IR 05000333/1978020
| ML20062D893 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 10/19/1978 |
| From: | Rottan J, Stohr J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20062D891 | List: |
| References | |
| 50-333-78-20, NUDOCS 7812010036 | |
| Download: ML20062D893 (8) | |
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U.S. NUCLEAR REGULATORY COMMISSION 0FFICE OF INSPECTION AND ENFORCEMENT
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Region I Report No.
50-333/78-20 Docket No.
50-333 License No.
DPR-59 Priority Category C
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Licensee:
Power Authcrity of the State of New York
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I 10 Columbus Circle New York. New York 10019
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Facility Name:
James A. FitzPatrick Nuclear Power Plant Inspection at:
Scriba, New York
' spection conducted: Se tember 27-29, 1978
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Enspectors: de 4e W/1h
/C //f'/ 70 J. J. Kottan, Radiation Specialist
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D. M. Gloski, Co-op date signed date signed Approved by:
/0[lT[72 J. P.js1/ohr; Chief, Environmental and Special date signed
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Projects Section, FF&MS Branch (
isoection Summary:
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Inspection on September 27-29, 1978 (Recort No. 50-333/78-20)
Areas Inspected: Routine, unannounced inspection of the licensee's chemical
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and radiochemical measurements program using NRC:I Mobile Radiological Measurements Laboratory and laboratory assistance provided by DOE Radiological and Environ-mental Services Laboratory. Areas reviewed included: program for quality control of analytical measurements, audit results, perfomance on radiological analyses of split actual effluent samples, and effluent control records and procedures. The inspection involved 20 inspector-hours onsite by one NRC regional based inspector.
Results: Of the four areas inspected, no items of noncompliance were identified.
7812010036 Region I Form 12 (Rev. April 77)
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DETAILS 1.
Persons Contacted Principal Licensee Employees
- J. Leonard, Resident Manager
- R. Pasternak, Superintendent of Power
- R. Burns, Radiological and Environmental Services Superintendent
- E. Mulcahey, Radiation Protection and Radiochemistry Supervisor
- B. Gorman, Environmental Supervisor
- R. Shropshire, New York Office Senior Radiological Engineer M. McMahon, Radiation and Environmental Technician M. Cosgrove, Site QA Engineer The inspector also interviewed other licensee employees including members of the chemistry and health physics staffs.
- denotes those present at the exit interview.
2.
Licensee Action on Previous Insoection Findings (Closed) Unresolved item (77-28-01): Computer procedure for handling gaseous effluent data. The inspector noted the licensee performs daily
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calculations to determine compliance with gaseous effluent release
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limits and includes the gaseous effluent release data from the Nine I
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Mile Point Nuclear Station in these calculations. This item is closed.
I (Closed) Unresolved item (77-28-02): Tritium measurement disagreement.
The inspector noted that the results of a sample split during a previous inspection (Inspection Report 50-333/78-11) indicated the tritium meas-urement on a Waste Collector Tank sample was in agreement. This item is closed.
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(Closed) Unresolved item (78-11-01): Cs-134 measurement in liquid samples.
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The inspector determined, based on measurements made during this inspec-tion, that the licensee was able to measure Cs-134 in liquid samples.
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Refer to Table I.
This item is closed.
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3.
Laboratory OC Program The inspector reviewed the licensee's program for the quality control of analytical measurements and noted the licensee had made modifications to his QC program. The inspector noted the modification included a
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documented preplanned radiological and nonradiological program for split, spiked, duplicate, and interlaboratory QC sample analyses. The modification to the QC program was approved by the licensee's review committee in May 1978. The inspector reviewed the licensee's QC data since this modification had been approved. The inspector noted the
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licensee was following the QC sample analysis schedule, and the various sample analyses were reviewed and acknowledged by the Radiation Protection and Radiochemistry Supervisor. The inspector noted that with the exception of the modification the licensee's QC program remains the same as documented in Inspection Report 50-333/77-28 with the QC program being detailed in Section II of Volume III of the site Chemistry and Radiation Protection Manual.
The inspector noted the licensee had no regulatary requirements in the area of laboratory QC and had no further questions in this area. No items of noncompliance were identified.
4.
Audit Results l
The inspector determined that the licensee's effluent monitoring program was on the corporate QA audit list. The inspector reviewed PASNY i
Standard Audit Nos. 263 dated June 13, 1978; 267 dated July 7,1978; and 273 dated August 4,1978 which were the last audits performed in this area. The inspector had no further questions in this area. No items of noncompliance were identified.
5.
Confinnatory 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 l
Measurements Laboratory. Joint analyses of actual effluent samples
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detennine the licensee's capability to measure radioactivity in effluent j
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 requiring 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 docu-mented in a subsequent inspection report.
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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.
(SeeAttachment1) The results of the comparisons are listed in Table I.
6.
Records and Procedures The inspector reviewed the following records and procedures:
a.
Gaseous effluent analysis data (January 1978 to September 1978).
b.
Liquid affluent analysis data (January 1977 to September 1978).
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Counter calibration and check records (January 1978 to August 1978).
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Laboratory QC sample analyses (May 1978 to September 1978).
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The following procedures:
(1) PSP-5, Radioactive Airborne Sampling, Analysis and Equipment Calibration.
(2) PSP-4, Waste Water Sampling and analysis.
(3) CAP-9, Chloride Ion Analysis in Water.
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Exit Interview
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The inspector met with licensee representatives (denoted in paragraph 1)
at the conclusion of the inspection on September 29, 1978. The inspector sumarized the purpose and scope of the inspection and the l
inspection findings.
l The licensee agreed to perform the analyses listed in paragraph 5 and report the results to the NR _.
TABLE 1
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FITZPATRICK VERIFICATION - TEST RESULTS
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SAMPLE ISOTOPE NRC VALUE LICENSEE VALUE COMPARISON RESULT 5 IN MICR0 CURIES PER MILLILITER Rad Waste Cs-134 (4.2119 50)E-6 (5.1819 77)E-6 Agreement 1035
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9/28/78 Cs-137 (7.7719 39)E-6 (7.03fp.80)E-6 Agreement Mn-54 (1.2719 04)E-5 (1.271p.10)E-5 Agreement Co-60 (2.0819 08)E-5 (2.00lp.15)E-5 Agreement Reactor Cs-134 (3.0819 09)E-3 (3.09fp.05)E-3 Agreement Water
i 1020 Cs-137 (3.4519 06)E-3 (3.36fp.05)E-3 Agreement l
9/28/78 I-131 (2.2419 04)E-3 (2.2019 03)E-3 Agreement
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Co-60 (1.lRip.02)E-2 (1.1419 01)E-2 Agreement Mn-54 (1.5919 01)E-2 (1.57fp.01)E-2 Agreement
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Zn-65 (2.1219 09)E-3 (1.7519 06)E-3 Agreement
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Co-58 (9.9419 08)E-3 (9.8819 07)E-3 Agreement
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TABLE 1
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FITZPATRICK VERIFICATION - TEST RESULTS
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SAMPLE IS0 TOPE NRC VALUE LICENSEE VALUE -
COMPARISON RESULTS IN TOTAL MICR0 CURIES
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Turbine Bldg.
Charcoal I-131 (5.7810.40)E-3 (5.9510.21)E-3 Agreement Cartridge 1648
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9/26/78 Turbine Bldg.
Particulate I-1 31 (2.6610.17)E-3 (3.3410.24)E-3 Agreement Filter 1200 Co-60 (1.3710.10)E-3 (1.3710.14)E-3 Agreement 9/11/78 Mri-54 (3.8110.33)E-4 (4.0210.66)E-4 Agreement Ba-140 (1.1310.25)E-3 (1.3910.29)E-3 Agreement
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TABLE 1
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FITZPATRICK VERIFICATION - TEST RESULTS
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SAMPLE ENERGY (kev)
NRC VALUE LICENSEE VALUE COMPARISON RESULTS IN GAP 9tA PER MINUTE NRC Simulated Off Gas Sample *
( 3.1410.17)E+5 (1.96)E+5 Possible Agreem' nt e
303 (1.7410.11)E+5 (1.41)E+5 Agreenient 346 (2.8910.17)E+6 (2.47)E+6 Agreenient 356 (5.1910.34)E+5 (3.99)E+5 Agreenient 779 (1.3910.10)E+6 (1.09)E+6 Agreenient 964 (1. 5610.10)E+6 (1.25)E+6 Agreenient 1408 (2.2110.17)E+6 (1.79)E46 Agreement At the tirae o'f the insp' ctio'n the licensee's facility was shut down for refueling, and,
e therefore.no offgas sample was available. An NRC simulated offgas sample was given to the licensee. The res'ults for the various photo peaks in the spectrum were compared in gansnas per minute emitted from the sample.
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Attachment 1 Criteria for Comoaring Analytical Measurement's
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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 the:s 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.
r LICENSEE VALUE RATIO = NRC' REFERENCE VALUE 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 - ?.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 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 nuclide.
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