ML20078S029

From kanterella
Jump to navigation Jump to search
Monthly Operating Rept for Oct 1983
ML20078S029
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 11/04/1983
From: Fuller C, Warembourg D
PUBLIC SERVICE CO. OF COLORADO
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
P-83367, NUDOCS 8311150365
Download: ML20078S029 (8)
v • d • e


Text

- . . .

., j .. 4 - - -

t PUBLIC SERVICE COMPANY OF COLORAD0' FORT ST..VRAIN NUCLEAR GENERATING STATION l

l- -_

l MONTHLY OPERATIONS REPORT NO. 117 October, 1983 i

T.

+

l 1: .

1 i.

l t!

i' 7

T1 k, ,

8311150365 831104 '

t PDR ADOCK 05000267

.. R PDR 4.,

w i' t

- ~ - , . . - .-.y..... , , . . . _ . . , , ,

. .. i l

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 October, 1983.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE l The month of October was dominated by "1C" feedpump problems and the turbine trip, scram and loop shutdown near the end of the month.

The repairs made to "1C" feedpump in October included changes to the pump pedestal and a new runner installation. .The feedpump was operating well when governor problems forced a pump shutdown for governor repairs. It is essentially complete at this time.

"1A" feedpump had severe oscillations which were traced to worn throttle linkage. This linkage was repaired and no further problems with oscillations have been noted.

.The average. reactor power for the month was very good until the 29th of October when a turbine trip was the initiating event for a high moisture scram and followed by Loop I shutdown and steam water dump. The shutdown is being utilized to repair key plant components, and perform required surveillance testing (previously scheduled for December). Startup is projected for -

the first full week of November.

The fuel and reflector elements for the next reload have been inspected.

2.0 SINGLE RELEASES OF RADIOACTIVITY OR RADIATION EXPOSURE IN EXCESS OF 10% OF THE ALLOWABLE ANNUAL VALUE e None K 3.0 INDICATION OF FAILED FUEL RESULTING FROM IRRADIATED FUEL EXAMINATIONS

<y ,

4' L None ji E 4.0 MONTHLY OPERATING DATA REPORT

{d Attached Y

li t'

?:

R 0 m s

p 6

.go p e e gi g a,p g sp q pe_q emmW-,eppeg a wet h wi yn aw- _-pw -w.e m-.%,e -

g

-~ _ .. . ~

6 *

-;,. . /

. ** TSP-3 7' Att achmen t-38

~* Issue 2 ortPAnNe DATA REroRT DoCr2T No. 50-267 dan November 4, 1983 Cc::PLETED sY Chuck Fuller TELEPHONE (303) 785-2224

' ortpATING STATUS NOTES

1. ~ Unit Names Fort St. Vrain
2. Reportins Period: 831001 thru 831031 s 3. Licensed Thermal Power (W E):- 842

-4 Nameplate Rating (Cross We): 342

5. Design Electrical Rating (Net We)
330
6. Maximus Dependable Capacity. (Gross We): . 342
7. Maximum Dependable Capacity (Net W ): 330
8. If Changes occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Cive Reasons:

None 9 Power Level To Which Restricted, If Any (Not We): 231

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

This Month Year to Date Cumulative 4

11.' Hours in Reporting Period 745 -7.296 38.017

12. Number of Hours Reactor Was Critical 683.0 4.711.0 24.457.7

( 13. Reactor Reserve shutdown Hours. 0.0 0.0 0.0 14 aours Generator on-Line .__

682.9- 3.404.1 16.578.6

13. . Unit Reserve Shutdown Hours 0.0 0.0 0.0 i
16. Cross Thernal Energy Generated (WW) . 387.910.3 1.868.968.3 8.658.393.7 c
17. Cross Electrical Energy Generated (MWH)

^

135.325 595.084 2.921.988 4

16. see Electrical Enersy Generated (WH) 127,011 532,863 2.655,973-

[

t

~

19. Unit Service Factor 91.7 46.7 43.6

'f C

20. . Unit Availability ractor 91.7 46.7 43.6

-j 21. Unit Capacity Tactor (Using MDC Net) 51.7 22.1 21.2 J

0; 22. Unit capacity rector (Using DER Net) 51.7 22.1 21.2 r C 2 23. Unit Forced ousase Rate 8.3 53.3 41.2 t.

g. 24. Shutdowns Scheduled Over Next 6 Months (Type. Date, and Duration of Each): Surveillance testine P 11-1-83 thru 11-5-83, 107 hours0.00124 days <br />0.0297 hours <br />1.76918e-4 weeks <br />4.07135e-5 months <br />; Refueling, 2-1-84 thru 4-30-84, 2159 hours0.025 days <br />0.6 hours <br />0.00357 weeks <br />8.214995e-4 months <br />.

9 5- 23. 'If Shut Down at End of Report Period Estimated Date of Startup: 11-5-83

26. Units In Test Status (Prior to Coimercial operation): Forecast Achieved I (

IxInAL CrinCALin - N/A N/A IxInA1, ELECTRICIn N/A N/A i' N/A COMMERCIAL OPERATION N/A l

s

. - . - - - ~ . _ . . .. --.~.-,. , . . . n.,,.._. .-

F .

' -.

  • TSP-3 Attachnent-3A AVERAGE DAILY UNIT POWER LEVEL Issue 2 Page 1 of 1 Docket No. 50-267 Unit Fort St. Vrain Date November 4. 1983 Completed By Chuck Fuller Telephone (303) 785-2224 Month October. 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY PO'a'ER LEVEL.

(MWe-Net) (MWe-Net) 1- 179.5 17 194.2 2 179.3 18 194.2 3 179.2 19 203.4 4 179.3 20 232.5 5 179.5 21 238.2

~

6 ~175.3 22 160.0 7 149.0 23 187.8 8 179.5 24 188.9 9 178.7 25 188.8

- 10 144.3 26 189 0 11 169.5 27 188.8

, 12 194.8 28 188.8

! 13 195.0 29 81.9 h ,' 14 194.8 30 0.0

}~

ll 15 '95.0 1 31 0.0 F 16 194.2

' f.

b

  • Generator on line but no net generation.

'k i

li q

-- . .. . . . . . . . . - . - . . - - . - . - - . . .... . . . - . ~ . . . - . . - -

n . . - ,.. n- - - , ,

w _ - - - .--.

1 TSP-3 ,

At t adisern t-3C

.. 2 Page I of I UNIT SnUTtMWNS AND IWER PEDLICTINIS su)CKET tal. 50-267 UNIT NAnE Fort St. Vrain nAiE November 4,1983 avre.EtEn si Chuck Fuller REroRT MoNm October, 1983_ TrarruoNE nenion or SHUTTING DOWN SYSTEM COHroNFNT too. DATE UrE DURATION REASON REACTOR _ t.ER I CODE ODDE CAlfSE AND 0)RRECTIVE ACTInts TO rREVI.NT RECURRENCE 83 gg7 8M006 F 6 A 4 RO 50-2M/8342 HE MSTRU Power reduction to replace an electro pneumatic converter (XEP) transmitter in the hydraulic oil pressure circuit i on IA boiler feed pump. The turbine

generator remained on line.

> 83-018 831007 F 9 A 4 RO 50-267/83-42 IIHD INSTRU Power reduction to replace an XEP transmitter in the hydraulic oil pressure circuit on lA boiler feed pump. The turbine generator remained on line.

83-019 831010 F 19 A 4 RO 50-267/83-42 IHID MECFUN Power reduction for maintenance on IA boiler feed pump governor control.

The turbine generator remained on line,83-020 831022 F N/A A 4 N/A IHID MECFUN Power reduction for maintenance on IC boiler feed pump governor control.

The turbine generator remained on line.

, 83-l 021 831029 F 62.1 11 3 N/A IIBD INSTRU Turbine trip due to loss of electro-hydraulic control power. Reactor scram due to moisture. Continue the outage to perform surveillance testing.

4

. ~

i REFUELING INFORMATION I l 1 l 1. Name of Facility l Fort St. Vrain Unit No. 1 l l 1 I i l 2. Scheduled date for next l February 1,1984 l l refueling shutdown. l l l l 1 i l 3. Scheduled date for restart l May 1, 1984 l l following refueling. l l I l l l l- l 4. Will refueling or resumption ofl l l operation thereafter require a l l l technical specification change l l l or other license amendment? l Yes l l l l l If answer is yes, what, in l l l general, will these be? l Use of type H-451 graphite. l l l l l If answer is no, has the reloadj l l fuel design and core configura-1 l l tion been reviewed by your l l l Plant Safety Review Committee l --------------------- l l to determine whether any unre- l l l viewed safety questions are l l l associated with the core reload l l l (Reference 10 CFR Section l l l 50.59)? l l l l l

l If no such review has taken l --------------------- l j l place, when is it scheduled? l l l l 1 l S. Scheduled date(s) for submit- l l

, l ting proposed licensing action l Not scheduled at this time; l l and supporting information. l to be determined. l I I I

~j l 6. Important licensing considera- l l

}- l tions associated with refuel- l l

j. l' ing, e.g., new or different l l 4 l fuel design or supplier, unre- l --------------------- l 1 l viewed design or performance l l l l analysis methods, significant l l s I changes in fuel design, new l l l operating procedures. I l l l l l 7. The number of fuel assemblies l l l (a) in the core and (b) in the l 1482 HTGR fuel elements. l l spent fuel storage pool. I 11 Spent HTGR fuel elements. l

---_-____---.._.._4_mme.--a.rm+d -e-=

. __  %- 9Werph4 _ 1l>"*'*"

6' REFUELING INFORMATION (CONTINUED) l I l l 8. The present licensed spent fuell l

.l pool storage capacity and the l l l size of any increase 11n 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 l (approximately 500 HTGR elements).l l planned, in number of fuel- l No change is planned. l

,1 assemblies. l l 1 .

l l l 9. The projected date of the last l 1992 under Agreements AT(04-3)-633l l refueling that can be dis- l and DE-SC07-791D'1370 between l

.l 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 fucl segment will be discharged in 1992.

t e

m i

PLIblie $'rVice (Omjmy @ CdMdG' 16805 Road 19 1/2, Platteville, Colorado 80651-9298 L

November 10, 1983 Fort St. Vrain Unit No. 1 P-83367 Office of Inspection and Enforcement ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Reference. Facility Operating License

., No. DPR-34 1

Docket No. 50-267

Dear Sir:

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

Very truly yours, O., an.a , yJ m&ps Don Warembourg Manager, Nuclear Production DW/djm Enclosure cc: Mr. John T. Collins Hoo5 II i

Retrieved from "https://kanterella.com/w/index.php?title=ML20078S029&oldid=2760723"