ML20204H731
| ML20204H731 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 02/28/1987 |
| From: | Colombo R SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| RWC-87-213, NUDOCS 8703270082 | |
| Download: ML20204H731 (9) | |
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FEBRUARY 1987
SUMMARY
OF PLANT OPERATIONS The plant has been in cold shutdown for the entire month of February 1987.
The initial shutdown was due to the December 26, i
1985, loss of ICS power event.
PERSONNEL CHANGES REQUIRING REPORT Pursuant to Technical Specification Figure 6.2-2, there was one change in personnel which requires reporting.
j Nuclear Operations Manager -- William Kemper Mr. Kamper has a bachelor of science in electrical engineering, and a Navy nuclear background.
His experience was obtained primarily at the Crystal River Unit 3 B&W nuclear plant where he worked from 1973 until 1986.
His duties at Crystal River included simulator project manager, operations technical advisor, nuclear licensing specialist, and nuclear operations training manager.
His experience includes two and a half years in the l
Control Room as shift supervisor, over one-year as assistant shift supervisor and four years as an assistant nuclear operator.
SUMMARY
OF CHANGES IN ACCORDANCE WITH 10 CFR PART 50.59 The plant staff accepted documentation packages for the following facility changes in February 1987.
These change were approved i
and reviewed by the Plant Review Committee (PRC) and the Management Safety Review Committee (MSRC).
There were no l
documentation packages completed for tests, procedura changes, or experiments during February 1987.
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1.
ECN R-0498, Revision 0 was installed to implement the long term resolution of NCRs S-5343, Revision 0 and S-5340, Revision 2.
The ECN redesigned and replaced the drain lines on the Decay Heat Removal (DHR) pump casing to restore pressure boundary integrity.
The design l
change installed three separate drains, each with its own isolation valve: one on the pump discharge volute, and one on each of the pump suction housings.
This modification was made to both pumps, P-261A and P-261B.
Elimination of the unwanted recirculation path does not affect the minimum flow requirements for the i
pumps because the system is designed to provide minimum l
recirculation flow.
The increase in pump output (flow I
and discharge head) is not significant, and does not l
affect the DHR system performance or design basis as i
described in USAR Section 9.5.
Inspection of j
Technical Specifications 3.1.1, 3.3, 3.8, and 4.5 t
indicate that this change does not affect the l
Technical Specifications.
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'This change does restore system. operability, and neither enhances nor reduces.the DNR system capability to perform its intended function.
No new failure modes are introduced.
Therefore, this change does not involve an unreviewed safety question. (Log No. 865, Revision 0).
2.
ECN R-0636 specifies the reduction in size of cable lilB10A in panel H4PRlB of the Reactor Protection System from #2AWG to #8AWG.
The disposition of NCR S-5395, Item one, calls for reworking of existing lugs, and installation of reduced connections which utilize the correct size and type of AMP lugs.
The ECN to institute these changes states:
o Some existing lugs had been physically modified to fit onto terminals.
o Class 1 Raychem splice kit per drawing E-605, Sheet 7, Revision 1, Detail 1 is to be used to replace #2AWG cable with #8AWG cable.
o Less than one foot of #8AWG cable will be used within the panel immediately adjacent to the terminal block.
o Calculation Z-ICS-E0306 justifies the adequacy of #8AWG cable to handle the available short circuit current.
o Resulting increases in voltage drop from the use of less than one foot of #8AWG cable is an insignificant 0.04 volts.
o No new failure mode is introduced by this modification.
o Use of qualified Class 1 splice to accommodate correctly sized lugs will eliminate the possibility of circuit failure due to high contact resistance from the cut lugs.
The modification to RPS panel H4PR1B will not inhibit the necessary current flow, and will not prevent the RPS from functioning properly.
The change will decrease the possibility of RPS current failure and thus enhance nuclear safety. (Log No. 778, Revision 0).
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ECN R-0644 specifies the reduction in size of cable 111010A in panel H4PRIC of the Reactor Protection System from #2AWG to #8AWG.
The disposition of NCR S-5403, Item two, calls for.
reworking of existing lugs, and installation of reduced connections which utilize the correct size and type of AMP lugs.
The ECN to institute these changes states:
o Some existing lugs had been physically modified to fit onto terminals.
o Class 1 Raychem splice kit per drawing E-605, Sheet 7, Revision 1, Detail 1 is to be used to replace #2AWG cable with #8AWG cable, o Less than one foot of #8AWG cable will be used within
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the panel immediately adjacent to the terminal block.
o Calculation Z-ICS-E0306 justifies the adequacy of.#8AWG cable to handle the available short circuit current.
o Resulting increases in voltage drop from the use of less than one foot of #8AWG cable is an insignificant 0.04 volts.
o No new failure mode is introduced by this modification.
o Use of qualified Class 1 splice to accommodate correctly sized lugs will eliminate the possibility of circuit failure due to high contact resistance from the cut lugs.
The modification to RPS panel H4PR1C will not inhibit the necessary current flow, and will not prevent the RPS from functioning properly.
The change will decrease the possibility of RPS current failure and thus enhance nuclear safety. (Log No. 780, Revision 0).
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_4-4.
ECN R-0663_ specifies lthe reduction in size of cable i
111D10A.in panel H4PRlD of the' Reactor Protection System from #2AWG to #8AWG.
The disposition of NCR S-5408, Revision 1, Item ig, calls for reworking of existing lugs, and installation of reduced connections which utilize the correct size and type of AMP lugs.
The ECN to
,7 institute these changes states-o Some existing luga had been physically modified-to fit onto terminals.
i, o Class 1~ Raychemisplice kit per drawing E-605,. Sheet 7, Revision 1, Detail 1 is to be used to replace ?#2AWG cable with #8AWG cable.
t o Less than one foot of #8AWG cable will' be used within L
the panel immediately adjacent to the terminal block.
o Calculation Z-ICS-E0306. justifies the adequacy of #8AWG
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cable to handle the available short circuit curren't.
o Resulting increases'in voltage drop from'the use/of less than one foot of #8AWG cable is an insignificant 0.04 volts.
o No new failure mode is introduced by this modification.
o Use of -qualified Class l' splice to accommodate correctly sized lugs will eliminate the, possibility of circuit failure, duo,to high contact resistance from the cut lugs.
2, The modification to RPS panel H4PRlD will not inhibit the
.necessary current flow, 'and will not prevent the RPS from functioning properly.
The change will decrease the possibility of RPS current failure and thus enhance nuclear safety. (Log No. 782, Revision 0).
MAJOR ITEMS OF. SAFETY-RELATED' MAINTENANCE I
1.
The code relief valve on the reactor coolant system was installed in preparation for the decay heat outage 9;,
2.
Emergency feedwater initiation dnd control work on'the atmospheric dump valves and the spin feedwater valves was completed.
3.
The cable raceway tracking system inspection prog am i's underway.
Over'200 circuits are in the sample to be (
checked, and checks on 140 were completed.
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- REFUELING INFORMATION REQUEST 1.
_Namegaf Facility Rancho Seco Unit 1 2.
Sch duled'date for next refueling shutdown:
September '15. 1988
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Schediled date for restart following refueling:
January 15. 1989 3.
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Technical Specific 6t-lon change or other license amendment required:
(
a)
Chapge to Rod Irdex 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:
March 15,1988 6.
Important licensing considerations associated with refueling:
N/A 7.
Numh,iroffue1asssmblies:
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a)-
n the core:
177 b)
In the Spent Fiiel Pool:
316 8.
Prn q t licensed'sr;ent fuel capacity:
1080 Prc' orted data of the last refueling that can be discharged to j
9.
the SDent Fuel Pool:
December 3, 2001
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4', YW AVERAGE DAILY UNIT POWER LEVEL:
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DOCKET NO.
50-312 UNIT Rancho Seco Unit'1 L
DATE 2/28/87 s
COMPLETED BY R. Colombo r.
TELEPHONE (916) 452-3211 MONTH February 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEV'L E
(We-Net)
(MWe-Net)
/
(
1 0
17 0
'tt w
2 0
18 0
[
u..,
3 0
19 0
4 0
20 0
S 0
21 0
6 0
22 0
7 0
23 0
8 0
24 0
9 0
25 0
10 0
26 0
11 O
27 0
12 0
28 0
. g, --,
13 0
29 a
14 0
30 15 0
31 16 0
INSTRUCTIONS-On this fo'ntat, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.
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OPERATING DATA REPORT DOCKET NO.
50-312 DATE 2/28/87 COMPLETED BY R. Colombo TELEPHONE (916) 452-3211 OPERATING STATUS 1.
Unit Name:
Rancho Seco Unit 1 Notes 2.
Reporting Period:
February 1987 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 Octur 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):
0
- 10. Reasons For Restrictions, If Any:
NRC letter dated 12/26/85 This Month Yr-to-Date Cumulative
- 11. Hours in Reporting Period 672 1.416 104.041
- 12. Number of Hours Reactor Was Critical 0
0 54.322
- 13. Reactor Reserve Shutdown Hours 0
0 10.300.2
- 14. Hours Generator On-Line 0
0 50.363.8
- 15. Unit Reserve Shutdown Hours 0
0 1.210.2
- 16. ~ Gross Thermal Energy Generated (MWH) 0 0
127.861.688 17.
Gross Electrical Energy Generated (MWH) 0 0
41.523.187
- 18. Net Electrical Energy Generated (MWH)
-3.182
-6.842 38.281.943
- 19. Unit Service Factor 0.0%
0.0%
48.4%
- 20. Unit Availability Factor 0.0%
0.0%
49.6%
. 21. Unit Capacity Factor (Using MDC Net) 0.0%
0.0%
42.1%
- 22. Unit Capacity Factor (Using DER Net) 0.0%
0.0%
40.1%
- 23. Unit Forced Outage Rate 100.0%
100.0%
38.4%
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- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
N/A 25.
If Shut Down At End Of Report Period, Estimated Date of Startup:
Indefinite
- 26. Units In Test Status (Prior to Commercial Operation):
Forecast Achieved INITIAL CRITICALITY N/A N/A i
INITIAL ELECTRICITY N/A N/A COMMERCIAL OPERATION N/A N/A 1
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50-312 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
UNIT NAME Rancho Seco Unit 1 DATE 7/28/87 COMPLETED BY Ron W. Colombo REPORT MONTH February 1987 TELEPHONE (916) 452-3211 E
1E jg 3
j.E h Licensee p,
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Cause & Corrective Date g
3g i;
.3 s s Event gi pO Action to H
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jgg Report a mu Prevent Recurrence g
1 85/12/26 F
672 D
3 85-25 CB Instru Rx trip following loss of ICS power.
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4 F-Forced Reason:
Method:
Exhibit G - Instructions S Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram.
Entry Sheets for Licensee C-Refueling 3-Automatic Scram.
Event Report (LER) File (NUREG-D-Regulatory Restriction 4-Other (Explain) 0161)
E-Operator Training & License Examination F-Administrative 5
G-Operational Error (Explain)
Exhibit I-Same Source N 19/77)
Il-Other (Explain) 9,'
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$SMUD SACRAMENTO MUNICIPAL UTILITY DISTRICT C P. O. Box 15830, Sacrament h' 95852-1830, (916) 452-3211 AN ELECTRIC SYSTEM SERVING'THE HEART OF CALIFORNIA j
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RWC 87-213
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,2 March 12, 1987 J B MARTIN REGIONAL ADMINISTRATOR REGION V OFFICE OF INSPECTION AND ENFORCEMENT U S NUCLEAR REGULATORY COMMISSION 1450 MARIA LANE, SUITE 210 WALNUT CREEK, CA 94596 OPERATING PLANT STATUS REPORT DOCKET NO. 50-312 Enclosed is the February 1987, Monthly Operating Plant Status Report for the Rancho Seco Nuclear Generating Station pursuant to Technical Specification 6.9.3.
R. W.
COLOMBO REGULATORY COMPLIANCE SUPERINTENDENT Encl (5) cc:
I&E Wash (12)
MIPC (2)
INPO l
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JL.2 l RANCHO SECO NUCLEAR GENERATING STATION G 14440 Twin Cities Road, Herald, CA 95638-9799;(209) 333 2935