ML20246Q224

Monthly Operating Rept for June 1989 for Fort St Vrain Unit 1

ML20246Q224
Person / Time
Site:	Fort Saint Vrain
Issue date:	06/30/1989
From:	Block M, Fuller C PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
P-89266, NUDOCS 8907210030
Download: ML20246Q224 (16)

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'16805 WCR 19 1/2, Platteville, Colorado 80651 July '15,1989 Fort St. Vrain Unit No. 1 P-89266 U. 5. Nuclear Regulatory Commission ATTN: Document Control Desk p

Washington, D.C. 20555 Docket No. 50-267

SUBJECT:

JUNE 1989 MONTHLY OPERATIONS REPORT

REFERENCE:

Facility Operating License Number DPR-34

Dear Sir:

Enclosed, please find.the Monthly Operations Report for the month of-June 1989, submitted per the requirements of Fort St. Vrain Technical Specification AC 7.5.1.

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

Sincerely, C. H. Fuller Manager, Nuclear Production CHF/sih Enclosure cc: Regional Administrator, Region IV ATTN: Mr. T. F. Westerman, Chief Projects Section B Mr. Robert Farrell Senior Resident. Inspector Fort St. Vrain ,

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

MONTHLY OPERATIONS REPORT

. . . NO. 185 June, 1989 1

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l 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 No. DPR-34. .This report includes the monthly partial scram / maximum temperature reports for control rod drive and orificing assemblies. This report is for the month of June,1989.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE The reactor remained critichi the entire month of June,1989.

At 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> on June 1, 1989, the hot reheat steam temperature for steam generator module B-2-6 increased by approximately 43 degrees. React.r. power was reduced and attemperation was taken out of service. It was determined that the attemperator nozzle to the module was blocked. During subsequent maintenance, the nozzle was removed and repaired.

At 1422 hours0.0165 days <br />0.395 hours <br />0.00235 weeks <br />5.41071e-4 months <br /> on June 7, 1989, with the plant operating at 59 percent power, an automatic shutdown of Loop I primary and secondary coolant systems was initiated by the Plant Protective System. It was determined that the line power fuse.in FM-2205-8, the Loop I .feedwater flow to circulator speed characterized, .had blown, removing the remote speed setpoint signal from ' A' and 'B' circulator speed controllers. As a result circulator speeds were automatically reduced, and both circulators tripped on programmed low speed, which in turn tripped the loop. Reactor power was automatically reduced and stabilized by the plant control system at 30 percent power. The turbine generator was taken off line at 1445 hours0.0167 days <br />0.401 hours <br />0.00239 weeks <br />5.498225e-4 months <br />. Since this automatic loop shutdown actuation was not part of a pre planned sequence, this event was reported to the Nuclear Regulatory Commission in Licensee Event Report 89-0010.

The Turbine Generator was again placed on line at 1127 hours0.013 days <br />0.313 hours <br />0.00186 weeks <br />4.288235e-4 months <br /> June 9, 1989.

A hydraulic oil leak developed on HV-2224. Oil was isolated to the valve during repairs resulting in utilization of the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> grace period of LC0 4.4.1. The oil leak on HV-2224 was repaired.

The valve stroke-tested satisfactorily and was returned to service.

On June 17, 1989, 'C' Boiler Feed Pump was removed from service due to excessive vibration and reactor power was reduced accordingly. Pump internals were removed and replaced and 'C' Boiler Feed Pump was placed in service at 0110 hours0.00127 days <br />0.0306 hours <br />1.818783e-4 weeks <br />4.1855e-5 months <br /> on June 22, 1989.

On June 20, 1989, a hydraulic oil leak developed on 'A' Circulator Speed Valve SV-2105. The circulator was shutdown and reactor power was reduced to approximately 30 per cent. Repairs and testing of SV-2105 were completed on June 22, 1989. Reactor rise to pows- commenced at that time.

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. At approximately' l0217 hours. on June 23, 1989, it was discovered-that reheat attemperation flow had not- been factored into the secondary iheat balance _ calculation- of reactor power. Upon manually updating the secondary heat balance program, . reactor p'ower (as indicated by secondary- heat- balance) indicated approximately 83.4 per _ cent. Immediate action was .taken to reduce reactor power below the 82.per cent NRC authorized limit.

This event is being reported to the Nuclear Regulatory Commission-in Licensee Event Report 89-0011.

At. 0155 hours0.00179 days <br />0.0431 hours <br />2.562831e-4 weeks <br />5.89775e-5 months <br /> on June 28,.1989, with'the reactor operating.at 79 percent, a smal1 portion of an unanalyzed gas waste receiver 'was released to -the plant ventilation exhaust stack. -Immediate action was=taken to terminate the release. The receive'r Efrom which this. release occurred was sampled and' analyzed. Activity concentrations.were.found to be well within 'allowcble limits.

Since Fort St. Vrain . Technical Specification ELCO 8.1.1 d requires.the contents of the gas waste receiver be sampled and analyzed prior to a release, this . event constitutes operation' in

-violation of:the Technical Specification and will be reported..to the Nuclear: Regulatory Commission. in- Licensee Event Report.89-0012.

While- performing the- annual calibration surveillance onA' diesel generator set:an June 29, 1989, problems' were- discovered

.with the over-speed trip mechanism. Repairs were immediately-initiated and on June 30, 1989,. 'A' diesel generator ' set' was-declared operable.

2.0 SINGLE RELEASES OF RADI0 ACTIVITY OR RADIATION EXPOSURE IN EXCESS OF 10% OF-THE ALLOWABLE ANNUAL VALUE None

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3.0 INDICATION OF- FAILED FUEL RESULTING FROM IRRADIATED. FUEL EXAMINATIONS None 4.0 MONTHLY OPERATING DATA REPORT Attached 5.0 CONTROL ROD DRIVE PARTIAL SCRAM TEST RESULTS AND MAXIMUM DAILY TEMPERATURE REPORT Attached p &

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OPERATING DATA REPORT DOCKET NO. 50-267 DATE July 15, 1989 COMPLETED BY M.L. Block TELEPHONE (303) 620-1180 OPERATING STATUS NOTES

1. Unit Name: Fort St. Vrain, Unit Number 1

2. Reporting Period: 890601 through 890630

3. Licensed Thermal Power (MWt): 842

4. Nameplate Rating (Gross MWe): 342

5. Design Electrical Rating (Net MWe): 330

6. Maximum Dependable Capacity (Gross MWe): 342

7. Maximum Dependable Capacity (Net MWe): 330

8. If Changes Occur In Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:

.None.

9. Power Level To Which Restricted, if Any (Net MWe): 270.6 (82%)

10. Reasons For Restrictions, if Any: Reanalysis of safe shutdown cooling following a 90 minute interruption of forced ccoling.

' This Month Year To Date Cumulative

11. Hours In Reporting Period 720.0 4,343.0 87.672.0

12. Number Of Hours Reactor Was Critical 720.0 2,164.0 39,408.8

13. Reactor Reserve Shutdown Hours _

0.0 0.0 0.0

14. Hours Generator On-Line 675.2 1,548.6 26,621.4

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thennal Energy Generated (MWH) 391,039.6 801,528.7 13,689,238.8

17. Gross Electrical Energy Generated (MWH) 146.751.0 285,238.0 4,545,642.0

18. Net Electrical Energy Generated (MWH) 138,610.0 256,359.0 4,006,353.0

19. Unit Service Factor 93.8 35.7 30.4

20. Unit Availability Factor 93.8 35.7 30.4

21. Unit Capacity Factor (Using MDC Net) 58.3 17.9 13.9

22. Unit Capacity Factor (Using DER Net) 58.3 17.9 13.9 '

23. Unit Forced Outage Rate 6.2 63.6 64.1

24. Shutdowns Scheduled Over Next 6 Months (Type. Date, and Duration of Each):

None.

25. If Shut Down At End Of Report Period. Estimated Date Of Startup: N/A

26. Units In Test Status (Prior To Connercial Operation): F recast Achieved.

INITIAL CRITICALITY N/A N/A INITIAL ELECTRICITY N/A N/A COMMERCIAL OPERATION N/A N/A

AVERAGE DATLY UNIT POWER LEVEL

. Docket No. 50-267

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Unit Fort St. Vrain Unit No. 1

' Date July 15, 1989 Completed By M. L. Block-Telephone (303) 620-1180 Month JUNE DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 183.0 17 227.5 2 204.5 18 212.3 3 182.1 19 208.3 4 178.9 20 113.1 5 177.8 21 87.5 6 177.4 22 134.0 7 106.5 23 224.7 8 0.0 24 195.3 9 57.3 25 240.0 10 212.0 26 244.3 11 239.0 27 241.2 12 240.1 28 242.7 13 240.9 29 242.6 14 ?40.0 30 244.0 15 239.6 31 N/A 16 243.7

• Generator on line but no net generation.

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REFUELING INFORMATION i ,

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l 1. Name of. Facility i Fort St. Vrain Unit No. 1- [

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~ l 2. Scheduled date for next l None, no further refueling at. l l_ refueling shutdown. FSV is expected. l l- .

l l 3. Scheduled date. for restart l N/A l

_l following refueling. l l l l l l 4. Will refueling or resumption ofl N/A l operation t'lereafter require a l

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l l l technical specification change l l l_ or other license amendment? -1 j-I l l l 'If answer is yes', what, in l ---------------- l

l. general, will these be? I ,j l l l

.] If: answer is no,'has the reloadj l l fuel design and core configura-l l-l: ' tion been reviewed by your l .

l l Plant Safety Review Committee l'N/A l l to. determine whether any unre- l l

l. viewed, safety questions.are l l l associated with the core reload l j.

-l (Reference 10 CFR Section l l~

l 50.59)? I l 1 I I l- If no such review has.taken_ l N/A 1 l place, when is it scheduled? l l l .

I i l 5. Scheduled date(s) for submit- l -l l ting proposed. licensing action l ---------------- j' I and supporting information. i l

-l l I l .6.- Important licensing considera- 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

.I 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

t REFUELING INFORMATION (CONTINUED) l l'

L I- 1 i l 8. The present licensed spent fuell )

l pool storage capacity and the [ l-l size of any increase in l Capacity is limited in size to [

] licensed storage capacity that I about one-third of core l l has been requested or is I (approximately 500 HTGR elements).1

] planned, in number of fuel l No change is planned. l l assemblies. l l l 1 l l 9. The projected date of the last l 1993 under Agreements AT(04-3)-6331 1 refueling that can be dis- l and DE-SC07-791001370 between l l charged to the spent fuel pool l Public Service Company of I l assuming the present licensed l Colorado, and General Atomic l l capacity. I Company, and 00E.* l No further refueling is. anticipated at Fort St.-Vrain. Spent fuel discharged during the defueling process will be stored by DOE at the Idaho Chemical Processing Plant. The storage capacity is presently sized to accommodate eight fuel segments. It is estimated that the eighth fuel segment will be discharged in 1993. .

I

CONTROL ROD DRIVE PARTIAL SCRAM TEST RESULTS AND MAXIMUM DAILY TEMPERATURE REPORT REPORT PERIOD:

June 1,1989 - June 30,1989 i

Prepared by:f'o)b'G1pgafff System Engineer Systems Engineering i

Approved by: My gme-Steve Jonfs~~

Preventive Maintenance Supervisor Systems Engineering Public Service Company of Colorado Fort St. Vrain Unit No. I l

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4L ABSTRACT This . : report summarizes the partial scram test results and 'the maximum daily-temperature of those control rods .with motor temperatures above 215 degrees Fahrenheit. . -It is prepared to satisfy the Fort St. Vrain LInterim Technical Specification Surveillance Requirement 4.1.1.A.I.a'. . The time period. covered.

by this report is June 1, 1989, through June 30, 1989.

.II. BACKGROUND Because proper operation. . of the Control Rod Drive techanism (CRDM) ds critical for safe. operation of the reactor, a series of quaiaJication tests were conducted over a one year l time span to. demonstrate its capability.. The motor temperature during these tests varied between 200 degrees Fahrenheit and.

230 degrees Fahrenheit, and averaged 215 degrees Fahrenheit.

[ A total of 135,000 jog cycles plus 1600 scrams was logged.

during the final design testing, which is many times that expected over..the normal life of a CRDM. The operating temperature of the CRDM is limited by .the motor's. Class H insulation which is de-rated to. 272 degrees Fahrenheit to.

account- for motor temperature. rise, frictional- torque.

increase, and winding life expectancy.

In order to monitor CRDM temperatures, Resistance' Temperature c

Devices (RTD's) are mounted on the closure _ plate, orifice-valve motor plate, and CRDM motor. as shown on : Figure 1. ' All CRDM's installed in the-' Reactor are ' equipped' with RTD's.

Three recorders located in- the control roam record each of these' temperatures for all 37 CRDM's. CRDM motor tempt 3tures-are alarmed at 212 degrees Fahrenheit and 247 ;grees Fahrenheit.

CRDM motor temperatures. are monitored at least' once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to verify that they are less than 250 degrees Fahrenheit, which is a limiting condition for operation. If one or more CRDM motor temperature (s) is found to be greater--

than 215 degrees Fahrenheit during the daily surveillance,'the motor temperature of all CRDMs exceeding 215 degrees-Fahrenheit is- recorded and a partial scram test is performed on the CRDM with the highest motor' temperature once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. These surveillance ensure that CRDM motor temperatures exceeding 215 degrees Fahrenheit do not degrade the CRDM's reliability. to perform its design function when required.

III.

SUMMARY

OF RESULTS During the month of June, Region 12 and Region 30 "RDM motor temperatures exceeded 215 degrees Fahrenheit. The temperatures were in excess of 215 degrees Fahrenheit for the period of June 1,1989 through June 7, 1989, June 10, 1989 through June 20, 1989 and June 23, 1989 through June 30, 1989.

On June 11, 1989, Region 30 CRDM exceeded 250 degrees Fahrenheit. Repositioning the orifice valve brought the temperature below 250 degrees Fahrenheit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

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The partial scram test results and maximum daily temperature t -

of'those CRDM's with motor temperatures' above 215 degrees Fahrenheit are presented on Table 1. The pertinent parameters are: reactor region' involved, control rod position,. maximum daily 1 ' motor temperature, extrapola.ted scrami. times (actual value'and projected value) and starting acceleration. The control rod position is presented because of its relationship to. available , starting torque which affects the starting acceleration -:and extrapolated scram time. The extrapolated scram time'is affected by control rod position because it is calculated- using ' distance traveled 'versus time. Since the acceleration is slower at lower control rod positions, a 4 longer period of time is required to reach steady state speed.

This longer acceleration period results Lin a decrease in distance travelled. over. a given period of time..thereby

[., indicating a longer extrapolated ' scram-time. The extrapolated scram time calculated by; the Back EMF program applies a-correction factor.to provide a projected full length scram time.'

The starting acceleration values presented are. calculated by the Back EMF program. These values reflect the CRDM's freedom of. rotation to accelerate to steady state speed and therefore are considered to be valuable performance indicators. Two-values are presented: The actual acceleration measured during a scram from the indicated control rod position- and the.

projected acceleration .i f the control rods were at the full.

out position (greater than 168 inches). If the.. control. rod position is. greater than 188 inches, no data is presented for a: projected starting acceleration since the actual and projected are the same. As indicated with scram times,~the projected starting acceleration is more readily trended since the value should be independent of control rod position.

IV. CONCLUSIONS The performance of CRDMs with motor temperatures in excess of 215 degrees Fahrenheit did not show any significant trends or degradation during this report ' period. Therefore, it is concluded that CRDM motor temperatures exceeding 215 degrees Fahrenheit did not degrade the'CRDM's capability to perform its design function when required.

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DATEL REGICN , CCitTROL . R'O -iAXIMUM DAILY SCRAM TIME STARTING POSITICN HOTOR TEMP ACCELERATICtl TEST' FULL "'FOKE ACTUAL ~ MOJECTED o***n**********************nnana******ws**********************n******ws***************

9pc;/cg. j;s, ' ---_.-_ _ 244,9 . _ _ _ _ . _ _ . .-- ....__...___...____

30 188.0 249 10 -134.0 117.7 - - - - - - - -

n6/02/09 - 12* - --- - -- 229.5 - - - - - - - - - - - " - - - - ------ -----------

30 '180.0 230.7 10 134.9 117.7 -------- -

-30/G3f39 12* - - - - - ~

225 - - - - - - - - - - - - - - - -

30 199 226.2 10 134.9 117.1.---------

2 06/04/89 12* -----*-- 226.1 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

30 189 228.1 10 134.3 120.3.---------

- 0G/05/E9 12* --------"- 224.6 -----------~~----- - - - - - - - - - - - - - - - -

30 108.9 220.5 10 134.3 12 0 . 3 . - -- --- - -

36/0C/09 12* - - - - - - - - - 223.3 - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

30 180.3 225.3 10 134.G 120.3 ---------

OG/07/09: 12* - - - - - - - - - -

223.1 -------- ----- -----------------

30 100.0 226 10 134. G 1 16 . 5 ------- -

- - - - - ~ ~ - - - - - - - - -

06/10/89 12* -- -- ---- 235 ---------- - ----

30 189.9 247.2 10 137.6 NO BACK EHF DATA-06/11/09 12* ---~ ~---- 231 - - - - - - - - - - - - - - - - -

30 189.3 250.~**** 10 130.1 NO BACK EHF DATA 06/12/89 12* ----- - - -

229 --------------- -

10 109.' 244.2 10 174. I!?.8 ---------

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229 . . . . . _ _ - . _ . .__,_ . _____ ..

30 103.9 246.4 10 136.9 NO GACK EMF DATA 06/!4/09 12* - - ~ ~ - -

229.5 ------- ----- --- ----~- ~~~------

30 188.0 246.7 10 135 121.6 ---------

06/15/09 12* --------- 235.1 - - - - - - ~ ~ - - - - - - - - - - - - - - - - - -

30 188.0 244.5 10 134.8 100.7 ---------

06/18/89 12* -----------

235.6 --- ------- ------ -----------------

30 108.6 240.3 10 134.8 116.1 ---------

06/17/09 12* -- - -----

236 - - - - - - - - - - - - -

30 188.G 240.5 10 134.3 121.2 - ------

l 06/10/09 12* - - - - - - - - - - 225.5 --~ ~~---------- - - - - - - - - - - - - - -

! 30 180.9 228.5 10 134.2 110.1 ---------

1 06/19/89 12* ------ ---

224.0 --- ------ -- - - - - - - - - - - - - - - - -

30 189.8 228 10 134.9 117.8 ---------

00/20/89 12* ----------- 221.9 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

30 190 223.4 10 134 .1 81.3 -------- *****

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DATE REdICH CCtJTROL RCO ~ MAXIMUM WlLv CCRAM TDiE  : T '.; tit Ki inSITICfl MOTOR TEMP CE .!R/Fl0N TEST FULL ITROr<E 'TO' PROJECTED W*********vrussem*************************uar**************************u,+wr**********-

D6/23lU9L 1;Y- -- +L------ 23L. - - - - - - - - ~ ~ ~ - --- =--- -------

20 160./ 240.: 10 134.7 !25 - -------

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230.2 ---------------- - - -- - ---- --

G 191 232.7 10 134.G ~L.2 -------- *****

06/25/09 12+ - - - - - - - - - -

234.0 ----------------- -- --- --------

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. 191 240.L 10 134.9 !08.0 --- -----

06/26/09 1'* ---------

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30 109 241.6 !O- 134.9 'O.9 -------- *****

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- 6/27/09 12" --------~~- 235.3 ---------------- - - - - - - - - - - - - - -

20 189.3- 241.8 10- 134.0 '9.I ---------

, g3/79/g9- 3;' - -----~~-- 235.5 ---------- ----- -~ -------- -

30 109.2 241.9- 10 134.0 '1:3.9 --------

gg/29/g9 19* . -------- 035.0 -

30 109.6 241.L 10 134.0. It?.1 - - - - - - ~

, CG/30/89 42* -----------

235.5 ------------------ - ----------- -

.189.4 242.3 .10 134.0 ;13.2 -- -- - -

30-

+ Cnly Region with Highest CF.0M Hoter Temperature is Testen

" Limiting Condition for Cpei sti sn: <152 Seconds "T * .cuptance Criteria Applina Uring Preventive Maintenance: 93.83 Rad /Sec/Sec

" * * -scion 30 CRDOA Deciared S ersble. Adjustment of oi;r:~' 31ve position sought temperature below M C 'Mgrees Fahrenheit m thic :  ;. s

• * * " C ara nout unusable due N -iectrical interference ff0TE: ,n June 10, 11, and 13, IcGC oo Sack EHF data cclheted 1

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