05000271/LER-1991-001, :on 910104,radiation Protection (RP) Technician Entered Posted High Radiation Area W/O Dose Rate Monitoring Device Due to Personnel Error.Technician Relieved of Further RP Duties
| ML20028H750 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 01/23/1991 |
| From: | Reid D VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LER-91-001, LER-91-1, VYV-91-018, VYV-91-18, NUDOCS 9101290360 | |
| Download: ML20028H750 (4) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(ii) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(x) |
| 2711991001R00 - NRC Website | |
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VERMONT YANKEm NUCLEAR POWER CORPORATION l
P. O. BOX 157 GOVERNOR HUNT ROAD VERNON, VERMONT 05354 January 23, 1991 VYV W91-018 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555
REFERENCE:
Operating License DPR-28 Docket No. 50-271 Reportable Occurrence No. LER 91-01
Dear Sirs:
As defined by 10 CFR 50.73, we are reporting the attached Reportable Occurrence as LER 91-01.
Very truly yours, VERMONT YANKEE NUCLEAR POWER CORPORATION A <~
Donald A. Reid Plant Manager cc:
Regional Administrator USNRC Region I 475 Allendale Road King-of Prussia, PA 19406 9101290360 910123 PDR ADOCK 05000271
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_m WRC Form 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED OMS NO.3150-0104 (6-89)
EXPIRES 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTION REQUEST:
50.0 HRS. FORWARD COMMENTS REGARDING LICENSEE EVENT REPORT (LER)
BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P-530), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (3160-0104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20603.
FACILITY NAME ( )
DOCKET NO.
8)
PAGE (8)
O l 5 l 0 l 0 l(0 l 2 l 7 l 1 0 l 1 l 0F l 013 VERMONT YANKEE NUCLEAR POWER STATION TITLE (*) Entry Into.A High Radiation Area By A Radiation Protection Technician Without A Dose Rate Monitorina Device Due To Personnel Error EVENT DATE (')
LER NUMBER (')
REPORT DATE (')
OTHER FACILITIES INVOLVED (*)
MONTH DAY YEAR YEAR SEQ. #
REV#
MONTH DAY YEAR FACILITY NAMES DOCKET NO.(S) 0 5
0 0 0
_0 l 1 0l4 9l1 9l1
- - 0l0l1
- - 0l0 0l1 2l3 9l1 0
5 0
0 0 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO REQ'MTS OF 10CFR $2 V ONE OR MORE
()
MODE (')
N 20.402(b)
POWER 20.405(a)(1)(i) 20.405(c) 50.73(a)(2)(iv) 73.71(b) 50.36(c)(1) 50.73(a)(2)(v)
LEVEL ($')
1l 01 0 20.405(a)(1)(ii) 50.36(c)(2) 50.73(a)(2)(vii) 73.71(c) 20.405(a)(1)(iii) 50.73(a)(2)(i) 50.73(a)(2)(viii)(A)
OlHER:
_x 20.405(a)(1)(iv) 50.73(a)(2)(ii) 50.73(a)(2)(viii)(B) 20.405(a)(1)(v) 50.73(a)(2)(iii) 50.73(a)(2)(x)
LICENSEE CONTACT FOR THIS LER (18)
NAME TELEPHONE NO.
AREA CODE 00NALO A. REID, PLANT MANAGER 8l d 2 2lSI7l-l717l1l1 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (18)
CAUSE
SYST COMPNT MFR REPORTABLE
CAUSE
SYST COMPNT MFR REPORTABLE TO NPROS TO NPRDS N/A l
lll ll l N/A l
lll ll l N/A l
lll lll N/A l
lll lll SUPPLEMENTAL REPORT EXPECTED (14)
EXPECTED M0 DA YR SUBMISSION lYES (If ves, complete EXPECTED SUBMISSION DATE) X l NO DATE (i')
l l
l ABSTRACT (Limit to 1400 spaces, i.e.,
approx. fifteen singic-space typewritten lines) ()
On January 4, 1991, at approximately 1115 hours0.0129 days <br />0.31 hours <br />0.00184 weeks <br />4.242575e-4 months <br />, a Radiation Protection (RP) tech-nician entered a posted High Radiation Area, the radioactive waste Cask Room, to check the condition of the resin and move a resin cask, without a dose rate monitoring device, as required by Technical Specification 6.5.B.1.
A RP Supervisor went to the Cask Room to check on the job progress, discovered the problem and immediately directed the technician to return to the step-off pad until a dose rate monitoring device could be obtained, as required.
The general area dose rate during l
this event was less than 100 mr/hr.
l The root cause of this event is personnel error.
The technician failed to use a donc rate meter as required by procedures and Tech Specs when entering a High Radiation Area.
1 NRC Form 366 (6-80) l I
.U.S. NUCLEAR REGULATORY COMMISSION APPROVED OMS N0.3150-0104 i.
(6-89)
EXPIRES 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTION REQUEST:
50.0 HRS. FORWARD COMMENTS REGARDING LICENSEE EVENT REPORT (LER)
BURDEN ESTIMATE TO THE RECORDS AND REPORTS TEXT CONTINUATION MANAGEMENT BRANCH (P-530), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (3160-0104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20603.
UTILITY NAME (t)
DOCKET NO. (8)
LER NUMBER (5)
PAGE (8)
YEAR SEQ. #
REV#
VERMONT YANKEE NUCLEAR POWER STATION 0l Sl d Ol d 21711 9l1 0!0l1 0l0 d2 0F d3 TEXT (If more space is required, use additional NRC Form 366A) (5')
DESCRIPTION
On January 4, 1991, at approximately 1115 hours0.0129 days <br />0.31 hours <br />0.00184 weeks <br />4.242575e-4 months <br />, a Radiation Protection (RP)
Technician entered the radioactive waste Cask Room, a posted High Radiation Arca, to check on the condition of the resin and move a resin cask prior to having it filled.
The tech-nician entered the Cask Room without a dose rate monitoring device as required by procedures and Technical Specifications 6.5.B.1.
At approximately 1125 hours0.013 days <br />0.313 hours <br />0.00186 weeks <br />4.280625e-4 months <br />, a RP supervisor went to the Cask Room to monitor the work and immediately directed the technician to return to the step-off pad and wait there until a doce rate monitoring device could be obtained.
During this time, the technician was not working on the top of the cask and the general area doce rate was less than 100 mr/hr and the dose rate where he was working was less than 50 mr/hr.
While working in tne area, without a dose rate monitoring device, his dose is estimated to be approximately 20 mr based on his donimeter reading of 10 mr from the previous day and his dosimeter reading of 30 mr when he was required to return to the step-off pad.
The Cask Room area is posted as a High Radiation Arca due to the potential radiation icvels of the casks.
On January 7, 1991 the RP Supervisor brought this event to the attention of the RP Department Head.
The department head took immediate action to initiate a RP incident report and to have the event reviewed to determine reportability. He also relieved the technician of his dutics pending further investigation.
CAUSE OF EVENT
The root cause of this event is personnel error.
Technical Specifications, procc-dures, and training clearly state that personnel shail have a dose rate monitoring device before entering a High Radiation Area.
Further, the technician had previously completed this same job correctly the day before this incident.
ANALYSIS OF EVENT
The Cask Room is posted as a High Radiation Arca due to the potential dose rates from the various radioactive waste casks.
During this event, the general area dose rates were less than 100 mr/hr and the area in which the technician was working was less than 50 mr/hr.
As the work required to move the cask took less than 20 minutes, the dose the technician received during the incident is within Vermont Yankec's administrative limits and below any 10 CFR limits.
No overexposure occurred due to this event.
MARC Form 366A U.S. NUCLEAR REGULATORY COMMISSION APFROVED OMS RO.3150-0104 (6-09)
EXPIRES 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTION REQUEST:
50.0 HRS. FORWARD COMMENTS REGARDING LICENSEE EVENT REPORT (LER)
BURDEN ESTIMATE TO THE RECORDS AND REPORTS TEXT CONTINUATION MANAGEMENT BRANCH (P-530), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (3160-0104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20603.
UTILITY NAME (5)
DOCKET NO. (8)
LER NUMBER (*)
PAGE (*)
YEAR SEQ. #
REV#
VERMONT YANKEE NUCLEAR POWER STATION 0l Sl d 0l d 2l 711 9l1 0l0l1 0l0 d3 0F Ol 3 TEXT (If more space is required, use additional NRC Form 366A) (1')
CORRECTIVE ACTIONS
The immediate corrective action was that a RP Supervisor had the technician return to the step-off pad and wait until he received a done rate monitoring device.
Subsequent corrective actions as follows:
1.
The technican that caused the incident was relieved of further RP duties.
2.
The incident was discussed with all RP supervisors and in a department meeting with all RP personnel.
3.
A RP Incident Report and a Corrective Action Report were initiated which will identify long term corrective actions and any possible contributing factors.
4.
This event will be incorporated into the 1991 RP continuing training requirements.
5.
All personnt "ho have access to the Radiation Control Arca will receive training on this LER.
ADpITIONAL INFORMATION No similar events have been reported to the Commission in the past five years.
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