ML19322D186

Forwards Chronology of Operating Experience,Summary of Reactor Trips & Operating Power History.Tmi Operating Experience Summary & Selected Pages from Monthly Operating Repts Encl

ML19322D186
Person / Time
Site:	Crane
Issue date:	07/30/1979
From:	Lanning W NRC - NRC THREE MILE ISLAND TASK FORCE
To:	Parler W NRC - NRC THREE MILE ISLAND TASK FORCE
Shared Package
ML19322D187	List: ML19322D186 ML19322D188
References
TASK-TF, TASK-TMR NUDOCS 8002100032
Download: ML19322D186 (20)

Text

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July 30,1979 MEMORANDUM FOR: William Parler, Group 1, Task Leader FROM:

W. Lanning, Group 1

SUMMARY

OF TMI-2 OPERATING EXPERIENCE.

REFERENCCS:

1.

Death and Taxes: M Investigation of the Initial Operation of Three Mile Island No. 2, Public Citizen's Health Research Group, April 5,1979 2.

Inter-0f# ice Memorandum, R. Cutler to R. Arnold, "Startup Test Program History and Delay Analyses,"

GPU Service, January 23, 1979 3.

Inter-Office Memorandum, R. Cutler to R. Arnold, "TMI-2: Startup Test Program History and Delay Analyses," GPU Service 4.

TMI-2 Ponthly Operating Reports February 1978 through March 1979 5.

Memorandum, W. Lanning to W. Parler, " Summary of Licensee Event Reports for TMI-2," May 29,1979 6.

Letter, J. Herbein to S. Varga, " Power Operation with Three Pumps." March 29, 1978 7.

Letter, S. Varga to J. Herbein, "TMI-2 Partial Loop Operation," May 3,1978 8.

Letter, J. Herbein to S. Varga, Response to May 3 letter, May 12, 1978 9.

Memorandum, W. Lanning to W. Parler, " Review of Out-standing Items. for TMI-2 License," June 28, 1979

10. Memorandum, W.Lanning to W. Parler, " Summary of Post-0L Actions," June 22, 1979 From February 1978 to March 1979, TMI-2 experienced at least 34 reactor trips.

I Approximately one-third of these originated in the Feedwater and Condensate Systems. Reference 1 provides a good chronology of operating experience. How-ever, there are some missing reactor trips which were not contained in the l

8002looO 3g #

r William Parler 2

July 30, 1979 monthly operating, but appeared on the operating log (source for References 2 and 3).

These h've been added to the Unit Shutdown Summaries taken from the Monthly Operati.19 Reports (4) and are enclosed. The LER's have been sunmurized in Reference 5.

Some importance can be atts led to the operating mode of TMI-2 during the period March 14 through May i7,1978. As the result of the failure of one of the primary reactor coolant pumps, the plant was operated using three' coolant pumps. This enabled the plant to achieve criticality (Mode 2) on March 28, 1978, approximately two months sooner than could have been attained using four pumps.

The Technical Specifications permit operations with three pumps.

It appears that the staff discussed operation with three pumps with the licensee. This discussion resulted in a lett2r from the Licensee (reference 6) in which they voluntarily increased the nuclear power peaking factor. This is a change in,the Technical Specifications without formal approval by the NRC.

Reference 7 requested additional analyses of 3-pump operation for longer.

term operation.

The licensee responded in Reference 8 that the disabled pump had been fixed and that it ws not necessary to further define safety margins.

It appears that no analyses were completed to justify temporary 3-pump operation.

During this two-month period, a number of preoperational tests were completed.

These included control rod group rod drop testing, zero power physics testing, rod worth measurements, power escalation testing.

It appears that the reduced flow and possible slight power redistribution would not have any adverse effects on the outcome of these tests. -(Ron Hayes will study in detail).

Changes to the operating license and other post-OL actions are summarized in References 9 and 10.

A plot showing the reactor power levels as a function of time is contained in (Reference 2).

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ayne'D. Lannin Group 1

Enclosures:

1.

Summary _of Reactor Trips 2.

Operating power history cc:

R. Hayes, w/o encls, Group 1, i

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Docket,i.o.

50-M' U'IT SHUTDOWHG AIU Eit HEDUC'I'TCriS M~

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REPORT MONTli March

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Completed By R. A. Lene.el A.

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Date Type cu o

Code li Code 5 Action to gg o egg oy y

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h/18/'l8 F

76 H

3 Trip caused by noise spike on a flux /flov/

imbalance channel.

I h/23/78 F

174.5 H

3 78-33/1P Trip caused by noise spike on a power range channel.

h/01/78 F

182 9 A

3 Loss or power monitor to RCP-1A causin.;

IC3 to believe no pumps were operating in one loop.

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IRIIT SilVTDOWUS AND POWF.R REDUCTIOriS Unit Name THT-2

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UMn The outage was extended due to con.u 5

10-5-78 S

181 B

2 connector problems on the steam genera.'-

The turbine generator was taken off line to 6

10-13-78 F

4.0 A

NA repair a hydraulic leak on GVF2 The turbine tripped due to a feedwater pune 7

10-14-78 F

3.2 A

3 problem. The reactor then tripped on low pressure due to manually overcompensation for the turbine trip.

Feedwater pump problem 8

10-14-78 F

10.5 A

3 Main generator dif ferential relay rrch le s 9

10-17-78 S

1.1 B

NA Main generator differential relay problem 10 10-20-78 h'

4.1.

A NA Main generator differential relay problemi 11 10-21-78 F

2.5 A

NA Breakdown of insulation on the #9 excitnr 12 10-28-78 F

90.1 A

1 bearings j

3 U*hIDi' O ~ I"8'"""'I""'

2 eason:

M m odi I: Forced R

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i Ncht Ns. _50-320 N, UNIT SHUTDOWNS AND POWER REDUCTIONS = Unit Name THI-2 12-15-78 REPORT HONT) November Date Completed By L. W. liardInn 215-921-6576 Telephone i 9 Cat n and Corrective D' ,'Date Type h or, ( System Component l o Code 5 Action to Code 18 /- 4/ ~ .,l ',, Y@ S 0C U$g Prevent Recurrence 3 g 'g g g g, 4 ti n u 88p ses 3A= 12 11-1-78 14.25 A 1 Breakdown of insulation on the No. 7 Exciter. Bearing (Generator of f line) N'! 26.75 C 3 Loss of power to Condensate Polishing Valuu 13 11-3-78 (Generator of f line) 14 11-7-78 F., 570.4 A 3 Condensate Dooster Pump tripped thereby tripping the Feedwater Pumpa (Cencrator enf f line) i I '.t i e 1: Forted 2ecasoni 3 " Exhibit G - Instructions F Hethods S: Scheduled.:. A-Equipment Failure (Explain) 14amal 5-Maintenance or Test ' Entry Sheets for Licensee Et 2-Mamal Scram, D, .* c-Refueling Event Report LER) File d

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UlitT ClittrDOWilS A ) Weit il@UCTI0 tis Dock:;t tb. _ 50-; HEPORT HoliTil ~Deccnber Unit ifame _ THI-2 N ~ Date __ 1/15/19-Completed By H. A. f.cnget ~ q Telephone _ 921-6501 tio. Date Typel 07 g M b cu Uh N 'o t o O' Code D Code 5 cause and corrective System component p Na U gen N*h i M ~s sE .c 0 y s Y,E Prevent Recurrence Action to CRe 3"B xmm adm lle 12/1/78 F 2.2 A 3 Condencate booster pump tripped, trippinr reeil 15 12/2/78 Fi. 17 11 3. water pumps Lost FW flow while chifting WP 'Nrbine 1A frr= 16 12/2/78 P' h.8 0 3 auxiliary steam to main oteam Turbine tripped when condensate valve was

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17 12/2/78 F 28.3 vertently positioned to the' f\\all open MIMion 3 OT3G "D" feed utopped due to W-V-l'r3 cein 18 12/16/7t' F 1h6 A 3 fully closed g i. 19 12/20/70 S 23.8 a 1 Turbine tripped due to loss of W-P-!?: 20 L2/30/7ti F,, 2.h B 'Phyoice testing load rejecticn :est liigh pressure turbine system steam leak } I: Forced ,2Renoon: 1 l F i _ ___ i 8: Scheduled t ,' 'A-Equipment Failure (Expla!n } i 3 _Exhibi t G - Ins truc tions ! D-Maintennnce or Test g I llc-IlcNeling for Preparation of Data " "" "1 ! -Regulatory Restriction anual Scrum. Entry Sheets for Licensee IT' D E-Operator Training & Licensen Pynmllltsl[ 3-Au tomatic Scrum. Event Report (LER) T'2e k ht.: ryg 3-thnr @rplialgi) (10lHP.0-0161) 8 C' l+ I I 'G-Operational Error (Explain) i li-Other (Explain) SEchibit 1 - Same sonrec

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1/2/79F 11 5 A N/A Turbine taken off line to repair hydraulie 2 1/9/79 F 0 leak on GV-1 3 1/lk/79 F hl2 7 A 1 Decreased power to 60% to try and 1::1.3 repair condenser leaks Unit shutdown repair leaking primary valves a while startup Reactor tripped on lev presr. tre outage continued to repair atmospherie 1 t.p bellovs. s i 9 1: Forced 2 Reason: F S: Scheduled 3 A-Equipment Failure (Explain) Method Exhibit G - Instructions B-Maintenance or Test 1-Manu al f r Preparation f Data C-Re rueling D-Regulatory Restriction 2-Manual Scram Entry Sheets for Licensee C, 2' 3-Automatic Scram' Event Report (LER) File E-Operator Training & Licensee Ecamination b-Other (Explain) (NUR G-0161) y' F-Administrative G4....cational Error- (Explain) H-Other (Exp1nin) S.v b i bi t. r 1 - nn-r'. ".

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1 A =j 2/10/79 h

13.[ A I4 1 Repair Turbine EllC Leaka i ly. yo,.c ed 2 Reason l s i S: Scheilu led 3 A-Equipment Failure (Explain) tiethod:

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D-Regulatory Restriction 3-Automatic Scron. Emt Rep rt (I.ER) l'ile C <E-Operator Training & Licenace Examination 1 -Other (Explain) """ ~ i 4 F-Administrative , G-Operational Error (Explain) II-Other (Explaiti) S Erh i b t t. 1 - nem.. n,in e..-

i I UiiIT SIRJTD0'5S AND 40'JER REDUCTIOI4S Docket No. 50-3c Unit Name Three Mt. REPORT Moimi March, 1979 ~ Date April 18 Completed By R. A. Lene A Telephone _ ?1s 021 r.,n,,. N \\ w s l 57 f No. Date Type m o System Component Cause and Corrective U$ oS Code h Code 5 Action to oe &S E e5o E*n Prevent Recurrence 8" E S0$ tas 3*S a&= xmz 5 33/06/79 F' 16.5 A 3 Turbine generator tripped follo cd by Ro.ictor Trip on Core Power Imbalance 6 33/28/79 F. 92.0 A 3 Feedpump trip, turbine trip, reactor trip on high pressure. Cause and correctice 2:: 17 to prevent recurrence vill be proviiloil a t a later date. I 'I .i I I: Forced 2 Reason; 3 " xhibit G - Instruction: P S: Scheduled A-Equipment Failure (Explain) Method: B-Maintenance or Tes't 1-kanu al f r Preparation of Data p C-Refueling 2-Mama' Scram. Entry Sheets for Licencae D-Regulatory Restriction 3-Automatic Scran. Event Report (LER) File [ r E-Operator Training & Licensee Examination b-Other (Explain) 7-Administrative 'G-opet rit L l oniti Err or (Ex plet t o ) M*hibl8 I - Ita""- "'- !!-Other (Explain)

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1 4 i 4 jik )m7 SM MARY.0F MONTHLY OPERATING EXPERIENCE / TFE Unit 2 returned to service following the screen outage and removal of oil from the condensate cystem at 0312 on December 2. The unit experienced a loca of feedwater at Oh30 and the turbine was manually tripped. Generatar breakers were reclosed at 0609 and at 0720 the reactor tripped on low pressure during a recovery from a loss of feedvater. The un'it returned to service at 15% at 1204. The reactor tripped en low precoure due to overfeeding. The trip was folleved by an E.S. actuation and subsequent H.P. injection. The overfeeding occurrel when the rain feed-water block valves automaticclly opened vith the downstream main feedwater regulating valves manually pinned open at the local air controllero. Tne unit returned to service at 17h8 on December 3 and power escalation commenced. The unit achieved 90% reactor pcver at 215h on December h and the 90% power level testing continued. The unit reduced power to 60,% on December 12 in order to remove main feed pump 1B from service in order to repair a leak on the suction strainer. Fover vac Ibrther reduced to $5% on December 13 due to high codium levels in the condensate cystem. It was also discovered that main feed pump 1B had a mechanical interference and could not be rotated freely. The unit was removed from service at 0151 on December 16 to replace the impeller assembly in 1B main feed pump. The unit returned to cervice December 22 and power was increased to 50%. On December 23 the unit achieved 97% power and testing continued. On December 27 power was reduced to 65% and returned to 97% for transient tecting. At 1522 on December 28 main feed pump'1A was manually tripped in accordance with the test procedure. The feed ptmp was returned to cervice and power increaced to 97%. At 2318 the main turbine was manually tripped per the test procedure. The unit responded properly and ran inck to 15% power. The unit vac subsequently chut d7.n to repair a number of steam leaks. ) The unit returned to service December 29 and power was increased to hh%. I At 1100 hrc on December 30 the main turbine was removed from service in order to repair a steam leak en the high pressure turbine. The turbine vac returned to cervice at lh15 hra and power escalation began. The unit achieved 80% reactor power at 2020 hrs and commenced cc=mercial operation at 2300 hrs on December 30 at a net 765 MWe. 7901190 /'S ---n

m - \\ \\ Fover vaa reduced to 75% ct 0030 hrs cn D cemb;r 31 p:;nding v;rification or rcei: tor coolant flow calculations. The unit returned to 82% power at 0630 hrs. At this time plans are to naintain 825 power level until a cecond heater drain pump can be returned to service. Y --me

f , _ ~ . _ _. ~.. _ _ _ _ _ _. _. _.. _, _... _ _. ,-a OPERATING DATA REPORT Docket No. 50-320 Date 1/15/79 ' Completed By R. A. Lengel uPERATING STATUS Telephone Wi-0)U1 1. Unit Name: Three Mile Island Nuclear Sta., Uriit 2 2. Reporting Period: Dece ber. 1978 3. Licensed Thermal Power (Wt): 2772 L. Nameplate Rating (Gross We): 961 5 Design Electrical Rating (Net We): 906 6. Max. Dependable Capacity (Gross M4e): 930 7 Max. ' Dependable Capacity (Net M'de): 880 8. If Changes Occur in Capacity Ratings (Items No. 3 through 7) Since Last Report, Give Reasons: 9. Power Level to which Restricted. If Any (Net We): 10. Reasons for Restrictions, If Any: MONTH YR TO DATE CUMMULATIVE 11. l'ours in Reporting Period Thh 6692 25 12. No. of Hours Reactor was Critical 5h1.1 1753.3 25.0 13. Reactor Reserve Shutdown Hourt 202.9 323h.h 0.0 lb. Hours Generator On-Line 509.3 1298.0 25.0 0.0 0.0 0.0 15 Unit Reserve Shutdown Hours 17. Gross Elect. Energy Generated (WH) 383h26 727677 ~ 565hh 16. Gross Thermal Energy Generated (MWH) 1197696 2219379 197C9 18. Net Electrical Energy Generated (MWH) 353051 576921 18716 19. Unit Service Factor 68.5 19.h 100.0 20. Unit Availability Factor 68.5 19.h 100.0 21 '. Unit Capacity Factor (Using MDC Net) 53.9 9.8 85 1 22. Unit Capacity Factor (Using DER Net) 52.4 9.5 82.6 23. Unit Forced Outage Rate 31.4 76.7 0.0 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: 26. Units In Test Status (Prior to Commercial Operation): FORECAST ACHIEVED INITIAL CRITICALITY M /78 3/28/78 INITIAL ELECTRICITY 3/15/78 h/21/78 COMMEFCIAL OPERATION 12/10/78 12/30/78

. _ =, sj-s AVERAGE DAILY UNIT PCTER LEVEL j ., N 1 j1 '~ Docket No. 50-320 Unit M -2 Date 1/15/79 Completed By R. A. Lengel go m December, 1978 DAY AVERAGE DAILY POWER LEVEL DAY ' AVERAGE DAILY POWER LEVEL (MWe-Net)" (MWe-Net) 1 -35 17 -36 2- -17 18 -27 3 40 19 -27 h 600 20 -36 5 8h2 21 -36 6 847 22 257 7 830 23 708 8 838 2h 887 o 837 e5 896 10 838 26 891 11 837 27 884 12 531 98 8h3 13 h82 29 -32 1h 485 30 367 15 485 31 7h8 16 -15

1. Please Note:

Negative numbers indicate that more energy was used by the unit than was produced by it, and are included for your infor-mation only. 'T+-r _,yy

4 Dock t No. 50-320 o UNIT SifUTDOW33 AND POUER REDUCTIO 5S Unit. Na=e M -2 REFORT MONTH December D2te 1/15/79 Completed By R. A. Lencel { Telephone 921-6501 j Et I y l 52 Im S bi System Component Cause and Corrective No. Date Type U$ 5 Ie eS Code k Code 5 Action to 8$ E Eo $*L Prevent Recurrence i <3 " UU EY$ TEE 3#5 1 i u tn x a ca n i lh 12/1/78 F 27.2 A 3 Ocndensate booster purp tripped, tripping fec water p=ps 15 12/2/78 F 1.7 H 3 Lost FW flow while shifting WP Turbine 1A fr auxiliary steam to main stea= 5i 16 12/2/78 F h.8 G 3 Turbine tripped when condencate valve was int vertently positioned to the full open positic 17 12/2/78 F 28.3 3 OTSG "B" feed stopped due to W-V-193 being fully closed 18 12/16/76 F 1h6 A 3 Turbine tripped due to loss of W-P-1B 1 19 12/23/78 5 23.8 B 1 Physics testing load rejection test j j 20 12/30/78 ? 2.4 B High pressure turbine systen stea= leak 1 3 2 easen: 3 - nsWM ons IF: Foreed R Methods r rep ea n Data S: Scheduled A-Equipment Failure (Explain) 1 Atanual n ee s for Mcensee B-Maintenance or Test 2-Manual Scram. Event Report (LER) File C-Refueling 3-Automatic Scram. D-Regulatory Rectriction b-Other (Explain) E-Operator Training 1 Licensee Examination F-Ad=inistrative 2 } G-Operational Error (Explain) Exhibit 1 - Same Source } H-Other (Explain) i k .}}