Text

Monthly Operating Rept for Mar 1988
	ML20151G194
Person / Time
Site:	Fort Saint Vrain
Issue date:	03/31/1988
From:	Fuller C, Novachek F; PUBLIC SERVICE CO. OF COLORADO
To:	; NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
	P-88131, NUDOCS 8804190273
	Download: ML20151G194 (17)
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3 PUEl.IC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION i

1' MONTHLY OPERATIONS REPORT NO, 170 March, 1988 i

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"O'804190273 880331 PDR ADOCK 05000267 R DCD .

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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 No. DPR-34. This report includes the monthly partial scram / maximum temperature reports for control rod dirve and orificing assemblies previously submitted as a separate report. This report is for the month of March, 1988.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE The reactor remained critical the entire month of March, 1988.

On March 12, 1988, at 0600 hours0.00694 days 0.167 hours 9.920635e-4 weeks 2.283e-4 months , reactor power was reduced to approximately 60% in preparation for RT-500 fluctuation testing.

Testing was completed on March 13, 1988, at 0540 hours0.00625 days 0.15 hours 8.928571e-4 weeks 2.0547e-4 months . The core Delta P was increased from 3.37 psid to 4.37 psid with no core ,

shift observed. The highest control rod drive motor temperature observed during the testing was 245 degrees Fahrenheit on Region 12. This completes RT-500 testing for Cycle 4. Core Delta P is not predicted to exceed 4.3 psid during normal operation in Cycle 4.

On March 29, 1988, at 1835 hours0.0212 days 0.51 hours 0.00303 weeks 6.982175e-4 months , "C" helium circulator tripped on buffer-mid buffer when "C" recirculator tripped and "D" recirculator failed to pickup the helium load adequately. At 1841 hours0.0213 days 0.511 hours 0.00304 weeks 7.005005e-4 months , the turbine generator tripped on low main steam temperature. The "C" helium circulator was recovered at 2150 hours0.0249 days 0.597 hours 0.00355 weeks 8.18075e-4 months and the turbine generator was returned to service at 2335 hours0.027 days 0.649 hours 0.00386 weeks 8.884675e-4 months . As a result of the circulator trip, a minor moisture ingress occurred and the reactor entered the 90-Day Limited Acceptable Operation section of the LCO 4.2.11 curve at 2200 hours0.0255 days 0.611 hours 0.00364 weeks 8.371e-4 months . The reactor was returned to Acceptable Operation under LC0 4.2.11 at 0400 hours0.00463 days 0.111 hours 6.613757e-4 weeks 1.522e-4 months on March 30, 1988, when the reactor :

de r point was reduced to less than -20 degrees Fahrenheit. "

On March 30,1988, at 1200 hours0.0139 days 0.333 hours 0.00198 weeks 4.566e-4 months , the grace period for LC0 4.2.10 was entered when total primary coolant oxidants exceeded 10 ppm.

The LCO 4.2.10 grace period was exited on March 31, 1988, at 1330 l l hours when total primary coolant oxidants were reduced to less

than 10 ppm. A total of 2.4 PPM Days were accumulated during this period.

On March 31, 1988, at 1416 hours0.0164 days 0.393 hours 0.00234 weeks 5.38788e-4 months , "0" helium circulator tripped after "D" recirculator tripped and the standby "C" recirculator

{ failed to pickuo helium ioad adequately. The "D" helium circulator was recovered at 2158 hours0.025 days 0.599 hours 0.00357 weeks 8.21119e-4 months . The problems with the l

, recirculators tripping is presently under further evaluation. !

During the month of March, 1988, Fort St. Vrain set a new record for total net generation during a single month of 160,184 MWHe. l

_ The previous record was 156,977 MWHe during September,1981. :

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l 2.0 SINGLE RELEASES OF RADI0 ACTIVITY OR RADIATION EXPOSURE IN EXCESS OF 10'4 0F THE ALLOWABLE ANNUAL VALUE None 3.0 INDICATION OF FAILED FUEL RESULTING FROM IRRADIATED FUEL EXAMINATIONS None 4.0MONTHLYOPERATINGDATAREP0E Attached 1

5.0 CONTROL ROD ORIVE PARTIAL SCRAM TEST RESULTS AND MAXIMUM DAILY -

TEMPERATURE REPORT Attached i

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OPERATING DATA REPORT DOCKET .'40. 50-267 DATE Aoril 15. 1988 COMPLETED BY F. J. Novachek TELEPHONE (303) 620-1007 OPERATING STATUS h0TE5

.. Unit Name: Fort St.-Vrain. Unit No. 1

2. Reporting Period: 880301 throuah 880331

3. Licensed Thermal Power (Itit): 842 4 Nameplate Rating (Gross MWe): 342

5. Design Electrical Rating (Net MWe): 330

5. Maximum Dependable Capacity (Gross Fde): 342

7. Maximum Dependable Capacity (Net MWe): 330 ___

8. If Changes Occur in Capacity Ratings (!tems Number 3 Througn 7) Since Last Report, Give Reason:'

None

9. Power Level To Which Restricted, If Any (Net MWe): .270.6

10. Reasons For Restrictions, If Any: Reanalysis cf safe shutdown cooling following a 90 minute interruotion of forced coolina.

This Morth Year to Date Cumulative

11. Hours in Reporting Period 744 2.184 76.729

12. Number Of Hours Reactor Was Critical 744.0 2.149.1 35.595.R

13. Reactor Reserve Shutdown Hours 0. 0_ 0.0 0.0 14 Hours Generator On-Lir- 739.1 2.102.3 23.6A7.A

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0 IC. Gross Thennal Energy Generated (F4H) 455.972.8 1.099.219.1

, __12.032.553.7

17. Gross Electrical Energy Generated (F4H) 169.126.0 401.160.0 3.943.380.0 ta. Net Electrical Energy Generated (FWH) 160.184.0 378.278.0 3.468.544.0

19. Unit Service Factor 99.3 96.3 10.9

20. Unit Availability Factor 99.3 96.3 30.9

21. Unit Capacity Factor (Using MDC Net) 65.2 52.5 13.7

22. Unit Capacity Factor (Using DER Net) 65.2 52.5 13.7

23. Unit Ferced Outace Rate 0.7 . 3.7 62.5 24 Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each): Helium Circulatnr Reoairs. 880705. 2.184 hours0.00213 days 0.0511 hours 3.042328e-4 weeks 7.0012e-5 months .

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

26. Units In Test Status (Prior To comercial Operation): Forecast Achieved INITIAL CRITICALITY N/A N/A INITIAL ELECTRICITY N/A N/A COMMERCIAL O'PERATION 'u A N/A

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AVERAGE DAILY-UNIT POWER LEVEL-

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Docket No. 50-267 Unit Fort St. Vrain Unit No. 1 Date April 15, 1988 Completed By F.-J. Novachek Telephone (303) 620-1007 Month ' MARCH' OAYLAVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL.

.(MWe-Net) (MWe-Net) 1 233.1 17 229.1 2 235.5 18 224.7 3 237.7 19 216.4 4 233.3 20 203.9 5 234.1 21 203.4 6 231.2 22 204.4

7. 225.1 23 221.0

8. 234.6 24 217.3 9 227.4 25 219.2 10 189.1 26 217.8 11 215.9 27 216.0-12 201.6 28 226.5 13 233.9 29 168.8 14 229.6 30 120.2 15 225.0 31 171.5 16 227.1

Generator en line but no net generation.

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TSP-3 Attachment TSP-3C issue 2 Page 1 o f' 1 bNii SHUTDOWNS AND POWER REDUCTl9BS DOCKET NO. 50-267 UNIT NAME [ ort S t. . VIein Unit No. 1 DATE enril 15. 1988 COMPLETED BY Frank J. Noyaghek _

TELEPHONE L3C3 ) 620-1007 REPORT MONTH HARCH. 1968 1 I I l t ~ iiffiHOo Oft i i i l I I I I I IsHus.;9c I l l l CAUSE AND CORRECTIVE ACTION l NO. I DAIE ITYPEl CORATION l RLASON lDOWN : LER # ISYSTEMICOMPONENTl TO PREVENT RECURRENCE I I I I I I R.LA_Q T OR__ l ICOD L ICODE 1 i i i i l I i l I i I 3 168-061 880329 I I I 84 .9 tir i A 1 84 i N/A ; XX l )O0000( l Turbine Trip On Low Main Steam Temperature I l i i i i i I i t i Tollowing Trip Or C Helium circulator. I I I I I I I I I I I I I I I i l I i l i i i I I I I I I I I l : 1 I I I i l i i I i i I i I I I I I I I i l l I 1 I I I I I i i l i ! I I I I l i I I I I I i ! I l ! I I I I I I I I I l l l l l 1 1 I I 8 I i I i l l I I I i 1 I I I I I I I I I ! I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I i 1 i i i i I i l i i l i I I i i l i ! I I I I I I 1 1 1 1 I I I i l i I i I I I I I I i l I I I i l i 1 : 1 i 1 1 I I I I I I I I I I I I I I I I I I I I I I I i 1 I I I I i i i i i 1 i i l I I i I I I I I I I I I I I I I I I i 1 I i i I I I i I i l i i i l i I I I I I I I I i I I I I I I I I I I I I I i 1 1 I I I I I I I I I I I I ! I I i 1 I i 1 I I I I I I I:

1 I I l i 1 1 1 I i 1

-_ r

s REFUELING INFORMATION i I. -

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

, l 2. Scheduled date for next l. l l refueling shutdown. I April 4, 1989 l l '

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[ 3. Scheduled date for restart l May 27, 1989 l l following refueling. l l 1 I I i l 4. Will refueling or resumption off No l l operation thereafter require a l l I technical specification char.ge l l .

l or other license amendment? l l ,

I l l l If answer ir yes, what, in l ---------------- l l general, will these be? I l l l l l If answer is no, has the reloadl l l fuel design and core configura-l l l tion been reviewed by your l 1 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)? I l' I I I l If no such review has taken l 1988 l

[ place, when is it scheduled? l l l l 1 l l 5. Scheduled date(s) for submit- l I l l ting proposed licensing action l ---------------- l l and supporting information. l l l

l l l l [ 6. Important licensing considera- l l l l tions associated with refuel- 1 i l ing, e.g., new or different l l

' l fuel de sign or supplier, unre- 1 ---------------- 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

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, l 7. The number of fuel assemblies l 1 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 l

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REFUELING INFORMATION (CONTINUED) l . I l l 8. LThe present licensed spent fuell l

'I pool storage capacity and the l l l size of any increase in l Capacity is limited in size to l

j. licensed storage capacity that I about one-thirdlof core l l has been requested cr is l (approximately 500 HTGR elements).l l 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 1995 under Agreements AT(04-3)-6331

( 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 Cclorado, and General Atomic l l capacity. I Ccmpany, and DOE.* l The 1996 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 :ized to accommodate eight fuel segments. It is estimated that the eighth fuel segment will be discharged in 1996.

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y-CONTROL RCD ORIVE PARTIAL SCRAM TEST RESULTS AND MAXIMUM DAILY TEMPERATURE REPORT REPORT PERIOD:

MARCH 1, 1988 - MARCH 31, 1988

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Prepared byf' 8//7 MC/k/ /

"D6ane L. Spiker /

Senior Technical Services Engineering Technician e

i Approved by: r. I l !

i r ry . : auley ~

cting ant Engineering Supervisor 1

i Public Service Company of Colorado Fort St. Vrain Unit No. 1 w

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. 1 I. ABSTRACT l

This. report summarizes the partial scram test results and the 1 maximum daily ter.:perature of those control rods with motor temperatures above 215 degrees Fahrenheit. It is prepared to satisfy the Fort St. Vrain Interim Technical Specification Surveillance Requirement 4.1.1.A.1.a. The time period covered by this report is March 1, 1988, through March 31, 1988. .

II. BACKGROUND Because proper operation of the Control Rod Drive Mechan %

(CRDM) is critical for safe operation of the reactor, a series of qualification te s'.s were conducted over a one year time span to demonstrate its capability. The motor temperature during these tests varied between 200 degrees Fanrenheit and 230 degrees Fahrenheit, and averaged 215 degrees Fahrenheit.

A total of 130,000 jog cycles plus 1600 r : rams was logged c'uring 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 Devices (RTD's) are mounted on the closure plate, orifice valve motor plate, and CRDM motor as shown on Figure 1. All i

CRDM's installed in the Reactor are equipped with RTD's.

Three recorders located in the control room record each of these temperatures for all 37 CRDM's. CRDM motor temperatures are alarmeci at 212 degrees Fahrenheit and 247 degrees Fahrenheit.

CRDM motor temperatures are monitored at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to verify that they are less than 250 degrees i Fahrenheit, which is a limiting condition for operation. If l one or more CRDM motor temperature (s) is found to be greater l tnan 215 degrees Fahrenheit during the daily surveillance, the motor temperature of all CRDM's exceeding 215 degrees Fahrenheit is recorded and a partial scram test is performed i on the CRDM with the highest motor temperature once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . These surveillances ensure that CRDM motor temperatures exceeding 215 degrees Fahrenheit do not degrade the CRDM's reliability to perform its design function when required.

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SUMMARY

OF 6ESULTS Regions 12 and 30 CROM motor temperatures exceeded 215 degrees Fahrenheit during the entire month of March, 1988, with the exception of March 11 and 30. The partial scram test ,esults and maximum daily temperature of those C7.0M ' s with motor temocratures above 215 degrees Fahrenheit are presented on Table 1. The pertinent parameters are: reactor region involved, control rod position, maximum daily motor temperature, extrapolated scram times (surveillance value and Back EMF calculated value) and starting acceleration. The control rod position is presentea because of its relationship to available starting torque which affects the starting acceleration and extrapolated scram time calculated by surveillance. The surveillance extrapolated scram time is affected by control rod position because it is calculated using distance travelled versus time. Since the acceleration is slower at lower control rod positions, a longer period of time is required to reach steacy state speed. This longer acceleration period results in 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 prnjected full length scram time. Therefore, the surveillance scram times can only be compared for trends if the control rod position is approximately the same. The Back EMF calculated scram time is more readily trended since the value should be incependent of control rod position.

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 speec 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 if the control rods were at the full out position (greater than 188 inchesj. If the control rod position is greater than 188 incnes, no data is presented for a projected starting acceleration since the actual and projected are the same. As dndicated with scram times, the projected starting acceleration is more readily trended since the value should be independent of control rod position.

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8 Page 3 IV. CONCLUSIONS The performance of CRDM's with motor temperatures in excess of 215 degiees Fahrenheit did not show any significant trends or degradation during this recort period. Therefore, it is cone.iuded that CRDM motor temperatures exceeding 215 degrees Fahrenheit did not degrade the CRDM's capability to perform its cesign function when required.

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( TEMPERATURE

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CROM MOTOR / I ' '

TEMPERATURE /

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ORIFICE VALVE WOTOR ASSEWOLY n '

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WOTOR PLATE TE MPE R AT1,lRE

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I Figure 1 Control Rod Drive Mechanism Temperat'Jre Sensor Locations

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. . 5 Page 5 IABLE 1 Control Rod Ma x i stm Da i l y E x t ra po l a ted Sc rap. Starting AcCOleratIOn Date 14cgion# Position Motor Temperature T i me ( Sec ) * * (Rad /Sec/Sec) ***

(loches) ( Deg ree s f a h renhe i t ) Surv. Back (MF Actual Pro.jected 3-01-88 12 189." 225.0 147.3 143.9 113.7 -----

30* 220.0 -----

3-02-88 12 189.7 226.8 150.8 144.9 114.0 -----

30* 221.3 -----

3-03-88 12 189.7 221.0 149.6 1 r4 3. 9 116.0 -----

30* 220.0 -----

3-04-88 12 189.7 227.5 150.8 **** **** -----

30* 220.8 -----

3-05-88 12 189.8 226.8 149.6 **** **** -----

30* 220.4 --~~-

3-06-88 12 189.7 227.8 ' 150.8 145.1 114.0 -----

30* 221.8 -----

3-01-88 12 189.8 225.7 149.6 144.1 113.7 -----

30* 219.4 -----

3-08-88 12 189.8 232.0 150.8 **** **** -----

30* 221.0 ----.-

J-09-88 12 189.7 227.0 150.8 If4.0 4 116.3 ---

. 30* 222.0 -----

3-10-88 12 189.7 227.0 184 9. 6 144.1 114.4 -----

30* 222.0 -----

3-11-88 12 189.8 224.0 149.6 144.0 115.0 -----

Only itegino'with Highest Cf tM Motor Temperature is Tested

- Limiting Condition for Operation: <152 Seconds

- - Acceptance Cri teria Appl ied During Preventive Ma intenance: >98.83 Rad /Sec/Sec

- - - Back LMF Data Not Available for Date Indicated Note 1 No Survei l lance da ta is available for this date.

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h9e.6 TABl_E 1 Control Rod Maximens Da ily Extrapolated Scram Sta rting Accelera tion Date Regiong /osition Motor Temperature Time (Sec)** (Rad /SecfSec) ***

( i ncN*s ) ( Deg rees Fah renhe i t ) Sury. Back EMF Actual -Projected 3-12-83 12 189.6 224.0 150.8 143.8 114.1 = -=

30* 218.0 -----

3-13-88 12 189.7 247.8 149.6 144.3 115.1 -----

30' 237.9 -----

3-14-88 *2 See 233.7 See 144.1 113.9 -----

30' Note 1 227.3 Note 1 -----

3-15-?8 12 18'. 232.0 149.6 144.1 113.7 -----

30* 226.0 -----

3-16-88 12 189 8 233.0 152.0 144.0 116.0 -----

30* 224.0 -----

3-17-88 12 189.7 233.3 151.5 144.2 ~ 113.4 -----

3G" 226.8 -----

3-18-88 12 189.7 237.1 151,9 144.1 116.4 -----

30* 227.3 -----

3-19-88 12 189.6 233.4 151.8 144.1 114.2 -----

30* 226.7 3-20-68 12 189.8 228.6 150.0 144.1 113.2 -----

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30* 718.7 -----

) 3-21-58 12 189.8 226.5 150.6 144.0 113.8 -----

30* 219.5 -----

3-22-88 12 189.7 227.1 150.8 144.0 115.3 -----

30* 220.6 -----

Only Region with Highest CROM Motor Temperature is Tested

- t_imi ting Condi tion for Operation: <152 seconds - ',

- Acceptance C;'iteria Applied During Preventive Maintenance: >98.83 Rad /Sec/'.,ec

- - - Back IMF Data Not Available for Date Indicated Note 1 No Su rve i l lance da ta 33 available for this dete.

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(inches) ( Deg rees Fahrenheit) Surv. Back [MF ActuaI Projected 3-23-88 12 189.7 230.3 149.6 144.1 113.5 -----

30* 225.0 -----

3-24-88 12 189.6 229.6 150.8 143.9 115.5 -----

30* 224.1 -----

3-25-88 12 189.7 232.5 149.6 144.1 113.6 ----

30* 226.8 -----

3-26-88 12 189.6 232.6 151.5 144.0 114.8 -----

30* 227.5 -----

3-27-88 12 189.6 232.4 150.8 145.0 113.6 -----

30* 226.4 -----

3-28-88 12 189.6 232.6 151.8 144.0 116.0 -----

30* 226.2 -----

3-29-88 12 189.7 232.8 150.8 144.0 114.1 -----

30* 226.0 -----

3-30-88 NO CRDet MOION T[HPERATURE EXC((DED 215 DEGREES FAHRENHEl T THIS DATE, A1 THE TlHE OF OAY TEMPERATURES WERE SURVEILLED. -----

3-31-88 12 189.6 232.9 150.0 144.0 116.0 -----

. 30* 226.9 -----

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Only Reg.on wi th Highest CRDM Motor Temperature is Tested

- L i m i t i na cond ( t i on fo r ope ra t i on- <152 Seconds

- - Acceptance Criteria Applied During Preventive Maintenance: >98.83 Rad /Sec/Sec

- - - Back [Hf Da ta ' Not Ava ilable for Date Indicated Note 1 No Survei l lance da ta is availabl-3 for this date.

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h Public Service ~ ==L

}6805 WCR 19 1/2, Platteville, Colorado 80651 April 15, 1988 Fort St. Vrain Unit No. 1 P-88131 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20L 3 Docket No. 50-267 I

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SUBJECT:

MARCH 1988, MONTHLY l OPERATIONS REPORT

REFERENCE:

Fccility Operating License No. OPR-34 P-88106, Dated 3/21/88 l Williams to Calvo i

Dear Sir:

l l Enclosed, please find the Monthly Operations Report fu the month of l March 1988, submitted per the requirements of Fort St. Vrain Technical Specification AC 7.5.1.

l Also attached to the Monthly Operations Report is the Control Rod l

, Drive Partial Scram Test Results and Maximum Daily Tempera.ure l Report. Thi will be included as a regular attachment to the Monthly l Operations Report, as stated in P-88106.

l l If you have any questions, please contact Mr. M. H. Holmes at I

(303) 480-6960.

l Sincerely, 1

l C. H. Fuller l

Manager, Nuclear Production Enclosure cc: Regional Administrator, Region IV ATlN: Mr. T. F. Westerman, Chief Projects Section B Mr. Robert Farrell Senior Resident inspector

[h' i 1 Fort St. Vrain CHF:djm

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ML20151G194

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