ML20069K047

Monthly Operating Rept for Mar 1983

ML20069K047
Person / Time
Site:	Fort Saint Vrain
Issue date:	04/08/1983
From:	Fuller C PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML20069K043	List: ML20069K040 ML20069K047
References
NUDOCS 8304260186
Download: ML20069K047 (8)

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PUBLIC SERVICE COMPANY OF COLORADO -

FORT ST. VRAIN NUCLEAR GENERATING STATION x

e MONTHLY OPERATIONS REPORT NO. 110 March, 1983 i

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8304260186 830414 PDR ADOCK 05000267 l R PDR

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4 a .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 March, 1983.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATEDMAINTENANf.E On March 1, the reactor remained shut down for removal of moisture from the primary coolant, and repairs to Loop 1 main steam stop check valve, two mafn steam relief valves, and a bearing water makeup pump (P-2105) shaft seal.

These repairs were completed, and the reactor was brought to criticality on March 6. Primary coolant moisture continued a downward trend, and the main turbine generator was placed on line on March 8 with reactor power at 28%.

On March 9, the generator tripped due to a phase-to ground fault at the unit auxiliary transformer. A leaking cooling water coil in the bus duct cooling system was found to be the cause of the fault and the resulting trip. Reactor power remained at 28%

with a variance to LCO 4.6.1(a) granted by the Nuclear i Regulatory Commission for the unit auxiliary transformer outage.

Temporary bus duct cooling was installed.

On . March 11 through March 16, power and generation varied between 30% a,d 62%, governed by the moisture removal rate and the resulting core outlet temperature limiting conditions for i operation.

l On March 17,1A helium circulator was shut down as being suspect of moisture leakage into the core. Immediately thereafter, a scram occurred from the tripping of two high range moisture monitors.

During the period March 17 through March 31, investigations were conducted regarding the source of moisture ingress to the primary coolant, including 1A helium circulator, bearing water accumulator firings, and steam generator tube leaks. The source is et unknown, but investigations will continue.

Repairs to Loop 2 main steam stop check valve, ID helium

-circulator reheat flanges, 18 boiler' feedpump, and the replacement of the cooling water coils of the bus duct cooling system are being completed while moisture removal operations are in progress.

! The chiller system for IA purification train front end cooler e has been completed and is in service. This appears to have 3 enhanced the moisture removal process by allowing the train to

be in service for longer periods of time before regenerations.

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.- Liquid waste from the helium purification system front end coolers and regeneration knock out pot is being placed in carboys for a dilute release at a later date. This has eased the problem of accumulation of liquid waste in the liquid waste

. receivers and the Reactor Building sump.

The repairs to ID helium circulator steam flanges, HV-2224 main stop check valve, and IB boiler feedpump are the determining factors for restart. Estimated start of rise-to power is April 22.

' 2.0 SINGLE RELEASES OF RADIOACTIVITY OR R.4DIATION 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 rep 0RT Attached I l

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sp.g Attachment-33 Iatus 2 onuTrac mu uPoRT DocnT No. 50-267 un April 8,1983 .,

CcieLEnD sT Chuck Fuller nLEPaowE (303) 785-2224 OPERATING STATUS Nous

1. Unit Name: Fort St. Vrain

2. neporting Persod: 830301 throuah 830331

! 3. Licensed Thermal Power (Wt): 842

4. Nameplate Racing (Gross We): 342

5. Design Electrical Bating (Net We): 330

6. Nav4 == Dependable Capacity (Gross We): 342 -

7. Mari== Dependable capacity (Net We): 330

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

None

9. Power Level To Which Restricted If Any (Net We): 231 i to. Remons for nastrictions, If any: Restriction to 70% pending resolution of contractual matters.

This Month Tear to Data Cumulative

11. Hours is Reporting Period 744 2,160 32,881' I

12. Number of sours a. actor was Critical 252.9 1.153.9 20.900.6

13. Reactor userve shutdown aours 0.0 0.0 0.0

14. sours cenerator on-Lin. 126.3 905.0 14,079.5

15. Unic Reserve Shutdown sours . 0.0 0.0 0.0

16. cross Thermal Energy Generated (WH) 60,356.5 464,132.2 _

7,253,557.6 2,467,718

17. cross Electrical Energy cenerated (Wa) 11.024 140,814 is. Net Electrical Lergy cenerated (W u) 6.522 123.117 2.246.227

19. Unit Service Factor 17_0 41.9 42.8

20. Unit Availability Factor 17_O 41.9 42.8 2

21. Unit Capacity Tactor (Using MDC Net) 2_7 17.3 20.7

22. Unit Capacity Factor (Using DER Net) 2.7 17.3 20.7

- 23. Unit Forced outage Rate 83.0 58.1 _ 38.9 4

24. Shutdowns Scheduled over Next 6 Manths (Type, Date, and Duration of Each): 830401 throuah 830421 (504 hnurd for comoletion of helium circulator repair work.

23. If Shut Down at End of Raport Period. Estimated Date of Startup: 830421 i

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26. Units In Test Status (Prior to Connercial operation): Forecast Achieved INIT:AL CRITICALITT N/A N/A INITIAL ELICnICITT N/A N/A COMMERCML CPERATICN N/A N/A

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TSP-3 Attachment-3A e 2 AVERAGE DAILY UNIT POWER LEVEL p

Docket No. 50-267 Unit Fort St. Vrain Date Aoril 8.1983 Completed By Chuck Fuller Telephone (303) 785-2224 Month March. 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL. '

(MWe-Net) (MWe-Net) 1 0.0 17 25.7 2 0.0 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 l

9 1.s 25 0.0 l

10 0.0 26 0.0 1

! 11 0.0 27 0.0 l

! -12 23.6 28 0.0

! ' 13 46.7 29 0.0 14 70.8 30 0.0

.15 152.7 31 0.0

( 16 79.3

• Generator on line but no net generation.

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Issue 2 Page 1 of I unit smmxWNS AND POWER _REDUj(TpNS ry . 50-267 tlNIT NAME Jrt St. Yt*aill DATE April 8.1983 coert.ETrm av __ Chuck Fuller REPORT Ik)N111 March, 1983

, TEtEriions __(303) 785-2224 HE11tOD OF SHUTTING DOWN SYSTEM CUHl'ONENT NO. DATE TYPE DURATION REASON REAC10R LER f _

CODE 0)DE CAUSE AND 0)RRECTIVE ACTION 1T) PREVENT RECURRENCE 83-004 830301 F 193.8 A 2 83-007-L-0 EDD GENERA Remained shutdown due to primary coolant impurities.83-005 830309 F 62.3 A 4 83-013-L-0 EDD ELECON Turbine-generator trip due to failure of the output bus ducting. Reactor remained critical.83-006 830311 F 8.9 H 4 N/A IBH INSTRU Turbine-generator trip from Plant Protective System due to main steam conditions. Reactor remained critical.33-007 830313 'F 0.7 H 4 N/A IBH INSTRU Turbine-generator trip from Plant Protective System due to main steam conditions. Reactor remained critical.83-008 830314 F 1.4 H 4 N/A HBD INSTRU Turbine-generator trip from false transmitter signal in EHC system.

Reactor remained critical.83-009 830315 F N/A H 4- N/A CBI 2ZZZZZ Power reduction from 70% to 30% due to primary coolant impurity levels.83-010 830317 F 350.6 H 3 N/A IBH ZZZZZZ Reactor scram from Plant Protective System due to high primary coolant moisture. Remained shutdown for maintenance to "D" helium circulator.

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REFUELING INFORMATION i

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 l

fuel design and core configura-tion been reviewed by your Plant Safety Review Committee to deter-

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mine whether any unreviewed .

l safety questions are associated with the core reload (Reference 10CFR Section 50.59)?

If no such review has taken ____ __ _

place, when is it scheduled?

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

6. Important licensing considera-tions associated with. refueling, e.g., new or diffarent fuel de-sign-or supplier, unreviewed -- - --

design or performance analysis methods, significant changes in l

fuel design, new operating pro-cedures.

7. The number of fuel assemblies 1482 HTGR 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.

requested or is planned, in number of fual 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-SC07-791D01370 between Public Service discharged to the spent fuel i Compny of Colorado, General Atomic pool assuming the present Company, and DOE.*

l licensed capacity.

• The 1992 estimated date is based on the understanding that spent fuel discharged during the term of the Agreemente 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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