ML20206J594

From kanterella
Revision as of 01:30, 29 December 2020 by StriderTol (talk | contribs) (StriderTol Bot insert)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Monthly Operating Rept for Mar 1987
ML20206J594
Person / Time
Site: Diablo Canyon  Pacific Gas & Electric icon.png
Issue date: 03/31/1987
From: Keller A, Thornberry R
PACIFIC GAS & ELECTRIC CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 8704160129
Download: ML20206J594 (9)


Text

MONTHLY NARRATIVE REPORT

[

N OF OPERATION AND MAJOR MAINTENANCE EXPERIENCE This report describes the operating and major maintenance experience for the month of March, 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 March 1, 1987 Unit I started the month at 100% power.

Unit 2 started the month at 100% power. j Unit 2 was removed from the PGandE system and entered  ;

Mode 2 to repair a hydrogen leak from the hydrogen i coolers into the generator stator cooling syrten.  ;

I On March 5, 1987 Unit 2 connenced a reactor startup after repairing a  !

hydrogen leak in the generator stator cooling' system. l During-startup. while still in Mode 2. Unit 2 experienced a reactor trip on low-low steam generator l level.

On March 6, 1987 Unit 2 entered Mode 1, synchronized to the PGandE system and increased power to 50%.

On March 7, 1987 Unit 2 increased power to 100%.

On March 11, 1987 Unit 2 decreased power to 50% to search for leaking condenser tubes.

On March 12, 1987 Unit 2 returned to full power.

On March 14, 1987 Unit 2 decreased power to 42% to backflush condenser water boxes. On return to full power, power level had to be decreased to 50% due to high bearing temperature on 2-1 Circulating Water Pump.

On March-15, 1987 Unit 1 experienced a reactor-trip -due-to under voltage on '12kV- buses D- and E. n Unit :2sincreased power to 100% after repairing 2-1 Circulating Water Pump bearing.

On March 16, 1987 Unit i returned to Mode 2.

On March 17, 1987 Unit I returned to Mode 1, synchronized to the PGandE system and returned to full power.

8704160129 870331

  1. g I i PDR ADOCK 05000275 l(

R PDR M0.RPT

l l

On March 19, 1987 A significant event was declared on Unit 2 when Residual Heat Renoval Valve 87168 was identified to be closed. The valve was closed for maintenance activities and remained closed for approximately 26 hours3.009259e-4 days <br />0.00722 hours <br />4.298942e-5 weeks <br />9.893e-6 months <br />.

On March 21, 1987 Unit 2 experienced a reactor trip and safety injection due to high steam flow when a main steam isolation valve (MSIV) closed. This event was caused by failure

,/ of a MSIV valve closed position switch.

On March 24, 1987 Unit 2 entered Mode 2.

On March 25, 1987 Unit I reduced power to 50% due to high bearing temperature on 1-1 Circulating Water Pump. The bearing was damaged due to a loss of lubricating oil caused by a broken oil sight glass.

Unit 2. entered. Mode 1, . synchronized to the PGandE system and increased power to 605.

On March 26, 1987 Unit 2 increased power to 100%. )

l On March 27, 1987 Unit i returned to full power after repairing a broken ,

oil sight glass and replacing a bearing on 1-1 Circulating Water Pump.

On March 31, 1987 Unit 1 ended the month at full power. Unit 2 ended the month at full power.

l Unit 1 operated this month with a unit availability factor of 95.2% and a l unit capacity factor of 92.05. Unit 1 shutdown once this month due to a l reactor trip on reactor coolant pump bus under voltage. Unit I reduced l power once this month to replace an oil sight glass and bearing on 1-1 l Circulating Water Pump.

Unit-2-operated this month a' unit availability > factor +of-71.0% and a unit l

' capacity factor of*59.6%. ^ Unit-2 shutdown twice this month, once to repair a hydrogen leak in the-generator statorecooling: system.and once due to a reactor trip on high steam flow when a MSIV closed. Unit 2 reduced power 3  :

times this month, once to search for leaking condenser tubes, once to back flush condenser water boxes and once to repair a bearing in Circulating Water Pump 2-1.

Significant safety related maintenance consisted of:

o Repairs to the plant vent Radiation Monitor.

o Repairs to the Digital Rod Position Indication System.

No challenges to the steam generator safety valves or pressurizer power operated relief valves were made.

M0.RPT

OPERATING DATA REPORT DOCKET N0. 50-275 DATE 04/01/87 COMPLETED BY A.T. Keller TELEPHONE (805)S95-7351 OPERATING STATUS

1. Unit Name: Diablo Canyon Unit 1
2. Reporting Period: March 1987
3. Licensed Thermal Power (MWt): 3338
4. Nameplate Rating (Gross W e): 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 744.0 2160.0 16654.3
12. Number Of Hours Reactor Was Critical 724.4 2013.0 13278.6
13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0
14. Hours Generator On-Line 708.1 1951.4 12916.8
15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
16. Gross Thermal Energy Generated (W H) 2277945 5447392 38989461
17. Gross Electrical Energy Generated (MWH) 771000 1821700 12955432
18. Net Electrical Energy Generated (MWH) 734539 1716880 12244701
19. Unit Service Factor 95.2 90.3 77.6
20. Unit-Availability Factor 95.2 -90.3 77.6
21. -Unit Capacity Factor:(Using MC Net) 92.0 74.1 68.5
22. Unit Capacity Factor (Using DER Net)
  • 90.9 73.2 67.7
23. Unit Forced Outage Rate 4.8 9.7 5.8
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 04/01/87 COMPLETED BY A.T. Keller TELEPHONE (805)S95-7351 OPERATING STATUS

1. Unit Name: Diablo Canyon Unit 2
2. Reporting Period: March 1987
3. Licensed Thermal Power (W t): 3411
4. Nameplate Rating (Gross We): 1164
5. Design Electrical Rating (Net W e): 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. 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 744.0 2160.0 9213.0
12. Number Of Hours Reactor Was Critical 645.3 2061.3 8918.2
13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0
14. Hours Generator On-Line 528.3 1839.2 8569.6
15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
16. Gross Thermal Energy Generated (WH) 1568179 5787097 26867816
17. Gross Electrical Energy Generated (MWH) 515100 1909700 8822199
18. Net Electrical Energy Generated (MWH) 478503 1797184 8345358
19. Unit Service Factor 71.0 85.1 93.0
20. Unit Availability Factor 71.0 85.1 93.0
21. Unit Capacity Factor-(Using M C~ Net) 59.6 77.1 84.0
22. Unit Capacity Factor (Using DER Net) 57.5 74.4 80.9
23. Unit Forced Outage Rate 29.0 14.9 7.0
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Refueling Outage, April 3, 1987, 70 days  ;

1

25. If Shut Down At End Of Report Period, Est. Date of Startup: N/A
  • As of commercial operation on March 13, 1986 at 0300 PST.

M0.RPT

. 1 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-275 UNIT Diablo Canyon Unit 1 DATE 04/01/87 COW LETED BY A.T. Keller TELEPHONE (805)S95-7351 MONTH March 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL

.(We-Net) (We-Met) 1 1065 17 260 2 1083 18 1083 3 1084 19 1088 4 1079 20 1088 5 1083 21 1084 6 1080 22 1075 7 1079 23 1079 8 1071 24 1091 9 1088 25 875 10 1080 26 530 11 1088 27 1084 12 1087 28 _

1088 13 1080 29 1067 14 1083 ~30 1084 15 858 31 1080 16 -37 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 March, 1987 = 987.28 MWe-Met.

M0.RPT

--- r ,,-

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-323 UNIT Diablo Canyon Unit 2 DATE 04/01/87 COMPLETED BY A.T. Keller TELEPHONE (805)S95-7351 MONTH March 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (We-Net) (We-Net) 1 346 17 1088 2 -39 18 1092 3 -40 19 1091 4 -41 20 1087 5 -44 21 290 6 113 22 -39 7 981 23 -39 8 1038 24 -40 9 1071 25 154 10 1046 26 1014 11 917 27 1091 12 790 28 __ 979

~13 946 29 896 14 -691 30 847 15 718 31 851 16 1083 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 March, 1987 = 850.30 MWe-Net.

M0.RPT

UNIT SHUTDOWHS .

Page 1 Cf 1 DOCKET NO. 50-275 UNIT MAME Diablo Canyon Unit DATE 04/03/87 COMPLETED BY M.T. HUG

{ REPORT MONTH MARCH 1987 TELEPHONE (805)S95-7351

'*"S** ause & Corrective Method of System Component Action to Duration Event 4 5 No. Date Type l (Hours) Reason 2

Shutdown 3 Report f Code Code Prevent Recurrence 1 03/15/87 F 35.9 H 3 1-87-004 NA NA A reactor trip occurred when the Diablo Canyon-Gates 500 kV transmission line was hit by a small airplane, approximately 50 miles from the plant, while the main generator voltage regulator was in manual. At the time of the event, main generator voltage regulation was in manual control, awaiting adjustments to eliminate undesirable system fluctuations observed earlier while in automatic control. Due to the circumstances of the event, no corrective action is deemed necessary. Every effort is made to return control functions to automatic as soon as possible.

1 1 2 3 4 l

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 M0.RPT l

UNIT SHUTDOWNS

  • Page 1 of 1 DOCKET NO. 50-323 UNIT NAME Diablo Canyon Unit 2 1 DATE 04/03/87 COMPLETED BY M.T. HUG REPORT MONTH MARCH 1987 TELEPHONE (805)S95-7351 censee ause rrective I

Method of System Component Action to Duration Event ,

4 5 No. Date Type l (Hours) Reason 2

Shutdown 3 Report i Code Code Prevent Recurrence 1 03/01/87 F 117.6 A 1 N/A EL CLR Unit 2 was removed from the PGandE system and entered Mode 2 to repair a hydrogen leak from the hydrogen coolers into the generator stator cooling system. The leakage source was repaired and the unit returned to service. The weld that was leaking will be examined again during the i upcoming refueling outage.

2 03/21/87 F 98.1 A 3 2-87-003 SB 33 This event was caused by the failure of a MSIV valve closed position switch, POS-821 following a rain stom. The failure was caused by water entering into the switch housing which shorted out the internal contacts and provided

! the logic to vent the valve actuator and close mainstream isolation valve FCV-41. The resulting transient produced a high steam flow coincident with low steam line pressure safety injection. The failed switch was replaced with a newer model with 1

improved seals.

1 2 3 4 F: Forced Reason: . Method: . Exhibit G - Instructions

? S: Scheduled A-Equipment Failure (Explain) 1-Manual i for Preparation of Data j B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee

! C-Refueling 3-AutomaticiScram Event Report (LER) File D-Regulatory Restriction 4-Continuation from (NUREG-1022) i 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 i MO.RPT l

7 PACIFIC GAS AND ELECTR,IC C O M PANY

. DIABLO CANYON POWER PLANT I PO. Box 56 Avila Beach, Cahfomia 93424 * (805) 595-7351 lllllllll R.C. THORNBERRY PLANT MANAGER April 10, 1987 U.S. Nuclear Regulatory Comission Attn: Document Control Desk Washington, DC 20555 RE: -Docket.No. 50-275 and.50-323 License No. DPR-80 and DPR-82 Monthly Operating Report for March, 1987 Gentlemen:

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

Sincerely, 4v ()f4YkfA4 ,'

0BERT C. THORNBERRY RCT:lm Enclosures .. .

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

4 7

g\

M0.RPT ,

l

_ .--