IR 05000416/1987004: Difference between revisions

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{{Adams
{{Adams
| number = ML20205N145
| number = ML20238E101
| issue date = 03/18/1987
| issue date = 09/04/1987
| title = Insp Rept 50-416/87-04 on 870223-0312.No Violations Noted. Major Areas Inspected:Liquid & Gaseous Effluent Releases & Process Sys & Radiochemistry Qa,Including Results of Split Samples Analyzed by Licensee & Region II Mobile Lab
| title = Forwards Confirmatory Measurement Results for Spiked Liquid Samples Sent to Util on 870511 for Selected Radiochemical Analyses,Supplementing Insp Rept 50-416/87-04.Comparative Results in Agreement.Acceptance Criteria Encl
| author name = Harris J, Kahle J
| author name = Collins D
| author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
| author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
| addressee name =  
| addressee name = Kingsley O
| addressee affiliation =  
| addressee affiliation = SYSTEM ENERGY RESOURCES, INC.
| docket = 05000416
| docket = 05000416
| license number =  
| license number =  
| contact person =  
| contact person =  
| document report number = 50-416-87-04, 50-416-87-4, NUDOCS 8704020603
| document report number = NUDOCS 8709140139
| package number = ML20205N132
| document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE
| document type = INSPECTION REPORT, NRC-GENERATED, INSPECTION REPORT, UTILITY, TEXT-INSPECTION & AUDIT & I&E CIRCULARS
| page count = 4
| page count = 10
}}
}}


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   'TP O 41937 l
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l System Energy Resources, In !
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ATTN: Mr. O. D. Kingsley, J I Vice President, Nuclear Operations l P. O. Box 23054 Jackson, MS 39205 l       j Gentlemen:
, A [fr  UNITED STATES
SUBJECT: CONFIRMATORY MEASUREMENT RESULTS, SUPPLEMENT TO INSPECTION l       l REPORT NOS. 50-416/87-04 As part of the NRC Confirmatory Measurements Program, spiked liquid samples were sent on May 11, 1987, to your Grand Gulf- facility for selected radiochemical analyse We are in ' receipt of your analytical results transmitted to us by your letter dated July 13, 1987, and subsequent to verification of your values as per our conversation by telephone on September 2,1987, the following comparison of your results to the known values '
. NUCLEAR REGULATORY COMMISSION
are presented in Enclosure 1 for your information. The acceptance criteria for the comparisons are listed in Enclosure _
[   REGION ll
In our review of these data all comparative results were in agreement. These data should be reviewed in greater detail by cognizant staff members for any significant trends in the data among successive years in which samples have been analyzed by your facilit These results and any results from previous years pertaining to these analyses will be discussed at future NRC inspection
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$ j  101 MARIETTA STREET, * t  ATLANTA, GEORGI A 30323
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Mg 2 3 MB7 Report No.: 50-416/87-04 l Licensee: System Energy Resources, In Jackson, MS 39205 Docket No.: 50-416  License No.: NPF-29-Facility Name: Grand Gulf Nuclear Station    l Inspection Conducted:.. ebruary 23-March 12,1987 3// f/87
    ~
Inspector: '
dL- Icl,[i    l J. D. Hafr    (Date Signed) l Accompanying'Perso 1: R. R. M'arston G. L. Froemsdorf Approved by:  M](c b  3//J/g7 J.B.- hle, Section Chief  (Date Signed)
l  Divis n of Radiation Safety and Safeguards
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SUMMARY
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, Scope: This routine, unannounced inspection involved onsite and in-office  l l inspection in the areas of liquid and gaseous effluent releases and process  !
systems, and radiochemistry quality control, including the results of split samples analyzed by the licensee and NRC Region II Mobile Laboratory,
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Results: No violations or deviations were identified.


Sincerely, OPWNAL SIGNED BY DOUGLAS M. COUINS l    Douglas M. Collins, Chief Emergency Preparedness and
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l Radiological Protection Branch l    Division of Radiation Safety and Safeguards Enclosures: Confirmatory Measurement Comparisons Criteria for Comparing Analytical Measurements cc w/encls: (See page 2)
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8709140139 B70904 gDR ADOCK05%{6 I I IroG
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System Energy Resources, In cc w/encls:
T. H. Cloninger, Vice President, Nuclear Engineering and Support J. E. Cross, EdNS Site Director C. R. Hutchinson, GGNS General Manager J. G. Cesare, Director, Nuclear Licensing and Safety R. T. Lally, Manager of Quality Assurance Middle South Services, In R. B. McGehee, Esquire Wise, Carter, Child, Steen and Caraway N. S. Reynolds, Esquire Bishop, Libernan, Cook, Purcell
& Reynolds R. W. Jackson, Project Engineer bec w/encls:
NRC Resident Inspector L. Kintner, NRR Document Control Desk State of Mississippi l
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8704020603 870323 6 PDR ADOCK 0500
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RMarston 9/ ?./87 Kahle afi0'M ahce 9/cy'/87 9/ /87


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REPORT DETAILS Persons Contacted Licensee Employees
8S
  *J. D. Bailey, Compliance Coordinator
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*S. M. Feith, Director, Quality Assurance
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* E. Edge, Programs Manager, Quality Assurance
*J. L. Robertson, Superintendent, Plant Licensing
*R. F. Rogers, III, Project Manager, Unit 1
*R. D. Mooman, Technical Assistant to the Manager, Plant Maintenance
*A. McCurdy, Manager Operations
* C. Eiff, Principal Quality Engineer, Nuclear Plant Engineering
*J. M. Lassetter, Count Room Specialist, Chemistry
*T. L. Williamson, Chemistry Supervisor
*G. O. Smith, Plant Chemist
*F. W. Rosser, Radiation Control Supervisor  j
*R. Hutchinson, General Manager
*R. S. Lewis, Nuclear Plant Engineering
*G. W. Vining, PM&C
*A. J. Malone, IST Coordinator    i B. Lee, Supervisor, Quality Assurance Audits J. Holmes, PASS Specialist J. B. Edwards, Engineer, Maintenance J. V. Parrish, Chemistry / Radiation Control Superintendent  !
C. Elisaesser, Technical Assistant, Operations  '
R. Sorrels, Engineer, Technical Support Other Organizations J. R. Hunt, Vice President, Nuclear Containment Systems NRC Resident Inspector R. C. Butcher    l
* Attended exit interview Exit Interview The inspection scope and findings were summarized on February 27, 1987, ,
with those persons indicated in Paragraph 1 above. Discussions were also held by telephone on March 12, 1987, concerning tritium analysis and Post-Accident Samplin Licensee management representatives acknowledged the inspectors' comments and expressed no dissenting opinion The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspector during this inspectio .  .
 
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3. Licensee Action on Previous Enforcement Matters This subject was not addressed in the inspectio . Audits (80721,84723,84724,84725)
Technical Specification 6.5.2.8 defines the requirements for the audits that are to be performed under the cognizance of the Safety Review Committee. The inspector reviewed the most recent audits of; Offsite Dose Calculation Manual, Chlorine Detection System (Control Room Ventilation),
Chemical Control Program, Qualification and Training of Chemistry Personnel, Process Control Program, Radiological Environmental Monitoring Program, and Implementation of Regulatory Guide 4.15. " Quality Assurance for Radiological Monitoring Programs (Normal Operations) - Effluent Streams and the Environment."
 
The audits addressed the overall program content in addition to technical
,
specification conten The audits appeared very thorough and deeply probing. Most of the findings were resolved during the audit period. In discussions with cognizant licensee personnel, the inspector concluded that there was a high level of management commitment to fully address all finding No violations or deviations were identifie . RadioactiveLiquidWaste(84723)
Technical Specification 3/4.11.1 establishes upper limits for concentrations of radioactive materials in liquid effluent The inspector reviewed selected release records from November 1986 to February 198 All releases reviewed were within technical specification limit The licensee has had good operational performance from the liquid radwaste system since the last inspection in this area (50-416/86-09).
 
No violations or deviations were identifie . Radioactive Gaseous Waste and Gaseous Effluent Treatment Systems (84724)
Technical Specification 3/4.11.2 establishes upper limits for concentrations of radioactive material in gaseous effluent The inspector selectively reviewed release records for the Radwaste
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Building, Turbine Building and Fuel Handling Area Ventilation Systems from
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October 1986 to February 1987. All releases reviewed were within regulatory limit Technical Specifications 4.6.6.3 and 4.7.2 give surveillance requirements for the Standby Gas Treatment System and the Control Room Emergency Filtration System, respectivel _ _ ____ __ _ _ - _ . _ . _-  - _ _ - . ..- - . --      . . - - .- - -    - . _ - - . - - -
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The inspector selectively reviewed Operations and Maintenance records for December 1986 ~ to February 1987. During discussions of the Surveillance -
:  Program, the inspector noted that it is conservatively implemented, with l  most surveillance scheduled well within regulatory requirement j
{  The inspector selectively observed inspections and in-place leakage tests          .
 
of HEPA filters and charcoal adsorbers associated with the Standby Gas          ;
;  Treatment System,- the Control Room Emergency Ventilation Systems,
:  Containment Building Purge System, and the Containment Bu1_lding
;  Recirculation System performed by the licensee and contractor personne .
 
Activities observed were evaluated against the criteria of ANSI 510-1975, i  " Testing of Nuclear Air-cleaning Systems," and Regulatory Guide 1.52-1978,          -
i  " Design, Testing, and Maintenance Criteria for Post-Accident Engineered
:  Safety-Feature Atmosphere Cleanup System Air Filtration and Adsorption Units of . Light-Water-Cooled Nuclear Power Plant The licensee demonstrated Technical Specification compliance and good utilization of
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contracts. During the . review of filter systems, the inspector noted i  several differential pressure and flow indicators that at times were.


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offscale. The inspector discussed this finding with licensee personne ]   Cognizant licensee personnel acknowledged the . inspectors comments and
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  ,  stated that a design change request had been made for the differential
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:  pressure indicators and agreed to evaluate _ the flow indicator by l  initiating a material nonconformance report. Other instances of offscale l  instrumentation had been brought to the attention of the licensee by the          l j  resident inspector.
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j   No violations or deviations were identified.
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L j Radioactive Effluent Monitoring Instrumentation (92717, 84723, 84724)
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]   Technical Specification 3/4.3.7.1 establishes the minimum operability and          i j  surveillance for radioactive liquid and gaseous process and effluent
ENCLOSURE 2 Criteria for Comparing. Analytical Measurements This enclosure provides' criteria for comparing-results of capability tests and verification measurements. The criteria are based on an empirical relationship which combines prior experience and the accuracy needs of this progra In this criteria, the judgement limits denoting agreement or disagreement ~
;   stream monitoring instrumentation.
l    between licensee and NRC results are variable. This variability is a function
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of the NRC's value relative to its associated uncertainty. As the ratio of(the NRC value to its associated uncertainty referred to in this program as
    " Resolution"2 increases, the . range of acceptable differences between ' the:.NRC-and licensee values should be more restrictiv Conversely, poorer agree' ment between NRC and licensee values must be considered acceptable as the r.esolution decrease [i For comparison purposes, a ratio 2 of the licensee value to the NRC value is computed. This ratio is then evaluated for agreement based on the calculated resolution. The corresponding resolution and calculated ratios which denote agreement are listed in Table 1 below. Values outside of the agreement -ratios are considered in disagreemen Resolution = NRC Reference Value-Associated Uncertainty for the Value
    '8 Comparison Ratio = Licensee Value NRC Reference Value TABLE 1 Confirmatory Measurements Acceptance Criteria Resolutions vs. Comparison Ratio Comparison Ratio for Resolution  Agreement l
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    < 4   .4 - .5 - .6 - 1,66 16 - 50  .75 - 1.33 51 - 200  .80 - 1.25
    >200   .85 -.1.18
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j  The inspector selectively reviewed surveillance records for channel
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functional tests and channel calibrations including associated I
isolation / actuation signal circuit During the inspection, the i  licensee's liquid effluent monitor was out of service in order to modify l  its flush water line in an attempt to reduce the background radiation for          <~
!  that monitor. The inspector discussed the problem with cognizant licensee i  personnel in regard to similar problems at other licensed facilities.


,  The inspector discussed IE Infonnation Notice 86-42, " Improper Maintenance
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  !  of Radiation Monitoring Systems," with cognizant licensee personnel. The licensee has an independent verification program that addresses the types
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L  of occurrences as described in the. information notice. The inspector          -
!  reviewed Procedure 01-S-06-29. " Independent Verification Program," Rev.1,
:  September-25,-1986. Procedural implementation should prevent similar j  occurrence i
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No violations or deviations were identifie . Post-AccidentSamplingSystem(PASS)(92701,84723,84724,84725)
The inspector observed portions of a PASS Training Module being conducted
; during the inspectio Hands-on activities observed included Hot Lab Set-up, grab sampling, and sample analysis. Training activities were evaluated against established procedures, analytical techniques, and general good practice The training appeared to be effectively implemented. The inspector noted that the Plant Chemist and an auditor from Quality Assurance was in attendanc The inspector reviewed modifications made on the PASS during the recent refueling outage. The licensee installed flow instrumentation for air sampling streams and upgraded heat tracing near the sampling statio Currently the licensee PASS capability is dependent on grab sampling. The licensee plans to upgrade and reinstate online monitoring for chemistry parameters when the required design / modifications can be mad Future i
modifications are also planned for obtaining grab samples for isotopic
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analysis. After reviewing the licensee capabilities to obtain samples under accident conditions in regard to General Electric's technical evaluations and the licensee procedures for core damage estimates, tie e inspector concluded that the licensee is fully capable of implementing the requirements of NUREG-073 Any modifications to the PASS will be reviewed during routine inspection (Closed)InspectorFollowupItem 50-416/86-09-01: Review and verification testing of PASS engineering design changes.
; No violations or deviations were identifie . Radiochemical Quality Assurance Program (84725)
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The inspector reviewed the licensee's radiochemical quality assurance Guide 4.15, " Quality
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Assurance for Radiological Monitoring Programsprogram against the criteria giv l
Effluent Streams and the Environment."  i The inspector reviewed daily logs and calibration records for the ,
proportional counter, liquid scintillation system and gamma spectroscopy I system The inspector also reviewed the results of laboratory l intercomparisons of radioactive material measurements made between the licensee and a reputable vendor laboratory. A high level of agreement between the labs were note l i No violations or deviations were identified, j
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10. Confirmatory Measurements (84725)
Selected liquid and gaseous process streams were sampled with the resultant samples analyzed by both the licensee's and NRC's RII Mobile Laboratory gamma spectroscopy systems. The inspector provided a spiked charcoal cartridge and a spiked particulate filter to the licensee to ensure sufficient activity for valid comparisons for these geometrie Other licensee geometries utilized in the comparison included a 4,300 milliliter gas marinelli, a one-liter liquid marinelli, and 14 milliliter gas vial. Comparisons of licensee and NRC results are given in Table 1. The acceptance criteria is given in Attachment 1. All measurements were in agreement. The inspector noted the relatively low activity in plant systems reduced the overall number of comparisons. The inspector also split a water sample spiked with' tritium with the licensee to validate their ability to measure. The results are also given in Table 1 and show agreemen No violations or deviations were identifie l l
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ATTACHMENT 1 CRITERIA FOR COMPARING ANALYTICAL MEASUREMENTS This attachment provides criteria for comparing results of capability tests and verification measurements. The criteria are based on an empirical relationship which combines prior experience and the accuracy needs of this progra In these criteria, the judgement limits are variable in relation to the comparison of the NRC's value to its associated uncertainty. As that ratio, referred to in this program as " Resolution," increases, the acceptability of a licensee's measurements should be more selective. Conversely, poorer agreement-must be considered acceptable as the resolution decrease )
RATIO = LICENSEE VALUE NRC REFERENCE VALUE lj Resolution  Agreement
  >4  0.4 - .5 - .6 - 1.66  ,
16 - 50  0.75 1.33  l 51 - 200  0.80 - 1.25 ( 200   0.85 - 1.18
 
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TABLE 1 RESULTS OF CONFERMATORY MEASUREMENTS CONDUCTED AT CRAND GULF NUCLEAR STATION CONCENTRATION    RATIO SAMPLE  ISOTOPE  LICENSEE  NAC  RESOLUTION LICENSEE /NRC COMPARISON Cha rcoa l Ca rt ridge cd-109  1.60 E-0 1.83 i .01 E-0 183  .87 Ag reemen t (spiked)  Co-57  3.53 E-2 3.89 i .04 E-2 97  .91 Ag reement Detsctor 1  Ce-139  3.47 E-2 3.84 i .07 E-2 55  .90 Ag reemen t Hg-203  8.27 E-2 7.93 i .57 E-2 14  1.04 Ag reement Sn-113  7.15 E-2 7.80 i .57 E-2 49  .92 Ag reemen t Cs-137  5.70 E-2 5.79 i .07 E-2 83  .98 Ag reement Y-88  9.54 E-2 1.03 i .02 E-1 52  .93 Ag reement Co-60  4.65 E-2 5.04 i .08 E-2 63  .92 Ag reement Cha rcoa l Ca rt r i dge cd-109  1.72 E-0 1.832 1 .01 E-0 183  .94 Ag reement (spiked)  Co-57  3.81 E-2 3.89 i .04 E-2 97  .97 Ag reemen t Detsctor 2  Ce-139  3.70 E-2 3.84 i .07 E-2 55  .96 Ag reement ;
            .97 Ag reemen t
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Hg-203  7.73 E-2 7.93 i .57 E-2 14 Sn-113  7.45 E-2 7.80 i .16 E-2 49  .96 Ag reement Cs-137  5.58 E-2 5.79 i .07 E-2 83  .96 Ag reement Y-88  9.30 E-2 1.03 i .02 E-1 52  .90 Agreement Co-60  4.88 E-2 5.04 i .08 E-2 63  .97 Agreement Charcoal Ca rtridge  Cd-109  1.52 E-0 1.83 i .01 E-0 183  .83 Agreement (spiked)  Co-57  3.51 E-2 3.89 i .04 E-2 97  .90 Ag reement -
Detsctor 3  Ce-139  3.51 E-2 3.84 i .07 E-2 55  .91 Ag reement Hg-203  8.11 E-2 7.93 i .57 E-2 14  1.02 Ag reemen t Sn-113  7.23 E-2 7.80 i .16 E-2 49  .93 Ag reement Cs-137  5.45 E-2 5.79 i .07 E-2 83  .94 Ag reement Y-88  8.62 E-2 1.03 i .02 E-1 52  .84 Ag reemen t Co-60  4.68 E-2 5.04 i .08 E-2 63  .93 Agreement Charcoal Cartridge  Cd-109  1.76 E-0 1.83 i .01.E-0 183  .96 Ag reement (spiked)  Co-57  3.72 E-2 3.89 i .04 E-2 97  .96 Ag reemen t Detsctor 4  Ce-139  3.66 E-2 3.84 i .07 E-2 55  .95 Ag reemen t Hg-203  6.47 E-2 7.93 i .57 E-2 14  .81 Ag reement Sn-113  7.16 E-2 7.80 i .16 E-2 49  .92 Agreement Cs-137  5.81 E-2 5.79 i .07 E-2 83  1.00 Agreement Y-88  8.98 E-2 1.03 i .02 E-1 52  .87 Ag reement Co-60  4.95 E-2 5.04 i .08 E-2 63  .98 Agreement Particulate Filter  Am-241  4.47 E-3 4.83 i .18 E-3  27  .93 Ag reement (spiked)  Cs-137  1.24 E-2 1.24 i .02 E-2  62  1.00 Ag reement Detector 1  Co-60  8.74 E-3 8.07 i .24 E-3  34  1.08 Ag reement Particulate Filter  Am-241  5.94 E-3 4.83 i .18 E-3  27  1.22 Ag reement (spiked)  Cs-137  1.30 E-2 1.24 i .02 E-2  62  1.04 Ag reement i Co-60  8.91 E-3 8.07 i .24 E-3  34  1.10 Ag reement Detsctor 2 Particulate Filter  Am-241  6.02 E-3 4.83 i .18 E-3  27  1.24 Ag reement (spiked)  Cs-137  1.28 E-2 1.24 i .02 E-2  62  1.03 Ag reement Co-60  8.89 E-3 8.07 i .24 E-3  34  1.10 Ag reement Detector 3
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TABLE 1 (cont'd)
RESULTS OF CONFlRMATORY MEASUREMENTS CONDUCTED AT CRANC GULF NUCLEAR STATION CONCENTRATION  RATIO SAMPLE    LICENSEE LEC RESOLUTION LICENSEE /NRC COMPARISON
_lSOTOPE Particulate Filter  Am-241  4.07 E-3 4.83 i .18 E-3 27 .84 Ag reement (spiked)  Cs-137  1.30 E-2 1.24 i .02 E-2 62 1.05 Ag reement Detector 4  Co-60  9.17 E-3 8.07 .24 E-3 34 1.13 Ag reemen t One Li te r Ma ri ne l l i  C r-51  2.88 E-2 2.74 i .05 E-2 55 1.05 Agreement ( resctor coolant)  As-76  9.29 E-4 7.18 i .75 E-4 10 1.29 Ag reemen t Detector 1 One Liter Marinelli  C r-51  2.87 E-2 2.74 .05 E-2 55 1.05 Agreement ( retctor coolant)  As-76  9.72 E-4 7.18 i .75 E-4 10 1.35 Ag reement Dettctor 2 One Liter Marinelli  C r-51  2.82 E-2 2.74 i .05 E-2 55 1.03 Agreement ( reretor coolant)  As-76  9.26 E-4 7.18 i .75 E-4 10 1.29 Ag reement Detector 3 One Liter Marinelli  C r-51  2.89 E-2 2.74 i .05 E-2 55 1.05 Ag reement 10 1.37 Ag reement ( resctor coolant)  As-76  9.85 E-4 7.18 i .75 E-4 Dettctor 4 G1s Vial (ortgas)  Kr-85m  4.05 E-3 4.42 i .30 E-3 15 .92 Ag reemen t Det:ctor i  Kr-88  1.30 E-2 1.39 i .13 E-2 11 .94 Ag reemen t Xe-135  1.22 E-2 1.38 i .05 E-2 28 .88 Ag reemen t Xe-138  3.18 E-1 3.10 i .09 E-1 34 1.03 Agreement Kr-87  2.60 E-2 2.60 t .12 E-2 22 1.00 Ag reemen t Xe-135m  7.46 E-2 7.20 i .23 E-2 31 1.04 Agreement Css Vial (offgas)  K r-85m  4.00 E-3 4.42 i .30 E-3 15 .90 Ag reemen t Detector 2  Kr-88  1.22 E-2 1.39 i .13 E-2 11 .88 Agreement Xe-135  1.24 E-2 1.38 i .05 E-2 28 .90 Agreement Xe-138  2.80 E-1 3.10 i .09 E-1 34 .90 Ag reement K r-87  2.12 E-2 2.60 .12 E-2 22 .82 Ag reemen t .
Xe-135m  6.45 E-2 7.20 i .23 E-2 31 .90 Ag reement C2s Vial (offgas)  K r-85m  3.69 E-3 4.42 i .30 E-3 15 .83 Agreement Dettctor 4  K r-88  1.23 E-2 1.39 i .13 E-2 11 .88 Ag reemen t Xe-135  1.22 E-2 1.38 i .05 E-2 28 .88 Ag reement Xc-138  2.82 E-1 3.10 i .09 E-1 34 .91 Ag reement K r-87  2.19 E-2 2.60 i .12 E-2 22 .84 Ag reement Xe-135m  8.25 E-2 7.20 i .23 E-2 31 1.15 Ag reement
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TABLE A 1 (cont'd)
RESULTS of CONflRMATORY MEASUREMENTS CONDUCTED AT CRAND GULF NUCLEAR STATION CONCENTRATION    RATIO'-    -
SAMF?J  J SOTO PE LICENSEE  NRC  de 30Lt3110N LICENSEff_NHg  C0bpQJiGP(
 
4300 ml Ma r s ne l l i Vr-85m  2.92 r.-4 3.09 i .',2 E-4  10  .95  Ag reemen t --
Offgas Detector 4  Xo-1 M  8.60 E-4 9.04 i .50 r-h  18  .95  Ag ree ment y  Xe-136  2.04 E-2 2.0? i . 08 t,- 2 2'2-  1.01  Agreement Ag reemen t K r-87  1.63 F-3 1.82 1 .12 E-3  15 '  .90 Xe-135m  5.99 T-3 4.81 i .26 E-3  19  .1.25  Ag reemen t
            '
4300 ml Ma ri ew i l l K r- 85 .86 E-b 3.09 i .32 E-4  10  .93  Agreement Of fes . Le6ector 2 Xe-135- 8.36 E-4 7,04 i .50 E-4  18  .92  Ag reement (spikod)  Xe-138  2.04 E-2 # 02 i .08 E-2  25  1.01  Ag reemen t  ,
K r-8 7  1.73 E-3 1.52 i .12 E-?  15  .95  Ag reemant Xe-115*. 5.00 E-3 4.81 i .26 E ,  19  1.04  Ag reemen t 4300 mi % rinelli  e:r-05m 2.93 E-4 3.09 i .37 -4  10  .95  Ag reec.en t
:
Offgas Detector 3  X t,'- 13 5 9.05 E.'t 9.04 i .' E-4  18  1.00  ' Alj reemen t 25  .73
              -
(spiked)  Xe-138  1.48 E-2 E..'t 38 E-2  *  D i sac reement kr-87  1.55 F-3 <''* 12 E-3  15  .85  Ag reemen t s  Xe-135m 5.46 E-3 ..d* .26 E-3  19  1.1 t; s Ag reement
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T ri t e 99 Sp i f,e .
H-3  1.90 E-2 2.1 i i .01 E-2  213  . 89 '  r.greement  ,
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Forwards Confirmatory Measurement Results for Spiked Liquid Samples Sent to Util on 870511 for Selected Radiochemical Analyses,Supplementing Insp Rept 50-416/87-04.Comparative Results in Agreement.Acceptance Criteria Encl
ML20238E101
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 09/04/1987
From: Dan Collins
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To: Kingsley O
SYSTEM ENERGY RESOURCES, INC.
References
NUDOCS 8709140139
Download: ML20238E101 (4)
v • d • e


Text

'

6 D ALO o

'TP O 41937 l

l System Energy Resources, In !

ATTN: Mr. O. D. Kingsley, J I Vice President, Nuclear Operations l P. O. Box 23054 Jackson, MS 39205 l j Gentlemen:

SUBJECT: CONFIRMATORY MEASUREMENT RESULTS, SUPPLEMENT TO INSPECTION l l REPORT NOS. 50-416/87-04 As part of the NRC Confirmatory Measurements Program, spiked liquid samples were sent on May 11, 1987, to your Grand Gulf- facility for selected radiochemical analyse We are in ' receipt of your analytical results transmitted to us by your letter dated July 13, 1987, and subsequent to verification of your values as per our conversation by telephone on September 2,1987, the following comparison of your results to the known values '

are presented in Enclosure 1 for your information. The acceptance criteria for the comparisons are listed in Enclosure _

In our review of these data all comparative results were in agreement. These data should be reviewed in greater detail by cognizant staff members for any significant trends in the data among successive years in which samples have been analyzed by your facilit These results and any results from previous years pertaining to these analyses will be discussed at future NRC inspection

Sincerely, OPWNAL SIGNED BY DOUGLAS M. COUINS l Douglas M. Collins, Chief Emergency Preparedness and

,

l Radiological Protection Branch l Division of Radiation Safety and Safeguards Enclosures: Confirmatory Measurement Comparisons Criteria for Comparing Analytical Measurements cc w/encls: (See page 2)

,

8709140139 B70904 gDR ADOCK05%{6 I I IroG

.

.

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System Energy Resources, In cc w/encls:

T. H. Cloninger, Vice President, Nuclear Engineering and Support J. E. Cross, EdNS Site Director C. R. Hutchinson, GGNS General Manager J. G. Cesare, Director, Nuclear Licensing and Safety R. T. Lally, Manager of Quality Assurance Middle South Services, In R. B. McGehee, Esquire Wise, Carter, Child, Steen and Caraway N. S. Reynolds, Esquire Bishop, Libernan, Cook, Purcell

& Reynolds R. W. Jackson, Project Engineer bec w/encls:

NRC Resident Inspector L. Kintner, NRR Document Control Desk State of Mississippi l

l l

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ENCLOSURE 2 Criteria for Comparing. Analytical Measurements This enclosure provides' criteria for comparing-results of capability tests and verification measurements. The criteria are based on an empirical relationship which combines prior experience and the accuracy needs of this progra In this criteria, the judgement limits denoting agreement or disagreement ~

l between licensee and NRC results are variable. This variability is a function

~

of the NRC's value relative to its associated uncertainty. As the ratio of(the NRC value to its associated uncertainty referred to in this program as

" Resolution"2 increases, the . range of acceptable differences between ' the:.NRC-and licensee values should be more restrictiv Conversely, poorer agree' ment between NRC and licensee values must be considered acceptable as the r.esolution decrease [i For comparison purposes, a ratio 2 of the licensee value to the NRC value is computed. This ratio is then evaluated for agreement based on the calculated resolution. The corresponding resolution and calculated ratios which denote agreement are listed in Table 1 below. Values outside of the agreement -ratios are considered in disagreemen Resolution = NRC Reference Value-Associated Uncertainty for the Value

'8 Comparison Ratio = Licensee Value NRC Reference Value TABLE 1 Confirmatory Measurements Acceptance Criteria Resolutions vs. Comparison Ratio Comparison Ratio for Resolution Agreement l

'

< 4 .4 - .5 - .6 - 1,66 16 - 50 .75 - 1.33 51 - 200 .80 - 1.25

>200 .85 -.1.18

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