IR 05000424/1986032
| ML20205N925 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 05/06/1986 |
| From: | Gloersen W, Stoddart P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20205N923 | List: |
| References | |
| 50-424-86-32, NUDOCS 8605210013 | |
| Download: ML20205N925 (6) | |
Text
' pei ten, UNITED STATES
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. NUCLEAR REGULATORY COMMISSION O\\s p7,^
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101 MARIETTA STREET, N.W.
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ATL ANTA, GEORGI A 30323
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MAY 0 9 %6 Report No.: 50-424/86-32 Licensee: Georgia Power Company P. O. Box 4545 Atlanta, GA 30302 Docket No.: 50-424 Construction Permit No.: CPPR-108
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Facility Name: Vogtle 1 Inspection C nduc ed: April 15-18,1986 Inspector:V
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W. B.
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Date Signed Approved by: (f f
(M P. G. StodFart, Acting Section Chief Date Signed Radiological Effluents and Chemistry Section Division of Radiation Safety and Safeguards SUMMARY Scope: This special, announced inspection involved an onsite review in the areas of liquid and gaseous radioactive waste management, quality assurance and confirmatory measurements for in-plant radiochemical analyses and Vogtle Readiness Review Program Module 9B - Chemistry.
Results:
No violations or deviations were. identified.
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REPORT DETAILS 1.
Persons Contacted Licensee Employees
- H. P. Walker, Manager, Unit Operations
- C. E. Belflower, Q. A. Site Manager (OPS)
- C. Hayes, Quality Assurance
- W. C. Gabbard, Regulatory Specialist
- G. A. McCauley, Project Compliance Coordinator
- J. H. Draggs, Readiness Review, Q. A.
- E. D. Groover, QA Site Manager, (Construction)
- D. L. Edenfield, Readiness Review, Disc, Manager
- J. F. D' Amico, Superintendent, Regulatory Compliance
- D. F. Hallman, Chemistry Superintendent
- M. D. Llewellyn, Chemistry Support Consultant
- C. A. Moore, Chemistry Program Development Consultant R. A. Leineke, Chemistry Support Consultant R. Hand, Plant Chemist P. Jackson, Plant Engineer NRC Resident Inspectors
- H. Livermore, SRI-C
- J. Rogge, SRI-0
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on April 18, 1986, with those persons indicated in Paragraph 1.
The inspector described the areas inspected and discussed in detail the inspection findings.
Two inspector followup items (IFI), were identified in the areas of radiochemical analysis procedures (Paragraph 3.b) and effluent management and reporting (Paragraph 7).
The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspector.
3.
Procedures (84523, 84524, 84525)
a.
The inspector reviewed selected portions of the following approved procedures were related to radioactive effluent management:
30000C, Organization of the Chemistry Department, Rev.
2, February 23, 1986.
30035-C, Laboratory Standing Orders, Rev. 3, December 13, 1985.
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'3 31045-C, Chemistry Logkeeping, Filing, and Record Storage, Rev. 2,
' March 6, 1986.
33000-C, Preparation of Liquid Samples for Radiocnemical Analysis,
Rev. O, December 31, 1985.
33005-C, Determination of Gross Beta-Gamma Radioactivity, Rev.1,
March 16, 1986.
330010-C, Determination of Gross Alpha Radioactivity, Rev. 2,.
March 16, 1986.
37040-C, Sample Handling, Storage, and Shipment, Rev. 0, July 3,
1985.
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39004-C, Data Handling and Record Storage, Rev. 2, January 17, 1986.
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The inspector discussed Procedure 33000-C, Preparation of Liquid -
b.
Samples for Radiochemical Analysis, and noted that Step 6.5 described the technique of concentrating a liquid sample by evaporating a known
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volume to a pre-determined value as one way to meet. lower limit of
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detection (LLD) requirements.
The inspector noted that the LLD is a-function of counting efficiency, sample size, and elapsed time between
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sample collection and time _of counting-(for plant effluents) and is not affected by concentration of liquid samples.
The licensee agreed to revise the procedure appropriately.
This item was identified as an inspector followup' item and will be reviewed during future inspections (50-424/86-32-01),
The inspector noted that the majority of the procedures related' to c.
effluent management, laboratory quality assurance, and instrumentation maintenance and calibration had either not been approved or had ' not
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been written at the time of this inspection.
The licensee indicated that these procedures would be written and approved by approximately June 1986, and provided the inspector a list of procedures with
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projected completion dates.
No violations or deviations were identified.
j 4.
Audits (84523, 84524, 84525)
The inspector reviewed the special quality assurance audit of Operations Readiness Review modules - 9A and. 9B - OP26-86/01, dated February 7,1986.
This special QA audit addressed the inclusion of -commitments from appropriate ~ source documer.ts, incorporation of appropriate commitments from other modules when transfers were prescribed, preparation and implementation
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of module verification reviews-in accordance with pre-established review plans, verification checklist completion in accordance with Readiness Review
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program procedures, and the review of procedures for commitment inclusion.
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The inspector noted that the licensee had taken adequate actions to address the chemistry module Readiness Review concerns.
No violations or deviations were identified.
5.
Effluent Monitoring Instrumentation and Laboratory Facilities (84523, 84524, and 84525)
a.
The inspector and licensee representatives examined one radiological effluent air monitor (Air Ejector and Steam Packing Monitor - RE-12839 A, B, and C) which was physically installed but had no electrical power supply installed.
The inspector discussed with the licensee the installation status of the radiological effluent monitors.
According to the licensee, the various portions of the radiological effluent monitoring system were in the following approximate state of-completeness on April 9, 1986:
Detector Installation - 56% complete Data Process Module Installation - 63% complete Piping installed to monitor - 68% complete Electrical Installed to Monitor - 8% complete Monitors Complete - 6%
The licensee indicated that construction acceptance testing (CAT)
should be completed by the end of May 1986 and projected the
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preoperational testing to be completed approximately September L86.
The inspector noted that the licensee. had a-tracking system '.nat indicated the status of the plant's various effluent monitors.
b.
The inspector and licensee representatives toured the radiological counting laboratory to observe the construction progress and to examine the equipment that will be used for radiological counting activities.
The radiochemistry counting room had approximately 600 square feet of space not including the adjoining computer room.
At the time of this inspection, the counting room was still under the control of the construction engineers.
Ultimately, the radiochemistry counting room will be managed and operated by the Chemistry Department.
Radio-analytical instrumentation will include three alpha / beta proportional counters, one liquid scintillation counter (Beckman Model 3801), and four intrinsic germanium detectors.
Data processing and management will be accomplished by a primary Microvax II central processing unit.
Additionally, the licensee will have a backup Microvax II. The health physics counting room will consist of two intrinsic germanium detectors while the training center will have one' intrinsic germanium detector.
Nuclear Data Model 76 terminals will be used to display the data. The licensee indicated that-the radiochemistry counting room would be functional around September 1986.
c.
Additionally, the inspector and a licensee representative examined the primary and backup meteorological towers and associated sensing equip-mcat.
The inspector also observed the local readouts located at the
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meteorological tower site.
There were strip chart readouts for windspeed and wind direction and, in addition, a magnetic tape data storage unit which was not operational.
The licensee has not made definite plans to replace the magnetic tape system, but some consider-ation has been given to purchase a portable computer to store the data so that the data could be transmitted electronically to Pickard, Lowe, and Garrick for data collection and reduction.
No violations or deviations were identified.
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6.
Post Accident Sampling System (84523, 84524)
The inspector and licensee representatives toured the post accident sampling system (PASS) facilities.
The licensee was installing a Sentry Model B system. The licensee was beginning the construction acceptance test and had projected that the testing would be complete at the end of May 1986.
The preoperational test (to coincide with the hot functional test) was scheduled for August 1986. The Chemistry Department was scheduled to accept responsi-bility for the system around October 1986.
Ultimately, the PASS will have the capability to provide "on-line" gamma analysis of both liquid and gaseous samples and to provide remote readouts in the Technical Support Center (TSC).
For containment air and offgas samples, readout terminals for percent hydrogen percent oxygen, and isotopic analysis will be available in the TSC.
For reactor coolant samples, readout terminals for pH, dissolved oxygen, boron, fluoride, and isotopic analysis would be available in the TSC.
No violations or deviations were identified.
7.
Readiness Review Module 9B (Chemistry) Update In addition to the normal inspection activities conducted during April 15 - 18,1986, the inspector was also responsible for the evaluation of selected portions of Vogtle's Readiness Review Program Module 9B-Chemistry.
The inspector reviewed selected comitments that were detailed in the Implementation Matrix (Section 3.5).
The inspector noted that there were a total of 444 commitments contained in the Implementation Matrix.
The inspector reviewed the areas in the matrix that were concerned with radiological effluent management.
As noted in Paragraph 3.C, many of the procedures that were related to radiological effluent management had either not been approved or written. The inspector noted that the Regulatory
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Compliance Department was scheduled to perform a comprehensive audit of i
Readiness Review Module 9B around June 1986.
The inspector was informed
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that the audit would consist mainly of a procedure review to verify that the procedures are in place and approved.
The inspector noted that each Readiness Review Imp (lementation Matrix Number (RRIMN) had a commitment i
tracking data base CTDB) number assignment.
There were fcur status conditions for CTDB numbers:
(1) open (commitment identified);
(2) open-1 (draft procedure prepared);
(3) closed (Chemistry Department Closure); and (4) completed (Regulatory Compliance Closure).
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The inspector had noted a concern in RRIMN. 744.21, Regulatory Guide 1.21 Reporting Commitments-Sensitivity:
for some radionuclides, lower detection limits (LLD)' than those given may be.readily achievable and when measurements below the stated sensitivity limits are attained, the results should be recorded and reported.
The inspector questioned whether or not the licensee's effluent management reporting system reported zero for a particular reporting period when a particular nuclide.for that reporting period was below the stated sensitivity limits of the gamma spectroscopy system.
The inspector and the licensee discussed how "zero" should not be used in the semiannual. effluent release reports. An acceptable alternative to reporting "zero" was discussed, specifically to provide a range of gamma.
spectroscopy system specific lower limit of detection (LLD) values for a particular geometry and nuclide. The licensee agreed to evaluate this potential reporting problem. This item was identified as an IFI and will be reviewed during future inspections (50-424/86-32-02).
No violations or deviations were identified.
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