ML20005B823

Monthly Operating Rept for Jul 1981

ML20005B823
Person / Time
Site:	Fort Saint Vrain
Issue date:	08/03/1981
From:	Mcbride L PUBLIC SERVICE CO. OF COLORADO
To:
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ML20005B817	List: ML20005B816 ML20005B823
References
NUDOCS 8109020312
Download: ML20005B823 (10)

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PUBLIC SERVICE C0ftPAfiY OF COLORADO FORT ST. VRAlti ilVCLEAR GEllERATII4G STATIO!!

M0flTHLY OPERATI0lls REPORT Il0. 91 JULY, 1981 s

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v 21 8109020312 810827 DR ADOCK 05000267 PDR

~s This report contains the highlights of the Fort St. Vrain Unit No. 1, activities operated under the provisions of the Nuclear Regulatory y

Commission Operating License DPR-34.

This report is for the month of July, 1981.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY--

RELATCD MAINTENANCE 1.1 Summary The refueling efforts continued until July 6, when the last load of fuel was put in region 32.

The installation of the new "B" circulator and other shutdown maintenance activities prevented star;-up until July 13th.

The reactor was brought critical on July 13th in preparation for the training starts by the reactor operator candidates.

These starts were administered by the NRC beginning July 14th. The reactivity discrepancy between the. observed and predicted criticality was.006 ap which exceeded the +

.003 ao administrative limit. The reason for the unusually large discrepancy has been resolved.

A scran, on h'gh moisture was received on July 16th when a high levei ~aisture monitor spuriously tripped.

The reactor was brought critical again in 4 1/2 hours.

The reactor power was increased to about 25% on July 22nd.

The turbine generator was synchronized for testing to verify that the repairs made during the shutdown had solvea the vibration problem.

Power was then reduced to facilitate clean-up of the reactor primary coolant.

A loop 1 shutdown occurred on July 23rd when all of the loop 1 normal bearing water pumps tripped due to low surge tank level.

The back-ep bearing water system was fully operational and the resultant bearing water accumulator firing int cduced moisture into the vessel.

The reactor was pumped dow' through the purification system to remcve as much moist e as possible.

The high moisture levels in the PCRV prevented increasing reactor power enough to roll the turbine generator until July 26th. The turbine was on line for the remainder of the month at about 85 MW with moisture concentration precluding any further power increase.

1.2 Operations j

The last load of fuel was put in region 32 on July 6th.

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This completed the actual fuel loading but further 5

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preparations remained before the vessel could be pressurized.

Clean-up of water chemistry for the secondary side was started on July 7th.

Both steam generator loops were dumped later that day in an attempt to improve the water quality.

Durin, the process of dumping there was a short 30 minute period where all cooling was stopped because both loops were draining simultaneously.

It was necessary to drain the steam generators several more times before the correct water chemistry wre obtained.

The PCRV was evacuated July 8th with the purge vacuum pumps and backfilled with helium to a pressure of 85 psi on July 10th.

A purification system train was put in service at that time to improve primary coolant clean up.

The liquid nitrogen system was purged'with gaseous nitrogen and then cooled down with liquid on July 13 following repairs on the system.

Both high level monitors were put in service after filling tne dewars using the initial ff :1 piping.

The reactor was then brought critical at 2202 that day in preparation for operator qualification training

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starts.

The observed reactivity discrepancy between the calculated and predicted rod heights represented 0.0067 Ap which exceeded the 0.003 ap allowed without management authorization.

This permission was then obtained and the reactor remained critical.

General Atomic and Public Service Company had been in discussions about the predicted rod height calculation.

The conclusion was drawn that the discrepancy was primarily due to utilizing estimated core burn-up figures in calculating the base reactivity rather than the actual burn-up figure.

Operator training starts for the reactor operator qualification procedure were administered by the NRC beginning July 14, and the reactor remained less than 2%.

The written and walk around portions of this qualificat'.an procedure were completed later in July.

A two loop trouble scram caused by a spurious trip of a high level moisttre monitor occurred at 1515 on July 16th.

The reactor power level at the time was 1% and the reactor was again critical at 1952.

The reactor power was gradually increased as allowed by moisture limitations until July 22nd when the turbine generator was synchronized at 0008.

The turbine testing was

.i completed in 2 1/2 hours and test results verified that the vibration problem had been resolved by the repairs made to s

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. 3 the low pressure turbine blading.

The power increase to synchronize the turbine caused the moisture to increase and the power was reduced to 14% after the testing was completed.

Reactor power was increased on July 23rd and the turbine synchronized at 2025. All the bearing water pumps in loop 1 tripped at 2232 due to low level in the surge tank. This caused both circulators to trip and resulted in a loop 1 shutdown.

The bearing water accumulators fired during the circulator shutdown and moisture was introduced into the vessel.

The trip of the bearing water pumps on low surge tank level occurred when P-2105 was taken out of service and there was inadequate pressure available on the emergency feedwater header to supply sufficient make-up to maintain normal level in the surge tank.

Reactor power was then reduced to 2% to put loop 1 in service.

The reactor was pumped down to storage through the purification train on July 24th and repressurized on July 25th in an attempt to remove the moisture introduced during the circulator trips on July 23rd.

The reactor power was again gradually increased till 1834 on July 26th when turbine was synchronized and loaded to 68 MW.

The load was gradually increased to 83 MW on July 26th and was held there due to moisture limitations.

"D" circulator tripped on July 29th when POV-2192, a back-up bearing water control valve, inadvertently opened. A buffer system upset caused the circulator to trip.

"C" circulator properly compensated for the loss of "D" and no significant change in power was observed.

"D" circulator was then restarted without any problems.

"B" circulator tripped on buffer /mid buffer on July 30th when the knock out pots on the sensing line for buffer instrumentation were being blown cown.

No significant change in reactor power was observed after the trip and the i

circulator was immediately restarted.

The reactor power at month's end was being held at 31.8%,

87 MW because of high moisture in the primary coolant and the limitation of LCO 4.2.11.

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. 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 Attached 3

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OPtumC dan RDORT DOCKZT NO.

50-267 DAT: _ 810803 L. M. McBrike C0xPI.rIID sY TELEPHONE (303) 785-2224 CPERA U NC STATUS Norms 1.

Unit Names Fort St. Vrain 2.

Esporting Period 310701 through 810731 3.

Licensed Ihermal Power (,Wt):

842

7.. Nameplate Racing (,Grose We):

342 5.

Oeeign Electrical Racing (Nec W e):

330 6.

Faw4== Dependable Capacity (Cross We):

342 7.

Faw4== Dependable Capacity (Net We):

330 3.

If Changee occur in Capacity Ratings (Itene Nueber 3 Through 7) Since I.ast Report, Cive Reasons:

None 7.

Power t.evel To *.1tich Restricted If Any (Net We)t 231 10.

Raasone for Restrictions, If Any:

NRC restriction 70% nendine resolution of temperature fluxuations.

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This % nth Year to Date Cumulative

11. Hours in Raporting Period 744 5.087 19.198

12. Number of Hours Raaetor Was Critical 391.2 1.056.7 1'_101.0 L3.

Reactor Reserve Shutdown Hours 0.0 0n n_n 16.

Hours knerator on-Line 130.0

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13. Unit Reserve Shutdown Hours 0.0 on nn l

16.

Gross Thersel Energy Generated (NE) 96 979.1 1 194 ala-Q 1_967 CO7 7

17. Grose Electrical Energy Generated (WE) 10.441 410 9RR 1 999 AR9

13. Net Electrical Energy Generated 053E) 4.172 171.477 1.'7' 779

19. Unit Service Factor 17.5 44.5 al 5 23.

Unit Ava'iability Factor 17.5

&6.s 43.5 l

21. Cnic Capacity Factor (Using MDC Net) 1.7 22.2 19.4 I2.

Unit Capacity Factor (Using DElt Net) 1.7 22.2 19.4

23. Unic Forced cutage Race 34.3 35.7 16.o 26.

Shutdowns Scheduled over Next 6 maths (Type. Date, and Duration of tach):

Maintenance /r.oM fication shutdown September 1, 1981 lasting 4 months.

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15.

If Shut Down at End of Report Period, Estimated Date of Startup:

N/A 16.

Units In Test Status (Prior to Coursreial operation):

Forecast Achieved INITIAL CRITICALITT

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'I/ A INITuL ELICTRIC m N/A

'i/ A C xxzRCu L cert m cw N/A

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AVERAG1: DAILY UNIT POWER LEVEL Docket No.

50-267 Unit Fort St. Vrain Date 810803 Completed By L. M. McBride Telephone (303) 785-2224 Month July, 1981 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) i 1

0.0 17 0.0 2

0.0 18 0.0 3

0.0 19 0.0 4

0.0 20 0.0 5

o_o 21 0.0 6

0.0 22 0.0*

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oo 23 0.0*

8 on 24 2.88 t

9 0.0 25 0.0 10 n.0 26 0.0 11 on 27 61.o6 12 0.0 28 71.o 2 l

13 0.0 29 70.33 14 0.0 30 74.71 15 0.0 31 79.54 16 0.0

• Generator on line but no 'nat generation, l

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REFUELING INFORMATION 1.

Name of Faciliev.

Fort St. Vrain Unit No. 1 2.

Scheduled date for next refueling shutdown.

October 1, 1982 3.

Scheduled date for restart following refueling.

December 1. 1982 4

Will refueling or resumption of operation thereafter require a te Duical specification change or other license amendment?

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 Connittee to deter-mine whether any unreviewed safetf questions are associated The Plant Operations Review Committee will l

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with the core reload (Reference review any questions associated with the 10CFR Section 50.59)?

reload.

If no such review has e an place, when is it schee. Aled?

May 1, 1981 5.

Scheduled date(s) for submitting proposed licensing action and supporting information.

6.

Important licensing considera-tions associated with refueling, e.g., new or different fuel de-sign or supplier, unreviewed I

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 (b) in the spent fuel _ storage cool.

250 spent HTGR tuel elements 8.

The present licensed spent fuel pool storage capacity and the Capacity is lisited in size to about one-size of any increase in licensed third of core (approximately 500 HTGR storage capacity that has been elements).

No change is planned.

requested or is planned, in number of fuel assemblies.

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't'.'7UZI.EE CTF010fATION (C::NT21UED) 9.

Sie projected date of the 1986 under -Jte Three Par:y Agreement (Con-last refueling. that can be tract Ar (04-3)-633) between DOE, Public Ad --h=*ged a che spent-fuel Sarrice Company of Colorado (?Sco), and pool assuming the present General Atomic Company.*

licensed canaci:v.

• The 1986 date is based on the understanding : hat spene fuel discharged durdng-the ers of the Three Party Agreement wdii be shipped :o the Idaho National Engineering Laboratory for storage by DCE ac the Idaho Ch*1 Processing Plant (ICPP). The storage capacity has evidently been sized to accomodate fuel which is expected :o be dd ark =rged during the eight year period covered by the Three Par:y Agreement.

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