IR 05000220/1978014
| ML17053A266 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 10/19/1978 |
| From: | Kottan J, Stohr J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17053A263 | List: |
| References | |
| 50-220-78-14, NUDOCS 7812010041 | |
| Download: ML17053A266 (16) | |
Text
U.S.
NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I
0
. ~50-220 15-Docket No.
50-220 License No. DPR-63 Priority Category Licensee:
300 Eri u
va S racuse New York 13202 Facility Name:
Nine Mile Point Nuclear Station Unit
Inspection at:
Lycoming, New York Inspection conducted:
Septem er 25-27, 1978 Inspectors:
M W
e f'i J. J. Kottan, Radiation Specialist D.
M.
G s'-
Pat si gned date signed date signed Approved by:
J.
P S ohr, Chief, Environmental and Special Projects Section, FF&MS Branch ate igned Ins ection Summar
ns ection on Se tember 25-27, 1978 Re or t No. 50-220 78-14 A~:
1, dd
1
11
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radsochem~cal measurements program using NRC: I Mobile Radiological Measurements Laboratory and laboratory assistance provided by DOE Radiological and Environmental
= Services Laboratory.
Areas reviewed included:
program for quality control of analytical measurements, audit results, performance on radiological analyses of split actual effluent samples, and effluent. control records and procedures.
The inspection involved 20 inspector-hours onsite by the NRC regional based inspector.
Results:
Of the four areas inspected, no items of noncompliance were identified.
~ 8280 3, Qc)g(
Region I Form 12 (Rev. April 77)
DETAILS Persons Contacted Princi al Licensee Em lo ees
"T. Perkins, Plant Superintendent
- J. Quell, Assistant Chemistry and Radiation Protection Supervisor E. Leach, Radiation Protection and Radiochemistry Supervisor The inspector also talked with and interviewed other licensee employees including members of the chemistry and health physics staff.
- denotes those present at exit interview.
Licensee Action on.Previous Ins ection Findin s
(Closed) Infraction (77-22-02): Mercuric thiocyanate reagent dating.
The inspector examined the mercuric thiocyanate used for chloride analysis and noted the reagent was properly labeled as required.
(Closed)
Unresolved item (77-22-01): Action point indication on weekly
"
iodine and particulate filter analysis sheet.
The inspector noted that Procedure Nl-CRP-3, Stack Release Sampling and Analysis, contains
'n action point of 1X10"2 uCi/sec on the weekly iodine and particulate filter analysis sheet.
(Closed} Unresolved item (76-25-05):
MDA and error calculation incon-sistency.
The inspector determined by hand calculations that the licensee could meet the MDA's required by his technical specifications even though his multichannel analyzer system indicated higher MDAs.
The inspector noted this was a computer problem,'nd since the licensee was meeting the required MDA'nd would continue to resolve this problem this item is considered closed.
Laborator C Pro ram The inspector reviewed the licensee's program for quality control of analytical measurements and noted that the licensee's program remains the same as documented in NRC Inspection Report 50-220/77-22.
The gC program is detailed in Section II of Volume III of the Site Chemistry and Radiation Protection Manual.
The inspector discussed laboratory gC with the licensee.
The inspector also discussed various aspects of NRC Regulatory Guide 4.15, guality
Assurance for Radiological Monitoring Programs (Normal Operations)-
Effluent Streams and the Environment.
The, inspector noted the licensee had no regulatory requirements in the area of laboratory gC and had no further questions in this area.
No items of noncompliance were identified.
Audit Results The inspector determined that the licensee,'s effluent monitoring program was on the gA audit list.
The inspector reviewed Audit SR-78-023 dated August 14-22, 1978, which was the last audit performed in this area.
The inspector had no further. questions in this area.
No items of noncompliance were identified.
Confirmator Measurements During the inspection, actual liquid and gaseous effluent samples were split between the licensee and NRC:I for the purpose of intercomparison.
The effluent samples were analyzed by the licensee using his normal methods and equipment, and the NRC using the NRC: I Mobile Radiological Measurements Laboratory.
Joint analyses of actual effluent samples determine the licensee's capability to measure radio-activity in effluent samples.
In addition, a liquid effluent sample was sent to the NRC reference laboratory, Department of Energy, Radiological and Environmental Services Laboratory (RESL), for analyses requi,ring wet chemistry.
The analyses to be, performed on. the sample are: Sr-89, Sr-90, gross alpha, gross beta and tritium.
These results will be compared with the licensee's results when received at.a later date, and will be documented in. a subsequent inspection report.
The results, of'the sample measurements compared, indicated that all of the measurements were in agreement, or possible agreement, under the criteria used for comparing results.
(See Attachment 1.)
The results of, the comparisons are listed in Table l.
Records and Procedures The inspector reviewed the following records and procedures:
a.
Gaseous effluent analysis data (January 1978 to August 1978).
b.
Liquid effluent analysis data (January 1977 to August 1978).
c.
Counter calibration and check records (January 1978 to August 1978).
d.
Laboratory gC sample analyses (January 1977 to August 1978).
e.
The following procedures:
(1)
PSP-4, Liquid Waste Sampling, Analysis, and Record Keeping (2)
PSP-7, Radioactive Airborne Radwaste Sampling and Analysis (3)
S-CAP-ll, Chloride Ion Analysis in Water (4)
Nl-CRP-3, Stack Release Sampling and Analysis (5)
Nl-CRP-8, Reactor Water Isotopic Analysis 7.
Exit Interview The inspector met with licensee representatives (denoted in paragraph 1)
at the conclusion of the inspection on September 27, 1978.
The inspector summarized the purpose and scope of the inspection and the inspection findings.
The licensee agreed-to perform the analyses listed in paragraph 5 and report the results to the NR TABLE 1 NINE MILE POINT - VERIFICATION TEST RESULTS SAMPLE ISOTOPE NRC VALUE LICENSEE VALUE COMPARISON RESULTS IN MICROCURIES PER MILLILITER Waste Hold Up Tank 1125 9/26/78 I-131 Cs-134 Cs-137 Co-60 (8.42+0.63)E-6 (7.74+0.09)E-5 (1.84+0.02)E-4 (2.35+0.12)E-5 (1.07~0.17) E-5 (7.79+0.30)E-5 (1.91+0.04)E-4 (2.5340.20)E-5 Agreement Agreement Agreement Agreement Off Gas 0730 9/25/78 Xe-133 Xe-135 Kr-85m (1. 67+0.01) E-2 (1. 85+0. 01) E-1 (2.50+0.20)E-2 (2. 29~0.02) E-2 (1. 93%.19) E-1 (4.692+7)E-2 Possibl e Agreement Agreement Possible Agreement
TABLE
NINE MILE POINT VERIFICATION TEST RESULTS SAMPLE ISOTOPE NRC VALUE LICENSEE VALUE COMPARISON RESULTS IN MICROCURIES PER MILLILITER Stack Charcoal 9/26/78 I-131 I-133 (2.1940.10)E-11 (9.24+0.46)E-10 (1.37+0.05)E-11 (2.98+0.25)E-10 Possible Agreement Possible Agreement Stack Particulate 9/22/78 I-131 Co-60 I-133 (1. 74+0.07) E-12 (5.56+0.94)E-13 (8.0840.17)E-11 (2.74+0.32)E-12 (9.22+1.91)E-13 (1.20+0.17)E-10 Poss ible. Agreement Agreement Possible Agreement Stack Charcoal 9/19/78 I-131 (2. 25+0. 11 ) E-11 (2.407+?)E-ll Agreement Stack Particulate 9/19/78 Co-60 I-131 (2.06+0.21)E-12 (2.310+?)E-12 (1.70+0.17)E-12 (2.573+?)E-12 Agreement Agreement
TABLE
NINE MILE POINT - VERIFICATION TEST RESULTS SAMPLE ISOTOPE NRC VALUE LICENSEE VALUE COMPARISON RESULTS IN HICROCURIES PER MILLILITER Reactor Water 1100 9/25/78 I-131 I-132 I-133 I-134 I-135 (8.51+0.41)E-4 (3.07+0.16)E-2 (1.2840.06)E-2 (1.0940.05)E-1 (3.2440.16)E-2 (8.207+?)E-4 (3.88+?)E-2 (1.08+?)E-2 (1.347+?)E-1 (2.787+?)E-2 Agreement Agreement Agreement Agreement Agreement
Attachment
Criteria for Com grin Anal tical 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 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 as the resolution decreases.
LICENSEE VALUE RATIO= NRC REFERENCE VALUE Resolution Agreement Possible A reement A
Possible A reement B
<34-7 8'- 15 16-50 51 - 200
>200 0.4-0.5-0.6-0.75-0.80-0.85-2.5 2.0 1. 66 1.33 1.25 1.18 0.3 - 3.0 0.4 - 2.5 0.5 - 2.0 0.6 - 1.66 0.75 - 1.33 0.80 - 1.25 No Comparison 0.3 - 3.0 0.4 - 2.5 0.5 - 2.0 0.6 - 1.66 0.75 - 1.33
"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.
Iodine on absorbers
"B" criteria are applied to the following analyses:
Gamma Spectrometry where principal gamma energy used for identification is less than 250 Kev.
89Sr and 90Sr Determinations.
Gross Beta where samples are counted on the same date using the same reference nuclid \\ tf 4+~
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