ML20076D383

Monthly Operating Rept for Apr 1983

ML20076D383
Person / Time
Site:	Fort Saint Vrain
Issue date:	05/10/1983
From:	Fuller C PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML20076D381	List: ML20076D377 ML20076D383
References
NUDOCS 8305230427
Download: ML20076D383 (8)

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PUBLIC SERVICE COMPANY OF COLORADO -

FORT ST. VRAIN NUCLEAR GENERATING STATION t

MONTHLY OPERATIONS REPORT NO. 111 April, 1983 E

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8305230427 830512 PDR ADDCK 05000267 R PDR

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_1 pU 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 April, 1983.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE ,

Mechanical repairs have been the primary consideration at Fort St. Vrain during the month of April, with the reactor shut down as a result of a scram which occurred on March 17, 1983.

18 boiler feedpump has been overhauled and is being reassembled.

Operational testing will commence in mid-May.

Problems with the installation of ID helium circulator reheat flange have been encountered because of the reluctance of a metallic seal to stay in place while hoisting this multi-ton unit into place with a hydraulic ram. A method of " sighting in" the position of this seal prior to hoisting the unit the last few inches has been devised. It is anticipated that the reheat flange will be successfully installed the week of May 9.

HV-2224 main steam stop check valve repair has required rebuilding and stress relieving of the valve and internals.

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4 Repairs have been completed to PV-22129 and PV-22153, Loop 1 depressurizing valves.

1B main condensate pump is being overhauled at this time.

The problem concerning the accumulation of excessive amount of liquid waste has been resolved by two corrective actions.

First, Sulphur 35 was identified as the restrictive isotope in the Reactor Building sump contents. This allowed release of the i liquid at a higher rate. Second, liquid waste from the l purification trains and regeneration train knock-out pots is being detrained to carboys for future disposal. This allows the release of lesser contaminated liquid from the liquid waste receivers with a very short holdup time being required.

The test of an " ultra-filtration" unit for removal of colloidal fron from condensate has proven successful. Further testing during startup conditions will be conducted.

2.0 SINGLE RELEASES OF RADIOACTIVITY OR RADIATION EXPOSURE IN EXCESS OF 107, OF THE ALLOWABLE ANNUAL VALUE None l E l

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3.0 INDICATION OF FAILED FUEL RESULTING FROM IRRADIATED FUEL EXAMINATIONS None 4.0 MONTHLY OPERATING DATA REPORT Attached e

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Att achen t= 38 In ve 2 Ort uTING DATA Rzr0RT DOCut 80. 50-267 DATE May 10. 1983 CourtrrrD sT c. H. Fuller TELzenour (103) 785 ???4 '

OPERATING STATUS NOTES

1. Unie x,,,, Fort St. Vrain

2. a.,orting Period: 830401 through 830430 ,

3. Licensed Ihermal Power (Wt): 842 4 Nameplate Rating (Gross We), 342 4

5. Design Electrical Racing (Net We): 330

6. Maximan Dependable Capacity (Gross We): 342 .

7. Maximum Dependable Capacity (Net We): 330

8. If Changes occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:

None

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

10. hasons for Restrictions. If Any: Restriction to 70% pending resolution of contractual matters.

This Month Tear to Data Cumulative

11. Hours in Reporting Period 719 2,879 33,600

12. Number of sours Raector was Crieicai 0.0' 1,153.9 20,900.6 i 13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0 is. sours cenerator On-Line 0.0 905.0 14,079.5

13. Unit ae orve Shutdown sours 0.0 0.0 0.0

16. Gross Therm 1 Energy Generated (MWH) 0.0 464.132.2 7,253,557.6

17. Cross Electrical F.nergy Generated os.a) 0 140.814 2,467,718 is. set Electrical Enersy cenerated (Wa) -2,814 120,303 2,243,413

19. Unit Service racter 0.0 31.4 41.9 l 20. Unit Avatiabitter ractor 0.0 31.4 41.9

21. Unit Capacity ractor (Using xDC see) 0.0 12.7 20.2

22. Unit Capacity Factor (Using DER Net) 0.0 12.7 20.2

23. Unit Forced Outage Kate 100.0 68.6 40.8

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each): Maintenance and Dlant recovery - 830501 through 830531 (744.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />).

25. If Shut Down at End of Report Period, Esti=ated Date of Startups 830601 e

26. Units In Test Status (Prior to Cos:inercial Operation): rotecast Achieved IntmL CRInCALIn N/A N/A l Iximt E:.EC RIC:n N/A N/A CCMMERCUL OPE 3ATION N/A N/A

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. TSP-3 Attechment-3A AVERAGE DAILY UNIT POWER LEVEL oue 2 p

Docket No. 50-267 Unit Fort St. Vrain Date May 10. 1983 Completed By C. H. Fuller Telephone (303) 785-2224 Month April ,1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL.,

(MWe-Net) (5'e-Net) 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 0.0 ' 21 0.0 .

6 0.0 22 0.0 7 0.0 23 0.0 8 0.0 24 0.0 9 0.0 25 0.0 10 0.0 2c> 0.0 11 0.0 27 0.0 12 0.0 23 0.0 13 0.0 29 0.0 14 0.0 30 0.0 15 0.0 31 N/A 16 0.0

• Generator on line but no net generation.

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ILcise 2 Page ! uf 1 "'

UNIT SilUTihAINS AND P(WER REDilC1DNS noCxET un. 50-267 unit une Fort St. Vrain mye May 10, 1983 I coeci.ETED sy C. H. Fuller i

um*T mwns _AgdL_.1983 m mmME (303) 785-2224 t

HE1110D OF SitUTTING IMWN SYSTEH COMPONENT NO. DATE 1TPE IMJRATION REASON HEACTOR I.ER f (X)DE (X)DE CAtBSE AND C(*RECTIVE ACT300' 10 PitEVENT RFfURRENCE 8-010 830401 F 719.0 B 3 N/A CBI BLOWER Shutdovin continued from reactor scram on 830317 for maintenance to "D" helium circulator, "B" boiler feed pump and primary coolant chemistry clean-up.

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. , . 6 REFUELING INFORMATION

1. Name of Facility. Fort St. Vrain Unit No. 1

2. Scheduled date for next refueling shutdown. February 1, 1984

3. Scheduled date for restart

following refueling. April 1,1984

4. Will refueling or resumption of operation thereafter require a

' technical specification change '

or other license amendment? Yes i If answer is yes, what, in l

ceneral, will these be? Use of tvoe H-451 orachite.

. If answer is no, has the reload fuel design and core configura-  ;

tion been reviewed by your Plant .

Safety Review Cornittee to deter- :

, =ine whether any unreviewed I

. safety questions are associated  !

with the core reload (Reference  !-----------------------------

10CFR Section 50.59)? l l

1 If no such review has taken ,,,,,,,,,,,,,,,,,,,,,,,,,,,,,

i olace, when is it scheduled?

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3. Scheduled date(s) for submitting proposed licensing action and Not scheduled at this time;

! supoortine information. to be determined.

i o. 'Important~ licensing considera-l tions associated with refueling, i

e.g., new or different fuel de- i sign or supplier, unreviewed I design or performance analysis j methods, significant changes in fuel design, new operating pro- l-----------------------------

l cedures. i

! I I 7. The number of fuel assemblies 1482 HTGR fuel elements.

! (a) in tne core and (b) in "

i the spent fuel storage pool. 11 spent HTGR fuel elements.

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I i 8. The present licensed spent fuel  !

pool storage capacity and the size of any increase in licensed Capacity is limited in size to about one-

. storage capacity that has been third of core (approximately 500 HTGR requested or is planned, in elements). No change is planned. -

number of fuel assemblies.

REFUELING INFORMATION (CONTINUED)

9. The projected date of the 1992 under Agreements AT(04-3)-633 and last refueling that can be !DE-SC07-791001370 between Public Service discharged to the spent fuel Company of Colorado, General Atomic pool assuming the present Company, and DOE.*

licensed. capacity. -

• 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 has evidently b.een sized to accomodate eight fuel segments. It is estimated that the eighth fuel segment will be discharged in 1992.

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