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=Text=
=Text=
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i JUNE 1986
i JUNE 1986


==SUMMARY==
==SUMMARY==
OFPLANTOPERATIONS                                                                         I The plant has been in cold shutdown for the entire month of June 1986. The initial shutdown was due to the December 26,1986 loss of ICS power event.
OFPLANTOPERATIONS I
The plant has been in cold shutdown for the entire month of June 1986. The initial shutdown was due to the December 26,1986 loss of ICS power event.
PERSONNEL CHANGES RE0UIRING REPORT There were no changes in personnel which require reporting pursuant to Technical Specification Figure 6.2.2.
PERSONNEL CHANGES RE0UIRING REPORT There were no changes in personnel which require reporting pursuant to Technical Specification Figure 6.2.2.


Line 27: Line 28:
The final documentation packages for the following facility and procedure changes were completed in June 1986. All of these changes have been subjected to the review and approval of the I'lant Review Committee (PRC) and the Management Safety Review Committee (MSRC). The District did not produce any final documentation packages for tests or experiments during June 1%6.
The final documentation packages for the following facility and procedure changes were completed in June 1986. All of these changes have been subjected to the review and approval of the I'lant Review Committee (PRC) and the Management Safety Review Committee (MSRC). The District did not produce any final documentation packages for tests or experiments during June 1%6.
1 Auditins! 500 TM fu vse s%d to Atuilitry Building rooms 102 and 103 to provide a positive pressure for these rooms and to limit the airborne sources of exposure received by the Post Accident Sampling System control panel operator.
1 Auditins! 500 TM fu vse s%d to Atuilitry Building rooms 102 and 103 to provide a positive pressure for these rooms and to limit the airborne sources of exposure received by the Post Accident Sampling System control panel operator.
This change will provide an air makeup duct for the existing air handling unit
This change will provide an air makeup duct for the existing air handling unit such that positive pressure of 1/16 to 1/8 inches W. G.. shall be maintained to purge radioactive noble gases from the room during post accident sampling.
  !                  such that positive pressure of 1/16 to 1/8 inches W. G.. shall be maintained to purge radioactive noble gases from the room during post accident sampling.
The existing air handling unit was equipped with an air intake plenum box including mixing damper to either fully recirculate room air or makeup only enough air from outside to pressurize the room. The makeup air duct is also provided with a fire damper and a fusible link for fire protection purposes. (Log i
The existing air handling unit was equipped with an air intake plenum box including mixing damper to either fully recirculate room air or makeup only enough air from outside to pressurize the room. The makeup air duct is also provided with a fire damper and a fusible link for fire protection purposes. (Log i                   '740,Rev.1) l MA IOR ITEMS OF SAFETY RELATED MAINTENANCE
'740,Rev.1) l MA IOR ITEMS OF SAFETY RELATED MAINTENANCE 1.
: 1.       Repair efforts on the makeup pump (P-236) continued through the month of June 1%6.
Repair efforts on the makeup pump (P-236) continued through the month of June 1%6.
: 2.       The process of performing preventive maintenance on various plant valves continued through the month of June 1%6. The District began data collection on IEB 85-03 MOVs.
2.
l l           3.       Funds for preventive Once-Through-Steam-Generator tube sleeving was authorized by the District.
The process of performing preventive maintenance on various plant valves continued through the month of June 1%6. The District began data collection on IEB 85-03 MOVs.
: 4.       PASS modifications continued through June 1%6.
l l
: 5.       Continued rework and testing efforts on NNI-I Cabinets. The rework on the RP5 cabinets was completed.
3.
: 6.       Continued localleak rate testing of reactor building penetrations.
Funds for preventive Once-Through-Steam-Generator tube sleeving was authorized by the District.
07 860630 h U h CK           05000312 R
4.
PASS modifications continued through June 1%6.
5.
Continued rework and testing efforts on NNI-I Cabinets. The rework on the RP5 cabinets was completed.
6.
Continued localleak rate testing of reactor building penetrations.
h U h CK 05000312 07 860630 R
PDR
PDR
                                                                                                              \
\\
: o.
 
2-
o.
: 7.               Installed and completed the new E- Battery testing. Installed and completed the new A -
2-7.
Installed and completed the new E-Battery testing. Installed and completed the new A -
Nuclear Service Battery testing.
Nuclear Service Battery testing.
: 8.               Continued snubber testing.
8.
: 9.               Removed plug in the A - Letdown cooler drain line and started an additional flushing program.
Continued snubber testing.
9.
Removed plug in the A - Letdown cooler drain line and started an additional flushing program.
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    ~     .                                                                                  .
~
REFUELING INFORMATION REQUEST
REFUELING INFORMATION REQUEST 1.
: 1. Name of Facility             Rancho Seco Unit 1
Name of Facility Rancho Seco Unit 1 2.
: 2. Scheduled date for next refueling shutdown:         March 1. 1988
Scheduled date for next refueling shutdown:
: 3. Scheduled date for restart following refueling:     July 1. 1988
March 1. 1988 3.
: 4. Technical Specification change or other license amendment required:
Scheduled date for restart following refueling:
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)
July 1. 1988 4.
: 5. Scheduled date(s) for submitting proposed licensing action:     September 1,1987
Technical Specification change or other license amendment required:
: 6. Important licensing considerations associated with refueling:       N/A
a)
: 7. Number of fuel assemblies:
Change to Rod Index vs Power Level Curve (TS 3.5.2) b)
a)   In the core:                         177 b)   In the Spent Fuel Pool:             316
Change to Core Imbalance vs Power Level Curve (TS 3.5.2) c)
: 8. Present licensed spent fuel capacity:         1080
Tilt Limits (TS 3.5.2) 5.
: 9. Projected date of the last refueling that can be discharged to the Spent Fuel Pool:     December 3. 2001 I
Scheduled date(s) for submitting proposed licensing action:
September 1,1987 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 I
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  ~
~
* AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.                           50-312 UNIT   Rancho Seco Unit 1 DATE     06-30-86 COMPLETED BY                     R. Colombo TELEPHONE                 (916) 452-3211 MONTH       June 1986 DAY                   AVERAGE DAILY POWER LEVEL               DAY AVERAGE DAILY POWER LEVEL (MWe-Net)                                                     (HWe-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 MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-312 UNIT Rancho Seco Unit 1 DATE 06-30-86 COMPLETED BY R. Colombo TELEPHONE (916) 452-3211 MONTH June 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(HWe-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 MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.


OPERATING DATA REPORT DOCKET NO.             50-312 DATE           06/30/86 COMPLETED BY           R. Colombo TELEPHONE       (916) 452-3211 OPERATING STATUS
OPERATING DATA REPORT DOCKET NO.
: 1. Unit Name:               Rancho Seco Unit 1
50-312 DATE 06/30/86 COMPLETED BY R. Colombo TELEPHONE (916) 452-3211 OPERATING STATUS 1.
: 2. Reporting Period:             June 1986
Unit Name:
: 3. Licensed Thermal Power (MWt):                 2.772
Rancho Seco Unit 1 2.
: 4. Nameplate Rating (Gross MWe):                     963
Reporting Period:
: 5. Design Electrical Rating (Net MWe):               918
June 1986 3.
: 6. Maximum Dependable Capacity (Gross MWe):         917
Licensed Thermal Power (MWt):
: 7. Maximum Dependable Capacity (Net MWe):           873
2.772 4.
: 8. If changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:                                                               N/A
Nameplate Rating (Gross MWe):
: 9. Power Level to Which Restricted, If Any (Net MWe):                           0
963 5.
: 10. Reasons For Destrictions, If Any:         NRC Letter dated 12/26/85.
Design Electrical Rating (Net MWe):
This Month         Yr-to-Date         Cumulative
918 6.
: 11. Hours in Reporting Feriod                             720             4.343             98.208
Maximum Dependable Capacity (Gross MWe):
: 12. Number of Hours Reactor Was Critical                   0                   0           54.322
917 7.
: 13. Reactor Reserve Shutdown Hours                         0                   0           10.300.2
Maximum Dependable Capacity (Net MWe):
: 14. Hours Generator On-Line                                 0                   0           50.363.8
873 8.
: 15. Unit Reserve Shutdown Hours                             0                   0             1.210.2
If changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
: 16. Gross Thermal Energy Generated (MWH)                   0                   0       127.861.688
N/A 9.
: 17. Gross Electrical Energy Generated (MWH)                 0                   0       41.523.187
Power Level to Which Restricted, If Any (Net MWe):
: 18. Net Electrical Energy Generated (MWH)           -2.652             -20.791         38.309.311
0 10.
: 19. Unit Service Factor                                 0.0%               0.0%           51.3%
Reasons For Destrictions, If Any:
: 20. Unit Availability Factor                             0.0%               0.0%           52.5%
NRC Letter dated 12/26/85.
l 21. Unit Capacity Factor (Using MDC Net)                 0.0%               0.0%           44.7%
This Month Yr-to-Date Cumulative 11.
: 22. Unit Capacity Factor (Using DER Net)                 0.0%               0.0%           42.5%
Hours in Reporting Feriod 720 4.343 98.208 12.
: 23. Unit Forced Outage Rate                           100.0%               100.0%           34.0%
Number of Hours Reactor Was Critical 0
l 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
0 54.322 13.
N/A
Reactor Reserve Shutdown Hours 0
: 25. If Shut Down At End Of Report Period, Estimated Date of Startup:                 Indefinite
0 10.300.2 14.
: 26. Units In Test Status (Prior to Commercial Operation):                     Forecast       Achieved INITIAL CRITICALITY                       N/A           N/A INITIAL ELECTRICITY                       N/A           N/A
Hours Generator On-Line 0
.                                        COMMERCIAL OPERATION                       N/A           N/A l
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)
-2.652
-20.791 38.309.311 19.
Unit Service Factor 0.0%
0.0%
51.3%
20.
Unit Availability Factor 0.0%
0.0%
52.5%
l 21.
Unit Capacity Factor (Using MDC Net) 0.0%
0.0%
44.7%
22.
Unit Capacity Factor (Using DER Net) 0.0%
0.0%
42.5%
23.
Unit Forced Outage Rate 100.0%
100.0%
34.0%
l 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 INITIAL ELECTRICITY N/A N/A COMMERCIAL OPERATION N/A N/A l
l
l


DOCKET NO.       50-312 UNIT SHUTDOWNS AND POWER REDUCTIONS                                   . RANCHO SECO UNIT 1 UNIT NAME DATE 06/30/86 COMPLETED BY         R. W_ COIOMBO REPORT MONTH JUNE 1986 TELEPHONE (916) d57 1711 w.
50-312 DOCKET NO.
                                                    -      E                           c
UNIT SHUTDOWNS AND POWER REDUCTIONS
                          -,       5g         3     *I3         Licensee   ,E3,                         Cause & Corrective V         Daie     i       3g         s   ;s5           Event     g         j{e.,                    Action to H      y:         5     ~~ ;f3 c    Report #  mU        o                   Prevent Recurrence e       a                         u 3
. RANCHO SECO UNIT 1 UNIT NAME DATE 06/30/86 JUNE 1986 COMPLETED BY R. W_ COIOMBO REPORT MONTH TELEPHONE (916) d57 1711 w.
720       A         3         85-26       CB   INSTRU     REACTOR TRIP ON HIGH PRESSURE 1      85-12-26    F PRECEDED BY TOTAL LOSS OF ICS POWER. CORRECTIVE ACTIONS BEING IMPLEMENTED.
E c
I                 2                                                 3                             4 f Forced         Reason:                                           Method:                         Exhibit G-Instructions S 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 (NUREG-D Regulatory Restriction                           4-Other (Explain)               0161)
j{e.,
E-Operator Training & Ucense Examination F-Administrative                                                               5 G-Operational Error (Explain)                                                       Exhibit 1 Same Source
5g 3
-    19/77 p               Il-Other (E xplain)
*I3 Licensee
O                                                               O                                                             O
,E3, Cause & Corrective Action to V
Daie i
3g s
;s5 Event g
Prevent Recurrence c
Report #
mU y:
5
~~ ;f3 H
o e
a u
3 1
85-12-26 F
720 A
3 85-26 CB INSTRU REACTOR TRIP ON HIGH PRESSURE PRECEDED BY TOTAL LOSS OF ICS POWER. CORRECTIVE ACTIONS BEING IMPLEMENTED.
I 2
3 4
f Forced Reason:
Method:
Exhibit G-Instructions S 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 (NUREG-D Regulatory Restriction 4-Other (Explain) 0161)
E-Operator Training & Ucense Examination F-Administrative 5
G-Operational Error (Explain)
Exhibit 1 Same Source 19/77 p Il-Other (E xplain)
O O
O


  $fSMUD                                                                                     "EF" SACRAMENTO MUNICIPAL UTILITY DISTRICT E 6201 S Street, P.O. Box 15830. Sacramento CA 95852-1830.1916)452-3211 AN ELECTRIC SYSTEM SERVING THE HE. ART OF CAglF                     NIA n ) 7 F.8. k RWC 86- 389 July 15,1986                                                                               ,,4 n.
$fSMUD "EF" SACRAMENTO MUNICIPAL UTILITY DISTRICT E 6201 S Street, P.O. Box 15830. Sacramento CA 95852-1830.1916)452-3211 AN ELECTRIC SYSTEM SERVING THE HE. ART OF CAglF NIA
7 J B MARTIN REGIONAL ADMINISTRATOR REGION V 0FFICE 0F INSPECTION AND ENFORCEMENT U S NUCLEAR REGULATORY COMMISSION 1450 MARIA LANE, SUITE 210 WALNUTCREEK,CA 945%
) 7 F.8. k n
RWC 86-389 July 15,1986 n.
7
,,4 J B MARTIN REGIONAL ADMINISTRATOR REGION V 0FFICE 0F INSPECTION AND ENFORCEMENT U S NUCLEAR REGULATORY COMMISSION 1450 MARIA LANE, SUITE 210 WALNUTCREEK,CA 945%
OPERATING PLANTSTATUS REPORT DOCKET N0.50-312 Enclosed is the June 1986 Monthly Operating Plant Report for the Rancho Seco Nuclear Generating Station pursuant to Technica1 Specification 6.9.3.
OPERATING PLANTSTATUS REPORT DOCKET N0.50-312 Enclosed is the June 1986 Monthly Operating Plant Report for the Rancho Seco Nuclear Generating Station pursuant to Technica1 Specification 6.9.3.
Or R. W. COLOMB0 LlM&wh REGULATORY COMPLIANCE SUPERINTENDENT Enci (5) cc:     I&E Wash (12)
Or LlM&wh R. W. COLOMB0 REGULATORY COMPLIANCE SUPERINTENDENT Enci (5) cc:
I&E Wash (12)
MIPC (2)
MIPC (2)
INP0 RANCHO SECO NUCLEAR GENERATING STATION C 14440 Twin Cities Road, Herald, CA 95638-9799;(209) 333-2935 1[d}}
INP0 1[d RANCHO SECO NUCLEAR GENERATING STATION C 14440 Twin Cities Road, Herald, CA 95638-9799;(209) 333-2935
-}}

Latest revision as of 20:47, 6 December 2024

Monthly Operating Rept for June 1986
ML20207K897
Person / Time
Site: Rancho Seco
Issue date: 06/30/1986
From: Colombo R
SACRAMENTO MUNICIPAL UTILITY DISTRICT
To: Martin J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
RWC-86-389, NUDOCS 8607300107
Download: ML20207K897 (7)


Text

_

i JUNE 1986

SUMMARY

OFPLANTOPERATIONS I

The plant has been in cold shutdown for the entire month of June 1986. The initial shutdown was due to the December 26,1986 loss of ICS power event.

PERSONNEL CHANGES RE0UIRING REPORT There were no changes in personnel which require reporting pursuant to Technical Specification Figure 6.2.2.

SUMMARY

OF CHANGES IN ACCORDANCE WITH 10 CFR 5059 i

The final documentation packages for the following facility and procedure changes were completed in June 1986. All of these changes have been subjected to the review and approval of the I'lant Review Committee (PRC) and the Management Safety Review Committee (MSRC). The District did not produce any final documentation packages for tests or experiments during June 1%6.

1 Auditins! 500 TM fu vse s%d to Atuilitry Building rooms 102 and 103 to provide a positive pressure for these rooms and to limit the airborne sources of exposure received by the Post Accident Sampling System control panel operator.

This change will provide an air makeup duct for the existing air handling unit such that positive pressure of 1/16 to 1/8 inches W. G.. shall be maintained to purge radioactive noble gases from the room during post accident sampling.

The existing air handling unit was equipped with an air intake plenum box including mixing damper to either fully recirculate room air or makeup only enough air from outside to pressurize the room. The makeup air duct is also provided with a fire damper and a fusible link for fire protection purposes. (Log i

'740,Rev.1) l MA IOR ITEMS OF SAFETY RELATED MAINTENANCE 1.

Repair efforts on the makeup pump (P-236) continued through the month of June 1%6.

2.

The process of performing preventive maintenance on various plant valves continued through the month of June 1%6. The District began data collection on IEB 85-03 MOVs.

l l

3.

Funds for preventive Once-Through-Steam-Generator tube sleeving was authorized by the District.

4.

PASS modifications continued through June 1%6.

5.

Continued rework and testing efforts on NNI-I Cabinets. The rework on the RP5 cabinets was completed.

6.

Continued localleak rate testing of reactor building penetrations.

h U h CK 05000312 07 860630 R

PDR

\\

o.

2-7.

Installed and completed the new E-Battery testing. Installed and completed the new A -

Nuclear Service Battery testing.

8.

Continued snubber testing.

9.

Removed plug in the A - Letdown cooler drain line and started an additional flushing program.

I i

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REFUELING INFORMATION REQUEST 1.

Name of Facility Rancho Seco Unit 1 2.

Scheduled date for next refueling shutdown:

March 1. 1988 3.

Scheduled date for restart following refueling:

July 1. 1988 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:

September 1,1987 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 I

i l

~

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-312 UNIT Rancho Seco Unit 1 DATE 06-30-86 COMPLETED BY R. Colombo TELEPHONE (916) 452-3211 MONTH June 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(HWe-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 MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

OPERATING DATA REPORT DOCKET NO.

50-312 DATE 06/30/86 COMPLETED BY R. Colombo TELEPHONE (916) 452-3211 OPERATING STATUS 1.

Unit Name:

Rancho Seco Unit 1 2.

Reporting Period:

June 1986 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 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 MWe):

0 10.

Reasons For Destrictions, If Any:

NRC Letter dated 12/26/85.

This Month Yr-to-Date Cumulative 11.

Hours in Reporting Feriod 720 4.343 98.208 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)

-2.652

-20.791 38.309.311 19.

Unit Service Factor 0.0%

0.0%

51.3%

20.

Unit Availability Factor 0.0%

0.0%

52.5%

l 21.

Unit Capacity Factor (Using MDC Net) 0.0%

0.0%

44.7%

22.

Unit Capacity Factor (Using DER Net) 0.0%

0.0%

42.5%

23.

Unit Forced Outage Rate 100.0%

100.0%

34.0%

l 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 INITIAL ELECTRICITY N/A N/A COMMERCIAL OPERATION N/A N/A l

l

50-312 DOCKET NO.

UNIT SHUTDOWNS AND POWER REDUCTIONS

. RANCHO SECO UNIT 1 UNIT NAME DATE 06/30/86 JUNE 1986 COMPLETED BY R. W_ COIOMBO REPORT MONTH TELEPHONE (916) d57 1711 w.

E c

j{e.,

5g 3

  • I3 Licensee

,E3, Cause & Corrective Action to V

Daie i

3g s

s5 Event g

Prevent Recurrence c

Report #

mU y:

5

~~ ;f3 H

o e

a u

3 1

85-12-26 F

720 A

3 85-26 CB INSTRU REACTOR TRIP ON HIGH PRESSURE PRECEDED BY TOTAL LOSS OF ICS POWER. CORRECTIVE ACTIONS BEING IMPLEMENTED.

I 2

3 4

f Forced Reason:

Method:

Exhibit G-Instructions S 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 (NUREG-D Regulatory Restriction 4-Other (Explain) 0161)

E-Operator Training & Ucense Examination F-Administrative 5

G-Operational Error (Explain)

Exhibit 1 Same Source 19/77 p Il-Other (E xplain)

O O

O

$fSMUD "EF" SACRAMENTO MUNICIPAL UTILITY DISTRICT E 6201 S Street, P.O. Box 15830. Sacramento CA 95852-1830.1916)452-3211 AN ELECTRIC SYSTEM SERVING THE HE. ART OF CAglF NIA

) 7 F.8. k n

RWC 86-389 July 15,1986 n.

7

,,4 J B MARTIN REGIONAL ADMINISTRATOR REGION V 0FFICE 0F INSPECTION AND ENFORCEMENT U S NUCLEAR REGULATORY COMMISSION 1450 MARIA LANE, SUITE 210 WALNUTCREEK,CA 945%

OPERATING PLANTSTATUS REPORT DOCKET N0.50-312 Enclosed is the June 1986 Monthly Operating Plant Report for the Rancho Seco Nuclear Generating Station pursuant to Technica1 Specification 6.9.3.

Or LlM&wh R. W. COLOMB0 REGULATORY COMPLIANCE SUPERINTENDENT Enci (5) cc:

I&E Wash (12)

MIPC (2)

INP0 1[d RANCHO SECO NUCLEAR GENERATING STATION C 14440 Twin Cities Road, Herald, CA 95638-9799;(209) 333-2935

-