ML19305D652

Monthly Operating Rept for Jan 1980

ML19305D652
Person / Time
Site:	Fort Saint Vrain
Issue date:	04/07/1980
From:	Gahm J PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML19305D651	List: ML19305D650 ML19305D652
References
NUDOCS 8004150336
Download: ML19305D652 (9)

Text

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'd mMTHLY OPERATTONS REPORT DISTRIBUTION

. Number of Coptoe Depa rtmen t o f Ene rgy - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 (P Letter)

San Francisco Operations Office Aten: California Patent Group 1333 aroadway Oakland. California 94612 De p a r tme n t o f Ene rgy - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 (P Letter)

Office of Nuciaar Engineering Prograae Washington, D.C. 20545 De p a rtme n t o f Ene rgy - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 (P Letter)

Mr. Glen A. Newby. Chief HTR Branch Division of Nuclear Power Development Mail Station B-107 Washingten. D.C. 20545 Dep a rtmen t o f Ene rgy - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 (P Letter)

Atto: Senior Program Coordinator P. O. Box 81325 San Diego California 92138 Depa r tment o f Ene r gy - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 (P Letter)

Technical Information Center P. O. Box 62 Cak Ridge, Tennessee 37830 Direc to r o f Nuclear Reactor Re gula tion - - - -. - - - - - - - - - - - - - - - - - 1 (Original P Letter)

Attn William P. Cammi11. Chief Operating Reactors Safequard Branch Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington. D.C. 20555 Philadelphia Electric Company -

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--- 1 Attn M. J. Cooney 2301 Market Street Philadelphia. Pennsylvania 18101 French Embassy - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 Atta Mrs. Duberney 1730 Rhode Island Avenue, NW Suite 1217 Washington, D.C. 20036 colorado Department of Health - ------------------------- 1 (P Letter)

Attn Al Hazel 4210 East lith Avenue Denver. Colorado 20220 W. Bushnell. Site Manager ----------------------------10 (Original of PPLC plus General Atomic Company 2 copies of FPI,C plus P. O. Box 426 ,. 1 copy of P Letter)

Platteville. Colorado 80651 NRC Resident Site Inspector -----w-

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1 (P Letter)

S004150 M

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e PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION L

MONTHLY OPERATIONS REPORT No. 73 i

JANUARY , 1980 '

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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 January,1980.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFTTY RELATED MAINTENANCE 1.1 Summary The reactor was taken critical on December 25, 1979, and power held  !

at approximately 1.5% for primary and secondary coolant system clean-up. A reactor scram and Loop 2 shutdown occurred on December 30, 1979, following the operation of 1C circulator at speed. High moisture levels are attributed to the ingress which occurred on December 7, 1979. Following this shutdown, maintenance on two major Loop 2 com-ponents was started. These were to stop the Icakage on V-2256 and to stop the oil supply flange leakage on EV-2254.

The reactor was taken critical again on January 5,1980, but on Janu-ary 8,1980, the 1B circulator primary seal was discovered to be inoperable and the reactor was placed in a shutdown condition. The outage to replace the IB circulator started on January 17, 1980, and continued through this report period.

l 1.2 Operations ,

Plant operations consisted primarily of maintaining the reactor coolant, secondary coolant, and associated auxiliary systems in the most opti-mum condition as possible, pending the completion of maintenance  ;

activities on 1B circulator. i 1.3 Testing ,

Ninety surveillance and preventive maintenance tests were issued '

to Operations to be done during this report period. All necessary testing was completed. Simulated over-speed tests on steam turbine boiler feedwater pumps were also done. Gamma scan testing was com-pleted on reflector blocks. i 1.4 Major Equipment Problems Circulator speed / wobble connectors and cables were replaced on all circulators except 1C.

Reactor is "off" with conditions for internal maintenance being main-tained for C-2102 replacement.

The seal on C-2102 was tested to determine the leak rate on seal area prior to depressurization and after depressurization.

l Loop 1 was cleared out for work on steam / water dump valves, HV-2215 E

and HV-2217.

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1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE (Cont'd) 1.4 Major Equipment Problems (Cont'd)

I Miscellaneous work is being done on hydraulic valve leakage problems.

Loop 1 safety valves are being repaired, t

Replaced and tested HEPA filters on two of the reactor plant exhaust ,

fans.

2.0 SINGLE RELEASES OF RADIOACTIVITY OR RADIATION EXPOSURE IN EXCESS OF 10% )

0F THE ALLOWABLE ANNUAL VALUE None 3.0 INDICATION OF FAILED FUEL RESULTING FROM IRRADIATED FUEL EXAMINATIONS None i 4.0 MONTHLY OPERATING DATA REPORT 1

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OPEitAmG DATA RErCaf DOCEET NO. cin_ % 7

• DATE 800201 C0xrtETED sf J. W. Gahm TEz,Eru0NE (303) 785-2253 _

OPEaATING STATU5  ;

NOTES

1. Unit Nemes Fort St. Vrain #1  !

2. aeportsas Period: 800101 through 800131

3. Licensed Thermal rover osit): 842

4. Nameplate natins (Cross We): 342  :

5. Design Electrical natins Olet We): 330

6. Maximum Dependable capacity (Gross We): 342 ,

7. Mawh= Dependable capacity (Net We): 330 r

8. If Chanses occur in Capacity natinsa (Items Number 3 Throush 7) Since Last Report, Cive Reasons:

None i

9. rower Level To Which Restricted. If Any (Net We): 231  !

10. amasons for Restrictions, If Any: Nuclear Regulatory Commission restriction 70% pending i resolution of temperature fluctuations. I i

i Ihis Month Tear to Data Cuenslative  !

11. sours in neporting Period 744 744 5,16 1 {

12. Number of sours anactor was Critical 36.0 36.0 2,569.1 l

13. neactor asserve Shutdown sours 0. 0 0.0 0.0  !

14. sours Generacor on-Lin. 0.0 0.0 982.2 l

15. Unit Reserve Shutdown sours 0.0 0.0 0.0 l

16. Cross Thermal Energy Generated (WR) 406.8 406.8 478,361.6 l

17. Cross Electrical Enerar Generated 0535) 0.0 0.0 140,796 '

is. Net Electrical Energy cenerated (Wa) 0.0 0.0 123.584 I

19. Unit Service Factor 0.0% 0.0% 19.0%

20. Unit Availability rector 0.0% 0.0% 19.0%

21. Unit Capacity ractor (usins MDC Net) 0.0% 0.0% 7.3% ,

. 22. Unit Capacier raetor (csing DEt Net) 0.0% 0.0% 7.3%  !

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23. Unic rareed Outase anc. 0.0% 0.0% 65.1% >

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[ 24. Shuedowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each): Plant shutdovn to j

replace helium circulator.

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23. If Shut Down at End of amport Period. Estinated Date of Startup 4-1-80 i

26. Units In Test Status (Frior to Connercial Operation): Forecast Achieved j INITIAL CRITICALITT N/A N/A l i

INITIAL ELECIRICITT N/A N/A <

1 COMMERCIAL OrERATION N/A N/d l l

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UNJT StitTTDOWHS AND POWER RE!WCTONS Fo rt S t. Vrain #1 UNIT NAnt

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DATE 800201 CoHPt.ETED af J. W. Cahm .

REroRT HONTH January, 1980 ten.ErNoNE (303) 785-2253 DETHOD OF

.l SHUTTING DOWN SYSTEN C00f0NENT NO. DATE TYPE DimATION REASON REACTOR I.ER f CODE Q)DE CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE 79-14 791026 S 744.0 B 2 N/A N/A N/A Scheduled shutdown for plant mainte '

nance and installation of region coit- .

straint devices was completed De-1 cember 24, 1979. Although the reactoi was critical at less than 2% for a l' brief period in January, discovery of. a ruptured helium circulator statis seal necessitated plant shutdown to replace the circulator with a spare, report submitted on LER #80-01/01-T-O.

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SUMMARY

Plant shutdown January 8,1980, to replace "B" helium circulator. , Shutdown to continue through March,1980.{

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AVERAGE DAILY UNIT POWER LEVEL

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Docket No. 50-267  !

Unit fort S c. Vrain #1 Date 800201 Completed By J. W. Gahm Telephone (303) 785-2253 I i

Month January, 1980 l

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 0 17 0 2 18 i 3 19 i 4 20 i

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8' 24 i 9 25  :

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10 26 11 27 l

12 28 l

13 29 [

14 30 '

15 31 v 16 s I l

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i REFUELING INFORMATION l

1. Name of Facility. Fort St. Vrain, Unit No. 1 I i

2. I Scheduled date for next refueling l shutdown. September 1,1980

3. Scheduled date for restart fo11 ewing refueling. i Novembe r 1, 1980

4. Will refueling or resumption of l I

operation thereafter require a technical specification change .

or other license amendment? No If answer is yes, what, in general, will these be?

If. answer is no, has the reload The Plant Operations Review Cocmittee will fuel design and core configura- review any questions associated with the tion been reviewed by your Plant core reload.

Safety Review Committee to deter-

• mine whether any unreviewed safety questions are associated with the core reload (Reference  !

10CFR Section 50.59)? ,

If no such review has taken  !

place, when is it scheduled? March 1,1980

5. Scheduled date(s) for' submitting - - - - - - - - - - - - -

proposed licensing action and supporting information. '

6. Important licensing considera- --- --

tions associated with refueling, e.g., new or different fuel de-sign or supplier, unreviewed j design or performance analysis methods, significant changes in i fuel design, new operating pro-cedures. L

7. The number of fuel assemblies a) 1482 HTGR fuel elements.

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

i b) 244 spent HTGR fuel elements.  !

8. The present licensed spent fuel Capacity is limited in size to about one-L pool storage capacity and the third of core (approximately 500 HTGR size of any increase in licensed elements). No change is planned. '

storage capacity that has been '

requested or is planned, in  :

number of fuel assemblies. (

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j REFUELING INFORMATION (CONTINUED)

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9. The projected date of the 1986 under the Three Party Agreement (Con-last refueling that can be tract AT (04-3)-633) between DOE, Public  !

discharged to the spent fuel Service Company of Colorado (PSCo), and  !

pool assuming the present General Atomic Company.*

licensed capacity.

• The 1986 date is based on the understanding that spent fuel discharged during the i term of the Three' Party Agreement will be shipped to the Idaho National Engineering l Laboratory for storage by DOE at the Idaho Chemical Processing Plant (ICPP). The i storage capacity has evidently been sized to accomodate fuel which is expected to l be discharged during the eight year period covered by the Three Party Agreement. I i

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