IR 05000395/2002002
| ML022110092 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 07/29/2002 |
| From: | Plisco L Division Reactor Projects II |
| To: | Byrne S South Carolina Electric & Gas Co |
| References | |
| EA-02-122 IR-02-002 | |
| Download: ML022110092 (45) | |
Text
July 29, 2002
SUBJECT:
VIRGIL C. SUMMER NUCLEAR STATION - NRC INTEGRATED INSPECTION REPORT NO. 50-395/02-02; EXERCISE OF ENFORCEMENT DISCRETION
Dear Mr. Byrne:
On June 29, 2002, the NRC completed an inspection at your Virgil C. Summer Nuclear Station.
The enclosed report documents the inspection findings which were discussed on July 3, 2002, with Mr. G. Halnon and other members of your staff.
The inspection examined activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your license.
The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.
Based on the results of this inspection, two findings were identified which were determined to be of very low safety significance (Green). One finding was determined to involve a violation of regulatory requirements. However, because the issue has been entered into your corrective action program, the NRC is treating the issue as a non-cited violation, in accordance with Section VI.A.1 of the NRCs Enforcement Policy. If you deny the non-cited violation, you should provide a response with the basis for your denial, within 30 days of the date of this inspection report, to the United States Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington DC 20555-0001; with copies to the Regional Administrator, Region II; the Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington, DC 20555-0001; and the NRC Resident Inspector at the Virgil C. Summer Nuclear Station.
The second finding, involving a failure to establish a fitness for duty procedure consistent with 10 CFR 26.24 requirements, was also a violation of regulatory requirements. Based on your prompt corrective action, the apparent generic nature of the issue, and conflicting NRC guidance regarding the 10 CFR 26.24 requirements, and after consultation with the Director, Office of Enforcement, the NRC has determined that the exercise of enforcement discretion is warranted in accordance with Section VII.B.6 of the "General Statement of Policy and Procedure for NRC Enforcement Actions - May 1, 2000, NUREG-1600, as amended on November 3, 2000 (65 Federal Register 59274), and February 16, 2001 (65 Federal Register 79139) (Enforcement Policy). Accordingly, a Notice of Violation will not be issued.
SCE&G
In accordance with 10 CFR 2.790 of the NRCs Rules of Practice, a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRCs document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
Loren R. Plisco, Division Director Division of Reactor Projects Docket No.: 50-395 License No.: NPF-12
Enclosure:
Integrated Inspection Report No. 50-395/02-02
REGION II==
Docket No.:
50-395 License No.:
NPF-12 Report No.:
50-395/02-02 Licensee:
South Carolina Electric & Gas (SCE&G) Company Facility:
Virgil C. Summer Nuclear Station Location:
P. O. Box 88 Jenkinsville, SC 29065 Dates:
March 31, 2002 through June 29, 2002 Inspectors:
M. Widmann, Senior Resident Inspector
M. King, Resident Inspector
K. Green-Bates, Project Engineer, RII (Sections 1R06 and 1R07)
W. Bearden, Reactor Inspector, RII (Section 1R08.2)
K. Davis, Physical Security Specialist, RII (Sections 3PP1, 3PP2, 4OA1.6, 4OA5.2)
J. Wallo, Physical Security Specialist, RII (Sections 3PP1, 3PP2, 4OA1.6, 4OA5.2)
R. Hamilton, Radiation Specialist, RII (Sections 2OS1, 2OS2, 2PS2, 4OA1.4 and 4OA1.5)
E. Testa, Senior Radiation Specialist, RII (Sections 2OS1, 2OS2, 2PS2, 4OA1.4 and 4OA1.5)
F. Wright, Senior Radiation Specialist, RII (Sections 2OS1, 2OS2, 2PS2, 4OA1.4 and 4OA1.5)
Approved by:
K. Landis, Chief, Reactor Projects Branch 5 Division of Reactor Projects
Attachment:
Supplemental Information
SUMMARY OF FINDINGS IR 05000395/02-02, on 03/31/2002 - 06/29/2002, South Carolina Electric & Gas Co., Virgil C.
Summer Nuclear Station. Non-Routine Evolution and Events - Reactor Trip.
The inspection was conducted by the resident inspectors, a project engineer, three radiation specialists, two physical security specialists, and a reactor inspector. The inspection identified two Green findings involving one non-cited violation and one violation for which the NRC exercised enforcement discretion. The significance of the findings is indicated by its color (Green, White, Yellow, Red) using IMC 0609 Significance Determination Process (SDP).
Findings for which the SDP does not apply are indicated by No Color or by the severity level of the applicable violation. The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described at its Reactor Oversight Process website at http://www.nrc.gov/NRR/OVERSIGHT/ASSESS/index.html.
A.
Inspector Identified Finding Cornerstone: Mitigating Systems
Green. The inspectors identified one non-cited violation evaluated as having very low safety significance (Green) for inadequate design control of the main feedwater pumps recirculation flow control valves logic. The licensee failed to implement proper design control through adequate testing of the digital control logic modification in order to fully understand the operation of the system. The design change to the circuit logic prevented the control room operators from having manual control of the valves which resulted in an automatic reactor trip. Post-modification testing did not identify the logic flaw in the recirculation valve controls.
The safety significance of the finding was very low because the reactor trip response and emergency feedwater system availability were unaffected by the design flaw in the circuit logic. (Section 1R14)
Enforcement Discretion. The inspectors identified a violation for failure to establish a fitness for duty procedure consistent with 10 CFR 26.24 requirements. Based on prompt corrective action, the apparent generic nature of the issue, and conflicting NRC guidance regarding the 10 CFR 26.24 requirements, the NRC has determined that the exercise of enforcement discretion is warranted in a
Inspection Report
Inservice Inspection
kV
kilovolt
LCO
Limiting Conditions for Operations
LER
Licensee Event Report
Loss of Coolant Accident
Licensed Operator Requalification
MWe
Megawatt - electric
Attachment
Motor Driven Emergency Feedwater
Main Feedwater
Maintenance Rule
Mechanical Stress Improvement Process
MWR
Maintenance Work Request
NCN
Nonconformance Notice
Non-Cited Violation
NI
Nuclear Instrumentation
NPF
Nuclear Power Facility [Type of license]
NRC
Nuclear Regulatory Commission
Office of Nuclear Reactor Regulation
Nuclear Steam Supply System
NRC Technical Report Designation
OS
Occupational Safety
Personnel Access Portal
Performance Indicator
Post Maintenance Testing
PTP
Preventive Test Procedure
PS
Public Safety
Primary Water Stress-Corrosion Cracking
QSP
Quality Systems Procedure
Reactor Building
RBCU
Reactor Building Cooling Unit
Radiation Control Area
RF
Refueling Outage
RII
Region II [NRC]
Radiation Work Permit
SCE&G
South Carolina Electric and Gas
Significance Determination Process
System Operating Procedure
Structures, Systems or Components
Surveillance Test Procedure
Tavg
Temperature - average
Turbine Building
TI
Temporary Instruction
TS
Technical Specification
TWR
Technical Work Record
Unresolved Item
Ultrasonic
Very High Radiation Area
Work Order
Attachment
List of Documents Reviewed
Section 1R04 - Equipment Alignment (71111.04)
Procedures
SOP-211, Emergency Feedwater System
SOP-306, Emergency Diesel Generator
SOP-307, Diesel Generator Fuel Oil System
SOP-505, Control Building Ventilation System
FSAR Sections 6.4.1, 8.3.1, 9.5.4, and 10.4.9
TS Sections 3.7.1.2, 3.7.6, and 3.8.1
D-302-085, Emergency Feedwater (Nuclear)
D-302-351, Diesel Generator - Fuel Oil
D-302-353, Diesel Generator - Miscellaneous Services
D-302-842, Chilled Water - To Cooling Coils
D-912-140, Control Room Normal and Emergency Air Handling System
Section 1R06 Flood Protection Measures (71111.06)
Corrective Action Reports
CERs 0-C-00-0875, 00-1386, 00-1825, 01-0936, 01-1332, 01-1914, 02-0567, 02-0568, 02-
0611, 02-0788, 02-0916, 02-1110, 02-1111, 02-1417, 02-0949, 02-1154, 02-1329, 02-1359,
and 02-1741.
Procedures
V. C. Summer Station Administrative Procedure SAP-107; 10CFR50.59 Review
Process, dated 5/8/01
V. C. Summer Emergency Operating Procedure EOP 17.1; Response to Reactor
Building Flooding, dated 11/17/94
V. C. Summer Engineering Services Procedure ES-425; Cumulative Effects Program,
dated 6/18/01
V. C. Summer Engineering Services Procedure ES-416; Design Modification Change
Process and Control, Revision 0
V. C. Summer Engineering Guideline EC-01; Design Input Development, dated 3/2/01
Other Documents
V. C. Summer Flood Calculation DC03290-002; Flooding Evaluation for all Areas not
Affected by the FW System, Revision 6
V. C. Summer Evaluation Request 21007, Service Water System Pressure, dated
2/14/86
Attachment
V. C. Summer TS 6.8.1, Procedures and Programs, Regulatory Guide 1.33," dated
4/11/02
V. C. Summer 50.59 Design Package Implementation MRF 31738 dated 11/14/84
Section 1R07 Heat Sink Performance (71111.07)
Corrective Action Reports
CERs 0-C-01-0788, 01-0144, 01-1788, and 02-2087.
Other Documents
V. C. Summer Calculation PGT-2001-1711, Evaluation of the V.C. Summer Reactor
Building Cooling Units Thermal Performance Test Tube Side Turbulent Flow
Requirements, Revision 0
V. C. Summer Calculation PGT-2002-1003, Evaluation of the V.C. Summer Reactor
Building Cooling Unit Cooling Water Flow Instrument Bias Uncertainty, Revision 0
V. C. Summer Preventive Test Procedure PTP-213.002; Service Water System Heat
Exchanger Data Collection, Revision 0
V. C. Summer Station Administrative Procedure SAP-1255; Service Watr System
Reliability Optimization Program, Revision 0
Sections 1R08.1 and 1RO8.2 - Inservice Inspection Activities (71111.08)
Procedures
Westinghouse Procedure MRS-SSP-1300, Field Service Procedure for Application of
the Mechanical Stress Improvement Process (MSIP)
Procedure, SCEG-UT-89-4, Ultrasonic Straight Beam Examination, Revision 2
Procedure, SCEG-UT-89-9, Manual Ultrasonic Examination of Vessel Welds Less Than
or Equal to 2 Inches, Revision 2
Procedure, SCEG-UT-89-10, Ultrasonic Examination of Class 1 and 2 Vessel Welds
Over 2 Inches Thick, Revision 2
Procedure, SCEG-UT-89-11, Manual Ultrasonic Examination of Ferritic Piping Welds,
Revision 0
Procedure, SCEG-UT-89-1, Manual Ultrasonic Examination of Austenitic Piping Welds,
Revision 0
Westinghouse Procedure, CGE-ISI-208, Remote Eddy Current Examination of Reactor
Vessel Nozzle to Pipe Welds Inside Surface for Virgil C. Summer, Revision 1
Westinghouse Procedure, CGE-ISI-254, Remote Ultrasonic Examination of Reactor
Vessel for Virgil C. Summer, Revision 2
Other Documents
Virgil C. Summer letter dated April 17, 2002, Inspection/MSIP Plan for VCSNS Hot Leg
Attachment
AEA Technology Engineering Services, MSIP Parameters for B and C Hot Leg Nozzles,
January 2002
Virgil C. Summer Special Report SPR 2000-005, Steam Generator Tube inspection
during Refueling Outage 12, dated November 8, 2000
Condition Evaluation Report (CER) 0-C-02-1067, Snubber functional test results within
degraded acceptance criteria
CER 0-C-02-1073, Excessive inspection failures on component cooling supports
requiring inspection scope expansion
CER 0-C-02-1078, Snubber piping attachment gap exceeded acceptance criteria
CER 0-C-02-1108, Rigid pipe support found misaligned
CER 0-C-02-1110, Rust and blistered paint identified during containment inspection
CER 0-C-02-1111, Elastomer cover over moisture barrier not properly adhering
CER 0-C-02-1181, Flow accelerated corrosion components turned over to QC without
proper preparation to allow inspection
CER 0-C-02-1267, As-found support hot measurement exceeded acceptance criteria
CER 0-C-02-1268, Drawing deficiency identified during snubber inspection
CER 0-C-02-1272, Snubber functional test results within degraded acceptance criteria
CER 0-C-02-1294, SG Blowdown piping snubber functional test results failed
acceptance criteria
CER 0-C-02-1296, Weld on component cooling heat exchanger did not meet
requirements
CER 0-C-02-1301, Weld on component cooling heat exchanger ready for QC fit up
inspection without proper preparation to allow inspection
CER 0-C-02-1308, Flaw identified in B hot leg nozzle weld during pre-MSIP WESDYNE
NDE activities
CER 0-C-02-1321, Welds turned over to QC without proper preparation to allow
inspection
CER 0-C-02-1328, Incorrect velocity slope line identified during snubber activation test
Section 2OS1 Access Controls to Radiologically Significant Areas (71121.01)
Procedures, Instructions, and Manuals
Health Physics Procedure (HPP), 157, Personnel Monitoring for Contamination,
Revision 9, 03/08/02
HPP-158, Contamination Control for Equipment and Materials, Revision 10, 12/18/01
HPP-160, Control and Posting of Radioactive Control Zones, Revision 10, 03/21/02
HPP-163, Qualification for the Use of Respiratory Protection Equipment, Revision 9,
01/09/01
HPP-302, Radiation and Contamination Survey Techniques, Revision 9, 06/23/98
HPP-401, Issuance, Termination and Use of RWPs and Standing RWPs, Revision14,
09/25/01
HPP-402, Radiological Survey Requirements and Controls for Reactor Building and
Incore Pit Entries, Revision 10, 06/20/00
HPP-403, Radiological Control for Nuclear Work Activities, Revision 8, 03/21/02
Attachment
HPP-405, Personnel Decontamination and Skin Dose Determination, Revision 14,
06/20/00
HPP-408, Fuel Movement Control, Revision 8, 08/09/99
HPP-410, Health Physics Routine Survey, Revision 8, 09/25/01
HPP-419, Electronic Dosimeter Alarm Setpoint, Revision 0, 10/31/01
Station Administrative Procedure (SAP) SAP-500 Health Physics Manual, Revision 11,
02/08/02
SAP-1167, NRC Performance Indicators, Revision 0
Radiation Work Permits (RWPs) reviewed and pre-job briefings attended
RWP 02-00045/001, Perform ISI to Include All Support Work (Insulation, Scaffold, Weld
Prep, Etc.)
RWP 02-00049/001, All Work Associated With Seal Table Thimble Cleaning to Include
Retracting Thimbles
RWP 02-00059/001, All Test Unit Activities Including STPs 215.008, 230.006A,B,C,D, &
E, All 250 Series, and Fire Service Testing
RWP 02-00063/001, All Work in the Pressurizer Cubicle to Include Manway
Removal/Replacement, PZR Safety, and Misc. Valve Work
RWP 02-00070/001, Reactor Head Work to Support Refueling
RWP 02-00071/001, RVLIS, CRDM Ductwork, NOZZLE Covers, NI Covers, Cavity Seal
Plate, Missile Shields, Detension, Tension Studs
RWP 02-00090/001, All Work Associated With Steam Generator Secondary Side
Inspections and Maintenance
Condition Evaluation Reports (CERs)
CER 0-C-02-1007, Individual was found to have trace amounts of radioactivity on his
pants and belt when he in-processed through dosimetry
CER 0-C-02-1010, During in-processing through Dosimetry, trace amounts of Co-60
and Co-58 on the lanyard
CER 0-C-02-1077, Low level radioactive material found on individuals lanyards when
in-processing through dosimetry
CER 0-C-02-1418, Low level radioactive material found at security portal
CER 0-C-02-1146, Low level radioactive material found upon exit count at the Whole
Body Count Room
Section 2OS2 As Low As Is Reasonably Achievable (71121.02)
Procedures, Instructions, and Manuals
Chemistry Procedure (CP), CP-614, Reactor Coolant Chemistry Control, Revision 11
CP-625, Degasification And Oxygenation of The Reactor Coolant System, Revision 8
HPP-150, Requirement For Issuance And Use of Personnel Dosimetry, Revision 8,
10/17/01
Attachment
HPP-151, Use of The Radiation Work Permit and Standing Radiation Work Permit,
Revision 8, 07/24/00
HPP-152, Radiation Control Area Access Control, Revision 8, 11/06/01
HPP-413, Diving Operations, Revision 2
HPP-719, Authorization and Control for Resin Transfer, Revision 4, 01/06/99
HPP-819, Temporary Shielding Evaluation, Installation, and Removal, Revision 11,
02/02/02
SAP-500, Health Physics Manual, Revision 11, 02/08/02
ALARA Packages /RWPs
02-0045, ISI-UT,PT, ETC. (MSIP not included)
02-0050, All Snubber Inspection
02-0053, MSIP (B&C Nozzle w / Spider Assembly Also) (Actual work not observed on
this RWP)
02-0059, All Test Group Work Except LLRT
02-0071, RVLIS, CRDM, Detension/Tension, Nozzle Covers Etc.
Miscellaneous Documents
Corporate ALARA Plan, Revision 10
FSAR Chapter 12 (Radiation Protection), Amendment 00-01, Dated 12/2000
Virgil C. Summer Nuclear Station, Health Physics and Radwaste Services, RF-12,
Outage Report
Attachment I, RF-12 Health Physics ALARA Report, A RCS Hot Leg Piping Inspection
and Repair
Virgil C. Summer Nuclear Station, RF-13 Outage, ALARA Plan, Issued 3/20/2002
QA-CHP-02-001, 2001 Annual ALARA Appraisal, February 7, 2002
Health Physics Field Operations, Self-Assessment Summary Report, QA-CHP-01-002,
Assessment Period, February 26 - March 2, 2001
VIRGIL C. SUMMER ALARA Action Plan, 4/01/2002
ALARA Committee Meeting Minutes, 1st QUARTER 2002, 02/05.02
ALARA Committee Job Review (pre-job), RWP 02-090, 05/7/02
Plan of the day schedule 05/06/02 (Outage Schedule)
Dose Printout by individual for Health Physics, Mechanical Maintenance, and Master-
Lee, 05/07/02
Condition Evaluation Reports (CERs)
CER 0-C-01-1901, Identified enhancements for ALARA program and ALARA Committee
CER 0-C-02-1169, CER written to formalize policy for ensuring ED alarms are
recognized when hearing protection is utilized consistent with the radiological hazards
that may be present
CER 0-C-02-1187, Electronic Dosimeter dose rate alarm-ED# 207401
CER 0-C-02-1241, Divers back pocket chamber was offscale when he exited the RCA
(Dose of less than 20 mrem estimated)
Attachment
CER 0-C-02-1273, Individual received electronic dosimeter dose rate alarm
CER 0-C-02-1315, Did not estimate man-rem for decon activity to support MSIP for
RWP 02-00043
CER 0-C-02-1388, Unnecessary exposure expended on attempts to repack XVG08085
CER 0-C-02-1416, Trace amounts of Co-58 on an exit count were not investigated in
accordance with guidance initiated for RF-13, but no procedure violation occurred
Section 2PS2 Radioactive Material Processing and Transportation (71122.02)
Procedures, Instructions, and Manuals
Engineering Services (ES) Procedure, ES-362, Radioactive Material Shipping
Inspection, Revision 7, 09/01/00
System Operating Procedure (SOP), SOP-108, Liquid Waste Processing System,
Revision 10, 03/12/99
HPP-703, Shipping Radioactive Material, Revision 13, 12/05/01
HPP-712, Classification of Radioactive Materials, Revision 9, 11/19/01
HPP-716.028, Transfer and De-watering Ion Exchange Resin and or Activated Charcoal
Filter Media Using the Scientific Ecology Group (SEG) Rapid De-watering System,
Revision 0, 12/09/99
HPP-716.029, 10-160B Cask Handling, Revision 0, 11/19/01
HPP-717, Sample Collection, Preparation and Analysis Techniques For Assuring
Compliance with 10 CFR Part 61, Revision 6, 12/09/99
SEG S.D.-P-03-046, Transfer and De-watering Ion Exchange Resin and or Activated
Charcoal Filter Media Using the SEG Rapid De-watering System, Revision 2, 11/22/93
Process Control Program-001, Process Control Program for Processing Wet Waste,
Revision 10, 03/12/99
Drawings
DURATEK Corporation Vendor Drawing DT-61, Radwaste Demineralizer Package
P&ID, Revision 2, 5/23/93
FSAR Figure 10.4-17, D302-362, Liquid Effluents from Nuclear Plant to Fairfield
Penstock, Revision 9, 08/01/96
FSAR Figure 11.2-2, Sheet 1, E-302-735, System Flow Diagram Waste Processing,
Revision 14, 01/19/01
FSAR Figure 11.2-2, Sheet 2, E-302-736, System Flow Diagram Waste Processing,
Revision 13, 09/13/97
FSAR Figure 11.2-2, Sheet 3, E-302-737, System Flow Diagram Waste Processing,
Revision 11, 10/11/01
FSAR Figure 11.2-2, Sheet 4, E-302-738, System Flow Diagram Waste Processing,
Revision 10, 12/19/01
FSAR Figure 11.2-2, Sheet 5, E-302-734, System Flow Diagram Waste Processing,
Revision 13, 03/05/01
Radioactive Shipment Documentation
Attachment
Virgil C. Summer 01-60, Radioactive Material, n.o.s, 7, UN2982,10-160 Poly HIC
Containing De-watered Bead Resin in 10 -160B Cask USA/9204/B(U)-85, 07/31/01
Virgil C. Summer 01-62, Radioactive Material, Type B(U) Package, Fissile Excepted, 7
UN2916, Ir-192 Radiography Source, 08/16/01
Virgil C. Summer 02-14, Radioactive Material, Type B(U) Package, 7, UN2916, Special
Form Ir-192, 03/06/02
Virgil C. Summer 02-20, Radioactive Material, Low Specific Activity (LSA), n.o.s., 7
UN2912, C-van Containing Dry Active Waste and One Liner of Charcoal Media,
03/26/02
Virgil C. Summer 02-31, Radioactive Material, Low Specific Activity, LSA, n.o.s, 7
UN9212, Contaminated Laundry and 2 boxes on Non Rad Modesty Clothing, 04/24/02
Virgil C. Summer 02-41, Radioactive Material, Surface Contaminated Object, SCO 7,
UN2913, Contaminated Equipment, 05/07/02
Miscellaneous Documents
Virgil C. Summer 1, FSAR, § 11, Radioactive Waste Management
Virgil C. Summer 10 CFR Part 61 Waste Stream Analysis Reports: (Primary Resin,
sampled 10/12/01; Nuclear Blow-down Resin, sampled 06/21/00; Reactor Coolant
Sample Filter, sampled 02/09/02; Seal Water Injection Filter, sampled 02/17/02; Spent
Fuel Pool Filter, sampled 02/20/02; Waste Water Charcoal Media, sampled 02/01/02;
Dry Active Waste, sampled 02/13/02; and Waste Water Resin, sampled 02/01/02)
Radioactive Shipment Record Log 2001 and 2002
Certificate of Compliance 9269, USA/9269/B(U)-85, Revision 3, Docket Number 71-
9269
Certificate of Compliance 9204, USA/9204/B(U)-85, Revision 7, Docket Number 71-
9204
Condition Evaluation Reports (CERs)
CER 0-C-01-2183, Unitech laundry truck arrived with tires unsuitable for radioactive
material transport, 11/27/01
CER 0-C-02-0281, Approximately 2000 gallons of Floor Drain Tank water was
inadvertently transferred to the Decon Pit Collection Tank, 02/07/02
CER 0-C-02-0570, Radiography source received in excess of site radiography license
limit, 03/08/02.
CER 0-C-02-1027, XDM-0040D vessel failure identified during resin reload, 04/19/02
CER 0-C-02-1030, XDM-0040A potential vessel failure identified during vessel reload,
04/18/02
CER 0-C-02-1213, Depleted demineralizers allowed chromated water to break through
to the floor drain while draining component cooling water in the Intermediate Building,
04/27/02
CER 0-C-02-1234, Chromated water observed being drained directly to floor drain
without being processed, 04/29/02
CER 0-C-02-1427, NRC inspectors identified need to procedurally control radioactive
shipment emergency and exclusive use instructions, 05/06/02
Attachment
CER 0-C-02-1423, Health physics did not adequately verify drivers qualification for
hauling hazardous material, 05/07/02
Sections 3PP1, 3PP2 - Access Authorization and Access Control (71130.01 and 71130.02)
Procedures
SAP-1005, Unescorted Access Authorization Program, Revision 7
SPP-210, Security Lock & Key Control, Revision 9
SPP-211, Security Key Card Control, Revision 7
SPP-224, Operational Testing of Security Access Control & Intrusion Detection System
Revision 4
SPP-228, Search Equipment Operational Test Procedure, Revision 4
SPP-213, Security Identification Badge Fabrication I Control, Revision 14
Fitness For Duty Procedure FFD-100, Revision 5, For Cause Testing Following
Accidents Involving Failures In Individual Performance Resulting In Personal Injury.
FFD-100, Revision 5, Attachment 1, Statement of Alcohol Consumption - Call In
FFD-100, Revision 5, Attachment 2, Change D, Emergency Recall Positive Result Form
FFD-100, Revision 5, Attachment 3, Change D, Request to Administer Drug/Alcohol
Test For Cause
Other Documents
Virgil C. Summer Physical Security Plan, Amendment 45
Virgil C. Summer Contingency Plan, Revision 10
Key and Lock Daily and Annual Inventory Logs
Semi-Annual Fitness for Duty Report, July - December, 2001