Text

Monthly Operating Repts for Dec 1980
	ML19340E717
Person / Time
Site:	Point Beach
Issue date:	01/07/1981
From:	Fay C; WISCONSIN ELECTRIC POWER CO.
To:	;
Shared Package
ML19340E716	List: ML19340E715; ML19340E717;
References
	NUDOCS 8101150519
	Download: ML19340E717 (10)
	v • d • e

I OhER TING DATA REPORT Wd DOCVET tin. 50-266 o

W DATE January 7, 1981 o

N COMPLETED BY C. W. F Y TELEFilONE 414 277 2811

Q OPERATING STATUS 1". UNIT NAME:

PQiNT BEACH NUCLE R PL NT blJiT 1 hNOTES f.

2 REPORTING PERIOD:_ DECEMBEP 1980

3. LICFUSED THFRMAL POWER (MMT):

1518, 4,. NAIAEPLATE RATING (CP.OSS MWE):

523.8 5

DESIGN ELFCTRICAL RATING.(llET MWE):

497.

6.'. MAX {MIK1 DEPENDAOLE CAPACITY (GROSS MWE):SJ9.

495.

7,. If AXIt/ti!1 DEPFNDADLE C APACITY. (NET.MWE) : _(ITEMS N11MDFR 3 THf Ol'Gli 71 SINCE I AST P 8.

IF CilANGFS.OCCliR.IH CAPACITY RATINGS NOT APPLICADLE 9,. POtJFP LEYUI TO WiliCil,RESTPICTEDe..IF ANY (['FT MWF) :

390.0 Power restriction is the result of a self-imposed

10. REASONC FOR !?FSTRICT101JSe (IF AtlYl: XXXXXXMXXfDUEXMXKX reduction in core average temperature in an attempt to inhibit corrosion of steam generator tubes within th_e TilIS t'ONTil YR To DATE ClMilLATIVE tubesheet crevice.

li', HQbRS iN PEbORTiNG [EhiOD.

74's,

8e78f4, 89,016, 57 9 6e918 3 73 43rg.a 12,. NtlMDEP OF HOliRS PEACTOP WAS, CRITICAL 3,6 23,5 605,7 13,. PFACTOP I'FSEl;VF SittlTOOWN llotJPS 34,'t 6e742,9 71e136,9 14, IIGl.'RS GENFR ATOR ON LIllE 9.1 161.9 764.3 15,. l' NIT RFSFHVE SHUTDOWN HollPS, 16e350 8e085e649 98,83 te 44n 16 GPOSC TilEPM At,.ENFHGY GCtr'P ATED (MWH) 17 GPOSC ELFCTRICAl. EtVRGY CFrICPATFD (MWH) 4e690 2e625e970 33e259e720

1e623, 2e477e108, 31e6i7e285, 18, IJFT FLi'CT13IC AI,_FNEPGY GENFP ATro (MWH) 4,6 76,8 79,9 19,tiNIT SFPVICF., FACTOR _,

5,. 8 78,.6 80,.3 20,. 1,' HIT AV AIL /yDILTTY F ACTOR.

21, UNIT CAEPCITY FACTOR (USING MDC NET) 0,4 57,0 73,0 0,4 56,7 71,6 2',t.if1IT CAPACITY, FACTOR _(tJSING DER NET) 0,0_

0.6 3.3 23 IINTT FORCED _ OUTAGE RATF

24. Sitt.lTDOWNS ECilFDllLED. OVFR NEXT 6 MONTils (TYPEe DATEe AND lil'P ATIOli 0F EAcil):

25". iF SHbTDOWN i Et3D OF RFPORT bFRiOD, rSTiMATFD D TF OF STED115:

t!OT clitiTD01r:t' D th OFh0PiFD ENn F EiOAS bEfibi iND S R'FObi'cTc0 TtJ NPE I NT'e rs' nITrn ci-6Ti lenrs' 2? e 1977 9

OhEDATitJG DATA RFPOrtT DATE January 7, 1981 O

COMPLFTED DY C. W. FY TELEPHONE 414 277 2811 OEERATiNG STATUS 1[. UNIT NAME:. POINT DEACH NbCLE R hLANTUfliT 2

[. NOTES h

2, REPORTING PERIOD:

DECrMDER 1980 3, LICEUSED THERP.4AL POWER (MFT):

1518,

4. NAMEPLATE RATING (CROSS MWE):

523.8 5, DESIGN ELrCTPIC AL RATING. (!!ET MWE):

497.

6,.

MAX]!41,lM DEPFNDABLE CAP ACITY (GROsc-MWE):

5)9.

7 SAXIMil" DEPFilDADLC CAP $ CITY _(flET,t4WE):. 495.

3............,

8. IF CllANGES_0CCUP IN CAPACITY RATINGS (ITEMS NtHOER 3 THrOl'Gif 7) STtJCE L AST PEPOrTe GIVF Rr

_ NOT APPLICABl,E 9, POk,FR LFV.'L TO WHICil.RESTPICTEDe_IF AtlY (t'E T 13 Wl' ) 2 tlOT ILPrLIC Ant F

~

10. PEASOttc FOP HESTr. ICTIOt1S e (IF AtlY) :

t!OT APPLICABl.E THiS MONTH kP TO D TE ClJMt*LhTiV'E 11[.HObRSiN.PEPORTiNG_hFRiOD, 74's, Be7A4,_

73,801, 12, NtWDER OF HOUPS HEACTOP WAS, CRITICAL 74's 0 7e653,1 66,5S0,0 0n 20,P 186,3 13 RFACTOR I-ESEf?VF SHUTOOWN HOllRS 7438 0 7,571,.5 65 248 5 i t+. IlOi, FPS CFilFR ATOP ON LIllE 0.0 17.5 123.9 15 UNIT PFSFRVE SHUTDOWil HOURS

_1, 1 1 4 e 's 3 2 11e137,210 88 739 746 16, GPOSc THFPMAL ENFRGY GEttrP ATc0 (MWill 17 GPOSc FLFCTRICAL FN'~RGY CFICPATFD (MWH) 378e'610 3e762e510 30e123eP50 18,t)FT ELFCTSICAL,ENrRGY GrNFRATFD (MWil)

362e617, 3e588e294, 20e653e421, 10!!,0 86.2 81.5 19, I,fMIT SERVICF,FACTOf?

10ll ')

86,.4 83.6 20 UN}T AVOILi>DTIYIY FACTOR.

98 5 82,5 79 2

21. UNIT CAeArITY FACTOP (llSIt1G MDC flFT) 22, UNIT CAPACITY, FACTOR (USING DER NFT) 98.1 82,2 78,1 0.0, 4.7 1.9

23. IltliT FORCED OllTAGE PATF

24. SHilTDOWNS TCilFOULFO OVi:R NEXT 6 Mot!THS (TYPre DATFe At!D flip ATIOtl ^F FACll) :

Refueling shutdown April 17, 1981, expected to last approximately five weeks.

25". EF SHbTDOWN AT END OF RFhnt?T hPI'iOD, FSTiMh7rD 05TI: OF cTEI"il5:

tiOT EHI e DOrt!

D iA PFPOPTFD ENO F Ei~ obr hEtEbl5TFD de D'FOlf'~cT'D itJIEb IFi,r nivrn cifis tap,'T 22, 59i7

~

SUPPLEMENT TO MONTHLY REPORT FOR Deceeer 1980 REFUELING INFORMATION REOUEST i

In accordance with our letter dated February 21, 1978, which provided certain refueling infomation, we are providing the following update to that refueling infonnation:

(NC = No Change) a) Next Scheduled Refueling Shutdown:

Unit 1:

10/9/81 Unit 2:

4/17/81 b) Scheduled Date.for Restart:

Unit 1:

1/1/82 Unit 2:

5/22/81 c) License Anend:nent Required / Staff 10 CFR 50.59 Review Coupleted:

Unit 1:

None Anticipated Unit 2:

None Anticipated d) Scheduled Date for Submitting Unit 1:

Aucust 1981 Supporting Information:

Unit 2,:

February 1931 Unit 1:

Note 1 e) Inportant Licensing Considerations:,

Unit 2:

None f) Nucber of Fuel Assentlies in Storage Pool:

284 g) Other:

NOTE 1: Possibility of Steam Generator Tube Sleeving Program During Next Refueling Outage.

DOCKET NO.

50-266 UNIT NAME Point nonch Unit 1 1

~

]

DATE January 7, 1981 COMPLETED BY C. W.

Fay i

TELEPHONE 414/277-2811 AVERAGE DAILY UNIT POWER LEVEL MONTH December, 1980 AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL DAY MWe NET DAY MWe NET DAY MWe NET l

1

-2 11

-2 21 2

22 4

2

-2 12 2

3

-2 13 2

23 7

4

-2 14

-2 24 7

5

-1 15

-2 25 g

6

-2 16

-2 26

- lo 7

-1 17

-2 27

- 11 j

8

-2 18

-2 28 g

9

-1 19

-2 29 a

10

-2 20

-2 30 28 31 1 36 AD-28A (1-77)

DOCKET NO.

50-301 UNIT NAME Point Beach Unit 2 DATE January 7, 1981 COMPLETED BY C. W.

Fay TELEPHONE 414/277-2811 AVERAGE DAILY UNIT POWER LEVEL MONTH Decembe r, 1980 AVERAGE AVERAGE AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL DAY MWe NET DAY MWe NET DAY MWe NET POWER LEVEL 21 485 11 492 1

492 22 488 12 488 2

491 23 488 13 490 3

463 24 488 14 490 4

491 25 486 15 491 5

489 26 485 16 489 6

491 27 487 17 490 7

491 28 488 18 491 8

474 29 487 19 486 9

489 30 485 10 490 20 487 31 488 AD-28A (1-77)

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-266 i

UNIT NAME Point Beach Unit 1 i

DATE January 7, 1981 l

REPORT MONTH Decembe r, 1980 COMPLETED BY C.

W.

Fay TELEPHONE 414/277-2811,,]

i

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m 4

a W tD o M

.o a N

oa4 Ev c

re a c

~4 o ee en 1

.-4o eu o

'o e as a 'o ae gg g

jjg Licensee Event y

o'g Cause and Corrective Action No.

Date O.

N

s :c -

e v.c Report No.

u)

Eo To Prevent Recurrence Q-84 e U2 A o

2:

3 U

i 8

7 801129 S

709.6 C

4 N/A ZZ

?ZZZZZ The unit was off line for its annual refueling outage.

Major work items performed during the outage included inservice inspection of the j

steam generators, overhaul of the "A"

reactor coolant pump, steam 1,

generator feedline and feed nozzle i

inspection, inspection of turbine J

generator LPl and LP2, and numerous 1

l TMI-related modifications.

The unit I

returned to service at 1333 hours0.0154 days 0.37 hours 0.0022 weeks 5.072065e-4 months on December 30, 1980.

1 e

g 1

s f

1 3

4 F: Forced Reason:

Method:

Exhibit G-Instruc-S: Scheduled A-Equipment Failure (explain) l-Manual tions for Prepar-B-Maintenance or Test 2-Manual Scram at.'.on of Data Entr C-Refueling 3-Automatic Scram Shi.'_s for LER Filt D-Regulatory Restriction 4-Other (explain)

(NvREG-0161)

E-Operator Training & License Exam F-Administrative 5

AD-28B Exhibit I-Same G-Operational Error (explain)

Source (01-78) 11-Other (explain)

. -.x. u.. _.

. _ _ _ -. ~. --

DOCKET NO. 50-301 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME Point Beach Unit 2 REPORT MONTH December, 1980 COMPLETED C

1 Fa TELEPIIONE 414/277-2811 "u

c W tD o 4

37 "c

St P.

En e

au o

mee em no No.

Date g

gg g

jgy Licensee Event y

gy Cause and Corrective Actiun f(

s m o

v.c Report No.

u) eu To Prevent Recurrence Q~

K o

Em u2 >a o

g O

9 e

1 3

4 F: Forced Reason:

Method:

Exhibit G-Instruc-S: Scheduled A-Equipment Failure (e;;;9ain) l-Manual tions for Prepar-B-Maintenance or Test 2-Manual Scram ation of Data Entr C-Refueling 3-Automatic Scram Sheets for LER Filt D-Regulatory Restriction 4-Other (explain)

(NUREG-0161)

E-Operator Training & License Exam F-Administrative 5 Exhibit I-Same AD-28B G-Operational Error (explain)

Source (01-78) 11-Other (explain) l

~~

~

i NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE Docket No.

50-266 Unit Name Point Beach Unit 1

.e Date January 7, 1981 Completed By C. W. Fay 43 Telephone 414/277-2811 Unit 1 Refueling 8 outage _was completed on December 30, 1980 -fter a 34-day outage.

Following successful completion of turbine overspeed tests on December 31, 1980, Unit 1 power was increased at 3%

per hour to allow new fuel conditioning.

Due to the slow increase in power, full power (80%) was not achieved until January 2, 1981.

During the~ outage, a 2000 psi differential pressure primary-to-secondary leak check and a subsequent 800 psid secondary-to-primary leak check were performed on both steam generators.

Visual inspection during the secondary-to-primary leak check determined that two " wet" tube ends were present in each steam generator.

The eddy current inspection program consisted of the examination of 100% of the hot leg tubes in both steam generators through the first tube support plate.

At least 3% of the tubes, including all previously degraded tubes on the cold leg side, were inspected over their entire length.

Three tubes in the "A" steam generator and five tubes in the "B"

steam generator f

were identified as having crevice d'efects which exceeded the 40%

These tubes were tube plugging limit of the Technical Specifications.

removed from service with mechanical plugs.

In addition, five tubes in the "A" steam generator and two tubes in the "B"

steam generator were determined to have very small volume but otherwise undefinable indications.

These indications cannot be quantified as a tube defect but have been recorded as an abnormal signal.

The two tubes in the "B" steam generator with the abnormal signals have been The five tubes in the "A" steam generator have been plugged.

left unplugged as potential candidates for a sleeving demonstration program.

The following is a summary of the tube plugging that

- occurred during the outage (Licensee Event Report 80-014/0lT-0) :

I "A" Steam "B"

Steam Generator Generator j

i 3

5 Tubes with defects >40%

0 0

Tubes with defects <40%

0 2

Tubes with undefinable indications.

3 7

Total tubes plugged

3 r

a

i

. Subsequent to tube plugging, photographic verification of the tubesheet was completed to ensure the plugs had been correctly inserted.

Unit 1 Refueling 8 was completed at 1333 hcurs on Decemb'r 30, 1980 after completion of reactor coolant system fill

.d vent, establishment of containment integrity, and performance of the primary system 2335 psig leak test.

In addition to Licensee Event Report 80-014/0lT-0 issued in response to the steam generator tube eddy current two other licensee reportable events occurred.

results, On December 10, 1980, during refueling surveillance snubber lHS14 testing of safety-related shock suppressors, was determined to be' inoperable.

The failure was traced to fluid leakage past the piston rod 0-ring seals.

The snubber was repaired'on the same day and additional snubbers were (Licensee inspected as required by Technical Specifications.

Event Report No. 80-015/0lT-0)

On December 17, 1980 at 1210 hours0.014 days 0.336 hours 0.002 weeks 4.60405e-4 months , ORT 53, Loss of was conducted.

On-Site AC and Initiation of Safety Injection Test, At 1243 hours0.0144 days 0.345 hours 0.00206 weeks 4.729615e-4 months the 4D emergency diesel generator failed.to load as was required by the test.

The 4D diesel was subsequently satisfactorily tested and returned to service at 1530 hours0.0177 days 0.425 hours 0.00253 weeks 5.82165e-4 months .

ORT #3 was completed at 1830 hours0.0212 days 0.508 hours 0.00303 weeks 6.96315e-4 months .

An investigation into the failure of the 4D diesel to accept load during the initial test The initial problem suspected was drf.fting in the was begun.

The investigation into setpoints of the speed sensing relays.

the problem on the 4D diesel continued on an intermittent basis until on December 30, 1980 it was discovered.that the frequency The coupling was subsequently generator coupling was slipping.1980 and the 4D diesel was satisfactorily repaired on December 30, The 4D diesel was operable during tested and returned to service.-

(

the investigation except during periods for special testing.

(Licensee Event Report No. 80-016/03L-0)

The completion of the follow-up inspection of the feedwater nozzles per NRC IE Bulletin 79-13 was accomplished The second inspection consisted of both during this outage.

ultrasonic and radiographic examinations and no rejectable indications were found.

Work continued on IE Bulletin 79-14, seismic analysis for as-built safety-related piping systems.

reactor coolant Other work consisted of an overhaul of the "A" l

inspection of the low pressure turbine rotors LPl and LP2,

(

pump, and numerous Three Mile Island-related modifications.

l With the exception of normal refueling operations, no other major safety-related maintenance was performed during the period.

NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE Docket No.

50-301 Unit Name Point Beach Unit 2 Date January 7, 1981 Completed By C. W. Fay Telephone 414/277-2811 Unit 2 operated at 495 MWe net throughout the period l

with two load reductions.

On December 3, 1980 load was reduced as required by Technical Specifications due to a safety injection pump out-of-service.

Load was again reduced on l

December 8, 1980 to 332 MWe to allow for turbine stop valve testing.

I i

One licensee reportable event occurred during the period.

At 0448 hours0.00519 days 0.124 hours 7.407407e-4 weeks 1.70464e-4 months on December 2, 1980 during normal power j

operation, a routine test of the Unit 2 safety injection pump, 2P15A, revealed slippage of the shaft driven seal water pump impeller, resulting in overheating of the throttle bushing.

Repairs to pump 2P15A were initiated upon verification of l

operability of the remaining safety injection pump.

Since repairs to pump 2P15A were not completed within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , a load reduction to hot shut-down was commenced at 0448 hours0.00519 days 0.124 hours 7.407407e-4 weeks 1.70464e-4 months December 3, 1980.

Repairs to the pump were completed at 0618 hours0.00715 days 0.172 hours 0.00102 weeks 2.35149e-4 months on December 3, 1980 and a one hour test run was begun.

The load reduction was halted l'

at 0633 hours0.00733 days 0.176 hours 0.00105 weeks 2.408565e-4 months at 260 MNe.

At 0718 hours0.00831 days 0.199 hours 0.00119 weeks 2.73199e-4 months , the one-hour test run was successfully completed and ascension to full load was commenced.

Full power was reached at 0915 hours0.0106 days 0.254 hours 0.00151 weeks 3.481575e-4 months on December 3, 1980.

Notification to the NRC was made via the " red phone" when the unit load reduction was initiated per the limiting condition for operation.

(Licensee, Event Report No. 80-012/03L-0)

The only safety-related maintenance performed during the period was the repair of the 2P15A safety injection pump.

e b

I

_.

ML19340E717

Text

SUMMARY

SUMMARY

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