ML20205C641

Monthly Operating Rept for Aug 1985

ML20205C641
Person / Time
Site:	Fort Saint Vrain
Issue date:	08/31/1985
From:	Gahm J, Novachek F PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
P-85320, NUDOCS 8509230065
Download: ML20205C641 (9)

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PUBLIC SERVICE COMPANY OF COLORA00 FORT ST. VRAIN NUCLEAR GENERATING STATION -

('T MONTHLY OPERATIONS REPORT j NO. 139 August, 1985 c

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8509230065 850831 PDR R ADOCK 05000267 s I J

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(3 w.. _1-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 August, 1985.

1.0 NARRATIVE SUMS.ARY OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE Efforts continued to reduce the levels of primary coolant moisture during August of 1985. The temperature and pressure of the primary system w6s raised to enhance the moisture removal rate of the helium purification system. Throughout the month, water continued to be removed from the primary coolant via the helium purification system front-end coolers.

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There were two operating situations which were determined to be reportable to the Nuclear Regulatory Commission through the Licensee Event Reporting System (10CFR50.73) during August. The Loop II Steam . Generator Penetration interspaces were determined to have been operated below cold . reheat pressure while the reactor was pressurized to greater than 100 psia (LER #85-013).

In addition, an automatic trip of the A Helium Circulator occurred on high buf fer-mid-buffer AP (LER #85-014).

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Public Service Company of Colorado continued its efforts to increase its present staffing level to those indicated at the SALP review meeting. Applicants were screened and interviewed throughout the month. Several offers have been made, and new staff members have begun to report.

Efforts to continue to improve the general level of housekeeping at Fort St. Vrain continued during August. The general area of the Turbine Deck received extensive attention with painting and new ceiling tile installation, and general cleanup being performed.

Work was performed to rebuild the hydraulically operated steam

' turbine block valve (HV-2249) on A Helium Circulator.

The Nuclear Regulatory Commission conducted a Performance Appraisal Team audit during August, from the nineteenth through the twenty-eighth of the month. Audit results are pending.

Public Service Company is in the process of changing its Standard Clearance forms and Operation Deviation Report forms to have an independent verification on all valves. This is anticipated to l ,

be in effect by September 10, 1985.

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s h 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 EXAMINATIONS None 4.0 MONTHLY OPERATING DATA REPORT

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TSP-3 Att achren t-38

. Issue 3 OPERATING DATA REPORT DOCKET NO. 50-267 DATE September 9, 1985 CoMPtETED sy Frank Novachek m tPuoNE (303) 785-2224 OPERATING STATL3 NOTES

1. Unit Name: Fort St. Vrain

2. Reporting Period: 850801 through 850831 l 3. Licensed Thermal Power (Wt); 842

4. Nameplate Rating (Cross We): 342

5. Design Electrical Rating (Net We): 330 j

6. Maximum Dependable Capacity (Cross We): 342

7. Maximum Dependable Capacity (Net We): 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 (Net We): 280

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

I This Month Year to Date Cumulative

11. Hours in Reporting Period 744 5,831 54,096

12. Nu=ber of Hours Reactor Was Critical 0.0 67.7 27,219.1

13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0

, 14. nours Generator on-tsne 0.0 0.0 18,468

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

! 16. Cross Thermal Energy Generated (51) 0.0 109.5 9,861,823.9 1

17. Cross Electrical Energy Generated (WH) 0.0 '0.0 3,248,594

18. Net Electrical Energy Generated (51) -3,218.0 -18,473 2,909,485 c

19. Unit Service Factor 0.0 0.0 34.1

20. Unit Availability Factor 0.0 0.0 34.1 0.0

21. Unit Capacity ractor (Using MDC Net) 0.0 16.3

22. vait Capacity ractor (Using DER Net) 0.0 0.0 16.3

23. Unit rorced outage Rate 100.0 100.0 54.5

24. Shu*devns Scheduled Over Next 6 }bnths (Type, Date, and Duration of Each): None

25. If Shut Down at End of Report Period, Estimated Date of Startup: October 1, 1985

26. Units In Test Status (Prior to Cornercial Operation): Forecast Achieved INITIAL CRITICALITY N/A N/A INITIAL ELECTRICITY N/A N/A CO5ERCIAL CPERATION N/A N/A .

- TSP-3 A tt a chmen t-3A AVERAGE DAILY UNIT POWER LEVEL Issue 2 Page 1 of 1 Docket No. 50-267 Unit Fort St. Vrain Date September 9, 1985 Completed By Frank Novachek4 Telephone (303) 785-2224

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Month August, 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERACE DAILY POWER LEVEL (MWe-Net) (E'e-Ne t) 0.0 1 0.0 17 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 9 0.0 25 0.0 10 0.0 2o 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 0.0 16 0.0

• Generator on line but no net generation.

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l b t'- J Attachsent-3C Issue 2 Paga l'of 1 UNIT SIIUTDOWNS AND POWER REDUCTONS ,

DoCxET NO. 50-267 UNIT NAME Fort St. Vrain DATE _$0ptember 9, 1985 COMPLETED BY Frank Novachek r

REPORT MONut Au9ust. 1985 TELEPiioNE (303) 755-2224 t'LDiOD OF harTTING DOWN SYSTEM COMPONENT NO. DATE TYPE DURATION REASON REACTOR LER # CODE CODE CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE 85-001 850724 F 744 G 3 50-267/85-012 AB XXXXXX Primary Coolant Cleanup e

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REFUELING INFORMATI0_N l l l l 1. Name of Facility l Fort St. Vrain Unit No. 1 l l l l l 2. Scheduled date for next l l l refueling shutdown. l January 1, 1987 l l l l l 3. Scheduled date for restart l February 1,1987 l l following refueling. l l l l 1 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 1 l If answer is yes, what, in l ---------------- l l general, will these be? l l 1 I 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 l ---------------- l l and supporting information. l l l 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 methods, significant l l l changes in fuel design, new l l l operating procedures. l l l -

l 1 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 . l b) 137 spent fuel elements l r

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I REFUELING INFORMATION (CONTINUED)  !

l l 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. I 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-SC07-791001370 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 tha; 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 accommodate eight fuel segments. It is estimated that the eighth fuel segment will be discharged in 1992.

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OPublic Service ~ .im .. .

Company of Colorado 16S05 WCR 19 1/2, Platteville, Colorado 80651 September 16, 1985 Fort St. Vrain Unit No. 1 P-85320 Office of Inspection and Enforcement i

ATTN: Document Control Desk -

V. S. Nuclear Regulatory Commission Washington, D.C. 20555 Docket No. 50-267

SUBJECT:

Monthly Operations Report For August, 1985 l

REFERENCE:

Facility Operating i License No. DPR-34 l

Dear Sir:

j Enclosed, please find the Monthly Operations Report for the month of August, 1985.

Sincerely,

/j&'hh J. W. Gahm Manager, Nuclear Production Fort St. Vrain Nuclear Generating Station Enclosure cc: Mr. John T. Collins JWG:djm b

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