IR 05000010/1977026
| ML20037B419 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 09/27/1977 |
| From: | Barker J, Essig T, Oestmann M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20037B416 | List: |
| References | |
| 50-010-77-26, 50-10-77-26, 50-237-77-23, 50-249-77-23, NUDOCS 8009260690 | |
| Download: ML20037B419 (8) | |
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U.S.' NUCLEAR REGULATORY C0!! MISSION
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OFFICE OF INSPECTION AND ENFORCEMENT
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REGION III
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Report Nos. 50-10/77-26; 50-?37/77-23; 50-249/77-23 Docket Nos. 50-10; 50-237; 50-249 License Nos. DPR-2; DPR-19; DPR-25 Licensee: Commonwealth Edison Company Post Of fice Box 767
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Chicago, IL 60690 Facility.Name: Dresden Nuclear Generating Station, Units 1, I, and, Q.
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Inspection at: Dresden. Site, Morris,. IL
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Inspectian Conducted: August 30, 31, and September 2, 1977
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'.ij/.% { a f,lits 6.
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Inspectors:
b.JfOestmann 4!M/7 7'
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.fbCA
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i EI7/h J. L. Barker
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Approved By:
T. H.
f Environmental.and Special Projects Section
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Summary:
Inspection on August 30-31, and September 2, 1977 (Report Nos.- 50-10/77-26;
l 50-237/77-23; 50-249/77-23)
i freas Inspected: Confirmatory Measurements involving results of-iomparative analyses of. radiological effluent samples collected in i
.May 1977 and. standard liquid and simulated gas. samples; reviewed the status of the cil leakage and cleanup; assessed the status of the chemical spill and corrective _ action in the makeup demineralizer room.
The inspection involved 23 inspector-hours on site by two NRC inspectors.
- Results: No apparent items of noncompliance or deviations were identified.
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The licensee has taken appropriate corrective action to avoid fumes in the
control room from'the chemical spill and to minimize c'1' leakage into the Illinois River.
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~s DETAILS
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Persons Contacted
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Principal Licensee Employees
- A, Roberts, Assistant Plant Superintendent N. Scott, Shift Supervisor R. Ragan, Operating Engineer L. Duchek, Assistant Operating Engineer
- D. Adam, Radiation / Chemistry Supervisor
- G.
Bergan, Plant Chemist
- G.
Reardan', Quality Assurance Engineer
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The inspectcrs also interviewed seven other licensee employees'
during the course of the inspection. They involved chemistry and health physics staff, and members of the security force.
- denotes those present at the exit interview.
2.
Confirmatorv Measurements Program The Confirmatory Measurements inspection censisted of a test of
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the licensee's capability to measure radioactivity in actual or simulated effluent samples by comparing the licensee's measure-ments with those of the NRC's Reference Laboratory. The two laboratories performed measurements on the same samples, or on duplicates or splits of the same samples. The measurements made by the NRC Laboratory are referenced to the National Bureau of Standards' radioactivity measurements systen.3 by laboratory intercomparison.
A discussion of a confirmatory measurements progra'm was presented in a letter dated September 3,1976, from Mr. J. G. Keppler, Director, RIII, USNRC, to Commonwealth Edison Company.
3.
Comparison of Analytical Measurements The inspector reviewed the analytical results of the gaseous and liquid waste, particulate filter and charcoal adsorber samples collected from the Dresden Nuclear Generating Station in May 1977.
In addition a standard liquid sample and a standard simulated gas sample were provided to the licensee. The results of the licensee's and the NRC Reference Laboratory's (Health Services Laboratory)
analyses were compared using the " Criteria for Comparing Analytical Measurements" (Attachment 1).
A summary of these results by sampic
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type and isotope is presented in Table 1 (Attachment 2).
In s
Table 2, the results of comparison of the licensce's analyses
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of the standard simulated gas sample for seven major gamma peaks are also presented.
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The inspector discussed these results with licensee' representatives and noted the following analyses which were in disagreement.
a.
Liquid Waste The inspector noted that the licensee did not report the presence of cesium-lS4 in the liquid waste sample as compared with those results fron the NRC Reference Laboratory. The inspector discussed with the licensee representatives the
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techniques used to analyze for this nuclide. The licensee in one of its analyses did find cesium-134 present but the*,
concentration found was below the einimum detectable limit and therefore the licensee did not report any present.
If the difference in results of cesium-134 is real and represen-tative of routine analyses, the licensee could have under-reported the release of this nuclide during the time of comparison. However, during this time the licensee did not discharge any liquid radioactive effluents from Units 2/3
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and thus could not exceed the technical specification limits.
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b.
Simulated Gas Standard Sample The inspector arranged to provide the licensee with a sim-ulated gas standard sample. The licensee was to determine the gamma activity at the major gamma energies of the standard sample. Results show that the licensee's analyses were in disagreement with the standard values. The inspector discussed with the licensee representatives the techniques used to analyze for the gamma peaks but there was no apparent explanation of the discrepancies in the results.
It was agreed that results from other licensees would be compared-to determine the performance cf other laboratories using the same source.
No apparent items of noncompliance or deviations were identi-fled.
Correction of Misstatement in Previous Inspection Report In Inspection Report No. 50-010/77-14 it uns stated on page 3 that the licensce's concentration of iodine-131 in the liquid
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waste rample was found to be 21 times higher than that obtained
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by the NRC Reference Laboratory. Upon reexamination of the
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results, it was determined that the licensee's measurement of the iodine-131 concentration in the liquid waste sample,was about five times higher than that obtained by the NRC Reference Laboratory.
5.
Observation of Corrective Action For Oil Leakace The inspector observed the corrective action being taken by the licensee to locate the source of oil leakage into the intake canal. The licensee has excavated several areas and has kept the leakage under control from the fuel oil storage tank to the storm sewer which drains into the intake canal.
In addition, the inspector observed that the licensee had placed log booms in the discharge canal to collect and skim the oil film from the water. *
surface. The total amount of oil discharged was estimated by the U. S. Coast Guard to be about 240 gallons. Representatives from the Environmental Protection Agency also have visited the site.
It appears that the licensee has taken appropriate corrective action to minimize the leakage and to remove the oil-contaminated soil.
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No items of noncompliance or deviation was disclosed.
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6.
Licensee Event Followup-LER 77-31 The inspectors verified that the licensee's review, corrective action, and report of the identified event and associated condi-tions were adequate end in conformance with regulatory require-ments, Technical Specifications, and licensee procedures and controls.
The licensee indicated that the short term corrective action for the event was as follows:
Issue a procedural change preventing the simultaneous filling a.
of the acid and caustic day tanks.
b.
Issue a procedure to allow jumpering control room ventilation relays so that 100% outside air ventilation dampers could be opened.
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s The licensee indicated that the long tenn corrective action was as follows:
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a.
Issue a major modification of the makeup demineralized _ water system containing controls preventing acid and caustic tank overflow, b.
Install a switch in the control room which would allow control room ventilation dampers to be switched to the 100% outside air ventilation rode.
c.
Install a new fan in the makeup demineralizer area exhaust ventilation ducting.
d.
Install a damper in the shift locker area exhaust ventilati'on ducting which will shut on reverse flow.
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Install electrical conduit sealant a'round all floor penetration above the makeup demineralizer area.
No items of noncompliance or deviations were identified.
7.
Exit Interview
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The inspector met with licensec' representative (denoted in Paragraph 1)
at the conclusion of the confirmatory measurements inspection on August 31, 1977. The inspector summarized the scope and findings of the inspection. The licensee representatives made the following remarks in response to certain of the items discussed by the in-spector:
a.
Acknowledged the findings by the inspector with respect to the analytical results of the confirma' tory measurements program.
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Acknowledged the findings by the inspector with respect to the corrective actions taken to cleanup the oil spill and-
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i to prevent recurrence of fumes entering the control room
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from the chemical spill in the makeup demineralizer room.
l Attachments:
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Attachment 1, Criteria for Comparing Analytical Measurements 2.
Table 1, USNRC Confirmatory Measure-ments Program, 2nd quarter of 1977, Dresden 3.
Table 2, USNRC Confirmatory Measure-ments Program, 2nd quarter of 1977, Dresden-5-t l
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ATTACIDtENT 1
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CRITERIA FOR CO:1 PARING ANALYTICAL liEAS11RD;ENTS
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This attachment provides criteria for comparing results of capability tests and verification measurements. The criteria are baned on an
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empirical relationship which combines prior experience and the accuracy
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needs of this program.
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In these criteria, the judgment limits are variable in relation to the comparison of the NRC Reference Laboratory's value to its associated one sigma uncertainty. As that ratio, referred to in this program as
" Resolution", increases, the acceptability of a licensec's measurement should be more selective. Conversely, poorce agreement should be con-sidered acceptable as the resolution decreases.
The values in the ratio criteria may be rounded to feucr significant figures to maintain statistical consistency uith the number of significant figures reported
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by the NRC Reference Laboratory, unless such rounding uill result in a
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narrowed category of acceptance. The acceptance category reported uill be the narrouest into which the ratio fits for the resolution being'used.
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RESOLUTION RATIO. LICENSEE VALUE/NRC REFERENCE VALUE
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Possibic Possibic Agreement Agreement "A" Agrecable "B"
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No Comparison No Comparison No Comparisen
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>3 and <4 d.4 - 2.5 0. 3
- 3.0 No Ccmparison 3'4 and <8 0.5 - 2.0 0.4
- 2.5 0.3
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3'8 and <16 0.6 - 1.67 0.5
- 2.0 0.4
- 2.5
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3'16 and <51 0.75 - 1.33 0.6
- 1.67 0.5
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3'51 and <200 0.80 - 1.25 0.75 - 1.33 0.6
- 1.67
][200 0.85 - 1.18 0.80 - 1.25 0.75 - 1.33
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"A" criteria are applied to the following analyses:
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Gamma spectrometry, where principal gamma energy.used for identifi-cation is greater..han 250 kcV.
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Tritium analyses of liquid samples.
"B" criteria are applied to the following analyses:
Camma spectrometry, whcre principal gamma cncray used for identifi-cation is less than 250 kcV.
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Sr,-89 and Sr-90 determinations.
Gross beta, where sanples are counted on the same date using the
.same reference nuclidc.
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U S HUCLEAR RECULATORY C6MHISSION'
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0F,F I CE OF INSPECTION AND ENFORCEMENT
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E EO CONF I R M A T OP Y MEASUREMENTS Ph0 GRAM
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i gg g FACILITY: ORF50EN123 FOR THE 2 00ARTER OF 1977
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b55U------NRC-------
---LICENSEE-----
N R C : L I C E N S E E ---------- ---
S A MP LE ISOTONE
'R E-S U L T ERh0R RESULT FRROR Z V3LUE FCT RATIO RES T
.0FF GAS XE 133 3 7 E -0 2 1 1E-03 4 3E-02 1 0E-n3 4 0E+00 1.ot+01 1 2E+00 3.CF+01 A
XE 133M 4 '. 0 E -0 3 1 0E-03 2 6E-03 3 0E-04 1 3E+00 3 5E+01 6 5E -01 4 0E+00 A
L VASTE BFTA 1 3E -05 3'.05-07 8 1E-06 2 0E' 0 7 1 4E+01 3 6E +01 662E-01 e.3F+01 F
CO 60 1 6E-05 5.CE-07 1 5E-05 1 0E-06 8 9E-01 6 3E+00 9 4E-01 3 2E+01 C
00
00 1.1E+01 D
?.0E -0 7 2 4 E -0 6 2 0E-07 2 1E+00 2 0E +01 8.0 E -01 1 5 E + 01 A
H 3 5 0E-9 3 2 0F-05 5 2E-03 5 0E-04 4 0E-01 4 0E +00 1 0E+00 2 5E+02 A
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P FILTER CG 58 1 2E-04 1 2E -0 5 8 4 E -0 5 7 0E-0 6 2 6E+00 3 0E +01 7 0 E -G 1 1 0E+01 A
C0 60 1 3E-04 1 2c-05 1 4E -0 4 2 0E-05 4 3E-01 7 7E +00 1.1F+00 1 1E+01 A
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CS 134 1 8 E-0 4 1.0E-05 1 6E-04 1 0E -0 5 1 4E+00. 1 1E +01 8 9E-01'
1.EF+G1-
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CS 137 6 1E-04-2 4C-05 6 2E-04 1 0E-0 5 3 8E-01 1 6E +00 1 0E +00 245E+C1 A
B*
140 1 5E-03 1..E-04 1 5E-03 1 0E-04
00 1 0E+00 1 1 E + G1 A
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d.5E-01 N
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'.3E+00 i
C FILTER I 1 31
6 6E-02 2 6E+00 8,0E-01 3 7E-01 1 3E+01 1 1E+0C 3s5E+01 A
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L SPIKED Sr, 69 5 7E-03 1 2E-04 5 1'-03 5 0E -0 4 1 2E+00 1 1 E + 01 S e 9 E -01 4 7F+G1 A
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SR 90 5.bE-04 264E-05 4enE-04 4 0E-05 3 9E+00 3 1 E + 01-6 9E-01 2.4E+01 F
CG 60 2.1E-04 1.GE-05 2'FE-04 1 1E-05 4 7E+00 3 3 E + 01 ' 143E+00 2 1E+01 P
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CS 137 1 8E-04 1 0E-05 1 9 E -0 4, 7 0E-06 6 2E-01 So6c+00 1 1E+00 1 5 E +01 A
BA 133 1 8E-03 1 0E-04 T.7E-03 1 0E -0 5 1 0E+00 5 6E +00 9 4E-01 1.8E+01 A
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2 9E-03 6 0E-05 3 0E-03-3 0E-04 3 3E-01 3 4E +00 1 0F+00 4.BE+01 A
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1 TEST RESULTS:
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A => 0f EEFE N T
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P=FOSSI?LE AGREEMENT
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N=NO CO? tRISON
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TABLE 2
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U. S. NUCLEAR REGULATORY COMMISSION I
CONFIRI!ATORY MEASUREMENTS PROGRAM FACILITY: DRESDEN FOR Tile 2ND QUARTER OF 1977
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NRC: LICENSEE---
SAMPLE ENERGY RESULT ERROR RESULT ERROR RES RATIO T
IN KEV (6/1/77)
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2.16E+05 0.9E+04 1.47E406 1.2E+05
6.81 D
303 1.34E+05 0.9E+04 1.73E+06 1.2E+05
12.9 D
346 2.7E+06 1.9E+05 5.87E+07 0.3E+06
21.7
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356 3.68E+05 2.8E404 6.03E+06 1.4E+05
16.4 D
779 1.33E+06 0.8E+05 2.59E+07 0.3E+06
19.5 D
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964 1.50E+06 0.9E+05 2.89E+07 0.3E+06
19.3 D
1408 2.14E+06 1.3E+05 4.17E+07 0.4E+06
19.5 D
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