ML18152A285
| ML18152A285 | |
| Person / Time | |
|---|---|
| Site: | Surry |
| Issue date: | 05/03/1988 |
| From: | Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Cruden D VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| References | |
| NUDOCS 8805100186 | |
| Download: ML18152A285 (46) | |
See also: IR 05000280/1988010
Text
Docket Nos. 50-280, 50-281
MAV O 3 \\988
Virginia Electric and Power Company
ATTN:
Mr. D. S. Cruden, V"ice President,
Nuclear Operations
P. 0. Box 26666
Richmond, VA
23261
Gentlemen:
SUBJECT:
ENFORCEMENT CONFERENCE SUMMARY
(NRC INSPECTION REPORT NOS. 50-280/88-10 AND 50-281/88-10)
off; t I 8)
This 1 etter refers to the Enforcement Conference held at our request on
April 21, 1988.
This meeting concerned activities authorized for your Surry
facility.
The issues discussed at this conference related to the findings of
the investigative task force formed to review the incore detector maintenance
radiation exposure event of March 3, 1988, and the subsequent corrective
actions in response to Inspection Report Nos. 50-280/88-10 and 50-281/88-10.
A
summary, a list of attendees, and a copy of your handout are enclosed .
It is our opinion that this meeting was beneficial and has provided a better
understanding of the inspection findings, the enforcement issues, and the
status of your corrective actions.
We are continuing our review of these
issues to determine the appropriate enforcement action.
In accordance with Section 2.790 of the NRC
1s
11Rules of Practice,
11 Part 2,
Title 10, Code of Federal Regulations, a copy of this letter and its enclosures
will be placed in the NRC Public Document Room.
Should you have any questions concerning this matter, please contact us.
Enclosures:
1.
Enforcement Conference Summary
2.
List of Attendees
3.
Handout
cc w/encls:
(See page 2)
Sincerely,
J. Nelson Grace
Regional Administrator
8805100186 880503
ADOCK 05000280
Q
J:.fOi
Virginia Electric and Power Company
2
cc w/encls:
D. L. Benson, Station Manager
N. E. Hardwick, Manager - Nuclear
Programs and Licensing
bee w/encls:
NRC Resident Inspector
DRS Technical Assistant
Document Control Desk
J. Lieberman, DOE
G. Jenkins, EICS
Commonwealth of Virginia
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ENCLOSURE 1
Enforcement Conference Summary
Licensee:
Virginia Electric and Power Company
Facility:
Surry
Docket Nos.:
50-280, 50-281
License Nos.:
Subject:
Corrective Actions Regarding Inspection Report Nos. 50-280/88-10 and
50-281/88-10 and Findings of the Investigative Task Force Formed to
Review the Incore Detector Maintenance Radiation Exposure Event
An Enforcement Conference was held at the Region II office on April 21, 1988,
to discuss the findings identified in Inspection Report Nos. 50-280/88-10 and
50-281/88-10 and the results of the licensee's investigation of the incident
and review the corrective actions taken as a result .
Licensee representatives discussed the sequence of events surrounding the
incore detector exposure incident of March 3, 1988.
A summary of the licensee's
investigative team findings was presented including calculated estimates of the
whole body and extremity doses received by each of the three individuals
involved.
Whole body doses ranged from 707 to 1,033 millirem and extremity
doses from 996 to 1,267 millirem.
The licensee presented the basis for their
calculations, their assessment of the root cause of the problem and their short
and long term corrective actions.
The lack of awareness on the part of licensee
personnel involved that the detector drive cable could become activated and
cause high radiation levels was identified as the root cause.
NRC representatives discussed the breakdown of the licensee's system, including -
management review, which had been implemented to prevent such occurrences.
Other items discussed included an apparent lack of procedural compliance on the
part of the workers, adequacy of the procedure used to free the detector, and
the licensee determination of the actual root cause of the problem.
The
Regional Administrator made the point that it was fortuitous that apparently no
exposures in excess of NRC limits had occurred .
\\ .. I
ENCLOSURE 2
Enforcement Conference Attendees
Virginia Electric and Power Company
W. Bartlett, Senior Staff Health Physicist, Corporate
R. Berryman, Manager, Nuclear Analysis and Fuel, Corporate
D. Cruden, Vice President, Nuclear
E. Grecheck, Assistant Station Manager, Surry
N. Hardwick, Manager, Nuclear Power and Licensing, Corporate
J. Hegner, System Engineer, Corporate
G. Pannell, Director, SEC
S. Sarver, Superintendent, Health Physics, Surry
R. Thomas, Senior Staff Engineer, Corporate
F. Thomasson, Supervisor, Health Physics, Corporate
Nuclear Regulatory Commission
C. Bassett, Radiation Specialist, Division of Radiation Safety and Safeguards
(DRSS)
F. Cantrell, Section Chief, Division of Reactor Projects (DRP)
D. Collins, Branch Chief, DRSS
0. DeMiranda, Enforcement Specialist, Enforcement and Investigation
Coordination Staff (EICS)
J. Grace, Regional Administrator
C. Hehl, Deputy Director, DRP
W. Holland, Senior Resident Inspector, Surry
C. Hosey, Section Chief, DRSS
G. Jenkins, Director, EICS
T. MacArthur~*Reactor Inspector, Technical Support Staff (TSS)
C. Patel, Project Manager, Surry, Office of Nuclear Reactor Regulation (NRR)
W. Rankin, Technical Assistant, DRSS
M. Scott, Project Engineer, DRP
L. Slack, Enforcement Specialist, EICS
B. Wilson, Branch Chief, DRP
INCORE DETECTOR MAINTENANCE
RADIATION EXPOSURE EVENT
NRCENFORCEMENTCONFERENCE
APRIL 21, 1988
/
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R.M. BERRYMAN
Manager
- Investigative Task Force
-~
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- DEMONSTRATE THE SEQUENCE OF EVENTS
BY PRESENTING A VIDEOTAPE REENACTMENT
- SUMMARIZE INVESTIGATION FINDINGS
- IDENTIFY CORRECTIVE ACTIONS
- MEASURES NEUTRON FLUX DISTRIBUTION AT
SELECTED LOCATIONS WITHIN REACTOR CORE
- FIVE MOVABLE DETECTORS ARE AVAILABLE TO
SCAN THE LENGTH OF FIFTY SELECTED FUEL
ASSEMBLIES
Reactor
Vessel
Seal
Table
5-Path
Transfer Devices
t
10-Path
Transfer Devices
l
Limit
Switch
i
Crane
Wall
Containment
Wall~
Drive
Box
J
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Crane Wall~
......
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CM.IIIIA TIIJH TUI£
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Inserted/Withdrawn Limit
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Switch
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10-Path
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k-1
Concrete
Storage
Area
IN-CORE NEUTRON
DETECTION SUBSYSTEM
I .
FISSION
CHAMBER
.........
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l'ELEFLEX
I
CABLE~
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Fission Chamber and Drive Cable Schematic
HARO LINE
CABLE
MICRODOT
CONNECTOR
-.. -- -----------
STORAGE
LOCATI~
1
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Table
Plan View - Incore Detector Qrive System
10-Path
Transfer Devices
i
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Transfer Devices
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THEAMOC:ou,L.E
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,ORT COLUMN
SOCKET PLANGE*
VESSEL SEAL LINE
D"IVE MECHANISM
THUIMOCOUl'LI CONDUIT
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UPPIR
SUPPORT
PU.Tl
SUPf'ORT COLUMN ~~to..1....ll
THEAMOCOI.WLI CONDUIT
AT COLUMNS AND MIXING
DEVICI
TOP o, ACTIVE ,uEL
CORE S\\m'ORT ........_
COLUMN
'
INSTRUMENT THIMaLI
GUIDI
VESSEL 'ENETflATION
TUH
THIMBLE GUIDE TUBE
TO VESSEL WELD JOINT
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y
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THIMaLI GUIDI
TUH MOUNT
THIMBLE GUIDE-*
TUBE W!L.D
UNION
Elevation View - Incore Detector Drive System
FEB 8, 1988
"A" INCORE DETECTOR STUCK
MARCH 3, 1988
CONTAINMENT ENTRY TO FREE AND REPLACE DETECTOR
(2 INST. TECHS. AND 1 HP TECH)
DETECTOR MANUALLY WITHDRAWN WHEN ATTEMPT
TO DRIVE ELECTRICALLY FAILED
WORK TERMINATED BY HP TECH WHEN HIGH RADIATION
LEVELS WERE DETECTED
MARCH 8,.1988
EVALUATIONS IDENTIFY THE PRIMARY SOURCE
. OF RADIATION TO BE ACTIVATED CABLE
MARCH 9, 1988
RECOVERY ACTIONS COMPLETED
MARCH 11, 1988
INVESTIGATION TASK FORCE APPOINTED
..
."
..
- SOURCE OF RADIATION IN WORK AREA
- WHOLE BODY AND EXTREMITY RADIATION DOSES
- ROOT CAUSE OF THE EVENT
- OTHER CAUSAL FACTORS LEADING TO
THE OCCURRENCE
-~
PRIMARY SOURCE OF RADIATION WAS THE CARBON STEEL DRIVE
CABLE WHICH HAD BECOME HIGHLY ACTIVATED
"A" DETECTOR WAS STUCK IN CORE LOCATION J5 APPROXIMATELY
55 INCHES INTO THE ACTIVE FUEL REGION FOR 26 DAYS
CAUSE OF THE STUCK DETECTOR WAS MISALIGNMENT OF THE
"B" TEN PATH TRANSFER DEVICE
RESULTS OF SURVEY MEASUREMENTS WERE USED TO ESTABLISH
THE FINAL POSITION OF THE DETECTOR AND ACTIVATED CABLE
.... . ..
. . . . .
.
. . ...
. .
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W. T. Bartlett, Ph.D
RADIATION DOSE ASSESSMENT
- MEDICAL EXAMINATION AND FOLLOWUP
- DETERMINE WHOLE BODY AND EXTREMITY DOSES
- WORST CASE SCENARIOS
- EXPERT REVIEW
- NON - UNIFORM EXPOSURE
- * EXTREMITY DOSE
)
' .*.
- POTENTIAL CONT ACT WITH ACTIVATED CABLE
- ISOTOPE OF CONCERN: Mn - 56 -
- SKIN REACTIONS
- BETA ATTENU.ATION
- MAX RANGE MN-56 BETAs
- ERVTHEMA THRESHOLD
2
112 MG/CM
1400 MG/CM 2
150~400 RAD
- COMPANY PHYSICIAN ( MARCH 10, 1988)
- HISTORY/BIOLOGICAL SYSTEMS
- PHYSICAL EXAM {HANDS)
- LABORATORY
- NO EVIDENCE OF RADIATION INJURY
- .FOLLOWUP
- - PERIODIC VISUAL EXAM (3 WEEKS)
- BLOOD ANAL VSES
- ASYMPTOMATIC
- VERIFIED BY INTERVIEW
- NO EVIDENCE OF CABLE CONTACT
' .*
- BASED ON MOCKUP REENACTME*NT, POSITIONING
OF PERSONNEL WAS ESTABLISHED
- SOU.ACE POSITION AND ACTIVITY
- RELATE SURVEY MEASUREMENTS
- ,-
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RAO l AT ION
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Table
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10-Path
Transfer Devices
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Transfer Devices
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Crane f
Wall
Driv1
its
!-
,.
Relative Positions of Individuals During Incident
Five Path
Transfer
Device
Crane Wall _/
Take up Reel -1'
Activated portion of cable is shown by the hash marks
..
HP Technician
Technician No. 1
Technician No. 2
Knee * 18 inches
Shin
13 inches
UpperArm
17inches
Forearm
17 inches
Knee . 23 inches
Shin
20 inches
- *
-~
.
MOVING LINE SOURCE
RATE OF MOVING
TUBE CASING
- Mn-56 DOMINANT ISOTOPE (208 Ci)
- DETECTOR (16.6 Ci)
- 55 INCH LENGTH
I
.
I
- -
©/A\\[L©(U)[LfA\\ YD@~
- LINE SOURCE EQUATION
- INTEGRAL OF VELOCITY {Chabot)
- NUMERICAL ANAL VSIS (VP)
- RATIO TLD TO BODY PARTS
1388
I
Unshielded Cable
mR/sec
12 inches
I
1388
Shielded Cable
mR/sec
12 inches
I
Whole Body Dose
Measured Calculated
HP Technician
240
707
Tech. No. 1
538
347
958
Tech. No. 2 *
555
1033
Extremity
Calculated
1217
996
1267
.
- *
- *
- CONSISTENT WITH SOURCE ACTIVITY
- FINAL CABLE POSITION IN DRIVE BOX
WW@[rulf ©£~ ©~~£[ruQ@
©£[ID~~ @~ [F)@@~
- 207 Ci Mn-56 CIRCULAR SOURCE
Dose Rate
255 mR/sec 170 mR/sec
73 mR/sec
Distance
1 Foot
2 Feet*
3 Feet
. * . *~
- NO SIGNIFICANT HAND DOSE *
- NO QUARTERL V LIMITS EXCEEDED
- UNIQUE SOURCE & GEOMETRY FOR DOSIMETRY
- MEASUREMENTS
- EXPERT CONCURRENCE
. '.
R.M.BERRYMAN
Manager
Investigative Task Force
.*
.
w
- PERSONNEL WERE UNAWARE OF THE POTENTIAL
THAT THE DRIVE CABLE COULD BE HIGHLY
RADIOACTIVE
- LACK OF AWARENESS ATTRIBUTED TO:
- P.REVIOUS EXPERIENCE WITH DETECTOR REPLACEMENTS
- NOT INCLUDED IN TRAINING (NO GENERIC INDUSTRY
INFORMATION HAD IDENTIFIED THE PROBLEM)
- INADEQUATE HEALTH PHYSICS INVOLVEMENT IN PRE-JOB PLANNING
-- HEAL TH PHYSICS PERSONNEL NOT INCLUDED IN PRE-JOB
BRIEFING HELD BY INSTRUMENT DEPARTMENT
- INSTRUMENT DEPARTMENT CONTINUED WORK ONCE UNANTICIPATED
CONDITIONS DEVELOPED
--
ACTION TAKEN TO FULLY WITHDRAW THE DETECTOR BY HAND
WAS NOT INCLUDED IN THE APPROVED PROCEDURE
--
HEALTH PHYSICS WAS NOT MADE AWARE OF THE ACTION TAKEN
I,,
E. S. GRECHECK
ASSISTANT STATION MANAGER
SURRY POWER STATION
..
©©~~~©WOW~ £©WO@~
. (Implementation Dates)
- INFORM NUCLEAR INDUSTRY AND APPROPRIATE STATION
PERSONNEL OF THE HIGH DOSE RATES POSSIBLE FROM AN
INCORE DETECTOR AND ACTIVATED DRIVE CABLE
- INITIAL NETWORK ENTRY (Completed)
- FINAL TASK FORCE REPORT (April 1988)
- . FINAL NETWORK ENTRY (May 1988)
- INPO RADIATION PROTECTION WORKSHOP (June 1988)
- DISTRIBUTE TRAINING VIDEOTAPE TO INDUSTRY (June 1988)
'r
©@~~~©LFO\\\\l~ £©1FO@WJ~ 1©@WJ()lf>>
(Implementation Oates)
- MODIFY APPROPRIATE TRAINING PROGRAMS TO INCLUDE
LESSONS LEARNED
- *DETERMINE ENHANCEMENTS AND DEVELOP
. * ACTION PLAN TO REVISE INSTRUMENT *
AND HEAL TH PHYSICS TECHNICIAN TRAINING
- . PROGRAMS (May 1988)
.
' .
©@OOOO~©lfOW~ IA\\©lfO@~ 1©@~
0lf>>
(Implementation Dates)
- MODIFY PROCEDURES USED TO OPERATE OR MAINTAIN THE
INCORE DETECTOR SYSTEM TO INCLUDE ADEQUATE PRECAUTIONS
AND INSTRUCTIONS WITH REGARD TO IRRADIATED DETECTORS
AND DRIVE CABLE
- SNSOC PRE-APPROVAL OF INCORE DETECTOR
. * SYSTEM MAINTENANCE ACTIVITIES (Completed)
- REVISE MAINTENANCE PROCEDURES (July 1988)
i
©@[ru[ru~©tYOW~ £©1YO@~© 1©@~
0tf>>
(Implementation Dates)
- EMPHASIZE THE IMPORTANCE OF STOPPING WORK AND
EVALUATING THE SITUATION WHENEVER UNANTICIPATED
CONDITIONS ARISE (Completed)
- ENHANCE HEAL TH PHYSICS INVOLVEMENT IN WORK PLANNING
- INCREASE CONTROLS REGARDING SUBATMOSPHERIC
CONTAINMENT ENTRIES (Completed)
©@~©[s(Ll)~D@~~
- NO EXPOSURE If~ EXCESS OF REGULATORY
LIMITS OCCURRED
- THE POTENTIAL FOR AN EXPOSURE IN EXCESS OF
REGULATORY LIMITS WAS LIMITED BY:
- CONSERVATIVE ACTIONS BY THE INSTRUMENT TECHNICIANS
- TIMELY RESPONSE BY THE HEAL TH PHYSICS TECHNICIAN
- PRE-JOB ACTIVITIES CAN AND WILL BE IMPROVED
- INFORMATION REGARDING THIS TYPE OF EVENT
WILL BE DISSEMINATED THROUGHOUT INDUSTRY
-
.
'*
,. *