Ro:On 800207,control Rod Withdrawal Inhibit on Intermediate Power Level Period Recorder Found Set at Less than 30-s Setpoint.Caused by Nut Loosened During 800207 Maint Allowing Setpoint to Be Changed During Channel CheckML19294B170 |
Person / Time |
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Site: |
05000054 |
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Issue date: |
02/18/1980 |
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From: |
Ruzicka W UNION CARBIDE CORP. |
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To: |
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References |
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NUDOCS 8002270392 |
Download: ML19294B170 (2) |
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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO
MONTHYEARML19323F2881980-05-15015 May 1980 RO 50-54/80-01:during Reactor Startup,Control Rod Found Separated Between End Piece & Poison Section.Cause Unstated. Silver Indium Rods Inspected.Startup Reactivity Check Procedures Being Revised to Prevent Misinterpretation ML19309H4921980-05-0505 May 1980 Ro:On 800503,poison Section of Control Rod Assembly Found Separated from Rod Drive.Failure Did Not Compromise Shutdown Margin.Rod Replaced & Reactor Returned to Power. Remaining Rods Will Be Closely Monitored Until Insp ML19294B1701980-02-18018 February 1980 Ro:On 800207,control Rod Withdrawal Inhibit on Intermediate Power Level Period Recorder Found Set at Less than 30-s Setpoint.Caused by Nut Loosened During 800207 Maint Allowing Setpoint to Be Changed During Channel Check ML19271A0091980-02-0808 February 1980 Ro:On 800207,control Rod Withdrawal Inhibit on Intermediate Power Level Period Monitor Set Below Specified Setpoint. Possibly Caused by Inadvertent Movement During Channel Check.Withdrawal Inhibit Adjusted to Proper Setpoint 1980-05-05
[Table view] Category:LER)
MONTHYEARML19323F2881980-05-15015 May 1980 RO 50-54/80-01:during Reactor Startup,Control Rod Found Separated Between End Piece & Poison Section.Cause Unstated. Silver Indium Rods Inspected.Startup Reactivity Check Procedures Being Revised to Prevent Misinterpretation ML19309H4921980-05-0505 May 1980 Ro:On 800503,poison Section of Control Rod Assembly Found Separated from Rod Drive.Failure Did Not Compromise Shutdown Margin.Rod Replaced & Reactor Returned to Power. Remaining Rods Will Be Closely Monitored Until Insp ML19294B1701980-02-18018 February 1980 Ro:On 800207,control Rod Withdrawal Inhibit on Intermediate Power Level Period Recorder Found Set at Less than 30-s Setpoint.Caused by Nut Loosened During 800207 Maint Allowing Setpoint to Be Changed During Channel Check ML19271A0091980-02-0808 February 1980 Ro:On 800207,control Rod Withdrawal Inhibit on Intermediate Power Level Period Monitor Set Below Specified Setpoint. Possibly Caused by Inadvertent Movement During Channel Check.Withdrawal Inhibit Adjusted to Proper Setpoint 1980-05-05
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20237C5181998-08-19019 August 1998 Safety Evaluation Supporting Order Terminating Facility License R-81 for Cintichem,Inc Research Reactor ML20211C5761997-09-22022 September 1997 Bedrock Dose Assessment Rept. W/One Oversize Drawing ML20149G9201997-06-27027 June 1997 Final Survey Repts for Cintichem Outdoor Areas Inside of Former RCA, Chapters 13 & 14 ML20070S2991990-12-31031 December 1990 Annual Rept for 1990 for Centichem,Inc Nuclear Reactor. W/ ML20055F9141990-07-17017 July 1990 Safety Evaluation Supporting Amend 26 to License R-81 ML20236D2121989-03-14014 March 1989 Safety Evaluation Supporting Amend 25 to License R-81 ML20248K2341988-12-31031 December 1988 Annual Rept for 1988 ML20151W5051988-08-16016 August 1988 Safety Evaluation Supporting Amend 24 to License R-81 ML20153B0341987-12-31031 December 1987 Annual Rept for 1987 for Cintichem,Inc Nuclear Reactor ML20214J1771986-12-31031 December 1986 Annual Operating Rept for 1986 ML20113C6411984-12-31031 December 1984 Annual Rept for 1984 for Union Carbide Nuclear Reactor (Ucnr) ML20087L4251983-12-31031 December 1983 Annual Rept for 1983 ML20072P3641983-03-28028 March 1983 Annual Operating Summary,1982 ML20042C1021982-03-23023 March 1982 Annual Operating Rept,1981. ML19350C7301981-03-31031 March 1981 Annual Operating Rept 1980. ML20003E6431981-03-31031 March 1981 Annual Operating Summary,1980, Page 5 ML19323F7061980-05-31031 May 1980 Revisions to Sar,Submitted in Support of Application for Renewal of License R-81 ML19323F7001980-05-23023 May 1980 Annual Financial Rept 1979 ML19323F2881980-05-15015 May 1980 RO 50-54/80-01:during Reactor Startup,Control Rod Found Separated Between End Piece & Poison Section.Cause Unstated. Silver Indium Rods Inspected.Startup Reactivity Check Procedures Being Revised to Prevent Misinterpretation ML19309H4921980-05-0505 May 1980 Ro:On 800503,poison Section of Control Rod Assembly Found Separated from Rod Drive.Failure Did Not Compromise Shutdown Margin.Rod Replaced & Reactor Returned to Power. Remaining Rods Will Be Closely Monitored Until Insp ML19309C3971980-03-31031 March 1980 Annual Operating Rept 1979, Reporting Facility Mod & Major Maint ML19294B1701980-02-18018 February 1980 Ro:On 800207,control Rod Withdrawal Inhibit on Intermediate Power Level Period Recorder Found Set at Less than 30-s Setpoint.Caused by Nut Loosened During 800207 Maint Allowing Setpoint to Be Changed During Channel Check ML19271A0091980-02-0808 February 1980 Ro:On 800207,control Rod Withdrawal Inhibit on Intermediate Power Level Period Monitor Set Below Specified Setpoint. Possibly Caused by Inadvertent Movement During Channel Check.Withdrawal Inhibit Adjusted to Proper Setpoint 1998-08-19
[Table view] |
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% UNION CARBIDE CORPORATION MEDICAL PRODUCTS DIVISION P.O. BO X 324 TUXE DO, NEW YO RK 10987 TELEPHON E: 914-351 2131 February 18, 1980 Mr. Boyce H. Grier U. S. Nuclear Regulatory Commission Office of Inspection & Enforcement, Region 1 631 Park Avenue King of Prussia, PA 19406
Dear Mr. Grier:
Mr. E. B. McCabe of your office was notified via tele-phone on February 8, 1980 of a Technical Specification re-quired Limiting Condition for Operation setpoint being out of adjustment. A confirming telecopy was also sent to you on February 8, 1980. Technical Specification 6.5. 3.a. (3) (b) re-quires this report to the Commission following any operation exceeding any Limiting conditions for Operation as established in the Technical Specifications.
At approximately 2400 hours0.0278 days <br />0.667 hours <br />0.00397 weeks <br />9.132e-4 months <br /> on February 7,19 80, 'the con-trol rod withdrawal inhibit on the intermediate power level period recorder was found to be set at less than the 30 second setpoint as required by Technical Specification Section 3.2.3.
The reactor was shut down and the on-call Senior neactor Oper-ator (in this care the Reactor Instrument Technician) was con-tacted. The Senior Operator directed that the setpoint be adjusted and tested and the reactor returned to power. During the time the reactor was operated with the out of adjustment setting, the reactor was protected by its redundant safety system design. The intermediate range 10 second reverse en,d 3 second scram setpoints were at all times correctly set.
2:ais protection along with the count rate 30 second period in-hibit and the power level reverse and scram provided adequate reactor protection.
The improper setpoint is believed to have existed during no more than six hours of reactor operation. On February 7 at 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br />, the reactor was shutdown for refueling and maintenance, including maintenance on the intermediate power level channel. Following this, the reactor console checklist (Reactor Standard RS-01) was completed which checked satis-factorily 'he 30 second inhibit setpoint. During subsequent operation, the console operator observed that rod withdrawal was not inhibited as it should have been when he reached a 30 0 second period. It has been postulated that a nut may have dY
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i Mr. Boyce H. Grier - Page 2 -
U. S. Nuclear Regulatory Commission February'18, 1980 L
been loosened during maintenance which then allowed the set-point to be changed during the performance of the channel check. This would have allowed the channel check to be per-
, formed satisfactorily and at the same time misadjusted the setpoint. All similar equipment has been checked for proper tightness. This has not been a recurring occurrence and is
, considered an isola' 2 event.
The Senior Reactor Operator on call should have techni-cally been present for the restart. However, he was of the understanding that the reactor was simply subcritical at the time of the call and not yet fully shutdown. After the set-point was adjusted and retested, he believed that he was authorizing a return to power and not a complete startup.
His presence at this particular startup would not have had a significant effect on reactor safety. Had this not been the case, he would have been present regardless of his under-standing of the reactor power level. This occurrence is being discussed with all operators to emphasize the import-
~
ance of thorough communications and strict adherence to operating procedures.
Sincerely,
- u. s. 62niJ~-
WGR:ltm J. G. Ruzicka Reactor Project Engineer cc: Mr. M. H. Voth Manager Nuclear Operations O
e e