ML20107L684

Monthly Operating Repts for Sept 1984

ML20107L684
Person / Time
Site:	Hatch
Issue date:	09/30/1984
From:	Mcbay M, Nix H GEORGIA POWER CO.
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
GM-84-889, NUDOCS 8411130602
Download: ML20107L684 (16)

Text

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r NARRATIVE REPORT UNIT 1 September 1st 0000 Unit of f-line due to react or scram on loss of condenser vacuum on 8-31-84.

0348 Unit t ied to line & increa sing power.

0800 Vacuum dropping again. Power being held at approximat ely 20%

of rated capacity.

September 3rd 0900 Began pulling rods & ramping up from loss of condenser vacuum ,

der at i ng . (

September 4th 2400 Unit at maximum power via 105%

recire flow. Unit also in fuel cycle coastdown which is now approximately 85% of design capacity.

September 28th 2100 Reducing load for scheduled refueling outage.

4 September 29th 0008 Turbine tripped and unit of f-li ne for 10 week refueling outage.

DO O D k tA

1. sx1 2 . . - . . -

4 HATCH 1 SAFETY-RELATED MAINTENANCE REQUESTS TO BE RSPORTED FOR September 1984 NUMBER DATE COMPLETED DESCRIPTION 82-2143 08-28-84 Ran weld leads for torus work t hru penet rat ion sleeve on east reactor b1dg.

wall-south of column R3.

Re f . D CR 8 0-199.

82-2729 09-15-82 Installed drains & vent li ne s , & sump pump to new shift supervisor's of fice/ kit chen in cont rol b1dg. (MPL lZ44) . Re f . D CR 80-348.

84-1550 09-11-84 Installed 3/4" air compressor pressure switch root valve into existing 2 1/2" JBE process li ne . (MPL

1. 1R43-S001B) . Ref . DCR 80-98.

84-2189 08-20-84 Replaced existing Standby Liquid Control Relie f Valve (MPL 1C41-F029A) Re f . D CR 84-235.

84-3232 07-26-84 Cut bar st ock from plate in warehouse and transferred heat number to each piece of -

bar. (MPL 1T2 3 ) Ref. DCR 82-75.

4524 08-06-84 Removed existing SRV Tailpipe Temperat ure Recorders (L&N Speedomax )

and installed new recorder (L&N Series 250) (MPL 1B21-R614) Ref . DCR 84-001.

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OIERATIE DATA REIORT ,'

DOCKET NO. 50-321 IATE 10-10-84 CDMPLEPED BY: M.G. McBay TELEPHOtE (912) 367-7851 OPERATIE S'IATUS Notes

1. Unit Name: E. I. Hatch Nuclear Plant Unit 'l

2. Report ing Period: 09 '

3. Iicensed Thermal Power (MWt ): 2436

4. Nameplate Rating (Gross MWe): 8 09.3

5. Dasign Electrical Rating (Net MW): 777.3

6. Maximum Depe:dable Capacity (Gross MWe): 801.2

7. &ximta Deperdable Chpcity (Net MW): 752.2

8. If Changes Occur in Capacity Ratings (Itens Number 3 through 7) Since Last Report, Give Reamns:

9. Power Iavel to midt &stricted, If Any (Net MW)

10. Reasons for Restrict ions, If Any:

) This bbnth Yr-todht e Ctnulat ive

11. Hours In Repating Period ,

720 6575 76702

12. &mber of Hours Reactor was Critical -

672.1 5638.8 55164

13. Reactor & serve Shutdown Hours .; O O O

14. Hours Cenerator On-Line '

668.3 5474.9 51867.9

, 15. Unit Ibserve Shutacwn Hours O O O

16. Gross Thermal Energy Generated (MWH) 1294200 12151162 109369190

17. Gross Electrical Energy Generated (MWH) 398050 .T/97550 35255720

18. Net Electrical Energy Generat ed (MWH) 375747 3609181 33468544

19. Unit Service Factor 92.8 83.3 67.6

20. thit Availability Factcr 92.8 83.3 67.6

21. Unit Capacity Ebetor (Using 10C Net) 69.4 73.0 58.0

22. thit Capcity Factor (Using DER mt ) 67.1 70.6 56.1 '

2 3. Unit Ebrced Outage Rate 0 15.0 18.1

' 24. Stutdowns Scheduled Over Ext 6 bbnths (Type, Ihte, ard Duration of Each):

Refueling 10-1-84 10 week duration

25. If Shutdown at End cf Report Period, Estimat ed Date of Start up:

26. Unit s in 'Ibst Status (Prior to Canmercial Operat ion): Ebrecast Achieved INITIAL CRITICALITY INITIAL FLECTRICITY CDbMERCIAL OIERATION

AWIUGE DAILY UNIT MWER LEVEL DOCKET NO. 50-321 IATE: 10-10-84 CDMPLEI'ED BY: M.G. McBay TEMPIDE (912) 367-7851 Motel 09-84 DAY ANERPGE DAILY MWER LEW.L IAY AWR7GE IAILY MWER LEWL (MWe-Net ) (Mhh-Net.)

1 106 17 611 2 142 18 6 07 3 309 19 606 4 546 20 603 5 651 21 601 6 630 22 5%

7 630 23 593 8 628 24 591 9 625

• 25 589 10 623 26 588 11 618 27 587 12 615 28 ' 554 13 612 29 -15 14 609 30 -15 15 607 31 16 612 (9/77) w

• G  ?:-k 50-321 J UNIT SI:UTDOWNS AND POWER REDUCTIONS .

DOCKET NO. Hatch 1 UNIT .N A?,lE

• DATE i 10-4-84 COMPLETED BY M. McBay REPORT MONT11 September TELE!'110NE 912-367-7851

. -, ,$g };; ,Y Licensee ,E, e,, h,- "Cause & Corrective -

g 2 :, 5 y gQ Nii. Date 38 Event Action to H

dI $ j iji g Repor: # mO ,

Prevent Recurrence S

T 84-68 840901 F 3.8 A 2 NA HC XXXXXXXX Loss of condenser vacuum from in-leakage through crack between condenser

& LP turbine. Outage ,

84-09 840901 F 53.2 B 5 NA HC XXXXXXXX Load at approximately 20% due to in-stability of vacuum. Problems being resolved.

84-70 840903 F 39.0 F 5 NA HC XXXXXXXX Ramping up from vacuum problems to ratec via recirc flow.

84-71 840928 S 3.13 C 2 NA RC FUELXX Reducing load for scheduled refueling outage.

~

84-72 840929 S 47.87 C 2 NA RC FUELXX Unit refueling outage i{i progress.

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• A 1 2 3

• 4 F: Forced Reason: Method: Exhibit G.15structions S: Scheduled A Equipment

• Failure (Explain) .

1 Manual -

for Preparation of Data 84taintenance of Test '

2-Manual Scram. Entry Sheets for Licensee . -

C Refueling . 3 Automatic Scram. j Event Report (LER) File (!3UREG-:

4 -Continuations D Regulatory Rest:.c; ion '

016I) -

E Operator Yraining & License Examination .. l 5-Icad Reduction } i 9 #

e sm) 5 Irati 21 Errer(Explain)

(.Other (Explain) ,

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Exhibit I-Same Source , .

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NARRATIVE REPORT U NIT 2 September 1st 0000 Unit still in recirc piping replacement outage.

September 3rd 0758 Reactor mode now swit ched to run. ,

Prepared for unit st art up.

1817 Turbine t ripped.

1837 Turbine reset.

2151 Unit on line at approximat ely 50 GMWe.

September 4th 0140 Main t urbine tripped due t o MSR hi level.

0335 Main turbine back on line following MSR hi level trip.

0401 Main turbine t ripped due t o MSR hi level.

0552 Main turbine back on line following MSR hi level trip.

F 0617 Main turbine 't ripped due to MSR -

hi level. ,1 September 5th 0122 Turbine rolling. Prepared to tie unit on line.

0232 Unit now t ied on line following multiple turbine t rips. Startup testing in progress. Power at approximat ely 20% of rated.

September 6th 2300 Pulling rods t o approximat ely 40%

CMWt to increase power. Startup testing st ill in progress.

September 8th 0000 Holding power at approximat e ly 70% for st art up testing.

September 10th 0000 Still holding power at approximat ely 70% for test ing.

4

September lith 0132 Both recirc pumps tripped during procedure te st ing (HNP-2-1026 3) .

0545 Back to 70% power from recirc pump t rip & holding.

2122 Inserting rods for testing of scoop t ubes on recirc pumps.

1939 Testing scoop tubes complete.

Commencing t o pull rods per STA inst ructions to rated power .

September 15th 0535 Rod pulling stopped due to detect ed problems with condensat e domineralizers.

0715 Reducing reactor back to approximatey 630 MWe.

0735 Stopped reducing load.

1110 2E condensate demineralizer taken out of service because of low -

flow rate & high resin t rap.

September 15t h 2256 2E condensate demineralizer placed backed in service af t er backwash & precoating. Increasing power again.

September-17th 2150 Reducing power for the removal of condensate demineralizer 2E.

Power reduced to approximately 75% of rated.

September 20th 0320 Increasing power via recire flow

& beginning precondit ioning ramp to rated power.

September 21st 1701 Unit at rated power. React or scram from the inboard MSIV's drifting closed.

September 22nd ldO3 Reactor critical. Preparing to put unit on li ne .

September 23rd 16 47 Main generator on line. Unit again going through start up.

September 24th 1040 Holding load at approximatey 60%

of rated t o complet e OD-1.

1614 OD-1 completed.

~

-Sept ember 24t h 1721 Condensate booster pump t rip when auxiliary oil pump swit ched to a uto posit ic a.

2205 Recirc pumps placed in master manual posit ion. Begin increasing power.

September 25t h 18 58 Holding load for RHR pump bolt problems.

September 26t h 1910 "B" recirc pump drif ting down.

Load reduced down to approximately 45% of rated.

Sept ember 27t h 1245 Increasing react or power via rod pulls & recirc flow following recirc pump problem. Increasing to rated.

Sept ember 30t h 0007 Unit running at rated power. Load reduced during startup testing procedur e (HNP-2-10 26 3) .

-0600 Unit operating at 2436 CMWt.

1145 Reactor scram due to a loss of condenser vacuum. Of f li ne at end of reporting period.

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HATCH 2 SAFETY-RELATED MAINTENANCE REQUESTS TO BE REPORTED FOR September 1984 NUMBER DATE COMPLETED DES CRIPTION 83-2896 02-03-84 Retagged panel valves and tag the instrument valves on 2 H21 in st rume nt racks. Ref.

DCR 81-139, Rev. 1.

83-4948 01-13-84 Installed cable raceways on React or Protect ion System &

scram discharge volume. (MPL 2C11) . Ref . DCR 82-220.

83-6142 04-09-84 Pulled cables per HNP-6921 on the drywell pneumatics sy ste m. (MPL 2P7 0) . Ref. DCR 81-112.84-203 08-26-84 Red li ned , funct ional tested, and calibrated all in st rume nt at io n a nd associated logic installed on t he ATTS . (MPL 2A70) Ref.

DCP 81-139, Rev. 1.84-477 05-31-84 Installed replacement valve for existing 2P70-F076H D/W pneumat ic salve. Ref. DCR 84-152.84-675 08-09-84 Modified piping supports 2G41-FPC-R13 4 & H81. Ref.

DCR 82-257.84-678 08-09-84 Modified pipe supports on instrument air system (MPL 2P5 2) Ref. DCR 82-257.84-724 07-17-84 Modified pipe support 2T46-SBG-A47. Re f. DCR 82-257.84-726 07-02-84 Modified pipe supports on RHR system (MPL 2E11) . Re f.

DCR 82-257.84-906 07-02-84 Modified exist ing pipe support 2 P41-S W-HRll7 . Ref.

DCR 82-257, Rev. 1.84-915 08-09-84 Modified exist ing pipe support s f or 2Cll system.

Ref . DCR 82-257.

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HATCH 2 SAFETY-RELATED MAINTENANCE REQUESTS TO BE RSPORTED FOR September 1984 NUMBER DATE COMPLETED DESCRIPTION 84-1020 07-23-84 Modified pipe support s 2 PS 2 -S 31-H 802, H804, H806 &

2 P52 -S 43-H8 04. Re f . D CR 82-257.

84-1482 07-02-84 Modified existing piping support s f or 2G31 system.

Ref. DCR 82-257. .

84-1486 07-23-84 Modified pipe supports on 2P41 system. Re f . DCR 82-257.

84-1773 07-17-84 Removed exi sting flow i nstrument s ( 2Cll-R60 2A, B) &

installed new Rosemount transmitters 2E11-N019A&B.

Also removed orifice plates "

and installed new orifice plates. 2 Ell-N00 6-A& B . Ref.

DCR 82-158.

84-2012 07-08-84 Installed supports, piping &

tubing for instruments 2G31-NO31A&B. Installed Roto Hammer Gearbox reach rods on valve 20A and also gear box supports. Made core drill for reach rod assembly for valve 2G31-F208A & sealed aba ndoned penet ration . Ref.

DCR 83-86.

84-2022 08-26-84 Tagged /retagged inst rument panel (isolation & drain) valves & inst rument valves for Analog Transmitter Trip System inst rument racks (MPL 2 H21) Ref . DCR 81-139, Rev.

1.

84-2453 08-20-84 Redlined Primary Containment Cooling System circuitry (MPL 2T47-B008A&B) Ref. DCR 83-173.

84-2510 08-21-84 Installed & calibrated strain gauges on start up inst rume ntat ion 2831-G001.

Ref . DCR 83-17 3.

HATCH 2 SAFETY-RELATED mal t.7ENANCE REQUESTS TO BE PE PORTED FOR Sept ember 1984 NUMBER DATE COMPLETED DESCRIPTION 84-2560 07-23-84 Modified hanger 2B21-MSRV-R60 at Main Steam Relief /alve. Ref. DCR 84-044.

84-2996 07-05-84 Invest igated leak at RWCU F/D "B" Resin Trap Isolation Valve f.2G31-P06 3B) . Ref . MR 2-84-2779.

84-3132 07-12-84 Terminated cables &

performed internal wiring in panels to implement required logic changes in Standby Gas Treat me nt & Ventilation system circuits. (MPL 2 C61-K48A & 49A) . Re f . D CR 81-139, Rev. 1.

84-3989 08-20-84 Replaced existing motor pinion, wornshaft gear &

torque swit ch limit er plate with new part s on RHR Torus Isolat ion Valves (MPL 2 Ell-F028B) . Ref. DCR 84-211.

84-4144 08-24-84 Modified existing reactor bldg. cable tray / conduit supports per 10CFR21 seismic evaluation. (MPL 2R3 3) . Re f .

DCR 84-227.

84-4146 08-18-84 /alibrated & checked se t poi nt on 2E32-N655 Bailey Alarm Unit Setpoint changed from 2.40 volt s DC to 2. 26 volt s DC Ref. DCR 83-10.

84-4256 08-21-84 Replaced existing 25 amp circuit breakers in MCC 2R24-S012 component 13B &

13C wit h 30 amp circuit breakers for MCVs 2E 21-F004B

& 2E 21-F00 5B . Ref . D CR 81-177.

84-4452 08-21-84 Inst alled new conduit support s & added anchor bolt t o exi sting conduit supports. ( MPL R3 3 ) Re f . DCR 80-348, Re v . 2.

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OIERATItG DATA REIORT .

DOCKET NO. 50-366 IATE 10-10-84 CDMPLETED BY: M.G. McIhy TELEPH0tE (912) 367-7851 OPERATItG STATUS Not.es

t. Linit Name: E. I. Hat ch Nuclear Plant thit 2

2. Reporting Period: 08-84

3. Licensed Thermal Itwer (Wt ): 2436

4. Nameplate Rating (Gross MWe): 8 17 .0

5. Design Electrical Rating (Net MW): 784.0

6. Maximum Deperdable Capacity (Gross mie): 803.9

7. mximun Deperdable Capcity (Net MWe): 7 47 .9 ti . If Changes Occur in Capcity Rat ings (Itens t& amber 3 thraucp 7) Since Last Report , Give Reasons:

9. Power Imvel to W11ch Ibstricted, If Any (Net mie):

10. Reasans fcr Restrictions, If Any:

This ebnth Yr-to-lht e Cunulat ive I t. tiours In Reporting Period 720 6575 44328 685 1059.4 28130.7 12.11mber of Hcurs Reactor was Crit ical 0.0 0 0

13. Ibact or Ibserve &ttdown Hours 874.3 26662.2 L4. Hcurs (bnerator On-line 5 66 .1 0.0 0 O

15. Unit Ibserve mttdown Iburs 1715218 56931473

16. Gross Thermal Energy Generated (MI) 986668

17. Gross Elect rical Energy Generated (WH) 312780 555420 18727200

18. tet Electrical Energy Generated (MI) 294596 504981 17794088 78.6 13.3 60.1

19. thit Service Pactor 13.3 60.1

20. thit Availability Factcr 78.6 2L thit Capacity Pactor (Using POC Net) 54.7 10.3 53.7

22. thit Capeity Factor (Using IER Net ) 52.2 9.8 51.2 2 3. Unit Rrced Outage Rate 12.9 8.8 13.1

24. Slutdowns Scheduled Over text 6 tenths (Type, Iht e, ard 11: rat ion of Each):

Recirc piping outage atill in Irogress.

25. If Shutdown at End of Report Period, Est imat ed Dat e of Start tp:

N. tbit a in 'Ibst St atus (Prior to C-rcial Operat. ion): Ebrecast Achieved INITIAL CRITICALI'lY INITIAL ILECTRICITY CDfMERCIAL OIERATION

AEIUGE DMLY UNIT IGER IEEL ,

DOCKET NO. 50-366 IATE: 10-10-84 (DMPMTED BY: M.G. McBay TEMPH0tE (912) 367-7851 runu 09-84 law AEIUGE DMLY POWER MEL IAY A'ERAGE DMLY POMiR LEEL (Mee-Net ) (Mde-Net. )

1 -15 17 640 2 -17 18 585 3 -13 19 591

-1 -12 20 700 5 105 21 544 u 204 22 -17 7 362 23 9 a 538- 24 3 69 3 521 25 670 '

10 522 26 650 iL 47 6 27 454  !

l2 276 28 708 13 503 29 765 14 639 30 334 l 15 582 31 16 602 (9/77)

d ,,;

\$" 50-366 d -

UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKE1 NO. Hatcn 4 UNIT N A'.lE IMT E '10-4-84 COMPI.E'It la BY M- McRav REPORT MONT11 September TELLl'IlONE Q19 v7_7nci i

3 a

- ,Eg "g Licensco Eg wl, - "Cause & Costei. live -

Nii. Date (

P- h

=

,, 3.M55 j if; Event Report #

p to O Eh g ,

A"*'

Prevent Recurrcnce w

84-5 840901 S 69.85 H 2 NA CB PIPEXX Recirc pipe replacement outage.

84-6 840903 F 28.41 A 9 NA HA VESSEL Turbine trips during startup due to MSR Hi Level. Unit off-line majority of event duration.

84-7 840905 S 143.0 B 5 NA SH INSTRU- Startup testing. Load increased per Shift Supervisor instructions.

84-8 840911 F 4.22 A 5, NA CB PUMPXX Trip of both recirc purgps. Load reduc-tion. I.

4 ,

84-9 840911 S 15.62 B 5 NA SH INSTRU Power derating for startup testing.

Load reduction. ,

84-10 840911 S 22.28 B 5 NA CB PUMPXX Testing of scoop tubes lon recirc pumps.

s i

I 2 3 .

4 F: Forced Reason: Method: Edn5: G - Itht ructions for Preparation of Data '

A Equipmeni~ Failure (Explain) 1-Manust -

S: Scheduled

• B.Msintenance of Test 2 Manual Scram. Entry Sheets for Licensee . -

C.R:fu:lia 3. Automatic Scram. } Event Repor (LER) File (!JUREC -

D Pgulatory Rest:.c.iun 4 -Continuations . 01611 -

E C yetstor ' training & Ucense Examination -: 5-Icad Reduction } .~

9S d- atk 21 Erre:(2xplain)

Il-Other(Explain)

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Exhibit ! Same Souree .

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. F. 50-36 d DOCKI:I No.

UNITSl!UTDOWNS A D POWER REDUC 110NS U.NIT h A*.!E liat.ch 2 g, ale t 10-4-84 COMPLEll.1813Y M. McBay REPORT MONTH September TELLi'llONE 912-367-7 R8il i

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'Cause & Corrective

.{} E3, -

- Licensco Nii. Date g= } ,, , 3 a: Event Eh A ' ' ' "" ' *

• k a$ #. j g5 g Report # mQ 3 ,

Prevent i<ccurrence 3 .

w 84-11 840912 S 57.85 F 5 NA RC :0NR00 Pulling rods per STA instructions for ramp up.

84-12 840915 F 117.83 A 5 NA HH DEMINX Load reduction because of condensate demin problems.

84-13 840921 F 37.77 A 3 NA CD VALVEX- Rx scram from inboard MSIV's drifting closed.

84-14 840923 S 17.88 F 3, NA SH INSTRU Startup from above rx scram.

84-15 840924 F 4.73 A 5 NA HH PUMPXX Condensate booster pump tripped. Load reduction.

34-16 840926 F 17.58 A 5 NA CB PUMPXX "B" recirc pump drif tin ( down. Load reduction.

84-17 840930 F 12.25 A 3 NA . HC FILTER Rx scram on loss of concenser vacuum.

Y I 2 3 4 l F: Forced Reason: Method: Ex]nba G . !cirucitons '

S: Scheduled A Equipmert' Failure (Explain) 1 Manual -

for Piccaration of Data 041aintenance o(Test 2 Manual Scram.

Entry Sheets for Licensee . - J C Refu:lia!; 3 Automatic Scram. Eve r,i i<c puri (LE R) File (!JU REG- :

. l '

D Replatory Rest:.c' ion 4 -Continuations . 0161) -

5-Ioad Reduction E Operator ' training & License Examination - ,,'

3 F-Adrain's ra:!ve 9 -Other (Explain) Exhibii !- Same Souree ,' .

G-Operational Errt (2xplain) ,.g

< iln) Il-Other (Explain) i.- .

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• Georgia Power Company a Post Office Box 439

. Baxley, Georgia 31513 Telephone 912 367-7781 912 537-9444 m

Edwin 1. Hatch Nuclear Plant October 5, 1984 GM-84-889 PIANT E. I. HATCH NRC Monthl r Operating Report Of fice of Plans and Schedules Directorate of Licensing Unit ed St ates Nuclear Regulatory Commission Washington, D. C. 20545

Dear Sir:

Per Tech Specs sect ion 6.9.1.6 please find attached the NRC Monthly Operating Report for Hat ch Unit 1, Docket #50-321, and for Hat ch Unit 2, Docket #50-366.

H. C. Nix General Manager HCN/CTJ/ JAB /hh 3stl i I