ML17319A484

Monthly Operating Rept for June 1980

ML17319A484
Person / Time
Site:	Cook
Issue date:	07/03/1980
From:	Gillett W INDIANA MICHIGAN POWER CO.
To:
Shared Package
ML17319A482	List: ML17319A481 ML17319A484
References
NUDOCS 8007150547
Download: ML17319A484 (10)

Text

OPER%,TWiC DATARc~ORT DOCK"T I4'O.

DAT" CO~tPL TM SY Tij "~HOP=

~50-

. T. Gi.l ett Ol

>>O? -RA~GZiA,TUS Donald C.

Cook 1980 1089 1044 I. Unit ifarnez 1

Reporting oez'ad-June

3. Licaxsnf TheW?owe." g S'.)z 3250

4. Nstnephte Retina (Gpss IIDVe}z

o. Desi(nt H~U RMng (Net MSVe}z 1

6. )~am Dependshle Cspac'p (Grass MYe)z 1080

,. 'Eieermome=-odUir=Cm"mrr (H=r k(lee}r 8'. IfChnnl es Occur in Canc.".d}'xrhgs (lt ms Yumb= 3 Thzovgh 7j Sine" Lssz Repoz-.. Give Rmons: "'. Paa}M~vei~ti&Restz.', IfAny (5 t!}O'Ie}: IR'matts Faz ~Mans, IfAny. This hlonth Yz.<Q-Dot= Ca~use 0 0 I>>> R~oW~ Sita daVdtt HQ~

-t~: HoqzrCezte~z'On~, 0- ~ UrdrR W~ltntdawn Holm "Ur. Nor=(~r r.-U Ceoem:~ (!(lerU 0

19. Uni>Se~~~ccttsr UrltCmordrr ee mr(Ur IUeq. ice I'.

Uo(re'ore-"dMrogr Rere .4. SnatdovesSc.'".doled Ova'Ncx: o ~lonths lType. Date. nd Dv=tion of Each)z 3 207.9 3 199.7 0

73. 3 3.3 71.2 36 196.6 321

76. 7

76. 7 67.4

62. 9

~ ~}o"-er. 5oC'OIR=Ior:rot dorLBrim=red 0 reoidr.mp: ~ .'S. Units ln Test Status iPrior to Ce......~hiOp..:lon): Forest Ac-ievc )INITIALCRlTICALITY PITIAL='=C (? 'Cl~a COeii.ei~+C}wl Oo .- A ((O.i

AVERAGE DAILY UNIT POWER LEVEL "'OCKET NO. 50-315 UNIT 1 DATE 7-3-80 COMPLETED BY W. T. Gillett TELEPHONE 616-465-5901 MONTH June 1980 DAY AVERAGE DAILY POWER LEVEL 10 12 13 14 15 16 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 17 18 19 20 21 22 23. 24 25 26 27 28 29 30 31 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.

UNITSIIUTDO'IVNSAND POPOVER REDUCTIONS REPORT hlON'fll )3une, 1980 DOCKET NO. DATE COhlPLETED IIV B.A. Svens son TELEPIIONF. 616 465-5901 Dale C Vl I L C' )J )) << ~ C/) g Liccnscc Event Rcpofl 4 C+ C) Cl 'e) Vl ~Vl o ~ Q D Eu O Cr Cause &. CoffcclIYc Action lll Pfcvcnl Rccuffcnec 160 800530 S 720 BIEIC N.A. ZZ ZZZZZZ The unit was removed from service for Cycle, IV V refueling outage at 2228 hours EDT on 800530. The unit remained out of service the entire month. I: Forced S: Scheduled (')/77) Reason: A-Equipmcnl Failure (Explain) II-hlaintcnancc oi Test C-Refueling D.Regulatory Restriction I.'pcfalof Tfahllng &. Uccnsc I:xanlhlalh)n F-Administrative G.Operational Llror(I'.xplain) I I.Other (Explain) hicthod: I.hlanual 2.hlanual Scfanl. 3.Anti)n)atic Scraln. 4.Other (Explain) 4 Exhibit G - Inst ru et ious for Preparatio>> ol'Data LollyShccls fof Llccnscc Event Report (LI!R) File (NURliG-OI6I) 'L'xhibil I - Salne Source

UNITSHUTDOWNS AND POWER RE TIONS INSTRUCTIONS This report should describe all plant shutdowns during the report period. In addition. it should be the source ofexplan-ation of significant dips in average power levels. Each signi-ficant reduction in power level (greater than 20% reduction in average daily power level for the preceding 24 hours) should be noted, even though the unit may not have been shut down completelyl. For such reductions in power level, the duration should be listed as zero, the method of reduction should be listed as 4 (Other), and the Cause and Corrective Action to Prevent Recurrence column should explain. The Cause and Corrective Action to Prevent Recurrence column should be used to provide any needed explanation to fully describe the circumstances of the outage or power reduction. NUMBER. This column should indicate the sequential num. ber assigned to each shutdov n or sianificant reduction in power for that calendar year. -.-When a shutdown or significant power reduction begins in one report period and ends in another. an entry should be made for both report periods to be sure ~il shutdowns or signiricant power reductions are reported. Until a unit has achieved its first power generation, no num-ber should be assigned to each entry. DATE. This column should indicate the date of the start of each shutdown or significant power reduction. Report as year. month, and day. Auaust 14. 1977 would be reported as 770814. When a shutdown or significant power reduction begins in one report period and ends in another, an entry should be made for both report periods to be sure all shutdowns or significant power reductions are reported. TYPE. Use "F" or "S" to indicate either "Forced" or "Sche-duled," respectively, for each shutdown or significant power reduction. Forced shutdowns include those required to be initiated by no later than the weekend following discovery of an off-normal condition. It is recognized that some judg-ment is required in categorizing shutdowns in this way. In general. a forced shutdown is one that would not have been completed in the absence of the condition for which corrective action was taken. DURATION. Selfwxplanatory. When a shutdown extends beyond the end of a report period, count only the time to the end oi the report period*and pick up the ensuing down time in the. fouowing report periods. Report duration of outages rounded to the nearest tenth ofan hour to facilitatesummation. The sum of the total outage hours plus the hours the genera-tor was on line should equal the gross hours in the reporting period. REASON. Categorize by letter designation in accordance with the table appearing on the report form. Ifcategory H must he used. supply brief comments. METHOD OF SHUTTlNG DOWN THE REACTOR OR REDUCING POWER. Categorize by numher designation INote that this differs i'rom the Edison Electric Institute FEEI) definitions of -Forced Partial Outage" and -Sche. du!ed Partial Outage.- For these ierms. FEI uses a'hange of .0 MW as the break point. For lar er power reactors.30 MW is idio small a change to warrant explanation. in accordance with the table appearing on the report form. Ifcategory 4 must be used, supply brief comments. LICENSEE. EVENT REPORT. Reference the applicable reportable occurrence pertaining to the outage or power reduction. Enter the first four parts (event year. sequential report number, occurrence code and report type) of the five part designation as described in Item 17 of Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG4161). This information may not be immediately evident for all such shutdowns, of course, since further investigation may'e required to ascertain whether or not a reportable occurrence was involved.) If the outage or power reduction will not result in a reportable occurrence. the positive indication of this lack of correlation should be noted as not applicabie (N/A). SYSTEM CODE. The system in which the outage or power reduction originated should be noted by the two digit code of Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG4161). Systems that do not fit any existing code should be designa-ted XX. The code ZZ should be used for those events where a system is not applicable. COMPONENT CODE. Select the most appropriate component from Exhibit I - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG4161). using the followingcritieria: A. Ifa component failed, use the component directly involved. B. If not a component failure, use the related component: e.g.. wrong valve operated through error: list valve as " component. C. If a chain of failures occurs, the first component to mal-function should be listed. The sequence of events. includ- 'ng the other components which fail, should be described under the Cause and Corrective Action to Prevent Recur-rence column. Components that do not fit any existing code should be de-signated XXXXXX. The code ZZZZZZ should'be used for events where a component designation is not applicable. CAUSE & CORRECTIVE ACTION TO PREVENT RECUR-RENCE. Use the column in a narrative fashion to amplify or explain the circumstances of the shutdown or power reduction. The column should include the specific cause for each shut-down or significant power reduction and the immediate and contemplated long term corrective action taken. if appropri-'te. This column should also be used for a description of the major safety-related corrective maintenance performed during the outage or power reduction including an identification of the critical path activity and a report of any single release of radioactivity vr single radiation exposure speciiically associ-ated with the outaae which accounts for more than 10 percent oi the allowable annual values. For long textual reports continue narrative on-separate paper and ret'erenee ihe shutdown or power reduction ior tl'.is ilaffJ tlve. (~)I7 I

Docke~.: Unit l%lhe: Completed By: 'elephone: Date: Page: 50-315 D. C. Cook Unit 81 R. S. Lease (616) 465-5901 July 8, 1980 10f1 MONTHLY OPERATING ACTIVITIES -- JUNE, 1980 Hi hli hts The Unit has been shut down the entire reporting period for it's fourth Refueling Outage. The time of shut down was 2228 hours 5/30/80. Electrical generation for the month was 0. ~Sumnar 6/1/80 6/3/80 6/9/80 6/13/80 6/14/80 6/16/80 6/18/80 6/26/80 6/27/80 The unit was cooled down to Mode 5 at 1835 hours. Hydrogen Peroxide clean up in the Reactor Coolant System was completed by 2300 hours. Reactor Plant entered Mode 6 at 1800 hours with the unbolting of the reactor vessel head. The Motor Driven Auxiliary Feedwater Pump,was inoperable for a 38 hour period starting at 0830 hours. This was to make a piping tie with a new Auxiliary Feedwater Pump being installed. Unit 2 was dependent on this pump during this period for operability. During this outage an additional Auxiliary Feedwater Pump is being installed on each Unit and cross unit dependency will be eliminated. Reactor Vessel Head was removed. The upper internals were removed and placed in the Storage Stand. -- Transfer of fuel was initiated, at 2352 hours. Fuel transfer was completed at 1058 hours. Control Rod Drive Shafts were latched and the rods drag tested by 1445 hours.

P A

DOCKET NO. UNIT NAME DATE COMPLETED BY TELEPHONE PAGE 50 - 315 D. C. Cook - Unit No. 1 7-9-80 B. A. Svensson 616 465-5901 1 of2 MAJOR SAFETY-RELATED MAINTENANCE

JUNE, 1980 M-2 M-3 Containment isolation check valve NSW-415-3 failed to pass 1'eak rate test.

A new valve was installed and satisfactory leak test achieved. Boron injection tank sample valve SI-128 leaked by. Replaced valve. The motor driven auxiliary feedpump discharge valve to the No. 4 steam generator leaked by. Replaced -the valve seat and plug. Also repacked the valve and had it tested. The No. 3 accumulator check valve SI-166-3 had a body to bonnet leak. The gasket was replaced. Containment isolation check valve NSW 415-1 failed to pass the type C leak rate test. Replaced valve discs, cleaned valve and had it re-tested. M-8 M-10 M-11 Pressurizer power operated relief motor operated isolation valve breaker tripped when trying to open the valve.(NM0-151). Investigation revealed the valve operator motor running backward. The motor rotation was cor-rected and the valve tested satisfactorily. The valve had been closed during operation. 1AB2 starting air compressor discharge check valve, DG-101A, for AB diesel was leaking by. Cleaned valve and'apped seat. Tested satis-factorily. Planned inspection of seals on No. 2 reactor coolant pump. Replaced No. 1 seal insert, No. 2 seal and runner, and No. 3 seal. Low pressure letdown safety valve SV-51 was leaking by. Disassembled valve, lapped seats, reassembled, and adjusted pressure set point. No."-1 steam generator stop valve dump, valve, MRV-211, was leaking by. Disassembled'valve,

cleaned, replaced gaskets,'lapped

seats, and re-assembled valve;

-Had valve tested. 1 No. 1 steam generator stop valve dump'alve, MRV-212, was leaking by. Disassembled valve, cleaned, lapp'ed seats,replaced,

gaskets, and re-assembled.

Had valve tested.

r t h ll J (

DOCKET No. UNIT NAME DATE COMPLETED BY TELEPHONE PAGE 50 - 315 ook - Unit No. 1 7-9-80 B. A. Svensson 616 465-5901 2of2 MAJOR SAFETY-RELATED MAINTENANCE

JUNE, 1980 Nonessential service water containment isolation check valve, NSW-415-4, failed to pass type C leak rate test.

Cleaned valve and replaced discs. Had valve retested. Pressurizer power operated relief valve NRV-151 was leaking by. Replaced the valve stem, seats, and gaskets. Repacked and had valve tested. Pressurizer power operated relief valve, NRV-153, had a ruptured dia-phragm in the air operator. Replaced the diaphragm and had the valve tested. 'No. 2 boric acid transfer pump mechanical seal leaked excessively. Re-placed the mechanical seal and rebuilt pump. Had pump tested. WCR-945 NESW containment isolation valve failed leak test. Valve was cleaned and seat was lapped. Valve'was, retested satisfactorily.

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