ML20199D037

Monthly Operating Rept for May 1986

ML20199D037
Person / Time
Site:	Fort Saint Vrain
Issue date:	05/31/1986
From:	Gahm J, Novachek F PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
P-86424, NUDOCS 8606180484
Download: ML20199D037 (9)

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

MONTHLY OPERATIONS REPORT

- NO. 148 May, 1986

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8606180484 860531 / I

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hDR ADOCK 05000267 PDR l

h 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 May, 1986.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND' MAJOR SAFETY RELATED MAINTENANCE The month of May started with the reactor at 34.2% and 93 MWe on the generator.

On May 4, 1986, from approximately 0630 hours0.00729 days <br />0.175 hours <br />0.00104 weeks <br />2.39715e-4 months <br /> to 1056 hours0.0122 days <br />0.293 hours <br />0.00175 weeks <br />4.01808e-4 months <br />, the average region outlet temperature exceeded 1200 degrees Fahrenheit. During this period the total of the primary coolant oxidants (H20, CO, and CO2) was 11.0 ppm, 1.0 ppm greater than the 10.0 ppm specified by LCO 4.2.10. The integrated ppm-day count for this period totaled 0.185 ppm-days. The total ppm-day accumulation for this fuel cycle is 0.2647 ppm-days, well within the 900 ppm-days allowed by LCO 4.2.10.

On May 6,1986, at 0830 hours0.00961 days <br />0.231 hours <br />0.00137 weeks <br />3.15815e-4 months <br />, while cperating at 34.2% reactor power, under a Nuclear Regulatory Commission power limit of 35%,

an unplanned transient occurred that increased reactor power to a O~ maximum level of 39.2%. This transient was caused by leakage through a main steam bypass pressure control valve. The leakage through this pressure control valve created a decrease in the main steam pressure and caused the overall plant control system to increase feedwater flow to restore main steam pressure. This increased feedwater flow increased both the turbine generator output and the reactor power level. Operators took quick and appropriate corrective action to stop the increase in turbine generator load and reactor power, investigated the reason for the power increase, and corrected the problem. The plant was returned to normal operation without further incident. A One-Hour Non-Emergency Event Report was made to the Nuclear Regulatory Commission per 10CFR50.72. As a precautionary i measure, reactor power was limited to 30% by placing the Interlock Sequence Switch (ISS) in the " Low Power" position so that the reactor would not automatically follow a turbine generator load increase as called for by the control system.

This event was reported to the Nuclear Regulatory Commission in Licensee Event Report #86-019.

l The power transient resulted in the Nuclear Regulatory Commission l calling for an enforcement conference at Region IV headquarters.

The Superintendent of Operations accompanied the Manager of l . Nuclear Production to Arlington, Texas, to discuss the event and i what was being done to prevent recurrence.

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. On May 29, 1986, the turbine generator was taken off-line and successfully conducted a turbine overspeed test. It was placed back on line at 2214 hours0.0256 days <br />0.615 hours <br />0.00366 weeks <br />8.42427e-4 months <br />. On May 30, 1986, at 2159 hours0.025 days <br />0.6 hours <br />0.00357 weeks <br />8.214995e-4 months <br />, the turbine generator was again taken off-line during the shutdown process for the Environmental Qualification modifications outage.

The reactor was manually shutdown on May 31, 1986, at 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br />.

During the month of May, maintenance crews completed the semiannual preventive maintenance _ inspection of K-9205X and K-9206X- diesel units. During the startup of these units after the work, a noise was detected from the inboard area of one engine. Further investigation revealed that the west turbocharger had severe signs of rubbing, some metal displacement, and a portion of blading missing. The Caterpillar vendor was contacted, and an investigative program was developed by the engineers that consisted of a visual examination of the exhaust system internals, the air intake system for the affected side and a cylinder pressure check. This examination confirmed that no damage to pistons or valves had occurred. The turbocharger was repaired and the diesel was returned to operable status.

2.0 SINGLE RELEASES OF RADIOACTIVITY OR RADIATION EXPOSURE IN EXCESS h 0F 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 l Attached l

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, NOTES

1. ve r.ame: Fort St. Vrain, No. 1

2. ur rtins rerne: 860501 throuah 850531 ' -

3. Liter.see' Ther al P:wer (76?t): 842

4. Na:eplete R. ting (Crcas We): 342

- 5. Design nectrical Racing (Net We): 330 _

' 6. w.azimum Depeneatie Cap. city (Cross We): _342

- l.', .w.ard cus Depeneable cap ci ty (f.'e t We):

330 _ _,

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1f chasses 6: cur is cap.cist Ratings (Ite=s f:u=ber 3 Thrc4h 7) Einee Lage report, Cive Reuens:- N None '\ .__

9. . r wer Level To *.*cich Restricted. I$- A=y C;et We): 115.5 1o. rumens for us:rs tons, rr Asy: Limited to 35% power through 860531. oendina completion of Environmental Qualification.

This Menth Taar to D.te Cu=ulative

11. seurs in reperu=s re.rioe ,. 744.0 3.623.0 60.648.0

12. s= ear or sours ructer ira .critte.1 _

743.0 2,456.6 30,537.8

13. t..eur ine:ve stu:em sours 0.0 0.0 0'. 0

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4 st. nou-s ceneh:gr e.-tree 707.6 __

1,087.1 19.555.1 is cut rese:w sh2:so sours O.0 0.0 0.0

16. cress ter e ts. a cen. rate 4 cr.a) 187,331.5_ 320,316.6 10.265.399.8

17. cress riectrient t=errr ener.:ea c (rra) 55,225.0 85,402.0 3.333.996.0_ .

sa. re: rie:tria: rz ,. rc cener.ree o4) 50,308.0 -65,926.0 2.962.199.0

19. re t service racar .

95.1 30.0 32.2

o. tut avaitailin i.e:or 95.1 30.0 32.2

1. tut c.;.cier r c:or (rung ex reti 20.5 5.5 14.8

. :nis c.p. city recur Grins etthet) 20.5 5.5 44.8

3. : nit rcreee o n ,s. rat. ,

4.9 70.0 58.4

s. shuteer_. s:teet:.4 cver seu s renths (rfpe. case, ane Dur. tion or t.:h): Environmental Qualification modifications, May 31, 1986, 2688 hours0.0311 days <br />0.747 hours <br />0.00444 weeks <br />0.00102 months <br />.

5. :s shut e. .t te ,e.z.per: rertoa, tst:=2:ee :sre or s:.r:up Sep_tember 21. 1986

6. l'a5 :s la Te s t s t.:2s (rrscr to Co-nere:.1 Op er.rion): Tcree.st Achievee is nu cx2ncntn N/A N/A

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2 AVERAGE -DAILY UNIT POWER LEVEL f88" gg

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- Doeket - No. 50-267

' Unit Fort St. Vrain.- No.1 s Date June 12. 1986 Completed By Frank J. Novachek Telephone (303) 785-6471 ext. 201

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>bnth May. 1986 DAY AVERAGE DAILY POWER LEVEL D k* AVERAGE DAILY POWER LEVEL (ige-Net) (5*e-Ne t)

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1 83.1 17 66.5 2 85.5 18 7b.'4 3 84.4 19 67.6 .

4 87.5 20 66.3 5 86.4 21 67.1 -

6 47.3 22 68.8 7- 73.4 23 69.9 8 69.6 24 65.3 9 68.2 25~ 66.9 10 71.4 26 67.7 11 67.6 27 65.9 12- 68.4 28 69.4 13 65.7 29 63.8 14 72.1 30 58.7 15 67.5 31 0.0 16- 69.9

• Generator on line but no net generation.

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REFUELING INFORMATION 1

1 I l l 1. Name of Facility i Fort St. Vrain Unit No. 1 l l l l l 2. Scheduled date for next l 1 l refueling shutdown. l March 1, 1988 l 1 l l l 3. Scheduled date for restart l June 1, 1988 l l following refueling. l l l . l l l 4. Will refueling or resumption ofl No I l operation thereafter require a l l l technical specification change l l l or other license amendment? l- 1 l l l l If answer is yes, what, in 1 ---------------- 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 reload l l l (Reference 10 CFR Section l l l 50.59)? l l 1 l 1 l If no such review has taken l 1986 l l place, when is it scheduled? l l l -

l 1 l 5. . Scheduled date(s) for submit - l l l ting proposed licensing action l ---------------- l l and supporting information. l l l l 1 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. I b) 0 spent fuel elements I l

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REFUELING INFORMATION (CONTINUED) l l

.1 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. l l I I 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. l Company, and DOE.* l t

• 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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O Public Service ~ ~o.

Company of Colorado 16805 WCR 19 1/2, Platteville, Colorado 80651 June 13, 1986 Fort St. Vrain Unit No. 1 P-86424 Office of Inspection and Enforcement ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Docket No. 50-267

SUBJECT:

Monthly Operations Report For May, .1986

REFERENCE:

Facility Operating License No. DPR-34

Dear Sir:

Enclosed, please find the Monthly Operations Report for the month of May, 1986.

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

Sincerely, d.d.G M b 1 -

J. W. Gahm Manager, Nuclear Production Fort St. Vrain Nuclear Generating Station Enclosure cc: Mr. R. D. Martin, Regional Administrator, Region IV JWG:djm

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