ML20214J019

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Monthly Operating Repts for Apr 1987
ML20214J019
Person / Time
Site: Diablo Canyon  Pacific Gas & Electric icon.png
Issue date: 04/30/1987
From: Hug M, Keller A, Thornberry R
PACIFIC GAS & ELECTRIC CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8705270595
Download: ML20214J019 (9)
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MONTHLY NARRATIVE REPORT OF OPERATION  !

AND MAJOR MAINTENANCE EXPERIENCE Th'is report describes the operating and major maintenance experience for

! the month of April, 1987. This narrative report was prepared by the

plant staff and is submitted in accordance with Section 6.9.1.7 of the Units 1 and 2 Technical Specifications.

On April 1, 1987 Unit 1 started the month at 100% power.

Unit 2 started the month at 100% power.

4 0n April 3, 1987 Unit'2 decreased power to 78%'to reduce chlorides due to leaking condenser tubes.

Unit 2 experienced a turbine generator trip due to antimotoring relay actuation and subsequent reactor trip while operators were shutting down the unit in

> preparation for a. refueling outage.

On April 5,-1987 Unit 2 entered Mode 4 and then Mode-5.

2 On April 10, 1987 Unit 2 residual heat removal flow was interrupted for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and'28 minutes. The reactor coolant j system (RCS) had_just been drained to mid-loop

! level to-facilitate removal of steam generator l

primary manways and subsequent nozzle dam i installation. In addition, preparation for a local i' leak rate test on containment isolation valves was in progress (including draining the penetration).

! Due to leaking valves in the penetration being i drained, RCS inventory was lost to the_ reactor i coolant drain tank. Loss of inventory caused a y decrease in RCS water level and resulted'in air 4

entrainment in the operating RHR pump because of vortexing in the pump suction line. The RHR pump was manually tripped.-After verifying that the steam generator manways were still installed'and after venting the RHR pumps, RCS was flooded from the RWST and a RHR pump was' restarted. This event resulted in some localized boiling but no damage to the core or significant radiological release.

i on April-14, 1987 Unit 2 entered Mode-6.

On April 21, 1987 Unit 2 reactor head removed in preparation for

, refueling.

On April 22, 2987 On-site biologists made a preliminary determination that approximately 68 pcinds of ferric sulfate

inadvertently discharged from the Seawater Reverse Osmosis Facility to the intake cove on April 21, 1987, had an environmental impact. Based on this result a Non-emergency Four Hour Report report was 5

8705270595 870430 G' PDR ADOCK 05000275 R ppg _ ll}

l made in accordance with 10CFR50.72.(b)(2)(vi).

Commenced removing fuel from Unit 2 reactor.

on April 28, 1987 Completed Unit 2 reactor core offload. Exited mode

~

6.

On April 30, 1987 Unit 1 ended the month at full power. Unit 2 ended the month shut down for a refueling outage.

Unit l~ operated this month with a unit availability factor of 100% and a unit capacity factor of 100%.

Unit 2 operated this month with a unit availability factor of.10.0%.and

,~

a unit. capacity factor of 7.0%. Unit 2 reduced power once this month to '

reduce' chlorides due to leaking condenser tubes. Unit 2 tripped once this month due to antimotoring relay actuation with subsequent turbine trip - reactor trip while operators were shutting down the unit in preparation for a refueling outage. The reactor remained shutdown for ,

the Unit 2 refueling' outage.

Significant safety related maintenance consisted'of Unit 2 reactor head removal and core offload, Unit 2 testing of safety valves to verify set points and repairs to plant vent radiation monitor.

During the-April 3, 1987 Unit 2 reactor trip, loop 4 atmospheric steam dump valve PCV-22 did not open when steam generator pressure exceeded its lift setpoint which subsequently caused a loop 4 main steam line code safety valve actuation. No other challenges to the steam generator safety valves or pressurizer power operated relief valves were made.

l No major changes to the radwaste treatment-systems as required by l

Technical Specification 6.15.1 were made.

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OPERATING DATA REPORT DOCKET NO. 50-275 DATE 05/06/87 COMPLETED BY A.T. Keller TELEPHONE (805)S95-7351 OPERATING STATUS

1. Unit Name: Diablo Canyon Unit 1
2. Reporting Period: April 1987
3. Licensed Thermal Power (W t): 3338
4. Nameplate Rating (Gross We): 1137
5. Design Electrical Rating (Net W e): 1086
6. Maximum Dependable Capacity (Gross MWe): 1125
7. Maximum Dependable Capacity (Net MWe): 1073
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): N/A
10. Reasons For Restrictions, If Any: None This Month Yr-to-Date Cumulative *
11. Hours In Reporting Period 719.0 2879.0 17373.3
12. Number Of Hours Reactor Was Critical 719.0 2732.0 13997.6
13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0
14. Hours Generator On-Line 719.0 2670.4 13635.8
15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
16. Gross Thermal Energy Generated (WH) 2394500 7841891 41383961
17. Gross Electrical Energy Generated (MWH) 814300 _2636000 13769732
18. Net Electrical Energy Generated (MWH) 777186 2494066 13021887
19. Unit Service Factor 100.0 92.8 78.5
20. Unit Availability Factor 100.0 92.8 78. 5 _ _
21. Unit Capacity factor (Using MDC Net) 100.7 80.7 69.9
22. Unit Capacity Factor (Using DER Net) 99.5 79.8__ 69.0
23. Unit Forced Outage Rate 0.0 7.2 5.5
24. Shutdowns Scheduled Over Next 6 Months (Type. Date, and Duration of Each):

N/A

25. If Shut Down At End Of Report Period. Est. Date of Startup: N/A
  • As of commercial operation on 5-7-85 at 0243.

M0.RPT

OPERATING DATA REPORT DOCKET NO. 50-323 DATE 05/06/87 COMPLETED BY A.T. Keller TELEPHONE (805)S95-7351 OPERATING STATUS

1. Unit Name: Diablo Canyon Unit 2
2. Reporting Period: April 1%7
3. Licensed Thermal Power (W t): 3411
4. Nameplate Rating (Gross We): 1164
5. Design Electrical Rating (Net We): 1119
6. Maximum Dependable Capacity (Gross MWe): 1130
7. Maximum Dependable Capacity (Net MWe): 1079
8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report.

Give Reasons:

N/A

9. PowerLevelToWhichRestricted.IfAny(NetMWe): N/A
10. Reasons For Restrictions If Any: None This Month Yr-to-Date Cumulative *
11. Hours In Reporting Period 719.0 2879.0 9932.0
12. Number Of Hours Reactor Was Critical 71.9 2133.2 8990.1
13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0
14. Hours Generator On-Line 71.9 1911.1 8641.5
15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
16. Gross Thermal Energy Generated (WH) 190948 5978045 27058764
17. Gross Electrical Energy Generated (MWH) 62400 1972100 8884599
18. Net Electrical Energy Generated (MWH) 54034 1851218 8399392
19. Unit Service factor 10.0 66.4 87.0
20. Unit Availability Factor 10.0 66.4 87.0
21. Unit Capacity Factor (Using MDC Net) 7.0 59.6 78.4
22. Unit Capacity factor (Using DER Net) 6.7 57.5 75.6
23. Unit Forced Outage Rate 0.0 14.9 7.0
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Refueling Outage. April 3, 1987. 70 days

25. If Shut Down At End Of Report Period Est. Date of Startup: June 16. 1987
  • As of consercial operation on March 13, 1986 at 0300 PST.

M0.RPT

AVERAGE DAILY UNIT POWER LEVEL DOCKET N0. 50-275 UNIT Diablo Canyon Unit 1 DATE 05/06/87

. COMPLETED BY A.T. Keller TELEPHONE (805)595-7351 MONTH April 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (We-Net) (We-Net) 1 1083 17 1088 j

2 1087 18 1088 3 1081 19 1071 4 1076 20 1088 5 1012 21 1092 6 1074 22 1076 7 1074 23 1088 8 1071 24 1092 9 1079 25 1080 10 1081 26 1079 11 1085 27 1088 i 12 1077 28 1076 _

13 1081 29 1080 14 1082 30 1084 15 1082 16 1090 INSTRUCTIONS On this format, list the average daily unit power level in We-Net for each day in the reporting month. Compute to the nearest whole megawatt.

The Average Monthly Electrical Power Level for April, 1987 = 1079.42 We-Net.

M0.RPT

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-323 UNIT Diablo Cartyon Unit 2 DATE __ 05/06/87 COMPLETED BY- A.T. Keller TELEPHONE (805)S95-7351 MONTH April 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (We-Net) (We-Net) 1 855 17 -6 2 856 18 -6 3 733 19 -6 4 -38 20 -6 5 -19 21 -6 6 -10 22 -6 7 -9 23 -7 8 -8 24 -7 9 -5 25 -7 10 -3 26 -6 11 -3 27 -6 12 -3 28 -5 13 -3 29 -5 14 -3 30 -5 15 -3 16 -3 INSTRUCTIONS On this format, list the average daily unit power level in We-Net for each de in the reporting month. Compute to the nearest whole megawatt.

The Average Monthly Electrical Power Level for April, 1987 = 75.05 W e-Net.

M0.RPT

UNIT SHUTDOWNS Page 1 ef 1 DOCKET NO. 50-275 .

UNIT NAME Diablo Canyon Unit 1 +

DATE 05/06/87 i COMPLETED BY M.T. HUG REPORT MONTH APRIL 1987 TELEPHONE (805)S95-7351 Duration Method of System Component Ac i o 2 4 5 No. Date Type l (Hours) Reason Shutdown3 Report # Code Code Prevent Recurrence None a

.i 4

1 2 3 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 D-Regulatory Restriction 4-Continuation from (NUREG-1022)

E-Operator Training & License Examination previous month F-Administrative 5-Power reduction 5 ,

G-Operational Error (Explain) 6,7,8-N/A Exhibit I - Same Source H-Other (Explain) 9-Other MD.RPT

\

UNIT SHUTDOWNS -

Page 1 of 1 DOCKET NO. 50-323 -

UNIT NAME Diab 17 Canyon Unit 2 .

DATE 05/06/87 COMPLETED BY M.T. HUG REPORT MONTH APRIL 1987 TELEPHONE (805)S95-7351 Ucensee System Component "S' '

  • I'*

Duration Method of Event Action to 2 4 Shutdown3 S

No. Date Type l (Hours) Reason Report # Code Code Prevent Recurrence el 04/03/87 F 647.1 G 3 2-87-004-00 TA TRB Unit 2 experienced a turbine generator trip at 12% reactor power when differential pressure switch PS-30 reached its setpoint and caused antimotoring relay actuation and subsequent reactor trip while operators were shutting down the unit in preparation for a refueling outage.

Approximately 23 seconds after the reactor trip, a safety injection occurred on high steam flow signal coincident with low-low Tavg.

Operators were unaware of the antimotoring relay actuation.

Providing annunciation of this relay actuation as well as reducing the

, setpoint is being considered.

  • Since this reactor trip occurred during the scheduled shutdown there was no attempt to restart the reactor.

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 or Test 2-Manual Scram Entry Sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER) File D-Regulatory Restriction 4-Continuation from (NUREG-1022)

E-Operator Training & License Examination previous month F-Administrative 5-Power reduction 5 G-Operational Error (Explain) 6,7,8-N/A Exhibit I - Same Source H-Other (Explain) 9-Other MO.RPT

PACIFIC GAS AND E LE C T RI C C O M PANY DIABLO CANYON POWER PLANT

[gllglllllj + PO. Box 56. Avila Beach, Cahfornia 93424 (805) 595 7351 m_ _ _ _ ,

R C. THORNBERRY PLAP47 MANAGER i

May 15,1987 U.S. Nuclear Regulatory Comission Attn: Document Control Desk

! Washington, DC 20555 RE: Docket No. 50-275 and 50-323 License No. OPR-80 and DPR-82 Monthly Operating Report for April, 1987 Gentlemen:

Enclosed are the completed monthly operating report forms for Diablo Canyon Units 1 and 2 for April, 1987. This report is submitted in accordance with Section 6.9.1.7 of the Units 1 and 2 Technical Specifications.

Sincerely, l

eeT W ROBERT C. Ti10RNBERRY h RCT:lm Enclosures I

cc Mr. John B. Martin, Regional Administrator Region V - USNRC l

l M0.RP1

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