ML20135F175
| ML20135F175 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 03/05/1997 |
| From: | Brockman K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Ray H SOUTHERN CALIFORNIA EDISON CO. |
| References | |
| NUDOCS 9703110253 | |
| Download: ML20135F175 (30) | |
See also: IR 05000361/1996019
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NUCLEAR REGULATORY COMMISSION
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REGloN IV
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5 1997
Harold B. Ray, Executive Vice President
Southern California Edison Co.
San Onofre Nuclear Generating Station
P.O. Box 128
,
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San Clemente, California 92674-0128
SUBJECT:
MANAGEMENT MEETING SUMMARY
Dear Mr. Ray:
On February 27,1997, a management meeting was held with representatives of Southern
California Edison Company in the Region IV Office, Arlington, Texas, to discuss three
violations identified in NRC Inspecdon Report 50-361/96-19:50-362/96 19. This meeting
was held at the request of the licensee.
The licensee stated that they disagreed with the violations and plan to deny the violations
in their response to the Notice of Violation. The licensee presented the? reasons for
denying the violations.
The attendance list and the licensee's presentation are enclosed wi+h this summary
(Enclosures 1 and 2).
In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this
summary and its enclosures will be placed in the NRC Public Document Room.
Sincerely,
. w<
rd
enneth E. r ~ man, Acting Director
Division of Reactor Safety
Enclosures: As Stated
Docket Nos.: 50-361;50-362
cc w/ Enclosure 1:
Chairman, Board of Supervisors
County of San Diego
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1600 Pacific Highway, Room 335
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San Diego, California 92101
9703110253 970305
ADOCK 05000361
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Southern California Edison Co.
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Alan R. Watts, Esq.
Woodruff, Spradlin & Smart
701 S. Parker St. Suite 7000
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Orange, California 92868-4720
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Sherwin Harris, Resource Project Manager
Public Utilities Department
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City of Riverside
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3900 Main Street
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Riverside, California 92522
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R. W. Krieger, Vice President
Southern California Edison Company
San Onofre Nuclear Generating Station
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P.O. Box 128
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San Clemente, California 92674-0128
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Dr. Harvey Collins, Chief
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Division of Drinking Water and
Environmental Management
California Department of Health Services
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P.O. Box 942732
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Sacramento, California 94234-7320
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Terry Winter, Manager
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Power Operations
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San Diego Gas & Electric Company
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P.O. Box 1831
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San Diego, California 92112
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Mr. Steve Hsu
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Radiological Health Branch
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State Department of Health Services
P.O. Box 942732
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Sacramento, California 94234
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Mayor
City of San Clemente
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100 Avenida Presidio
San Clemente, California 92672
Mr. Truman Burns \\Mr. Robert Kinosian
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California Public Utilities Commission
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505 Van Ness, Rm. 4102
San Francisco, California 94102
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E-Mail report to NRR Event Tracking System (IPAS)
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Regional Administrator
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DRP Director
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Senior Project inspector (DRP/F, WCFO)
RIV File
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Branch Chief (DRP/TSS)
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Leah Tremper (OC/LFDCB, MS: TWFN 9E10)
WCFO File
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DOCUMENT NAME: R:\\_SO23\\SC619MS.MPS
To receive copy of document, indicate in box: "C" = Copy without enclosures
"E" = Copy with enclosures "N" = No copy
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bec distrib. by RIV w/Enclosurcs 1 and 2:
Regional Administrator
Resident inspector
DRP Director
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Branch Chief (DRP/F, WCFO)
MIS System
Senior Project inspector (DRP/F, 'NCFO)
RIV File
Branch Chief (DRP/TSS)
M. Hammond (PAO, WCFO)
Leah Tremper (OC/LFDCB, MS: TWFN 9E10)
WCFO File
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DOCUMENT NAME: R:\\_SO23\\SO619MS.MPS
To receive copy of document, indicate in box: "C" = Copy without enclosures "E" = Copy with enclosures "N" = No copy
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ENCLOSURE 1
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MEETING:
SAN ONOFRE NUCLEAR GENERATING STATION
SUBJECT:
DISCUSS THREE RADIATION PROTECTION VIOLATIONS
IDENTIFIED IN INSPECTION REPORT 96-19
DATE:
FEBRUARY 27, 1997, AT 1:00 p.m.
AlIENDANCE LIST
(PLEASE PRINT CLEARLY)
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NAME
ORGANIZATION
POSITION TITLE
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ENCLOSURE 2
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NRC INSPECTION REPORT 96-19
EDISON IMPLEMENTATION OF HEALTH PHYSICS
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PROGRAMS
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EDISON /NRC CONFERENCE - FEBRUARY 27,1997
SAN ONOFRE NUCLEAR GENERATING STATION
2
UNITS 2 & 3
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02/27/97
PAGE1
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AGENDA
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INTRODUCTION
R. W. KRIEGER
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DISCUSSION OF PROPOSED
J. A. MADIGAN
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VIOLATIONS
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OVERALL CONCLUSION
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PAGE 2
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INTRODUCTION
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Edison does not believe that the cited examples violate
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regulatory requirements.
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Edison does not bslieve that any of the examples cited
provide a basis to question Edison's station's
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attentiveness or to have a heightened concern with our
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radioactive material control program.
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02/27/97
PAGE 3
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Violation A
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" Procedure SO123-Vil-20.11, " Access Control Program,"
Revision 3, states that individuals shall read, understand, and
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comply with the reqttirements listed on the Radiation Exposure
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Permit, on radiological postings, and on health physics field
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instructions."
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" Contrary to the above, between December 16-20,1996, the
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inspectors discussed radiological work conditions with workers
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authorized to perform work in the containment building and
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determined that: (1) none of the workers knew the area
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contamination levels in their work areas, (2) some were not
aware that they were working in a posted airborne area, and (3)
none knew the airborne concentration levels."
02/27/97
PAGE 4
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Worker Knowledge Requirement:
10CFR19.12, Instruction to Workers, states, in part:
"(a) All individuals who in the course of employment are likely to
receive in a year an occupational dose in excess of 100 mrem
(1mSv) shall be... Instructed in the health protection problems
associated with exposure to radiation and/or radioactive
,
materials, in precautions or procedures to minimize exposure,
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and in the purposes and functions of protective devices
[
employed... The extent of these instructions must be
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commensurate with potential radiological health protection
problems present in the work place."
02/27/97
PAGE5
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Worker Knowledge Program:
Workers informed of prevailing radiological conditions commensurate
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with actu'ai radiological hazards (SO123-20.10.1; REP Program).
Informed via pre-job briefings and radiation exposure permits (REP)
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REP defines radiological conditions as Airborne Area, Contamination
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Area, and Radiation Area.
Workers need to know requirements / controls specified by HP.
Workers not required to memorize /know actual levels
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Quantitative contamination levels provide little protective value
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Extraneous information minimized to avoid information
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overload
Programmatically, pre-posting areas during the shift is an acceptable
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practice.
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02/27/97
PAGE 6
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Worker Knowledge Compliance:
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Workers demonstrated compliance by proper actions
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- Dosimetry use
- Protective clothing
- Jobsite behavior
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Demonstrated compliance by performance measures
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- Person-REM accumulation
- External contamination events
- Internal contamination events
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02/27/97
PAGE 7
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Worker Knowledge Compliance (Continued):
Nuclear Oversight observations concluded satisfactory
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level of performance.
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NRC Regulations / Edison Program does not require
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knowing quantitative contamination / airborne levels.
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No airborne posting conditions / requirements existed at
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time of inspection.
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PAGE 8
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Summary:
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Edison did not violate 10 CFR 19.12
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Consistent with other nuclear facilities, Edison requires
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instructions to workers commensurate with the
potential radiological conditions and worker's ability to
minimize exposure.
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Edison did not violate TS 5.5.1 - workers complied with
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Procedure SO123-Vil-20.11.
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Conclusion:
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There is no basis for this violation, and it should be
retracted.
02/27/97
PAGE 9
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Violation B
" Procedure SO123-Vil-20.9.2, " Material Release Surveys,"
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Revision 1, states that site workers are responsible for
presenting all items to health physics for removal from a
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radiological controlled area / radioactive materials area
(RCA/RMA) and that health physics divisional personnel are
responsible for performing surveys in accordance with this
procedure to ensure that no licensed material is
released from an RCA/RMA."
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" Contrary to the above, between August 1995 and December
16,1995, the licensee identified 23 radioactive materials outside
of the radiological controlled area. Seven of these items were
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identified with magenta paint or radioactive material tape."
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02/27tV
PAGE to
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Material Release Requirements:
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"No license to transfer radioactive material; continuous control
required." (10 CFR 30.3)
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... guidance is needed which will provide reasonable assurance
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that contaminated materials are properly controlled and
dispersed of while at the same time providing a practical method
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for the uncontrolled release of materials from the restricted
area... Items and material should not be removed from the
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restricted area until they have been surveyed or evaluated for
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potential radioactive contamination...." (IE Circular 81-07)
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Material Release Program:
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SO123-Vil-20, Health Physics Program Description.
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SO123-V11-20.9.2
Describes survey methods & criteria for removal of
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materials from RCA and Radioactive Materials Area
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(RMA) to preclude release of licensed radioactive
materials to unrestricted area.
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Program based on IE Circular 81-07.
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PAGE 12
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Material Release Program (Continued):
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Two-tier program
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Radioactive material outside RCA/within RA is not
prohibited.
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Program is designed to minimize the amount of
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radioactive material in the restricted area.
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02/27/97
PAGE 13
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SONGS TWO-TIER RADIOLOGICAL CONTROL PROGRAM
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UNRESTRICTED
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AREA (Owner
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Controled Area)
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RESTRICTED;-
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AREA (Protected drea)
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2/27/97
Page 14
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Material Release Compliance:
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23 items identified / tracked by licensee, including four with
magenta markings.
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All 23 items were maintained within restricted area.
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6 of 23 items represent survey deficiencies
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- Adequate / timely corrective actions
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- No recurrence
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Extremely low rate of survey deficiencies (6 out of thousands of
material release surveys).
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23 licensee identified items represent low radioactive material
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hazard.
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02127/97
PAGE 15
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Table 1: Raciiological Observation Report (ROR) Categorization
(Seventeen month period 8/95 to 12/96)
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FIXED
LOOSE
CATEGORY
ROR#
DESCRIPTION
CPM
in Accordance with
95197
Portable heater
SAM-9 only (8nCQ
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Material Release
Program (1)
96011
Pigtail Electric Cord
SAM-9 only (3nCQ
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96020
Concrete Floor Plug
200
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95211
Extension Cord
150
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95201
Hose
300
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95191
Blowdown System Valve
300
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95189
Pipe Support bracket from U3 Outfall
150
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96021
Hose reducer, from U1 Intake Area
1,800
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95210
Plywood
400-600
80-100
95188
Packing gland Main Steam Trap Bypass Valve
500
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96046
Covers on U1 Gantry Crane (5 items)
300-500
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96019
Inside wooden REMS box
4,000
3,000
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95186
Blowdown System valve
500
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Survey Deficiency
96016
3" pipes with contamination inside (3 items)
100-300
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(2)
96031
Wrench in tool room with magenta paint
700
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96010
Wood Pallet
300
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95190
Gas Bottle
1,200
2,000
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02/27/97
PAGE 16
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Table 1: Radiological Observation Report (ROR) Categorization
(Seventeen month period 8/95 to 12/96)
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(1)
Seventeen of the 23 items (13 of the 17 RORs) were handled in accordance with
Edison's material release program
One item with radioactive tape which should have been removed during the
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release survey.
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Some items represented very low levels of fixed contamination, indicating
differences in instrument sensitivity (portable frisker probes vs. a stationary box
contamination monitor), or a difference in detection sensitivity due to background
radiation levels which normally approximate 100 to 200 cpm at various RCA
boundaries.
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Some items were located in secondary plant systems and/or in HP controlled
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locations in the Restricted Area in accordance with the Material Release
Procedure.
(2)
Six of the 23 items represented survey deficiencies. This equates to four out of the
referenced 17 RORs.
02/27/97
PAGE 17
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Summary:
All 23 items remained inside the Restricted area.
Extremely low rate of survey deficiencies (6 items out of thousands of
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material release surveys).
Four instances (six of the 23 cited items) involved deficient surveys
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- Adequate / timely corrective actions
- No recurrence
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SONGS two-tiered release program, and proactive practice of
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documenting and investigating each occurrence, demonstrated
commitment and diligence to identify and properly capture lessons
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learned from each event.
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02/27/97
PAGE 18
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Conclusion:
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These survey deficiencies:
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1) Represent isolated / unrelated failures to properly
survey;
2) Represent minor survey deficiencies beyond
regulatory requirements; and
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Should not be cited
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02/27/97
PAGE 19
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Violation C
"10 CFR 20.1904(a) requires that the licensee ensure that each
container of licensed material bears a durable, clearly visible label
bearing the radiation symbol and the words " CAUTION RADIOACTIVE
MATERIAL," or " DANGER, RADIOACTIVE MATERIAL." The label
must also provide sufficient inforroation (such as the radionuclides
present, an estimate of the quantity of radioactivity, the date for which
the activity is estimated. radiation levels, kinds of materials, and mass
enrichment) to permit individuals handling or using the containers, or
working in the vicinity of the containers, to take precautions to avoid or
minimize exposures."
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" Contrary to the above, on December 18,1996, the inspectors
identified six sealed cloth radioactive material bags (which contained
eddy current probe pushers) that were not properly labeled."
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02/27/97
PAGE 20
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Labeling Requirement:
20.1904(a), "The licensee shall ensure that each container of
licensed material bears a durable, clearly visible label bearing
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the radiation symbol and the words ' CAUTION, RADIOACTIVE
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MATERIAL', or ' DANGER, RADIOACTIVE MATERIAL.' The
label must also provide sufficient information (such as the
radionuclide(s) present, and estimate of the" quantity)of
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radioactivity, the date for which the activity is estimated,
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(radiation levels; kinds of materials, and mass enrichment) to
permit individuals handling or using the containers, or working in
the vicinity of the containers, to take precautions to avoid or
minimize exposures."
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02/27/97
PAGE 21
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Labeling Program:
SO123-Vil-8.1.14 states that "This procedure provides guidance to
ensure that labels provide sufficient information to permit
individuals handling or using these containers, or working in the
vicinity, to take precautions to avoid or minimize their exposure."
Ensures all the information necessary to enable safe radioactive
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material handling and ALARA.
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If contents not significantly different than area ambient conditions,
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additional information is not required.
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Program based on NUREG/CR-5569 and NUREG/CR-6204:
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Q&A 127, HPPOS #27/28 which states in part, "It must be
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emphasized to the licensee that the purpose of
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10CFR20.203(f) (and 10CFR20.1904) is to ensure adequate
information is available to workers to enable them to safely
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handle radioactive materials and minimize exposure."
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02/27/97
PAGE 22
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Labeling Compliance:
Procedure compliance
Performance Indicators
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Person-REM accumulation
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External contamination events
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Internal contamination events
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Routine HP Surveys
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Station Oversight
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HP management oversight
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Nuclear Oversight Division
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Leadership Observation Program
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O2/27/97
PAGE 23
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Labeling Compliance (Continued):
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Event Compliance
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Each bag adequately labeled with tri-foil" Caution Radioactive
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Materials"
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Additional Information unnecessary
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Contents posed no significant hazard compared to area
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radiation / contamination levels
Significance equal to worker behavior changes
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Program requires additional information when needed to take
precautions to avoid / minimize exposure and safely handle
radioactive materials.
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02/2W97
PAGE 24
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.
.
..
.
.
!
Summary:
Edison's container labeling program is consistent with
.
.
regulatory requirements.
Additional information required only when increased
.
hazard is present.
Conclusion:
j
4
Edison did not violate 10CFR20.1904(a) because
.
adequate information was provided to workers.
!
.
.
i
I
!
!
02/27/97
PAGE 25
-- 9
n
-
-
.
- - - -
- - - _ _
.
.
.
.
_.
,
Overall Conclusions
Edison has a very conservative well managed radioactive
!
e
material control program which provides significant
defense in depth well beyond regulatory requirements.
i
e
There is no bases for violations A and C, and Edison
requests that they be retracted.
Violations B represents isolated / unrelated failures to
properly survey which represent minor procedural
.
deficiencies beyond regulatory requirements and should
not be cited.
e
There is no bases for questioning the attentiveness of the
staf or the effectiveness of our corrective actions or
radiation control program.
i
02/27/97
PAGE 26
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