IR 05000424/1986128
| ML20212G081 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 12/30/1986 |
| From: | Kahle J, Stoddart P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20212G049 | List: |
| References | |
| 50-424-86-128, NUDOCS 8701120264 | |
| Download: ML20212G081 (7) | |
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UNITED STATES
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jo NUCLEAR REGULATORY COMMISSION e
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Report No.: 50-424/86-128 Licensee: Georgia Power Company P. O. Box 4545 Atlanta, GA30302-Docket No.: 50-424 License No.:
CPPR-108 Facility Name: Vogtle 1 and 2
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Inspection Conductgd:, December 8-11, 1986
'Yh M.jL'
UkW0 Inspector:
).Stopart
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Date Signed
. Approved by:
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/4/ap//Z J.Kape~,SectiodChief Date Signed Division of Radiation Safety and Safeguards SUMMARY Scope:
This routine, announced inspection covered the areas of liquid and gaseous radwaste systems, ventilation and exhaust treatment systems, liquid and gaseous effluent monitoring and sampling systems, and post-accident sampling system.
Results: No violations or deviations were identified.
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REPORT DETAILS 1.
Persons Contacted Licensee Employees
- C. Belflower, Quality Assurance Site Manager
- D. Hallman, Chemistry Superintendent R. Hand, Process and Effluent Radiation Monitoring and Sampling System Supervisor P. Jackson, Post Accident Sampling System Engineer J. Pappes, Systems Engineer M. Canaboy, Systems Engineer J. Nadzam, Systems Engineer A. Parton, Test Supervisor P. Burwinhel, Heating, Ventilating and Air Conditioning Engineer W. Barrett, Test Supervisor
- A. Stalker, Corporate Chemist
- Attended exit interview
- Participated in exit interview by telephone from Corporate Headquarters 2.
Exit Interview The inspection scope and findings were summarized on December 11, 1986, with those persons indicated in Paragraph 1 above.
The inspector described the areas inspected and discussed in detail the inspection findings.
No dissenting comments were received from the licensee.
The inspector's review indicated that approximately 95% of the preoperational test procedures for the post accident sampling system (PASS)
had been completed.
For the process and effluent monitoring system (PERMSS), about 90% had been completed and for the liquid and gaseous radwaste systems, only about 50% had been done.
It was noted that most of the HEPA filter and charcoal absorber installations had not been either
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loaded or tested.
The inspector expressed the NRC's concern that tests at.
other power plants indicated the presence of non-representative sampling of radiciodine in plant gaseous effluent samples as a result of plateout and
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deposition in long sampling lines of the type used at Vogtle. The inspector noted the (PASS) containment air sampling system was not functioning properly during preoperational testing.
The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspector during this inspection.
3.
Post Accident Sampling System (II.B.3) (83523, 83524)
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The inspector reviewed Post Accident Sampling System (PASS) Preoperational
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Test Procedure 1-3RP-02, Rev. O, dated April 23, 1986, and change requests (CRs) I through 20.
The procedure had been reviewed and approved in
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accordance with applicant requirements and a spot check of the 20 CRs
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indicated that all had been properly entered.
Preoperational work was
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initiated July 22, 1986.
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The inspector noted that work had been interrupted in three sections; in
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each case, the time, date, and cause of the interruption was appropriately
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The inspector discussed the incomplete sections with cognizant
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applicant staff and determined that most of the remaining work was expected to be completed after completion of testing of the Engineered Safety Feature s
Actuation System (ESFAS).
One problem, however, was concerned with the
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sampling of. containment atmosphere.
An air eductor device had been used to draw the' containment atmosphere sample from containment through a 1" line, through two Valcor valves, and through charcoal and paper filters.
The sampled air, plus the instrument air expended in the eductor, was to be
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returned to containment via a similar path. ~ Preliminary testing indicated that the return air did not flow through the return path at an adequate
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rate.
The inspector noted that the volume of air being returned to containment was approximately five times greater than was being removeo from containment.
The result was that the return line, which was identical in
size to the sample intake line, developed a substantially higher resistance to the increased flow and was incapable of accepting the larger flow without some form of modification, such as an auxiliary mechanical pump or an
increase in the diameter of the return line.
As of the end date of the
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inspection, the-applicant.was considering two possible modifications, one being replacement of the return line isolation valves with a type of valve with less internal flow resistance, and the other being the replacement of
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the air eductor with a flexible metallic bellows vacuum pump, which would eliminate the added load of the extra air expended in the eductor.
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Vendor training of plant personnel on operation of the PASS was conducted during the period of the inspection but had not been completed as of the end
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date of the inspection.
(0pened) Inspector Followup Item (IFI) 50-424/86-128-01: Review corrective
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actions on return of containment air sample flow back to containment.
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No violations or deviations were identified.
4.
Process and Effluent Radiation. Monitoring and Sampling System (PERMSS)
(NUREG-0737, Items II.F.1-1 and II.F.1-2, and Modules 83523,83524)
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- The inspector reviewed the Preoperational Test Procedures for the
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- safety-related display console, identified as " Digital Radiation Monitoring System (Safety-Related Display Console)," 1-3SD-02.
Work on the preoperational testing was initiateu on November 6,1986.
The inspector
spot-checked CRs, numbered 1 through 15 (through December 6,1986), and found the referenced procedures had received pen-and-ink changes in
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accordance with the CRs.
Under Section 6, " Test Procedures," the inspector
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i noted that 12 of 15 procedure subsections had been completed and that three were incomplete (Section 6.7, RX-2562 Data Processing Module; Section 6.8,
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RX-003 Data Processing Module; and Section 6.15, Detector Calibration).
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Based on the above, the ins ector estimated percentage completion on
, Procedure 1-35D-02 to be 90% asofDecember9,1986).
The inspector reviewed the Preoperational Test Procedures for the non-safety-related portion of the PERMSS, identified as " Digital Radiation Monitoring System (Non-Safety-Related) 1-3SD-02.
Work on the procedure was initiated November 25, 1986.
The inspector spot-checked 14 CRs, numbered 1 through 15 (through December 6,1986), and found the referenced procedures had received pen-and-ink changes in accordance with the CRs.
Under Section 6. " Test Procedures," the inspector noted that ten of 27 procedure subsections had been completed (as of December 9,1986) and that 17 were incomplete or partially complete (Section 6.3, RX-008; Section 6.5, RX-014; Section 6.9, RX-17646;.Section 6.10,'
RX-48000; Section 6.13, RX-016; Section 6.14, RX-017; Section 6.16 RX-024; Section 6.18, RX-50002; Section 6.19, RX-009; Section 6.20, RX-1950, Section 6.21, RX-2565; Section 6.22, RX-12442; Section 6.23, RX-12444; Section 6.24. RX-12839; Section 6.25,
" Flow Transmitter Loop Check;"
Section 6.26,
" Minicomputer / Communication Console Test;" and Section 6.27
" Detector Calibration and Operability Verification").
Additionally, Sections 8.0,
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" Restoration (System)" and 9.0, " Acceptance Criteria" were not complete.
l Based on the above, the inspector estimated the percentage completion on l
Procedure 1-3SD-02 to be 40% complete (as of December 9, 1986).
The Vogtle Process and Effluent Radiation Monitoring and Sampling System (PERMSS) is a Westinghouse system desigr.ated by Westinghouse as the " Digital Radiation Monitoring System (DRMS)" but designated by the applicant as
"PERMSS."
The PERMSS consists of a variety of detectors located at important locations throughout the plant. Each detector has its own " data processing module" or
"DPM," which converts the detector signed to the desired units (i.e., counts per minute, milliroentgens per hour, or microcuries per cubic centimeter).
A limited amount of information is stored in DPM memory to protect PERMSS against data loss due to short-term malfunction.
Each DPM is linked to a " communications console" by a two way 9600-band communications link.
Safety related DPMs have two links, one to the communications console, the other to the safety-related display console.
The display consoles provide remote control and status display capability for the PERMSS.
Each display console sequentially interrogates each DPM to obtain the current radiation level and can request the historical data file from DPM memory.
The communications console is linked to the PERMSS minicomputer system. The-PERMSS minicomputer system has the installed software to generate additional display formats, which can be presented on color CRT terminals in the Control Room, Health Physics lab, and the onsite Technical Support Center (TSC).
The r:inicomputer also provides for the long term permanent storage of accumulateu radiation data on high-capacity magnetic disc and on backup magnetic tape. The minicomputer also picks up process data, such as process system flows and includes integration of plant data, current radiation
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levels, and inputs from the plant multiple-channel analyzer (gamma spectrometer). - Output from the minicomputer can also be fed to the onsite TSC computer for further processing.
The Vogtle PERMSS minicomputer is a Data General " Eclipse Model S/130" computer with two disc drives, one 10 negabyte fixed drive (non-removable)
and one dual-sided 10 megabyte removable cartridge disc drive.
The system can be expanded to 80 megabytes in 20 megabyte increments, if needed.
Each DPM determines the average radiation level for each elapsed minute and calculates ten minute, hourly, and daily averages.
This data is stored in DPM memory and can be displayed in command at the canmunications console and at the minicomputer terminals.
A DPM will lose all of its accumulated data if power is interrupted; however, on re-gaining power, the DPM can
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interrogate the communications console to obtain its own historical data from the minicomputer's data storage to re-establish its own file.
The PERMSS communications console and the minicomputer are considered operable by Technical Specification provisions since the minicomputer can generate hard copy data sheets which can be stored as the plant's permanent record.
The applicant should, however, continue efforts to resolve the problem of transferring record data from the magnetic disk storage to the permanent tape storage system.
The PERMSS system, as such, cannot be considered operable until the appurtenant monitors are fully tested, calibrated, and functional.
Under the REC purview, this would include the following monitors:
RE-0013 Water Gas Process System Process
- RE-12116 Control Room Air Intake Process Monitor
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- RE-12117 Control Room Air Intake Process Monitor
- RE-13119 - 13122 Main Steam Line Monitors
- ARE-2532 A/B Fuel Handling Building Noble Gas Effluent
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Process Monitors
- ARE-2533 A/8 Fuel Handling Building Noble Gas Effluent Process Monitors
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RE 2565 A 3/C Containment Vent Effluent Air Monitor i
- RE 50003 Technical Support Center Air Intake Monitor i
RE-12442 A/B/C Plant Vent Effluent Air Monitor-Normal Range l
RE-12444 A/B/C/D/E Plant Vent Effluent Air Monitor-High Range l
RE-12839 A/B/C/D/E Air Ejector and Steam Packing Exhauster Air Ejectors
- 0nly these monitors had completed preoperational testing as of l
December 9, 1986.
(0pened) Inspector Followup Item (IFI) 50-424/86-128-02:
Review incomplete preoperational test procedures remaining from Inspection 86-128 for PERMSS.
No violations or deviations were identified.
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5.
Liquid Radwaste Treatment Systems (84523)
The inspector reviewed liquid radwaste system preoperational procedures and discussed procedures and equipment with applicant representatives.
The review area included both primary and secondary reactor coolant cleanup and purification systems and the interface to the miscellaneous radwaste system to be used in the Alternate Radwaste Building.
The preoperational tests included under Procedure 1-3HB0-1, Rev. O, included the reactor coolant drain tank (RCDT), confirmation of recirculation flow to the pressure relief tank (PRT), time of closure of RCDT containment isolation valve under water flow conditions, waste evaporator condensate tank (WECT) system, reactor water makeup (WEC) holdup tank, waste monitor tanks 1 and 2, chemical drainsto condensate tank (CDT), spent resin storage, and spent resin sluicing operation. At the time of the inspection, 1-3HB0-1 was approximately 100% complete.
Tests of the boron recycle evaporator were approximately 78% complete and tests of the waste evaporator were approximately 36% complete.
A test of the resin transfer line from the boron recycle area to the alternate radwaste building (ARB), using nonradioactive resin, was successful.
(0pened)
Inspector Followup Item (IFI) 50-424/86-128-03, Review preoperational procedures for the boron recycle system and waste evaporator.
No violations or deviations were identified.
6.
Gaseous Waste Treatment Systems (84524)
The inspector discussed preoperational testing of the waste gas system with licensee representatives.
Tests included the vent header, waste gas surge tank, and verification that automatic isolation features fail in the closed position.
Leak tests had been done and one train of the system had been operated. Tests were expected to be completed by December 15, 1986.
The inspector also discussed preoperational testing of the control room and effluent air HEPA filtration and charcoal absorption systems with licensee representatives. As of the end date of the inspection, only one ESF system, the electrical penetration room exhaust, had been loaded and that system had not been leak tested.
None of the other ESF and non-ESF air treatment systems had been loaded with either HEPA filters or charcoal.
The ESF and non-ESF systems had been pressure leak tested but only the electrical penetration room exhaust system had received airflow capacity and distribution tests.
Installation of a charcoal absorber in the Technical Support Center habitability HVAC system had been completed but neither charcoal nor the system's HEPA filters had been installed as of the end date of the inspection.
All plant buildings and facilities with a known potential for generation of radioactive gaseous aerosols are exhausted through air treatment systems consisting of, sequentially, a prefilter or " roughing" filter, a high efficiency particulate air (HEPA) filter, a six-inch deep bulk-loaded
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charcoal absorber bed, and a downstream HEPA filter.
With two exceptions, all plant air having known potential for radioactive contamination will be continuously proccssed through the treatment systems described above and will be released through the plant vent.
One exception is the main condenser air ejector system, which is simflarly filtered but is released through an independent vent.
The second exception is the smoke removal system, which is an optional system which has the function of clearing smoke from the control room area and the sampling and chemistry hood areas in the case of a smoke-producing event; the smoke removal system is vented to the atmosphere unfiltered through a separate vent.
(0pened) IFI 50-424/86-128-04, Review preoperational tests of the waste gas system which were to be completed by December 15, 1986.
(0pened) IFI 50-424/86-128-05, Review installation of HEPA filters and charcoal absorbers in ESF and non-ESF ventilation / exhaust treatment systems.
No violations or deviations were identified.
7.
Sampling of Plant Effluent Gaseous Aerosols (84524)
The inspector discussed sampling of gaseous aerosols in the plant vent with applicant personnel.. It was noted in a previous inspection (50-424/86-119)
that the number of sampling points provided in the vent was less than the number recommended in ANSI N13.1-1969; this question remained unresolved.
During this discussion, it was brought to the attention of the applicant representatives that recent tests at other nuclear power plants indicated that the transport of aerosol iodine through a long sampling tube was subject to a number of variables that were not well understood and that caused random deviations and errors in sampling results.
The applicant representatives were referred to the recent literature on iodine sampling and made a verbal commitment, concurred in by a corporate representative, to review the problem.
(0pened) IFI 50-424/86-128-06.
Review applicant evaluation of mechanisms of sample transport for iodine in long sampling lines.
No violations or deviations were identified.
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