IR 05000369/1988017
| ML20151K191 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 07/15/1988 |
| From: | Marston R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20151K173 | List: |
| References | |
| 50-369-88-17, 50-370-88-17, NUDOCS 8808030141 | |
| Download: ML20151K191 (7) | |
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JUL 2 0 W Report Nos.:
50-369/88-17 and 50-370/88-17 Licensee: Duke Power Company 422 South Church Street Charlotte, NC 28242 Docket Nos.:
50-369 and 50-370 License Nos.: NPF-9 and NPF-17 Facility Name: McGuire 1 and 2 Inspection Conducted: June 20-24, 1988 JG.I.(t 7//(//J Inspe or:
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rston Dat'e Sisned
. M ) (c. I d a 7/Mff Approved by:[. B./Kahle, Section Chief DaYe Signed DivMion of Radiation Safety and Safeguards SUMMARY Scope:
This routine, unannounced inspection was in the areas of liquid and gaseous effluents.
Results:
In the areas inspected, no violations or deviations were identified.
8808030141 880720 DR ADOCK 0500
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w REPORT DETAILS 1.
Persons Contacted Licensee' Employees
- N. Atherton, Production Specialist, Compliance W.Byrum,SupervisingScientist(HP)pervisor D. Britton, Health Physics General Su W. Carter, Supervising Scientist (Dosimetry)
- K. Connell, Design Engineer, Mechanical
- D. Ethington,' Nuclear Production Engineer, Compliance
- J. Foster, Station Health Physicist
- R.:Futrell, Nuclear Safety Assurance J. Gabbert, Chemistry Supervisor
- G. Gilbert, Assistant to Station Manager L. Haynes, Associate Scientist (HP)
T. Henrickson, Production Specialist, Chemistry
- L. Honeycutt, Mechanical Maintenance P. Huntley, HP General Supervisor
- S. LeRoy, Production Specialist, Licensing
- T. McConnell, Station Manager
- D. Motes, Mechanical Maintenance Support Engineer
- R. Rider, Mechanical Maintenance P. Roberson, Nuclear Production Engineer G. Singletary, I&E Support Engineer
- A. Sipe, Chairman, McGuire Safety Review Group
- J. Snyder, Performance Engineer P. Wingo, Technical Systems Manager, Health Sciences Other licensee employees contacted during this inspection included engineers, operators, security force members, technicians, and administrative personnel.
NRC Resident Inspectors
- W. Orders, SRI
- R. Croteau, R1
- D. Nelson, R1
- Attended exit interview 2.
Audits (80721,84723,84724,84725)
Technical Specification (TS) 6.5.2.9 requires that audits of unit activities shall be performed under the cognizance of the Nuclear Safety Review Board (NSRB) encompassing conformance of unit operation to provisions contained within the TSs and applicable license conditions at least once per 12 months; the Radiological Environmental Monitoring
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Program and the results thereof at least once per 12 months; the Offsite Dose Calculation Manual (00CM) and implementing procedures at least once per 24 months; and the performance of activities required by the Quality Assurance Program for effluent and environmental monitoring at least once per 12 months.
The-inspector reviewed the following audit reports:
Departmental Audit PS-87-01 (PS), Production Support Department--
Activities, August 12, 1987, conducted June 8 - July 17, 1987; MC-88-4, Chemistry Waste Solidification, March 3,1988, conducted January 7 - February 4 1988; and MC-88-07, Station Testing, HP Testing, March 21, 1988, conducted
February 5-24, 1988.
The inspector reviewed the radwaste program, the environmental program, the counting room and quality control activities, the 00CM, and the Measuring and Test Equipment.
The inspector noted that deficient and unresolved items were tracked and appeared to be corrected in a timely manner.
Violations or deviations were not identified in the review of this program area.
3.
Procedures (80721, 84723, 84724, 84725)
TS 6.8 requires that written procedures shall be established, implemented, and maintained covering:
The applicable procedures recommended in Appendix A of Regulatory
Guide 1.33, Revision 2, February 1978; The applicable procedures required to implement the requirements of
NUREG-0737; Offsite Dose Calculation Manual implementation; and
Quality Assurance Program for effluent and environmental monitoring.
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'S also specified requirements for review and approval, temporary chi ng 's, and programs procedures for Secondary Water Chemistry and Post-Accident Sampling.
The inspector reviewed selected Health Physics Procedures, Radwaste Chemistry Procedures, Power Chemistry Procedures, and the Environmental Radiological laboratory's Radiological Environmental Sample Collec^, ion Program for McGuire Nuclear Station.
The inspector primarily reviewed those procedures which had been revised since the last inspection (Region 11 Inspection Pseport 50-369,370/87-13).
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The procedures appeared to have been written and approved in accordance
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with TS requirements.
Violations or deviations were not identified in the review of this program area.
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LiquidAndGaseousEffluent(84723,84724)
TS 3/4.11.1 specifies holding and release limits for liquid effluents, and surveillance requirements.
TS 3/4.11.2 specifies holding and release limits for gaseous effluents, and surveillance requirements.
The inspector toured the plant with cognizant licensee representatives, inspecting components of the liquid and gaseous radwaste processing systems. The inspector noted that the waste gas system included six waste gas tanks, one shutdown tank, and one relief tank.
A licensee representative stated that the shutdown tank normally did not receive purge gases or radioactive gases.
The inspecter selectively reviewed 43 Gaseous Radwaste Release Permits and 10 Liquid Radwaste Release Permits for the period from April 30, 1988, to the date of the inspection.
The permits had apparently been completed in accordance with TS and procedural requirements.
TS 4.11.4.1 requires that cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with TSs 4.11.1.2, 4.11.2.2, and 4.11.2.3, and in accordance with methodology and parameters in the ODCM.
The referenced TSs specify that the cumulative dose contributions for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days, The inspector reviewed completed Procedure PT/0/B/4600/25, Cumulative Offsite Dose from Liquid and Gaseous Effluents.
The completed procedure was reviewed for the effluents from April 1987 through April 1988.
The calculations were done at least once per 31 days, and the cumulative doses were within TS limits.
Violations or deviations were not identified in the review of this program area.
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Effluent Monitor Instrumentation a.
TSs 3.3.3.8 and 3.3.3.9 specify operability requirements and actions for radioactive liquid and gaseous effluent monitoring
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instrumentation.
TSs 4.2.2.8 and 4.3.3.9 specify surveillance requirements for this instrumentation.
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The inspector toured the plant inspecting the effluent monitors and i
discussing their installation and functions with cognizant licensee representatives.
The inspector also inspected the indicatort and
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recorders for these monitors which were located in the Control Room.
The inspector also reviewed documentation of calibrations and functional checks for selected effluent monitors.
Calibrations and functional checks appeared to have been done.at required intervals.
Health Physics Periodic Test PT/0/B/4600/08 Correlation of EMFs, September 18, 1987, requires correlation of process and effluent monitors (EMFs) readings with laboratory' analysis of radionuclide concentrations.to be performed annually.
The' inspector reviewed completed copies of the procedure which showed that the required correlations had last been performed for the monitors during June and July 1987.
The inspector noted that in some cases the activity sampled was below detectable limits, so the licensee calculated the correlation based on the most recent calibration.
Violations and deviations were not identified in the review of this program area.
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CountRoom(84723,84724)
' The inspector inspected the count room and discussed the equipment with cognizant licensee personnel. The count room was equipped with four Ortec intrinsic germanium detectors (ND 9900 System), two Beckman LS-5800 Liquid Scintillation systems and two Tennelec LB 5100-Series II Proportional Counting systems.
The inspector reviewed calibration, check, and quality control records for the lab instrumentation for the period from May 1987 through May 1988.
All calibrations and checks appeared to have been done at required frequencies.
Violations or deviations were not identified in the review of this program area.
7.
Filter And Absorber Testing (84724)
TS 4.6.1.8 requires leak testing of HEPA filters and charcoal absorbers of the Annulus Ventilation System, and laboratory testing of a carbon sample from the absorber beds. The testing is to meet the criteria of Regulatory Guide 1.52.
TS 4.7.6 specifies HEPA filter and charcoal testing requirements for the Control Area Ventilation system, and TS 4.7.7 states the requirements for HEPA filter and charcoal testing for the Auxiliary Building Filtered Ventilation Exhaust System.
The inspector discussed the HEPA filter and charcoal testing program with a licensee representative and reviewed the completed Periodic Tests under which the testing was done.
Completed copies of the procedure showed that the in-place tests were conducted at least annually. Operating times of the filter systems were being monitored by computer on Periodic Test PT/0/A/4450/17 which was done each quarte n (-
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Records showed that laboratory testing of the carbon was performed at least annually.
The records showed that charcoal samples from TS Systems was tested at both 30 C and 80'C, and charcoal samples from non-TS systems were tested at 30 C only.
Violations or deviations were not identified in the review of this program area.
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Post-Accident Sampling System (84723, 84724)
The Final Safety Analysis Report (FSAR), Section 9.3.7 provides a description of the Post Accident Liquid Sampling (PALS) System.
The inspector inspected the control panel of the system and discussed it with licensee representatives.
The system provided for collection of a sample from a hot leg or the reactor sump.
The sample was then cooled and pressure reduced. During an accident, the coolant would be routed back to containment.
During normal operations, the sample was routed to the Waste Drain Tank.
The sample was degassed by depressurization. The liquid was further stripped by bubbling nitrogen through the sample.
Nitrogen was used to drive the liquid sample to the sample loop.
Some coolant was routed to the pH analyzer, and 4 to 5 ml was routed to the dilution tank.
One mi gas sample was withdrawn for isotopic and hydrogen analyses.
A liquid sample was withdrawn for isotopic, boron, and chloride analyses.
The system was checked every six weeks by running a preventive maintenance periodic test.
The inspector also reviewed records of the completed Periodic Test, PT/1/B/4600/57, Unit 1 Post-Accident Containment Air Sampling System Periodic Test Procedure performed quarterly from April 1987 through June 1988.
Violations or deviation * were identified in the review of this program area.
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Environmental Monitoring Program (80721)
TS 3/4.12.1 providas requirements for the conduct of the licensee's environmental monitoring program.
The inspector inspected the meteorological parameter recorders in the Control Room and determine that the displays were easy to rcad.
The inspector discussed the environmental monitoring program with licensee represeitatives and inspected the laboratories and equipment used to process and evaluate the samples taken for the program.
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Collocated Environmental TLDs (25022)
Temporary Instruction TI 2500/22 describes the collection of measurement results for collocated NRC/ licensee environmental TLDs.
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The inspector discussed the data required for the program described in TI 2500/22 with licensee representatives and received the required information.
InspectorFollowupItem(IFI)TI 2500/22 is closed.
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Action On Previous Inspection Findings (92701)
(Closed) IFI 369,370/87-13-02, Evaluation of Operational Problems Concerning the March 1987 Spent Resin Spill.
The licensee agreed to evaluate methods to prevent recurrence of the incident which resulted in radioactivity contaminated backwash from the condensate polishing demineralizer being spilled to the floor drain and eventually to the Initial Holdup Pond.
The inspector reviewed Nuclear Station Modification NSM MG-12059/00, Project Description.
This document specified temporary modifications implemented to prevent recurrence of the incident and the proposed permanent modification to the system.
The proposed modification would change flow in the system, add filtering, and add monitoring capability to prevent recurrence.
A licensee representative stated that the modification would be installed in Unit 1 during the 1990 refue ing outage and in Unit 2 during the 1989 refueling outage.
Completion of this modification will be followed as an Inspector Followup Item:
(0 pen) IFI 369,370/88-17:
Complete modification to condensate polishing demineralizer backwash system to revent spill to floor drain by end of 1989 refueling outage for Unit 2 and 1990 refueling outage for Unit 1.
12.
Exit Interview The inspection scope and results were summarized on June 24, 1988, with those persons indicated in Paragraph 1.
The inspectors described the areas inspected and discussed in detail the inspection results listed above.
Proprietary information is not contained in this report.
Dissenting comments were not received from the licensee.