ML20195B618
| ML20195B618 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 05/31/1988 |
| From: | Crunk S SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | |
| Shared Package | |
| ML20195B614 | List: |
| References | |
| NUDOCS 8806210466 | |
| Download: ML20195B618 (6) | |
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MAY 1988 SUMARY OF PLANT OPERATIONS Rancho Seco was at approximately 29% reactor power until the scheduled outage for routine maintenance and surveillance.
The turbine was tripped at 0925 hours0.0107 days <br />0.257 hours <br />0.00153 weeks <br />3.519625e-4 months <br /> on May 4, 1988, as scheduled.
The reactor tripped immediately (ahead of schedule) due to the lifting of the "A" Letdown Cooler relief valve.
The R eote Shutdown Test (STP.ll54) was successfully completed.
The reactor was brought critical at 2342 hours0.0271 days <br />0.651 hours <br />0.00387 weeks <br />8.91131e-4 months <br /> on May 11 and power increased to 15%.
The plant began producing electricity at 0919 hours0.0106 days <br />0.255 hours <br />0.00152 weeks <br />3.496795e-4 months <br /> on May 12. Reactor power was increased to the 40% power plateau on May 12 and remained there through the month.
PERSONNEL CHANGES REQUIRING REPORT There were no management changes in May 1988 which require reporting pursuant l
to Technical Specification Figure 6.2-2.
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SU MARY OF CHANGES IN ACCORDANCE HITH 10 CFR 50.59 The plant staff accepted a documentation package in May 1988 for the special test procedure described below which required a detailed safety analysis.
This procedure was reviewed in accordance with the Technical Specifications by the Plant Review Committee (PRC) and the Management Safety Review Committee (MSRC).
There were no documentation packages completed for facility changes or experiments during May 1988, 1.
Special Test Procedure STP.1041 is a test which strokes the electromatic operated relief valve (EMOV) and the EH0V block valve open and closed with nominal primary system pressure.
STP.1041 also tests operation of the pressurizer relief discharge acoustic monitors and thermocouples, and the pressurizer relief discharge annunciator.
This duplicates the actual operational condition under which the valves must operate.
This special test procedure did not introduce any new single-failure modes; it verified the operability of the EMOV as designed.
If both the EMOV and its block valve fail open, 5'P.1041 directs the operators to procedure E.03 "Loss of Subcooling."
The probability of occurrence or the.onsequences of an accident or malfuncticn of equipment important to safety previously evaluated in the safety analysis report was not increased because this test procedure verified the ;p,; tion of the EMOV and its block valves as described in the USAR.
The possibility for an accident or malfunction of a different type than any evaluated previously in the safety analysis report was not created since the test verified design basis operation of the EHOV and EHOV block valve. 880621046c., 880615 PDR ADOCK 05000312 R
SUMARY OF CHANGES IN ACCORDANCE HITH 10 CFR 50.59 (Continued)
The margin of safety as defined in the basis for any Technical Specification was not reduced by this procedure because the test verified operation of the EHOV as described in Technical Specification basis for Section 3.1.
Performance of STP.1041 did not involve an Unreviewed Safety Question.
(Log No. 1008)
MAJOR SAFETY-RELATED MAINTENANCE. TESTS AND MODIFICATIONS NOT REQUIRING DETAILED SAFETY ANALYSES 1.
Work in the Reactor Building during Hay included snubber inspections, leak repairs, and valve work on the Letdown System.
Planned maintenance and survelliance activities during the month included calibration of core flow tank level transmitters and seal injection and make-up valve weld repairs.
Repairs on the "B" Regenerant Holdup Tank liner and agitator motor were completed.
2.
ECN R-2956, Revision 0, modified turbocharger and jacketwater supports on the G100A TOI diesel to prevent failures similar to those experienced on the G100B TDI diesel.
3.
FC;i d-3150, Revision 1, installed additional supports on a G100A TDI diosel jecketwater line to reduce the vibration level of the line.
4.
ECN R-0138, Revision 0, replaced the overload heater in breaker 2E101 to accommodate the increase in current draw.
5.
ECN R-2990, Revision 1, added Nitrogen Purge System to the AFH turbine governor.
The nitrogen purge is intended to prevent the introduction of moisture and preclude the formation of corrosion products which may inhibit governor / turbine operation.
6.
ECN R-30ll, Revision 0, removed the Essential Control Room temperature auto-start circuits because spurious automatic starts were creating a nuisance for operators.
The Essential Control Room temperature start signal is now alarmed in IDADS.
The alarm has two alert levels, one at a high temperature of 80*F and a second at 85'F.
Manual operator action is now required to initiate the essential units on temperature only. Other automatic functions such as Toxic Chemical and Radiological starts are unchanged.
7.
EFIC Channel D OTSG "B" low range level transmitter has been given an interim release (ECN R-3101, Revision 0).
8.
An interim release was given to a TDI pressure indicator installed on the Backup Bottle Air System (ECN R-2983, Revision 1). _. __
REFUELING INFORMATION REQUEST 1.
,Name of Facility Rancho Seco Unit 1 7.
Scheduled date for next refueling shutdown:
March 1. 1989 3.
Scheduled date for restart following refueling:
June 27. 1989 4.
Technical Specitication 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:
January 15. 1989 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 l
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AVERAGE DAILY UNIT P0HER LEVEL DOCKET NO.
50-312 UNIT Rancho Seco Unit 1 DATE 5/31/88 COMPLETED BY S. L. Crunk TELEPHONE (916) 452-3211 MONTH May 1988 DAY AVERAGE DAILY P0HER LEVEL DAY AVERAGE DAILY POWER LEVEL (MHe-Net)
(MHe-Net) 1 235 17 322 2
231 18 317 3
234 19 314 4
163 20 310 5
0 21 307 6
0 22 308 7
0 23 311 8
0 24 312 9
0 25 314 10 0
26 312 11 0
27 310 1
12 205 28 313 13 278 29 316 14 310 30 321 15 309 31 318 16 319 INSTRUCTIONS On this format, list the average daily unit power level in MHe-Net for each day in the reporting month. Compute to the nearest whole megawatt.
OPERATING DATA REPORT DOCKET N0.
50-312 DATE 5/31/88 COMPLETED BY S. L. Crunk TELEPHONE (916) 452-3211 OPERATING STATUS 1.
Unit Name:
Rancho Seco Unit 1 Notes:
2.
Reporting Period:
May 1988 3.
Licensed Thermal Power (MHt):
2.772 4.
Nameplate Rating (Gross MWe):
963 5.
Design Electrical Rating (Net MHe):
918 6.
Maximum Dependable Capacity (Gross HHe):
917 7.
Maximum Dependable Capacity (Net HHe):
873 8.
If changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
N/A 9.
Power Level to Hhich Restricted, If Any (Net MHe):
N/A 10.
Reasons For Restrictions, If Any:
N/A This Month Yr-to-Date Cumulative
- 11. Hours in Reporting Period 744 3.647 115.031
- 12. Number of Hours Reactor Has Critical 561.7 1.253.3 55.575.3 13.
Peactor Reserve Shutdown Hours 0
0 10.300.2
- 14. Hours Getarator On-Line 552.1 1.001.9 51.365.7
- 15. Unit Reserve Shutdown Hours 0
0 1.210.2
- 16. Gross Thermal Energy Generated (MHH)
.__JRE 645 963.925
_128.825.613
- 17. Gross Electrical Energy Generated (MHH) 184.440 297.183 41.820.380
- 18. Net Electrical Energy Generated (MHH) 156.954 202.523 38.434.549
- 19. Unit Service Factor 74.2%
27.5%_
44.6%-
- 20. Unit Availability Factor 74.2% -
27.5%_
45.7%
- 21. Unit Capacity Factor (Using MDC Net) 24.2%__
6.4%-
38.3%
- 22. Unit Capacity Factor (Using DER Net) 23.0% -
6.0% -
36.4%___
- 23. Unit Forced Outage Rate 0%
68.1%
44.3%
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
As cart of the oower ascension testina orogram. a shutdown is scheduled for July 13-15.
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 COMMERCIAL OPERATION N/A N/A
DOCKET NO. 50-312 UNIT SHUTDOWNS AND FOWER REDUCTIONS ancho Seco UNITNAME pSY 3 3 -
DATE 1988 COMPLETED BY 5. L. Crunk May 1988 TELEPHONE i?_l6) 452-3211 REPORT MONTH e.
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Y3 Licensee Ev.
Cause & Conrectne No Dat e i
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88-05-04 5
191.9 8
3 N/A N/A N/A The turbine was tripped as part of the power ascension testing program.
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I 1..e ce d Reason:
Method:
Exhibit G - Instructions
% 5t hed ufed 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 (LE RI File INUREG-D-Regulatory Restriction 4-Other (Explain) 0161)
E-Operator Training & Ucense Examination F-Adnunist rative 5
G Operational Esror (Explaint Exhibii ! - Same S. urce 3
ro773 Il-Other ( E xplain) l 4
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