ML20079F230

Monthly Operating Rept for Dec 1983

ML20079F230
Person / Time
Site:	Fort Saint Vrain
Issue date:	12/31/1983
From:	Fuller C, Warembourg D PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
P-84019, NUDOCS 8401180194
Download: ML20079F230 (9)

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PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION MONTHLY OPERATIONS REPORT NO. 119 December, 1983 I

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This report contains the highlights of the Fort St. Vrain, Unit No. 1, activities operated under the provisions of the Nuclear Regulatory Commission Operating License DPR-34 This report is for the month of January, 1983.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE December began with the reactor operating at approximately 70%

power. Reactor power level was still being restricted due to 1C Boiler Feed Pump (BFP) problems. New fuel element handling continued with loading of the fuel storage wells for the upcoming refueling outage. The turbine generator was producing approximately 200 MWe, At 0530 hours0.00613 days <br />0.147 hours <br />8.763227e-4 weeks <br />2.01665e-4 months <br /> on December 8, 1983, while experiencing high velocity chinook winds, the deluge system on the Reserve Auxiliary Transformer (RAT) activateds This caused the loss of the RAT and an upset in the Reactor Building HVAC system, resulting in less than adequate ventilation cooling to the Prestressed Concrete Reactor Vessel bottom head region. The higher temperature, combined with previously tripped ultrasonic detectors, activated the steam pipe rupture detection circuitry and resulted in a Loop II Plant Protective System shutdown.

Immediately following the loop shutdown, one of the remaining N

circulators in Loop I (IA circulator) tripped on program speed.

This placed the reactor in a one-circulator flow condition. The Shift Supervisor elected to manually scram the reactor and trip the turbine generator.

Later in the morning of December 8, 1983 Loop I was cooled for repairs to a main steam relief valve, V-2215. At 1415 hours0.0164 days <br />0.393 hours <br />0.00234 weeks <br />5.384075e-4 months <br />, Loop II recovery commenced. As recovery operations continued with Loop II, the pressure control valve, PV-22130-1, was operating erratically and it was decided to return Loop II to a shutdown condition to permit repairs.

As maintenance continued on Loop II, a reactor startup commenced on Loop I at 2117 hours0.0245 days <br />0.588 hours <br />0.0035 weeks <br />8.055185e-4 months <br /> on December 9, 1983. The reactor achieved criticality at 2237 hours0.0259 days <br />0.621 hours <br />0.0037 weeks <br />8.511785e-4 months <br /> the same cay. At 0510 hours0.0059 days <br />0.142 hours <br />8.43254e-4 weeks <br />1.94055e-4 months <br /> on December 10, 1983, Loop II was recovered. Warm-up of the turbine generator began at 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br />.

At 0308 hours0.00356 days <br />0.0856 hours <br />5.092593e-4 weeks <br />1.17194e-4 months <br /> on December 11, 1983, the turbine generator was again synchronized to the distribution system. Reactor power was returned to approximately 70% by 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br /> the same day.

The IC Boiler Feed Pump problems continued to restrict reactor power.

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Late in the day on December 15, 1983, the #5 hot reheat heaoer bypass valve opened for no apparent reason. After approximately 10 minutes, the valve reciosed by itself. Results department personnel investigated and found no problems, but at 0605 hours0.007 days <br />0.168 hours <br />0.001 weeks <br />2.302025e-4 months <br /> on December 18, 1983, the same valve opened on it's own power again. At 1830 hours0.0212 days <br />0.508 hours <br />0.00303 weeks <br />6.96315e-4 months <br /> the same day, reactor power was reduced in preparation for repairs to the bypass valve. At 2225 hours0.0258 days <br />0.618 hours <br />0.00368 weeks <br />8.466125e-4 months <br />, the turbine generator was tripped and repairs commenced. The repairs were made, and the turbine was resynchronized at 2327

hours.

i At 0603 hours0.00698 days <br />0.168 hours <br />9.970238e-4 weeks <br />2.294415e-4 months <br /> on December 19, 1983, with reactor power back near 70%, warming operations on 1C boiler feed pump were initiated to  :

begin testing. Again, IC boiler feed pump failed to perform as ,

required.

The remainder of December saw the reactor at or near 70% power with the turbine generating near 200 MWe. The IB boiler feed pump performance began showing indications of slow degradation.

Capacity checks were being run daily to keep track of 't's status.

The installation of the new 4160/480 Volt transformers took place with the delivery of much of the electrical bus change-out materials.

2.0 SINGLE RELEASES OF RADI0 ACTIVITY OR RADIATION EXPOSURE IN EXCFSS 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 rep 0RT Attached l

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. TSP-3 Attechewnt-35 Itsue 2 9 P t ge 1 of I cPERA !NC DATA RrPCR LOCKt: SO. 50-267 DAtt January 10. 1984 CCc .tne si Chuck Fuller itLtruost (303) 785-2224 erteA :s: : Airs sorts

1. Unit Name: ForC St. Vrain

2. Reporting period: 831201 thru 831231

3. Licensed Thermal Power ($t); 842

4. Nameplate Rating (Cross HWe): 342

5. Design tiectrical Rating (Net We): 330

6. Naimum Dependable Capacity (Gross We): 342

7. Maximum Dependable Capacity (Net We): 330 S. If Changes occur in Capacity Ratings (1tecs Number 3 Through 7) Since Last Report, Cive Reasons:

None

9. Power Level To 1thich Restricted, If Any (Net We): 231

10. Reasona for Restrtettons, if any: Restriction to 70% pending resolution of contractual matters.

This Month Tear to Date Cuwlative

11. Hours in Reporting Period 744 8,760 39,481

12. Number of Hours Reactor k'as Critical 703.6 6.080.6 25,827.3

n. Reacter Reserve shutdown sours 0.0 0.0 0.0

11. . wours cenerator on-Line 671.6 4,628.7 17,803.2

15. tnit Reserve shutdown Hours 0.0 0.0 0.0

16. Gross Thornal Energ" Cenerated (>Lm) 396,898.1 ,580,332.2 9,521,317.6 _

17. cross ti ctrical Energy cenerated (>c.m) 130,463 826.546 3.153.450

15. set taestrical Inergy cenerated (>Lm) 122.223 _ 748.420 2,871.530

19. tnit senice tacter 90.3 52.8 45.1

20. Unit Availability Factor 90.3 52.8 45.1

21. Unit Capacity Tactor (Lising MDC Net) 49.8 25.9 22.0

22. twit Capacity raetor (csins DER set) 49.8 25.9 22.0

23. tntt rorced outage Rate 9.7 47.2 39.9 24 Shutdowns Scheduled Over Next 6 Months (Type. Date, and Duration of tach): Refueling 1-20-84 throuch 4-18-84. 2,f 0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />.

23. If Snut Down at tr.d of * >rt Period, tsti=ated Date of Startup: N/A 2 ti . Units In Test Statua (Prior to Cour.ercial Operation): Forecast Achieved Ixt:tA:. Cni: CAL:n N/A N/A INITIAL ELECTRIC::: N/A N/A Cc:e:IsCIAL crIAAT:oN N/A N/A eP

TSP-3 43 Att achment-3A AVERAGE DAILY UNIT POWER LEVEL Issue 2

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Docket No. 50-267 Unit Fort St. Vrain Date January 10, 1984 Completed By Chuck Fuller Telephone (303) 785-2224 1

Month December 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL.

(MWe-Net) (MWe-Net) 1 188.4 17 186.0 2 188.0 18 140.0 3 188.4 19 168.8 4 188.8 20 187.3 5 188.5 21 187.9 6 188.7 22 187.2 7 188.9 23 181.9 8 40.0 24 189.1 9 0.0 25 184.7 10 0.0 26 184.8 11 108.6 27 184.7 12 184.2 28 183.3 13 187.0 29 180.8 14 187.0 30 181.0 15 187.5 31 180.3 16 186.5

• Generator on line but no net generation.

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UNir sutrTrwNs Ano ~~ rWER REIRCRWIS~~~

r >cRrf en. 50-267 unit NAt E Fort St. Vrain

, oAiE January _10, 1984 cotri.t.trn ny Chuck Fuller REroRT HoNus December 1983 TrtrrIDINE (303) 785-2224 9,

I SHUTTINC DOWN SYS fl fl OW6'ONINT Nt), DATE TTFE BR'RATIttN REASON REACTOR LER f CODE (UDE cal'SE AND 01RRFCTIVE ACTION Til rRt.VI.NT 4trCliRRENCE 83-

, 024 831208 F 69.1 H 1 N/A ABC ZZZZZZ Manual scram following activation of firewater deluge for the Reserve Auxiliary Transfurmer.83-025 831218 F.- 3.3 B 4 N/A HBE VAINEX Repaired #5 hot reheat header bypass valve, the reactor remained critical,

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i gr REFUELING INFORMATION I

I I I l 1. Name of Facility l Fort St. Vrain Unit No. 1 l l l l l 2. Scheduled date for next l January 20, 1984 l l refueling shutdown. l l l l 1 l 3. Scheduled date for restart l April 19, 1984 l l followina refuelino. I l l I I l 4. Will refueling or resumption ofi l l operation thereafter require a l l l technical specification change l l l or other license amendment? I Yes l l l l l If answer is yes, what, in l l l general, will these be? I Use of type H-451 graphite. l 1 l l l If answer is no, has the reload l l l fuel design and core configura-l l l tion been reviewed by your l l l Plant Safety Review Committee [ --------------------- I

l. to determine whether any unre- l l l vicwed safety questions are l l l associated with the core reloadj l 1 (Reference 10 CFR Section l l 1 50.59)? I l l l l l If no such review has taken l -------------------- - l l place, when is it scheduled? I l 1 I . I l 5. Scheduled date(s) for submit- l l l ting proposed licensing action l Net scheduled at this time; I l and supporting information. I to be determined. l 1 l l l 6. Important licensir.g considera- l l l tions associated with refuel- l l l ing, e.g., new or different l l 1

l fuel design or supplier, unre- l --------------------- l l viewed design or performance l l l analysis methods, significant l l l changes in fuel design, new l l l oper ating procedures. l l l l l l 7. The rumber of fuel assemblies l l l (a) in the core and (b) in the i 1482 HTGR fuel elements. l l spent fuel sterage pool. I 11 Spent HTGR fuel elements. l 1

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REFUELING INFORMATION (CONTINUED) l l i l 8. Tne present licensed spent fuell l l pool storage capacity and the l l l size of any increase in l Capacity is limited in size to l l licensed storage capacity that l about one-third of core l l has been requested or is j (approximately 500 HTGR elements).l

, l planned, in number of fuel l No change is planned. l ,

I assemblies. l l i l l l ,

l 9. The projected date of the last l 1992 under Agreements AT(04-3)-6331 i l refueling that can be dis- l and DE-SC07-79ID01370 between l I charged to the spent fuel pool l Public Service Company of l l assuming the present licensed l Colorado, and General Atomic l l capacity. I Company, and DOE.* l The 1992 estimated date is based on the understanding that spent fuel discharged during the term of the Agreements will be stored by DOE at the Idaho Chemical Processing Plant. The storage capacity has evidently been sized to accomodate eight fuel segments. It is estimated that the eighth fuel segment will be discharged in 1992.

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16805 WCR 19 1/2, Platteville, Colorado 80651 January 13, 1984 Fort St. Vrain Unit #1 P-84019 Office of Inspection and Enforcement ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, D.C. 20555

Reference:

Facility Operating License No. OPR-34 Docket Nc. 50-267

Dear Sir:

Enclosed please find our Monthly Operations Report for the month of December, 1983.

Very truly yours, 0' /Yauds Don Warembourg Managar, Nuclear Production Enclosure cc: Mr. John T. Collins DWW/djm y e 9"'+

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