ML19343A144
| ML19343A144 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 09/03/1980 |
| From: | Warembourg D PUBLIC SERVICE CO. OF COLORADO |
| To: | Gammill W Office of Nuclear Reactor Regulation |
| References | |
| P-80296, NUDOCS 8009160290 | |
| Download: ML19343A144 (4) | |
Text
-
I public semee company of ceaemde 16805 ROAD 19%
PLATTEVILLE COLOR ADO 80651 September 3, 1980 Fort St. Vrain Unit No. 1 P-80296 Director of Nuclear Reactor Regulation ATTN:
W. P. Ga:muill, Chief Operating Reactors Safeguard Branch Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, D.C.
20555
Reference:
Facility' Operating License No. DPR-34 Docket No. 50-267
Dear Sir:
Enclosed please find our Monthly Operations Report for the month of June, 1980.
Very truly yours, dL 7%
Don Warembourg Manager, Nuclear Production DW/cis Enclosure P
3
//
800g1gg
.) fg
This report contains the highlights of the Fort St. Vr ain, Unit No.1 activities, operated under the provisions of the Nuclear Regulatory Commission Operating License, DPR-34 This report is for th9 month of June,1980.
1.0 NARRATIVE
SUMMARY
OF OPERATING EXPERIENCE AND MAJ0F SAFETY RELATED MAINTENANCE 1.1 Summary Reactor power was 54% with generator at 150 M4e on June 1, 1980.
On June 2, 1980, reactor power was increased to 60% with generator load _of 172 MWe, followed by an increase to 68%,
200 MWe on June 3.
On June 5,1980, curified helium leakage rates of the Loop 2 steam generator penetrant approached Technical Specification limits. A v:riance was received from the Nuclear Regulatory Commission to increase LCO 4.2.9 limits from 400 pounds per cay to 700 pounds per day.
On June 11,'1980, reactor power was reduced to 68% and 195 MWe because high ambient temperatures were affecting the service and circulating water system capability.
On-June 12, 1980, with reactor power at 68% and 195 MWe, main cocling tower blowdown was swapped from hot to cold side te comply with EPA temperature limits.
On June 17, 1980, "B" helium circulator tripped due to high buffer-mid-buffer, and approximately three hours later "A"
circulator-tripped for the same reason, causing a loop shutdown.
The turbine generator was manually tripped.
Activity increased in the low pressure separator as did moisture in the primary coolant.
Reactor power was reduced to 2% to recover Loop 1.
The problem was traced to a ruptured diaphragm in pressure differential transmittar (contributing circulator trips).
Loop 1 was recovered and reactor power was increased to 5%.
Reactor power was held at 10%, with A, C, and 0 circulators operating and both loops in service on emergency feedwater on June 18.
On June 19, reactor power was increased to 25%
and the turbine placed on line.
Heater #6 and the normal feedwater. header were returned to service.
On June 20, "A" circulator tripped causing Loop I to
. shutdown.
Power was reduced to approximately 10% and held.
Moisture in prestressed concrete reactor vessel increased in i
excess of 100 ppm and activity was noted in the low pressure separator.
Power was reduced to 2% to recover Loop 1.
i i
l
~
. Primary coolant moisture levels decreased, and Loop 1 steam generator was returned to service on June 21, with reactor power at 3.5% and moisture down to 19 ppm.
Power was increased to 8% and orifices were set.
Primary coolant moisture leveled out at 40 ppm.
Reactor power was reduced to less than 2*; 1 June 23, and
~
loop 2 was shut-down to repair various leaking valves (mainly V-2248).
Power was subsequently reduced to 10 -'% with condensate cooling loop 2.
Valve repacking was completed June 24, and Loop 2 was recovered.
On June 27, with the reactor at 7% power, PDT-2175-1 was re-installed on "A" circulator.
Primary coolant moisture increased rapidly when "A" circulator was brought up to speed.
Reactor power was held steady at 8% awaiting primary coolant moisture, reduction.
On June 29,. reactor power was increased to 20*;, and on June 30, the turbine generator was synchronized and power increased to 29% and 50 MWe.
Reactor power was increased to 45% with a turbine g ne stor load of 125 MWe, but was later reduced due to an increase in primary coolant moisture.
1.2 Ooerations On June 1,1980, the reactor power was 54*; and 150 MWe.
Oxidants in the primary coolant had decresed to 4.7 ppm.
Reactor power was increased to 6C% and 172 MWe, resulting in an oxidant increase to 5 ppm. The plant remained in tM s condition until June 3 when reactor power was raised to 6&.
and 200 MWe on the emergency feedwater header.
On June 4, reactor power was increased to 69% and 205 MWe, with oxidants holding at 5 ppm. A penetration leak cf purified helium into the cold reheat header developed.
This required Nuclear Regulatory Commission approval of a variance to LCO 4.2.9 which allows up to 700 pounds per day total leakage from the system ve' sus 400 pounds per day previously allowed. The leak has nor progressed beyond the initial rate and it now appears we will be able to stay within the above limit until repairs can be made during the 1981 i
refueling outage.
Plant operations continued at above levels and conditions until June 17, when Loop 1 circulators tripped from buffer upset resulting in a Lo6p 1 shutdown.
Reactor power was reduced to 2% to recover the shutdown 1o00. During this occurrence, activity increased in the low pressure separator, and moisture increased in primary i
coolant.
The cause of the circulator trips was a ruptured diaphragm in a main drain pressure transmitter.
The loop was recovered and power increased to 10*; on June 18.
.j Reactor power was increased to 25% on June 19 and turbine g
generator was placed on line with the normal feedwater n
, ~. -,,
header in service. On June 20, "A" circulator tripped. As it was the only circulator operating in Loop 1, the loop was shut down and power was reduced to 2% to recover the loop.
Primary coolant moisture increased (greatar than 100 pom) as a result of the "A" circulator trip.
Loop 1 was recovered on June 21 and reactor power was increased to 8%.
Primary coolant moisture leveled out at 40 ppm.
The unit'was held at 8% to dry out the primary coolant until June 23 when Loop 2 had to be shut down to repair valves.
Power was reduced to 10-2% and cooling was transferred to condensate.
Loop 2 was restored to service on June 25 and reactor power was increased to 4.5%.
Primary coolant moisture was at 12.7 ppm and secondary coolant chemistry was not acceptable for operation above 400 F.
Reactor power was increased slowly over the next four days to 25%, and the turbine generator was placed on line on June 30.
Reactor power was increased to 45% and 125 MWe at this time, but a power reduction was necessary due to high moisture in the primary coolant.
Spent fuel shipping continued throughout the entire report period with a total of ten shipments being made to date.
Feedwater heater #5 is still out of service and will not be repaired until the September shutdown. We were able to
('/
isolate it and return the normal feedwater header to service.
Some plant efficiency will be lost until the repairs are made'.
The hot weather of June placed-some limitations on service water system capability which limited the unit load carrying capabilities.
2.0 SINGLE RELEASES OF RADI0 ACTIVITY OR RADIATION EXPOSURE IN EXCESS OF 10% OF THE ALLOWABLE ANNUAL VALUE None 3.0 INDICATION OF FAILED FUEL RESULTING FRCM IRRADIATED FUEL EXAMINATIONS None 4.0 MONTHLY OPERATING DATA REPORT Attached e
3 e,
s v-r-
, *n m-
-v-
-w-,
c
, - ~.
L Crm::s: m 9mn oce.c: so.
50-267
- A:
800701 Cc.m.nra n J. W. Gahm it:. rses:
(303) 785-2253 OPERATING STAT S NOTES 1.
- nt: sace:
Fort St. Vrain 2.
Reporting Period:
800601 throuch 800630 3.
Licensed *hermal Power (Wt):
So2 L.
Namepla:e R4:ing (jross We):
342 5.
Design Electrical Rating C;et We):
330 f
6.
".axisu:2 Sependable Capacity (Gross We):
342 7.
- '.aximum Oependable Capacity Clet We):
330 3.
If Changes Occur in Capacity Racings (! tens Nu=ber 3 *hrough 7) Since Last Report, Give Reasces:
None 3.
?:wer Level To ~4hich Restric:ed. If Any (Net We):
2 31 u.
Rusons ter Restricti:na, :f Any: Nuclear Reculatory Cormission restriction 70% cendina resolution of temcerature fluctuations Thia Month Year to cace Ca=alative 11.
Hours in Reporting Pericd 720 d.367 B,78a 1:. Nc=ber of Hours F.eac:ce ~4as Cri:ical 720.0 3.024.9 5.557.7 u.
Reactor Reserve shutdcwn sours 0.0 0.0 0.0 te.
acurs cenerator en-t.tne 406.6 2.053.5 3.035.7 if.
- ni Reserve Shutdown Hours 0.0 0.0 0.0 n.
cross n.er=al Inere en rated cita) 24d.228 969.291 1.d47.2d6 c
17 cross Electrical Insrc Generated (51) 75.923 312.946 453,742 s.
sec ::ee:rica: Energy cenerated (sd>
70.314 290,327 413,911 n.
- ni: service rac:ar 56.5%
A7.0%
34.65 56.5%
47.0%
34.6%
- c. :n2
.uabitt:7 ra::2r
- . :n u Capac1:7 rae::: (: sing :cC x.e) 29.6%
20.1%
14.35
~
- 29. 6 *;
20.1 ';
14.3%
43.55 27.3%
16.2%
and Oura-ion of Iach):
Au2ust 30 - Secterber 30, DUPLICATE DOCUMENT Entire document previously N/A of Scar:aa:
entered into system under:
):
Forecase A.: hies.d ANO S Q<s 9 \\to 6 A.S,9, N/A N/A No. of pages:
N/A N/A cem-a om : N N/A N/A