ML20210D289
| ML20210D289 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 02/28/1986 |
| From: | Colombo R SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| RWC-86-130, NUDOCS 8603260400 | |
| Download: ML20210D289 (7) | |
Text
r FEBRUARY 1986 SpHARYOFPLANTOPERATIONS-The plant has been in cold shutdown for the entire month of_ February.
Initial shutdown was due to the-December 26, 1985 Loss of ICS Event.
PERSONNEL CHANGES REQUIRING REPORT ~
Effective February 15, 1986, Mr. Bill Spencer was replaced by Mr. Thomas D.
Tucker as Operations Superintendent. Mr. Tucker started with the District in September 1971 as an auxiliary operator after having worked as an equip-ment operator for five years and pump casting operator for four years with previous employers. Mr. Tucker was promoted to Control Room Operator in November 1972. Mr. Tucker was promoted to Senior Control Room Operator in December.1973 and to Shift Supervisor in June 1976 Mr. Tucker has most re-cently served as Outage Coordinator until his recent promotion to Operations Superintendent.
SUMMARY
OF CHANGES IN ACCORDANCE WITH 10 CFR 50.59(b)
The documentation for the following_ facility and procedure changes was completed in February 1986. All of the changes have been subjected to the review and approval of the Plant Review Committee (PRC) and the Management-Safety Review Committee (MSRC).
1.
In order to provide alternative shutdown capability for a hypothetical fire in the. Control Room, push button controls were installed at remote shutdown panel H250 for 14 pieces of equipment and 5 motor operated valves previously having no point of control outside the Control Room.
This modification was necessary~in order to comply with the requir'ements of 10 CFR 50, Appendix R.
The modifications are limited to the "A" channel equipment only and would only be required-to be used in the event that shutdown from the Control Room was not possible due to a fire.
The addi-tional switches to be installed in the. control circuits of the Channel "A"
equipment may slightly decrease the reliability of the particular equipment because of-the possible failure of the switch.
However, the additional switches will increase the protection of the plant in the event of a fire in the Control Room.
2.
The District - Rancho Seco Emergency Plan (AP.500) was revised to:
a.
Include in Section 8, information concerning the placement of siren information to make it available to the transient population, b.
Change.Section 7.0 to include the actuation times of the Technical Support Center (TSC), Emergency Operations Facility (EOF) and the Operations Support Center (OSC) and Radiation Monitoring Team, and c.
Change Section 6.1 to identify the group in the District's organiza-tion that is responsible for the maintenance and periodic testing of the_public warning system including the attaching of the letters of agreement between the District and the three counties to tne Emer-gency Plan.
~
8603260400 860220 Tgi,
PDR ADOCK 05000312 R-PDR
, These changes are consistent with NRC correspondence dated March.14, April 20 and May 11, 1984 and enhance the effectiveness of the Rancho Seco Emergency Response Capability.
3.
In order to implement symptom based Emergency Operatin~g Procedures based on AT0G, in accordance with Item I.C.1 of NUREG-0737 and Supplement 1 to NUREG-0737, Procedures E.01 through E.07, CP 101 through CP 105 and Rules 1 through 7 have been revised. The NRC review of ATOG was docu-mented by a Safety Analysis Report (Generic Letter 83-31, dated Septem-ber 14, 1983 and by a supplement dated December 14, 1985.
The NRC concluded "AT0G is acceptable as a basis'for' implementation of improved plant specific procedures and will provide improved guidance for operator emergency procedures over that which currently exists" (i.e., event oriented procedures). The NRC SER (Item 1 of Section 1.3) required that, prior to implementation, AT0G be extended to better cover ATWS and certain aspects of natural circulation. This was accomplished and approved in the afore-mentioned SER supplement. These improvements are not in the Rancho Seco AT0G.but were incorporated directly into the Rancho Seco Emergency Operating Procedures.
MAJOR ITEMS OF SAFETY RELATED MAINTENANCE 1.
A Steam Generator Inspection Program was initiated and the results of the inspection program, including the number of tubes plugged, the number and extent of tubes inspected, the location and percent of wall thickness penetration for each indication of an imperfection will be provided ir the monthly report following the completion of the program.
2.
Makeup Pump P-236 was disassembled and inspected by District engineers and the manufacturer's service representatives.
It was determined that the pump case was repairable and the rotating element will have to be replaced.
The pump was damaged during the December 26, 1985 Loss of ICS Event.
3.
The flange face for the "B" 0TSG (12 B riser) was machined to remove minor steam cutting of flange face. The flange was reassembled with new gaskets.
4.
Reactor Coolant System "B" loop cold leg thermocouple was replaced to correct a disparity in the "B" loop temperature reading.
5.
Boric acid addition valve HV-23006 was disassembled and repaired to correct an observed gradual increase in reactor coolant system boron concentration.
6.
Preventive maintenance was performed on the hydrogen analyzer to maintain equipment qualification. Pressure Control Valve PCV-53820 and PCV-53818 were replaced.
7.
Various plant equipment relief valves were verified to have proper pressure setpoints, or were replaced.
(Third and fourth point feedwater heater shellside relief valves, "C" reactor building emergency cooler relief valve,)
REFUELING INFORMATION REQUEST 1.
Name of Facility Rancho Seco Unit 1 2.
Scheduled date for next refueling shutdown:
April 1. 1987 3.
Scheduled date for restart following refueling:
August 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
--AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-312 UNIT Rancho Seco Unit 1 DATE 02-28-86 COMPLETED BY R. Colombo TELEPHONE' (916) 452-3211 MONTH February 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(tNe-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 14 0
30 15 0
31 16 0-INSTRUCTIONS
~
On this format,.1ist the average dall'y unit power level -in MWe-Net for each day in the reporting month.
Compute to the nearest whole megawatt.
OPERATING DATA REPORT DOCKET NO.
50-312 a.
DATE 02/28/86 COMPLETED BY R. Colombo TELEPHONE (916) 452-3211 OPERATING STATUS NOTE:
1.
Unit Name:
Rancho Seco Unit 1 2.
Reporting Period:
February 1986 3.
Licensed Thermal Power (NWt):
2.772 4.
Nameplate Rating-(Gross NWe):
963 5.
Design Electrical Rating (Net NWe):
918 i
6.
Maximum. Dependable Capacity (Gross NWe):
917 7.
Maximum Dependable Capacity (Net NWe):
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 NWe):
0
.10.
Reasons For Restrictions, If Any:
NRC limit pursuant to letter dated 12/26/85.
This Month Yr-to-Date-Cumulative 11.
Hours in Reporting Period 672 1.416 95.281 12.
Number of Hours Reactor Was Critical 0
0 54.322 I
13.
Reactor Reserve Shutdown Hours 0
0 10.300.2 14 e: Hours Generator On-Line 0
0 50.363.8 t
- 15. Unit Reserve Shutdown Hours 0
0 1.210.2 16.
Gross Thermal Energy Generated (NWH) 0 0
127.861.688 t
17.
Gross Electrical Energy' Generated (NWH) 0 0
41.523.187 18.
Net Electrical Energy Generated (NWH) 0 0
38.527.432 19.
Unit Service Factor 0.0%
0.0%
52.9%
- 20. Unit Availability Factor-0.0%
0.0%
54.1%.
.21.
Unit Capacity Factor (Using MDC Net) 0.0%
0.0%
46.3%
22.
Unit Capacity Factor (Using DER Net) 0.0%
0.0%
44.0%
- 23. ~ Unit Forced Outage Rate 100.0%
100.0%
31.4%
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:
April 18,1986 26.
Units In Test Status (Prior to Commercial Operation):
Forecast.
Achieved INITIAL CRITICALITY
'N/A N/A INITIAL ELECTRICITY N/A N/A CONNERCIAL OPERATION N/A N/A i
DOCKET NO. 50-312 UNIT SHU1 DOWNS AND POWER REDUC 110NS UNIT NAME Rancho Socn Unit'No. 1-DATE 2/28/86 COMPLETED BY R. Colombo REPORT MONTH FEBRUARY 1986 TELEPHONE (916) 452-3211 w.
b C
Cause & Corrective
.= 3
.f
. Licensee' E e,,
k No.
Date k
j8 y'
Action to o s a:
Event uT
-65 5'
djg Report #
N0 Prevent Recurrence 3
1 85-12-26 F
672 A
3 85-25 CB INSTRU Reactor trip on high pressure. Total loss of all ICS power. Corrective actions being implemented.
M s..
2 3
4 F Forced.
Reason:
Method:
Exhibit G. instructions
. 5: 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) 0161) 1.
E-Operator Training & Ucense Examination F-Administrative 5
G-Operational Error (Explain)
Exhibit I-Same Source 19/77)
Il-Other (Explain) 4 9
4 ~,
g
I c 3.uu.
SACRAMENTO MUNICIPAL UTILITY DISTRICT O 6201 S Street. P.O. Box 15830, Sacramento CA 95852-1830 (916) 45'-3211 AN ELECTHIC SYSTEM SERVING THE HEART OF CALIFU< ilA RWC 86-130 i
March ' 10, 1986 DIRECTOR OFFICE OF INSPECTION AND ENFORCEMENT U S NUCLEAR REGULATORY COMMISSION WASHINGTON DC 20555 OPERATING PLANT STATUS REPORT DOCKET N0. 50-312 Enclosed is the February 1986 Monthly Plant Status Report for Rancho Seco Unit One.
R. W. COLOMB0 REGULATORY COMPLIANCE SUPERINTENDENT Enci (5).
cc:
I & E Washington (9)
Region V MIPC (2)
INP0 I
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