ML20084M009

Monthly Operating Rept for Apr 1984

ML20084M009
Person / Time
Site:	Fort Saint Vrain
Issue date:	04/30/1984
From:	Fuller C, Warembourg D PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF ADMINISTRATION (ADM)
References
P-84141, NUDOCS 8405150163
Download: ML20084M009 (9)

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

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, MONTHLY OPERATIONS REPORT l

NO. 123 April, 1984 l

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8405150163 840430 a

PDR ADOCK 05000267 R PDR

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O f" 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 rnonth of April,1984.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE The reactor was shutdown for the entire month of April. The primary activities included testing of equipment and components affected during the refueling outage, and maintaining plant conditions for the core support floor work.

The core support floor tube epoxy job, made difficult due to equipment problems, was completed. From all indications, the epoxy appears to have sealed off the leaking tubes. It is too early to tell if the overall job will be successful at operating conditions.

The following tests were completed during April:

1. The functional test of the Auxiliary Cooling Method (ACM) generator. This unit was overhauled during refueling.

-- 2. Overspeed test on 1A and 1C feedpumps. The units s were overhauled during refueling.

3. The Loss of Outside Electric Power Tests. The 480V essential buses were upgraded and extensively changed during refueling.

4. The firewater pump capacity test. The pumps were overhauled during refueling.

5. Ultrafiltration unit performance test on condensate cleanup. This unit was installed during refueling.

Plant operation was also modified to allow clearances for reheat marmon flange replacement, core support floor epoxy, 480V bus testing, circulator outages, and auxiliary boiler work.

A complete plant valve lineup was performed and changes required to plant documents were noted. The process revise the documents is in progress.

Core orifice valves were being partially stroked daily and core heating techniques were being utilized in an effort to return two orifice valves to operational status. The reactor vessel was depressurized to provide for replacement of an inoperable i orifice valve with an operable one. All orifice valves were

operational for equal flow positions by the eno of this a repcrting period.

s~ Prestressed Concrete Reactor Vessel tendon surveillance activities continued throughout the month, including lift-off testing of one bottom cross head tendon. One bottom cross head tendon was also detensioned and two wires were pulled for metallurgical and engineering evaluation. Further detensioning, testing, and inspection will continue in support of the overall analysis efforts.

Moisture removal from the Prestressed Concrete Reactor Vessel is in progress, but the present high levels have been predicted to extend the outage through May 28, 1984.

2.0 SINGLE RELEASES OF RADIOACTIVITY OR RADIATION EXPOSURE IN EXCESS OF 10% OF THE ALLOWABLE ANNUAL VALUE None.

3.0 INDICATION OF FAILED FUEL RESULTING FROM IRRADIATED FUEL EXAMINATION None.

4.0 MONTHLY OPERATING DATA REPORT Attached.

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. Attachment-D Issue 1

• Pep l af 1 orturtnG ncA urou nocret m. 50-267 nur May 8. 1984 court.zTrn er Chuck Fuller m .rPuowr (303)785-2224 ottaArixG stAns no:rs

1. unit meme: Fort St. Vrain .

1. m porties persed: 840401 through 840430

3. Licensed Thornst Poser oef t): 842 4 Nameplete 1 tias (Groes lese): 342

s. Desi, nectrical anting (met asse): 330

6. Maximum Deeeedable capacity (Grose leie): 342

7. ment == Dependable ce, city (met sese): 330

s. If changen occur in Capaalty Betings (Item. Hueber 3 Through 7) stace tant Report, Give Bessees None

9. Power Level Te Which ametricted, If Any (met gese): 280

10. amenese fer asetriettene. If any:

Per commitment to the NRC, long term operation above 85% power is pending completion of 8-0 Startup Testing.

Tsse n=th fear te note ca mlett,e

n. news in me,orties Perted 719 2.903 42.384

12. member et meets neu u r veo critt ul 0.0 468.0 26.295.3 l

13. meneter me.orve shadees ne ue 0.0 0.0 0.0

14. news cennier oe-t. tee 0.0 446.6 18.249.8

13. unit amerve sheedeve now. 0.0 0.0 0.0

16. orea Thermal seersy oneersted one) 0.0 240,818.8 9,762.136.4 eeret.d oes) 0 77.412 3,230.862

17. creu neetrie 1 smore c 1s. mt nutrial seersy c eersted oem) -2,507 64,924 2,936,454 1s. vais s'errtee ruter 0.0 15.4 43.1

20. uni Antientitty ruar 0.0 15.4 43.1

21. unit ce,=1ty rec u r (uetes une m i) 0.0 6.8 21.0

22. cati caputty ruter (notas paa mi) 0.0 6.8 21.0

23. vastpercedouissenew 0.0 1.5 38.9

26. shutdesee sen. deled over mest 6 se,sithe (Type, note, sed purettee et seen>i 5-1-84 through 5-28-84, primary coolant cleanup following shutdown, 672 hours0.00778 days <br />0.187 hours <br />0.00111 weeks <br />2.55696e-4 months <br />,10-19-84 through 11-10-84,

23. MfMN"$'sel'eYMl M.E.0Qi ted oate et starte,i E-16-84

26. untu la Test sutw (trier te ca.=rtut opereiten) tereem Aeneved 1x171A1. c11T1 cat.1TT N/A N/A 1x1nAL ELtcTucm N/A N/A N/A N/A co m sac 1AL oranAtton ,

. TSP-3 Attcchment-3A AVERAGE MILY UNIT POWER LEVEL Is m 2 Pcge 1 of 1 Docket No. 50-267 Unit Fort St. Vrain Date May 8, 1984 Completed By Chuck Fuller Telephone (303)785-2224 Month April 1984 -

MY AVERAGE MILY POWER LEVEL DAY* AVERAGE MILY POWER LEVIL (We-Net) (We-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 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 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 N/A 16 0.0

• Generator on line but no not generation.

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REFUELING INFORMATION I l l l 1. Name of Facility l Fort St. Vrain Unit No. 1 l l l l l l 2. Scheduled date for next l 3rd Refueling: l 4th Refueling:l l refueling shutdown. I currently underwayl Feb. 1, 1986 l l l l l l 3. Scheduled date for restart l May 28, 1984, l May 1, 1986 l l following refueling. I 2130 hours0.0247 days <br />0.592 hours <br />0.00352 weeks <br />8.10465e-4 months <br /> l l l l l l l l 4. Will refueling or resumption ofl No l No l l operation thereafter require a l l l l technical specification change l l l l or other license amendment? l l l .

I I l If answer is yes, what, in l ---------------- l ------------ l l general, will these be? l l l l l l l l If answer is no, has the reload l l l l fuel design and core configura-l l l l tion been reviewed by your l l l l Plant Safety Review Committee l ---------------- l No l l to determine whether any unre- l l l l viewed safety questions are l l l l associated with the core reload l l l l (Reference 10 CFR Section l -

l l l 50.59)? I l l l l l l l If no such review has taken l ---------------- l 1985 l l place, when is it scheduled? l l l l l l l l 5. Scheduled date(s) for submit- l l l ting proposed licensing action 1 ---------------- l ------------ l and supporting information. ' l l

l i l l 6. Important licensing considera- l l l l tions associated with refuel- l l l l

ing,'e.g., new or different l l l l . fuel design or supplier, unre- l ---------------- l ------------ l l viewed design or performance l l l l analysis methods, significant l l l l changes in fuel design, new l l l l operating procedures. l l l l l l l

-l 7. The number of fuel assemblies l l l (a) in the core and (b) in the l 1482 HTGR fuel elements l l spent fuel storage pool, i 251 spent HTGR fuel elements l

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 Capaci+v 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 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-SC07-79ID01370 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. I Company, and 00E.* l

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

r public servlee company or cenorado

, 16805 Road 19 1/2, Platteville, Colorado 80651-9298 t

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May 11, 1984 Fort St. Vrain l Unit No. 1 P-84141 l Office of Inspection and Enforcement ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, D.C. 20555 i

Reference:

Facility Operating License ,

4 No. DPR-34 Docket No. 50-267 .

I

Dear Sir:

t Enclosed please find our Monthly Operations Report for the month of April, 1984.

t Very truly yours, j I

l hC0 b Don Warembourg  :

Manager, Nuclear Production DW/djm -

l Enclosure .

t cc: Mr. John T. Collins i

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