ML19095A346
| ML19095A346 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 07/09/1975 |
| From: | Stallings C Virginia Electric & Power Co (VEPCO) |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| Download: ML19095A346 (8) | |
Text
....
RICHMOND.VIRGINIA 23261
/
Office of Plans and Schedules Division of Reactor Licensing
/
July 9, *.1975* /.~~i
' *~ !
- .:~*/rTJ>.er.;i;~l ijo. 565/021974
~PO&M/JTB: clw U.S. Nuclear Regulatory Commission Washington, D. C.
20555 Docket Nos *<ibi?
Dear Sir:
License Nos. DPR-32 DPR-37 Operating information for Surry Unit Nos. 1 and 2 for the month of June 1975 is attached.
Attachment cc:
Mr. Norman C. Moseley Very truly yours,
~-m#~
C. M. Stallings Vice President~Power Supply and Production Operations
DOCKET NO. 50-280 UNIT Surry Unit No. 1 DATE July 2, 1975 COMPLETED BY W. C. Earl AVERAGE DAILY UNIT POWER LEVEL MONTH JUNE
~~~~~~~~~~-
AVER AGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWe-net)
DAY (MWe-net) 1 746.6 17 737.1 2
746.4 18 734.5 3
750.4 19 737.0 4
748.4 20 737.6 5
764.4 21 726. 7 6
748.6 22 743.6 7
748.6 23 744.2 8
711. 5 24 367.5 9
748.8 25 0
10 748.8 26 0
11 682.7 27 377~1 12 750.4 28 651.8 13 746.9 29
'748. 3 14 734.6 30 746.2 15 740.4 31 16 739.1 DAILY UNIT POWER LEVEL FORM INSTRUCTIONS On this form, list the average daily unit power level in MWe-net for each day in the reporting month.
Compute to the nearest whole megawatt.
These figures will be used to plot a graph for each reporting month. Note that by using maximum dependable capacity for the* net electrical rating of the unit, there may be occasions when the daily average power level exceeds the 100% line (or the restricted power level line). In such cases, the average daily unit power output sheet should be footnoted to explain the apparent anomaly.
UNIT Surry Unit No. 1 DATE July 2, 1975 COMP1~ETED BY w. c. Earl DOCKET NO. 50-280 OPERA TING ST A TUS
- l.
REPORTING PERIOD: __ o_o_o_1 __
7_5_0_6_0_1 _______ THROUGH __ 2_4_0_0 ___ 7_5_0_6_3_0 ___ _
HOURS IN REPORTING PERIOD: __
7_2_0 ___ --::-.-":--=---------------------
- 2.
CURRENTLY AUTHORIZED POWER LEVEL (M\\Vth) 2441 MAX. DEPENDABLE CAPACITY (MWe-NET) 788
- 3.
LOWEST POWER LEVEL TO WHICH SPECIFICALLY RESTRICTED (IF ANY) (MWe-NET):
- 4.
REASONS FOR RESTRICTION (IF ANY):
THIS REPORTING PERIOD
- 5.
.HOURS REACTOR WAS CRITICAL.............
- 6.
REACTOR RESER VE SHUTDOWN HOURS.......
- 7.
HOURS GENERA TOR ON LINE...............
- 8.
UNIT RESERVE SHUTDOWN HOURS...........
- 9.
GROSS THERMAL ENERGY GENERATED(MWH).....................
JO.
GROSS ELECTRICAL ENERGY
-GENERATED (MWH).....................
l J.
NET ELECTRICAL ENERGY GENERATED (MWH).............................
- 12.
REACTOR AVAILABILITY FACTOR (1)....*....
- 13.
UNIT AVAILABILITY FACTOR (2)............
- 14.
UNIT CAPACITY FACTOR (3).... -..........
UNIT FORCED OUTAGE RATE (4)............
662.3 0
660.8 0
1,566,410 502,800 477,277 92 91.8 84.1 8.2 YR TO DATE 3428.6 0
3157.8 0
7,448,665 2,435, 770 1._,_3152124 78.9
_.1..2....J_
67.6 5.7 CUMULATIVE TO DATE 14,153 0
132575.3 0
29,504,075*
__2_._163,533 922452477 64.0
- 61. (!
53.1 25.8
- 15.
- 16.
SHUTDOWNS SCHEDULED TO BEGIN IN NEXT 6 MONTHS (STATE TYPE, DATE, AND DURATION Of EACH):
- 17.
- 18.
(!)
(2)
Scheduled refueling October 15 1975.
IF SHUT DOWN AT END Of REPORT PERIOD, ESTIMATED DATE Of STARTUP:-------------
UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION) REPORT THE FOLLOWING:
REACTOR AVAILABILITY FACTOR UNIT AV AILABI L!TY FACTOR INITIAL CRITICALITY INITIAL ELECTRICAL POWER GENERATION COMMERCIAL OPERATION HOURS REACTOR WAS CRITICAL HOURS IN REPORTING PERIOD X)OO HOURS GENERA TOR ON LINE
XIOO HOURS IN REPORTING PERIOD NET ELECTRICAL.POWER GENERATED DATE LAST FORECAST DATE ACHIEVED (3)
UNIT CAPACITY FACTOR MAX. DEPENDABLE CAPACITY (MWe-NET) X HOURS IN REPORTING PERIOD FORCED OUTAGE HOURS
- ....::.:.:..:.==---=.....:~:..::..:::....:c.:..=..-=-=-------~-~----~x100 (4)
UNIT FORCED OUTAGE RATE HOURS GENERA TOR ON LINE+ FORCED OUTAGE HOURS
- Corrected figure-Corrected error carried forwarded since February 1975
TYPE F-FORCED DURATION NO.
DATE S-SCHEDULED (HOURS) 75-17 062475 F
59.2
.... ~ "
SUMMARY
UNIT SHUTDOWNS REPORT MONTH JUNE DOCKET NO. 50-280 UNIT NAME Surry Unit No. 1 DATE July 2, 1975 COMPLETED BY W
- c
- Earl METHOD OF
~HUTTING DOWN REASON (1)
THE REACTOR (2)
CORRECTIVE ACTIONS/COMMENTS A
1 Equipment failure was a packing failure of MOV-RH-1700 resulting in excessive primary coolant leakage.
(1) REASON (2) METHOD A -EQUIPMENT FAILURE (EXPLAIN)
I-MANUAL B MAINT. OR TEST 2-MANUAL C
- REFUELING SCRAM D-REGllLATORY RESTRICTION 3--A UTOMA TIC E--Ol'ERATOR TRAINING AND SCRAM LICENSE EXAMINATION F-ADMINISTRATJVE G-*Ol'ERATIONAL ERROR (EXPLAIN)
H-OTHER (EXPLAIN)
I I
i DOCKET NO. 50-281 UNIT Surry Unit No. 2 DATE July 2, 1975 COMPLETED BY W
- C. Earl AVERAGE DAILY UNIT POWER LEVEL MONTH JUNE AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWe-net)
DAY (MWe-net) 1 0
17 23.2 2
0 18 288.4 3
0 19 544.3 4
0 2.0 701.3 5
0 21 725.5 6
0 22 729.6 7
0 23 751.2 8
0 24 751. 5 9
0 25 744.7 10 0
26 746.1 11 0
27 749.5 12 0
28 752.5 13 0
29
' 754.1 14 0
30 747.7 15 0
31 16 0
DAILY UNIT POWER LEVEL FORM INSTRUCTIONS On this form, list the average daily unit power level in MWe-net for each day in the reporting month.
Compute to the nearest whole megawatt.
These figures will be used to plot a graph for each reporting month. Note that by using maximum dependable capacity for the* net electrical rating of the unit, there may be occasions when the daily average power level exceeds the 100% line (or the restricted power level line). In such cases, the average daily unit power output sheet should be footnoted to explain the apparent anomaly.
Q UNIT Surry Unit No.
DATE July 2, 1975 COMPLETED BY W. c. Earl DOCKET NO. 50-281 OPERATING STATUS
- l.
REPORTING PERIOD: __
o_oo_1 _ _,7,,...50-0_6_0_1 ______ THROUGH _2_4_0_0 __
7_5_0_6_3_0 _____ _
HOURS IN REPORTING PERIOD: __
7_2_0 _____.,-,---------------------
- 2.
CURRENTLY AUTHORIZED POWER LEVEL (MWth) 2441 MAX. DEPENDABLE CAPACITY (MWe-NET) 788
- 3.
LOWEST POWER LEVEL TO WHICH SPECIFICALLY RESTRICTED (IF ANY) (MWe-NET): _________
. 4.
REASONS FOR RESTRICTION (IF ANY):
THIS REPORTING PERIOD
- 5.
. HOURS REACTOR WAS CRITICAL.............
385.4
- 6.
REACTOR RESERVE SHUTDOWN HOURS.......
0
- 7.
HOURS GENERATOR ON LINE...............
317.6
- 8.
UNIT RESERVE SHUTDOWN HOURS...........
0
- 9.
GROSS THERMAL ENERGY CUMULATIVE YR TO DATE TO DATE 3007.1 11,516.1 0
304.3 2881. 2 11~265.4 0
0 2
GENERA TED (MWH).....................
720, 968 6,621,747 24,846,536 IO.
I l.
- 12.
- 13.
I4.
IS.
I6.
I 7.
- 18.
(l)
(2)
GROSS ELECTRICAL ENERGY
-GENERA TED (MWH).............. *..*....
228,827 221732462 821952929 NET ELECTRICAL ENERGY GENERATED (MWH).............................
216,234 2,062,954 7,762,253 69.2 60.7 66.3 59.3 60.3
- 51. 9 4.3 23.9 REACTOR AVAILABILITY FACTOR (1)....*....
UNIT AVAILABILITY FACTOR (2)............
UNIT CAPACITY FACTOR (3)...............
UNIT FORCED OUTAGE RATE (4)............
53.5 44.1 38.1 3.0 SHUTDOWNS SCHEDULED TO BEGIN IN NEXT 6 MONTHS (STATE TYPE, DATE, A.ND DURATION OF EACH):
IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:-------------
UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION) REPORT THE FOLLOWING:
REACTOR AVAILABILITY FACTOR UNIT AVAILABILITY FACTOR INITIAL CRITICALITY INITIAL ELECTRICAL POWER GENERATION COMMERCIAL OPERATION HOURS REACTOR WAS CRITICAL HOURS IN REPORTING PERIOD X.100 HOURS GENERA TOR ON LINE
XIOO HOURS IN REPORTING PERIOD DA TE LAST DA TE FORECAST ACHIEVED (3)
UNIT CAPACITY FACTOR NET ELECTRICAL POWER GENERATED MAX. DEPENDABLE CAPACITY (MWe-NET) X HOURS IN REPORTING PERIOD FORCED OUTAGE HOURS (4)
UNIT FORCED OUTAGE RATE
XlOO HOURS GENERATOR ON LINE+ FORCED OUTAGE HOURS
/
TYPE F*FORCED DURATION NO..
DATE S-SCHEDULED (HOURS) 75-7 042675 s
392.3 75-8 061575 F
3.8 75-9 061675 F
4.0
SUMMARY
UNIT SHUTDOWNS Page.!. of ~
DOCKETNO. _s_o_-2_8_1~~~
UNIT NAME Surry Unit No. i; DATE July 2, 1975 COMPLETED BY W. c. Earl REPORT MONTH _
__::_JU.:...::N~E=-----
METHOD OF
$HUTTING DOWN REASON (1)
THE REACTOR (2)
CORRECTIVE ACTIONS/COMMENTS c
1 Refueling I
G 3
Reactor trip caused by high steam flow with low Tavg resulting from unequal pressure between steam generator and header and rapid header isolation valve opening.
A 3
Malfunction of EHC caused turbine to roll at a high rate as the governor valves opened spiking 1st stage pressure above 15 per cent which tripped turbine.
Turbine trip, caused reactor trip.
(1) REASON (2) METHOD A EQUIPMENT FAILURE (EXPLAIN)
I-MANUAL B MAINT. OR TEST 2-MANUAL C-REFUELING SCRAM D-REGULATORY RESTRICTION 3-,AUTOMATIC E-OPERATOR TRAINING AND SCRAM LICENSE EXAMINATION F-ADMINISTRATIVE G--OPERATIONAL ERROR (EXPLAIN)
H-OTHER (EXPLAIN)
TYPE F-FORCED DURATION NO.
DATE S-SCHEDULED (HOURS) 75-10 061775 F
2.2
- fl-*
~
SUMMARY
UNIT SHUTDOWNS REPORT MONTH JUNE Pagel of l DOCKET NO. ~50~--2_8_1~~~-
UNIT NAME Surry Unit No. 2 '
- DATE July 2, 1975 COMPLETED BY W. c. Earl
~~~~~~~~-
METHOD OF
$HUTTING DOWN REASON (1)
THE REACTOR (2)
CORRECTIVE ACTIONS/COMMENTS A
3 Turbine control valves opened rapidly spiking first stage pressure above 15 per cent tripping turbine.
EH control system mal-function.
'[
(1) REASON (2)_ METHOD A -EQUIPMENT FAILURE (EXPLAIN) 1-MANUAL B-MAINT. OR TEST 2-MANUAL C-REFUELING SCRAM D-REGULATORY RESTRlCTJON 3--AUTOMATIC E-OPERA TOR TRAINING AND SCRAM LICENSE EXAMINATION F-ADMINISTRATIVE G-OPERATIONALERROR (EXPLAIN)
H-OTHER (EXPLAIN)