ML19095A352
| ML19095A352 | |
| Person / Time | |
|---|---|
| Site: | Surry |
| Issue date: | 02/14/1975 |
| From: | Stallings C Virginia Electric & Power Co (VEPCO) |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| Serial No. 404/021974 | |
| Download: ML19095A352 (7) | |
Text
VIRGINIA ELECTRIC.A.ND POWER COMPANY RICHMOND.VIRGINIA 23261 February 14, 1975 Off ice of Plans and Schedule!}'t~~\\;;i;tcr;f flle Cy.
Directorate of Licensing
',~
- United States Nuclear Regulatory Commission Washington, D. C.
20555
Dear Sir:
Serial No. 404/021974 PO&M/JTB:clw Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37 Pursuant to Mr. L. Manning Muntzing's directive of February 19, 1974 requiring that certain operating information be forwarded to you on a monthly basis, the Virginia Electric and Power Company submits the information enclosed herewith for the month of January 1975.
Attachments cc: Mr. Norman C. Moseley, Director Region II 1705
- t. 'f *,
DOCKET NO.
5o-2so UNIT Surry Unit No. 1 DATE 2-3-75 COMPLETED BY W. C. Earl AVERAGE DAILY UNIT POWER LEVEL MONTH __
J_AN_U_AR_Y _____
AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWe-net)
DAY (MWe-net) 1
-o* - - - - -*--- ---*-. - -
-- --- *- - _o 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 0
16 0
DAILY UNIT POWER LEVEL FORM INSTRUCTIONS On this fom1, 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 _2_-_3_-_7_5 ____
COMPLETED BY _w_._c_. _E_a_r_l __ _
DOCKET No._5_0_-_2_8_0 ____
OPERA TING ST A TUS
- l.
REPORTING PERIOD:_o_0_0_1.....,__7_5_o_1_0_1 _______ THROUGH _2_4_0_0_7_5_0_1_3_1 ______
HOURS IN REPORTING PERIOD: ___
7_4_4 __ -.,,-..,......,._-------------------
- 2.
CURRENTLY AUTHORIZED POWER LEVEL (MWth) 2441 MAX. DEPENDABLE CAPACITY (MWe-NET) 7 88
- 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....... *.. ;.. *.
42.2
- 6.
REACTOR RESERVE SHUTDOWN HOURS.......
0
- 7.
HOURS GENERATOR ON LINE...........*...
0
- 8.
UNIT RESER VE SHUTDOWN HOURS...........
0
- 9.
GROSS THERMAL ENERGY GENERATED(MWH)................ : *..*
611
- 10.
GROSS ELECTRICAL ENERGY
-GENERATED (MWH).....................
0
- 11.
NET ELECTRICAL ENERGY GENERATED (MWH).............................
0
- 12.
REACTORAVAILABILITYFACTOR(l)....*....
- 13.
UNIT AVAILABILITY FACTOR (2)............
5.7 0
- 14.
UNIT CAPACITY FACTOR (3)...............
0
- 15.
UNIT FORCED OUTAGE RATE (4)............
0 CUMULATIVE YR TO DATE TO DATE 42.2 10,766.6 0
0 0
10!417.5 0
0 611 22,056,021 0
7,327,763 0
6,930,353 5.7 58.2 0
56.3 0
47.5 0
30.3
- 16.
SHUTDOWNS SCHEDULED TO BEGIN IN NEXT 6 MONTHS (STATE TYPE, DATE, AND DURATION OF EACH):
- 17.
IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: ____________ _
- 18.
UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION) REPORT THE FOLLOWING:
(I)
REACTOR AVAILABILITY FACTOR (2)
UNIT AVAILABILITY FACTOR (3)
UNIT CAPACITY FACTOR (4)
UNIT FORCED OUTAGE RATE INITIAL CRITICALITY INITIAL ELECTRICAL POWER GENERATION COMMERCIAL OPERATION HOURS REACTOR WAS CRITICAL HOURS IN REPORTING PERIOD x 100 HOURS GENERATOR ON LINE
XIOO HOURS IN REPORTING PERIOD NET ELECTRICAL POWER GENERATED DATE LAST DATE FORECAST ACHIEVED MAX. DEPENOABLE CAPACITY (MWe-NET) X HOURS IN REPORTING PERIOD FORCED OUT AGE HOURS
XIOO HOURS GENERATOR ON LINE+ FORCED OUTAGE HOURS
TYPE F-FORCED DURATION NO.
DATE S-SCHEDULED (HOURS) 74-21 102474 s
744.0 (Cl-81 )
SUMMARY
UNIT SHUTDOWNS
' 1.-
DOCKET NO.
50-280 UNIT NAME Surry Unit No. 1 DATE 2-3-75 COMPLETED BY W. C. Earl REPORT MONTH __
J_AN_U_AR_. _Y ___
METHOD OF
$HUTTING DOWN REASON (1)
THE REACTOR (2)
CORRECTIVE ACTIONS/COMMENTS c
3 Unit was down for refueling.
(1) REASON (2) METHOD A -EQUIPMENT FAILURE (EXPLAIN)
I-MANUAL B-MAI NT. OR TEST 2-MANUAL C-REFUELING SCRAM D-REGULATORY RESTRICTION 3-A UTOMA TIC E-OP.ERA TOR TRAINING AND SCRAM LICENSE EXAMINATION F-ADMINISTRATIV.E G-OPERA TIONAL ERROR (EXPLAIN)
H-OTHER (EXPLAIN)
DOCKET NO. 50-281 UNIT Surry Unit No. 2 DATE 2-3-75 COMPLETED BY W. C. Earl AVERAGE DAILY UNIT POWER LEVEL MONTH_J_AN_U_AR_Y ______ _
AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWe-net)
DAY (MWe-net) 1 0
17 676.7 2
0 18 4.2 3
0 19 439*
4 122.2
- 20.
770.6 5
215.3 21 741.4 6
400.4 22 740.6 7
554.2 23 673 8
589.3 24 727. 7 9
664.1 25 754.2 10 764.1 26 764.2 11 762.1 27 76'.3.5 12 756.7 28 763 13 762. 2 29 702.7 14 661.4 30 756.8 15 573 31 759.5 16 758.2 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 ratin_g 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. 2 DATE 2-3-7 5 COMPLETED BY w. c. Earl DOCKET NO. 50-2Bl OPERATING STATUS
- l.
REPORTING PERIOD:
0001 750101 THROUGH __
2---'4-"0_0 __
7_5-'-0_1""""3_1 _____ _
HOURS IN REPORTING PERIOD: _____ 7_4_4 ______________________ _
- 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.............
663.3
- 6.
REACTOR RESERVE SHUTDOWN HOURS.......
0
- 7.
HOURS GENERATOR ON LINE...............
641.4
- 8.
UNIT RESERVE SHUTDOWN HOURS...........
0
- 9.
GROSS THERMAL ENERGY GENERA TED (MWH).....................
1,371,463
- 10.
GROSS ELECTRICAL ENERGY
-GENERA TED (MWH).....................
447,815
- 11.
NET ELECTRICAL ENERGY GENERATED (MWH).............................
424,102 REACTOR AVAILABILITY FACTOR (1).........
89.2*
UNIT AVAILABILITY FACTOR (2)............
86.2 UNIT CAPACITY FACTOR (3)...............
UNIT FORCED OUTAGE RATE (4)............
72.3
- 11. 2 YR TO DATE 663.3 0
641.4 0
1,371,463 447,815 424,102 89.2 86.2 72.3
- 11. 2 CUMULATIVE TO DATE 9,172.3 304.3 9,025.6 0
19,596,252 6,470,282 6,123,401 59.6
- 58. I 50.5 27.9
- 12.
- 13.
- 14.
- 15.
- 16.
SHUTDOWNS SCHEDULED TO BEGIN IN NEXT 6 MONTHS (STATE TYPE, DATE, AND DURATION OF EACH):
Refueling - April, approximately six weeks
- 17.
- 18.
IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:-------------
UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION) REPORT THE FOLLOWING:
(1)
REACTOR A VAlLABILITY FACTOR (2)
UNIT AVAILABILITY FACTOR (3)
UNIT CAPACITY FACTOR (4)
UNIT FORCED OUTAGE RA TE INITIAL CRITICALITY INITIAL ELECTRICAL POWER GENERATION COMMERCIAL OPERATION HOURS REACTOR WAS CRITICAL HOURS IN REPORTING PERIOD x 100 HOURS GENERATOR ON LINE
XIOO HOURS IN REPORTING PERIOD NET ELECTRICAL POWER GENERATED DATE LAST FORECAST DATE ACHIEVED MAX. DEPENDABLE CAPACITY (MWc-NET) X HOURS IN REPORTING PERIOD FORCED OUT AGE HOURS
~x100 HOURS GENERATOR ON LINE+ FORCED OUTAGE HOURS
TYPE F-FORCED DURATION NO.
DATE S-SCHEDULED (HOURS) 74-12 090674 F
79.9 01147 5 F
0 75-1 011775 F
8.0 75-2 01187 5 F
14.6 I
SUMMARY
UNIT SHUTDOWNS DOCKET NO.
50-281 UNIT NAME Surry Unit No. 2 DATE 2-3-75 COMPLETED BY W. c. Earl REPORT MONTH _J_A_NU_AR_Y ___
METHOD OF
~HUTTING QOWN REASON (1)
THE REACTOR (2)
CORRECTIVE ACTIONS/COMMENTS A
2 High turbine vibration due to broken blades in Unit No. 2 L.P. turbine.
B N/A Feedwater regulator valve repair.
A N/A Repair leak in bypass line at "B" main feedwater pump discharge valve.
G 3
Operator error while manually feeding steam generator.
(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-OPERA TOR TRAINING AND SCRAM LICENSE EXAMINATION F-ADMINISTRATIVE G--OPERATIONAL ERROR (EXPLAIN)
H-OTHER (EXPLAIN)
' -