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{{Adams | |||
| number = ML20205N145 | |||
| issue date = 03/18/1987 | |||
| 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 | |||
| author name = Harris J, Kahle J | |||
| author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) | |||
| addressee name = | |||
| addressee affiliation = | |||
| docket = 05000416 | |||
| license number = | |||
| contact person = | |||
| document report number = 50-416-87-04, 50-416-87-4, NUDOCS 8704020603 | |||
| package number = ML20205N132 | |||
| document type = INSPECTION REPORT, NRC-GENERATED, INSPECTION REPORT, UTILITY, TEXT-INSPECTION & AUDIT & I&E CIRCULARS | |||
| page count = 10 | |||
}} | |||
See also: [[see also::IR 05000416/1987004]] | |||
=Text= | |||
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, A [fr UNITED STATES | |||
. NUCLEAR REGULATORY COMMISSION | |||
[ REGION ll | |||
' | |||
$ j 101 MARIETTA STREET, N.W. | |||
* t ATLANTA, GEORGI A 30323 | |||
%,..../ - | |||
Mg 2 3 MB7 | |||
Report No.: 50-416/87-04 | |||
l Licensee: System Energy Resources, Inc. | |||
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 | |||
! | |||
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, | |||
' | |||
Results: No violations or deviations were identified. | |||
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8704020603 870323 6 | |||
PDR ADOCK 0500 | |||
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REPORT DETAILS | |||
1. Persons Contacted | |||
Licensee Employees | |||
*J. D. Bailey, Compliance Coordinator | |||
*S. M. Feith, Director, Quality Assurance | |||
*W. 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 | |||
*W. 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 | |||
2. 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 Sampling. Licensee management representatives acknowledged | |||
the inspectors' comments and expressed no dissenting opinions. The | |||
licensee did not identify as proprietary any of the materials provided to | |||
or reviewed by the inspector during this inspection. | |||
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2 | |||
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3. Licensee Action on Previous Enforcement Matters | |||
This subject was not addressed in the inspection. | |||
4. 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 content. 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 | |||
findings. | |||
No violations or deviations were identified. | |||
5. RadioactiveLiquidWaste(84723) | |||
Technical Specification 3/4.11.1 establishes upper limits for | |||
concentrations of radioactive materials in liquid effluents. | |||
The inspector reviewed selected release records from November 1986 to | |||
February 1987. All releases reviewed were within technical specification | |||
limits. 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 identified. | |||
6. 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 effluents. | |||
The inspector selectively reviewed release records for the Radwaste | |||
, | |||
Building, Turbine Building and Fuel Handling Area Ventilation Systems from | |||
! | |||
October 1986 to February 1987. All releases reviewed were within | |||
regulatory limits. | |||
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, respectively. | |||
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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 requirements. j | |||
{ The inspector selectively observed inspections and in-place leakage tests . | |||
4 | |||
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 personnel. | |||
. | |||
1 | |||
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 Plants. The licensee | |||
demonstrated Technical Specification compliance and good utilization of | |||
, | |||
contracts. During the . review of filter systems, the inspector noted | |||
i several differential pressure and flow indicators that at times were. | |||
- | |||
offscale. The inspector discussed this finding with licensee personnel. | |||
] Cognizant licensee personnel acknowledged the . inspectors comments and | |||
, stated that a design change request had been made for the differential | |||
: 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. | |||
j No violations or deviations were identified. | |||
L | |||
j 7. Radioactive Effluent Monitoring Instrumentation (92717, 84723, 84724) | |||
: | |||
] Technical Specification 3/4.3.7.1 establishes the minimum operability and i | |||
j surveillance for radioactive liquid and gaseous process and effluent | |||
; stream monitoring instrumentation. | |||
; | |||
j The inspector selectively reviewed surveillance records for channel | |||
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functional tests and channel calibrations including associated | |||
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isolation / actuation signal circuits. 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 | |||
! of Radiation Monitoring Systems," with cognizant licensee personnel. The | |||
licensee has an independent verification program that addresses the types | |||
' | |||
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 occurrences. | |||
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No violations or deviations were identified. | |||
8. Post-AccidentSamplingSystem(PASS)(92701,84723,84724,84725) | |||
The inspector observed portions of a PASS Training Module being conducted | |||
; during the inspection. 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 practices. The training appeared to be effectively | |||
implemented. The inspector noted that the Plant Chemist and an auditor | |||
from Quality Assurance was in attendance. | |||
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 statior. | |||
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 made. Future | |||
i | |||
modifications are also planned for obtaining grab samples for isotopic | |||
' | |||
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-0737. | |||
Any modifications to the PASS will be reviewed during routine inspections. | |||
(Closed)InspectorFollowupItem 50-416/86-09-01: Review and verification | |||
testing of PASS engineering design changes. | |||
; No violations or deviations were identified. | |||
9. Radiochemical Quality Assurance Program (84725) | |||
, | |||
The inspector reviewed the licensee's radiochemical quality assurance | |||
Guide 4.15, " Quality | |||
, | |||
Assurance for Radiological Monitoring Programsprogram against the criteria giv | |||
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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 | |||
systems. 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 noted. | |||
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i No violations or deviations were identified, | |||
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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 geometries. | |||
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 agreement. | |||
No violations or deviations were identified. | |||
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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 program. | |||
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 decreases. ) | |||
RATIO = LICENSEE VALUE | |||
NRC REFERENCE VALUE | |||
lj | |||
Resolution Agreement | |||
>4 0.4 - 2.5 | |||
4-7 0.5 - 2.0 | |||
8 - 15 0.6 - 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 | |||
' | |||
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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4 | |||
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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( | |||
8 | |||
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- 85c. 2.86 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 | |||
. (' | |||
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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Latest revision as of 01:54, 20 December 2021
ML20205N145 | |
Person / Time | |
---|---|
Site: | Grand Gulf |
Issue date: | 03/18/1987 |
From: | Harris J, Kahle J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
To: | |
Shared Package | |
ML20205N132 | List: |
References | |
50-416-87-04, 50-416-87-4, NUDOCS 8704020603 | |
Download: ML20205N145 (10) | |
See also: IR 05000416/1987004
Text
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, A [fr UNITED STATES
. NUCLEAR REGULATORY COMMISSION
[ REGION ll
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$ j 101 MARIETTA STREET, N.W.
- t ATLANTA, GEORGI A 30323
%,..../ -
Mg 2 3 MB7
Report No.: 50-416/87-04
l Licensee: System Energy Resources, Inc.
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
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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
!
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,
'
Results: No violations or deviations were identified.
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8704020603 870323 6
PDR ADOCK 0500
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REPORT DETAILS
1. Persons Contacted
Licensee Employees
- J. D. Bailey, Compliance Coordinator
- S. M. Feith, Director, Quality Assurance
- W. 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
- W. 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
2. 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 Sampling. Licensee management representatives acknowledged
the inspectors' comments and expressed no dissenting opinions. The
licensee did not identify as proprietary any of the materials provided to
or reviewed by the inspector during this inspection.
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3. Licensee Action on Previous Enforcement Matters
This subject was not addressed in the inspection.
4. 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 content. 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
findings.
No violations or deviations were identified.
5. RadioactiveLiquidWaste(84723)
Technical Specification 3/4.11.1 establishes upper limits for
concentrations of radioactive materials in liquid effluents.
The inspector reviewed selected release records from November 1986 to
February 1987. All releases reviewed were within technical specification
limits. 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 identified.
6. 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 effluents.
The inspector selectively reviewed release records for the Radwaste
,
Building, Turbine Building and Fuel Handling Area Ventilation Systems from
!
October 1986 to February 1987. All releases reviewed were within
regulatory limits.
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, respectively.
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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 requirements. j
{ The inspector selectively observed inspections and in-place leakage tests .
4
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 personnel.
.
1
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 Plants. 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.
-
offscale. The inspector discussed this finding with licensee personnel.
] Cognizant licensee personnel acknowledged the . inspectors comments and
, stated that a design change request had been made for the differential
- 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.
j No violations or deviations were identified.
L
j 7. Radioactive Effluent Monitoring Instrumentation (92717, 84723, 84724)
] Technical Specification 3/4.3.7.1 establishes the minimum operability and i
j surveillance for radioactive liquid and gaseous process and effluent
- stream monitoring instrumentation.
j The inspector selectively reviewed surveillance records for channel
'
functional tests and channel calibrations including associated
I
isolation / actuation signal circuits. 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
! of Radiation Monitoring Systems," with cognizant licensee personnel. The
licensee has an independent verification program that addresses the types
'
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 occurrences.
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No violations or deviations were identified.
8. Post-AccidentSamplingSystem(PASS)(92701,84723,84724,84725)
The inspector observed portions of a PASS Training Module being conducted
- during the inspection. 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 practices. The training appeared to be effectively
implemented. The inspector noted that the Plant Chemist and an auditor
from Quality Assurance was in attendance.
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 statior.
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 made. Future
i
modifications are also planned for obtaining grab samples for isotopic
'
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-0737.
Any modifications to the PASS will be reviewed during routine inspections.
(Closed)InspectorFollowupItem 50-416/86-09-01: Review and verification
testing of PASS engineering design changes.
- No violations or deviations were identified.
9. Radiochemical Quality Assurance Program (84725)
,
The inspector reviewed the licensee's radiochemical quality assurance
Guide 4.15, " Quality
,
Assurance for Radiological Monitoring Programsprogram against the criteria giv
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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
systems. 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 noted.
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i No violations or deviations were identified,
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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 geometries.
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 agreement.
No violations or deviations were identified.
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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 program.
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 decreases. )
RATIO = LICENSEE VALUE
NRC REFERENCE VALUE
lj
Resolution Agreement
>4 0.4 - 2.5
4-7 0.5 - 2.0
8 - 15 0.6 - 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
'
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(
8
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- 85c. 2.86 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
. ('
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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