ML20028F279
| ML20028F279 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 01/17/1983 |
| From: | Warembourg D PUBLIC SERVICE CO. OF COLORADO |
| To: | Jay Collins NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| Shared Package | |
| ML20028F282 | List: |
| References | |
| P-83023, NUDOCS 8301310337 | |
| Download: ML20028F279 (5) | |
Text
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. public servlee company ce odernufte
. 16805 Road 19 1/2, Platteville, Colorado 80651-9298 January 17, 1983 Fort St. Vrain Unit No. 1 P-83023 . - -
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L ,
Mr. John T. Collins, Regional Administrator Jm 20 GB '!
Region IV _ _
'M Nuclear Regulatory Commission 611 Ryan Plaza Drive Suite 1000 Arlington, Texas 76011
Reference:
Facility Operating License No. OPR-34 Docket No. 50-267
Dear Mr. Collins:
Enclosed please find a copy of Reportable Occurrence Report No. 50-267/83-001, Final, submitted per the requirements of Technical Specification AC 7.5.2(a)6.
Also, please find enclosed one copy of the Licensee Event Report for Reportable Occurrence Report No. 50-267/83-001.
Very truly yours, i kW Don Warembourg Manager, Nuclear Production DW/cis Enclosure cc: Director, MIPC 0
h 10 b l 8301310337 830117 pDR ADOCK 05000267 8 PDR
REPORT DATE: January 17, 1983 REPORTABLE OCCURRENCE 83-001 ISSUE 0 OCCURRENCE DATE: January 3. 1983 Page 1 of 4 FORT ST. VRAIN NUCLEAR GENERATING STATION PUBLIC SERVICE COMPANY OF COLORADO 16805 WELD COUNTY ROAD 19 1/2 PLATTEVILLE, COLORADO 80651-9298 REPORT NO. 50-267/83-001/01-T-0 Final IDENTIFICATION OF OCCURRENCE:
On Monday, January 3, 1983, at approximately 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br />, while the plant was operating at 30% power, it was determined that due to an erroneous interpretation of Table 4.4-1 in LCO 4.4.1, the minimum number of operable moisture monitor channels were not operable for a duration exceeding 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> without the reactor being shut down.
This event occurred during routine startup operations from approximately 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br /> on January 1, 1983, to approximately 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> on January 2,1983.
As the reactor was maintained operational for greater than the 12- ,
hour grace period allowed, this event is being reported per Fort St.
Vrain Technical Specification AC 7.5.2(a)6.
CONDITIONS PRIOR TO AND DURING OCCURRENCE:
The reactor was being maintained near 30% power during a routine startup operation. The plant had previously been shutdown or or arated at low power for a three-month period.
DESCRIPTION OF OCCURRENCE:
l On January 3, 1983, following reviews of the station's logs and reports from the previous weekend, it was noted that several moisture monitors had been temporarily removed from service for maintenance and/or calibration. Further, it was noted that one of the high range moisture monitors (MM-1119) had been in an inoperable, yet untripped, condition for the period of time beginning at approximately 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br /> on January 1, 1983, and ending at approximately 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> on January 2,1983. This period of time exceeded the allowable time in such a configuration by seven hours.
When questioned as to the circumstances behind the situation 2with .
MM-1119, Operations personnel stated that the monitor, although inoperable, could not be tripped without causing protective action to occur, and therefore, by Note (f) of Table 4.4-1 in LCO 4.4.1, was
REPORTABLE OCCURRENCE 83-001 ISSUE O Page 2 of 4 not require,d to be tripped until an acceptable configuration was attained.
A management conference was held at 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br /> on January 3, 1983, to discuss the validity of the LC0 4.4.1 interpretation made by Operations personnel, The conclusion of the conference was that an erroneous interpretation had been made. Rather than providing a permissible bypass condition as presumed by Operations personnel, Note (f) provides a pe rmi ssible mode of operation within the -
applicable 12-hour grace period.
APPARENT'CAUSE OF OCCURRENCE:
Personnel error.
Due to an erroneous interpretation of Note (f) for Table 4.4-1 of '
LCO 4.4.1, the minimum number of operable moisture monitor channels were not operable per definition for a period of time exceeding the 12-hour grace period. Operating personnel correctly interpreted Note (f) to mean that a moisture monitoring channel should not be placed in the tripped position if it will cause a protection action to occur, but they failed to recognize that once a situation of this type arises, a 12-hour grace period is entered.
ANALYSIS OF OCCURRENCE:
Throughout the event, primary coolant moisture levels were being monitored by the analytical moisture monitors. At no time during the event did the moisture levels reach the setpoint of the low range l plant protective system moisture monitors. Had the setpoint been
! reached, a manual scram could have been inserted.
Subsequent to this occurrence, with the anticipation that additional moisture monitor work would be required, temporary relief from the applicable portions of LCO 4.4.1 was requested from the Nuclear Regulatory Commission so that startup operations could continue.
Relief was granted on January 3, 1983, for a period of 10 days provided that the intent of LCO 4.9.2 would be met. The intent of LCO 4.9.2 is to monitor the primary coolant moisture levels with analytical moisture monitors, in lieu of inoperable plant protective system monitors, in a manner similar to that used during this event.
The health and safety of the public was not endangered at any time during this event.
CORRECTIVE ACTION:
Upon determination that the plant had been operated in violation of the Technical Specifications, a prompt notification was made to the t , . .-. . -,
i REPORTABLE OCCURRENCE 83-001 ISSUE 0 Page 3 of 4 -
Nuclear Redulatory Commission. The moisture monitoring system had been returned to an acceptab e configuration prior to this determination.
The operating staff was re-instructed on the proper interpretation of the footnotes concerned with LCO 4.4.1.
- A Technical Specification change will be submitted to clarify the intent of Note (f) in LCO 4.4.1, and thereby prevent future -
occurrences of this type.
No further corrective action is anticipated or required.
FAILURE DATA /SIMILAR REPORTED OCCURRENCES:
Similar reported occurrences are: R0's 78-08, 78-13, and 78-40.
PROGRAMMATIC IMPACT:
None ,
CODE IMPACT:
None l
- - - . .m
REPORTABLE OCCURRENCE 83-001' ISSUE O Page 4 of 4 Prepared By: > > ew . Mu -c Owen J. fl)yton A Senior Mnical SeMices Technician Reviewed By: o /Im Charles Fuller ~
Technical Services Engi eer ng Supervisor
/
s Reviewed By: f /
Edwin D. Hil F'"
Station Manager i
Approved By: M[d Don Warembourg V Manager, Nuclear Production 1
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