ML20083E346
| ML20083E346 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 09/27/1991 |
| From: | Withers B WOLF CREEK NUCLEAR OPERATING CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| WM-91-0135, WM-91-135, NUDOCS 9110020311 | |
| Download: ML20083E346 (3) | |
Text
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W$1.F CREEK NUCLEAR OPERATING CORPORATION Bart D. Withers r
Pres 6 dent and CNet Executw Otheer September 27, 1991 WM 91-0135 U. S. Nuclent Regulatory Conunission ATTN:
Document Control Desk Mail Station F1-137 Washinbton, D. C. 20555
,1
Reference:
Letter dated August 28, 1991 form S. J.
- Collins, NRC, to B. D. Withers, WCNOC
Subject:
Docket No. 50-482: Response to Violation 482/9118-01 Gentlemen:
Attached is Wolf Creek Nuclear Operating Corporation's (WCNOC) response to violation 482/9118-01 which is documented in the Reference.
Violation 482/9118-01 involved the failure to follow an approved procedure.
If you have any questions concerning this matter, please contact me or Mr. H. K. Chernoff of my aff.
Very truly yours, Bart D._ Withers President and Chief Executive Officer BDW/jra Attachment cc:
L. L. Gundrum (NRC), w/a A. T. Howell (NRC), w/a R. D. Martin (!!RC), w/a W. D. Reckley (NRC), w/a f
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j Attachment to WM 91-0135-Page 1 of 2 Response to Violation 482/9118-01 Violation (482/9118-01) Failure to Follow an Apptoved Procedure Findinn.
Technical Specification 6.8.1.a requires that written procedures shall be established, implemented, and maintained covering those activities recommended in Appendix A of Regulatory Guide (RG) 1.33 Revision 2 February 1978. RG 1.33 requires, in part, that procedures for operation of safety-related pressurized water reactor systems be implemented.
This requirement is implemented, in part, by Wolf Creek Generating Station (WCGS)
System Operating Procedure CKL EJ-120,
'RHR Normal System Lineup." Page 2 of CKL EJ-120 req' tires that Valves EJ '.' 16 and EJ-V012 be open.
Contrary to the.above, on July 14, 1991, the
'B' residual heat removal pump discharge pressure transmitter isolation. Valve E5-V016 and pump suction pressure indicator isolation Valve EJ-V032 were confirmed to be in the closed position.
These valves were apparently manipulated during the performance of Surveillance Test Procedure STS EJ-100B, Revision 8
'RHR Inservice Pump B Test," on June 19, 1991. With EJ-V016 closed, "RHR B DISCH PRESS H1' annunciator was rendered inoperable.
Reason for Violation:
A review of-the available documentation associated with this eve did not conclusivr.ly identify the reason for the violation.
Procedure CKL EJ-120,
'RHR Norral System Lineup *,
performed on November 11, 1988 verified that valves EJ-V012 and EJ -V016 were open.
The satisfactory performance of procedure STS EJ-100B,
'RHR System Inservice Pump B Teet' on June 19, 1991 indicates that the two valves were closed on or after this date.
A review of the work history on EJ-V012 and EJ-V016 was performed and identified that no work had been performed on these valves after June 19, 1991.
> review of the calibration records for the RHR System Suction Pressure gauge
.EJ PI-602 and RHR System Discharge Pressure iransmitter EJ PT-615 identified that calibration cf the instruments had not been performed after June 19, 1991.
From discussions with Operators, Instrument and Control (I&C) technicians and Results Engineering personnel involved, Wolf Creek Nuclear Cperating Corporation (WCNOC) was unable to determine the reason that these valves were in the closed position.
Inspection Report 50-482/91-18 states, "Apparently personnel performing this surveillance routinely close these valves even though Procedure STS EJ-1 COB does no+ caquire them to be manipulated." The standard practice at Wolf
-Creek antrating station la to leave the instrument root valves in the open positie If additional test pressure gauges are required to perform the surveilAance, the procedure provides guidance for instr 111ng the gauge on the manifold utilizing the manifold drain valves.
Authorization from the Control Room is necessary if a valve is to be manipulated that is not specifically allowed by procedure.
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Attachment to WM 91-0135 Page 2 of 2 Corrective Steos Which Have Been ?aken And Results Aqblevedt
-Upon_ notification to Control Room personnel, aa operator confirmed the
-position"of valves EJ-V012 and EJ-V016 and the valves were subsequently opened.
Additionally, operators verified that the similar train
'A' residual heat removal root valves were open.
A Programmatic Det'iciency Report (PDR) was initiated on July 14, 1991 to evaluate thi, event.
Corrective Steps i'!.ich Will Be Taken To Avoid Further Violations 4
A c,py Lof the PDR was placed in Operations, I&C and Re>ults Engineering required reading-to remind personnel of the philosophy regarding operation of valves - and -equipment in the plant.
A letter from the Deputy Director Plant Operations was issued.- to station personnel as a result of an unrelated eveut1 to. reemphasize that Operations persennel are the only individuals authorized to manipulate valves and operate equipment _in-the plant unless-specifically authorized by procedure or authorized by the Control-Room.
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_The detalle_of tnis_ event will be included in licensed operator and nuclear station _ operator requalification training cycle 92-1 on plant /indastry.
events.
Requalification training cycle 92-1 is scheduled to begin on November 11, 1991.
Additior. ally, this event well be included in General (Employco_ Training (CET) requalification trainlag for 1992.
'Date When Full Compliance Will Be Achievedt Full compliance.has been achieved, i
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