NL-88-975, Monthly Operating Rept for Aug 1988 for Rancho Seco Unit 1

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Monthly Operating Rept for Aug 1988 for Rancho Seco Unit 1
ML20154F795
Person / Time
Site: Rancho Seco
Issue date: 08/31/1988
From: Crunk S
SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NL-88-975, NUDOCS 8809200134
Download: ML20154F795 (8)
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Text

{{#Wiki_filter:' AUGUST 1988 SU MARY OF PLANT OPERATIONS Rancho Seco reached 80% power at 0308 hours on August 1, 1988. At 1258 hours on August 5, the "A" Main Feedwater Pump was tripped in accordance with Special Test Procedure STP.1023. "Loss of Single Main Feed Pump Test" which initiated an Integrated Control System runback of the reactor to 62% st 1308 hours. On August 6, reactor power was incteased to 80% at 0018 hours; at 0045 hours the reactor was manually tripped in accordance with STP.1082, "Reactor Trip Test." The reactor was brought critical at 1202 hours on August 13. The plant was brought on line at 0358 hours on August 15 and reached 80% power at 2325 hours on August 15. Power reduction to the 60% level began at 1700 hours on August 25 in order to perform maintenance on the "B" Main Feedwater Pump. Power was returned to the 80% level at 2359 hours on August 25 and remained there through month's end. PERSONNEL CHANGES REQUIRING REPORT There was one management change in August 1988 which requires reporting pursuant to Technical Specification Figure 6.2-2. Hr. Charles Aycock is acting Manager, Nuclear Engineering. Mr. Aycock, acting Manager, Nuclear Engineering, has over 25 years of utility engineering and construction experience. He has been responsible for several construction projects including engineering support, scheduling, budget, safety, quality, and compliance with regulatory guidelines. Mr. Aycock was assigned to the Institute of Nuclear Power Opera' ions for about a year, during which he conducted site evaluations as part of the Construction Project Evaluation Program for nuclear power construction. He has a 8.S. in Electrical Engineering from North Carolina State University and has worked for Duke Power Company since receiving his degree.

SUMMARY

OF CHANGES IN ACCORDANCE WITH 10 CFR 50.59 The plant staff accepted documentation packages in August 1988 for the facility changes and interim procedure change described below which required detailed safety analyses. These changes were reviewed in accordance with the Technical Specifications by the Plant Review Committee (PRC) and the Management Safety Review Committee (HSRC). There were no documentation packages completed for procedure changes, tests or experiments during August 1988.

1. ECN A-3749 changed wiring to allow local reset of relay lockouts of the 3A, 3B, 3C1, 3D1, 3D2 and 3E buses. Hiring changes do not affect normal operation of the bus. These changes do not cause a change in the failure mode of the buses.

These changes did not increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the FSAR or create the possibility for an accident or malfunction of a different type than any evaluated previously in the FSAR or reduce the margin of safety as defined in the basis for any Technical Specification. These changes do not involve an unrevitwed safety question. (Log No. 284) l 

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9809200134 0s0331 PDR ADOCK 05000312 t l R ppe gg J j

l l SUMARY OF CHANGES IN ACCORDANCE HITH 10 CFR 50.59 (Continued)

2. Procedure Interim Chance Notice PICN-01 to Procedure A.51, Revision 36 was accepted to leave valve HV-20578 in the open position during the l rework effort on its sheared gear roll pin and to close valve FV-20528. '

Hith the valves in those positions, it has been determined that the Auxiliary Feedwater (AFH) and Emergency Feedwater Initiation and Control (EFIC) Systems are operable and that the margin of safety as defined in the Technical Specification bases is not reduced. MAJOR SAFETY-RELATED MAINTENANCE, TESTS AND N00IFICATIONS NOT REQUIRING DETAILED SAFETY ANALYSES

1. The test of the "A" Main Feedwater Pump was successfully completed at 1257 hours, August 5, prior to the planned reactor trip. The test of the EFIC System was successfully completed following the reactor trip. The 100 hour capability test run was completed at 2300 hours on August 21.

An Emergency Preparedness rehearsal drill was held on August 31.

2. Maintenance was performed on the "A" Bruce-GH diesel generator, "B" Bruce-GH diesel generator, "A" TDI diesel generator, "B" Decay Heat Pump and the Auxiliary Boiler. Outage work completed in the Reactor Building included the Furmanite injections on the "A" and "C" Reactor Coolant Pumps and minor valve leak repairs. Other work included repair of the leak on the "B" Steam Generator Hanway, installation of a camera to monitor the "C" Reactor Coolant Pump, and repacking of an Auxiliary Feedwater pump.
3. ECN R-0151, Revision 0, replaced four Demineralized Hater System air operated valves with new manually operated valves to correct a leakage problem in the system.
4. ECN R-2719, Revision 1, modified security barriers for plant buildings and structures in response to a NRC review of Vital Area Barriers.
5. ECN R-2982, Revision 0, replaced indl o ting temperature controllers in the Lube Oil System.
6. ECN R-3230, Revision 0, replaced four open head fire water spray nozzles on the AFH pump area Deluge System (Zone 110) which were positioned to -

spray directly upon the AFH pump motor housings with closed head fusible element spray nozzles. Hater spray shields on the cooling air inlets were providev with removable covers for the filter access openings.

7. ECN R-3175, Revision 0, replaced inoperable heat tracing heater HTR-0902. The replaced heater, a Chemelex 4ATV with a 4 watts per foot rating, is no longer manufactured so a Chemelex 5BTV with a 5 watts per foot rating was used.
8. ECN R-3164, Revision 1, changed wiring in Motor Control Center cubicles 2E211 and 2E212 to allow pump P-976A to start if pump P-976B is overloaded and vice versa.

f J

MAJOR SAFETY-RELATED MAINTENANCE TESTS AND MODIFICATIONS NOT REQUIRING DETAILED SAFETY ANALYSES (Continued)

9. ECN R-3156, Rev'.. ion 0, removed the exhaust shroud on the G-100A TDI Diesel, capped the supply and return headers, added insulation to the exhaust pipes to reduce the heat load to the environment, added four new supports to the jacket water return header, replaced the 4-inch flex hose from the jacket water return header with a 6-inch Dresser coupling, modified a pipe support and rerouted a line to match the configuration on the G-1008 Diesel.
10. ECN A-5780, Revision 0, added two Black Box model 596 Error Controllers to the existing 9600 BPS modem link between the IDADS Plant Computer System and the Emergency Offsite Facility HIDAS terminal to improve communications reliability between them.
11. ECN R-3892, Revision 1, modified the domestic water piping system into a loop through the site in order to provide an adequate supply of water to the site.
12. ECN R-2982. Revision 0, replaced the United Electric Indicating Temperature Controller type 1202 model 6BS in the Lube Oil System with a type 802 dual switch model 6BS.
13. DCP R-88-0012A provided a local alarm to indicate a high differential pressure drop across the control oil filters for the Lovejoy Main Feedwater Turbine Control System and local differential pressure indicators for each filter canister at the Turbine Control consoles.
14. An interim release was given for the heat trace on radiation monitor R15100 skid sample lines, and associated wiring, heater and temperature controller.
15. To ensure that the plant continues to operate smoothly in the fully automatic mode following the loss of a main feedwater pump, the ICS was reset to run the power level back to 657.. An interim release was given
after the work and testing were complete but prior to the closure of the i work request.

I REFUELING INFORMATION REQUEST

1. Name of Facility Rancho Seco Unit 1
2. Scheduled date for next refueling shutdown: July 1. 1989
3. Scheduled date for restart following refueling: August 29. 1989
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) l 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: j 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 I

[

1 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-312 UNIT Rancho Seco Unit 1 DATE 8/31/88 COMPLETED BY S. L. Crunk TELEPHONE (916) 452-3211 MONTH August 1988 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY P0HER LEVEL (MHe-Net) (MHe-Net) 1 694 ___ 17 715 2 708 18 715 3 709 19 715 4 701 20 716 5 616 21 716 6 632 22 719 7 0 23 _ 717 8 0 24 718 9 0 25 661 10 0 26 699 11 0 27 715 12 0 28 711 13 0 29 . 707 14 359 30 _ 706 15 539 31 _ 710 16 709 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.

De OPERATING DATA REPORT DOCKET NO. 50-312 DATE ._ 8/31/88 COMPLETED BY S. L. Crunk TELEPll0NE (916) 452-3211 OPERATING STATUS

1. Unit Name: Rancho Seco Unit 1 Notes:
2. Reporting Period: Auaust 1988
3. Licensed Thermal Power (MHt): 2.772
  • Gross Electrical Energy
4. Nameplate Rating (Gross HHe): 91L_ Generated (HHH) for
5. Design Electrical Rating (Net HHe): 918 July 1788 should have
6. Maximum Dependable Capacity (Gross HHe): 917 t;een 42,505,116.
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. Powt.r Level to Which Restricted, If Any (Net HHv). N/A
10. Reasons For Restrictions, If Any: N/A ,

This Month Yr-to-Date Cumulative

11. Hours in Reporting Period 744 5.855 117.239
12. Number of Hours Reactor Has Critical 564.7 3.282.0 57.604.0_,_,
13. Reactor Reserve Shutdown Hours 0 0 10.300.2
14. Hours Generator On-Line 548.8 3.014.7 53.378.5
15. Unit Reserve Shutdown Hours _

0 0 1.21_0.2 _ 

!    16. Gross Thermal Energy Generated (HHH)           1.204.238            4.296.712            132.158.400
17. Gross Electrical Energy Generated (HHH) 400.132 1.382.051 _42.905.248a
18. Het Electrical Energy Generated (HHH) 368.024 1.193.899 39.425.925
19. Unit Service Factor 73.BL 51. 5% _ 45.5%
20. Unit Availability Factor 73.8%__ 51. 5L 46.6%--
21. Unit Capacity Factor (Using HDC Net) 56dL 23.4%- 38.5% _
22. 'Mit Capacity Factor (Using DER Net) 53.9%- 22.2%= 36.6%---
23. Unit Forced Outage Rate 0%- 41.6%- 43.4% --
. 24. Shutdowns Scheduled Over Next 6 Honths (Type, Date, and Duration of Each):
!          _ Hone                                                                              _ _ _ _
25. If Shut Down At End Of Report Period, Estimated Date of Startup: _ l_'T '
26. Units In Test Status (Prior to Commercial Operition): Forecast Achieved INITIAL CRITICALITY _ N/A N/A-INITIAL ELECTRICITY N/A N/A COHHERCIAL OPERATION N/A N/A l

r m s: ,. i DOCKETNO. 59-312 I UNIT SHUTDOW:4 #.D POWER REDUC 110NS UNIT NAME Rancha seen l DATE August 31, 1988 COMPLETED BY 3Ceve L. Crunk . REPORT MONTH August 1988 TELEPHONE (916) 452-3211 f 1 E E jg "h jY5 Licensee E*, Cause A Corrective i g% l .% D4:e -{ 3g 4 255c Event g? Eb 

                                                                                                                                                                                                                                                                          ^'      '"

Prevent Recurrence

  • yE E j;f3 Report 8 in U g

l 3 l 6 88-08-05 S 

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B 4 N/A N/A N/A In accordance with STP-1023, MW pumi: tripped which ir itiated an ICS g runback of reactor. 7 88-08-06 S 195.2 B 2 N/A N/A N/' Reactor tripped as part of the power ascensica testing program. 8 88-08-25 S 7.0 B 4 N/A N/A N/A Power reduced to perform maintenance on "B" MW pump. 1 [ ._ 3 4 s 2 i l~. aJ Reasors: Method: Exhibit C. Instructions i I-Manual for Preparazion of Data l  % S.hed deJ A-Equaprnent Failure (Explain) 2-Manual Scram. Entry Sheets for Licensee S-Maintenance of Test Event Report (LER) File iNUREG-C-Relucting .3 Automatic Scraen. D-Regulatory Resarictsua 4Other(Explaan) 01611 EOperatur Training & IJcense Exandnasion F-Adtrunistrative 5 G4;peras onal Errus (Captain) Exhibis ! - Same S.mru l llother IEmplaan) e el n i l l l 1 --

hSMUDSACRAMENTO MUNICIPAL UTIUTY DISTRICT P P. O. Box 15830, Sacramento CA 95852 1830,(916) 452-3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CAllFORNIA NL 88-975 SEP 151998

d. 5. Nuclear Regulatory Commission Attnt Document Control' Desk Hashington, DC 20555 Docket No. 50-312 Rancho Seco Nuclear Generat hg Station License No. OPR-54 00ERATING PLANT STATUS REPORT Attention: George Knighton Enclosed is the August 1988 Honthly Operating Plant Status Report for the Ran:ho Seco Nut. lear Generating Station. The District submits this report pursuant to Technical Specification 6.9.3.

Sincerely, 

                                   ~

te . Crunk Manager Nuclear Licensing Enci (5) cc: J. B. Martin, Nf:0, Walnut Creek INPO R. Twilley, Jr. I ZEL4 i,g RANCHO SECO NUCLEAR CE '; R/aTING STATION D 1< % 'wm Cities Roa1, :letald. CA 95638 9799;(209) 333-2935 l 

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