ML20054M104
| ML20054M104 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 06/09/1982 |
| From: | Dupree D, Eddings M, Wallen P TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20054M098 | List: |
| References | |
| NUDOCS 8207090253 | |
| Download: ML20054M104 (16) | |
Text
{{#Wiki_filter:p: I, . TENNESSEE VALLEY AUTHORITY DIVISION OF NUCLEAR POWER SEQUOYAH NUCLEAR PLANT MONTHLY OPERATING REPORT MAY 1, 1982 - MAY 31, 1982 UNIT 1 DOCKET NUMBER 50-327 LICENSE NUMBER DPR-77 UNIT 2 DOCKET NUMBER 50-328-t LICENSE NUMBER DPR-79 4 Submitted By: . . 3-- - Power Plant Superintendent I w I 8207090253 820609 PDR ADOCK 05000327 R PDR l
TABLE OF CONTENTS 1 Operations Summary . . . . . . . . . . . . . . . .. . . . . . . . . . . . 1-7 Significant Operational Events . . . . . . . . . . . . . . . .. . . . . . 7 PORV's and Safety Valves Summary . . . . . . . . . . . . . . . . . . . . 7-9 Licensee Events and Special Reports . . . . . . . . . . . . . . . . . . . 9 Offsite Dose Calculation Manual Changes . . . . . . . . . . . . . . . . . Operating Data
. 10-12 Unit 1 . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
13-15 Unit 2 . . . . . . . . . . . .. . . . . . . . . . . . .. . . . . . 16 Plant Maintenance Summary . . . . . . . . . . . . . . . . . . . . . . .
. . . . .. . . . . . . . 16-17 Field Services Maintenance Summary . . . .
. 18-22 Appendix A . ..............................
i 1 I
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Operations Summsry May, 1982 The following summary describes the significant operational activities for the month of May. In support of this summary, a chronological log of significant events is included in this report. Unit 1 Unit I was critical for 744 hours, produced 858,410 MWil (gross) with 3.40 percent station service use resulting in an average hourly gross load of 1,153,777 KW during the month. The net heat rate for the month was 10,400 BTU /KWii. There are 92.86 full power days estimated remaining until the end of cycle 1 fuel. With a capacity factor of 85 percent the target EOC exposure would be reached September 17, 1982. The capacity factor for the month was 99.2 percent. There were no reactor scrams, no manual shutdown, and one power re-duction during May. Unit 2 Unit 2 was critical for 335.6 hours, produced 316,440 MWH (gross) with 6.80 percent station service use, resulting in an average hourly gross load of 962,701 kW during the month. The net heat rate for the month was 10,960 BTU /KWH. There are 330.37 full power days estimated remaining until the end of cycle 1 fuel. With a capacity factor of 85 percent the target EOC exposure would be reached June 23, 1983. The capacity factor for the month was 36.0 percent. There were three reactor scrams, one manual shutdown, and four power reductions during May. Significant Operational Events Unit 1 Date Time Event 05/01/82 0001 Reactor in mode 1 at 100% power pro-ducing 1150 MWe. 05/26/82 2128 Reactor in mode 1 at 100% power pro-ducing 1150 MWe. Began a load reduction to replace a solenoid on 1A MFPT stop valve. i Significant Operational Events (Continued) Unit 1 Date Time Event 05/27/82 0030 Reactor at 70% power, 1A MFPT off for solenoid replacement on the stop valve. 0415 1A MFPT back in service, increasing reactor power to 100%. 0645 Reactor in mode 1 at 100% power pro-ducing 1150 MWe. 05/31/82 2359 Reactor in mode 1 at 100% power pro-ducing 1150 MWe. Unit 2 05/01/82 0001 Reactor in mode 1 at 33% power pro-ducing 320 MWe. Holding power level until secondary chemistry comes into specification. 0435 Began reducing reactor power to repair the #7 heater drain tank level controller. 0500 Reactor at 25% power producing 244 MWe. 0605 Began increasing reactor power back to 30%. Repairs complete on the #7 heater drain tank level controller. 0620 Reactor at 30% power producing 323 MWe. 1429 Began power ascension. 1930 Reactor at 69% power producing 780 MWe. Began reducing to 65% power to remove 2A MFPT from service to repair a leak on the injection water line. 2045 2A MFPT removed from service. 2327 2A MFPT returned to service. t
Significant Operational Events (Continued) Unit 2 Date Time Event 05/02/82 0145 Began power ascension. 1248 Reactor in mode 1 at 100% power producing 1132 MWe. 05/03/82 1134 Had an over power AT runback. Ranback 0.5% power loop 1 and 3. 1400 Began reducing power to 20% to add oil to reactor coolant pump #2. 1653 Reactor holding 24% power producing 256 MWe. 1805 Began power ascension. 05/04/82 0359 Reactor at 100% power producing 1130 MWe. 1645 Began load reduction to replace a blown manway gasket on #3 heater drain tank. 1755 Reactor at 20% power producing 210 MWe. 2120 Began power ascension. 05/05/82 0630 Reactor at 100% power producing 1130 MWe. 1529 While working on 2A MFPT vibration i pickup a thrust bearing wear alarm tripped the MFPT. 2B MFPT was unable to come up to speed fast I enough to maintain proper feedwater i flow, therefore, the reactor tripped on #2 steam generator Lo-Lo level. 1704 Reactor taken critical. 1806 The unit was tied on line. 1900 Reactor at 30% power producing 285 MWe and holding for secondary chemistry. Significant Operational Events j m (Continued) _ 2 Unit 2 Z A Date Time Event C5/06/82 0218 Began power ascension 0630 Reactor at 98% power producing 1136 m ::Egi tNc. n
-A 05/08/82 1104 Had a 10% load drop for feedwater -
pump performance data. Reactor at ---- , 92% power producing 1104 MWe. __l--- 1117 Reactor at 100% power. W--- ,. 05/13/82 1212 Reactor tripped from 100% power due _sammme to the turbine tripping because of 2=== low auto oil pressure. -gEEEEE 1452 Reactor critical. '==M=E M 1601 Unit tied on line. 2-fi[ 1800 Reactor at 30% power producing 280 9 g MWe and holding for chemistry. 4 05/14/82 0720 Began power ascension. --
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1500 Reactor at 98% power producing 1127 '- tNe. .B
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2308 Manual turbine trip for Start-Up ------- Test 9.4A, thus the reactor tripped. 05/15/82 0120 Began cooling down the reactor lesses! coolant system. Ice weighing outage -- began. N 0603 Reactor entered mode 4. -- 5555 C -- 1302 Reactor entered mode 5. _===- m 05/20/82 2300 Ice weighing complete. -
"""5" Wm 05/28/82 0910 Began heat-up. ---((]
05/31/82 1905 Reactor taken critical. M 2359 Reactor in mode 2 at 1% power.
PORV's and Safety Valves Summary No PORV's or safety valves were challenged during the month. Licensee Events and Special Reports The following Licensee Event Reports (LER's) were sent during May 1982, to the Assistant Director of Nuclear Power (Operations) for reporting to the Nuclear Regulatory Commission. Unit 1 LER SUBJECT SQRO-50-327/82048 AFW automatic control valve 1-PCV-3-132 failed to open on demand due to a faulty soldered con-nection and again due to blocked oil passages to the servo valves. SQR0-50-327/82050 Diesel generator IA-A inoperable due to a short in the annunciator horn caused the power fuses to blow in the control circuit. SQR0-50-327/82051 A design error made the containment ventilation isolation system inoperable due to the loss of its automatic isolation capabilities following reset signal with no high radiation signal being cleared. SQR0-50-327/82053 Vital battery bank II inoperable due to cell 4 connection resistance found > 150 micro ohms caused by a loose bolted connection. SQRO-50-327/82054 Steam generator blowdown containment isolation valve 1-FCV-1-25 would not reopen after isola-tion due to a ruptured diaphragm caused by normal wear. SQR0-50-327/82055 Demand position indicator control bank A group 2 and bank C group 2 step counters inoperable due to faulty step counters. Bank A step counter found dirty and bank C step counter found to have faulty circuit boards due to voltage spikes. SQRO-50-327/82056 AFW control valve 1-LCV-3-175 failed to open during surveillance test due to a broken micro switch on pressure switch 1-PS-3-165E. l l 1 1
I OPERATING DATA REPORT DOCKET NO. 50-327 { DATE June 3, 1982
- COMPLETED BY M. Eddinns
! TELEPHONE (615) 751-0343 OPERATING STATUS
- 1. Unit-Name: Sequoyah One Notes
- 2. Reporting Period: May 1982
; 3. Licensed Thermal Power (MWt): 3411 j 4. Nameplate Rating (Gross MWe): 1220.58 1 5. Design Electrical Rating (Net MWe): 1148 I 6. Maximum Dependable Capacity (Gross MWe): 1163
- 7. Maximum Dependable Capacity (Net MWe): 1128
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
- 9. Power Level To Which Restricted, If Any (Net MWe):
j 10. Reasons For Restrictions, If Any: I i l This Month Yr-to-Date Cumulative i
! 11. Hours in Reporting Period 744 3,623 8,040
- 12. Number of Hours Reactor Was Critical 744 2,308 5,109.3 l
, 13. Reactor Reserve Shutdown Hours 0 0 0
- 14. Hours Generator On-Line 744 2,206 4,896.4 l
- 15. Unit Reserve Shutdown Hours 0 0 0 l ~
- 16. Gross Thermal Energy Generated (MWH) 2,519,021 7,039,654 15,104,608 l 17. Gross Electrical Energy Generated (MWH) 858,410 2,385,390 5,031,340
- 18. Net Electrical Energy Generated (MWH) 829,236 2,277,556 4,804,581 j 19. Unit Service Factor 100 60.9 60.9
- 20. Unit Availability Factor 100 60.9 60.9
- 21. Unit Capacity Factor (Using MDC Net) 98.8 55.7 53.0
- 22. Unit Capacity Factor (Using DER Net) 97.1 54.8 52.0
- 23. Unit Forced Outage Rate 0 29.8 24.1
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Refueling / Modification Outage September 19, 1982 (Scheduled) 6 Months
- 25. If Shut Down At End Of Report Period, Estimated Date of Startup:
- 26. Units In Test Status (Prior to Commercial Operation):
Forecast Achieved INITIAL CRITICALITY 7-4-80 7-5-80 INITIAL ELECTRICITY 8-21-80 7-22-80 COMMERCIAL OPERATION 7-1-81 7-1-81 (9/77) t i
Licensee Events and pecial Reports Unit 2 LER SUBJECT SQRO-50-328/82052 Ice condenser intermediate deck doors under AHU 9B were frozen closed due to water dripping from drain pan after ice built up caused by unlevel drain pan. SQRO-50-327/82057 Steam generator narrow range level indicator 2-LI-3-107 was inoperable due to loss of power to instrument loop caused by improperly installed fuse. SQRO-50-328/82058 Diesel generator 2A-A tripped on both crankcase overpressure switches prior to reaching 900 RPM due to improper latching of reset button. Special Reports There were no special reports sent during the month of May. Offsite Dose Calculation Manual Changes There were no changen to the Sequoyah Nuclear Plant ODCM during the month of May. i I i l l l l I i _______ __ __ _,.-__- ..._ l
taig- - - - - - - - - :unilf, s l#2 ] COMPLETED BY 't Eddincs REPORT MD fli '!-y_ _!? _2___ TELEPHONE ___ g j_;jl_ g i_ _ _ _ _ l p-e
. r c. "f __ 3 T.i c c: ice . E Cause & Corrective
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i 1 x ! ' o s / S' F -- A i % i nt enance 'n lA % infeed Pump i u r F i :w H [ iip E ] ] \, t - I "L 1 l l , 1 2 3 4 F: Forced Reason. Jethod: E.< h i b i t G-Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram. Ent ry Sheets for Licensee C-Refueling 3-Automatic Scram. Event Report ( LER 'i File (NUREG-D-Regulatory Restriction 4-Cont. of Existing 0161) E-Operator Training & License Examination Outage F-Administrative 5-Reduction G-Operational Error (Explain) 9-Other 5 (9/77) H-Other (Explain) Exhibit I-Same Source
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l AVERAGE DAILY UNIT POWER LEVEL ..
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DOCKET NO. 50-327 - .
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UNIT Sequoyah one :
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DATE June 3, 1982 .,' ' -
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COMPLETED BY M. Eddings -- 4 TELEPIIONE (615) 751-0343
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MONTil May 1982 . DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL
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(MWe-Net) (MWe-Net) ,. 2 I~ I I 1,119.8 17 1,120.2 2 1,124.5 18 1,121.0 a
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3 1,125.5 19 1,120.3 '
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4 1,123.5 20 1,119.2 U 5 1,118.7 21 1,119.0
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6 1,120.3 22 1,118.7 . :. . 7 1,122.0 23 l'Il9 7
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8 1,120.8 24 1,118.0 -
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9 1,120.5 25 1,118.8 -
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10 1,118.7 26 1.100.5
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11 1,122.3 27 1,038.5 12 1,121.0 28 1,044.3 . ; . 13 1,121.0 29 1,114.2 - 14 1,120.5 30 1,113.2 . 15 1,116.3 31 1,112.3
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16 1,121.7 . : INSTRUCTIONS J- . t+?," On this format, list the average daily unit power level in MWe-Net for each day in - - ' j .4
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the reporting month. Compute to the nearest whole megawatt. - '
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OPERATING DATA REPORT DOCKET NO. 50-328 DATE June 19, 1982 COMPLETED BY David Dupree TELEPHONE (615) 751-0343 OPERATING STATUS
- 1. Unit Name: Sequoyah Two Notes
- 2. Reporting Period: May 1982
- 3. Licensed Thermal Power (MWt): 3411
- 4. Nameplate Rating (Gross MWe): 1220.58
- 5. Design Electrical Rating (Net MWe): 1148
- 6. Maximum Dependable Capacity (Gross MWe): 1183
- 7. Maximum Dependable Capacity (Net MWe): 1148
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
- 9. Power Level To Which Restricted, If Any (Net MWe):
- 10. Reasons For Restrictions, If Any:
This Month Yr-to-Date Cumulative
- 11. Ilours in Reporting Period 744 3,623 5,087
- 12. Number of Hours Reactor Was Critical 335.6 2,216.6 2,473.8
- 13. Reactor Reserve Shutdown Hours 0 0 0
- 14. Ilours Generator On-Line 328.7 2,076.7 2,090.3
- 15. Unit Reserve Shutdown Hours 0 0 0
- 16. Gross Thermal Energy Generated (MWH) 943,376 4,296,164.9 4,312,078.9
- 17. Gross Electrical Energy Generated (MWH) 316,440 1,156,280 1,393,644
- 18. Net Electrical Energy Generated (MWH) 294,916 1,281,259 1,281,209
- 19. Unit Service Factor 44.2 57.3 41.1
- 20. Unit Availability Factor 44.2 57.3 41.1
- 21. Unit Capacity Factor (Using MDC Net) 34.6 30.8 21.9
- 22. Unit Capacity Factor (Using DER Net) 34.6 30.8 21.9
- 23. Unit Forced Outage Rate 55.8 42.7 58.9
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
- 25. If Shut Down At End Of Report Period, Estimated Date of Startup: 6-2-82
- 26. Units In Test Status (Prior to Commercial Operation):
Forecast Achieved INITIAL CRITICALITY 11-5-81 11-5-81 INITIAL ELECTRICITY 12-31-81 12-31-81 COMMERCIAL OPERATION 6-1-82 6-1-82 (9/77) UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-328 l UNIT NAME sequovah Two DATE June 4 5982 COMPLETED BY David Dupree REPORT MONTl! May 1982 TELEPHONE (615) 751-0143 en W 4J No* Date ~ c^ " ox3 Li'*""
- s g, cause & Corrective c3 35 E y .5 g Event o.g g.g Action to R %5 8 jg& Report #
m g3 gg Prevent Recurrence
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3 82/05/03 F 0 B 5 Reduced load to add oil to #2 reactor coolant pump. 4 82/05/04 F 0 B 5 Reduced load due to blown manhole gasket on
, #3 heater drain tank.
T 21 82/05/05 F 2.6 A 3 Rx Trip: Ma in t . on vibration pickup brought in thrust bearing trip on "A" MFPT. "B" MFPT could not maintain steam generator level: causing a Rx trip. 22 82/05/13 F 3.8 B 3 While performing SI-93.1 on auto stop oil pressure switches, the turbine tripped thus the reactor tripped. 23 82/05/14 , S 408.9 B 2 Manual Trip: Startup Test 9.4A. (Begain ice weighing outage per tech. specs.) 1 2 3 4 F: Forced Reason: Method: Exhibit G-Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram. Entry Sheets for Licensee C-Refueling 3-Automatic Scram. Event Report (LER) File (NUREG- l D-Regulatory Restriction 4-Cont. of Existing 0161) l E-Operator Training & License Examination Outage F-Administrative 5-Reduction G-Operational Error (Explain) 9-Other 5 (9/77) Il-Other (Explain) Exhibit I-Same Source 5
UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-328 UNIT NAME Sequovah Two DATE June 4. 1982 COMPLETED BY David Dupree REPORT MONTH May 1982 TELEPHONE (615) 751-0343 n 4 4.J c^ o ec 3 Li"*"S** s En Cause & Corrective No* Dat* ~ a .S $ "@ y .5 g Event o4 g4 Action to R y5 y ,8 g y Report # g3 gg Prevent Recurrence o 05 e t2 m e
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3 82/05/03 F 0 B 5 Reduced load to add oil to #2 reactor coolant pump. 4 82/05/04 F 0 B 5 Reduced load due to blown manhole gasket on
#3 heater drain tank.
T 21 82/05/05 F 2.6 A 3 Rx Trip: Fb int . on vibration pickup brought in thrust bearing trip on "A" MFPT. "B" MFPT could not maintain steam generator levelt causing a Rx trip. 22 82/05/13 F 3.8 B 3 While performing SI-93.1 on auto stop oil pressure switches, the turbine tripped thus the reactor tripped. 23 82/05/14 S 408.9 B 2 Manual Trip: Startup Test 9.4A. (Begain ice weighing outage per tech. specs.) 1 2 3 4 F: Forced Reason: Method: Exhibit G-Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram. Entry Sheets for Licensee C-Refueling 3-Automatic Scram. Event Report (LER) File (NUREG-D-Regulatory Restriction 4-Cont. of Existing 0161) E-Operator Training & License Examination Outage F-Administrative 5-Reduction G-Operational Error (Explain) 9-Other 5 (9/77) H-Other (Explain) Exhibit I-Same Source
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x AVERAGE DAILY l: NIT POWER LEVEL
=
DOCKET No. 50-128 - UNJT _M Sequoyiih _]wo _ ._ i DATE .Iune___- 3, 1982 l 1 COMPLETED BY Jilv i d__ Dup r '_c _ . _ __
=_- _
A TEI.EPHONE (615) 751- 34 3 _ HUNTil M tv 198-
- )AY AVERAGE DAll Y l()WER LEVEL DAY AVERAGE DAILY POWER LEVEL
( %e-Ne t ) (MWe-Net) Y-1 iHl.k _ 17 0 J I , n i '. . / 18 0 _ __ ____ _
'} 9.' l . ! 19 0 ^ ~
4 8.' h . / 20 Z 0 5 hhh.5 21 0 _ _ _ . . _ . . t> J 9 '+ ( ) . ( ) - () d 7 1, l ( h) . ~ 2 .1 0 M 8 1,000.i 24 0 __ 9 1,101./ 25 0 o 1,098.' 26 0 1 1,101.0 27 0 2 1,101.H 28 0 _ _ _ _ 3 6 '4 1.J 29 0 _ __ 54 hh/ 1 .30 () - 5 0 31 0 O _ iSTRif floNS this l o i nu t . ilst the .tverage (Lil l y un i t power level in MWe-Net f o r eac h <iay in le reporting month. Compute to the nearest whole megawatt. (9/77) M
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Plant Maintenance Summary M
'I h e following s i gn i f i t .in t maintenance items re completed during the -f month of May 1982:
Mechanical Ma i nt en in .- rh M 1 Weighed 144 ice baskets in the l:n i t 2 it ondenser. l 2. Repaired lhe auxiliary feedwater pressu- control valves 2-PCV-3-122, and _
- 1 12 . j
- 1. Replac ed the rotating element in 2B-H "ntrifugal ( harging pump. ___-
- 4. HepIa<ed the b r .1 r i n g , a 11 gned .ind ha 1 a nt ed 2A MFPT. . __R F.1 e t t r i ( a1 'ti i n t e n a n c e -
I kepairs were made ti the RP1 ( .i b l e s . - [ 11 % l ' lllll('It t Na l llt ellilllc e Niuie rep <> r t a b l e <iri CSSC e<ju i pmerit . s= Field Services Maintenance N 2 Wo rk ( ontinues on the tollowing items: __ M
- l. 'l he power c.ibinets for the reactor head venting system have been instal. led. W G
- 2. Conduit installation and cable pulling continues for the high range area -
radiatton monitors for the residual heat removal lines and containment __ spray heat exchanger room lA. _-
-d
- 1. Terminating the cables in CAS and SAS and functional testing is all that ___ _
remains to be done on the a l a rms being installed on the containment - hatches and doors. -
- 4. Conduit has been installed and cable pulling is in progress serving addi- ,
ttonal radiation monitors to be used during times when containment is isolated. Y _
- 5. l.ock moditication and functional testing is all that remains to be done _
W on lloo r A- 181 I'h e door has been replaced and a card reader installed.
- b. Radiation monitor flow switch 1-RM-90-211 is being replaced. - - - - -
M
- 7. Sixteen of t w'e n t y - e i g h t secu ri t y ba rrie rs remain to be fabricated and __
installed. m
- b. b b.lllg I rig t tie F.HW t a r-bori steel p i p i tig tt> s t a t riless steel piping c oi!t i ntie s . _
_a mm d
Field Services Maintenance (Continued) The following work was completed during the month.
- 1. Sludge lancing and manhole machining of all four Unit _2 steam generators were accomplished during the outage.
- 2. Various solenoid valves have been replaced with environmentally qualified valves.
- 3. Permanent ladders and handrails have been installed in the Unit 2 fan rooms inside containment.
- 4. The Unit 2 lower compartment coolers were cleaned during the outage.
- 5. Pressure transmitter 2-PT-68-68 was relocated above the maximum post accident flood level.
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