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j OPERATItr., DATA REPORT

s DOCKET NO. 50-266=4o DATE June 5, 19804N COMPLETED DY C. h. FAY41

TELEPilOt4E 414 277 2811h OPERATIt4G STATUS

. . . . . . . . . . . . . . . . . . . . . . . .1. UNIT IJAME: POINT tiEACil NUCLEAR PLANT UNIT 1 NOTES. .

2. REPORTING PERIOD: MAY 1980 . .

3. LICEIJSED TilERMAL POWER (MWTI: 1518. . .

4. tJAMEPLATE RATItJG (GROSS MWE): 523.8 . .

S. DESIGN ELECTRICAL RATING (NET MWE): 497. . .

6. MAXIMUM DEPLt1DAl!LE CAPACITY (GROSS MWE): 519 . .

7. MAXIMUM DEPENDA!iLE CAPACITY (NET MWE): 495. . . . . . . . . . . . . . . . . . . . . . . . .8. IF CllAtlGES OCCUR IN CAPACITY RATINGS (ITEMS NUMi1ER 3 TilROUOli 7) SINCE LAST REPORT, GIVE REASOlJS:

NOT APILICA11LE9. POWER LEVEL TO hilICil RESTRICTEDe IF ANY (NET MWE): 390 0

10 REASONS FOR RESTRICTIONSe (IF ANY): SEExWRINCmMR)dIR Power restriction is the result of a self-imposedreduction in core average temperature in an attempt to inhibit corrosion of steam generator tubes within thetubesheet crevice. TilIS MONTil YR TO DATE COMULA1IVE

11. IlOURS Ill HEPORTING PERIOD 744 3e647 83,67912. NUMiiER OF fiOURS PEACTOR WAS CRITICAL 744 0 2e898.5 69,415.0

13. REACTOR i<ESLRVE SilOTDOhN llOURS 00 18.8 601.014. IlOURS GENERATOR ON LIl4E 744.0 2e755.5 67e149.510. UNIT DESERVE SiluTDOhtJll0URS 00 151.5 753.916. GROSS TilERMAL E11ERGY GENER ATED (MWil) 901,815 3,314e924 94e067,71917. GROSL ELECTRICAL ENERGY GENERATED (Mwil) 294e140 1,081,600 31,715,43018. NET ELLCTRICAL ENLRGY GENERATED (MWil) 278e216 1,021e793 30e211e97119. UNIT SERVICE FACTOR 100.0 75.6 80.120. UNIT AVAIL AllILITY F ACTOR 100.0 79.7 81.021. UNIT CAPACITY FACTOk (USING MDC NET) 75.S 56.6 74.02.1. UNIT CAPACITY FACTOR (USItJG DER NET) 75 2 56.4 72.523. UNIT FORCED OUTAGE RATE 00 0.0 3.424. SilVTDOWNS SCllEDULED OVER NEXT 6 Mol4Tels (TYPEe DATEe AND DURATIOl4 OF EACil):

Unit scheduled to shutdown July 25, ''380, for ten days to perform steam generator leak testingand eddy current inspection.

25. IF Silu1DOhu AT EllD OF REPORT PERIODe ESTIMATED l) ATE OF STAbTUP: NOT SiluTDOLl4

DATA REPORTED AllD FACTOFS CALCULATED AS PEOUESTED IN NRC LETTEk DATED SEPTEMilLF 22e 1977

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OPERATING DATA REPORTDOCKET NO. 50-301

DATE June 5, 1980

COMPLETED DY C. W. FAY

TELEPHONE 414 277 2811OPERATING STATUS

. . . . . . . . . . . . . . . . . . . . . . . .1. UNIT NAME: POINT DEACH NUCLEAR PLANT UNIT 2 . NOTES .

2. REPORTING PERIOD: MAY 1980 . .

3. LICENSED THERMAL POWER (MWT): 1518. . .

4. NAMEPLATE RATING (GROSS MWE): 523.8 . .

5. DESIGN ELECTRICAL RATING (NET MWE): 497. . .

6. MAXIMUM DEPENDADLE CAPACITY (GROSS MWE): 519. . .

7. MAXIMUM DEPENDABLE CAPACITY (NET MWE): 495. . . . . . . . . . . . . . . . . . . . . . . . .O. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORTe GIVE REASONS:

NOT APPLICABLE9. POWER LEVEL TO WHICH RESTRICTEDr.IF ANY (NET MWE): NOT APPLICABLE

10. REASONS FOR RESTRICTIONSe (IF ANY): NOT APPLICABLE

THIS MONTH YR TO DATE CUMULATIVE

11. HOURS IN REPORTING PERIOD 744 3e647 68e66412. NUMBER OF HOURS REACTOR WAS CRITICAL 458.7 2e546.9 61,443.8

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13. REACTOR RESERVE SHUTDOWN HOURS 98 19.2 185.314. HOURS GENERATOR ON LINE 407.7 2e480.7 60e207.715. UNIT RESERVE SHUTDOWN HOURS 10 4 13.5 119 916. GROSS THERMAL ENERGY GENERATED (MWH) 539,505 3,566,569 81e219,10517. GROSS ELECTRICAL ENERGY GENERATED (MWH) 182e120 le186e790 27,548,13018. NET ELECTRICAL ENERGY GENERATED (MWH) 170e733 le127e626 26e202,75319. UNIT SERVICE FACTOR 54.8 68.0 87.720. UNIT AVAILA91LITY FACTOR 56 2 68.4 87.921. UNIT CAPACITY FACTOR (USING MDC NET) 46 4 62.5 77.822. UNIT CAPACITY FACTOR (USING DER NET) 46 2 62.2 75.823. UNIT FORCED OUTAGE RATE 0.0 12.4 2024. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPEe DATEe AND DURATION OF EACH):

NONF,

25. IF SHUTDOWN AT L:7 0F REPORT PERIODr ESTIMATED DATE OF STARTUP: NOT SHUTDOhN

DATA REPORTED AND FACTORS CALCULATED AS REQUESTED IN NRC LETTER DATED SEPTEMUEk 22e 1977

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DOCKET NO. 50-266.

UNIT NAME Point Beach Unit 1

DATE June 5, 1980.

COMPLETED BY C. W. Pav

TELEPHONE 414/277-2811

AVERAGE DAILY UNIT POWER LEVEL

5 MONTH May, 1980

AVERAGE AVERAGE AVERAGEDAILY DAILY DAILY

POWER LEVEL POWER LEVEL POWER LE* ELDAY MWe NET DAY MWe NET DAY MWe NET

1 377 11 367 21 374

2 374 12 374 22 373

3 375 13 37g 23 376'

i 4 374 14 17a 24 371

5 375 15 373 25 373

6 374 16 377 26 373

7 375 17 370 27 374

8 373 18 375 28 373

9 376 19 372 29 374

10 375 20 375 30 375

31 374

AD-28A(1-77)

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DOCKET NO. 50-301.

UNIT NAME Point Deach Unit 2

DATE June 5, 1980

COMPLETED BY C. W. Fay

TELEPHONE 414/277-2811

AVERAGE DAILY UNIT POWER LEVEL

MONTH May, 1980

AVERAGE AVERAGE AVERAGEDAILY DAILY DAILY

POWER LEVEL POWER LEVEL POWER LEVELDAY MWe NET DAY MWe NET DAY MWe NET

1 - 3 11 - 11 21 492

2 - 2 12 - in 22 483

3- - 2 13 - 12 23 431

4 - 4 14 21 24 287

5 - 4 15 116 25 466

6 - 2 16 346 26 467

7 - 9 17 361 27 474

8 - 11 18 167 28 490

9 - 7 19 42g 29 493

10 - 8 20 492 30 493

31 494

AD-28A(1-77)

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-266UNIT NAME Point Beach Unit 1

REPORT MONTH May, 1980haCOMPLETE 1,

TELEPHONE 414/277-2811

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C W tn o #

a2 3R Ve in"a Ce au o co o e

a 'g g'g Cause and Corrective Actiona ce

No. Date D. gg jgg Licensee Eventa gN :s m e v .c Report No. m eo To Prevent Recurrence

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! 1 3 4F: Forced Reason: Method: Exhibit G-Instruc-1 S: Scheduled A- Equipment Failure (explain) 1- Manual tions for Prepar-

B- Maintenance or Test 2- Manual Scram ation of Data EntryC- Refueling 3- Automatic Scram Sheets for LER File,1

D- Regulatory Restriction 4- Other (explain) (NUREG-0161)| E- Operator Training & License ExamF- Administrative 5

i AD-28B Exhibit I- SameG- Operational Error (explain) Source(01-78) 11- Other (explain)

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-301UNIT NAME Point Beach Unit 2

DATE June 5, 1980REPORT MONTH May, 1980COMPLETED BY C. W. Fay

TELEPHONE 414/277-2811

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8- o ?B en %n2* 8 msM Be~ *

e ce'No. Date g gg jgg Licensee Event gg gy Cause and Corrective Actiona

e om e v ;c Report No. m eu To Prevent RecurrenceO- M gmg g

82 800411 S 326.6 C 1 N/A N/A N/A

3 800515 S 2.6 B 1, N/A HA TURBIT Turbine overspeed trip testing.

4 800523 S 7.2 B 1 N/A HB VALVE) Moisture separator reheater dumpvalves were clogged causing levelcontrol problems. Valves werecleaned during the shutdown.

1 3F: Forced Reason: Method: Exhibit G-Instruc-S: Scheduled A- Equipment Failure (explain) 1- Manual tions for Prepar-

B- Maintenance or Test 2- Manual Scram ation of Data EntryC- Refueling 3- Automatic Scram Sheets for LER FileD- Regulatory Restriction 4- Other (explain) (NUREG-0161)E- Operator Training & License Exam*

F- Administrative 5AD-28B Exhibit I- Same

G- Operational Error (explain) Source(01-78) H- Other (explain)

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NARRATIVE SUMMARY OF OPERATING EXPERIENCE

' Docket No. 50-266Unit Name Point Beach Unit 1Date June 5, 1980Completed By C. W. FayTelephone 414-277-2811

Unit.1 operated at 375 MWe net throughout the periodwith one load reduction. The-load was reduced to 285 MNefor five hours on May 11, 1980 for turbine stop valve testing.

No other major safety-related maintenance was performeddurir 7 the period.

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NARRATIVE SUMMARY OF OPERATING EXPERIENCE

50-301Docket No. Point Beach Unit 2Unit Name June 5,-1980Data C. W. FayCompleted By 414-277-2811Telephone

Inspection of the Unit 2 low pressure turbine rotorsindications were found inwas completed. Thirty-five (35) l. Thethe L-3 and L-4 blade roots and disc steeples of LP35 indications consisted of five blade root and 30 discThe five blades have been replacedhave beensteeple indications.and all except one of the' disc steeple indicationsThe final disc steepleremoved by polishing and grinding.Nine indications were found in the L-1, L-3, and L-4 b a eindications were repaired by cutting off the top serration.ld

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The nine indicationsroots and disc steeples of LP2. included four blade root and five disc steeple indications.l d andTo repair the indications, two blades have been rep acedisc steeple

the other two blade indications, along with all theindications, have been removed by polishing and grinding.bines

Numerous small tendon rivet cracks in both low pressure turThe inspection

have also been removed by polishing and grinding.of the LPl spindle identified a 0.120" deep indicationThe indication has ain the

3 disc keyway apex on the governor end. h safety factor

calculated lifetime-to-critical size of 7.7 years witAn indication below the equipmentNo.

based on initial interpretation. was also identified indefinition capability (less than .020")No indications werethe generator end.the No. 3 disc 1

identified during the LP2 spindle inspection.~

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Significant events prior to going on line were steamcompleted on May 9,generator crevice cleaning (eight cycles)and heatup of the reactor coolant system on

inservice leak testing with satisfactory resultsinitial Unit 2 criticality at 4:59 p.m.1980; fill, vent,May 10, 1980;

and completion of BOL physics testing withSafety injection actuation11, 1980;completed on May

on.May 12, 1980; 1980. been satis-training startups on May 13, test.and all other operational refueling tests havefactorily completed.

The unit was reduced to 97% of full power on May 22,l

1980 to administratively control FAH enthalpy rise hot channeThe unit wasfactors within Technical Specification limits.

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i betweentaken.off line and remained in hot shut-down condit on1980 for moisture separator12:08 a.m. to 7:21 a.m. on May 23,the load was kept at 95% full power

reheater drain valve repairs; in order to limit the a oveb |

27, 1980

mentioned hot channel factors as a result of the shut-down.until-3:00 p.m. on May 6ing '

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Four moisture separator reheater dump valves with corresponisolation valves and the"C" drain valve were cleancd during-

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the shut-down. ]

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Unit 2 Nos. 2 and 4 condenser waterboxes weretested for leakage by a freon detection method. The Nos. 1 and 3condenser waterboxes were checked previously during unit shut-down.

The pressurizer access modification and the installationof the orifice flanges for auxiliary feedwater flow indicationwere completed.

The "C" charging pump motor was reassembled, theatmospheric steam dump valves were repaired, and the reactorcoolant drain tank "A" discharge pump check valves were replaced.

Work continues on IE Bulletin Nos. 79-02, anchor boltinspection, and 79-14, seismic analysis for as-built safety--

related piping systems, with balance of Unit 2 containment workcompleted.

No other major safety-related maintenance was performedduring the period.

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