ML20138M368

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Monthly Operating Rept for Nov 1985
ML20138M368
Person / Time
Site: Rancho Seco
Issue date: 11/30/1985
From: Colombo R, Reinaldo Rodriguez
SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
RJR-85-582, NUDOCS 8512200404
Download: ML20138M368 (8)
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'. i AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-312 UNIT Rancho Seco Unit 1 DATE 11-30-85 COMPLETED 8Y R. Colombo TELEPHONE (91'6) 452-3211 MONTH November 1985 DAY- AVERAGE' DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 0 17 581 2- 0 18I 670 3 106 19 730 4' 331 20 794 5 343 21 796 s

6 352 22 798 7 103 23 795 8 251 '24 790 9 334 25 792 10 335 26 793 .

11 338 27 791 12 337 28 795 13 349 29 794 14 347 30 795 15 348 31 ---

16 368 INSTRUCTIONS.

On this format, list the average daily unit power level in MWe-Net for each day.

l-in the reporting month. Compute to the nearest whole megawatt.

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B512200404 851130 PDR ADOCK 05000312: /

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OPERATING DATA REPORT )

DOCKET NO. 50-312 DATE 11/30/85 COMPLETED 8Y R. Colombo TELEPHONE (916) 452-3211 OPERATING STATUS NOTE:

7

1. Unit Name: Rancho Seco Unit 1
2. Reporting Period: November 1985
3. Licensed Thermal Power (MWt): 2.772

. 4. Nameplate Rating (Gross MWe): 963

5. Design Electrical Rating (Net MWe): 918

. 6. Maximum Dependable Capacity (Gross MWe): 917

7. Maximum Dependable Capacity (Net MWe): 873
8. .If changes-Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons: N/A

-9. Power Level to Which Restricted If Any (Net MWe): N/A

10. Reasons For Restrictions, If Any: N/A This Month Yr-to-Date Cumulative
11. Hours in Reporting Period 720 8.016 93.121
12. Number.of= Hours Reactor Was Critical 673.2 2.466.6 53.914

! 13. ~ Reactor Reserve Shutdown Hours 0 110.5 10.300.4

14. Hours Generator On-Line 643.3 2.316.1 49.979.6 ,'
15. Unit Reserve Shutdown Hours 0 0 1.210.2
16. Gross Thermal Energy Generated (MWH) 1.175.252 5.306.624 126.913.026
17. Gross Electrical Energy Generated (MWH) 388.966 1.772.746 41.204.709

, 18. Net Electrical Energy Generated (MWH) 356.641 1.646.629 38.237.825

! 19. Unit Service Factor 89.3% 28.9% 53.7%

20. Unit Availability Factor 89.3% 28.9% 55.0%

i 21. Unit Capacity Factor (Using MDC Net) 56.7% 23.5% 47.0%

22. Unit Capacity Factor (Using DER Net) 54.0% 22.4% 44.7%

i 23. Unit Forced Outage Rate . .

8.5% 28.8% 29.8%

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

N/A i

25. If Shut Down At End Of Report Period Estimated Date of Startup: N/A
26. Units In Test Status (Prior to Commercial Operation): Forecast Achieved INITIAL CRITICALITY N/A N/A
INITIAL ELECTRICITY N/A N/A N/A N/A COMMERCIAL' OPERATION 4

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6 DOCKET NO. 50-312 -

UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME Rancho Seen (fnit i DATE Nov 30. 1985 COMPLETED BY R. Colombo REPORT MONTH NOVEMBER TELEPHONE (916) 452-3211 e.

-, 3? };; Yh Licensee E*,

q Cause & Corrective

%. Date g 3g ,, g 5 Event aT Action to

  • $3 5 j$g Report er N0 yV Prevent Recurrence d

6 85/11/01 F 46.8 H 1 85-19 ZZ ZZZZZZ Reactor trip on high pressure. Trip preceded by "A" MFP turbine trip and a low condenser vacuum. An " action item" list was submitted to the NRC on 10/18/85. Reactor brought criti-cal on 11/2/85.

I 2 3 4 F: Forced Reason: Method: Exhibit G - Instructions S Scheduled A Equipment Failure (Explain) 1 Manual for Preparation of Data B Maintenance of Test 2 Manual Scram. Entry Sheets for Licensee C Refueling 3 Automatic Scram. Event Report (LER) File INUREG-D-Regulatory Restriction 4-Other (Explain) 01611 E-Operator Training & License Examination F Administrative 5 G-Operational Error (Explain) Exhibit I - Same Source tH77) Il-Other (E xplain)

$ SMUD SACRAMENTO MUNICIPAL UTILITY DISTRICT O 6201 S Street, P.O. Box 15830. Sacramento CA 95852-1830.1916) 452-3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA RJR 85-582 December 16, 1985 DIRECTOR OFFICE OF INSPECTION AND ENFORCEMENT U S NUCLEAR REGULATORY COMMISSION WASHINGTON DC 20555 OPERATING PLANT STATUS REPORT DOCKET NO. 50-312 Enclosed is the November 1985 Monthly Plant Status Report for Rancho Seco Unit No. 1.

\ \

R DR UE ASSISTANT GENERAL MANAGER, NUCLEAR Enci (5) cc: I & E Washington (9)

Region V MIPC (2)

INP0 TE24

'Ii

NOVEpBER 1985

SUMMARY

OF PLANT OPERATIONS Following a thirty (30) day period in a hot shutdown condition, the reactor was taken critical at 2248 hours0.026 days <br />0.624 hours <br />0.00372 weeks <br />8.55364e-4 months <br /> on November 2, 1985. The 200 KV breakers were closed to bring the plant on line at 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br /> on November 3, 1985 and power was leveled to approximately 42%. At 1115 hours0.0129 days <br />0.31 hours <br />0.00184 weeks <br />4.242575e-4 months <br /> on November 7, 1985, power was reduced to 15%, the 220 KV breakers were opened, and the turbine trip test per-formed. At 0606 hours0.00701 days <br />0.168 hours <br />0.001 weeks <br />2.30583e-4 months <br /> on November 8, 1985 the breakers were closed and power brought to approximately 42%. On November 17, 1985 at 0430 hours0.00498 days <br />0.119 hours <br />7.109788e-4 weeks <br />1.63615e-4 months <br />, power was increased to approximately 75%. On November 19, 1985, power was increased to approximately 91% and held at this level for the remainder of the month.

PERSONNEL CHANGES REQUIRING REPORT None

SUMMARY

OF CHANGES IN ACCORDANCE WITH 10 CFR 50.59(b)

None MAJOR ITEMS OF SAFETY RELATED MAINTENANCE

1. The 427-B1 undervoltage relay for the 4B 4160V bus was replaced. The relay was found to be erratic while performing Engineering Change Notice (ECN)

R-Oll2. ECN R-Oll2 adds a pickup voltage tolerance band of i 0.3V at the 94.2. volt level to prevent the undervoltage relay inverse time delay characteristics from falling outside the technical specification's requirements.

CORRECTIONS / ADDITIONS TO PREVIOUS REPORT The description of the once-through-steam-generator (OTSG) tube plugging

-contained in the May 1985 report did not meet the District's full reporting requirements (Technical Specification 4.17) for inservice inspections.

The following information supersedes that given in the May report.

OTSG Tube Plugging Summary

1. Total number of tubes inspected:

a b c d "A" 0TSG 3246 641 1555 444 "B" 0TSG 464 646 1558 446 a - random samples (full length inspection) b - lane / wedge inspection above 14th tube support plate (TSP) c - periphery / drilled holes above 13th TSP d - outermost periphery above 15th TSP

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2. Total number of tubes plugged / pulled:

"A" 0TSG 27 plugged /2 pulled "B" OTSG 7 plugged /1 pulled

3. Locations of' indications:

"A" 0TSG "B" 0TSG Row / Tube  % Thru Wpil OD/ID Row / Tube  % Thru Wall OD/ID 36/6 33 OD 75/11 32 OD 72/2 27 OD 75/22 22 OD 75/21 29 OD 75/29 22 OD 78/51 32 OD 75/14 22 OD 24/95 34 OD 77/11 22 OD 26/99 27 OD 77/20 26 OD 2/18 22 OD 75/57 33 OD 77/60 31 00 89/1 29 OD-

4. Location of plugged / pulled tubes (* indicates pulled tube)

OTSG Row / Tube  % Thru Wall OD/ID Stabilized (yes/no)

A 77/23* 40 0D No A 80/9

  • 23 OD Yes A 33/5 58 OD Yes A 46/7 56 00 Yes A 49/5 60 OD Yes A 101/10 36 OD No A 146/28 90 OD Yes A 65/2 91 OD Yes A 75/12 39 OD Yes A 75/18 34 OD Yes A 12/65 35 OD. Yes A 2/23 68 OD Yes A 3/22 36 OD Yes A 28/2 67 OD Yes A 29/3 76 OD Yes A 32/4 78 OD Yes A 45/1 81 OD Yes A 45/2 37 OD Yes A 46/1 54 OD Yes A 50/121 74 OD Yes A 50/122 93 OD Yes A 59/3 46 OD Yes A 119/108 69 OD Yes A 120/106 78 00 Yes A 149/22 40 OD Yes

)

m 0TSG Row / Tube  % Thru Wall 0D/ID Stabilized (yes/no)

A 83/138 Tubes plugged OD Yes A 88/126 because of OD Yes A 94/129 proximity to 0D Yes A 105/1 AFW HDR OD Yes B 77/4 99 OD Yes B 22/89 44 OD Yes B 115 1 34 OD Yes B 122/1 38 OD Yes B 124/1 37 OD Yes B 133/82 63 OD Yes B 136/76 40 0D Yes B 77/6 23 OD Yes

5. An inspection of the special interest OTSG peripheral tubes was performed.

Four tubes (see Item No. 4) were plugged because of their proximity to the auxiliary feedwater header.

6. An inspection of the secured internal header attachment welds and external header thermal sleeves was performed (SP 210.068). No unacceptable dis-crepancies were found.

REFUELING INFORMATION REQUEST

1. Name of Facility Rancho Seco Unit 1
2. Scheduled date for next refueling shutdown: Jan 1. 1987
3. Scheduled date for restart following refueling: May 1. 1987
4. Technical Specification change or other license amendment required:

a) Change to Rod Index vs Power Level Curve (TS 3.5.2) b) Change to Core Imbalance vs Power Level Curve (TS 3.5.2) c) Tilt Limits (TS 3.5.2)

5. Scheduled date(s) for submitting proposed licensing action: Aug 1. 1986

, 6. Important licensing considerations associated with refueling: N/A

7. Number of fuel assemblies:

a) In the core: 177 b) In the Spent Fuel Pool: 316

8. Present licensed spent fuel capacity: 1080
9. Projected date of the last refueling that can be discharged to the Spent Fuel Pool: December 3. 2001

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