ML19312E671

Monthly Operating Rept for Apr 1980

ML19312E671
Person / Time
Site:	Fort Saint Vrain
Issue date:	05/29/1980
From:	PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML19312E670	List: ML19312E669 ML19312E671
References
NUDOCS 8006090381
Download: ML19312E671 (9)

Text

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O PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATUiG STATION 1

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MONTHLY OPERATIONS REPORT NO. 76 APRIL, 1980 l l

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This report contains the highlights of the Fort St. Vrain, Unit No. 1 activi-ties, operated under the provisions of the Nuclear Regulatory Commission Operating License, DPR-34 This report is for he month of April,1980, 1.0 NARRATIVE SUlefARY OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE 1.1 S ummary On April 1,1980, the reactor power was increased from 45% to 60%,

190 megawatts electrical, and held approximately at this level pending cleanup of the nrimary coolant oxidants.

"D" circulating water pump expansion bellows ruptured and required isolation pending repair.'

Experienced problems with the reverse osmosis unit in that the re-jection rate was unacceptable. The unit was chemically cleaned, and the membrane seals were replaced on April 2, which corrected l the problem.

On April 2,1980, problems developed with the backup bearing water system, which was traced to improperly working control valvea. The problem was corrected and backup bearing water system vas placed l in service.

On April 4,1980, reactor power was being maintained at 68 mega-watts when total oxidants increased sharply to approximately 50 ppm. l Electrical load was reduced to 185 megawatts. The sudden increase in oxidants is believed to be caused by a malfunctioning helium recovery compressor. The buffer flows to all circulators were re-duced and the recovery compressors vented. By April 5, primary  !

coolant oxidants were reduced to 40 ppm, with reactor power being maintained at 56%. During this period, "B" circulator buffer j knock-out pot required draining frequently. One attempt to drain <

the knock-out pot resulted in tripping "B" circulator off line. l "B" circulator was recovered for normal operation. At this time, (April 7), it was decided to take "B" circulator down to investigate '

what effects it might have on the ability to reduce total oxidants. '

On April 8,1980, while operating at 150 megawatts electrical, a i loop shutdown was received during an attempt to restart "B" circu- '

lator. The recovery of the loop was severely hampered by frequent loss of power to secondary coolant drain path valves. Utis loss of power was caused by blown fuses. A testing system, which is still in progress, was initiated to determine the cause. {

j The loop was recovered and reactor power was increased to support 65 megawatts electrical load on April 9, 1980. Region outlet

temperatures were being controlled below 1200*F until total oxi-3

dants decreased below 10 ppm. Reactor power was changed over the next few days between 30% and 65% as dictated by primary coolant

{ oxidant levels. The "B" and "C" circulators were removed from i

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1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED 1 MAINTENANCE (Cont'd) i 1.1 Summarv (Cont'd) service during this period (April 10 to April 18, 1980) to observe the effect, if any, on moisture ingress. No effect was observed. .

On April 18, 1980, while operating at 35% power, a turbine trip occurred from a spurious signal from the plant protective system while changing out a logic module. The same day, a Loop 1 shut-down occurred when buffer supply was disturbed to Loop 1 circulators caused by the relief action of "A" circulator penetration rupture disk.

l The reactor remained in a low power condition (2% to 10%) until April 21, 1980, to allow license candidates to complete required  !

Nuclear Regulatory Commission reactor starts.

Reactor power was raised to approximately 30% on April 23. On this l date, "B" circulator tripped from seal malfunction problems. The l circul- sr was restarted and power raised to 50% until an increase in or . ants required lowering region outlet temperature below 1200*F.

On April 25, a loop shutdown occurred, caused by a faulty plant protective logic module. The loop was recovered and reactor power was increased to approximately 30%.

The plant was shutdown to one loop operation on April 28, 1980, again due to a malfunction in the plant protective system. Investi-gation revealed a failed chip in a logic module. The loop was recovered and load increased to 130 megawatts.

On April 30, 1980, another loop shutdown occurred when "A" and "B" bearing water pumps tripped off as a result of construction work being performed in the area of the Loop 1 surge tank. Recovery of the loop was accomplished, and the load was increased to approximately 130 megawatts.

1.2 Testing Testing completed during the month of April, 1980, was the normally scheduled Surveillance Tests.

2.0 SINGLE RELEASES OF RADIOACTIVITY OR RADIATION EXPOSURE IN EXCESS OF 10%

OF THE ALLOWABLE ANNUAL VALUE None

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3.0 INDICATION OF FAILED FUEL RESULTING FROM IRRADIATED FUEL EXAMINATIONS 5

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% None 1

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y --- -- ------,.- - - --- - - - - - -

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4.0 MONTHLY OPERATING DATA REPORT Attached e

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CP!RAnNC OATA RDOR* DOCKET NO. 50-267 DA;z 800502 ccurt.z:so at J. W. Gahm Tr:.truoNr (303) 785-2253 OPERAT!':C 3?Att3 NOT!S

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• Name: Fort S t. Vrain

2. asportins Period: 800401 through 800430

3. L! ceased Thermal Fover OSit): 842

4. Nameplate Rating (Cross We): 342

5. Design Electrical 1 ting Cret se): 330

6. Maxista Ospendable Capacity (Cross 2Sie): 342

7. Maximum Oependable Capacity Clet We): 330

8. If Changes occur in Capacity natings (Items humber 3 Through 7) Since Last Report, Cive Reasons:

None

9. Fover Level To *4hich Restricted, If Any (Net We): 231

10. asasons for anscrictions, If Any: Nuclear Regulatory C, mmission restriction 70% pending resolution of temoerature fluctuations.

l This Month Year to Date Cumalative

11. Hours is asporting Period 719 2,903 7,320

12. Nummer of sours anactor was critical 697.0 1,560.9 4,093.7

13. Reactor asserve shutdova aours 0.0 0.0 0.0

14. sours Generator on-L1=e 551.3 909.3 1,891.5 <

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15. cait asserv shutdova sours 0.0 0.0 0.0 l

16. Gross "hermal !sergy Generated (5H) 245,462 406,611 884,566

17. Cross Electrical Isergy Generated Osm) 80,351 128,778 269,574

13. Net Electrical Energy Generated Osm) 74,589 117,636 241,220 -

19. Unit Service raetor 76.7 31.3 25.8

0. enic Availabt11er rector 76.7 31.3 25.8

21. Cait Capacity Tactor (Using MDC lre:) 31.4 12.3 10.0

22. enic Capacity Factor (Usiss DER Net) 31.4 12.3 10.0

23. Ltic Forced Outage Rate 23.3 _ 33.1* 54.7*

l 24 Shutdowns Scheduled over : Text 6 Months (Type Date, and Duration of Zach): N/A

23. If Shut Down at End of Report Period. Estimated Oate of Startup: N/A

*These numbers reflect the correction of an error in the March,1980, report.

26. Onits Is !ast Status (Prior to Cameercial Operation): Forecsse Achieved I:rInAL 02I:: CAL::T N/A N/A

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AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-267 Unie Fort S t. Vrain Date 800502 Completed By J. U. Gahm Telephone (303) 785-2253 _

Month Ac ril, 1980 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 166 17 80 2 202 18 48 3 215 19 0 4 190 20 0 5 172 21 0 6 172 22 0 7 154 23 15 _ . . .

8 92 24 77 9 0 25 85 10 101 26 105 11 124 27 120 12 125 28 124 .

13 124 29 123 14 149 30 55 15 172 31 N/A 16 149

• Generator on line but no ' net generation,

REFUELING INFOLVATION , 0

1. Name of Facility. Fort S t. Vrain, Unit No. 1

2. Scheduled date for next refueling shutdown. January 1, 1981

3. Scheduled date for restar

• following refueling. March 1, 1981

4. Will refueling or resumption of operation thereafter require a technical specification change or other license a=end=ent? No If answer is yes, what, in general, will these be?

If answer is no, has the reload The Plant Operations Review Co==ittee will fuel design and core configura- review any questions associated with the tion been reviewed by your Plant core reload.

Safety Review Committee to deter-mine whether any unreviewed safety questions are associated with the core reload (Reference 10CFR Section 50.59)? ,

If.no such review has taken place, when is it scheduled? July 1, 1980

5. Scheduled date(s) for submitting --- ---

proposed licensing action and l supoorting information.

6. Important licensing considera- -- --

tions associated with refueling,  ;

e.g., new or different fuel de-sign or supplier, unreviewed {

design or performance analysis methods, significant changes in fuel design, new operating pro-cedures.

7. The number of fuel assemblies a) 1482 HTGR fuel ele =ents.

(a) in the core and (b) in the spent fuel storage pool. b) 244 spent HTGR fuel ela=ents.

3. The present licensed spent fuel Capacity is limited in size to about one-pool storage capacity and the third of core (approx 1=ately 500 HTGR size of any increase in licensed eierents) . No change is planned.

storage capacity that has been requested or is planned, in number of fuel assemblies.

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4 REFUELING INFORMATION (CONTINUED)

9. The projected date of the 1986 under the Three Party Agreement (Con-last refueling that can be tract AT (04-3)-633) between DOE, Public discharged to the spent fuel Service Company of Colorado (PSco), and pool assuntag the present General Atomic Company.*

licensed capacity. *

• The 1986 date is based on the understanding that spent fuel discharged during the term of the Three Party Agreement will be shipped to the Idaho National Engineering Laboratory for storage by DOE at the Idaho Chemical Processing Plant (ICPP). The storage capacity has evidently been sized to accomodate fuel which is expected to be discharged during the eight year period covered by the Three Party Agreement.

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