IR 05000317/1979002
| ML19261C801 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 02/02/1979 |
| From: | Todd Jackson, Kotton J, Stohr J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19261C796 | List: |
| References | |
| 50-317-79-02, 50-317-79-2, 50-318-79-02, 50-318-79-2, NUDOCS 7904020221 | |
| Download: ML19261C801 (8) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT-Region I 50-317/79-02 Report No. 50-318/79-02 50-317 Docket No. 50-318 DPR-53 C
License No. OPR-69 Priority Category C
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Licensee:
Baltimore Gas and Electric Company P. O. Box 1475 Baltimore, Maryland 21203 Facility Name:
Calvert Cliffs Nuclear Power Plant, Units 1 and 2 Inspection at:
Lusby, Maryland Inspection conducted:
anuary 16-19, 1979 Inspectors: 4T (P (4h 1 79 J. J. Kot! tap, Radiation Specialist Idake signed m~
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v vT. J. Jackson, Radiation Specialist - Intern patt/ signed date sinned Approved by:
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stohr7 Chief, Environmental and date sign 6d ecial Projects Section, FF&MS Branch Insoection Summary:
Inspection on January 16-19, 1979 (Combined Report Nos. 50-317/79-02; 50-318/79-02)
Areas Inspected:
Routine, unannounced inspection of the licensee's chemical and radiochemical measurements program using NRC:I Mobile Radiological Measurements Laboratory and laboratory assistance provided by DOE Radiological and Fnviron-mental Services Laboratory. Areas reviewed included:
program for qua'.ity control of analytical measurements; audit results; performance on radiological analyses of split actual effluent samples; and_ effluent control records and procedures. The inspection involved 48 inspector-hours onsite by two NRC regional based inspectors.
Results:
Of the four areas inspected, one item of noncompliance was identified in one area (Infraction - failure to follow procedure, paragraph 6).
7 9 04 0 2 0 2a!
Region I Form 12 (Rev. April 77)
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s DETAILS 1.
Persons Contacted Principal Licensee Employees
- L. B. Russell, Chief Engineer
- A. J. Kaupa, Radiation Safety and Chemistry Engineer
- J. Carlson, Radiation Safety and Chemistry Foreman
- R. F. Eherts, Performance Engineer
- P. T. Crimgan, Performance 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 Inspection Findings (0 pen) Infraction (50-317/78-13-01, 50-318/78-13-01):
Failure to follow procedures:
liquid waste tanks sampling, gaseous effluent totals, implementation of chemistry QC program.
The inspector noted the licensee had not calculated his gaseous effluent totals as required and, therefore, this was a recurrent item of noncompliance.
(See paragraph 6.)
(Closed) Unresolved Item (50-317/77-05-01, 50-318/77-04-01):
Iodine Sampling efficiency. The inspector noted the licensee has modified his effluent sampling for iodine such that the flow rate through the charcoal cartridge was approximately one CFM.
This item is closed.
(Closed) Inspector Follow Item (50-317/77-05-02, 50-318/77-04-02):
Gamma Procedure Lines used for analysis.
The inspector noted that all measurements were in agreement or possible agreement for this inspection, and the licensee was using the accepted spectral lines for identifying and quantifying radionuclides.
This item is close.
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3.
Laboratory OC Program The inspector reviewed the licensee's program for the quality control of analytical measurements.
The inspector noted the licensee's procedure RCP-103 Rad-Chem QC, covers quality control for both reactor coolant chemistry analyses and radiological analyses of effluent samples. The licensee's QC program includes monthly verification of calibration curves, split sample analyses, and recommended periodic monthly inspections. The inspector dis-cussed laboratory QC with the licensee. The inspector noted the licensee has no regulatory requirements in the area of laboratory QC, and, therefore, the inspector had no further questions in this area. No items of noncompliance were identified.
4.
Audit Results The inspector determined that the licensee's effluent monitoring and chemistry program were on the site QA audit list. The inspector reviewed the following audits:
- 3-19-78 dated June 6-9, 1978;
- 3-36-78 dated October 30 to November 1r,1978; and #18-23-78 dated July 11-14, 1978.
The inspector had no further questions in this area. No items of noncompliance were identified.
5.
Confirmatory Measurements During the inspection, actual liquid and gaseous effluent samples were split between the licensee and NRC:I for the purpose of inter-comparison. 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 radioactivity 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 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 documented in a subsequent inspection repor.
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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.
(See Attachment 1)
The results of the comparison are listed in Table I.
6.
Records and Procedures The inspector reviewed the following records and procedures:
a.
12 month release rate calculation sheet (January 1978 to January 1979)
b.
weekly gaseous effluent reports (January 1978 to January 1979)
c.
counter background and standard checks d.
the following procedures:
(1) RCP l-206, Liquid Waste Releases Specifications and Curveillance (2)
RCP l-207, Gaseous Waste Releases Specifications and Surveillance (3) RCP l-218, Unmonitored Discharge Surveillance Program (4) RCP l-1006, Radiochemistry Analysis Determination of Strontium Activity (5) RCP l-103, Rad-Chem QC (6)
RCP l-906, Determination of Chloride (7)
RCP l-907, Determination of Fluoride The inspector noted that in Inspection Report 50-317/78-13 and 50-318/78-08 an item of noncompliance was identified in which the licensee failed to follow procedures RCP l-206 with regard to sampling location, RCP l-103 with respect to calibration curves and duplicate samples, and RCP l-207 with respect to calculating the twelve month release rate. The licensee's corrective action
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with regard to procedures RCP l-206 and RCP l-103 was in accordance with the licensee letter dated May 26, 1978 to NRC:I. The inspector noted however that the 12 month release rate calculation sheet was not completed for the months of November and December 1978.
The inspector stated that this was a recurrent item of noncom-pliance.
(50-317/79-02-01,50-318/79-02-01) The licensee brought the 12 month release rate calculation sheet up to date prior to the inspector leaving the site.
7.
Exit Interview The inspector met with the licensee representatives (denoted in Paragraph 1) at the conclusion of the inspection on January 19, 1979. The inspector summarized the purpose and scope of the in-spection and the inspection findings.
The licensee agreed to perform the analyses listed in Paragraph 5 and report the results to the NR.
TABLE 1
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CALVERT CLIFFS 1 & 2 VERIFICATION TEST RLSULTS RESULTS IN MICR0 CURIES PER MILLILITER Sample Isotope NRC Value Licensee Value Comparison
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Unit 2 Main Vent I-131 (2.1710.02) E-10 (2.76 1 0.02) E-10 Possible Agreement Charcoal Cartridge 0800 hrs.
1/15/79 Unit 1 Main Vent I-131 (4.20 1 0.08) E-ll (5.21 1 0.11) E-ll Agreement Charcoal Cartridge 0800 hrs.
1/15/79 Liquid Radwaste I-131 (3.41 1 0.50) E-6 (4.01 1 0.60) E-6 Agreement 1130 hrs.
1/17/79 Cr-51 (7.13 1 0.46) E-5 (7.11 1 0.54) E-5 Agreement Zr-95 (1.54 1 0.14) E-5 (1.29 1 0.09) E-5 Agreement Co-58 (1.30 1 0.02) E-4 (1.22 1 0.02) E-4 Agreement Mn-54 (2.77 1 0.32) E-6 (2.05 1 0.42) E-6 Agreement Co-60 (1.54 1 0.32) E-5 (1.46 1 0.15) E-5 Agreement Ru-103 (5.31 1 0.64) E-6 (6.68 1 0.75) E-6 Agreement
Sample Isotope NRC Value Licensee Value Comparison Reactor Coolant Co-58 (3.78 1 0.02) E-3 (4.5 + 0.1) E-3 Crud Filter
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Agreement
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0915 hrs.
Co-60 (1.01 + 0.08) E-4 (1.45 + 0.08) E-4 Agreement 1/18/79
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Hn-54 (1.30 1 0.05) E-4 (1.42 1 0.11) E-4 Agreement Cr-51 (9.48 1 0.40) E-4 (1.44 1 0.07) E-3 Possible Agreement I-131 (9.99 1 0.49) E-5 (1.32 1 0.09) E-4 Agreement Sr-91 (9.41 1 0.33) E-4 (9.69 1 0.84) E-4 Agreement I-133 (4.42 1 0.13) E-4 (6.94 1 0.19) E-4 Possible Agreement I-135 (5.92 1 0.60) E-4 (6.54 1 0.28) E-4 Agreement Zr-95 (4.33 1 0.43) E-4 (5.17 1 0.lv) E-4 Agreement
- 11 Waste Gas Xe-133 (1.5810.01) E-2 (2.1 1 0.1) E-2 Possible Agreement Decay Tank 0945 hrs.
Xe-131m (7.43 i 1.11) E-4 (7.95 1 0.48) E-4 Agreement 1/18/79 Unit 2 Reactor I-131 (1.32 1 0.04) E-2 (1.3310.03) E-2 Agreement Coolant 0915 hrs.
I-132 (5.18 1 0.10) E-2 (5.52 1 0.12) E-2 Agreement 1/18/79
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I-133 (5.95 1 0.07) E-2 (7.27 1 0.09) E-2 Agreement I-134 (7.31 1 0.22) E-2 (7.63 1 0.14) E-2 Agreement I-135 (6.40 1 0.45) E-2 (6.74 1 0.15) E-2 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 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
"A" criteria are applied to the following analyses:
Ga n._ 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.