1.4910.01E+00 1.13 Agreement 118Sn '(0) 7.9910.05E-02 6.2710.02E-02- 1.27 Disagreement (H) 7.0210.05E-02 1.12 Agreement ~

137cg- (0) 5.~8610.05E-02 4.6810.02E-02 1.25- Disagreement (H) -5.3410.05E-0? 1.14- Agreement 138Ce (0) 4.3010.02E-02' 3.3310.01E-02 1.29 Disagreement (H)- 3.62i0.02E-02 1.09 Agreement 20sHg (0) -1.1010.01E-01 - 8.7910.02E-02 '1.25 Disagreement (H) 9.75*0.05E-02- -1.11 Agreement NRC Scott Charcoal Cartridge Sta'ndard (SRS-21420-109)

-(Standardized 11:00 CST, October 1, 1986)

Wat-3 Wat-3 Results NRC Results Wat-3/NRC Comparison Nuclide De (uCi/ sample) (uCi/ sample) Ratio Decision s7Co '(1) 3.4810.01E-02 3.6210.01E-02 0.96 Agreement

.(2) 3.7810.02E-02 1.04 Agreement 60Co (1) 3.2410.03E-02 . 3.2010.02E-02 1.01 Agreement (2) 3.2610.03E-02 1.02 Agreement s8Y (1) 7.49*0.04E-02 8.7510.04E-02 0.86 Agreement (2) 8.9510.04E-02 1.02 Agreement 109Cd (1) 1.3210.01E+00 1.3510.01E+00 0.98 Agreement (2) 1.4210.01E+00 1.06 Agreement 113Sn (1) 5.5610.03E-02 6.3810.02E-02 0.87 Agreement (2) 6.8110.03E-02 1.07 Agreement

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-3-137Cs (1) ~ 4.8410.03E-02 4.7310.02E-02 1.02 Agreement (2) 5.0910.03E-02 1.08 Agreement 139Ce (1) 3.1210.01E-02 3.3710.01E-02 0.93 Agreement (2) 3.4710.02E-02 1.03 Agreement 20sHg (1) 6.0610.02E-02 8.9210.02E-02 0.68 Disagreement (2) 9.1910.03E-02 1.03 Agreement 4. Waste Gas Sample (1 Liter Gas Marinelli Beaker)

(Sampled 14:12 CST, October 28, 1986)

Wat-3 Wat-3 Results NRC Results Wat-3/NRC Comparison Nuclide De (uCi/cc) (uCi/cc) Ratio Decision asmKr (1) 9.5010.61E-07 9.5610.42E-07 0.99 Agreement (2) 1.0610.07E-06 1.11 Agreement (0) 1.0510.08E-06 1.10 Agreement (H) 9.7110.76E-07 1.02 Agreement 88Kr (1) 1.0610.11E-06 1.0710.12E-06 0.99 Agreement (2) 7.73tl.61E-07 0.72 Agreement (0) 1.2410.20E-06 1.16 Agreement (H) 9.50il.74E-07 0.89 Agreement 133mXe (1) 1.1210.28E-06 1.0210.16E-06 1.10 Agreement (2) 1.3410.27E-06 1.31 Agreement (0) 1.2610.42E-06 1.24 Agreement (H) 1.4110.36E-06 1.38 Agreement 13 axe (1) 3.6910.04E-05 3.4610.03E-05 1.07 Agreement (2) 3.8610.06E-05 1.12 Agreement (0) 3.8210.06E-05 1.10 Agreement (H) 3.7110.07E-05 1.07 Agreement 13sXe (1) 7.7110.13E-06 7.5710.09E-06 1.02 Agreement (2) 8.2710.12E-06 1.09 Agreement (0) 7.9710.17E-06 1.05 Agreement (H) 8.2710.18E-06 1.09 Agreement 5. Waste Liquid Tank "B" (1 Liter Liquid Marinelli Beaker)

(Sampled 14:05 CST, October 28, 1986)

Wat-3 Wat-3 Results NRC Results Wat-3/NRC Comparison Nuclide De (uCi/ml) (uCi/ml) Ratio Decision s8Co (1) 5.7110.74E-07 6.16 0.41E-07 0.93 Agreement (2) 5.8610.70E-07 0.95 Agreement (0) 5.9810.45E-07 0.97 Agreement (H) 6.2810.43E-07 1.02 Agreement

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(1) 7.3910.21E-06 7.5110.11E;06-- '0.98- Agreement

.(2)- -7.2610.18E-06 -

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(0) 7.5610.13E;06L 1.01 Agreement ~

.(H). 6.5010.11E-06 ,. M[/ s ' 0.87- ' Agreement *

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issI (1) 1.7810.14E-06= 2.1310 07E-06 0.44 Agreement (2)- 1.8710.12E-06, 7' -

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(0): 1.9510.08E-06  ! ) 0.92 Agreement ,

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(H) 1.7710.07E-06 0.83 Agreement

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137Cs- '(1) 3.1810.'81E-07 2.3610.33E-07 1.35 Agreement (2) 2.4710.68E-07 o 1.05 Agreement L

(0) 3.2010:43E-07 -t A 1.36 Agreement '

(H). 2.4710.422-07 1.05 Agreement' ,

a ReactorCoolantSystemGas(30ccssbulb)!

/a' / l 3 (Sampled 09:25 CST, October 28, 1936)

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Wat-3- Wat'-3 Rest $ ts NRCRdults Wat-3/NRC' Comparison'I-Nuclide De (uci/cc) f' (uch cc) Ratio' Decision r- . ,.

m ss Kr (1) 4.9410.02E-02 4'.8910.02E-02

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.(2) 4.9010.03E-02 1.00 Agreemeht

.(0) 4.7410.04E-021 >; ,

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, 0.97 Agreement (H) 4.9310.05E-02 I' e

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87Kr (1) 5.3610.05E-02 4.6210.05E-02 1.16 Agrehment'

'(2)' 5.2610.06E-02 / 1.14 Ageeement (0) 5.1810.14E-02 i 1.12 ;Agreeminti (H) 5.6610.15E-02 ,

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1.23 . Agreement 88Kr (1) 9.8510.06E-02[ 9.51*0.05E92 f 1.04' - Agreement.-

-(2) 9.3010.06E-02;

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,s ./ 0.98 Agreement (0)- 9. 2710.12E-02' "/ 0.97 Agreement (H) 9.9510.13E-Q2 .

1.05 Agreee #

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183"Xe (1) 1.1610.08E-02 1.1510.04E-02 1.01 Agreement 3 (2) 1.0610.07E-02 0.92 Agreement (0) 1.3510.11E-02 1.17 Agreement (H) 1.3410.14E-02 1.16 pgreement ,

183Xe (1) 3.8310.01E-01 3.5410.01E-01 1.08 ' Agreement (2) 3.6310.01E-01 1.02 Agreement (0) 3.6410.01E-01 1.03 Agree:nent (H) 3.8210.01E-01 1.08 Agreement issXe (1) 1.4710.01E-01 1.4210.01E-01 1.04 Agreement (2) 1.4810.01E-01 1.04 Agreement

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(0) 1.4210.01E-01 1.00 Agreement (H) 1.5010.01E-01 1.06 Agreement 7. Reactor Coolant System Degassed Liquid (20 ml Scintillation Vial)

(Sampled 09:04 CST, October 28, 1986)

Wat-3 Wat-3 Results NRC Results Wat-3/NRC Comparison Nuclide De (uci/ml) (uci/ml) Ratio Decision 24Na -(1) 9.4010.13E-03 9.2010.10E-03 1.02 Agreement (2) 8.4910.10E-03 0.92 Agreement ssCo (1) 2.1310.10E-03 2.8510.09E-03 0.75 Agreement (2) 8.2610.45E-04 0.30 Disagreement asRb (1) 1.8710.46E-01 1.9210.01E-01 0.97 Agreement (2) 1.6610.03E-01 0.86 Agreement 181I (1) 1.1410.01E-02 1.2610.01E-02 0.90 Agreement (2) 1.1610.01E-02 0.92 Agreement 1321 (1) 3.9510.03E-02 4.2010.02E-02 0.94 Agreement (2) 3.7210.02E-02 0.89 Agreement 1881 (1) 4.1610.02E-02 4.5510.01E-02 0.91 Agreement (2) 3.9910.01E-02 0.88 Agreement 184I (1) 7.5710.11E-02 8.2310.05E-02 0.92 Agreement (2) 7.2210.04E-02 0.88 Agreement 185I (1) 5.7310.07E-02 6.0310.05E-02 0.95 Agreement (2) 5.4810.05E-02 0.91 Agreement 134Cs (1) 1.9810.09E-03 1.9710.09E-03 1.00 Agreement (2) 2.0110.09E-03 1.02 Agreement 137Cs (1) 3.7210.10E-03 .9810.10E-03 0.93 Agreement (2) 3. 2810. 07F-M 0.82 Agreement 138Cs (1) 1.1110.03L-01 L.0910.01E-01 1.01 Agreement (2) 1.0410.01E-01 0.95 Agreement 13988 (1) 2.4610.54E-03 2.6210.29E-03 0.94 Agreement (2) 2.1210.47E-03 0.81 Agreement 187W (1) 4.8110.31E-03 5.1110.29E-03 0.94 Agreement (2) 5.1310.33E-03 1.00 Agreement

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. Reactor Coolant System Tritium Sample (Sampled 09:25 CST, October 28, 1986)

Wat-3 Result, NRC Result Wat-3/NRC Comparison Nuclid (uCi/ml) -(uCi/ml) Ratio Decision _

8H 1.12E-02 1.26E-02 0.89 Agreement

' RESL Liquid Sample (Standardized 12:00 MST, January 11,1986)

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Wat-3 Results NRC Results 1/ Wat-3/NRC Comparison Nuclide (uCi/ml) (uCi/ml) Ratio Decision 3H 7.3E-05 1.0110.02E-04 0.72 Disagreement 89Sr ,3.910.1E-05 1.2710.04E-04 3 0.31 Disagreemeht 90Sr 1.010.1E-05 1.2010.05E-05 0.83 Agreement'

55Fe 8.310.3E-05 7.4810.15E-05 1.11 Agreement 137Cs 1.64E-05 1.6210.05E-05 1.01 Agreement 60Co 1.44E-05 1.4410.03E-05 1.00 Agreement 54Mn ~1.12E-05 1.0010.02E-05 1.12 Agreement

'1/ 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 s

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