ML20010J025
| ML20010J025 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 09/01/1981 |
| From: | PUBLIC SERVICE CO. OF COLORADO |
| To: | |
| Shared Package | |
| ML20010J021 | List: |
| References | |
| NUDOCS 8109290515 | |
| Download: ML20010J025 (9) | |
Text
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PUBLIC SERVICE C0fiPAi4Y OF COLOPADO FORT ST. VRAlli ilVCLEAR GE!1ERATIllG STATION M014THLY OPERATI0f4S REPORT 110, 92 AUGUST, 1981 e
3 2 2109290515 810921
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, This report contains the highlights of the Fort St. Vrain Unit No. 1, activities operated under the provisions of tr e Nuclear Regulatory Commission Operating License DPR-34. This repcrt is for the month of August, 1981.
1.0 NARRATIVE
SUMMARY
OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE 1.1 Summary The turbine load was increased from 90 MW to 140 MW on August 2, 1981, but high vibration on the #3 bearing delayed ,
any further increase in load. The vibration was traced to an oil whip problem and the power was increased to 240 MW or 70% on August 5, 1981.
A hydraulic oil leak on tne 1A circulator steam turbine speed valve (SV-2105) resulted in a power reduction to 50%
on August 11. This valve was repaired and the reactor power returned to 70% on August 13.
Two spurious turbine generator runbacks to 50% power occurred, one on August 17 and one on August 18. A faulty relay driver in the Plent Protective System was found to be the source of these runbacks.
A test of the plant's radiological response was held on August 12, followed by a critique on August 13, with the outside agencies involved.
Another hydraulic oil leak was discovered on SV-2105 on PJgust 26. The reactor power was reduced to a three circulator operation configuration at a power level of 50%.
When the 1A circulator was tripped, a transient in the cold reheat header pressure caused loop II to shutdown and a turbine load excursion :aused a scram on two loop trouble.
A small fire occurred in the reactor building on August 26, I while construction workers were welding. Subsequent investigations revealed th;s damage had been done to about j 29 cables in a tray. Repairs and check out of these cables i took until 2000, August 30, 1981.
Reactor power was increased to 26% on August 31, and the turbine generator was synchronized at 0435, September 1, 1981.
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I vd 1.2 Operations The reactor power was held at 32% on August 1, due to high moisture in the primary coolant. An investigation on August 2, re;ealed suspiciously high moisture readings from the analytic moisture monitors and two Plant Protective System (PPS) moisture monitors were determined to be a more accurate measurement of moisture concentrations.
The turbine load was then increased to 140 MW when high vibration on the #3 bearing was discovered. A leaky valve in the exhaust load cooling soray system was found and this allowed increasing power to 175 MW on August 3. Once again, however, the #3 bearing vibration became excessive.
Mark Habam, Maintenance and Engineering Services, investigated the problem and in analyzing the nature of the vibration suspected an oil whip in the bearing. The lube oil temperatures were increased by 10*F leaving the hottest bearing drain temperature at 160 F. 'This eliminated the excessive vibration and the load was then increased to 240 MW or about 70% power. >
On August 11, 1981, a hydraulic oil leak on the 1A circulator steam turbine speed valve (SV-2105) became serious enough that it required shutting down the circulator to facilitate maintenance. This required a reduction in power to 50% from 1700, August 11, until 0600 on August 13, when the circulator was returned to service and the power increased to 70%.
A test of the plant and the Company's response to a radiological emergency was held on August 12, 1981, beginning at 0645 and ending about 1300. A critique was held on August 13, with the numerous local, state, and federal agencies involved in handling such an emergency.
This was then followed by an evaluation and appraisal of the Company's response performed by the NRC.
A spurious turbine generator runback to 50% occurred on i
l August 17, during surveillance testing of the PPS. the source of the runback could not be identified and the power was returned to 70% in 1 1/2 hours. A similar runback occurred on August 18, and the problem was traced to a l faulty relay driver module. This module was replaced and,
~a fter further tests, the power was again returned to 70%.
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. A hydraulic oil leak, again on SV-2105, became excessive' on 3 August 26, and it became necessary to take the circulator
- out of service. The reactor power was subsequently reduced l
to Sb% in preparation for tripping the circulator. When the l 5
circulator was tripped, a transient in the cold reheat header pressure caused loop II helium circulator to shutdown when both loop II steam turbines tripped due to abnormally high speeds. A rapid turbine load increase to 33% following a drop in throttle pressu e caused a rapid decrease in the loop I main steam temperature which resulted in a two loop trouble reactor scram. Analysis of the transient has resulted in a change to the pressure ratio controller bias on circulator trip and a proposed change to the initial pressure regulating and runback circuit of the turbine. -
A small fire occurred in the reactor building in the afternoon of August 26, while construction workers were welding. Welding sparks ignited a a4d containing hydraulic oil and the resultant fire did some damage to about 29 cables in a tray located above this mat. later inspections revealed only the outer coating of insulation to be damaged and the conductors intact. Temporary repairs were then made to the affected cables.
The reactor was orought critical at 1112 on August 27, and an agreement with the NRC was reached that the reactor would be limited to less than 2% power pending the completion of a final evaluation and permanent repair of damaged cables.
Those cables were then determinated, meggered for possible damage, reterminated and functionally tested. Repairs were made to 6 cables by installing junction boxes, and permanent repairs to the 23 remaining cables were completed per an approved procedure.
The cable repairs were completed at 2000 on August 30, 1981, and the reactor power was then increased. The turbine generator was synchronized at 0435, September 1, 1981, with the reactor operating at 30% power.
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 FROM IRRADIATED FUEL EXAMINATIONS None 4.0 MONTHLY OPERATING DATA REPORT i Attached
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cPth TING DATA RIPo E MCIZT No.50-26T sT: 810901 COMPLE:ZD sr L. M. McBride TzLI= HONE (303) 785-2224 otrunsc snT-s Notz:
- 1. cnic same Fort St. Vrain
- 2. Reporting Period: 810801 through 810831
- 3. Licensed :rnemel Power Out): 842
- 4. Nameplate ? *ng (,Grose m e):
. 342
- 5. Denia :.' .ctr> al nacins Clet We): 330 ,.
- 6. ParN= Dependable Capacity (cross We): 342
- 7. Mad == Dependable Capacity Clet We): 330 S. If Changes occur in Capacity 2atinge (Items Number 3 Throush 7) Since Leet Report, Give Reasone:
None
- 9. Power Level To Which Restricted, If Any Clet We): 231
- 10. Raaeone for Restrictione, If Any: NRC restriction 70% oendine resolution of temnerature fluctuations.
This Itach Teer to Date Cumulative f
l
- 11. Hours in Reporting Period 744 5.831 19.012
- 12. sumber of souro neector use Critical _
717.9 3,774.6 12.909.8 IJ. Reactor Reserve Shutdown Boure 0.0 0.0 0.0 aoure cenerator o Line 611.9 2,873.4 8,566.7 15.
- 15. enic toestv sh cdown soure 0.0 0.0 0.0 _
- 16. crose Thermal Energy Generated OWE) 330,206.3 1,489.621.2 4.197,.714.0
- 17. crose nectrical Emer:7 cenerated OWa) 128,803 539.691 1.41.'. 485 la. set nectrical Eners, cenerated Oms) 120.753 494.230 _
1.293.531 l 19. Unit Service Factor 82.2% 49.3% 45. 0':
- 20. Unit Availability Factor 82.2% 49.3% 45.0%
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- 21. Cait Capacity Factor (Usig MDC Net) 49.2% 25.7% 20.6%
- 22. cnit capacity rector (Usins Det set) 49.2% 25.7% 20.6%
- 23. Onic Forced outage mate 17.8% 12.6% 35.9%
l l 14. Shutdowne Scheduled Onr Next 6 !batne (Trs o Dete, and Duration of Each): Wintennnee/
nodification shutdot.rn. Octok r 15. 1981. through hnunrv. 10R2_
- 25. If shut Down at End of Report Period. Estimated Date of Startup: l l
- 26. Units In Test Status (P-ior to Commercial operation): Forecent Achieved ;
IETIAL CRInCALITY N/A N/A IETuL zLz=mICITY N/A N/A corazmCut orsxAnos N/A N/A
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l UNIT SHUTDOWNS AND POWER REDUC 1VMS
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suxxET no. 50-267 ,
unir r.NE Fort St. Vrain [j DATE 810901 s COMPLETEo Br L. H. McBride aEP0af Mowns Aunush 1981 TEt.Eruous (303) 785-2224 MEtuon or suuTTimo DUWW SYSTpt Coff008ENT DURATION REAS000 REACTOR LER f CODE Q)DE CAUSE AND CORRECTIVE ACTIOtl T., PREVENT RECURRENCE No. DATE TYPE 81-20 810826 F 26.3 11 3 Turbine trip and reactor scram on two loop trouble while manually shutting down IA helium circulator for maintenance.
77.8 D N/A Minor construction fire resulted in i damage to sever.a1 cables in cable tray ;
and subsequent cable repair. Service of cables waa not lost.
N/A N/A N/A Commenced raise to power after cable 28.0 H N/A repairs completed.
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Summary: Plan to operate at 70% power for the remainder of September, 1981. Will do testing above 70% during the first two weeks in October, 1981.
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- AVERAGE DAILY UNIT POWER LEVEL Docket Ns. 50-267 Unit Fort St. Vrain Date 810901 Completed By T._ M. wen,4a.
Telephone (303) 785-2224 Month August. 1981 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWa-Net) 1 78.92 17 216.38 2 110 gg 18 213.21 0 19n na 19 219.83 4 159.25 20 220.13 5 195.46 21 220.63 s
6 21 R . 61 22 220.13 7 219.58 23 220.42 l
8 220.17 24 225.0 ,
9 219.29 25 226.67 i 10 224.71 26 107.29 l 11 197.75 27 0.O _
12 1as_00 28 0.0 l
i 13 176_71 29 0.0 14 99s_qa -
30 0.0 l 15 223.38 31 0.0 16 221.67
- Generator on line but no ' net generation,
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RE7tTELING INFORMATION
- 1. Name of Faciliev. Fort St. Vrain Unit No. 1
- 2. Schedeled date for next refueling shutdown. October 1, 1982 a
- 3. Scheduled date for restarn following refueling. December 1. 1o82
- 4. Will refueling or resumption of ,
operation thereafter require a -
tech" N i specification change or other license ===ndment? No If answer is yes, what, in general, will these be?
If answer is no, has the reload fuel design and core configura-tion been reviewed by your- Plant Safety Review Committee to deter-zine whether any unreviewed safety questions are associated The Plant Operations Review Commictee will with the core reload (Raference review any questicas associated with the 10C71 Section 50.59)? reload.
If no such review has takan olace, when is it scheduled? May 1. 1982
- 5. Scheduled date(s) for submitting proposed licensing action and 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 1482 HTGR fuel elements (a) in the core and @) in 250 spent HTGR ft;e1 elements the scent fuel storage pool.
- 8. The present_ licensed spent fuel pool storage capacity and the Capacity is limited in size to about one-size of any increase in licensed third of core (approximately 500 HTGR t
storage capacity that has been elements). No change is planned.
I requested or is planned, in l number of fuel assemblies.
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- 9. The profecced. date of the 1986 under the Threa Party Agreement (Con-last ref'!=1**g that est be erset AT (04-3)-633) beeveen DOE, Public A4 = h=eged. to the spent fuel Ser rica Company of. Colorado (?Sco), and.
pool --"*! the present C==emi Atomic Cotgany.* ,
licensed canaciev.
- The 1986 data is based on the unders*=addag. that spene fual Ad eh=*ged during the tazz. of the Three Party Agreemnac vd be shipped to -da Idaho 'Jacional Tap-eing Laboraccry for storage by DOE at the Idaho Ch==4-=1 Proctasing Plac (ICPP) . Ther storsga capacity has evidently been sized to accoiandata fuel which is espected to be discharged during the eight year period covered by the Three Party age-e. ,
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