ML20034C879
| ML20034C879 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 04/30/1990 |
| From: | Delezenski J, Mueller M SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9005180045 | |
| Download: ML20034C879 (8) | |
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V SACRAMENTO MUNICIPAL UTIUTY DISTRICT C 0201 S Street. P.O. Box 16830. Secremento CA P68521830. (916) 452 3211 j
AN ELECTRIC SYSTEM SERVING THE HEART OF CAUFOPNIA i
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May 15, 1990 U. S. Nuclear Regulatory Commission Attn:
Document Control Desk Hashington, DC 20555 Docket No. 50-312 Rancho Seco Nuclear Generating Station License No. DPR-54 OPERATING PLANT STATUS REPORT Attention:
John Larkins Enclosed is the April 1990 Monthly Operating Plant Status Report for the Rancho Seco Nuclear Generating Station.
The District submits this report pursuant to Technical Specification 6.9.3.
Sincerely,
.- fh.*W r
lezenski Supervisor, Nuclear Licensing Enc 1 (5) cc w/ enc 1:
J. B. Martin, NRC, Halnut Creek A. D'Angelo, NRC, Rancho Seco R. Twilley, Jr.
9005180045 9nn43o
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32 RANCHO SECO NUCLEAR GENERATING STATION O 1444o Twin Cities Road, Herald, CA 95638 9799;(2o9) 33 2935
AP3It 1990 SUMARY OF PLANT OPERATIONS The plant has been in a defueled condition since the last.of the fuel was removed and placed in the Spent Fuel Pool at approximately 1030 hours0.0119 days <br />0.286 hours <br />0.0017 weeks <br />3.91915e-4 months <br /> on-Friday, December 8, 1989.
SUMMARY
OF CHANGES IN ACCORDANCE NITH 10 CFR 50.59 The plant staff accepted documentation packages in April 1990 for the changes described below which required detailed safety analyses. These
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changes were reviewed in accordance with the Technical Specifications by the Plant Review Committee (PRC) and the Management Safety Review Committee (HSRC).
1.
Plant Operations Procedure C.38, Revision 3.
Loss Of Spent Fuel System, was revised to include additional makeup methods in the event that spent fuel pool cooling is lost.
Several of the makeup methods do not provide boron to the pool.
However, the USAR states that 1800 ppm boron is not required for the safe storage of spent fuel assemblies. Also, this change does not affect any equipment and is bound by previously analyzed accidents.
Therefore, this change to C 38 does not increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety as previously evaluated in the USAR, nor is the i
possibility for ar accident or malfunction of a different type than any evaluated previously in the USAR created.
Revision 3 to C.38 does not involve an Unreviewed Safety Question.
2.
Rancho Seco Administrative Procedure RSAP-0260 Revision 0, Commitment Tracking System, identifies responsibilities and instructions for the performance of the commitment tracking process, including regulatory commitments, Long Range Scope List (LRSL) l items, Corrective Action Requests (CARS), and commitments to implement remedial corrective action and action to prevent recurrence for Deviation from Quality (DQ).
This is an administrative change for commitment control.
Thus, this procedure l
does not increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety as i
previously evaluated in the USAR, nor is the possibility for an accident or malfunction of a different type than any evaluated previously in the USAR created.
RSAP-0260 does not involve an Unreviewed Safety Question.
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SUMMARY
OF CHANGES IN ACCORDANCE WITH 10 CFR 50.59 (Continued) 1 3.
System Layup Package L-0064 for the Emergency Feedwater Initiation and Control System was completed during April.
This layup modification lifted field leads for affected valves at the EFIC "A" and "B" cabinets to ensure that valves modulated by EFIC level and pressure controllers do not stroke whtn EFIC is annually one'rgized.
EFIC is not required for the current defueled node.
This layup modification will be reversed prior to leaving the defueled mode; Since EFIC is not required in the current defueled mode, this layup.
modification does not increase the probability of occurrence or the i
l consequences of an accident or malfunction of equipment important to safety as previously evaluated in the USAR, nor is the possibility for an accident or malfunction of a different type than any evaluated previously in the USAR created.
This modification does not involve an Unreviewed Safety Question.
4.
Special Test Procedure STP.1317. Revision 0, Burn Building Test, was l
performed to test and cure the "Padgenite" boards installed in the Burn Building, and to ensure that installation of panels will protect the bu'lding structure during training exercises.
The Burn r'
Building was tested at 300-400*F, 600-700*F and 900-1000*F.
Test deficiencies were documented in PDQ 90-121. Disposition of PDQ 90-121 was to accept the test results since the purpose of the test I
was to " season" the building by gradually increasing the temperatures. This was accomplished during the low, medium and high temperature burns.
This test did not affect or impact any power block equipment, any.
safety related equipment, or any technical specification equipment.
The Burn Building was found suitable for use in fire brigade training.
Therefore, accepting this test does not increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety as previously evaluat6d in the USAR, nor is the possibility for an accident or malfunction of a different type than any evaluated previously in the USAR created.
This test did not involve an Unreviewed Safety Question.
MAJOR SAFETY-RELATEJ MAINTENANCE, TESTS AND MODIFICATIONS NOT REQUIRING DETAILED SAFETY ANALYSES 1.
Spent Fuel Pool instrumentation modifications were completed in April.
Reactor coolant and system layup work is in progress and solidification pad modification continues.
Routine maintenance and surveillance work continues on a daily basis.
2.
DCP R90-0007 provided handrails and a platform to access the Containment Building roof and provided a platform to service the stack radiation monitors, i ' i I
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NAJOR SAFETY-RELATED MAINTENANCE. TESTS AND MODIFICATIONS NOT REQUIRING DETAILED SAFETY ANALYSES (Continued) 3.-
ECN R-3053 added permanent oil skimmers in the Condenser Pit Sump,
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and RHUTS "A" and "B", and a portable oil skimmer in the Condensate Polisher Sump to reduce the volume of' oil in those locations.-
l 4.
Special Test Procedure STP.1162. Revision 0, Spent Fuel Pool Liner Leakage Identification Test, was performed in an attempt to determine the location of the leakage in the Spent Fuel Pool (SFP) liner using helium detection equipment.
It was determined that-the test was inconclusive in providing results as to the location of possible liner leaks. Additional tests are to be performed.
5.
Special Test Procedure STP.1233 Revision 3, Oil Skimmer System Functional Test, demonstrated the operability of the oil skimmers installed in the Condenser Pit Sump "A" Regenerate Hold-up Tank, and "B" Regenerate Hold-up Tank under ECN R-3053.
6.
Special Test Procedure STP.1315, Revision 0, Spent Fuel Pool Level Switch Functional Test, was a functional test of the level instruments LSL-27207, LSLL-27208 and LSH-27206 to verify operability during increasing and decreasing Spent Fuel Pool level.
Water was transferred from the Spent Fuel: Pool to the BHST prior to the completion of all initial conditions for the test.
This was documented in PDQ 90-0072 and the root cause of the event was determined. All acceptance criteria were met with the exception of LSL-27207, which was found-to be out of tolerance by -1 inch. This exception was corrected per PDQ 90-0073.
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REFUELING INFORMATION REQUEST 1.
Naine of Facility Rancho Seco 2.
Scheduled date for next refueling shutdown:
3.
Scheduled'date for restart following refueling:
~4.
Technical Specification change or other license amendment. required:
5.
Scheduled date(s) for submitting proposed licensing action:
6..
Important licensing considerations associated with refueling:
7.
Number of fuel assemblies:
a)' In the core:
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b) In the Spent Fuel Pool:
493 8.
Present licensed spent fuel capacity:
1080 i
9.
Projected date of the last refueling that can be discharged to the Spent fuel Pool:
_All fuel removed from the core as of December 8. 1989.*
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- Plant shut down June 7, 1989 following negative outcome of public vote regarding continued operation of Rancho Seco by SMUD.
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1 OPERATING DATA REPORT DOCKET NO.
50-312 DATE 4/30/90 COMPLETED BY Marla Hueller i
TELEPHONE (916) 452-3211
. OPERATING STATUS 1.
Unit Name:
Rancho _Seco Notes:
2.
Reporting Period:
Antil 1990 3.
Licensed Thermal Power (M4t):
2.772 4.
Nameplate Rating (Gross MHe):
963 i
5.
Design Electrical Rating (Net HHe):
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, i
Give Reasons:
N/A
'9.
Power Level to Which Restricted, If Any (Not HHe):
N/A
- 10. Reasons For Restrictions. If Any:
N/A This Month Yr-to-Date Cumulative
- 11. Hours in Reporting Period 719 2.879 131.807
- 12. Number of Hours Reactor Has Critical 0
0
,_fiL221. 5 13.
Reactor Reserve Shutdown Hours O
- 14. Hours Generator On-Line O __
0 12.736.6 O
57.811.1
- 15. Unit Reserve Shutdown Hours 0
0 3.647.5
- 16. Gross Thermal Energy Generated (MHH) 0 0
141.951.953
- 17. Gross Electrical Energy Generated (MHH) 0 0
.46.223.924 i
18.
Net Electrical Energy Generated (MHH)
-3.523
-14.762 42.443.497
- 19. Unit Service Factor 0%
0%
43.9%
- 20. Unit Availability Factor 0%
0%
46.6%
- 21. Unit Capacity Factor (Using MDC Net) 0%
0%
36/9%
- 22. Unit Capacity Factor-(Using DER Net) 0%
0%
35.1%
- 23. Unit Forced Outage Rate 0%
0%
42.7%
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
- 25. If Shut Down At End Of Report Period, Estimated Date of Startup:
- 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 F
- Plant shut down June 7 following negative outcome of public vote regarding continued operation of Rancho Seco by SMUD.
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l AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-312 UNIT Rancho Seco DATE 4/30/90 COMPLETED BY Marla Mueller TELEPHONE.
(916) 452-3211 MONTH Anril 1990 DAY AVERAGE DAILY P0HER LEVEL DAY AVERAGE DAILY POWER LEVEL (HHe-Net)
(MHe-Net) 1 0
17 0
2 0
18 0
3 0
19 0
4 0
20.
0 5
0 21 0
6 0
22 0
7 0
23 0
8 0
24 0
9 0
25 0
10 0
26 0
11 0
27 0
12 0
28 0
13 0
29 0
14 0
30 0
15 0
31 16 0
INSTRUCTIONS On this format, list the average daily unit power level in HHe-Net for each day in the reporting month, Compute to the nearest whole megawatt.
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UNIT SHtTTDOWIts AND POWDt REDUCTIONS DOCKET ND.
50-312 LMIT leUE _ Ranche Seco DATE 4-30-90 REPORT IONTH April 1990 C0prLETED BY M. Itse11er TELEPHONE (916) 452-3211 4
Method of Shutting Licensee Cause 4. Corrective Duration Down Event System Component Action to No.
Date Type (Hours)
Reason 2 Reactor 3 Report #
Code Code S Prevent Recurrence l
4 1
06-07-89 5
719 F
1 N/A 78/A N/A Plant shut down June 7,1989 following negative outcome of public vote regarding continued operation of Rancho Seco by SPtJD.
1 2
3 4
F Forced Reason:
Method:
Exhibit G - Instructions S Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data Entry B-Maintenance or Test 2-Manual Scram Sheets for Licensee Event C-Refueling 3-Automatic Scram Report (LER) File (NUREG-0161)
D-Regulatory Restriction 4-Other (Explain)
E-Operator Training 8. License Examination F-Administrative S
G-Operational Error (Explain)
Exhibit 1 - Same Source H-Other (Explain)
A C
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