IR 05000293/1979005
| ML19254D545 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 09/10/1979 |
| From: | Bores R, Kottan J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19254D540 | List: |
| References | |
| 50-293-79-05, 50-293-79-5, NUDOCS 7910290066 | |
| Download: ML19254D545 (8) | |
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U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT REJION I Report No.
50-293/79-05 Docket No.
50-293 License No.
DPR-35 Priority Category C
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Licensee:
Boston Edison Company M/C Nuclear 800 Boylston Straet Boston, Massachusetts 02199 Facility Name:
Pilgrim Station Inspection At:
Plymouth, Massachusetts Inspection Conducted:
July 25-27, 1979 Inspectors: T.a./
Ft 9-/d-79 J. J. Kottan, diation Specialist date T. T l f(Jak 9~/0-79
)tR.M.KnolI,Co-opStudent date
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d date Approved by:
9-/0 - 7/
R. J. Boreii, Acting Chief, Environmental and date Special Projects Section, FF&MS Cranch Inspection Summary:
Inspection on July 25-27, 1979 (Report No. 50-293/79-05)
Areas Inspected:
Routine, unannounced inspection of the licensee's chemical and raciochemical measurements program using laboratory assistance provided by DOE Radiological and Environmental Services Laboratory.
Areas reviewed included:
program for quality control of analytical measurements, audit results, performance in rzdiological analyses of split acutal effluent and spiked samples, and effluant control records and procedures.
The inspection involved 32 inspector-hours onsite by two NRC regional based inspectors.
Results:
Of the four areas inspected, no items of noncompliance were identified.
1221 224 Region I Form 167 7910290C((
(August 1979)
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DETAILS 1.
Persons Contacted
- P. J. McGuire, Station Manager C. Vantrease, Chief Technical Engineer
- R. A. Smith, Senior Chemical Engineer
- C. Mathis, Senior Plant Engineer A. Trudeau, Senior Radiological Engineer The inspector also talked with and interviewed several other licensee employees including members of the chemistry and health physics staffs.
- Denotes those present at exit intcrview.
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2.
Laboratory QC Program The inspector reviewed the liccasee's program for the quality control of analytical measurements ar.d noted that the licensee's laboratory QC pro-gram is detailed in the following procedures:
7.10.1 Radiochemistry Laboratory Quality Control
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7.10.2 Quality Control of Counting Room Instruments
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The inspector reviewed daily source checks, backgrounds, and counter con-trol charts as required by the above procedures for the period July, 1978 to June, 1979.
The inspector also reviewed the results of spiked radio-chemical samples sent to the licensae's contracting laboratory and the results of spiked chloride sample analyses.
Chloride analyses of reactor coolant are required by the licensee's Technical Specifications.
The inspector discussed various aspects of laboratory QC with the licensee.
The inspector noted the licensee had no regulatory requirements in the area of laboratory QC, and the inspector had no further questions in this area.
No items of noncompliance were identified.
3.
Audit Results The inspector reviewed QA Auit No. 79-16 which was conducted on May 2-4, 1979 by the licensee's QA Department.
The audit covered the licensee's chemistry program and included the areas of gaseous effluents, liquid effluents, and the laboratory QC program.
The inspector had no further
questions in this area.
No items of noncompliance were identified.
4.
Confirmatory Measurements During this inspection actual liquid effluent and reactor coolant samples were split between the licensee and NRC:I for the purpose of intercompari-son.
The samples will be analyzed by the licensee using his normal methods 1221 225
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and equipment, and by the NRC reference laboratory, the Department of Energy, Radiological and Environmental Services Laboratory (RESL).
The analyses to be performed on the liquid effluent sample are:
gross beta, gross alpha, strontium-89, strontium-90, tritium, and gamma isotopic.
The analyses to be performed on the reactor coolant sample are gamma isotopic and tritium.
Joint analyses of actual samples determine the licensee's capability to measure radioactivity in actual samples.
These results will be compared by the NRC wnen received at a later date and will be documented in a subsequent inspection report.
Ir addition a spiked charcoal cartridge, a particulate filter, and a simulated offgas sample were submitted to the licensee for analysis.
The comparison of the spiked and simulated sample measurements indicated that all of the measurementswere in agreement under the criteria used for com-paring results.
(See Attachment I.)
The results of an effluent sample split between the licensee and NRC:I during a previous inspection on July 31-August 3, 1978 were also compared during this inspection.
This results comparison indicated that all of the measurements were in either agreement, possible agreement or not comparable under the criteria used for comparing results (see Attachment 1) with the exception of the tritium, which was in disagreement.
No explanation for the disagreement could be offered at this time.
The licensee stated that his tritium analyses were performed by a contracting laboratory.
The inspector noted that in March, 1979 the licensee had submitted a spiked tritium sample to his contracting laboratory as part of his routine laboratory QC program, and the results of the spiked sample analysis were acceptable.
The inspector stated that this disagreement would be considered an Unresolved Item (50-293/79-05-01) and stated that the two liquid samples split during this inspection would be analyzed for tritium.
The inspector also reviewed the licensee's 1978 liquid effluent data and noted the disagreement wculd not have resulted in the licensee exceeding any liquid effluent release limits.
The results of the comparisons are presented in Table 1.
No items of noncompliance were identified.
5.
Records and Procedures The inspector reviewed the following records and procedures:
a.
Gaseous ef fluent analysis data (June,1978-June,1979)
b.
Liquid effluent analysis data (June, 1978-June, 1979)
c.
Counter calibration data (January, 1979-June, 1979)
d.
The following procedur2s:
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7.9.1 Gaseous Waste Discharge Procedure
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7.9.2 Liquid Radioactive Waste Discharge
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7.3.38 Determination of Conversion Factors for Liquid PRM's
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7.3.37 Determination of Conversion Factors for Gaseous PRM's
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7.3.11 Iodine
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6.
Facility Tour The inspector, in the company of a licensee representative, conducted a tour of the facility.
Iti.ms such as housekeeping, maintenance, and radia-tion posting were observed. Within the scope of this tour no items of noncompliance were identified.
7.
Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of noncom-pliance, or durations.
An unresolved item disclosed during the inspec-tion is discussed in Paragraph 4.
8.
Exit Interview The inspector met with the licensee representatives (denoted in Para-graph 1) at the conclusion of the inspection on July 27, 1979.
The inspector summarized the purpose and scope of the inspector and the inspection findings.
The licensee agreed to perform the analyses listed in Paragraph 4 and report the results to the NRC.
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TABLE 1 PILGRIM VERIFICATION - TEST RESULTS SAMPLE IS0 TOPE NRC VALUE LICENSEE VALUE COMPARISON RESULTS IN TOTAL MICR0 CURIES Spiked Charcoal Cartridge 6/1/77 Ba-133 (6.59 1 0.33) E-2 (5.27 i 0.13) E-2 Agreement Spiked Particulate Sb-125 (2.2 1 0.1) E-2 (2.78 1 0.24) E-2 Agreement Filter Cs-134 (3.1 1 0.7) E-2 (3.29 i 0.14) E-2 Agreement 10/28/74 Na-22 (0.57 1 0.04) E-2 (6.42 1 0.50) E-3 Agreement
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TABLE 1 PILGRIM VERIFICATION - TEST RESULTS SAMPLE kev NRC VALUE LICENSEE VALUE COMPARISON RESULTS IN GAMMAS PER MINUTE Simulated Off-Gas Sample
(2.96 1 0.16) E-5 2.78 E-5 Agreement 303 (1.64 1 0.10) E-5 1.46 E-5 Agreement 346 (2.79 i 0.16) E-6 2.82 E-6 Agreement 356 (4.88 1 0.32) E-5 5.43 E-5 Agreement 779 (1.34 1 0.08) E-6 1.32 E-6 Agreement 964 (1.50 1 0.09) E-6 1.47 E-6 Agreement 14C8 (2.13 1 0.16) E-6 2.09 E-6 Agreement
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TABLE 1 PILGRIM VERIFICATION - TEST RESULTS SAMPLE ISOTOPE NRC VALUE LICENSEE VALUE COMPARIS0N RESULTS IN MICR0 CURIES PER MILLILITER Filtrate Tank 1550 hrs.
8/1/78 H-3 (1.16 1 0.01)E-2 (7.28 1 0.73)E-3 Disagreement Gross Beta (5.6 1 0.2)E-6 (1.1 1 0.1)E-5 Possible Agreement Gross ?,1pha (1.3 1 0.8)E-9
<1 E-8 No Compariso.-
Sr-89 (4.4 1 0.2)E-6 (4.7 1 0.1)E-6 Agreement Sr-90 (2.5 1 0.4)E-8 (2.2 1 0.4)E-8 Agreement
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Attachment 1 Criteria for comoaring 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 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 Possible Possible Resolution Aoreement 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
"A" criteria are applied to the following analyses:
Gamma Spectrometry where principal gamna 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.
895r and 90Sr Determinations.
Gross Beta where samples are counted on the same date using the same reference nuclide.
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