ML20106D027

Monthly Operating Rept for Sept 1984

ML20106D027
Person / Time
Site:	Fort Saint Vrain
Issue date:	09/30/1984
From:	Gahm J, Novachek F PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
P-84421, NUDOCS 8410240455
Download: ML20106D027 (10)

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k PUBLIC SERVICE COMPANY OF COLORADO i FORT ST. VRAIN NUCLEAR GENERATING STATION i l

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l MONTHLY OPERATIONS REPORT <

NO. 128 September, 1984 i

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C' This' report contains the hig'hlights 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 j the month of September, 1984.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE .

i To satisfy a Nuclear Regulatory Commission commitment, the new ,

Shift Turnover Procedure was implemented on September 4, 1984. i This will allow time to use and review the procedure prior to the actual commitment date of October 10, 1984.

3-Water collected and stored from the primary coolant moisture removal process.has been added to the radioactive liquid waste system for release. Increments were increased from three gallons {

to fifteen gallons, and possibly as high as thirty gallons. We i are werking closely with Radiochemistry to eliminate any chance of exceeding maximum permissible concentration (MPC) at the site p boundary.

The west settling pond was pumped out to inspect.for silt buildup during the month of September. The silt has not been removed. l

. 4 "B" Helium Circulator' tripped on loss of bearing water due to i

- b.~; . the trip of P-2101-S. The accumulator fired, and the standby.

pump automatically started on September 8, 1984.

"A" Helium Circulator tests indicate a bearing water to ' '

interspace leak. Tests were performed to verify the source of water. Presently, the circulator is shut down with the auxiliaries isolated. The 1e k has been verified as a' leak into.

the interspace, and the circulator has to be removed for repair.

"B" purification train was out of service, and the investigation of regeneration problems was performed. Regeneration problems were traced to two improper valve-stroke lengths. The stroke lengths were adjusted, and regeneration was restarted.'

The high pressure separator drain change notice has been completed on Loop 2. We flushed the system to remove any construction debris. The system has been checked and has been returned to service. The Loop 1 portion of the change has not been started.

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i Inspection of Region 7 Control Rod Drive (#25) continues. We '

f' performed T-242-(Visual Ir.spection of the Bent Absorber String) to determine radiation levels on September 9, 1984. The control rod drive was successfully moved to the Hot Service Facility on i swing shift on September 11, 1984. Six absorber sections extend from the orifice valve, with several damaged, and. the absorber  ;;

.section is badly bent. The bent absorber string suspension  ;

cable is severed in several places. The absorber string is  !

still suspended, and attempts are being made to determine the .

cause of the absorber string not being fully retracted in the  !,

control rod drive and for the cable failure.  !

Control . rod drive #11 (currently in Region 27), with the frayed ji cables, has had the motor installed, the back-EMF tests !l performed and the motor removed. The rod was reassembled for 'l temporary insertion into the core. After the control rod drive l in Region 27 was removed, the temporary rod was installed. This l temporary rod does not have a shim motor or position I potentiometers.  !

1 The control rod drive in Region 9 (#20) has been removed, and a  !

refurbished rod has been installed in that. region. i Control rod drive #23 was removed from the Hot Service Facility l West Port and installed in Region 9. Once in the core, the i f control rod drive was exercised to verify operability. The

._ ( secondary cover for. Region 9 was then installed.

i Control rod drive #26 was removed from Equipment Storage Well #6  :

and placed in the Hot Service Facility West Port. A back-EMF test was conducted to get initial Hot Service Facility data. -

The shim motor on this control rod crive will be refurbished. l t

The control rod drive in Region 35 was removed for maintenance. i The removal was complicated by malfunctioning in and out limit l switches. The control rod absorbers were finally retracted using a manual retract tool. When the refurbished control rod drive was returned to the core, the auxiliary transfer cask ~

grapple would not disengage. The grapple had to be disassembled to disengage it. Three of four solenoids were found to be j burned out. The cask grapple solenoids were replaced and the cask was returned to service.

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/T' 2.0 SINGLE RELEASES OF RADI0 ACTIVITY OR RADIATION EXPOSURE IN EXCESS 0F 10?. OF THE ALLOWABLE ANNUAL VALUE I

None.

3.0 INDICATION OF FAILED FUEL RESULTING FROM IRRADIATED FUEL EXAMINATION

-None.

4.0 MONTHLY OPERATING DATA REPORT I

Attached.

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MTA REPORT DOCKET NO. 50-267 DATz October 12, 1984 C0euno nr Frank Novachek Tr:.trs0xx (303) 785-2224 OPERA *INO STATt!

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1. Unit name: Fort St. Vrain ,

2. m.portins Period: 840901 throuah 840930

3. Licensed Thermal Power 06ft): 842

4. sameplate Rating (Gross We): 342

5. Design Electrical Racing Olet We): 330

6. It 1 mum Dependable Capacity (Gross We): 342

7. Nad=== Papendable Capacity Olet We): 330

s. If Changes occur in Capacity Ratings (Items Nimber 3 Through 7) Since Last Report, Cive taasons:

_None _

4 9. Power Level To which Rastricted. If Any (Net We): 280

10. ammons for mastriction, if Any: Per commitment to the NRC. lono term ooeration above 85% power is pending completion of the B-0 Startup Testing This Nonth Year to Date Cumulative u . nours in m. port u s period 720 6,575 46,056

12. zumber of nours sector vu critical 0.0 1,324.1 27,151.4 ,'

13. a m eter w erve shutdown sours 0.0 0.0 0.0

14. nours cen rator on-Lin. 0.0 660.1 18,463.3

15. Unit tuerve shutdown Hours' O.0 0.0 0.0

16. Cross Thetaal Energy Generated (WR) 0.0 340,407.9 9,861,725.3

17. Cross neetrical snerar cen rated oors) 0 95.144 3.248.594 la. set nectrical Energy cenarated (Wa) -2.420 64,370 2,935,900

19. Unit s'ervice Tsetor 0.0 10.0 40.1

20. hit Availab u ity Factor 0.0 10.0 40.1

21. Unit Capacity y.ecer (usins xDC net) 0.0 3.0 19.3

22. Unit Capacity Tactor (Using DER not) 0.0 3.0 19.3

23. unit rore.d outage anta 100.0 78.7 43.2

24. Shutdowns Scheduled over Next 6 Honths (Type, Date, and Duration of Each): 10-1-84 throuah 3-31-85, 4360 hours0.0505 days <br />1.211 hours <br />0.00721 weeks <br />0.00166 months <br />, Control Rod Drive Investigation.

[ 25. If Shut Down at End of Report Period. Estimated Date of Startup: 4-1-85 i

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l 26. Units In Test Status (Prior to Connercial Operation): yorecast Achieved IxInAL CMnCAMTT N/A N/A InnAL r:.rCTaICIn N/A N/A Co m CIAI. OPERATION N/A N/A

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- Attechtnant-3A AVERAGE DAILY UNIT POWER LEVEL haue 2 Page 1 of 1 Docket No. 50-267 Unit Fort St. Vrain Date October 12, 1984

- Completed By Frank Novachek Telephone (303) 785-2224 Month September, 1984 .

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (We-Net) (We-Net) 1 0.0 17 0.0 2 d.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 26 0.0 11 0.0 27 0.0 12 0.0 28 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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REFUELING INFORMATION I . l . l l 1. Name of Facility l Fort St. Vrain Unit No. 1 l l l 1 l 2. Scheduled date for next l 4th Refueling: l l- refueling shutdown. I February 1, 1986 l l l 1 l 3. Scheduled date for restart l May 1, 1986 l 1 following refueling. l l 1 1 I l 4. Will refueling or resumption of] No l

[ operation thereafter require a l l l technical specification change l l l or other license amendment? l l l l 1 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 reloadj l l (Reference 10 CFR Section l l l 50.59)? I l l 1 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 l ---------------- l l and supporting information. l l 1 l l 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 metnods, significant l l l changes in fuel design, new l l l operating procedures. l l l 1 l l 7. The number of fuel assemblies l l l (a) in the core and (b) in the l a) 1482 HTGR fuel elements l l spent fuel storage pool. I b) 173 spent fuel elements l_

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l REFUELING INFORMATION (CONTINUED) l l l l 8. The present licensed spent fuell l i

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 9. 'The projected date of the last l 1992 under Agreements AT(04-3)-6331 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 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 Plar.c. 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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public servlee company *e cononde V, 16805 Road 19 1/2, Platteville, Colorado 80651-929'8 6

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October 12, 1984 Fort St. Vrain Unit-No. 1:

P-84421 Office of Inspection and Enforcement ATTN: Document Control Desk U. S. Nuclear Regulatory Co vnission j 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 4

September, 1984.

. Sincerely,

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.e J. WrCa m Manager, Nuclear Production JWG/djm Enclosure I cc: Mr. John T. Collins i

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