ML17325A974

Monthly Operating Rept for Sept 1988 for DC Cook Unit 1. W/881007 Ltr

ML17325A974
Person / Time
Site:	Cook
Issue date:	09/30/1988
From:	Giles H, Harner J, Will Smith INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8810260019
Download: ML17325A974 (10)

Text

~ I REGULA Y INFORMATION DISTRIBUTIO 'YSTEM (RIDS)

ACCESSION NBR: 8810260019 DOC. DATE: 88/09/30 NOTARIZED: NQ DOCKET 0 FACIL: 50-315 Donald C. Cook Nuclear Power Planti Unit 1> Indiana 5 05000315 AUTH. NAME AUTHOR AFFILIATION GILES'. Indiana Michigan Power Co. (formerly Indiana 5, Michigan Ele SMITHS'. G. Indiana Michigan Power Co. (formerly Indiana, 5,Michigan Ele RECIP. NAME RECIPIENT AFFILIATION

SUBJECT:

Monthly operating rept for Sept 1988 for DC Cook Unit l

W/881007 ltr.

DISTRIBUTION CODE: ZEROED COPIES RECEIVED: LTR TITLE: Monthlg Operating Report (per Tech Specs)

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RECIPIENT COPIES RECIP IENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 LA 1 0 PD3-1 PD 5 5 SCOTTI W 0 INTERNAL: AEOD/DOA 1 2

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AEOD/DSP/TPAB NRR/DLPG/PEB 11 1 1 ARM TECH ADO 1 1 NRR/DOE*/EAB 11 1 1 ~R=i'+)REPi%P 10 1 1 NUDOCS-ABSTRACT RGN3 1

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~EC F'IL 01 1 EXTERNAL'GSG SIMPSON' 1 1 EG5G WILLIAMS' 1 1 LPDR 1 1 NRC PDR 1 1 NSIC 1 1 TOT*i NUMBER QF COP IES REQUIRED: LTTR 22 ENCL 20

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N.R.C. OPERATING DATA REPORT DOCKET NO. 50-315 DATE 04-Oct-88 COMPLETED BY H. Giles TELEPHONE 616-465-5901 OPERATINQ STATUS

1. Unit Name D. C. Cook Unit 1

2. Reporting Period SEPT 1988 ,'nates

3. Licensed Thermal Power (MWt) 3250

4. Name Plate Rating (Gross MWe) 1152

5. Design Electrical Rating (Net MWe) 1030

6. Maximum Dependable Capacity (GROSS MWe) 1058

7. Maximum Dependable Capacity (Net MWe) 1020

8. If Changes Occur in Capacity Ratings (Items no. 3 through 7) Since Last Report Give Reasons

9. Pawer Level To Which Restricted.

If If Any (Net MWe)

10. Reasons For Restrictions. Any:

This Mo. Yr. to Date Cumm.

11. Hours in Reporting Period 720.0 6575.0 120527.0

12. No. of Hrs. Reactor Was Critical 522.3 6324.8 88162.5

13. Reactor Reserve Shutdown Hours 0.0 0.0 483.0

14. Hours Generator on Line 511.9 8301.9 86539 '

15. Unit Reserve Shutdown Hours 0.0 0.0 321.0

16. Gross Therm. Energy Qen. (MWH) 1448245 18248448 251245444

17. Gross Elect. Energy Gen. (MWH) 457110 5876520 82021190

18. Net Elect. Energy Qen. (MWH) 438285 5647052 78878050

19. Unit Service Factor 71.1 95. 8 73.0

20. Unit Availability Factor 71.1 95. 8 73.0

21. Unit Capacity Factor (MDC Net) 59.7 84.2 65.2

22. Unit Capacity Factor (DER Net) 59.1 83. 4 63.2

23. Unit Forced Outage Rate 28.9 3.6 8.0

24. Shutdowns Scheduled over Next Six Months (Type, Date, and Duration)-

C Fe

25. If Shut Down At End of Report Period, Estimated Date of Startup-

26. Units in Test Status (Prior to Commercial Operation)-

Forcast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COHKKCIAL OPERATION

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I/NITSIIIITI)OWNSANI)POWER RKI)IM1'IONS UNIT NAME D.C. Cook Unit 1 l)ATK Oct. 10 1988 C:f)Mtl+tKI)ItY J. W. Harner RKPOR I MPN III TKLEtIIONE (616) 465-5901 Page: lof 2 I.iecusee (auseh Cnrtei,tive N i. l4tc Knell) Aelinii tit pt) Retwirl 4 Prcvetll Reelulellcc 271 880907 207.6 NA CI PIPEA The Unit shutdown and the reactor coolant sys-

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tem cooled down to Mode 4 due to a calculated leak rate of 0.96 gpm. Upon containment ent an instrument line was found broken between the manual isolation valve and the instrument, QDA-21. The instrument'is the number 2 reac-tor coolant pump shaft seal thermal barrier differential pressure alarm. The failure was due to the pipe vibrating and. rubbing against a structural support creating a fault. The failed section of piping was removed and re-placed with a new one. The piping was then rerouted away from the support, thus preventi further problems or similar damage in the fu-ture. During the nine day outage selected Emergency Core Cooling System motor operated valves were inspected with no problems being identified. Also during this time selected S valves which were found to be a problem on Unit 2 were inspected on Unit 1. These valve were 1-SI-151 East, 1-SI-151 West, 1-SI-166-L and 1-SI-166-L4 which are check valves in the cooldown lines and safety injection lines to the reactor coolant system.

Reptant It was found tha 1-SI-151 East and 1-SI-151 West both had one 3 4 I: ln)A:d Rcasitn: Helhtiil: Exhibit Ci - Inst suet in)is S: Scltedttleil A-fillriptltenlfailure]Kap4hl) I -Man rial fnt Pteparatinri <<f I>ata O Matulenattcrt ni Tesl 2 Manual Seta tu. Iintty Sheets fni licensee C Rcfucltug 3 Au)outa!le Sc:iattt. Event II.I!RI I'ilc INlIRI G.

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UNITSIIIITIPOWNS AND I>OlTKN kEI)IJC'1'lONS Unit 1 UNITNAgh D.C. Cook pA~ Oct. 10 1988 c.ourlzmi lsV QEPORT NPH AI Page: 2 of 2 leavens

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kel>>>sl 4 Psevcns kec>uscnce 271 broken retaining block stud which were remove (con't) and replaced the new ones. There are 2 of these studs in each valve which hold the clap per assembly in place. The stud materials of 1-SI-166-Ll and 1-SI-166-L4 were in question, thus these studs were removed and replaced with new ones.

Prior to the unit heatup, a steam generator crevice flush of all four steam generators wa performed. The unit was paralleled at 0224 hours0.00259 days <br />0.0622 hours <br />3.703704e-4 weeks <br />8.5232e-5 months <br /> (EDT), brought to 48'4 power and held here for turbine warming prior to overspeed testing.

272 880916 0.5 NA ZZ ZZZZZZ The to reactor power level was reduced from 9'4 and at 1824 hours0.0211 days <br />0.507 hours <br />0.00302 weeks <br />6.94032e-4 months <br /> the unit was removed 4'

from parallel for turbine overspeed testing.

The unit was returned to service at 1855 hour0.0215 days <br />0.515 hours <br />0.00307 weeks <br />7.058275e-4 months <br /> The unit was returned to its administrative power limit of 90X on 9-17-88.

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DOCKET 50-315 NO'NIT NAME: D. C. Cook Unit 1 COMPLETED BY: J. W. Harner TELEPHONE: (616) 465-5901 DATE: October 10, 1988 PAGE: 1of1 MONTHLY OPERATING ACTIVITIES - SEPTEMBER 1988 HIGHLIGHTS:

The Unit shutdown and the reactor coolant system cooled down to Mode 4 due to a calculated leak rate of 0.96 gpm. Upon containment entry an instrument line was found broken between the manual isolation valve and the instrument, ADA-21. The instrument is the number 2 reactor coolant pump shaft seal thermal barrier differential pressure alarm. The failure was due to the pipe vibrating and rubbing against a structural support creating a fault. The failed section of piping was removed and replaced with a new one. The piping was then rerouted away from the support, thus preventing further problems or similar damage in the future. During the nine day outage selected Emergency Core Cooling System motor operated valves were inspected with no problems being identified. Also during this time selected SI valves which were found to be a problem on Unit 2 were inspected on Unit 1. These valves were 1-SI-151 East, 1-SI-151 West, 1-SI-166-Ll and 1-SI-166-L4 which are check valves in the cooldown lines and safety injection lines to the reactor coolant system. It was found that 1-SI-151 East and 1-SI-151 West both had one broken retaining block stud which were removed and replaced with new ones. There are 2 of these studs in each valve which hold the clapper assembly in place. The stud materials of 1-SI-166-L1 and 1-SI-166-L4 were in question, thus these studs were removed and replaced with new ones.

Prior to the unit heatup, a steam generator crevice flush of all four steam generators was performed. The unit was paralleled at 0224 hours0.00259 days <br />0.0622 hours <br />3.703704e-4 weeks <br />8.5232e-5 months <br /> (EDT);

brought to 48% power and held here for turbine warming prior to overspeed testing.

The reactor power level was reduced from 485 to 9X and at 1824 hours0.0211 days <br />0.507 hours <br />0.00302 weeks <br />6.94032e-4 months <br /> the unit was removed from parallel for turbine overspeed testing. The unit was returned to service at 1855 hours0.0215 days <br />0.515 hours <br />0.00307 weeks <br />7.058275e-4 months <br />. The unit was returned to its administrative power limit of 90% on 09-17-88.

An unusual event was declared on 09-22-88 due to a fire in a plastics factory in the village of Stevensvi lie.

DETAILS 9-7-88 At 0440 hrs. a planned unit shutdown and reactor coolant cooldown was commenced due to an elevated reactor coolant leak rate of 0.96 gpm.

The reactor coolant system was cooled down and the unit entered Mode 4 at 1914 hrs.

Following the repairs of the reactor coolant system leak, SG crevice flush, and reactor coolant heat-up the unit entered Mode 3 at 0540 hrs.

The unit entered Mode 2 with a reactor startup at 0447 hrs. The startup was terminated due to criticality not being reached at the conditions calculated, (ECP).

After recalculating an estimated critical rod position (ECP) a reactor startup at 1602 hrs was commenced. The reactor reached criticality at 1629 hrs.

The reactor entered Mode One at 2105 hrs.

The Unit was paralleled at 0224 hours0.00259 days <br />0.0622 hours <br />3.703704e-4 weeks <br />8.5232e-5 months <br /> (EDT) and reactor power was increased to 48K. Reactor power was held at this power level for turbine warming in preparation for a scheduled turbine overspeed test.

Reactor power was reduced to 9X power and the unit was removed from parallel at 1824 hours0.0211 days <br />0.507 hours <br />0.00302 weeks <br />6.94032e-4 months <br /> (EDT) to perform the scheduled main turbine overspeed test. The unit was returned to service at 1855 hours0.0215 days <br />0.515 hours <br />0.00307 weeks <br />7.058275e-4 months <br />.

The unit reached the 90K administrative power limit at 1133 hrs. and remained there for the remainder of the reporting period.

At 0407 hrs. an unusual event was declared due to a fire in a plastics factory in the local community of Stevensville. The unit exited the unusual event at 0740 hrs after it was determined no hazardous gases existed.

DOCKET NO. 50-315 UNIT NAME ~D. . Cook - Unit No. 1 DATE October 7 1988 COMPLETED BY J. W. Harner TELEPHONE 616 465-5901 PAGE 1 o 1 MAJOR SAFETY-RELATED MAINTENANCE SEPTEMBER 1988 M-1 1-ADA-21 (0'2 reactor coolant pump shaft seal thermal barrier differential pressure alarm). Instrument piping broken due to rubbing against structural member. The broken pipe was replaced with a new one and rerouted to prevent a reoccurance.

M-2 1-HV-AES-2 had an air leak through the charcoal bed which was greater than the technical specification limit due to a damaged damper gasket.

The damper gasket was replaced with a new one and the damper linkage adjusted accordingly.

M-3 1-SI-151 East and West (residual heat removal cooldown lines check valves). Found each valve had 1 broken retaining block stud which was removed and replaced with a new stud.

M-4 1-SI-161-L1 and 1-SI-161-L4 had studs made of questionable materials.

These studs were removed and replaced with new studs.

Indiana Michigan Power Company Cook Nuclear Plant P.O. Box 458 Bridgman, Ml 49106 616 465 5901 RF INDIANA NICHIGAN POWER U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 October 7, 1988 Gentlemen:

Pursuant to the requirements of Donald C. Cook Nuclear Plant Unit 1 Technical Specification 6.9.1.10, the attached Monthly Operating Report for the month of September 1988 is submitted.

Sincerely, Plant Manager WGS/jd cc: D. M. Williams, Jr.

M. P. Alexich C. A. Erikson J. J. Markowsky D. A. Timberlake R. F. Kroeger B. L. Jorgensen M. J. Parvin J. R. Sampson E. A. Smarrella Dolly Krieger T. R. Stephens D. S. Climer R. C. Callen D. W. Paul D. R. Mahn S. L. Mall INPO Records Center ANI Nuclear Engineering Department NRC Region III Nuclear Safety EPRI Analysis Center

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