ML20215H142

Monthly Operating Rept for Mar 1987

ML20215H142
Person / Time
Site:	Fort Saint Vrain
Issue date:	03/31/1987
From:	Novachek F, Robert Williams PUBLIC SERVICE CO. OF COLORADO
To:	NRC, NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
P-87147, NUDOCS 8704200168
Download: ML20215H142 (9)

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A t t achern t- 3t Issue 2 Page 1 of 1 oPERATIN:: DATA RIPOf1 DOCKET NO. 50-267 DATE Anril 15. 1987 Co.? LETED ET F. J. Novachek TELEPHONE (303) 620-1007 OPERATINO STAT'JS NOTES

___ 1. Unit Ea:ne: Fort St. Vrain. Unit No. 1 - - - -

2. Reporting Period: 870301 through 870331 l

3. Licensed Thermal Power (W t): 842

4. Nameplate Rating (Gross We): 142 ,,

5. Lesign Electrical Rating (Net We): 110

6. Maximum Dependable Capacity (Gross We): 342

7. Maximus Dependable Capacity (Net We): 330

8. If Changes Occur in Capacity Ratings (Itecs Nummer 3 Through 7) Since Last Report, Give Reasons:

None

9. Power Level To which Restricted. If Any (Net We): 0.0

10. Reasons f or Restrictions. If Any: Per commitment to the Nuclear Regulatory Commission.

remain shutdown vendina completion of Environmental Oualification modifications.

ThiS Mon th Tear 10 Latt Cumulktive

11. Hours in Reporting Period 744 2.160 67.945

u. .suster of Hours Reactor was critical 0.0 0.0 30.537.8

u. Reactor Reserve Shutdown Eours 0.0 0.0 0.0

n. Hours Generator on-Line 0.0 0.0 19.555.1

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. cross Thermal Energv Generated (WH) 0.0 0.0 J 0.265.399.8

17. Gross Electrical Energv Generated (WH) 0.0 0.0 3.333.996.0

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j Net Electrical Ecergv Generated (mH) -2.496.0 -7.050.0 2.941.230.0 r

19. Unit Service Factor 0.0 0.0 28.7

20. Unit Availability Factor 0.0 0.0 28.7 e

21. Unit capacity Factor (csing MDc Net) 0.0 0.0 13.1 b 22. Unit Capacity Factor (Uring DER Net) 0.0 0.0 13.1 Otr EN n. Unit Forced oute.ge Rate 100.0 100.0 64.1 P10 00 :4. Shutdowns Scheduled Over Next 6 Nnths (Type. Date, and Duration of Each): Environmenen1 be WO Orin 14 fi en t i nn mndi fi entinnn . 870401. 360.0 hourn (D X 40 23. If Shut Dom at Enc of Repert Period. Estimated Date of Startup: April 15. 1987 mO OQ

26. Units In Test Status (Prior to Co=nercial Operation): Forecast Achieved v

Otr INITIAL CRITICALITT y N/A N/A ha f (Dt1A INinAL ELEC n:CITT N/A N/A ccMMvl.c;AL OPIRATICS N/A N/A

AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-267 Unit Fort St. Vrain Unit No. 1 Date April 15, 1987 Cr aleted By F. J. Novachek i felephone (303) 620-1007 Month MARCH DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL

} (MWe-Net) (MWe-Net) 1 0.0 17 0.0 2 0.0 18 0.0 3 0.0 19 0.0 4 0.0 20 0.0 5 0.0 21 0.0 I 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 l

11 0.0 27 0.0 12 0.0 28 0.0 13 0.0 29 0.0 14 0.0 30 0.0 l

15 0.0 31 0.0 l 16 0.0 I

• Generator on line but no net generation.

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REFUELING INFORMATION I I I l 1. Name of Facility l Fort St. Vrain Unit No. 1 l l l 1 l 2. Scheduled date for next l l l refueling shutdown. I November 1, 1988 l l l l l 3. Scheduled date for restart l January 1, 1989 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 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 reloadj l l (Reference 10 CFR Section l l l 50.59)? l l 1 I I l If no such review has taken l 1987 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 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) 0 spent fuel elements l i

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N REFUELING INFORMATION (CONTINUED)

-l 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 I j 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-SC07-791001370 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, arid DOE.* l r

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 accommodate eight fuel segments. It is estimated that the eighth fuel segment will be discharged in 1992.

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Company of Colorado 16805 WCR 19 1/2, Platteville, Colorado 80651 April 15, 1987 Fort St. Vrain Unit No. 1 P-87147 Office of Inspection and Enforcement ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Docket Nc. 50-267

SUBJECT:

MONTHLY OPERATIONS REPORT FOR MARCH, 1987

REFERENCE:

Facility Operating License No. DPR-34

Dear Sir:

Enclosed, please find the Monthly Operations Report for the month of March, 1987.

If you have any questions, please contact Mr. M. H. Holmes at (303) 480-6960.

Sincerely, f)$ t R. O. Williams, Jr.

Vice President, Nuclear Operations Enclosure cc: Mr. R. D. Martin, Regicnal Administrator, Region IV R0W:djm J

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

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! MONTHLY OPERATIONS REPORT NO. 158 March, 1987 4

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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 1987.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE The reactor remained shutdown during the entire month of March for Environmental Qualification modifications.

Annual preventive maintenance on 1A and 18 diesel generator sets was completed during this month.

On March 10, 1987, following a walk-down of fire barrier 4 penetration seals, it was determined that 284 seals were missing '

l or degraded. A fire watch was posted to cover all affected t areas. These seals will be installed or repaired on a priority

basis. This event was investigated and reported to the Nuclear

Regulatory Commission in Licensee Event Report 87-006.

On March 10, 1987, Plant Protection System (PPS) module XDSH-93133, High Reactor Building Pressure, was discovered to

, ( have been inoperable since February 22, 1987. The inoperable channel was not placed in a tripped condition, which resulted in operation prohibited by Technical Specification 4.4.1. This event was investigated and reported to the Nuclear Regulatory Commission in Licensee Event Report 87-007.

On March 20, 1987, while Loop I was isolated, a spurious PPS actuation tripped Loop II. This trip should have been inhibited

by the logic circuitry since Loop I was already in a tripped condition. This event will be investigated and reported to the Nuclear Regulatory Commission in Licensee Event Report 87-008.

On March 26, 1987, during a followup investigation of Licensee Event Report 86-008, it was conservatively identified that sever!

Class I mechanical snubbers may have been inoperable during power operation. These snubbers have been removed from service and replaced. This event will be investigated and reported to the Nuclear Regulatory Commission in Licensee Event Report 87-009.

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O Certification of compliance with 10 CFR 50.49, Environmental Qualification of Electrical Equipment Important to Safety for Nuclear Power Plants, has been sent to the Nuclear Regulatory Commission by letter dated March 31, 1987.

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 Attached O

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