05000267/LER-1980-019, Forwards LER 80-019/03L-0
| ML19309F829 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 04/25/1980 |
| From: | Warembourg D PUBLIC SERVICE CO. OF COLORADO |
| To: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| Shared Package | |
| ML19309F830 | List: |
| References | |
| P-80089, NUDOCS 8005010394 | |
| Download: ML19309F829 (9) | |
| Event date: | |
|---|---|
| Report date: | |
| 2671980019R00 - NRC Website | |
text
80001039%
5 public service company o f C e n o m fI o 3 16805 Weld County Road 191/2, Platteville, Colorado 80651 April 25, 1980 Fort St. Vrain Unit No. 1 P-80089 Mr. Karl V. Seyfrit, Director Nuclear Regulatory Commission Region IV Office of Inspection and Enforcement 611 Ryan Plaza Drive Suite 1000 Arlington, Texas 76012 Reference: Facility Operating License No. DPR-34 Docket No. 50-267
Dear Mr. Seyfrit:
Enclosed please find a copy of Reportable Occurrence Report No. 50-267/
80-19, Final, submitted per the requirements of Tachnical Specification AC 7.5.2(b)2.
Also, please find enclosed one copy of the Licensee Event Report for Reportable Occurrence Report No. 50-267/80-19.
Very truly yours, WY%
Don Warembourg
/
Manager, Nuclear Production DW/cis Enclosure cc: Director, MIPC Y1 Yt
REPORT DATE:
April 25, 1980 REPORTABLE OCCURRENCE 80-19 ISSUE O OCCURRENCE DATE:
March 27. 1980 Page 1 of 8 FORT ST. VRAIN NUCLEAR GENERATING STATION PUBLIC SERVICE COMPANY OF COLORADO 16805 WELD COUNTY ROAD 19 1/2 PLATTEVILLE, COLORADO 80651 REPORT No. 50-267/80-19/03-L-0 Final IDENTIFICATION OF OCCURRENCE:
On six occasions between March 27, 1980, and April 16, 1980, the reactor was operated in a degraded mode of LCO 4.2.10.
On March 28, 1980, the reactor was operated in a degraded mode of LCO 4.2.11.
These events are reportable per Fort St. Vrain Technical Specification AC 7.5.2(b) 2.
EVENT
DESCRIPTION
The Fort St. Vrain Technical Specification LCO 4.2.10 limits operation of the reactor with average core outlet temperature greater than 1200*F when total primary coolant oxidants exceed 10 parts per million (ppm).
Contrary to this limit, the reactor was operated with the average core outlet temperature greater than 1200*F when the primary coolant oxidants exceeded 10 ppm for the following periods:
1.
March 27,1980, at 0830 hours0.00961 days <br />0.231 hours <br />0.00137 weeks <br />3.15815e-4 months <br /> to March 28,1980, at 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br />.
2.
April 1,1980, at 0945 hours0.0109 days <br />0.263 hours <br />0.00156 weeks <br />3.595725e-4 months <br /> to April 6,1980, at 0330 hours0.00382 days <br />0.0917 hours <br />5.456349e-4 weeks <br />1.25565e-4 months <br />.
3.
April 6,1980, at 0430 hours0.00498 days <br />0.119 hours <br />7.109788e-4 weeks <br />1.63615e-4 months <br /> to April 8,1980, at 1530 hours0.0177 days <br />0.425 hours <br />0.00253 weeks <br />5.82165e-4 months <br />.
4.
April 10,1980, at 1230 hours0.0142 days <br />0.342 hours <br />0.00203 weeks <br />4.68015e-4 months <br /> to April 10,1980, at 1330 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.06065e-4 months <br />.
5.
April 14,1980, at 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> to April 15, 1980, at 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br />.
6.
April 15,1980, at 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br /> to April 16, 1980, at 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br />.
These events constitute operation in a degraded mode of LC0 4.2.10.
Technical Specification LCO 4.2.11 limits the primary coolant dewpoint as a function of average core outlet temperature. Contrary to the limit of Figure 4.2.11-1, on March 28, 1980, the primary coolant dewpoint was
- - 9'F when the average core outlet temperature was 1195'F. Figure 4.2.11-1 shows a max 1=um acceptable dewpoint at this temperature of -19.5'F.
This event constitutes operation in a degraded mode of LCO 4.2.11.
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REPORTABLE OCCURRENCE 80-19 ISSUE O Page 2 of 8
CAUSE
DESCRIPTION:
l Event #1 (See Figure 1)
On March 27, 1980, the reactor was operating with primary coolant oxidants in excess of 10 ppm. The reactor power was increased for better clean-up and greater electrical generation, result ng in an average core outlet temperature above 1200*F at 0830 hours0.00961 days <br />0.231 hours <br />0.00137 weeks <br />3.15815e-4 months <br />, 1 on Figure 1.
Total oxidants l
remained above 10 ppm while the average core outlet temperature was above 1200*F, until 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> on March 28, 0, when reactor power reduction brought the temperature below 1200*F, on Figure 1.
Event #2 (See Figures 1 and 2) l On April 1,1980, the reactor was operating with primary coolant oxidants in excess of 10 ppm. The reactor power was increased for better clean-up and greater electrical generation, result ng in an average core outlet temperature above 1200*F at 0945 hours0.0109 days <br />0.263 hours <br />0.00156 weeks <br />3.595725e-4 months <br />, 3 on Figure 1.
Total oxidants remained above 10 ppm, and the average core outlet temperature was above 1200*F, until 0330 hours0.00382 days <br />0.0917 hours <br />5.456349e-4 weeks <br />1.25565e-4 months <br /> on April 6, 980, when power was reduced to re-cover a shutdown helium circulator, on Figure 2.
Event #3 (See Figure 2)
On April 6,1980, the reactor was operating with primary coolant oxidants in excess of 10 ppm. When reactor power was increased af ter recovery of a shutdown helium circulator, the avera core outlet temperature exceeded 1200*F at 0430 hours0.00498 days <br />0.119 hours <br />7.109788e-4 weeks <br />1.63615e-4 months <br /> on April 6,1980, on Figure 2.
The average core outlet temperature was above 1200*F unti 1530 hours0.0177 days <br />0.425 hours <br />0.00253 weeks <br />5.82165e-4 months <br /> on A ril 8,1980, when reactor power was reduced due to a loop shutdown, on Figure 2.
i Event #4 (See Figure 3)
On April 10, 1980, the reactor was operating with primary coolant oxidants less than 10 ppm. Reactor power was increased for better clean-up and greater electrical generation, resulting in an average core outlet temperature above 1200*F.
The primary co lant oxidants began to increase, and at about 1230 hours0.0142 days <br />0.342 hours <br />0.00203 weeks <br />4.68015e-4 months <br /> exceeded 10 ppm, 7 on Figure 3.
The oxidants remained above 10 ppm, while the average core outlet temperature remained above 1900*F, until 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br /> April 10, 1980, when reactor power was reduced, 8 on Figure 3.
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NOTE: The source of the sudden increase in primary coolant oxidants seen on Figure 3 on April 10, 1980, was a malfunction in the purification l
system which returned previously removed oxidants back to the primary l
coolant system.
REPORTABLE OCCURRENCE 80-19 ISSUE O Page 3 of 8
CAUSE
DESCRIPTION: (Cont' d)
Event #5 (See Figure 3)
On April 14, 1980, the reactor was operating with primary coolant oxidants less than 10 ppm. Reactor power was increased for better clean-up and greater electrical generation, resulting in an average core outlet temperature of greater than 1200*F. Prima oolant oxidants began to increase and exceeded 10 ppa at 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br />, on Figure 3.
Primary c ant oxidants remained above 10 ppm until 100 ours on April 15, 1980, on Figure 3.
Event #6 (See Figure 3)
On April 15, 1980, the reactor was operating with the average core outlet temperature greater than 1200*F.
The primary coolant oxi ts increased to greater than 10 ppm at 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br /> on April 15, 1980, on Figure 3.
The primary coolant oxidants remained above 10 ppm, and t e average core outlet temperature was above 1200', until 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br /> on April 16, 1980, when reactor power was reduced, 2 on Figure 3.
The cause of the high moisture in the primary coolant on March 28, 1980, is believed to be moisture in the buffer helium system due to malfunctioning in the buffer helium dryer.
CORRECTIVE ACTION:
Event #1 Reactor power was reduced, bringing the average core outlet temperature below 1200*F.
Event #2 Reactor power was reduced, bringing the average core outlet temperature below 1200'F.
Event #3 Reactor power reduction due to a loop shutdown reduced the average core outlet temperature below 1200*F.
Event #4 Reactor power was reduced until the average core outlet temperature was less than 1200*F.
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REPORTABLE OCCURRENCE 80-19 ISSUE O Page 4 of 8 l
l CORRECTIVE ACTION:
(Cont' d)
Event #5 i
The primary coolant oxidents were removed from the primary coolant system by the on-line purification system to a level below 10 ppm.
Event #6 Reactor power was reduced bringing the average core outlet temperature below 1200*F.
The operation in a degraded mode of LCO 4.2.11 was corrected by reducing power until the average core outlet temperature was below the limit speci-fied for the existing primary coolant dewpoint.
No further corrective action is anticipated or required.
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REPORTABLE OCCURRENCE 80-19
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DATE/ TIME I
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REPORTARLE OCCURRENCE 80-19 1400 ISSUE Q 5_ 3=:'~:_. _ m __E_ E_-g_,_ y. :....h_=_ _=_.__._=_~g.==.=..:_.-CIP. s g 2 6 of 8
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REPORTABLE OCCURRENCE 80-19 Maximta ISSUE a 186.3 1400
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REPORTABLE OCCURRENCE 80-19 ISSUE O Page 8 of 8 I
i Prepared By:
l/
fffim M,
dcN Richard F. Frost Technical Services Technician Reviewed By:
/,
M g.W.J,ahm
[/rechnical Services Supervisor l
Reviewed By:
[r'd.#t
/Nec vrank M. Mathie U
Operations Manager Approved By:
McucM Don Warembourg Manager, Nuclear Production i
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