ML20080K289
| ML20080K289 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 01/31/1984 |
| From: | Schroeder B, Scott D COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| 84-130, NUDOCS 8402150362 | |
| Download: ML20080K289 (17) | |
Text
'
1 OPERATING DATA REPORT DOCKET NO. 050-237 DATE Feb. 1, 1984 COMPLETED BY B. A. Schroedce TELEPHONE (815) 942-2920 OPERATlHG STATUS NOTES 1.
Unit Name:
Dresden II 2.
Reporting Period: Janusrv. 1984 3
Licensed Thermal Power (MWt):
?.527 4.
Nameplate Rating (Gross MWe):
828 5
Design Electrical Rating (Net MWe): 794 6.
Maximum Dependable capacity (Gross MWe):
812 7
Maximum Dependable Capacity (Net MWe):
772 8.
if Changes Occur in Capacity Ratings (items 3 Through 7) Since Last Report, Give Reasons:
N/A 9
Power Level to Which Restricted, if Any (Net HWe):
N/A 10.
Reasons For Restrictions, if Any:
N/A This Month Yr-to-Date Cumulativo.
11.
Hours in Reporting Period 744 744 120.264 12.
Number of Hours Reactor Was Critical 744 744
-92.968.5 13.
Reactor Reserve Shutdown Hours 0
0 0
14.
Hours Generator On-Line 722.1 722.:
91,628.1 15 Unit Rese.rve Shutdown Hours 0
0 0
16.
Gross Thermal Energy Generated (MWH) 1.733.202 1,733,202 178,427,838 17.
Gross Electrical Energy Generated (MWH) 567.636 567,636 57,069,835 18.
Net Electrical Energy Generated. (HWil) 542,098 542,098 53.930.364 19 Unit Service Factor 96.06 97.n6 76.19 20.
bnit Availability Factor 97.06 97.06
- 76. 19 21.
Unit Capac!ty Factos (Using MOC Net) 94.38 94.38 58.09 22.
Unit Capacity Factor (Using DER Net) 91.77 91.77 56.48 23 Unit Forced Outage Rate 2.92 2.92 11.60 24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Snubber inspection May 13, 1984 (plus or minus 45 days)
- 25. - If Shut Down At End Of Report Period, Estimated Date of Startup:
N/A R
-. we.m-ngmw,
.-a ww u..,
t OPERATING DATA REPORT DOCKET NO.
056-249 DATE Feb.
1, 1984 t
COMPLETED BY B. A. SchroMer TELEPHONE (g,5) 947_3 773, OPERATING STATUS NOTES 1.
Unit Name:
Dresden IEt
'2.
Reporting Period: January, 1984 3
Licensed Thermal Power (MWt):
2,527 4.
Nameplate Rating (Gross MWe):
828 5
Design Electrical Rating (Net HWe): 794 6.
Maximum Dependable Capacity (Gross MWe): 812 7
Maximum Scpendable Capacity (Net HWe):
773 8.
If Changes Occur in Capacity Ratings (items 3 Through 7) Since Last Report, Give Reasons:
N/A i
l 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 744 744 109.849___
12.
Number of Hours Reactor Was Critical 0
0 82,835g, _
13 Reactor Reserve Shutdown Hours 0
0 0
14.
Hours Generator On-Line 0
0 79,861.1.
15 Unit Reserve Shutdown Hours 0
0 0
16.
Gross Thermal Energy Generated (MWH) 0 0
159.961.098_
17.
Gross Electrical Energy Generated (MWH) 0 0
51.952.919__
18.
Het Electrical Energy Generated (HWit)
-2760
-2760 49.227.824_
19 Unit Service Factor 0
0 72.7
, 20.
Unit Availability Factor 0
0 72.7 21.
Unit Capacity Factor (Using MDC Net) 0 0
57.97 22.
Unit Capacity Factor (Using DER Net) 0 0
56.44
~
Unit Forced Outage Rate 0
0 12.66 23 24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
+
N/A l
- 25. _ If Shut Down At End Of Report Period, Estimated Date of Startup: Mid-March. 1984 e
DOCKET NO. 050-237-UNIT NAME Dresden II UNIT SHUTDOWNS AND POWER REDUCTIONS DATE February.!, 1984 -
COMPLETED BY B. A. Schroeder TELEPHONE (615) 942-2920 REPORT MONTH JANUARY, 1984 METHOD OF LICENSEE CAUSE & CORRECTIVE NO.
DATE TYPEl DURATION REASON 2 SHUTTING EVENT SYSTEM COMPONENT ACTION TO (HOURS)
DOWN REACTOR 3 REPORT'#
CODE 4 CODE 5 PREVENT FICURRENCE The "B" turbine EHC pressure 1
84-1-10 F
21.8 H
I regulator became faulty -
repaired.
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l 1
2 3
4 F:
Forced Reason:
Method:
Exhibit G-Instructions for S:
Scheduled A-Equipment Failure (Explain) 1-Manual Preparation of Data B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee C-Refueling 3-Automatic Scram Event Report (
) File D-Regulatory Restriction 4-Other (Explain)
E-Operator Training & License Examination F-Administrative C-Operational Error H-Other (Explain)
t DOCKET NO. 050-249 UNIT NMIE Dresden III UNIT SHUTDOWNS AND POWER P. EDUCTIONS DATE Februery 1, 1984 s
COMPLETED BY li. A. Schroeder TELEPHONE 7815) 942-2920 REPORT MONTH JANUARY, 1984 METHOD OF LICENSEE CAUSE & CORRECTIVE NO.
DATE TYPEI DURATION RFASON2 SHUTTING EVENT SYSTEM COMPONENT ACTION TO
[
(HOURS)
DOWN REACTOR 3 REPORT #
CODE 4 CODE 5 PREVENT RECURRENCE J
i 8
83-9-30 S
744 C
1 Refueling, ISI and Turbine overhaul outage.
t l
' i i
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l l
l l
1 2
3 4
F:
Forced Reason:
Method:
Exhibit G-Iostructions for S:
Scheduled A-Equipment Failure (Explain) 1-Manual Preparation of Data B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee C-Refueling 3-Automatic Scram Event Repor,.t (
) File D-Regulatory Restriction 4-Other (Explain)
(NUREG-Ol&l)
E-Operator Training & License Examination F-Administrative G-Operational Error H-Other (Explain)
b h.
f AVERAGE DAILY UtilT 20VER LEVEL j
DOCKET NO. 050-237 UlllT II j
DATE Feb.
1, 1984 COMPLETED BY B. A. Schroeder TELEPHONE 815/942-2920 i
i HONTH armtrny _ inn DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL Q
(HWe-Net)
(HVe-Net) 1 1
712 17 746 2
749 18 784 3
787 19 793
[
1 794 20 784 5
791 21 778
~
6 790 22 734 7
793 23 794 8
758 24 737 690 9
25 742 10 7
26 794 11 442
- 7 772 z
12 705 28 745 774 13 29 789
'764 787 14 30 I5 729 33 789 774 16
)
i AVERAGE DAILY UNIT POWER LEVEL l
DOCKET NO. 050-249 UlllT III l
DATE Feb. 1, 1984 l
COMPLETED BY B. A. Schroeder TELEPH0!1E 815/942-2920 H0 lith JANUARY, 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY F0WER LEVEL (MVe-Net)
(HWe-Net)
I o
17 0
2 0
18 0
t 3
19 0
0 4
0 20 0
5 0
21 0
6 0
22 0
0 7
0 23 0
8 0
24 0
9 25 0
10 0
26 0
0 11 0
27 0
12 0
28 13 0
29 0
j 14 0
30 0
15 0
31 0
16 0
DRESDEN UNIT 2 SAFETY RELATED MAINTENANCE - JANUARY, 1984 l
MAI. FUNCTION NATURE OF LER OR OUTAGE EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION l
l l M02-1501-13B rreventive W.R. #28034 N/A N/A Replaced broken light bulb.
EPN # 1501-13B Scram /ECSS Preventive W.R. #31650 N/A N/A Repacked all 3 valves on block assembly.
l l Yarway Valve Block EPN
- LIS2-263-58A U-2 Diesel Preventive W.R. #31389 N/A N/A Dismantled and repaired valve operator.
Generator Of fgas Rad Preventive W.R. #31703 N/A N/A Replaced "A" Offgas monitor with Unit 3 Monidor Ch. A "A" monitor.
EPN #2-1705-3A SRM 23 Retract Preventive W.R. #31497 N/A N/A Replaced lamp with a 30V lamp.
Permit Light RUM CRD Posi-Preventive W.R. #31450 N/A N/a Suspect computer problem -- problem tion Indicator resolved by itself.
U-2 SBLC Tank Preventive W.R. #31180 N/A N/A Repaired broken heat trace.
Pump Suction Heat Trace Torus to Rx Preventive W.R. # 31344 N/A N/A Replaced Versa valve on torus to Rx. Bldg.
vacuum breaker.
Bldg. Vacuum Breaker
- 2-1601-20B, EPN trA02-1601-20B
DRESDEN UNIT 2 SAFETY RELATED MAINTENANCE - JANUARY, 1984 MALFUNCTION NATURE OF LER OR OUTAGE EQUIPMENT MAINTENANCE NUMBER CAUSE RF.SULT CORRECTIVE ACTION
- 2 250V Preventive W.R. #30756 N/A N/A Replaced and rewired "Rl" resistors.
Battery Char-
, ger N/A N/A Replaced card and reset alarms.
SRM #21 Preventive W.R. #31002 N/A N/A Replaced pressure switch.
Target Rock Preventive W.R. #31467 Valve N/A N/A Adjusted limit on frame hoist.
i Frame Mounted Preventive W.R. #30912 Aux. Hoist
- 42 Snubber Preventive W.R. #31464 N/A N/A Moved pipe clamp up to remove binding problem.
"B" Inboard Preventive W.R. #31647 N/A N/A Replaced pressure scal rings.
Feedwater Check, EPN &
2-220-58B Re fuel Grappie Preventive W.R. #29777 N/A N/A l!eplaced brake.
U-2 LPCI Suc-Preventive W.R. #30641 N/A N/A Replaced both auxiliary contacts.
tion Valve EPN #MO-1501-SC N/A N/A Replaced switch assembly.
Scram Dis-Preventive W.R. #23991 charge Volume Level Switch IRM # 13 Preventive W.R. #30192 N/A N/A Replaced relay.
RBM Channel 8 Preventive W.R. #30534 N/A N/A Replaced blown fuse.
Inop.
I DRESDEN UNIT 2 SAFETY RELATED MAINTENANCE - JANUARY, 1984 l
MALFUNCTION NATURE OF LER OR OUTAGE j
EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION Control Rod Preventive W.R. #27942 N/A
{
N/A Disassembled and reassembled CRD.
i l Drives i Spare CRDs Preventive W.R. #28215 N/A N/A Assembled CRDs.
l Drywell Hi Rad Preventive W.R. #30119 N/A N/A Removed and replaced monitor.
)
Monitor Channel B, EPN #2-2419-B LPRM Group II Preventive W.R. #30535 N/A N/A Replaced broken fuse in 20VDC.
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N/A N/A Replaced pressure switch.
902-5 Alarms Preventive W.R. #30385
- 2 Diesel Gen-Preventive W.R. #30435 N/A N/A Performed quarterly inspection and replaced filters per DNP 6600-2.
erator l
Isolation Preventive W.R. #31459 N/A N/A Replaced motor on MO valve -- checked out l
Condenser satisfactorily.
Inlet M02-1301-1, EPN #2-1301-1 Relay 590-102H Preventive W.R. #30941 N/A N/A Investig ated relay for proper operation.
EPN #590-102H Operates satisfactorily.
4 Channel 2 APRM Preventive W.R. #31700 Nf' N/A Repairec defective contact pin in con-nector cable.
1501-3A Valve Preventive W.R. #31628 N/A N/A Corrected valve opening by readjusting lock nut and set screw. Verified settings and limits.
~ -.
DRESDEN UNIT 2 SAFETY RELATED MAINTENANCE - JANUARY, 1984 1
MALFUNCTION NATURE OF LER OR OUTAGE EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION 1
M02-2301-36, Preventive W.R. #28206 N/A N/A Relocated pushbutton station away from EPN #M02-2301-leakage problem.
36 l
l N/A N/A Inspected limit switch for cracks per l
, M0 1501-3B Preventive W.R. #29867 INPO request -- none found.
l MO 1501-3A Preventive W.R. #29868 N/A N/A Inspected limit switch for cracks per INPO request -- none found.
MSIV 2-203-1B, Preventive W.R. #29987 N/A N/A Readjusted limit switch to prevent double indication.
EPN #2-203-1B APRM Channel 1 Preventive W.R. #30659 N/A N/A Investigated APRM spiking problem --
burned " whisker" off per DIP 700-15.
SRM 21 Preventive W.R. #30022 N/A N/A Investigated SRM downscale problem, cleaned monitor connectors and recali-brated.LPRM 40-17A Preventive W.R. #29751 N/A N/A Investigated abnormally high LPRM (GP2) readings. Performed DIP 700-15.
2B RPS M6 Preventive W.R. #29253 N/A N/A Investigated motor thermal relay problem.
Checked for proper relay size and checked all wire connectior.s.
U-2 Local M0 Preventive W.R. #28786 N/A N/A Investigated valve position light indica-Valve Stations tion -- problem repaired.
LPRM Preventive W.R. #29967 N/A N/A Performed I.V. and T.D.R. arms for the listed LPRM's data required for G.E.
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DRESDEN UNIT 3 SAFETY RELATED MAINTENANCE - JANUARY. 1984 E M CTION NATURE OF LER OR OUTAGE EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION Feedwater Preventive W.R. #30807 M/A N/A Replaced check valve and made two hold I
Check Valve tabs.
3-220-62A, EPN #3-220-62A l
057 Snubber Preventive W.R. #30683 N/A N/A Adjusted pipe clamp to 534'8" elevation.
Pipe Clamp, EPN #3-3019A-
)
U8 l
D-3 "A" Stand-Preventive W.R. #31503 N/A N/A Repacked pump.
by Ligoid Control Pump, EPN #3-Il02-A Sus Tie 39-38 Preventive W.R. #31593 N/A N/A Tightened terminal screw on CX7 -- breaker (On Bus 39) closed -- operating ok.
1 U-3 Rx Bldg.
Preventive W.R. #31577 N/A N/A Replaced relay.
l Interlock Doors l
U-3 250V Preventive W.R. #31619 N/A N/A Adjusted pots to make voltages correct.
Battery Adjusted readings on local meter.
j Charger
- 3 250V Bat-Preventive W.R. #30932 N/A N/A Retorqued connectors on cell #101 tery Cell 101
)
i 125V DC Ground Preventive W.R. #31578 N/A N/A Found pinched wire and taped it.
U-3 Bus 39 Preventive W.R. #31639 N/A N/A Cleaned and adjusted motor cutout switch.
480V Breaker Feed From 34-1
DRESDEN UNIT 3 SAFETY RELATED MAINTENANCd - JANUARY, 1984 mal. FUN MION NATURE OF LER OR OUTAGE EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION 1501-26B Preventive W.R. #31336 N/A N/A Adjusted limit switch for proper align-Manual Stop ment.
U-3 SBLC EPN 027851 Preventive W.R. #27851 N/A N/A Replaced squib valve.
3B SBLC Pump Preventive W.R. #30389 N/A N/A Repacked 3B SBLC pump.
Auto Blowdown Preventive W.R. #31388 N/A N/A Recalibrated timer.
Time Delay Relay
- 3 250V Bat-Preventive W.R. #30755 N/A N/A Removed and installed new resistors.
tery Charger U-3 250VDC Preventive W.R. #31372 N/A N/A Replaced circuit board.
Battery Charger HPCI 485 Valve Preventive W.R. #30416 N/A N/A Removed and installed necessary jumpers.
Logic Turbine Step Preventive W.R. #31183 N/A N/A Tightened stud.
Valve 590-124A Closure Valve 3-2301-31-31 Preventive W.R. #31102 N/A N/A Replaced yoke.
Skinner Valve CRD Hatch Preventive W.R. #27831 N/A N/A Opened CRD hatch.
DRESDEN UNIT 2/3 SAFETY RELATED MAINTENANCE - JANUARY,j984 MALFUNCTION NATURE OF LER OR OUTAGE EQUIPMENT-MAINTENANCE NUMBER CAUSE PISULT CORRECTIVE ACTION I! D-#1 Fuel and Preventive W.R. #31778 N/A N/A Reversed couplings.
Canister Tool 2/3. Diesel Preventive U.R. #26931 N/A N/A Replaced 1/2" gate valve.
Generator Cooling Water
- Pump Cooling l Water l
2/3 Diesel Preventive W.R. #25884 N/A N/A Replaced thermostat housing gasket.
l Generator 2/3 Diesel Preventive W.R. #29149 N/A N/A Performed 6 month inspection.
Generator l
SUMMARY
OF OPERATING EXPERIENCE UNIT TWO JANUARY, 1985 01-01 to 01-10 Unit 2 entered the month at a power level of 730 MWe and operated until the 10th when the generator was dirconnected from the grid. Problems developed with the 23 EHC pressure regulator. To repair, it required the generator to be off-line. During control rod insertions to reduce reactor power, a number of steps in the control rod sequence were skipped due to NSO misinterpretation. When the error was discovered, the Shift Engineer was immediately informed and a Qualified Nuclear Engineer (QNE) called in (all rod move-ment terminated). The QNE evaluated the Banked Position Withdrawal Sequence (BPWS) concerns, precondicioning and rod pattern symmetry. He then issued change log instruc-tions to correct the control rod pattern to bring the control rods into compliance with the BPWS rules. A short time later control rod insertions were resumed to attain a
~
Hot Standby condition.
01-10 to 01-31 The 2B EHC pressure regulator was repaired and checked for proper operation. An extensive investigation was also held to determit.e the cause of the control rod insertion incident. The necessary corrective actions included a new operating Order, training sessions for licensed operators and revised procedural information.
j 1he unit was then brought back on-line per procedures.
The unit operated continuously for the remainder of the j
month (with normal power reductions on weekends for surveillances). The unit reached a power level of 836 MWe with a capacity factor of 91.45% and an availability of 97.07%.
i
SUMMARY
OF OPERATING EXPERIENCE UNIT THREE 1
JANUARY, 1984 01-01 to 01-31 Unit 3 was-shutdown for the entire month for its scheduled refueling and equipment overhaul outage.
Major work includes:
1)
H.P. Turbine and Main Generator overhaul
- 2) Inservice Inspection of Welds
- 3) CRD removal and replacement
- 4) LPRM removal and replacement
T Commonweilth Edicon e
'h Drzsd;n Nuctnr PowIr Stition O
R.R. # 1 Morris, filinoic 60450 Telephone 815/942-2920 j
February 1, 1984 DJS LTR:
84-130 Director, Office of Inspection and Enforcement United States Nuclear Regulatory Commission Washington, DC 20555 Attention: Document Control Desk
Dear Sir:
Enclosed, please find Dresden Station's operating data for last month. This information is supplied to your office per the instructions set forth in Regulatory Guide 1.16.
Sincerely, 1
D J. Scott Station Superintendent Dresden Nuclear Power Station DJS:BAE:hjb Enclosure cc: Region III, Regulatory Operations, U.S. NRC Chief, Division Nuclear Safety, State of Illinois O.S. NRC, Document Management Branch Nuclear Licensing Administrator Nuc. Sta. Div. Vice Pres.
Manager, Tech. Serv. Nuc. Sta.
Tech. Staff EA On-Site NRC Inspector Sta. Nuc. Eng. Dept.
Comptroller's Office INPO Records Center i
PIP Coordinator l
File /NRC Op. Data File / Numerical 9>k 4
3s
.