IR 05000369/1980017
| ML19331C517 | |
| Person / Time | |
|---|---|
| Site: | McGuire  |
| Issue date: | 07/16/1980 |
| From: | Montgomery D, Stohr J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19331C514 | List: |
| References | |
| 50-369-80-17, NUDOCS 8008180612 | |
| Download: ML19331C517 (7) | |
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UNITEO STATES
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NUCLEAR REGULATORY COMMISSION
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ATLANTA, GEORGIA 30303
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Report Nos. 369/ 80-17 Licensce: Duke Power Company 422 South Church Street Charlotte, NC 28242 Facility Name: McGuire Unit 1 Docket No. 50-369 License No. CPPR-83 Inspection at McGuire Site, Cornelius, N.C.
Inspector:
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D.M. Montgomery)
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J./ Philip Stop'r Date Signed SUMMARY Inspection on June 24-27, 1980 Areas Inspected.
This routine, unannounced inspection involved 22 inspector-hours on site in the areas of quality control and confirmatory measurements including review of the laboratory quality control program, and review of chemical and radiochemical procedures and instrumentation.
Results Of the two areas inspected, no items of noncompliance or deviations were identified in two areas; no deviations were found.
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A DETAILS 1.
Persons Contacted Licensee Employees M.D. McIntosh, Station Manager
- T.J. Keane, Station Health Physicist R.P. '1ichael, Station Chemist
- W.M. Sample, Projects License Engineer
- D. Lampke, Jr. Engineer L. Kimray, Power Chemistry Supervisor D. Franks, QA Supervisor
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on June 27, 1980 with those persons indicated in Paragraph I above. A licensee representative agreed to perform tlc analyses requested in Paragraph 8 and report. the results to NRC:RII.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Jtems Unresolved items were not identified during this inspection.
5.
Laboratory Quality Control Program The inspector reviewed the licensee quality assurance program in chemistry and radiochemistry.
Proposed Technical Specification 6.8.1 states that written procedures shall be established, implemented and maintained for the Quality Assurance Program for effluent and environmental monitoring using the guidance in Regulatory Guide 4.15, December 1977.
The licensee QA program was reviewed to verify compliance with the following elements as specified in Regulatory Guide 4.15:
Organizational Structure and Responsibilities of Managerial and Operational a.
Personnel.
The Station Health Physicist has the overall responsibility for radin-logical measurements. The operation of the quality control program for radiological measurements on a day to day basis has been delegated to the Health Physics Supervisor-Support Function. The responsibility
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for the Chemistry Quality Control program rests with the Station themist. The operatit.,a of the chemistry quality control programs on a day-to-day basis has been delegated to the Radwaste Chemistry and Power Chemistry Coordinators in their respective areas of responsibility.
b.
Specification of Qualifications of Personnel The qualification requirements of staff members involved in radiological monitoring activities are given in McGuire Station position guides.
Detailed position guides for the supervisory positions include a description of duties and qualifications.
Position descriptions are also available for the various categories of health physics technicians.
c.
Operating Procedures and Instructions The inspector verified that operating procedures have been written and implemented for the effluent monitoring procedures. A review of the procedures is addressed in Paragraph 6.
d.
Records The inspector verified that there is a system for docurentation of activities performed in the mcnitoring program. This includes records to track samples through the collection, analysis, and reporting process.
Records of the calibration program, and specific quality control checks for laboratory instrumentation are required by the instrument operation aM calibration procedures.
e.
Quality Control in Sampling (Including packaging, shipping and storage of samples)
Procedures for the collection of samples have been written and approved; however, some procedures for sample collection which involve shipping and preservation have not been written. (See Paragraph 6).
f.
Quality Control in the Radioanalytical Laboratory
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The quality control program appears to meet the basic requirements set forth in Regulatory Guide 4.15.
The proposed interlaboratory crosscheck program for effluent monitoring is the EPA crosscheck program. The inspector noted that this program is not designed for an effluent monitoring program since the radioactivity levels in EPA samples are too low. A licensee representative indicated that a Duke crosscheck program between facilities may be substituted for the EPA program.
g.
Review, Analysis, and Reporting Data Provisicas have been made for review of radioanalytical results by supervisory personnel.
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h.
Audits Annual quality assurance surveillances in the Chemistry and Health Physics areas are to be carried out in accordance with procedure QA-500 of the Duke Power Company, Quality Assurance Program.
The annual surveillance includes checking of documents, records, work in progress, or plant conditions for the purpose of verifying that action has been or is being accomplished in accordance with applicable aspects of the quality assurance program and regulatory requirements.
In addition there are provisions for audits by the Corporate Quality Assurance Audit Division. These audits are to be performed in accordance with procedure QA-210, Departmental Audit Procedure.
6.
Procedures and Instructions a.
The inspecto..eviewed the following procedures and instructions and discussed the review with licensee representatives as detailed in 6b, 6t, and 6d.
(1) McGuire Nuclear Station Radiochemistry Manual, 3.7 Documentation and Transmittal of Chemical Data, 8-12-79 and 3.8, Control of Laboratory Instrumentation, Rev. 2, 9-14-79.
(2) CP/0/A/8100/05A, Chemistry Procedure for the Determination of Boron in Aqueous Boric Acid Solution, Manual Method,11-2-79.
(3) CP/0/A/8100/05, Chemistry Procedure for the Determination of Boron in A-ueous Boric Acid Solutions, 2-1-80.
(4) CP/0/A/8100/06, Chemistry Procedure for the Dete mination of Chloride in High Purity Water,11-6-79.
(5) CP/0/A/8100/06A, Chemistry Procedure for the Determination of Chloride in High Purity Water Al' rnate Method, 10-19-79.
(6) CP/0/A/8100/10, Chemistry Procedure for the Determination of Fluoride in High Purity Water, 10-25-79.
(7) CP/0/A/8100/10A, Chemistry Procedure for the Determination of Fluoride in High Purity Water Alternate Method, 8-27-79.
(8) CP/0/A/8100/10, Chemistry Procedure for the Determination of Fluoride in High Purity Water, 10-25-79.
(9) CP/0/A/8100/10A, Chemistry Procedure for the Determination of Fluoride in High Purity Water Alternate Method.
(10) CP/0/.B/8100/17, Chemistry Procedure for the Determination of Oxygen in High Purity Water, 6-13-80.
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(11) CP/0/A/8100/17A, Chemistry Procedure for the Determination of Dissolved Oxygen in High Purity Water Alternate Method, 10-25-79.
(12) CP/0/A/8200/01, Chemistry Procedure for Gross Gamma Analysis, 1-12-79.
(13) CP/0/A/8200/02, Chemistry Procedure for Gross Beta Analysis, 1-10-79.
(14) CP/0/A/8200/04, Chemistry Procedure for the Analysis of Tritium, 1-31-79.
(15) CP/0/B/8200/08, Chemistry Procedure for Determination of I-131 Dose Equivalent.
(16) CP/0/A/8200/05, Chemistry Procedure for Radioisotope Analysis, 11-13-79.
(17) PT/0/B/4600/08, Correlation of EMF's, 3-12-80.
(18) TP/1/A/2600/15, Ef fluent Radiation Monitor Test, 6-13-80.
(19) HP/0/B/1001/01, Start-up and Maintenance of Counting Room Equipment, Rev 0, 6-23-78.
(20) HP/0/B/1001/02, Sample Preparation for Counting room Equipment, Rev 0, 7-17-78.
(21) HP/0/B/1001/03, Calibration procedure for Ge(Li) Detectors, Rev 2, 12-18-79.
(22) HP/0/B/1001/04, Operating Procedure for the Nuclear Data 6600 Series Model No. 6620 Multichannel Analyzer, Rev 2, 12-12-79.
(23) HP/0/B/1001/05, Operation of Automatic and Manual GM-Beta Gamma Counting Systems, Rev 0,5-22-78.
(24) HP/0/B/1001/06, Operation and Calibration of the TASC-12 Phoswich Alpha-Beta Counter, Rev 1, 1-15-79.
(25) HP/0/B/1001/07, Operation of the Manual Gamma Well Counting System, Rev 0, 7-17-78.
(26) HP/0/B/1001/08, Operation and Calibration of the PRIAS Automatic Liquid scintillation counter, Rev 0, 12-14-79.
(27) HP/0/B/1001/09, Counting Room Quality Assurance Procedure, Rev. 1, 7-22-79.
(28) HP/0/B/1004/05, Gaseous Radioactive Waste Sampling, Preparation and Analysis, Rev 0, 9-13-78.
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The inspector noted to licensee representatives that there were no written approved procedures for the following: Gross Alpha Analysis, E Determination, and Miscellaneous Liquid Waste Sampling. In addition the gas sampling procedure was not current and applicable to the gas sampling system that will be utilized. The inspector advised licensee representatives that completion and revision of the procedures will',be considered an open item and would be reviewed during the next inspection.
(309/80-17-01).
c.
The inspector noted that there were no procedures for Sr-89, Sr-90, P-32, and Fe-55 analyses in liquid effluents and Sr-89 and Sr-90 in gaseous effluents. Licensee representatives stated that these analyses would be performed by contract, and procedures for analysis, shipping and preservation would be written.
The inspector stated that any contractor should provide a quality assurance program consistent with USNRC Regulatory Guide 4.15 and that this would be reviewed during the next inspection. (369/80-17-02).
d.
The inspector verified that the prccedures for operation of the various radiation detection instruments for effluent measurements included QC checks; however, the procedures did not include acceptance criteria and corrective action, if neccessary.
In addition, the following items were not addressed in the following operating procedures:
HP/0/B/1001/05 - no provision was made for plateau determinations after repair or maintenance; and HP/0/B/1001/03-no efficiency calibra-tion frequency was stated. A licensee representative agreed to address the above items and make the necessary procedure revisions. (369/80-17-03).
e.
The inspector noted that Procedure, HP/0/B/1001/08 for operation of the liquid scintillation counters has no provision for monitoring the amount of quenching in sample.
This could result in underestimation of activity if quenching were significant. A licensee representative stated that the problem of quenching would be addressed in the procedure.
(369/80-17-04).
7.
Record Review The following records and logs were reviewed:
(a) Automatic Liquid Scintillation Calibration and Daily Checks, 9-37-79 to 6-25-80.
(b) Manual Liquid Scintillation Calibration and Daily Checks, 9-3-79 to 6-25-80.
(c) CM Counter Efficiency Calibration,1-80 to 5-1-80.
(d) NaI Counter Daily Checks, 11-30-79 to 5-1-80.
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(e) GeLi Daily Performance Checks, 4-3-80 to 6-20-80.
(f) GeLi Calibration Records, February,1980.
(g) MDA Calculation for GeLi Counters, June,1980.
j The inspector noted from the GeLi calibration records and MDA calculations that the required LLD's for effluent analysis by gamma ray spectroscopy can be met. The inspector had no further questions regarding the record review.
I 8.
Capability Test The inspector informed a licensee representative that spiked radioactive samples would be supplied to verify their capability to perform radiological analyses.
The following samples will be sent:
simulated liquid waste, simulated charcoal cartidge for I-131, and simulated stack sample particu-late filter. Analyses will include H-3, Sr-89, Sr-90, and gamma ray emitters.
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