ML20092B065

Monthly Operating Rept for May 1984

ML20092B065
Person / Time
Site:	Fort Saint Vrain
Issue date:	05/31/1984
From:	Fuller C, Warembourg D PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
P-84172, NUDOCS 8406200027
Download: ML20092B065 (9)

Text

-

10 PUBLIC. SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION LO

', _ MONTHLY OPERATIONS REPORT NO. 124 J

May, 1984 e

8

.O  : 84o6=ooo=7 e40sai PDR ADOCK 05000267 N

g PDR

.?

t

i h '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 May, 1984.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE The reactor remained shutdown for the majority of the month of May for final maintenance item completion and primary coolant

! chemistry cleanup.

On May 1, 1984, the reactor was depressurized to atmospheric to allow purge line check valve work in penetrations 13 and 21.

After completion, the reactor was repressurized on May 3.

On May 4, while approaching initial Cycle 4 criticality, high primary coolant moisture caused a reactor scrata and Loop I l

shutdown. To facilitate moisture removal, condensate was taken off the steam generator EES sections, and steam placed on both reheat sections and Loop I, System 46, was removed from service.

t L After successful completion of the overspeed test on tha IC Boiler Feedpump, it was shutdown and placed on the turning gear. The pump later seized, apparently due to foreign material entering the seal areas. The pump internals were removed, O

'd repaired, and reinstalled. At present, the IC Boiler Feedpump is operating satisfactorily (low vibration). In addition, new seals were installed in the 1A Boiler Feedpump and the overspeed test performed.

The Loop II helium dryer was removed from service to repair a malfunctioning check valve. During this time, the Loop I dryer supplied buffer helium to all four circulators.

Repair / refurbishment of the main cooling tower was completed and the tower returned to service on May 8, 1984.

The instrument air headers, IA and 18, were isolated, one at a time, to allow replacement of several leaking isolation valves.

i Also, the 1B receiver was internally inspected for scale buildup.

The 2% thermal power limit, placed on Fort St. Vrain in April, was removed by the Nuclear Regulatory Commission on May 16, 1984, after their evaluation of -the existing tendon wire degradation. Further testing and a expanded surveillance program is planned with followup reports to be submitted to the Nuclear Regulatory Commission.

r 3

n ~

L i IL

~2-( '3 On May 16, 1984, at approximately 1450 hours0.0168 days <br />0.403 hours <br />0.0024 weeks <br />5.51725e-4 months <br />, initial Cycle 4 K/ criticality was achieved. Primary coolant moisture removal i

continued via the helium purification trains and reactor power was increased to above 2% on May 24.

i Reactor- power was slowly increased to approximately 6.5% on May 29, when malfunction of a Loop II helium dryer valve required power reduction to less than 2%. The valve, HV-21564, was

-repaired and returned to service.

With reactor power less than 2%, one steam generator loop at a time was shutdown to facilitate repair of leaking sulzer valves.

On May 29, 1984, actuation of the rapid rise relay on the 4160/480 volt transformer (N-9274) resulted in a trip of the transformer and the 480V A.C. Essential Bus 1A. This led to actuation of the PPS circuitry for a Loop I shutdown due to the

. trip of both helium circulators in that loop. The transformer was thoroughly checked and tested prior to returning to service on May 30.

High pressure feedwater heaters, 5 and 6, were chemically treated, flushed, and operated on preb0iler recirculation flow in an atte.npt to. reduce the high iron levels which resulted from the repair / replacement of the heaters.

(~) At present, with reactor power near 8%, primary and secondary coolant impurities appear to be the major problem in increasing reactor power.

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 EXAMINATION None 4.0 MONTHLY OPERATING DATA REPORT Attached e

3

~T  :

(A J :

i l

i

{ . .

TSP-3 Atttchment-35 Iccue 2 OPERATING DATA REPORT DOCKET NO. 50-276 DATE June 4, 1984 COMPLETED BY Chuck Fuller TELEPHONE (303) 785-2224 OPERATINC STATUS NOTES

1. Unit same: Fort St. Vrain ,

2. Reporting Period: 840501 throunh 840531

3. Licensed Thermal Power Osit): 842

4. Nameplate Rating (Gross We):,

342

5. Design Electrical Rating Olet me): 330

6. Naw4== Dependable Capacity (Gross We): 342

7. Maximus Dependable Capacity Oest me): 330

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

None

9. Power Level To Which Restricted. If Any (Not me): 280

10. Raasons for Restrictions, If Any: Per commitment to the NRC, long term operation above 85% power is pending completion of the B-0 Startup Testing.

This Month Year to Date Cumulative

11. Bours in Reporting Period 744 3647 43,128

12. Number of sours Reactor was Critical 327.6 795.6 26,622.9 l

13. Rasctor Reserve Shutdown sourn 0.0 0.0 0.0

14. nours Generator on-I.ine 0.0 446.6 18,249.8 1

15. Unit Reserve Shutdown Ecure 0.0 0.0 0.0

16. Gross Thermal Energy Generated (wn) 7.584.2 248.403.2 9.769.720.6

17. Gross Electrical Energy Generated Deru) 0.0 77,412 3,230,862

18. Net Electrical Energy Genersted (wn) -3.660 61.264 2.932.794

19. Unit $'ervice Factor 0.0 12.2 42.3

20. Unit Availability Factor 0.0 12.2 42.3

21. Unit Capacity Tactor (Using MDC Net) 0.0 5.I 20.6

22. Unit Capacity Factor (Using DER Net) 0.0 5.I 20.6

23. Unit Forced Outage Rate 0.0 0.0 0.0

24. Shutdowns Scheduled Over Next 6 Months (Type. Date, and Duration of Each): 6-1-84 through 6-13-84. primary coolant cleanup following shutdown, 288 hours0.00333 days <br />0.08 hours <br />4.761905e-4 weeks <br />1.09584e-4 months <br />, 10-19-84 through l If11 Shut10-84 Down' , 552 Date stat Nr eillance tesf.inftimated hours.of Startup: N/A

25. of Report Perio E

26. Units In Test Status (Prior to Commercial operation): Forecast Achieved l

INITIAL CPITICALITY N/A N/A INITIAL ELECTRICHT N/A N/A comERCIAL OPERAMON N/A N/A

f . .

TSP-3 Attachment-3A AVERAGE DAILY UNIT POWER LEVEL Icaue 2 Pega 1 of 1 Docket No. 50-267 Unit Fort St. Vrain Date June 4. 1984 Completed By Chuck Fuller Telephone (303) 785-2224 Month May, 1984 -

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (We-Net) (We-Net) 1 0 17 0 2 O 18 0 3 0 19 0 4 0 20 0 5 0 21 0 6 0 22 0 7 0 23 0 8 0 24 0 9 0 25 0 10 0 26 0 11 0 27 0 12 0 28 0 13- 0 29 0 l 14 0 30 0 15 0 31 0 16 0 i

l

• Generator on line but no net generation.

I

7 .r ,

E p C u N

E n R a R

i t

e E l F

R c

n 4 T t i 2 N E

n a 4 r 2 V a r 8 e 2 E l V 9 l - R o 1 l 5 P o

. u 8 O c t ,

F 7 T 7 S 4 l y 6 k ) I c r 2 t e c 3 i T a . o

- r n u 0 C d n 0 o u h 3 A nw 5 F J C (

E oo V cd I et T

C su

. t E f t E h

- na A o u o T R d s n n n E PH R

O n

ag C

T T E. n i E i D yi

~

. m i t

r u

E T

I I

A rw ao o E ml C S il U

A ro C Pf T

w Z t

u Z o Z E Z wD o Z C (D Z e

o TE Z

Z sS Z yO sC 4

8 9

1 y

a M .

8 f A

/

R m

e E

L N

o n r T oG R N t o eI o r nT T 2 E sTxC m nUuA ENaE nSmR II o

S H A

E R

N 0 O

I T

4 A 4 R 7 U

D t S r

Y T

4 0

E 6 T 0 A

D 4 8

b

- 2

. 40 l

e 80 s

REFUELING INFORMATION I I i l 1. Name of Facility i Fort St. Vrain Unit No. 1 [

l l l l 2. Scheduled date for next l 4th Refueling: l l refueling shutdown. I February 1, 1986 l l 1 l l 3. Scheduled date for restart l May 1, 1986 l l following refueling. l l l l l l 4. Will refueling or resumption ofl No l l operation thereafter require a l l l technical specification change l l l or other license amendment? l l l l l l If answer is yes, what, in l ---------------- l l general, will these be? l l l 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 l No 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)? I l l l l l If no such review has taken l 1985 l l place, when is it scheduled? l l l l l l 5. Scheduled date(s) for submit- l l l ting proposed licensing action 1 ---------------- l l and supporting information. l l l 1 I l 6. Important licensing considera- l l l tions associated with refuel- l l l ing, e.g., new or different l l 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 operating procedures. l 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 251 spent HTGR fuel elements l L

a. .

REFUELING INFORMATION (CONTINUED) i I l l 8. The 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 l (approximately 500 HTGR elements).l l planned, in number of fuel l No change is planned. l l assemblies. l l l 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-SC07-79ID01370 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 4

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.

Public Service Company T OeBandIo V 16805 Road 19 1/2, Platteville, Colorado 80651-9298 June 15, 1984 Fort St. Vrain Unit No. 1 P-84172 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 Docket No. 50-267

Dear Sir:

Enclosed please find our Monthly Operations Report for the month of May, 1984.

Very truly yours, s.0~ Yhtml>

Don Warembourg Manager, Nuclear Production DW/djm Enclosure cc: Mr. John T. Collins h i 1

. W OQ.16. e sc

- _ - _ . .