IR 05000219/1975016
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IE I Form 12.
(Jan 75) (Rev)
U. S. NUCLEAR REGUIATORY COMMISSION
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OFFICE OF INSPECTION AND ENFORCEMENT
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REGION I
IE Inspection Report No:
50-219/75-16 Docket No:
50-219 s
Licensee: Jersey Central Power and Light Company License No:
DPR-16 Madison Avenue at Punch Bowl Road Priority:
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C Morristown, New Jersey 07960 Category:
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Safeguards Group:
Incation: Oyster Creek Station (OC), Forked River, NJ 08731 Type of Licensee:
BWR, 640 MWe
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Routine, Announced (Independent Measurements)
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- ,4 Dates of Inspection
May 29-30, 1975
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Dates of Previous Inspection:
May 21-22, 1975
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Reporting Inspector:
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J.' Everett, Radiation Specialist Accompanying Inspectors:
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DATE DATE Other Accompanying Personnel:
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bl; h/D Reviewed By:
M,m DAW Stofr,'
Senior Environmental Scientist J.
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9604230309 960213 PDR FOIA DEKOK95-258 PDR
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SUMMARY OF FINDINGS cm!
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Enforcement Action A.'
Items of Noncompliance 1.
Violations
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Infractions None
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Deficiencies None B.
Deviations i
None Licensee Action on Previously Identified Enforcement Items (Independent ggpq Measurements)
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None applicable.
Design Changes None applicable.
Unusual occurrences None Other Significant Findings A..
Current Findings-1.
General This report summarizes the. licensee's performance on verifi-cation test samples.
70% of the licensee's measurements were in agreement, 23% possible agreement and 7% disagreement.
(Details, Paragraph 3)
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Acceptable Areas (No items of noncompliance were noted)
Liquid rad waste compositing procedure.
(Details, Para-fl,l a.
kT graph 4)
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Unresolved Items None 4.
Infractions and_ Deficiencies Identified by Licensee a.
Infractions None
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Deficiencies None B.
Status of Previously Reported Unresolved Items (Independent Measurements)
1.
Reference R0 Report No. 50-219/73-19 and IE Report No.- 50-219/75-03 Licensee is now in agreement with the reference laboratory on iodine meaaurements of charcoal samples.
This item is considered resolved.
(Details, Paragraph 3)
3;gz Management Interview The following individuals attended the management interview at the conclusion of tis inspection:
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Mr. J. T. Carroll, Station Superintendent, OC Mr. E. J. Growney, Technical Engineer, OC Mr. J. R. Pelrine, Chemical Supervisor, OC
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Mr. R. J. Everett, Radiation Specialist, IE:I During the meeting the following items were discussed:
A.
Iodine Measurements of Gaseous Effluent-The inspector stated that the iodine test sample submitted during the inspection was in agreement with the reference laboratory.
The licensee stated that a counting method would be developed that would enable accurate measurement of iodines of any distri-bution'on the charcoal.
(Details, Paragraph 3)
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Compositing of Liquid Radwaste Samples
- :, 1 ffh The inspector stated that a review was made of the licensec's modified radwaste compositing procedure and that he had
.o further questions on this matter.
(Details, Paragraph 4)
C.
Location of Counting Facilties*
The licensee stated that plans now call for a new structure south of the plant that would house the counting laboratory and other plant functions.
(Details, Paragraph 4)
D.
Laboratory QA/QC Program
.a The inspector noted that the licensee's laboratory QA/QC implementing procedure was essentially complete and had no further questions.
The licensee stated that as portions of the program are written and approved, implementation would follow with final program completion by the end of 1975.
(Details, Paragraph 5)
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- Telephone conversation with J. T. Carroll on June 4, 1975.
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DETAILS
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Persons-Contacted
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Mr. J. T. Carroll, Station Superintendent, OC Mr. E. J. Crowney, Technical Engineer, OC Mr. E. J. Pelrine, Chemical Supervisor, OC Mr. C. Konta, Chemical Foreman, OC Mr. R. Dube, Site QA Engineer, OC 2.
General The' inspection consisted of a review of the licensee's performance
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on verification test samples collected by IE:I personnel and analyzed by the NRC's reference laboratory, Idaho Health and Safety Laboratory, (IHSL) and the IE:I Mobile Measurements Vehicle. These samples test the licensee's capability to measure radioactive material in actual effluent samples. Some test standards were also submitted to OC for analysis. The activity of the test' standards and IHSL's measurements of effluent samples are referenced to the National Bureau of Standards by laboratory intercomparisons.
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Results of Verification Test Samples
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This report summarizes the licensee's performance on verification test samples collected in the IE:I Mobile Lab Visit of January 20-23, 1975. The eight samples measured resulted in 70% agreement, 23% possible agreement and 7% disagreement.* The types of samples collected and the results of measurements were:
Type of Sample: Radwaste, 12-4-74 Acceptable Results in Units of Microcuries Per Milliliter Radionuclide NRC Measurement Licensee Measurement (1)
Cross beta 1.38 i.04 E-6 3.5 1.0 E-6 H-3 1.12
.01 E-2 1.2
.02 E-2 SR-89 2.4 i.2 E-7 3.6 !.1 E-7 SR-90 7.
2 E-9 1.4 1.05 E-8 Ce-141 2.9 i.9 E-7 3.4
.1 E-7 Co-60 3.6 i.5 E-7 2.8 i.4 E-7 Cr-51 2.7
.6 E-6 1.6 i.08 E-6
- See attachment 1 to this report for a description of the criteria
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used to evaluate differences between analytical results.
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. (1) Possible Agreement
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Type of Sample: Radwaste, 1330 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.06065e-4 months <br />, 1-21-75
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j Radionuclide-NRC Measurement Licensee Measurement Gross beta 2.83 i.03 E-4 4.2 i.1 E-4 (1)
H-3 1.20
.01 E-2 1.0 i.001 E-2
'Sr-89 1.01
.04 E-5 1.0
.03 E-5 Sr-90 1.07
.05 E-6 1.2
.02 E-6
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Mn-54 5.35
. 1 E-5 7.3 i.5'E-5 (1)
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Co-60 1.64 i.02 E-4 2.0 i.1 E-4 Cs-137 1.46 1.02 E-4 1.4
.07 E-4 Ba-140 8.0-1.6 E-6 7.0 1 2. E-6 I-131 9.99
.1 E-5 9.3 1.4 E-5
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l Cs-134 6.89
.1 E-5 6.7
.4 E-5 Type of Sample: Offgas, 0957, 12-4-74
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Acceptable Results in Units of Microcuries Per Milliliter Radionuclide NRC Measurement.
Licensen Measurement
Xe-133 3.51
.09 E-2 2.9
.1 E-2
Xe-135 1.9
.4 E-1 1.6 i.1 E-1
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Type of Sample: Offgas, 1509 hours0.0175 days <br />0.419 hours <br />0.0025 weeks <br />5.741745e-4 months <br />, 1-22-75 Acceptable Results in units of Microcuries Per Milliliter Radionuclide NRC Measurement Licensee Measurement
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Xe-133 4.3 i.1 E-2 3.5 i.05 E-2 Kr-87 2.1
.03 E-1 2.0
.04 E-1
Kr-88 11.5 i.5 E-2 9.0
.02 E-2 Xe-135 2.23
.01 E-1 1.8 1.04 E-1 (1)
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Xe-133M 3.7 i.2 E-3 1.0
,25 E-3 (1)
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Xe-135M 1.02
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Type of_Sampic: Charcoal Cartridge, 0840 hours0.00972 days <br />0.233 hours <br />0.00139 weeks <br />3.1962e-4 months <br />, 1-20-75 I
Not Acceptable Results in units of Microcuries
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Radionuclide'
NRC Measurement Licensee Measurement I-131
.450 1.002
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I-133
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' (1) Possible Agreement l
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- 5-Type of Sample: Standard Charcoal, reference date 8-6-74, Sample '"B" N[
Acceptable Results in Units of Microcuries Radionuclide NRC Measurements Licensee Measurements Ba-133 1.18 t.04 E-2 1.13 ! ? E-2 Type of Sample: Standard Charcoal, reference date 10-28-74, Sample "H4" Acceptable Results in Units of Microcuries Radionuclide NRC Measurements Licensee Measurements Ba-133 7.61
.01 E-2 5.9
? E-2 (1)
Type of Sample: Charcoal Cartridge, 0945, 12/3/74 Acceptable Results in Units of Microcuries Radionuclide NRC Measurements Licensee Measurements 1-131 4.1 i.01 E-1 3.3
.03 E-1 (1)
d4W1 The inspector noted that the licensee's effluent release were
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generally a few percent of Tech Spec limits, and any analytical discrepancies in themselves, would not have caused the licensee to exceed any regulatory limit.
The inspector noted that the iodine sample submitted during the inspection and analyzed by the licensee was in agreement with the reference laboratory. The inspector reviewed the measurement i
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stepwise and inquired as to why previous iodine measurements, over the past year were low by a factor of 1.6 - 1.8 and the current
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measurement was in agreement using the same efficiency factor.
The licensee stated that it was possible the wrong side of the cartridge was counted in the past. The inspector reviewed nuclear constants used in the measurement and noted that repeated counts during the night indicated spectrometer reliability. The inspector stated that the matter appeared to be a problem of counting pro-cedure rather than calibrations. The licensee stated that in the future, the counting procedure would require a measurement on each side of the cartridge. The two results would then be averaged.
This procedure would eliminate the problem of counting the wrong side and would also allow accurate measurement of iodine of any distribution on the cartridge, if a calibration for a uniform distribution is used. The-inspector stated that several iodine cartridge samples would be collected over the next few emonths to verify this procedure.
(1) Possible Agreement
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The inspector reviewed the results of measurements on all samples i/
from the last inspection and stated that with the exception of
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iodine measurements, no other action was indicated. Measurements
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in the category of possible agreement will be followed in subse-quent inspections.
4.
Radiochemical Practices The inspector reviewed a modified liquid radwaste compositing procedure. The inspector noted the requirement to add hydrochloric acid and sodium bisulfite to these solution to prevent losses of radioactivity during storage. The inspector had no further questions.
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The inspector inquired as to plans to relocate the counting facili-
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ties, now located in a higher than desirable radiation background area. The licensee responded that a new structure, south of the plant, was planned; pending approval of capital funds. The building would provide a permanent, regulated structure for the counting lab as well as other office space. The inspector stated that progress on this structure would be followed in subsequent inspections.
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Laboratory QA/QC Program i ;g The inspector reviewed a draf t of the licensee's laboratory QA g
impletaenting procedure and stated that except for the modifications
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outlined the procedure appears to cover the essential elements of a laboratory QA Program. The inspector asked when the procedure would be completed and the full program initiated.
The licensee stated sub-categories of the implementing procedure and detailed procedures covering tests and measurements were about 50% completed and anticipated completion and implementation of the program by the end of the year. The inspector reviewed the OC QA Manual and verified that the chemistry unit was on the audit list and necessary
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inspection procedures were specified. The inspector noted that the chemistry unit has never been audited by the site or corporate QA staff and inquired as to their schedule for this inspection.
The licensee responded that with present priorities, a early 1976 audit appeared certain.
The inspector stated that the checklist for this
inspection and the findings would be reviewed after completion.
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Attachment 1 Criteria for Comparing Analytical Measurements This attachment provides criteria for comparing results of capability
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tests and verifi ation measurements. The criteria are based on an 3.y i,3 empirical relationship which combines prior experience and the accuracy needs of this program.
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In these criteria, the judgement limits are variable in relation to the comparison of the NRC Reference Laboratory's value to its associated uncertainty.
As that ratio, referred to in this program as " Resolution",
increases the acceptability of a licensee's measurement should be more selective.
Conversely, poorer agreement must be considered acceptable
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as the resolution decreases.
LICENSEE VALUE 3*
RATIO = NRC REFERENCE VALUE
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Possible Possible Resolution Agreement Agreement A Agreement B,
<3 0.4 - 2.5 0.3 - 3.0 No Comparison 4-7 0.5 - 2.0 0.4 - 2.5 0.3 - 3.0 8 - 15 0.6 - 1.66 0.5 - 2.0 0.4 - 2.5 16 - 50 0.75 1.33 0.6 - 1.66 0.5 - 2.0 51 - 200 0.80 - 1.25 0.75 - 1.33 0.6 - 1.66
>200 0.85 - 1.18 0.80 - 1.25 0.75 - 1.33 ggy
"A" criteria are applied to the following analyses:
Gamma Spectrometry where principal gamma energy used for identification is greater than 250 Kev.
Tritium analyses of liquid samples.
"B" criteria are applied to the following analyses:
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Gamma Spectrometry where principal gamma energy used for identification is less than 250 Kev.
895r and 90Sr Determinations.
Cross Beta where samples are counted on the same date using the same reference nuclide.
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