ML20236C704
| ML20236C704 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 02/28/1989 |
| From: | Cartwright W, Tillack B VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 89-172, NUDOCS 8903220283 | |
| Download: ML20236C704 (17) | |
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NORTH ANNA POWER STATION,
. MONTHLY OPERATING REPORT
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OPERATING DATA REPORT I
DOCKET No.
50-338 DATE 03-01-89
_.._1__
COMPLETED BY,, Bob Tillack TELEPHONE. (703) 894-5151 X2632 OPERATING STATUS 1.
Unit Name:
North Anna 1
-2.
Reporting Period:
February 1989 3.
Licensed Thermal Power (MWt):
2893 4.
Nameplate Rating (Gross MWe):
947 5.
Design Electrical Rating (Net MWe):
907 6.
Maximum Dependable Capacity (Gross MWe):
963 7.
Maximum Dependable Capacity (Net MWe):
915 8.
If Changes Occur in Capacity Ratings (Items No. 3 thru 7) Since Last Report, I
Give Reasons:
1 N/A 9.
Power Level To Which Restricted, If Any (Net MWe):
N/A
{
- 10. Reasons For Restrictions, If Any:
N/A This Month Yr.-to-Date Cumulative 11.
Hours In Reporting Period 672 1,416 93,708 j
12.
Number of Hours Reactor Was Critical 590.1 1,334.1 67,5S3.5 13.
Reactor Reserve Shutdown Hours 39 39 6,496.3 14.
Hours Generator On-Line 590.1 1,334.1 64,845 6 15.
Unit Reserve Shutdown Hours 0
0 li""~
f 16.
Gross Thermal Energy Generated (MWH) 1,355,284 3,454,653 171,614,646 l
17.
Gross Electrical Energy Generated (MWE) 448,982 1,144,658 56,319,007 l
18.
Net Electrical Energy Generated (MWH) 422,958 1,084,413 53,276,305 j
19.
Unit Service Factor 88 94.2 69.2 l
20.
Unit Availability Factor 88 94.2 69.2 21.
Unit Capacity Factor (Using MDC Net) 68.8 83.7 63.8 22.
Unit Capacity Factor (Using DER Net) 69.4 84.4 62.7 i
l 23.
Unit Forced Outage Rate 12.1 5.8 14.4 l
24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Unit 1 Scheduled Refueling /10 Year ISI, March 4, 1989, 88 days 25.
If Shut Down At End Of Report Period, Estimated Date of Startup:
7 July, 1989 l
26.
Units In Test Status (Prior to Commercial Operation):
Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION i
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'f, e-AVERAGE DAILY UNIT POWER LEVEL 1
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DOCKET NO.
50-338 1
UNIT NA-1 j
DATE 03-01-89 l
COMPLETED BY Bob Tillack TELEPHONE 703-894-5151X2632 MONTH February 1989 1
DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 807 17 237 2
801 18 554 3
795 19 721 l
4 789 20 716 5
782 21 708 l
6 781 22 705 7
773 23 700 8
766 24 681 9
760 25 398 10 752 26 0
11 749 27 0
4 12 744 28 0
13 739 29 14 733 30 15 729 31 16 704 I
l INSTRUCTIONS On this format, list the average daily unit power level in FNe-Net for each day in the reporting month.
Compute to the nearest whole megawatt.
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Page 1
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UNIT SHUTDOWN AND POWER REDUCTIONS EXPLANATION SHEET DOCKET NO.
50-338 REPORT MONTH February UNIT NAME NA-1 YEAR 1989 DATE 03-01-89 COMPLETED BY Bob Tillack 89-01 1)
February 16, 1989, at 1310 - Indications of increased primary leakage were observed and 1-AP-16,
" Increasing Primary Plant Leakage," was entered.
Identified RCS leakage was determined to be 10.65 gpm and the Action Statement of T.S.
3.4.6.2 was entered at 1441.
Charging and letdown were secured and excess letdown was placed in service. A leakrate was performed and identified leakage was determined to be 9.4 gpm. The Action Statement was cleared at 1645.
Containment entries to collect valve leak-off temperatures were made. Using this information, it was determined that 1-RC-63 was probably the source of the leakage.
1-RC-63 is the "B"
loop RTD line common return isolation valve. At 2110, a rampdown was commenced.
The unit was stabilized at 30% power at 0152. A containment entry to backseat 1-RC-63 determined the valve could not be placed any further on its backseat. Mechanics were not able to go below the grating to adjust packing.
2)
February 17, 1989, at 0713, Identified RCS leakage was determined to be 10.69 gpm.
The Action Statement was again entered. The EPIPs were entered and a Notification of Unusual Event was declared at 1147 due to the high RCS identified leakage.
At 1149, the packing of 1-RC-63 was adjusted and the valve placed further on its backseat after the grating above the valve had been lifted. A RCS leakrate was performed and RCS identified leakage was 3.32 gpm.
The Action Statement of T.S.3.4.6.2 and the Notification of Unusual Event were cleared at 1404.
89-02 February 25, 1989, at 1407 a Reactor trip occurred on "C" S/G low level with a steam flow feed flow mismatch caused by the "C" MFRV failing closed. An airline on the valve had blown off.
As a result of the trip, a tube in "C" S/G developed a leak of approximately 77 gpm.
An ALERT was declared at 1525, and the unit was cooled down and depressurized. During the cooldown "C" RCP was secured due to high vibs. The cause is unknown.
In addition, N-32 failed. The unit entered Mode 4 at 1833 and the ALERT was secured at 2220.
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NORTH ANNA POWER STATION f
UNIT NO.
1 MONTH February
SUMMARY
OF OPERATING EXPERIENCE Listed below in chronological sequence is a summary of operating experiences for this month which required load reductions.or resulted in significant-non-load related incidents.
DATE TIME DATA-February 1,:1989 0000 Began mouth with Unit at 88%' power, 860 MW.
Operating IAW 1-TOP-2.2, Temperature / Power Coastdown.
February 07, 1989' 1140 Ramped down unit to 85% power, 817 MW, to match Tave/ Tref.
February 16, 1989 1310 Placed 45 gpm letdown orifice in service, secure 60 gpm orifice. Noted increase in RCS leakrate.
1441 Identified RCS leakrate is 10.65 gpm.
y Entered action statement.
1456 Secured charging and letdown 1502 Placed excess letdown in service 1645 Identified RCS leakrate is 9.4 gpm.
Cleared
)
action statement.
1946 Personnel entered containment to investigate leakage.
Suspect leakage from "B" loop RTD line common return isolation valve (1-RC-63).
2110 Commenced Unit ramp down to allow for reduced radiation exposure for personnel i
I entering containment.
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DATE TIME-DATA h
LFebruary?17' 1989.
0152-
' Holding'unitLat.30% Power, 260 MW.
0425
' Personnel enter containment 0510 Personne1' exit containment. confirm packing leak from.1-RC-63;-
10713 Identified RCS leakrate is 10.69 gpm,
- entered action statement.
0916'
' Personnel entered' containment.to work
.1-RC-63 1029
'All personnel exit containment.- ' Unable to adjust packing on 1-RC-63.due to very-inaccessible location of valve.
1130 Personnel enter containment.-
1149-
. Personnel, adjust packing on 1-RC-63 substantial decrease in leakage noted.
1147 Notification of Unusual. Event declared i
1155 All personnel ex'it containment.
~
1404 Identified RCS'leakrate 3.32 gpm. ' Cleared
. Notification of. Unusual' Event and action-statement., Unit holding at-30% power for Chemistry 1 hold..
1 February 18 -1989 0430 Cleared Chemistry hold.
0521 Commenced ramping up unit to 80% Power.
I 1300 Unit 6tabilized at;80% Power, 771MW.
February 23, 1989 2300 Ramped down unit to 77% Power, 731 MW to match Tave/ Tref.
February 25, 1989 1406 1-FW-FCV-1498, "C" Main Feedwater Regulating j
Valve failed closed due to the failure of a j
fitting in the-air supply line.
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4 DATE TIME DATA 1
l February 25, 1989 1407.
Reactor Trip on "C" Steam Generator Low Level with Steam Flow Feedwater Flow mismatch.
Control Room Operator backed up automatic reactor trip with manual Reactor Trip.
Auxiliary feedwater pumps received automatic start signal and steam generator blowdown isolated on "C" steam Generator Low-Low
- level, t
"A" and "B" Steam Generator Low-Low Level.
1408 Main Steam line radiation alarm received by the SPDS system and cleared.
Subsequent to the SPDS alarm (unable to establish the i
exact time) a control board main steam line radiation alert alarm was received, acknowledged and cleared. The U1 SR0 l
checked all main steam line radiation monitors and normal indications were noted l
on all steam lines.
[
l 1411 Secured Auxiliary feedwater flow to all steam generators.
{
pumps running on recirc.) Steam generators j
being fed using the Main Feedwater Pumps.
I Letdown isolated automatically.
1414 "B" Steam Generator Low-Low level cleared and letdown restored.
1417 Control operator noticed that RCS pressure was not increasing as fast as expected and l
more charging flow than expected was needed I
to restore pressurizer level. One charging l
pump sufficient to restore pressurizer level l
to 20%.
1425 Source range neutron detectors manually l
re-instated due to under compensation of I
intermediate range detectors. N-32 failed to indicate when re-instated.
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DATE TIME DATA February 25, 1989 1426 Air ejector radiation monitor alarn:s Hi and i
Hi-Hi.
Indication swinging erratically.
1-AP-5.1, " Unit 1 Radiation Monitoring i
System," entered. Health Physics directed to sample air ejector' exhaust.
Chemistry directed to sample Steam generator blowdown.
Shift Technical Advisor checked other radiation monitors for indications of.
primary to secondary leakage.
Blowdown radiation monitors did not indicate an increase in activity since blowdown was isolated. N-16 radiation monitors did not indicate an increase in activity since the reactor has tripped.
"C" main steam line radiation monitor showed slight increase in activity.
(Indicated approximately 0.15 mR/hr, normal-indication approximately 0.04 mR/hr.
"A" and "B" main steamlines indicated 0.02mR/hr.)
i Air ejector discharge verified to swap to containment on the hi-hi radiation alarm.
(When Hi radiation alarm cleared, radiation monitor hi-hi alarm was reset and air ejector, discharge swapped back to the atmosphere.
This sequence of actions was repeated numerous times until air ejector discharge was manually diverted to containment at 1511. The time the air ejector was discharging to the atmosphere is estimated have been less than ten minutes.)
1-AP-24.1, "Large Steam Generator Tube Leak requiring immediate and rapid unit shutdown," was consulted.
1427 Primary system response indicated a loss of inventory of approximately 50 gpm.
Suspected "C" Steam generator cause of leakage based on air ejector radiation monitor and "C" Main steam line radiation monitor indications.
"C" steam generator level trend did not support a positive diagnosis at this time. An increase in containment pumping frequency was also noted.
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D5TE TIME DATA i
"C" steam generator low-low level cleared.
Air ejector radiation monitor. exhaust i
sampling hindered by water in lines.
l 1432 Noticed TV-BD-100F, "C" steam generator outside containment isolation valve was open.
It should have been closed. Valve could not be closcd manually.
TV-BD-100E, i
"C" steam generator inside containment isolation valve, verified closed.
1440 "A" Steam generator Low-low level cleared.
Steam driven auxiliary feedwater pump secured.
(1-MS-TV-112A and B closed).
'. Main feedwater regulating valve manual i
isolation valves closed.
l Blowdown trip valves opened, sampling commenced.
(Blowdown flow to the blowdown tank had been manual 1y isolated.)
f Letdown flow reduced by placing a lower capacity flow orifice in service to decrease i
charging flow.
1 1442 "A" and "B" auxiliary feedwater pumps secured and returned to automatic.
1443 High Radiation alarm locked in on RM-RMS-160, " Containment Gaseous Radiation Monitor." AP-5.1 entered.
1 1445 Closed "C" feedwater regulating valve bypass valve and its manual isolation valve.
1448 High radiation alarm received and cleared on RM-VG-103, "A" stack radiation monitor.
l 1
1450 "C" Steam generator level trend constant.
)
Control room received information that l
personnel in Auxiliary Building were being delayed in exiting due to slight gaseous contamination.
Extensive walkdown of the Auxiliary Building was commenced. Auxiliary Building parameters had been monitored and did not show signs of a leak.
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l DATE' TIME DATA February 25, 1989 1506 "C" steam generator blowdown radiation monitor high/high alarm received.
1511 Letdown was secured in an attempt to isolated possible leak paths.
"C" Steam generator level observed to be decreasing.
Control Room received information that personnel exiting Security Building were being delayed in exiting due to slight gaseous contamination.
Air ejector discharge manually diverted to containment due to continued erratic indication.
1516 Commenced emergency boration IAW 1-AP-24.1.
1517 1-MS-95, "C" steam generator steam supply to the Steam Driven Auxiliary feedwater pump, manually isolated.
1520 Chemistry reports "C" steam generator blowdown sample high activity.
"C" steam generator positively identified as the source of leakage.
1521 Health Physics reports contact reading from "C" Main steam trip valve of 5 mR/hr.
Reading day before was 0.02 mR/hr.
1525 Leakage estimated to be approximately 65 gpm.
Station Emergency Manager declared an ALERT based on reactor coolant system leak of greater than 50 gpm.
(This was a conservative action because the EPIPs required an ALERT to be declared when reactor coolant system leakage greater than 50 gpm and more than one (1) charging pump needed to maintain pressurizer level.)
1526 Reactor Coolant system cooldown commenced in IAW 1-AP-24.1.
1531 Charging pump suction manually swapped to RWST from VCT.
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DATE TIME.
DATA February 25, 1989
'1544
. With. reactor coolantLtemperature at b
approximately 520 degrees F,' Shift Supervisor evaluated effects ofLcooling-down:
with "C" steam: generator. main' steam'tripL
- ; ou valve-(1-MS-TV-101C) open. Decision made to close valve >andfcontinue cooldown..
1550 Started a;second charging pump to keep up with inventory reduction due to'cooldown.
1600 Started Aux Feedwater-pumpscin recirculation, in the anticipation of loss of main:
feedwater ("C" steam generator level at 72%.
'.'C" steam generator'-level' ' started.' to slowly;.
decrease.as pressure'in reactor coolant; system was reduced to below steam generator pressure.
Entered 1-ES-3.li,-Post-SGTR Cooldown using
. backfill.
-j
'1609 Secured second charging pump.-. Pump no
' longer needed to' maintain pressurizer level.
1613 Letdown restored.
i 1619 Secured emergency boration.
1631 Secured Auxiliary-Feedwater pumps.
l 1833 Unit entered Mode 4.
2143 Placed RHR system in service.
2212 Unit entered Mode 5.
2220.
ALERT terminated February 28, 1989 2400 Ended month with Unit shutdown in Mode 5.
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OPERATING DATA REPORT DOCKET No. 50-339 DATE 03-01-89 COMPLETED BY Bob Tillack TELEPHONE (703) 894-5151 X2632 OPERATING STATUS 1.
Unit Name:
North Anua 2 2.
Reporting Period:
February 1989 3.
Licensed Thermal Power (MWt):
2893 4.
Nameplate Rating (Gross MWe):
947 5.
Design Electrical Rating (Net MWe):
907 6.
Maximum Dependable Capacity (Groes MWe):
963 7.
Maximum Dependable Capacity (Net MWe):
915 8.
If Changes Occur in Capacity Ratings (Items No. 3 thru 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:
N/A This Month Yr.-to-Date Cumulative 11.
Hours In Reporting Period 672 1,416 71,976
~~~~
12.
Number of Hours Reactor Was Critical 460.5 1,204.5 58,407.7 13.
Reactor Reserve Shutdown Hours 73.1 73.1 5,775.2 14, Houre Generator On-Line 459.4 1,203.4 57,567.6 15.
Unit Reserve Shutdown Hours 0
0 0
16.
Gross Thermal Energy Generated (MWH) 887.300 2,569,002 151,910,001 17.
Gross Electrical Energy Generated (MWH) 289,973 851,670 49,643,299 18.
Net Electrical Energy Generated (MWH) 270,478 799,808 47,742,131 19.
Unit Service Factor 68.4 85.0 80.0 20.
Unit Availability Factor 68.4 85.0 80.0 74.0 21.
Unit Capacity Factor (Using MDC Net) 44.0 61.7 22.
Unit Capacity Factor (Using DER Net) 44.4 62.2 73.1 0
7.8 23.
Unit Forced Outage Rate 0 _
24.
S'autdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Refueling Outage, 02-20-89, 62 days 25.
If Shut Down At End Of Report Period, Estimated Date of Startup:
04-29-89 26.
Units In Test Status (Prior to Commercial Operation):
Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION
+.
t AVERAGE DAILY UNIT POWER LEVEL s
DOCKET NO.
50-339 UNIT NA-2 DATE 03-01-89 COMPLETED BY Bob Tillack
)
TELEPHONE 703-894-5151X2632 MONTH February 1989 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 649 17 542 2
646 18 536 3
644 19 517 4
636 20 9
5 623 21 0
6 622 22 0
7 613 23 0
8 608 24 0
9 602 25 0
26 0
10 599 11 591 27 0
12 587 28 0
13 582 29 14 566 30 15 550 31 16 547 INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month.
Compute to the nearest whole megawatt.
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Page' 1 of 1
' UNIT SHUTDOWN AND POWER REDUCTIONS-EXPLANATION SHEET DOCKET NO.
50-339 REPORT MONTH
' February UNIT NAME NA-2' p
YEAR 1989 DATE
'03-01-89 l
COMPLETED BY Bob Tillack i
89-01 01)
February 20, 1989, Unit.Rampdown for refueling Outage, commenced at 2153.
Unit taken off line and entered Mode 2.
0325.
at Entered Mode 3 at 0428.
February 21, 1989, at 0450, Unit
.}
entered Mode 4 and on February 22, 1989, at 0535, entered Mode 5.
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~ VINGINIA ELECTHIC AND PowEH COMPANY RICIIMOND,VINGINIA 20 261 W. H.CA MTwMIGIIT Vsca Passiomrr Nocs. mas March 14, 1989 U.S. Nuclear Regulatory Commission Serial No.89-172 Attention:
Document Control-Desk N0/JMJ:jmj i
Washington, D.C.
20555 Docket Nos.
50-338 50-339 License Nos. NPF-4 NPF-7 i
Gentlemen:
I
' VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNITS 1 AND 2 MONTHLY OPERATING REPORI i
Enclosed is the Monthly Operating Report for North Anna Power Station Units 1 and 2 for the month of February 1989.
Very trul y r
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W. R. Cartwr ght Enclosures cc:
U.S. Nuclear Regulatory Commission 101 Marietta Street, NW Suite 2900 Atlanta, GA 30323 Mr. J. L. Caldwell NRC Senior Resident Inspector North Anna Power Station i
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NORTH' ANNA' POWER STATION UNIT NO.
2 MONTH February
SUMMARY
OF OPERATING EXPERIENCE j
l Listed below in chronological sequence is a summary _of operating experiences for this month which required load reductions or resulted.in significant non-load related incidents.
DATE TIME DATA
. February 01, 1989 0000 Began month with Unit at 71.7% Power, 693
)
MW.
Operating IAW 2-TOP-2.2, Temperature / Power Coastdown.
' February 04, 1989 1745 Ramped down Unit to 69% Power,'669 MW, to match Tave and Tref.
February-19', 1989 2153 Commenced Unit shutdown for scheduled refueling outage.
February 20, 1989 0325 Unit off line.
Entered Mode 2.
0412 Tripped Main turbine.
e t
0422 Commenced RX shutdown s
0428 RX shutdown entered Mode 3 February 21, 1889 0450 Entered Mode 4 February 22, 1989 0535 Entered Mode 5.
February 28, 1989 2400 Ended Month with Unit shutdcwn in Mode 5.
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