PM-81-292, Forwards Monthly Operating Rept for Mar 1981

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Forwards Monthly Operating Rept for Mar 1981
ML20008F723
Person / Time
Site: Hatch Southern Nuclear icon.png
Issue date: 04/10/1981
From: Manry M
GEORGIA POWER CO.
To:
Office of Nuclear Reactor Regulation
Shared Package
ML20008F724 List:
References
PM-81-292, NUDOCS 8104210543
Download: ML20008F723 (1)


Text

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s Giorgia Power Ccmpany Post o'fco B ~'x 442 Badey. Gecrg'a 3t513 Telephone 912 367-6686 912 367 7781 L

Georgiaibver Edwm t. Hatch Nuc: ear Plant fN ro#wm e-v'r s,sfe'"

April 10, 1931 P'!-81-292 PLANT E.

I. IIATCil NRC.ilonthly Operating Report Office of Plans and Schedules Directorate of Licensing United States Nuclear Regulatory Conaission dashington, D.

C.

20345

Dear Sir:

Par Tech Specs section 6.9.1.6 please find attached the NRC Monthly Operati.ng Report for liatch 'Jnit 2, Docket #50-366.

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This Month....... _...Yr.-to-Date

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. Hunber W tlours Fecctor Uas Criticci 503.C 723.7 8957.5 Reactna Reserve th@.dcun H o.a r s

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890374 1160526 10264424

. Gr o ss Electrical Energy _ Generated 'HHH) 293250 330910 6048190

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  • c t r_i c a 1,,E n e r g u Cenersted (cJH) 277132 353926 5756010

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m DOCKET NO.

50-366 UNIT SIIUTDOWNS AND POWER REDUCT10NS UNITNAME liltch ?

P

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DATE 4-10-81 j

[jf COMPLETED BY G. H. Elam fj j l

REPORT MON 111 March i

TELErilONE 912-36 7- /H$ 1

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Cause & Correc0ie y

Licensee Et

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Event g'g 1

Action to No.

Date k

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E j di e Report #

mo u

Prevent Recurrence b

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)ExscramdaetotucSir.estopvalve l3

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j HA i VA'_ VEX g fast closure 81-16 810301 F

14.3 S

81-17 810301 F

19.6 0

5 i

f4A IIA VALVEX Unit on startua rap from above snut-down,J81-16 81-18

810304, F

22.3 A

3 81-015' IA liisiRil Rx scran due

'.a IR:1 spike 81-19 810305 F

23.5, A

5

' I4A IA li4STRU ecovery from above scram #81-18 81-20 810306 F

6.0 A

5 ilA CB '

GENERA Power reduction due to exciter prob-1em of recirc pump 'A' 81-21 810306 F

196.3 A

1 81-017 CB GENERA Unit off line due te recirc pump 'A' exciter problems 81-22 810314 F

4.4 A

5 ilA OB.

GENERA Unit on startup from abovc shutdown

  1. 81-21 8

2 3

4 F: Forced Reason:

Method:

Exhibit G Instructions 5: Scheduled A-Equipment Failure (Explain) 14f anual for Preparation of Data B4ttintenance or Test

' 2 Manual Scram.

Entry Sheets for Licensee C. Refueling 3 Automatic Scram.

Event ReporI(LERI File (NUREG-D Regolatory Restriction 4 -Continuations 0161's E.Operatur Training & Ucense Examination 5-Ioad Deduction 5

F. Administrative 9-Other (Explain)

Exhibil1 SalpeSource i

G Operallonal Etrut (Espfein),

(9/77) llother (Esplein) '

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,j UNIT SillMDOWNS AND POWER REDUCDONS DATE 4-10-81 j

COMPLETED BY G H Fla"'

faPORT MONDI March TELEPil0NE 91/-367-78'31 J ~

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Date l

Prevent Recurrence g6F RCPU't#

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81-24 810315 F

18.9 A

3

.NA IA INSTRU Rx scram due to IRMs C&F spiked upscale T

81-25 810315 F

24.1 A

5 NA IA INSTRU Recovery from above scram 21-24 81-26 810317 F

-16.6 A

3 NA.

CD VAL 5IEX Rx' scram due to MSIV closure y

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81-27 81031fi F

27.7 A

5

,.NA' CD_

VALVEX R covery from above scram #81-26 C

81-28 810321 F

30.8 8

5 NA IIA -

ZZZZZZ Load reduction to perform turbine JlEll3

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C"s l) 81-29 810327 S

5.5 F

5 NA RB C0flROD Load redu'ction to perform weekiy turbine testing and rod pattern ad-2 i

justment.

F 81-30 810328 F

11.3 A

3 NA CH HTEXCil Rx scram due to loss of feedwater heaters 1

2 3

4 Method:

Exhibt: C -Instructions F: Forced Reason:

5: Scheduled A Ltuipment Failure (Emplain) 14tanual for Preparallon of Dasa B41aintenance of Test

' 2-Manual Scram.

Entry Sheets for Lkensee 3-Automatic Scrom.

Event Report (LERI File (NUREG.

C Refueling D Regulatory Restriction 4 -Cbntinuations 0161)

E.Opesator T aining & Ucense Examinstle't 5-Ioad reduction 5

F-Administrative 9-Other (Explain)

Emlelbil l-Jame Sisses GOpenailonal Enut(Caplsla)

(9/77)

IlOther(Emplain) w

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1 ET UNIT SilUYDOWNS AND FOWER REDUC 110NS H

, N DATE 4-in-81

' COhirLETED BY 3 H-f I" REPORT MONTil March TELEP110NE 8 2-3b /- M)l s-

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Licensee vl, Action to No.

Date 6

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81-31 810'329 F

.10.0 A-51

.,hh CH TEXCHc Recov'ery from abovq. scram #81-30

  • 2 A
3 ilA.

HA GENERA Rx scram 'due to high water' levei.causec l

81-32 810330 F

14.3

. by turbine: trip.

81-33

~810331 F

8 A

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  • H5 Gell $RA Recovery from abo'v5 scram #31-32

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F: Forced Reason:

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Exhibit G. Instructions I Manual for Preparation of Data 5: Scheduled A. Equipment Failure (Explain)

Entry Sheets for Lkensee 8 Maintenance of Test

' 2 Manual Scram.

C ".erueling

3. Automatic Scram.

Event Repors (LERIFile(NUREG-D Regulatory Restriction 4 -Continuations 0161)

E-Operator Training t License Esaminallose..

5-Ioad Reduction 9 -Other'(Explain) -

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4 (9/77)

IIChar (Emplain) '

V o.

NARRATIVE REPORT UNIT 2 March 1st Rx auto scram due to TSV fast closure at 0306 Ma::S ist Rx critical at 1142, tied to line at 1724 Ma-4th Rx auto scram at 1142 due to IRM spike Ma: _ a 4th Rx critical at 2046, tied to line at 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> on March 5th March 6th Reducing power at 0915 due to exciter problems of recirc pump A March 6th Unit off line due to recirc pump A exciter problems March 14th Rx critical at 0300, on line at 1938 hours0.0224 days <br />0.538 hours <br />0.0032 weeks <br />7.37409e-4 months <br /> March 15th Rx auto scram at 0622 due to IRM

'C' and

'F' spiked upscale March 15th Rx critical at 1136 and generator on line at 1855 hours0.0215 days <br />0.515 hours <br />0.00307 weeks <br />7.058275e-4 months <br /> March 17th Rx auto scram at 0938 due to MSIV closure March 17th Rx critical at 1745 hours0.0202 days <br />0.485 hours <br />0.00289 weeks <br />6.639725e-4 months <br /> and generator on line at 0216 hours0.0025 days <br />0.06 hours <br />3.571429e-4 weeks <br />8.2188e-5 months <br /> on March 18th March 21st Power reduced at 1110 for weekly turbine test March 27th Power reduced at 2210 for weekly turbine test and rod pattern adjustment March 28th Rx auto scram due to loss of feedwater heaters ASB March 29th Rx critical at 0045, tied to line at 0602 hours0.00697 days <br />0.167 hours <br />9.953704e-4 weeks <br />2.29061e-4 months <br /> March 30th Rx auto scram due to high water level caused by turbine trip March 30th Rx critical at 2114, on line at 0411 hours0.00476 days <br />0.114 hours <br />6.795635e-4 weeks <br />1.563855e-4 months <br /> of March 31st 1

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HATCH 2 SAFETY-RELATED MAINTENANCE REQUESTS TO BE REPORTED FOR MARCH 1981 NUMBER DATE COMPLETED DESCRIPTION 79-4584 2-17-81 Replaced (per DCR 79-32) down-stream side of

flanges, and all connecticas gaskets, flanges between and manifetds, field run p,iping to acconciate new MSIV air supply raan t red d s 2B21-F022 (A-D and F028A-D) 80-4532 1-20-81 Added
unistrut, fittings, aul pipe clamp at location N0639 and 18511 to 2C11-11-15" CDD piping, supports 81-1241 2-22-81 Changed core bottom linit ta 698 on 2C51N001B B tip nachine 80-3414 3-4-81 Replaced leaking outboard sc.1 on main HPCI pump 2E41-C001 81-54 1-21-81 Removed and cleaned 2E41-F021 HPCI turbine exhaust nsaat valves 81-1146 3-4-81 Replaced and calibrated
llPCI, EGM, EGR, rarap gen. and simul converter 2E41-R674 81-795 2-18-81 Fabricated and installed (per DCR 81-28)

RCIC pipe support 2E51-RCIC-R701 81-1231 2-25-81 Repaired ribbon connector on RCIC - 2E51-C001 81-532 2-9-81 Removed and cleaned valves on 2551-F001 and F002 torus drain valve 80-4588 2-17-81 Removed and replaced INS Co.

snubber with (per DCR 80-16)

Pacific Scientific Co. snubbers 2L3J 80-4592 2-18-81 Removed and replaced INS Co.

snubber with (per DCR 80-16)

Pacific Scientific Co. snubbers 2L3J i

80-4593 2-17-81 Ren;v;d cn rcplaccd INS Co.

snubber with (per DCR 80-16)

Pacific Scientific Co. snubbers 2L3J 80-4597 2-17-81 Removed and replaced INS Co.

snubber with (per DCR 80-16)

Pacific Scientific Co. snubbers 2L3J 8,0-4718 2-17-81 Removed and replaced INS Co.

snubber with (per DCR 80-16)

Pacific Scientific Co. snubbers 2L3J 80-4872 2-17-81 Removed and replaced INS Co.

snubber with (per DCR 80-16)

Pacifig Scientific Co. snubbers 2L3J 80-5211 2-17-81 Removed and replaced INS Co.

snubber with (per DCR 80-16)

Pacific Scientific Co. snubbers 2L3J 80-3299 2-10-81 Installed 2P11-C001A6B conden-sate transfer pump enclosure per DCR 79-190, R1 81-728 2-11-81 Removed seal plate from exteri-or end of standby diesel service water pipe (2P41-600) and prepare for liquid penet-rant examination 81-738 3-12-81 Removed and replaced seal gasket on 2P41-F410 hydrogen cooler PSW air relief valve 81-941 2-20-81 Removed seal plate from exteri-or end of standby diesel service water pipe 2P41-G001 and prepare for liquid penet-rant exam 81-776 2-17-81 Delete eight existing pipe supports (per DCR 80-453) and replace with 4

cooling water system pipe supports 2P42 l

81-125 2-16-81 Pulled circuits TLX701C01 and TLX702C01 (per DCR 78-268) in I

reactor bluilding Unit 2, 2T43 i

l l

81-458 2-17-81 R:; moved oxisting

ccnduits, installed pull bar and rein-stalled conduits78-135) pull and in cables (per DCR reactor HVAC unit 2 fire prot-ection 2T43 81-902 2-17-81 Removed

. existing

conduits, installed pull bar and rein-7 8-135) pull and stalled conduits in cables (per DCR reactor HVAC unit 2 fire prot-ection 2T43 SI-400 2-16-81 Installed instruments 2T47-N009 and 2T47-N003, circuits A's TFX922C09 and TFX023C01 on drywell cooling local RTD, 2T47 81-896 2-13-81 Terminate and redline TLX806M01 and TLA90F15 and calibrate 2Z43-P007 Alison Control Fire Detection Panel O

1

_.