ML20215F833
| ML20215F833 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon |
| Issue date: | 05/31/1987 |
| From: | Bedesem P, Thornberry R PACIFIC GAS & ELECTRIC CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8706230023 | |
| Download: ML20215F833 (18) | |
Text
_
OPERATING DATA REPORT DOCKET NO.
50-275 DATE 06/02/87 COMPLETED BY P. Bedesem TELEPHONE (805)S95-4097 OPERATING STATUS
'1.
Unit Name:
Diablo Canyon Unit 1 2., Reporting Period:
May 1987 3.
Licensed Thermal Power (MWt):
3338 4.
Nameplate Rating (Gross MWe):
1137
- 5.. Design Electrical Rating (Net MWe):
1086 6.
Maximum Dependable Capacity (Gross MWe):
1124**
7.
Maximum Dependable Capacity (Net MWe):
1073**
8.
If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report.
1 Give Reasons:
N/A I ~~
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 3623.0 18117.3
- 12. Number Of Hours Reactor Was Critical 694.9 3426.9 14692.5
- 13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0
- 14. Hours Generator On-Line 681.9 3352.3 14317.7
- 15. Unit Reserve Shutdown Hours 0.0 0.0-0.0 16.-. Gross Thermal Energy Generated (WH) 2118322 9960213 43502282 17..
Gross Electrical Energy Generated (MWH) 714000 3350000 14483732
- 18. Net Electrical Energy Generated (MWH)
_ 677178 3171244 13699065
- 19. Unit Service Factor 91.7 92.5 79.0 J
- 20. Unit Availability Factor 91.7 92.5_
79.0 j
- 21. Unit Capacity Factor (Using MDC Net) 84.8 81.5_
70.4
- 22. Unit Capacity Factor (Using DER Net) 83.8 80.6 69.6
- 23. Unit Forced Outage Rate 8.3-7.5 5.7
- 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 May 7, 1985 at 0243 PDT.
Recomputed due to changes in plant efficiency due to plant modifications made in the last refueling outage.
l 8706230023 870531
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PDR ADOCK 05000275 R
OPERATING DATA REPORT DOCKET NO.
50-323 DATE 06/02/87 COMPLETED BY P. Bedesem TELEPHONE (805)595-4097 i
l OPERATING ST/.TUS j
1.- Unit Name:
Diablo Canyon Unit 2 2.- Reporting-Period:
May 1987 3.
Licensed Thermal Power.(W t):
3411 3
4.
Nameplate Rating-(Gross We):
1164 l
S.
Design Electrical Rating (Net W e):
1119 q
6.
MaximusDependableCapacity'(GrossMWe):
1130 l
7...Maximus 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 Fcr Restrictions, If Any:
None This Month Yr-to-Date Cumulative *
- 11. Hours In Reporting Period 744.0 3623.0 10676.0-
- 12. Number Of Hours Reactor Was Critical 0.0 2133.2 8990.1
- 13. Reactor' Reserve Shutdown Hours 0.0 0.0 0.0
- 14. Hours Generator On-Line 0.0 1911.1 8641.5
- 15. Unit Reserve Shutdown Hours 0.0 0.0 0.0 1
- 16. Gross Thermal Energy Generated (WH) 0 5978045 27058764
- 17. Gross Electrical Energy Generated (MWH) 0 1972100 8884599 1
- 18. Net Electrical Energy Generated (MWH)
-2845 1848373 8396547 j
~19.
Unit Service Factor 0.3 52.7 80.9-1
- 20. Unit Availability Factor 0.0 52.7 80.9 l
- 21. Unit Capacity Factor (Using W C Net)
-0 4 47.3 72.9
~
- 22. Unit Capacity Factor (Using DER Net)
-0.3-45.6 70.3-l
- 23. Unit Forced Outage Rate 0.0 14.4 6.9--
- 24. ShutdownsScheduledOverNext6 Months (Type.Date,andDurationofEach):
N/A 25.
If-Shut Down At End Of Report Period. Est. Date of Startup:
July 1. 1987 i
- As of commercial operation on March 13, 1986 at 0300 PST.
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2 AVEPAGE DAILY UNIT POWER LEVEL-l<
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DOCKET NO.
50-275
' ' 'l UNIT. Diablo Canyon Unit 1-
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DATE- 06/02/87 COMPLETED BY P. Bedesem TELEPHONE (805)595-4097 i
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,f DAY AVERAGE' DAILY POWER LEVEL DAY
- AVERAGE DAILY. POWER LEVEL' y L(We-Net)
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'1084 17 1069 l
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1084; 19 1081 7
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331-25 1089 10 339
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'. INSTRUCTIONS
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.S-On this format, list the ' average daily unit power, level in We-Net for.each day in the::
l t
reporting month.. Compute to the nearest whole megawatt.-
j f -}he' Average Monthly Electrical Power Level.for May, 1987'=.910.19 MWe-Net. -
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AVERAGE DAILY UNIT POWER LEVEL J
DOCKET NO.
50-323 UNIT-Diablo Canyon Unit 2 DATE 06/02/87 COMPLETED 8Y P. Bedesem
{
TELEPHONE (805)S95-4097 I
1 MONTH May 1987
'i i
l DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL i
(We-Net)
-(We-Net)_
f l
'l
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-5 19
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-2 30
-2 15
-3 31
-1 16 ;
- INSTRUCTIONS On this format, list the average daily unit power level in We-Net for each dein the
. reporting month. Compute to the nearest whole megawatt.
The Average Monthly Electrical Power Level for May,- 1987 = -3.82 W e-Net.
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11 3
MONTHLY NARRATIVE REPORT OF OPERATION AND MAJOR MAINTENANCE EXPERIENCE I
i This report describes the operating and major maintenance experience for i
'the month of May, 1987. This narrative report was prepared by the plant t
staff and is submitted in accordance with Section 6.9.1.7 of the Units 1 and 2 Technical Specifications.
j Narrative of Daily Significant Plant Events
)
i Day of Month Description of the Event May 1 Unit 1 started the month at 100% power.
Unit 2 started the month shutdown for a refueling outage.
May 8 Unit 1 decreased power to 28% to perform maintenance on Main Feedwater Regulating Valve FCV-520 and condenser circulating-water pump bearings.
l May 10 Unit 1 performed demusseling operations.
Unit 2 entered and then exited Mode 6.
May 11 Unit 1 experienced a turbine trip / reactor trip due to a l
main transformer bank pilot wire differential relay j
signal. During pre-startup surveillance testing of Unit i
1, a reactor trip occurred, in Mode 3, when a fuse blew in an intermediate range nuclear instrument. Additional 1
information concerning these events may be found on the j
Unit Shutdowns Section.
A 10CFR50.72(B)(2)(vi) report was made regarding the mortality of a species protected by the Endangered Species Act.
May 12 A 10CFR50.72(b)(2)(iii) report was made regarding an inoperable Steam Generator 1-2 snubber.
Unit 1 Steam Generator 1-2 Relief Valve RV-7 lifted during actuation of'the 10%. steam dump valves. The 10%
steam dump valves were being used'for plant temperature control. The relief valve lifted at 1048 psig instead of its set point of 1065 psig, +/- 1%._The relief valve was reset and returned to service.
May 13 Unit 1 entered Mode 2 and then Mode 1 and was synchronized to the PGandE system. Unit 1 then increased power to 20%.
7
W May 14 Unit 1 increased power to 100%.
A 10CFR50.72(b)(2)(ii) report was made regarding a Unit 2 diesel generator start when an I&C technician inadvertently started the diesel while jumpering alarm inputs to test annunciator functions. The diesel was shutdown from the control room and returned to automatic.
May 15 Unit 2 entered Mode 6.
A 10CFR50.72(b)(2)(ii) report was made regarding an ESF actuation when power was inadvertently interrupted to Unit 2 Plant Vent Radiation Monitor RM-14B resulting in a containment ventilation isolation (CVI).
May 18 A 10CFR50.72(b)(2)(ii) report was made regarding an ESF actuation when an electrical arc occurred during j
reconnection of the cable in the Unit 2 seal table area radiation monitor. This arc was believed to cause a spike j
on Plant Ventilation Monitor RM-14A resulting in a CVI.
May 25 A 10CFR50.72(b)(2)(ii) report was made regarding an ESF actuation when an operator intending to do a source check on Unit 2 Radiation Monitor RM-18 inadvertently did a t
source check on RM-14B resulting in a CVI.
J May 31 Unit 1 ended the month at 100% power.
Unit 2 ended the month shutdown for a refueling outage.
Summary of Plant Operating Statistics, Power Reductions and Unit Shutdowns I
Unit 1 operated this month with a unit availability factor of 91.7% and a unit capacity factor of 84.8%.
Unit 1 tripped twice this month, once due to a turbine trip / reactor trip from a main transformer bank pilot wire differential relay signal and once sue to a reactor trip during Mode 3 when a fuse blew in an intermediate range nuclear instrument.
Unit 1 decreased power once this month to perform maintenance on FCV-520 and condenser circulating water pumps.
Unit 2 operated this month with a unit availability factor of 0.0% and a unit capacity factor of -0.3% due to the unit being shut down for refueling.
Summary of Significant Safety Related Maintenance There was no significant safety related maintenance for Unit 1.
Significant safety related maintenance for Unit 2 consisted of:
o Pressurizer Safety Valves were lapped, tested and reinstalled, o MSIV check valves were inspected and a modified method was developed to connect the disc to the swing arm of the check valve,
o Main Steam Safety Relief Valves (RV7,11,14) seats were lapped and the valves were reinstalled, o Steam generator tube stress relieving and eddy current inspection was performed, o Excore source range detector was replaced, o Fuel bundles from the Unit 2 core were visually and ultrasonically inspected. One fuel rod was replaced in each of three fuel bundles.
H Actuations of Steam Generator Safety Valves or Pressurizer Power Operated Relief Valves i
Unit 1 Steam Generator 1-2 Relief Valve RV-7 lifted during actuation of the 10% steam dump valves. The relief valve lifted at'1048 psig instead j
of its set point of 1065 psig +/- 1%. The relief valve was reset and returned to service.
No other challenges to steam generator safety valves.or pressurizer power operated relief valves were made.
Major changes to the Radwaste Treatment Systems No major changes to the radwaste treatment systems as required by Technical Specification 6.15.1 were made.
Report of Breakwater Inspections Required by Technical Specification 4.7.13.3 The breakwaters were inspected during the months of November to April in i
accordance with Technical Specifications 4.7.13.1 and 4.7.13.2. Results from this years survey were verified against the. survey performed during 1984. Changes in the positions of the breakwater survey monuments are l
given below:
Easting coordinates =
.04 feet 1
Northing coordinates =
.03 feet l
Elevation =
.01 feet These differences are so small as to be considered negligible and indicative that no appreciable breakwater displacement!or settlement has l
occurred. Breakwater settlement survey results and pictures taken during I
the survey are provided in enclosures 1 and 2.
I
PACIFIC GAS AND E LE C T RIC C O M PANY
)
DIABLO CANYON POWER PLANT Y
[lllllllllj PO. Box 56 Avila Beach, Cahfornia 93424 * (805) 595-7351 e=<
a l
R.C. THORNDERRY PLANT MANAGEM
]
q June 15, 1987 j
U.S. Nuclear Regulatory Commission I
Attn: Document Control Desk Washington, DC 20555
'E: Docket No. 50-275 and 50-323 License No. DPR-80 and DPR-82 Monthly Operating Report for May, 1987 l
Gentlemen:
Enclosed are the completed monthly operating report forms for Diablo Canyon Units 1 and 2 for May, 1987. This report is submitted in accordance with Section 6.9.1.7 of the Units 1 and 2 Technical Specifications.
Sincerely, 1
ROBERT C. THORNBERRY RCT:1m t
Enclosures cc Mr. John B. Martin, Regional Administrator I
Region V - USNRC
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