ML20071E785

Monthly Operating Rept for Feb 1983

ML20071E785
Person / Time
Site:	Fort Saint Vrain
Issue date:	03/08/1983
From:	Mcbride L PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML20071E774	List: ML20071E770 ML20071E785
References
NUDOCS 8303150350
Download: ML20071E785 (8)

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1 PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION MONTHLY OPERATIONS REPORT NO. 109 February, 1983 l

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I 8303150350 830311 l PDR ADOCK 05000267 R PDR

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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 February, 1983, 1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE On January 28, 1983, an upset in the Loop 1 buffer helium system caused a circulator trip. During this circulator auxiliary upset, there was a moisture ingress into the prestressed concrete reactor vessel which caused the reactor to scram on a two-loop trouble plant protective signal. .

Moisture removal from the primary coolant resulting from this incident was in progress at the beginning of the month.

Increased flow through the purification train was attained by using the helium transfer compressor recirculating to the prestressed concrete reactor vessel. Additionally, moisture removal was accelerated by using the reheater sections of the main steam generators, utilizing the steam drive of the helium circulators. This raised helium temperatures, thus assisting moisture removal. The capacity of the purification trains and the regeneration times were limiting factors for the moisture removal rate.

On February 8, the main generator was synchronized on line; however, it was manually tripped later the same day to prevent violating LCO 4.2.11.

On February 10, 1983, at 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br />, the turbine was again synchronized. A plant protective system turbine trip occurred later on February 10, but the turbine was recovered quickly.

Power generation continued until 1030 hours0.0119 days <br />0.286 hours <br />0.0017 weeks <br />3.91915e-4 months <br /> on

, February 15, 1983, when a fuse blew on "B" instrument power inverter. This caused a loss of various plant instrumentation

! in the Control Room, so the reactor was manually scrammed and the turbine tripped.

A moisture ingress to the prestressed concrete reactor vessel occurred during the February 15, 1983, transient, which necessarily dictated some unit downtime to permit moisture removal. It was decided to repair a main steam stop check valve and two safety valves of Loop 1 while shut down for moisture *

removal. Loop 1 and Loop 2 steam generators were checked for

tube leaks, and no evidence of leakage was found.

l Subsequent to the February 15 transient, problems developed with l the helium transfer compressor. The compressor was overhauled e and returned to service during the outage.

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Preparations are being made to start up as soon as repairs and moisture levels allow.

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

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• 9 Attachaett-38 Issue 2 e Ptge 1 of 1 OPE 3ATINC DATA REP J0 DOCEET NO. 50-267 DATE Mnech R. 1981 COMPLETED BY T_. M. McReide TELEPHONE (101T 7R5 7994 OPERATINC STATUS soIEs

1. Unit Name: Fort St. Vrain

2. Reporting Period: 830201 throunh 830228

3. Licensed thermal Power Otit): 842 4 Naanplace Rating (Gross We): 142

5. Design Electrical Racing (Net We): 110

6. '4=v4== Dependable Capacity (Croes We): 't A 7

7. Mad == Dependable Capacity Cset We): Tin

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Raasons:

NONE

9. Power Level To Which Restricted. If Any (Net 2Sie): 211

10. Reasons for Restrictions. If Any: Uservice4nn en 70T nand4ne vmenliveinn nf ennevncesim1 maceae._

This It: nth Year to Data Cmuistive

11. nours in Reporting Period 672 1.416 32.137

12. sunber of sours amector '.tas Critical 240.2 901.0 20.647.7

13. Rasetor saserve shutdown sours 0.0 0.0 0.0 14 Ecurs Generater On-Line ,,132.0 778.7 13.953.2

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Cross Thermal Energy Generated (:5m) 45.880.5 403.775.7 7.193.201.1

17. Gross Electrical EnergF Generated OSE) 7.729 129.740 2.456.694

18. Net Electrical Energ7 Generated (WE) 7_970 11A_949 7_710.705

19. Cait Service Factor 19.6 55.0 43.4

20. Unit Availability Tactor 19.6 55.0 43.4

21. Unit Capacity Tactor (Using MDC Net) 1.2 25.0 21.1

22. Unit Capacity Tactor (Using DER Net) 1.2 25.0 21.1 ,

23. Unit Forced Outage Race Rn_& 49_O 17.4

24. shutdowns schedated over Next 6 Months (Type. Date, and Duration of Each): 830301 through 830312 (288 hrni for n12ne recoverve 830323 through 830412 (504 hrs) for surveillance testing.

25. If Shut Down at End of Report Period. Estimated Date of startup: 830312

26. Units In Test Status (Prior to Commercial Operation): Forecast Achieved INITIAL CRITICALI"T N/A N/A INITIAL E:.EC:2:C:TT N/a y/A CONMERCIAL cPERATION N/a N/A

TSP-3 Attachment-3A AVERAGE DAILY UNIT POWER LEVEL Issa 2 Page 1 of 1 Docket No. 50-267 Unic Fort St. Vrain #1 Date March 8. 1983 Completed By I.. M. McBride Telephone (1011 785-2224 Month February, 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL -

(We-Net) (Wa-Ne t) 1 0 1.7 0 2 0 18 0 3 0 19 0 4 o 20 0 5 n 21 0 6 0 22 0 7 0 23 0

. 8 22.0 24 0 9 0 25 0 10 15.8 26 o 11 46.1 27 0 12 an_o 28 n 13 t, , 29 v /i 14 gn_9 30 N/A 15 9a i 31 N/A 16 0

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• Generator on line but no net generation.

i-s -y _- ,+---a, . - - , , + ,.y,.m , n - - - -- w . . , , , - . , - . --cr.- w _ ,_p.e-,.,,. --p ,._.m7y,. ,,4,_ y-_.,o w

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• Insee 2 Pare I of I uMIT SitUTIhnAIS AND P(WER REltiCDiffS-lu>cxET mi. 50-267 uMIr NAME ' Fort St. Vrain #1 nATE March 8, 1983 coNrLETra Ry L. M. McBride kt. PORT HONUt February 2 198'l Tu.mumE (303) 785-2224 _

HE1110D OF SilUTTING DulAl SYSTDI CotR*uMENT NO. DATE TYPE DuitATION REAS001 REACTOR I.RR # 0)DE oW CAUSE AND 01RRECTIVE ACTIOtt 10 PitEVENT HECURRueCE 83-001 830201 F 173.7 H 3 N/A IBH INSTRU Reactor scram and turbine trip on 830128 due to moisture ingress.

Purification system operation and plant statt-up.

83-00; 830208 F 38.7 D 4 83-003 - L - 0 CBI ZZZZZZ The turbine-generator was manually taken off-line to allow decreasing primary coolant temperature / pressure to prevent exceeding moisture limits of the Technical Specifications.

Reactor remained critical.

83-00: 830210 F 2.1 11 4 N/A IBM INSTRU Turbine-generator protective trip due to low main steam temperature.

Reactor remained critical.83-004 830215 F 325.5 A 2 83-007 - L - 0 EDD CENERA Manual reactor scram and turbine generator trip upon loss of "B" instrument bus. Instrument bus loss due to blown inverter fuse. Remained shutdown due to primary coolant impurities.

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REFUELING INFORMATION  !

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

2. Scheduled date for next refueling shutdown. September 1, 1983

3. Scheduled date for restart -

following refueling. November 1. 1983

4. Will refueling or resumption of operation thereafter require a ,

technical specification change or other license amendment? Yes If answer is yes, what, in general, will these be? Use of type H-451 graphite.

If answer is no, has the reload fuel design and core configura-tion been reviewed by your Plant Safety Review Committee to deter-

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mine whether any unreviewed safety questions are associated with the core reload (Reference i 10CFR Section 50.59)? l If no such review has taken _

place, when is it scheduled?

5. Scheduled dace (s) for submitting proposed licensing action and Not scheduled at this time; sunporting information, to be determined.

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 HIGR fuel elements.

(a) in the core and (b) in the spent fuel storage pool. 11 spent HTGR. fuel elements

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 storage capacity that has been elements). No change is planned.

requestad or is planned, in number of fuel assemblies.

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REFUELING INFORMATION (CONTINUED) i

9. The projected date of the ~ 1992 under Agreements AT(04-3)-633 and last refueling that can be DE-SC07-79ID01370 between Public Service discharged pool assumingto thepresent the spent fuel Company, li Company of Colorado, General Atomic and DOE.*

licensed capaciev. I

• 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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