ML20004F713

From kanterella
Jump to navigation Jump to search
Monthly Operating Repts for May 1981
ML20004F713
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 06/08/1981
From: Fay C
WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML20004F712 List:
References
NUDOCS 8106220211
Download: ML20004F713 (10)
v • d • e


Text

e.

UPERAIING' DATA REPORI

'j DOCKEI NO. 50-266 M

to DATE June 8,1981 O

g() ConPLETED BY C. U. FAY TELEPHONE 414 277 2811 OPERAllNG SIAIUS

l. UNil NAnE: ... BEACH NUCLEAR PLANT ' UNIT 1 . NOTES .
2. ALPURIING ..10D: nAf 1981 . .
3. IILENSEC lilERnAL POWER (nUI): 1518. . .
4. NAnEPLAfE RAIING (GROSS MUE): 523.8 . .

S. DESIGN ELEClkICAL RAllNG (NEI nUE)- 497. . .

6. nAninUn DEf'ENDA1LE CAPACIII (GROSS MUE): 519. . .

/. nAt! nun DEPENDADLE CAPAClif (NET nUE): 495. ........................

8. If CilANGES DECUR IN CAPAClif RATINGS (IIEnS NunBER 3 IHROUGH 7) SINCE LAST REPORI, GIVE REASONS:

NOI APPLILABLE

9. PUUER LEVEL 10 UHICH RESIRICIED, IF ANY (NET nUE): 390.0
10. REASONS FOR RESIRIC110NS, (If ANY): S$1K:#E43EMMENIE Power restriction is the result of a self-imposed reduction in core average temperature in an attempt to inhibit corrosion of steam generator tubes wi thin the tubesheet crevice. THIS MONTH fR TO DATE CUNULATIVE II. IluuRS IN REPURilNG PERIOD 744 3,623 92,639
12. HunBER OF Il0URS REACTOR WAS CRITICAL 744.0 3,620.0 77,054.8
13. REACIOR RESERVE SHUIDOUN HOURS  : 0.0 0.3 606.0
14. Il00RS GENERATOR ON LINE 744.0 3,614.0 74,750.9
15. UNil RESERVE SilGIDOUN HOURS 0.0 0.0 764.3
16. GRUSS IHERNAL ENERGf GENERATED (HUN) 902,360 4,354,019 103,192,463 1/. GRUSS ELECIRICAL ENERGY GENERATED inUH) 291,750 1,412,150 34,671,870
18. NEl ELECIRICAL ENERGf GENEPAIED (nUH) 276,017 1,339,271 33,006,557 17 UNil SLRVICE tAtluR 100.0 99.8 80.7
29. UNil AVAIL Ault ill I ACIOR 100.0 99.8 81.5 JI. UNil L APAtlll I AtluR (USillG nDC ffEI) 74.9 74.7 73.1
22. UNil CAPACllt IACIOR (USING DER NEll 74.6 74.4 71.7
21. Urlla FURCEU UUIAGE RAIL 0.0 0.2 3.2
24. bilulDUUNS Stil[DULED UVER NEXT 6 n0NIHS (TYPE, DATE, AND DURATION Of EACH):

Steam generau>r eddy current inspection July 4, 1981, expected to last two weeks.

Refueling - October 9,1981, expected to last seven weeks.

25. If SilulDOUN AT END OF REPORT PERIOD, ESllnATED DAIE OF STARTUP: NOT SHUIDOUN DAIA REPukIED AllD FACIORS CALCULATED AS REQUESIED IN NRC LETTER DATED SEPTEMBER 22, 1977

DOCKET NO. 50-265 .

UNIT NAME- Point Beach Unit 1 .

DATE June 8, 1981 COMPLETED BY C. W. Fay TELEPHONE 414/277-2811 AVERAGE DAILY UNIT POWER LEVEL MONTH May, 1981 AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL DAY MWe NET DAY MWe NET DAY MWe NET 1 370 11 371 21 371 2 370 12 371 22 374 3 375 13 371 23 374 4 366 14 369 24 373 5 370 15 .

372 25 373 6 371 16 370 26 373 7 370 17 354 27 373 8 372 18 372 28 372 9 371 19 371 29 372 10 372 20 372 30 373 31 373 AD-28A (1-77)

i l

-UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NOo 50-266 UNIT NAME Point Beach Unit 1 REPORT MONTH May, 1981 COMPLETED B . . Fay l TELEPHONE 414/277-2811

~

<n c w mo 4 32 "co It'.

o au eae 5t ae En ae No. Date o. gg m jgg Licensee Event gg gy Cause and Corrective Action N cm a- M e a sc emp Report No. m EU o

To Prevent Recurrence E e U 8

1 810517 S 0 11 4 N/A ZZ ZZZZZ Power reduction f rom 80% to 50%

power as directed by the Power Sys tem Supervisor.

2 810511 P 0 A 4 N/A ZZ ZZZZZL A control power fuse blew while ,

performing a nuclear instrumen-tation system check. This resulted in a turbine runback from 80% to 60% power.

1 4 F: Forced Reason: Method: Exhibit G-Instruc-S: Scheduled A- Equipment Failure (explain) l- Manual tions for Prepar-B- Maintenance or Test 2- Manur3. Scram ation of Data Entry C- Refueling 3- Automatic Scram Sheets for LER File D- Regulatory Restriction 4- Other (explain) (NUREG-0161)

E- Operacor Training & License Exam F- Administrative Exhibit I- Same AD-28B G- Operational Error (explain)

(01-78) Source H- Other (explain)

~

..> +

' NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE Docke t1 No. 50-266 . .

Unit Name Point Beach Unit 1 Date _.

June 8, 1981 Completed By C. W.' Fay Telephone 414/277-2811-Unit 1 operated at 390 MWe net throughout the period with three load reductions. On May 11, 1981, at 1630 hours0.0189 days <br />0.453 hours <br />0.0027 weeks <br />6.20215e-4 months <br />, while performing a nuclear instrument check on power range Channel 41, .a control power fuse , associated with the

- turbine runback circuit, blew, causing a turbine runback f rom 390 MWe ne t to 29 7 MWe ne t. Following replacement of

~ the fuse and ,a faulty diode in the turbine runback circuit, Unit 1 was returned to 390. MWe net ten minutes later. On May 16, 1991, at 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br />, load reduction was commenced to accommodate Technical Specification valve testing. At the request of the Power System Supervisor, load reduction was discontinued at ' 382 MWe net and Unit 1 was restored to 390 MWe net. On May 17, 1981, at 0 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> , load was reduced to 275 MWe net at the request of the Power System Supe rvisor. Unit 1 was restored to 390 MWe net at 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br />, on May 17, 1981.

Safety-related maintenance for the period included repairs to the control room emergency filtration system.

On May 15,1981, at.1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> , during Technical Specification testing, the control room emergency filtration system was found to be inoperable. The overall system flow rates were below the requirements of Technical Specification 15.3.12.2.C. The low system flow rate was due to an improperly balanced backdraft damper located downstream of the fan discharge of fan W14A, and an improperly adjusted balancing damper located just upstream of the system's roughing filter. The dampers were adjusted and the system was tested satis factorily. The control room emergency filtration system was returned to service at 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br />, on May 20, 1981. This occurrence is reportable in accordance with Technical Specification 15.6.9.2.B.2 as a 30 day report.

(Licensee Event Report 81-005/03L-0)

On May 13, 1981, the 3D Diesel generator would not close in on the bus curing the performance of the revised Operations refueling test (ORT) # 3, Safeguards Actuation with Loss of AC.- The test called for manually opening the generator breaker following automatic bus energization on loss ' of AC and then manually closing the breaker to assure that the system will resequence the bus loads. It was

'k v

Q e

determined that the performance of this portion of the revised '

ORT required additional specific breaker operating procedures to allow manual closing of the breaker. On.May 20, 1981, at 0615

~ hours, the 3D Diesel generator was retested satisfactorily using the modified procedure. This event was not a reportable occurrence, but has been documented as a-significant operating event for train-ing purposes.

9 e

OPERAllNG DATA REPORT DOCKET NO. 50-301 DATE June 8, 1981 COMPl.ETED BY C. U. FAY TELEPHONE 414 277 2811 UPERAllNG SIAIUS

1. UNil NAME: POINT BEACH NUCLEAR PLANT UNIT 2 . NOTES .
2. REPORTING PERIOD: MAY 1981 . .
3. LICENSED IllERNAL POWER (hWI): 1518. . .
4. tlAnEPLAIE RAllNG (GROSS MUE): 523.8 . .
5. DESIGN ELECTRICAL RATING (HET nuE): 497. . .
6. MAXInun DEPENDABLE CAPACITY (GROSS MWE): 519. . .
7. MAXIMUN DEPENDABLE CAPACITY (HET nuE): 495. ........................
8. IF CHANGES DCCUR IN CAPACITY RAllNGS (ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS:.

NOI APPLtCABLE

9. POWER LEVEL 10 WillCH RESTRICIED, IF ANY (HET nuE): none
10. REASONS FOR RESIR!Cil0NS, (IF ANY): SEE ATTACHnENIS THIS HONTil YR 10 DATE CUMULATIVE II. iluuks IN REPokilf0 PERIOD 144 3,623 77,424
12. NUnt:LR Uf Il0URS RE ACIOR WAS CRIll. 242.9 2.791.5 69,341.5
13. REAtluk RESERVE SilulD0uti ll00RS 0.0 0.0 186.3
14. IluuRS GENERAL 0R Ort LINE 175.7 2,721.2 68,019.7 gag , Ib. UtilI RESERVE SilUIDOWN ll0URS 3.3 6.3 130.2 8
14. GROSS lilERNAL ENERGY GErlERATFD (Mull) 186,873 3,982,762 92;'72,508 Cl II ,* 1/. URuss ELECIRICAt ENERGY GENf%AIED (nuH) 61,520 1,345,960 31,469,810

(""") 18. NEl ELEClRICAL ENERGY GENERAIED (MUH) 55,153 1,282,937 29,946,358 w;g;') IV. UNil SERVICE FACTUR 23.6 75.1 87.9

20. Utill AVAIL ABILI TY F ACTOR 24.1 75.3 88.0
21. UNil CAPACIlY FACIOR (USING MDC NET) 15.0 71.5 78.8
22. UNil CAPACif f F ACl0h 4JSING DER NET) 14.9 71.2 77.8 EE E 23. Utill FORCED OUI AGF RATE 0.0 0.0 1.0
24. SilulDOWNS SCllEDULED DVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):

CEE5I NutlE

=

25. IF SilulDOUN Al END OF REPORT PERIOD, ESilHATED DATE OF STARTUP: Ettx21ttile00tk June 1, 1981 P

t---

DAI A htPURIED AtID F ACIORS CALCULAIED AS REQUESTED IN NRC LETTER DATED SEPTEMBER 22, 1977

- - - - - - _ ~ . - . -

DOCKET NO. 50-301 .

UNIT NAME Point' Beach Unit 2 .

DATE June 8, 19 81 ,

'i' COMPLETED-BY C. W. Fay ,

TC'EPHONE 414/277-2811 AVERAGE DAILY UNIT POWER LEVEL MONTH ,

May, 1981 AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL DAY MWe NET DAY MWe NET DAY MWe NET 1 - 1 11 -2 21 -11 2 -2 12 -2 22 35 3 -2 13 - 2 2 'i 229 4 -2 14 - 3 24 348 5 -2 15 .

- 3 25 394 6 ,2 16 - 8 26 464 7 -2 17 -13 27 480 8 -2 18 -11 28 463 9 -2 19 -10 29 -6 4

10 -2 20 -10 30 -8 31 - 9 AD-28A (1-77)

UNIT SHUTDOWl53 AND POWER REDUCTIONS DOCKET NO. 50-301 UNIT NAME Point Beach Unit 2 REPORT MONTH May, 1981 COMPLETED B C . hay 414/277-2811

~

TELEPHONE m

c w mo v e

Mau "ao eoe 5t  %

4v ce No. Date a eg g jgy Licensee Event gg gy Cause and Corrective Action N cm e 4x Report No. m eo To Prevent Recurrence Q~ M gmg g 8

1 810417 S 501.1 C 1 N/A ZZ 'ZZZZZ The unit was shutdown for its annual ref ueling outage. Unit 2

. was taken critical on May 21, 1981, at 2106 hours0.0244 days <br />0.585 hours <br />0.00348 weeks <br />8.01333e-4 months <br /> and placed on line 0902 hours0.0104 days <br />0.251 hours <br />0.00149 weeks <br />3.43211e-4 months <br /> on May 22, 1981.

2 810529 'S 65.5 E 1 N/A ZZ 'ZZZZZ The unit was shutdown for license exam startups. Unit 2 was taken critical at 2254 hours0.0261 days <br />0.626 hours <br />0.00373 weeks <br />8.57647e-4 months <br /> on May 31, 1981, and placed on line at 0102 hours0.00118 days <br />0.0283 hours <br />1.686508e-4 weeks <br />3.8811e-5 months <br /> on June 1, 1981.

l 1 4 F: 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 Entry C- Refueling 3- Automatic Scram Sheets for LER File i D- Regulatory Restriction 4- Other (explain) (NUREG-0161)'

E- Operator Training & License Exam F- Administrative 5

AD-28B Exhibit I- Same G- Operational Error (explain) Source (01-78) H- Other (explain)

n - -

14" NARRATIVE

SUMMARY

OF' OPERATING EXPERIENCE Docket -No.- 301 m-Unit Name Point Beach Unit 2

- Date June 8, 1981 Completed By 'C. W. Fay

' Telephone 414/277-2811 Unit 2 Refueling was completed on May 21, 1981 after a-34 day outage.

Refueling work continued during the shutdown period .

of May. ' Sludge lancing of "A" and "B" steam generators commenced on May 2, 1981, and was completed on May 5, 1981, after a short delay due to a service air compressor problem.

The reactor vessel head was lifted to 1230 hours0.0142 days <br />0.342 hours <br />0.00203 weeks <br />4.68015e-4 months <br /> on

' May 1, 1981, followed by the commencement of fuel movement at 0812 hours0.0094 days <br />0.226 hours <br />0.00134 weeks <br />3.08966e-4 months <br /> on May 4, 1981. During fuel shuffling operations, at 0015 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br />, on May 5, 1981, while attempting to engage fuel assembly H-78 in core location J-9, the gripper partially engaged the fuel assembly above the nozzle plate aad below the springs.

Attempts to disengage and reengage-the assembly were unsuccessful.

At 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br /> on May 5, 1981, adequate engagement of all four springs was verified and the asembly was moved to the upender from the core. - The gripper was disengaged from the assembly springs at 1800 hours0.0208 days <br />0.5 hours <br />0.00298 weeks <br />6.849e-4 months <br />, on May 5, 1981, and the assembly was

' inspected for evidence of damage. No damage was noted during the inspection and fuel assembly H-78'was returned to its new core location. Fuel movement was completed at 2130 hours0.0247 days <br />0.592 hours <br />0.00352 weeks <br />8.10465e-4 months <br /> on May 7, 1981.

On May 8, 1981, the reactor vessel upper internals were_ installed, the control rods were latched, and the reactor vessel head was installed. The reactor vessel studs were in-stalled on May 11, 1981, and tensioned on May 12, 1981. On May 14, 1981, the reactor coolant system fill and vent was completed.

Heatup of Unit 2 reactor coolant system commenced on May 16, 1981, at 2327 hours0.0269 days <br />0.646 hours <br />0.00385 weeks <br />8.854235e-4 months <br />. Unit 2 was taken critical at 2106 hours0.0244 days <br />0.585 hours <br />0.00348 weeks <br />8.01333e-4 months <br />, on May 21, 1981, followed by steam line heatup commencing at 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> the same day. Unit 2 was placed on line at 0902 hours0.0104 days <br />0.251 hours <br />0.00149 weeks <br />3.43211e-4 months <br />'and loaded to 99 MWe net at 1050 hours0.0122 days <br />0.292 hours <br />0.00174 weeks <br />3.99525e-4 months <br />, on May 22, 1981.

At 2232 hours0.0258 days <br />0.62 hours <br />0.00369 weeks <br />8.49276e-4 months <br />, on May 22, 1981, Unit 2 was taken off line for turbine overspeed trip testing. Following satisfactory overspeed trip testing, Unit 2 was placed on line at 0448 hours0.00519 days <br />0.124 hours <br />7.407407e-4 weeks <br />1.70464e-4 months <br />, on May 23, 1981, and it was at full load at 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> on May 26, 1981.

I l

Unit 2 operated at 490 MWe net until 2321 hours0.0269 days <br />0.645 hours <br />0.00384 weeks <br />8.831405e-4 months <br /> .on-May 28, 1981, at which time a load reduction was commenced for a unit shutdown to support NRC licensing exams and

' repair of leaking uurbine stop valves. The unit was off line at 0133 hours0.00154 days <br />0.0369 hours <br />2.199074e-4 weeks <br />5.06065e-5 months <br /> on May 29, 1981. Following conpletion of -

the NRC licensing exams and repair of the turbine stop valves, the unit was placed on line at 0102 hours0.00118 days <br />0.0283 hours <br />1.686508e-4 weeks <br />3.8811e-5 months <br /> and returned to full load at 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br /> on June 1, 1981.

During normal ~ operations at 1250 hours0.0145 days <br />0.347 hours <br />0.00207 weeks <br />4.75625e-4 months <br />, on May 26, 1981, *

-attempts to remotely cycle "A" steam generator blowdown sample -

isolation valve, 2CV-20 8 3, were ' unsuccess ful. ~

Failure of 2CV-2083, a containment isolation valve, to close when .

actuated is a technical violation of . containment integrity as de fined in Technical Specification 15.1.d. Failure of 2CV-2083 to close upon actuation was due to excessive stem to packing

-friction resulting from dried out packing. The packing was-adjusted, the stem was lubricated, and the valve was tested satisfactorily and returned to operation at 1330 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.06065e-4 months <br />, on May 26, 1981. - This occurrence is reportable as a 14 day report in accordance with Technical Specification '15.6.9.2. A.2.

(Licensee Event . Report No. 81-00 3/0 lT-0)

On May 29, 1981, at 0256 hours0.00296 days <br />0.0711 hours <br />4.232804e-4 weeks <br />9.7408e-5 months <br />, "B". steam generator main steam stop, 2CV-2017, failed to shut upon remote manual actuation during a routine' shutdown. Immediate investigation revealed the two vent valves for the - air operator of 2CV-2017 failed to open, preventing the closure of 2CV-2017. Vent valve 2SV-2017C was tripped and 2CV-2017 shut .immediately. Both vent valves, 2SV-2017C and 2SV2017D, and' main s team stop valve,- 2CV-2017, were tested several times prior .to returning-

, to power. Both vent valves were replaced on June 1, 1981, due to . sluggish operation. This occurrence is reportable as a 14 day report in accordance with' Technical Specification 15.6.9.2.A.5. (Licensee Event Report No. 81-004/0lT-0)

~

, _ - - - ,-, , - , ,

Retrieved from "https://kanterella.com/w/index.php?title=ML20004F713&oldid=2339142"