ML20039D571

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Monthly Operating Rept for Nov 1981
ML20039D571
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 12/01/1981
From:
PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML20039D566 List:
References
NUDOCS 8201050220
Download: ML20039D571 (10)
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Text

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PUBLIC SERVICE CGMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION MONTHLY CPERATIONS REPORT NO. 95 November, 1981 E

C e201050220 goo 67

PDR ADOC PDR
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This report contains the highlights of the Fort St. Vrain, Unit No. 1, activit.ies operated under the provisions of the Nuclear Regulatory Commission Operating License DPR-34. This report is-for the month of November, 1981.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE 1.1 Summary The modifications to B-2-3 steam generator penetration piping were completed on November 2. The temporary configuration was agreed upon by the Nuclear Regulatory Commission to allow testing to 100% power for a maximum of a four-week time period. The penetration interspace between the primary- and secondary seals could then be operated at slightly above cold reheat pressure to minimize the internal steam generator leak into the cold reheat header. This leak led to a plant shutdown on October 25 when the leak rate exceeded the maximum allowed by the Technical Specifications.

The reactor was pumped up to full density on November 3, and the power was subsequently increased to 70% on November 4. We then commenced testing per RT-500K, and the power was gradually increased in 3% increments. Full power, 100%, operation was achieved at 1547 hours on November 6 and all systems performed as expected. The plant was operated at this power level for several days to gather data to further veri fy and document system performance.

"B" helium circulator tripped on a buffer upset on November 9. A 1 cop shutdown ensued when "A" circulator also tripped on overspeed. The only 100% data that was missed due to this unexpected upset was the iodine probe analysis. It was then decided to shut the plant down and commence the scheduled loop split modifications to the-belium circulator auxiliaries. This shutdown has continued throughout the month with the loop. split work now about 50%

complete. The targeted completion date is January 4, 1982.

1.2 Ooerations The modifications to the B-2-3 steam generator penetration piping were completed on November 2. These modifications consisted of removing one of the two safety valves and rupture disks from the Loop 2 penetration piping and installing them on the B-2-3 penetraticn. A temporary o

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piping change was made to feed purified helium from the B-2-3 penetration to the B-2-3 module. These modifications allow operating the B-2-3 penetration at. slightly above cold reheat pressure in accordance with the temporary approval granted by the Nuclear Regulatory Commission.

The reactor was pressurized to full density on November 3, 1981, and the reactor power increased until the turbine generator was synchronized at 1306 hours0.0151 days <br />0.363 hours <br />0.00216 weeks <br />4.96933e-4 months <br />. The power was increased further until reaching 70% on November 4. From this power level, we resumed the RT-500K testing.

The power was increased in 3% increments in accordance with .

l the test to allow data gathering and analysis during the rise. A power level of 100% was achieved at 1547 hours0.0179 days <br />0.43 hours <br />0.00256 weeks <br />5.886335e-4 months <br /> on November 6, 1981, for the first time in the plant's history. All the plant systems operated as expected.

The plant continued to operate at approximately 100% power for several days to gather data for startup test 1-0.

The data for 100% power operation has been reviewed and several of the preliminary conclusions are:

1. The difficulty maintaining deaerator level is probably due to icw condensate header pressure which will be corrected during the upcoming shutdown when the pumps are overhauled.
2. The steam generator and primary coolant system performance was acceptable considering the operating restrictions of RT-500K.
3. The prestresseu concrete reactor vessel liner cooling system performance was in agreement . with the predictions.
4. The feedwater flow measurement needs to be investigated further to datermine the effect on the heat balance calculations.
5. The primary coolant activity levels are about one-tenth of the anticipated values.
6. The region constraint devices performed as expected, and there were no significant problems with operating the reactor at 100% power.

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The "B" helium circulator tripped at 0155 hours0.00179 days <br />0.0431 hours <br />2.562831e-4 weeks <br />5.89775e-5 months <br /> on November 9 due to a buffer system upset. The resultant reheat steam pressure transient caused "A" circulator to trip on overspeed. A Loop 2 shutdown then followed because of the two circulator trips, and.the power was ramped down1 to about 30%. The power was then reduced further, and the turbine generator taken off at 0436 hours0.00505 days <br />0.121 hours <br />7.208995e-4 weeks <br />1.65898e-4 months <br />. The reactor was eventually scrammed, and the scheduled shutdown activities were. commenced. This' unexpected circulator trip prevented obtaining the iodine analysis at 100%, but the other "B" series startup test data was gathered.

The loop split modification began on November 9. The Stearns-Roger construction work force was able to complete a considerable amount of the prefabrication work prior to November 9 because of the delays in the shutdown schedule.

In fact, 28% of the work was completed prior to November 9.

The work was about 50% complete at month's end, and the estimated completion, date is still January 4, 1981. The turbine generator work should also be completed by General Electric by January 4.

Numerous major shutdown activities being accomplished concurrently include: 1) removal of the plateout probe,

2) removal of circulator water pump isolation valves,
3) overnaul of large condensate pumps, 4) modification of main steam desuperheater, 5) prestressed concrete reactor vessel rupture disk surveillance, 6) repair of several hydraul1c valve operators, 7) removal _of "B" hydrogen getter, and 8) instrument and valve calibrations. Internal maintenance in the reactor is also being performed to install a new neutron source in region 15.

During removal of a region constraint device from the core, an incorrect position signal from the fuel handling machine caused the region constraint device to be knocked against another region constraint device, resulting in a lock up of the fuel handling machine. The fuel handling machine grapple was eventually removed from the region constraint device, and an examination, using the camera viewing system, revealed the region constraint device to be resting precariously against another region constraint device and a region orifice valve. The fuel handling machine manipulator is now being installed and tests are being run in the hot service facility to demonstrate the fuel handling machine's ability to pick up the region constraint device in this unusual position.

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' - 4 2.0. SINGLE RELEASES OF RADI0 ACTIVITY OR RADIATION EXPOSURE IN EXCESS OF 10*. OF THE ALLOWABLE ANNUAL VALUE None 3.0 INDICATION -0F FAILED FUEL RESULTING FROM IRRADIATED FUEL EXAMINATIONS None 4.0 MONTHLY OPERATING DATA REPORT i

Attached i

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cPrumc cAu REPORT DOCKET 30. 50-267' DAtt 811201 CcMPt.z:ro si L. M..McBride TELZPHONE (303) 785-2224 CPE?ATINc STATUS NOTES

1. Unit Name: Fort St. VrMn

. amporting Period: 811101 through 811130

3.  :.icensed thermal Power Gert): 842 4 Nameplace Rating (, cross We): 342
3. Design Z1ectrical Racing Clet we): 330
6. Fa* == Oependable Capacity (Cross We): 142
7. "mewun Dependable capacity Olet We): 110 S. If Changes occur in Capacity Racings (Itaus Number 3 through 7) since Last Report, cive Raasons:

None

9. Fever Level To Which Eastricted If Any (Net We): 231
10. amasens for aastrictions, If Any: NRC restriction of 70% pending resolution of ._

temperature fluctuations.

This Month Tear to Oate Cumlative i M. Hours in Raporting Period 720 8.016 21.217

12. Nu=cer of scurs Reactor Was Critical 209.0 5.443.2 14.97R.4
13. Reactor assern shutdown sours 0.0 0.0 0.0
14. so us ce=aracor on-t.ine 135.5 4.215.0 9.908.3 t
15. cmit zeserve shutdown sours 0.0 0.0 0.0
16. cross Ther:nal Energy cenerated (sit) 97.826.4 2.225.852.0 4.933.944.8
17. cross Electrical Energy cenerated 05m) 35.671 819.562 1.691.356 1s. Net riectrical znargy cenerated (sa) 31,700 754,958 1,554,259 it enic service raetor 18.8 52.6 46.7
20. nic Availability ractor 18.8 52.6 46.7
21. Unit Capacity Factor (Using MDC ::et) 11.3 28.5 22.2
  • 2. Unit Capacity Factor (Using DER Net) 13.3 28.5 22.2-
23. Unie Forced Outage Race 31.1 28.8 34.0 24 shutdowns scheduled over Next 6 Months (Type, Data, and Duration of Each): Maintenance / modification shutdown December 1, 1981 through Januarv, 1982.
25. If shuc cova at End of saport Period, Estir. aced Date of startup: Februarv 1. 1982 i

j 25. Units In Test 3tatus (Prior to Comnercial Operatien): Forecast Achieved

! I::ITu:. C2I:ICAir T N/A N/A IN: u:. I:.:c:a:C::7 N/A N/A CO:et:1 Cut cPERA :CN N/A N/A L __

r:e_t,.-~" wa.m u ~ t w r = t:

iv>cs r lui. 50-267' -

UNIT NAHE Fort St. Vra in late 811201 COHPIR ED BY I, _. M . MC MIME arronT tamru Novemlier . 1981 TEIErin>NE W @ 785-2224 HEnnin or Si4HTTING DAMN SYSTEN COMPONENT Nil. IIATE TYPE lRlHATION REASON kEACTOR IFR f LI)DE DHIE CAilSE AND CONRECTIVE ACTION TO PREVENT krfUHkENCE

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i B 1-024811101 F 61.1 11 4 81-068/031.-0 CJA. PENETR Steam generator B.2.3 penetration leakage of lielium.

I j 81-025811109 F 0.0 11 4 N/A CBI INSTRU Power reduction due to loop sliutdown.81-026 811109 S 523.4 B 2 N/A CBI XXXXXXX 1.oop-split modiffcation.

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AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-267 Unit Fort St. Vrain Date 811201 Contpleted By L. M. McBride Telephone (303) 785-2224 Month November. 1981 -

DAY AVERAGE DAILY P0hT.A LEVEL DAY AVERAGE DAILY POWER LEVEL-(We-Ne c) (We-Ne t) 1 0.0 17 0.0 2 _

0.0' 18 0.0 3 32.6 19 0.0 4 196.3 20 0.0 5 232.4 21 0.0 6 290.4 22 0.0 7 309.8 23 0.0 8 316.4 24 0,o 9 27.9 25 0.0 10 0.0 26 0.0 11 0.0 27 0.0 k i

12 0.0 28 0.0

  • a 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 " net generation.

-me- - = = = = = -= + - ~ ~ * - * *

.wa_.'.G I'T7C?3C CN

1. Na=a of Tac 111: r. ?e-- se. 7:21: Uni: No. 1
2. Scheduled da:a f:r nes: refueling shu:devn. Oc::bar 1. 1983
3. Scheduled. data f:r :ssca.-

f=11:w.d r :sinali:2. 5 - :. t toa3 I

4. W :sdnaling er :ssu=p:1:n of ,,-

cperacies hersaf:m: : squire a

=.w,,e - - specige-,.ica changs er other liessse a==ad-en ? Yes If ansvar i.s yes, wha , is te eral. rill these be? Use of tr:e H-451 grauhite.

f If a=swer is so, has -d e 31:ad fuel desig: and c= s c=nfiguzz-

-1:n

- been :sriswed by yeu= Plan:

Saf a:7 Ze riaer C =mit:ss :: deca:-

ci=a whe:her a=7 ===sriawed safe:7 ques i.us a:s associated v'-" -la c::s :s.1:ad (Zaf a:sses 10C71 Secti:n 50.591? ,

If 4 such :srisw has .akan -

lace. when is it scheduled?

3. Scheduled da:a(s) f:r suh=1:-d !

pr: posed lics: sing ac:ics a= i -

sue:c--1:2 i=f m 1:n. Not scheduled at this ti=e: to be dete sined.

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6.  !=portas: lies: sing ceumiders-10:s assceia:ad vi_h refueling, e.g., new c; diffs:s== fuel da-sign or supplis=, ==rsriswed desig= or perferra ca analysis I catheds, signif'-*": changes i=

fuel design, saw cpe:a ' ! ;;:-

, CSd U*ts .

7. he cu=ber of fuel asse=blies laa: E GR fuel elaten:s (a) is .he c=:s and (b) in . 50 spen: 2.GR :.:al ele an s

..5.e seen- , ., se: see ree.,..

3. ~he ;;ssen:. lies: sed span: fuel
col s
:: age capaci:7 and :he Capacity is l' d :ed is size := ahcu: ace- i size of a..7 inersase is lies: sed .hird of core (app::xi-scaly 500 E GR s::: age ca:aci:7 :ha: has been ele =en:s). No change is p12 ed.
squastad c; is pla==ed, is

'er ef fuel asse=blies.

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e REFUE1ING I'TFORMATION (CONTINUD)

9. The projected date of the 1986 under the Three Party Agreement (Con-last refueling that can be tract AT (04-3)-633) between DOE, Public-discharged to the spent fuel Service Company of Colorado (PSCo), and

_.,_.. pool assuming the present General Atomic Company.* - - - - -

licensed cacaciev.

' ~ ~ ' ~

~ ~ *The 1986 date is based on the understanding that spent fuel discharged during the term of the Three Party Agreement will be shipped to the Idaho National Engineering Laboracory for storage by DOE at the Idaho Chemical Processing Plant (ICPP). The storage capacity has evidently been sized to accomodate

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fuel which is expected to be discharged during the eight year period covered by the Three Party Agreement.

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