IR 05000395/1982021
| ML20054D818 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 03/30/1982 |
| From: | Albright R, Barr K, Collins T, Hosey C, Peery W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20054D815 | List: |
| References | |
| 50-395-82-21, NUDOCS 8204230414 | |
| Download: ML20054D818 (11) | |
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UNITED STATES
NUCLEAR REGULATORY COMMISSION n
$
E FlEGION 11
o 101 MARIETTA ST., N.W., SUITE 3100 ATLANTA, GEORGIA 30303
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Report No 50-395/82-21 Licensee:
South Carolina Electric and Gas Company Columbia, SC 29218 Facility Name: Virgil C. Summer Nuclear Station Docket No. 50-395 License No. CPPR-94 Inspection at Summer ; t' near Jenkinsville, SC Inspectors:
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C. M. Hose)/ ~
Date Signed i
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W. W. Peery Uate igned af f'
g ww T. R. Collins te igned
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O!28!f1 R.H.Albrip Date signed Jo[gg.,
Approved by-
.P. barr, Section Chief
[Vate Signed Technical Inspection Branch Division of Engineering and Technical Programs SUMMARY Inspection on February 22-26, 1982 Areas Inspected This special announced inspection involved 128 inspector-hours on site in the areas of radiation protection, liquid and solid waste systems and gaseous waste systems.
Results l
l Of the three areas inspected, no violations or deviations were identified.
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l REPORT DETAILS l
1.
Persons Contacted Licensee Employees
- W. A. Williams, Jr., General Manager, Nuclear Operations
- J. G. Connelly, Deputy Plant Manager
- V. R. Albert, Assistant Manager - Support Services J. Barker, Corporate Health Physicist
- A. R. Koon, Technical Services Coordinator
- L. A. Blue, Director of Health Physics
- L. E. Atkinson, S/U Test Supervisor
- T. A. McAlister, QA Surveillance Specialist, Supervisor
- H. C. Fields, Technical Services Engineer
- R. G. Sweet, QA Surveillance Specialist
- S. S. Howze, Nuclear Licensing G. DiCorte, Assistant Health Physics Supervisor P. Shultz, Assistant Health Physics Supervisor J. Bellmore, Assistant Health Physics Supervisor l'
Other licensee employees contacted included five technicians.
NRC Resident Inspector
- J. L. Skolds
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on February 26, 1982, with l
those persons indicated in paragraph 1 above. An inspector discussed six open items identified during this inspection which are further discussed in the details of this report. The inspector also discussed the close out of 10 of 13 open items and three remaining open items from previous inspec-tions.
3.
Licensee Action on Previous Inspection Findings
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Not inspected 4.
Unresolved Items
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Unresolved items were not identified during this inspection.
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5.
Inspector Follow-up Items a.
(Closed)(IFI) 395/80-33-02, An inspector reviewed the Health Physics Specialist and Qualification Training Program to verify that Health Physics personnel were trained and qualified in specific tasks. The inspector concluded after his review that the program was adequate and had no further questions.
b.
(Closed)(IFI) 395/80-33-03, An inspector reviewed the completed modi-fication of the Radiation Control Area (RCA) access for traffic control to the RCA. The' inspector concluded the modification was adequate and had no further questions.
c.
(Closed)(IFI) 395/80-33-06, An inspector reviewed the initial calibra-tion of the Whole Body Counter as required by HPP-510, Set-Up and Calibration of Whole Body Counting System.
The inspector determined the initial calibration was completed on February 14, 1982 and had no further questions, d.
(0 pen)(IFI) 395/80-33-07, Area radiation monitors have not been cali-brated. This item will be reviewed during the next inspection.
e.
(Closed)(IFI) 395/80-33-08, An inspector reviewed the Respirator Maintenance Area to verify that the facility, equipment, storage and issuance of respirators was complete and adequate for normal use. The inspector concluded that this area was adequate and had no further questions.
f.
(Closed)(IFI) 395/81-11-01, Installation of liquid effluent monitors are now considered complete and questions the inspectors had concerning the monitors have been resolved.
g.
(Closed)(IFI) 395/81-21-01, Filter drain and vent connections now have corrections completed.
h.
(Closed)(IFI) 395/81-21-02, An inspector reviewed the measurements performed by the licensee on certain radwaste holding tanks to assure the capacity of the tank volumes. The inspector concluded that these measurements were adequate and had no further questions.
1.
(Closed)(IFI) 395/81-21-03, An inspector reviewed the new location and installation of the waste compactor in the mezzanine waste storage area. The inspector noted that the waste compactor ventilation system had not been connected to the filtered Auxiliary Building Plant Vent, however the inspector was informed by licensee personnel that tests have been performed to verify sufficient ventilation exhaust in this area to adequately remove the potential of airborne radioactivity during operation of the compactor.
The inspector stated that this appeared to be adequate and had no further question.
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(Closed)(IFI) 395/82-07-01, An inspector reviewed the approved proce-dure HPP-710, Release of Radioactive Liquid Effluents and concluded this procedure appeared to be adequate for plant operation.
The inspector had no further questions.
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(Closed)(IFI) 395/82-07-02, An inspector reviewed the completed and approved procedure HPP-701, Processing Solid Radioactive Waste and concluded this procedure was adequate for plant operation.
1.
(0 pen)(IFI) 395/82-07-03 Damaged Prefilters.
The licensee has not reached the point in plant preparation for startup that they consider it desirable to change the prefilters. The inspector stated that this item would remain open until the prefilters have been replaced.
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(0 pen)(IFI) 395/82-07-04 Procedures for Control and Release of Gaseous Waste. Revision of plant procedures HPP-709, Release of Radioactive Gaseous Effluents and SOP-119, Waste Gas Processing are in preparation and have not been approved. The inspector stated that these procedures
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would be reviewed during a subsequent inspection.
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(0 pen) (IFI) 395/82-21-01, Qualification of Health Physics Technicians.
The licensee's task qualification for health physics technicians is based on ANSI 3.1 which is incompatible with Technical Specification 6.3.1 requiring qualification in accordance with ANSI 18.1-1971.
Licensee representatives acknowleged that considerations will be given to requesting a change to the Technical Specifications incor-porating ANSI 3.1.
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(0 pen) (IFI) 395/82-21-02, Solid Waste Solidification Systems.
The Chem-Nuclear cement solidification system had not been installed.
An inspector stated that the systems should be operational as soon as posssible and that a 10 CFR 50.59 safety evaluation should be per-formed. Licensee representatives acknowledged these findings.
p.
(0 pen) (IFI) 395/82-21-03, Measurment of Hood Face Velocities. The air flow velocities st the face of fume / sample hoods had not been measured and a procedure for such measurements had not been written. A licensee representative stated that a procedure will be developed and the hoods tested.
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(0 pen) (IFI) 395/82-21-04, Gaseous Radioactivity Monitors.
Pre-op testing did not include verification that the flow from sample points was coming from the intended area. Licensee representatives acknowl-edged that there was no documentation for this item.
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(0 pen) (IFI) 395/82-21-05, Ventilation System Filter Testing.
Filter test results did not include documentation of residence times, flow distribution and testing of charcoal prior to loading the filters. A
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4 licensee representative stated that the documentation should be avail-able from the vendor. An inspector stated that the records will be reviewed during a subsequent inspection.
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(Open) (IFI) 395/82-21-06, Waste Gas System. The waste gas system had not been tested and operating procedures had not been written. This item will be reviewed on a subsequent inspection.
6.
Radiation Protection Program a.
Audits of Radiation Protection Program An inspector reviewed a draf t corporate health physics procedure, CHP-105, Schedule of Corporate Health Physics Activities and discussed the proposed audit program of plant activities with a corporate repre-sentative. The proposed audit schedule appears to cover the principle aspects of the plant's radiation protection program.
The inspector stated that corporate staff should take appropriate action to ensure that the audits assess the effectiveness of the plant's radiation protection program rather than limiting the audits to paperwork reviews or determining procedural compliance, b.
Safety Equipment While reviewing the radiation protection program, it was determined that the licensee does not have a program to test fume hood air velocities. A licensee representative stat.:d that a procedure would be developed to test fume hoods against the requirements of NBS Handbook 92.
c.
HP Qualifications and Training Program The qualifications of five health physics supervisors and five health physics technicians considered qualified by the licensee were reviewed against ANSI N18.1-1971 requirements. This review was accomplished by records review and personal interviews. All personnel appeared to meet the qualifications requirements of the ANSI standard as applied to their job description and responsibilities.
The licensee currently has 15 health physics technicians, of which five are considered qualified in accordance with ANSI N18.1-1971.
The licensee has job offers to seven additional health physics technicians.
The 22 available technician slots appear to be adequate to support a single unit PWR. In the event that additional technicians are needed, the licensee has established contracts with two contract technician companies, i
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The inspector reviewed the health physics technician training and retraining programs.
The programs appeared adequate and followed closely the health physics technician training program described in NUREG-0761. At the exit interview a licensee representative indicated that they intend to determine the value of adopting the qualifications requirements of ANSI N3.1 for the health physics technicians.
In the event they do decide that ANSI N3.1 is of more value than ANSI N18.1-1971 in the health physics area, they will seek a technical specifica-tion change to reflect this. The inspector stated that certain provi-sions of ANSI N3.1 were contrary to ANSI N18.1 so the technical speci-fication change would have to be in place prior to using ANSI N3.1 as the basis for their training qualification program.
The technician and supervisor retraining is fulfilled by a continuous training program and annual review of selected station procedures. The continuous training program will cover several subjects over the course of a year through monthly training sessions.
This program appears adequate to provide retraining for health physics technicians and supervisors.
d.
Radiation Worker Training The inspector reviewed the radiation worker training program and found it to be adequate. The program appeared to be in compliance with Reg Guide 8.27.
The program is a combination of lecture, testing and practical training. The inspector had no further questions.
e.
Test Results Review An inspector reviewed the following functional tests for adequacy and results:
RM-All
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Radiation Monitor RM-All Functional Test RM-A13
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Plant Vent Channel Functional Test RM-L3
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Radiation Monitor RM-L3 Functional Test RL-005 RM-L5
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Radiation Monitor RM-L5 Functional Test RM-G1
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Radiation Monitor RM-G1 Functional Test The review of RM-All did not indicate that a test had been performed to determine that the monitor was actually sampling the intended area.
Procedure RM-All is the functional test for RM-All which samples the air activity in various auxiliary building ventilation ducts. A licensee representative stated that there was a walkdown of the sample lines, however, this was not documented.
The inspector stated that the sample system should be tested to ensure that flow was coming from the intended area. The inspector stated that other radiation monitors functional tests may have this same proble.
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Ten of the air sampling and liquid process monitors have not been pre-op tested to test the interface of the radiation monitor to shut-off valves and ventilation dampers.
The area radiation monitoring system installation is not complete.
Installation of these monitors is scheduled for completion early in March. After installation is complete these monitors must be functional and pre-op tested (80-33-07).
7.
Gaseous Waste Systems a.
High Efficiency Filter Systems An inspector reviewed the results of the following preoperational tests of the plant's high Ef ficiency Filter Systems:
In place filter test of Auxiliary Building HEPA and HECA filters ( AH-15, AH-16 and AH-17)
In place filter test of fuel handling building HEPA and HECA filters (AH-20)
In place filter test of controlled access HEPA and HECA filters (AH-38)
In place filter test of Reactor Building cleanup HEPA filters (AH-AFS)
In place filter test of Hot Machine Shop HEPA filters (AH-39)
In place filter test of Reactor Building Purge HEPA and Charcoal Filters ( AH-F04)
The filters were tested by a vendor using approved plant test proce-
dures.
The filters were tested using the recommendations of ANSI N510-1975, Testing of Nuclear Air-Cleaning Systems. During the review of the test results, the inspector noted that two tests which are considered prerequisite tests to in place filter testing were not performed for all applicable systems.
These tests were the flow distribution test and the residence time test for charcoal filters. No evidence was available at the plant that the flow distribution test was performed for the hot machine shop filter or the auxiliary building HEPA exhaust system. When the flow distribution test was performed the test results did not indicate which instrument was used, nor appro-priate calibration information. Test results did not indicate that the residence time test had been performed on any HECA (charcoal) filter.
A licensee representative stated that the tests were performed on all systems however the appropriate information was not transcribed off of the vendor's reports into the official test procedure.
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stated that a vendor's instrument was used to perform the flow distribution test and that the, type, serial number and calibration
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information was available from the vendor. The inspector stated that the additional vendor supplied information would be reviewed during a subsequent inspection (82-21-05).
The inplace filter test results reviewed indicated that the filters were greater than 99.95*. efficient at the design flow rate.
ANSI N510-1975 recommends that the condition of the absorbent in the absorber systems be determined by analyzing a sample of the absorbent prior to loading into the absorber system.
A review of test data indicates that the licensee did not remove a sample for analysis prior to loading the charcoal into the filters.
A licensee representative stated that the charcoal was tested by the supplier and supplied to the plant in sealed containers and they did not consider the additional test necessary. The inspector stated that the supplier's test should be adequate. The ins p ctor stated that the supplier's test data would be reviewed during a subsequent inspection (82-02-05).
During tours of the plant the inspector noted that significant painting was in progress. Paint fumes could have a deleterious effect on the high efficieny particulate and charcoal filters and the licensee was informed that consideration should be given to retesting all filters prior to going beyond low power testing although the licensee's Tech-nical Specifications will only require periodic surveillance testing of the reactor building iodine cleanup system and the fuel handling building filter systems following painting, fire or chemical release in any ventilation zone communicating with the systems.
The inspector reviewed the results of the following filter housing pressure tests:
Fuel handling building filter housings (XAA-218-AH, XAA-21C-AH and XAA-21A-AH)
Auxiliary Building charcoal exhaust filter housing ( XAA-40A-AH and -
XAA-408-AH)
Auxiliary Building HEPA exhaust filter housing (XAA-41-AH)
Leakage rates met the acceptance criteria established in the test proce-dures. The inspector had no further questions.
The inspector reviewed the preoperational test results for the A and B hydrogen reccmbiners and had no further questions.
b.
Representative Sampling During tours of the plant, the inspector observed the sample probe configuration for the main plant vent monitor (RM-A1). The inspector also reviewed the engineering drawings for isokinetic sample nozzles for the following monitors:
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RM-Al Control Room Air RM-A2 Reactor Building Exhaust RM-A3 Main Plant Vent RM-A4 Reactor Building Purge RM-A6 Fuel Handling Building Exhaust The sample probes appear to be designed to provide for isokinetic and representative sampling of the appropriate air streams. The inspector had no further questions.
8.
Procedures Reviewed AP-701
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Issuance and Control of Personnel Dosimetry AP-702
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Use of the Radiation Work Permit (RWP) and Standing Radiation Work Permit (SRWP)
AP-703
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Self Reading Dosimeter Card AP-704
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Administrative Exposure Limits AP-705
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Issuance and Control of Respiratory Protective Equipment AP-706
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Control of Airborne (Internal) Radiation Exposure (MPC-hrs)
AP-707
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Use of Protective Clothing AP-708
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Personnel Monitoring for Contamination AP-709
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Contamination Control for Areas, Equipment and Materials AP-705
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Issuance and Control of Respiratory Equipment AP-714
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Station ALARA Committee Description AP-715
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Qualification Process for the Use of Respiratory Protection Equipment HPP-303
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Airborne Activity Sampling Techniques and Procedures HPP-304
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Operation of the EIC Personnel Radiation Monitor Model RM-14 HPP-305
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Operation of Victoreen Model 808-D, Area Radiation Monitor (VAMP)
HPP-401
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Issue, Termination and Use of RWP's HPP-402
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Radiological Survey Requirements for Reactor Building Initial Entry and Shutdown Conditions HPP-405
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Personnel Decontamination HPP-410
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Health Physics Routine Surveys HPP-609
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Administrative Controls for Calibration HPP-904
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Use of Radiation Monitoring System (Not Approved)
HPP-615
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Operation of the J. L. Shephard Model 149 Neutron Source HPP-614
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Operation of the J. L. Shepherd 100 mci Cs137 Sources HPP-619
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Recertification of Standard Calibration Sources HPP-810
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Sampling of Radioactive Gases and Liquids HPP-814
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Non-Routine Gas and Liquid Sampling HPP-914
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Operational / Calibration of the Biomarine Atmospheric Monitors HPP-503
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Thermoluminescence Dosimetry Test HPP-505
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Issuance and Control of Personnel Dosimetry HPP-508
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Quality Control of the Whole Body Counting System HPP-509
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Leak Test and Calibration of Pocket Dosimeters
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HPP-510
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Set-Up, Operation and Calibration of the (WBC-6000) Whole Body Chair HPP-511 Tritium Analysis of Urine Samples
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HPP-512 Tritium Bioassay Calculations of MPBB's
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HPP-513
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Operation of J. L. Shepherd Irradiator HPP-515
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Bioassay Program HPP-602
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Respirator Fitting HPP-604 Set-Up of Airline Respiratory Equipment
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HPP-404
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MPC-Hour Accountability HPP-703
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Shipping Radiactive Materials HPP-701
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Health Physics Coverage for Processing Solid Radioactive Waste HPP-407
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Controls for Receipt of New Fuel HPP-408
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Fuel Movement Controls HPP-708
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Handling of Contaminated Laundry and Trash HPP-709
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Release of Radioactive Gaseous Effluents HPP-710
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Release of Radioactive Liquid Effluents HPP-704
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Radioactive Source Inventory and Accountability HPP-705
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Liquid Scintillation Waste Disposal HPP-902
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Report and Investigation of Unusual Radiological Occurrences HPP-702
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Receipt of Radioactive Materials HPP-610
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Certification of Flow Rates for Portable Air Samplers HPP-611 Calibration of Station Survey Instruments
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HPP-613
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Operation of the Eberline Model 10008 Multiple Source Gamma Calibrator The inspectors had no further questions concerning these procedures.
9.
Health Physics Manual The V.C. Summer Nuclear Station Health Physics Manual was also reviewed and was determined to be adequate for plant operation. The inspector also made suggestions to the cognizant supervisor concerning corrections, changes and additions to the Health Physics Procedures. The Health Physics Supervisor acknowledged these comments to the HPP's and the inspector stated these changes would be reviewed at the time of the next inspection.
10.
Radwaste Solidification System The licensee intends to use a mobile cement solidifcation system supplied by
Chem Nuclear Systems, Inc. (CNSI).
At the time of the inspection this system had not been received and installed by the licensee, however an inspector reviewed the approved contract between CNSI and the licensee to verify the type of solidification system to be used. The inspector stated this system would be reviewed during subsequent inspections.
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11.
Liquid Waste Systems a.
Pre-op Test Results reviewed were as follows:
Reactor Coolant Drain Taiik Pumps, WD-001, 9/22/81
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Waste Evaporator Feed Pump, WD-002, 8/11/81
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Waste Evaporator Condensate Pump, WD-004, 4/6/81
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Chemical Drain Tank Pump, WD-006, 2/10/81
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Laundry and Hot Shower Tank Pump, WD-008, 8/21/81
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Floor Drain Tank Pump, WD-003, 9/22/81
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Waste Monitor Tank Pumps WD-009, (Not complete - started 3/26/81)
The inspector had no questions.
b.
Settling Pond Sampling This subject was discussed at the time of the last inspection (82-07)
and licensee representatives stated that the matter would be evaluated.
Discussions with site and corporate personnel at the time of this -
inspection revealed that the sampler was in the process of being installed. This will be reviewed at the time of the next inspection.
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