ML19330A619

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Monthly Operating Rept for June 1980
ML19330A619
Person / Time
Site: Hatch Southern Nuclear icon.png
Issue date: 07/10/1980
From: Blackwell R
GEORGIA POWER CO.
To:
Shared Package
ML19330A618 List:
References
NUDOCS 8007280680
Download: ML19330A619 (8)


Text

_ _ _ _ ___ _ _ .. __ .__- _ . _ . - _- __ -

' I OPERATING DATA REPORT ,

DOCKET NO. 50-321 ,

DATE 7- 10-s3 CO31PLETED BY R. M. Jiackwell TELEPHONE r a- m -/781

-OPERATING STATUS I Hatch 1 Notes I. Unit Name: i

2. Reporting Period. 6-E0
3. Licensed Thermal Power t.\lWt): 2436 809.3 '
4. Nameplate Rating (Gross 51%el: .

$. Design Elec:rical Ratin;INet 31Wei: 777.3 j

6. Maximum Dependable Capacity (Gross SIWE): 796.3 i
7. Maximum Dependable Cacacity (Net 31We): 7643  ;

S. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons: i, I

9. Pow;er Les el To Which Restricted. If Any (Net 31We):

l

-10. Reasons For Restric: ions.!! Any:

I l

This Month Yr to.Date Cumulative .

.  !!. Hours In Reporting Period 720 4367 39431 l

12. Number Of Hours Reactor Was Critical 392.0 3631.1 29429.1
13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0
14. Hours Generator On.Line 270.0 3421.1 27689.5 IS. Unit Resene Shutdown Hours 0.0 0.0 0.0
16. Gross Thermal Energy Generated (31WH) 568900 7717740 58070775 -

P

17. Gross Electrical Energy Generated 131WH) 1E0680 , _ .

2555300 188262d0 '

18. Net Electrical Energy Generated (SIWH) 167205 2d38498 17900431
19. . Unit Senice Factor 37.5 78.3 70.2 -
20. Unit Availability Factor 37.5 78.3 70.2 -
21. Unit Capacity Factor iUsing ilDC Net) 30.4 73.1 59.4
22. Unit Capacity Factor t Uu. ,0ER Net) 29.9 _ 71.8 58.4 23.' Unit Forced Outage Rate 62.5 21.7 20.8 ,
24. Shutdowns Scheduled Oser Next 6 31onths (Type. Date,and Duration of Each): .  :
25. If Shut Down At End Of Report Period. Estimated Date of Startup:
26. Units in Test Status (Prior to Commercial Operation): Forcess Achiesed INITIAL CRITICALITY INITIAL ELECTRICITY CO.\l.\lERCIA L OPER A TION (o/773 8087280 M O

i AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-321 t3.IT Hatch 2 3 ATE 7- 10-20 C0\tPLETED BY R. M. Blackwell TELEPHONE MONnt 6-80 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (5f We-Net) (31We-Net)

762 17 729 2 287 18 773

. 3 -14 19 773 4' -12 20 729 5 200 21 498 6 403 22 750 7 598 23 777 8 415 24 778 9 724 25 776 l 10 782 26 773

782 27 768 12 786 28 750 13 780 387 29 14 172 635 30 15 -15 3, 16 292 l

l l

INSTRUCTIONS l On this format. list the average dady unit power lesel in 5tWe-Net for each day in th: reputting month. Compute to the nearest whole megawatt.

(4177)

O O / S  ;

UNITSilVTDOWNS AND POWER REDUCTIONS CE O.

. i tc 1 DA1E /-lO-MO 6-80 COMPLETED HY H. H. UTackwe1I REPORT MONTil TELErilONE 912-367-/781 s

u 3 E

.! g };; Licensee ,E*,

  • e. Cause & Currective No. Date g 3g }Yh

,s5 Event *g?

g g3O Action to I- yE 5 j;gg Report # u. O g Prevent Recurrence 6 \ .

8019 800601 F 168 A 3 1-80-53 CF VALVEX Shutdown due to inop RilR valve E11-F017 8020 800608 F 150 A 3 1-80-55 Ild SUPORT Unit remained down for mechanical snubber repair 8021 800614 F 9 A 3 NA IIC XXXXX Rx scram - loss of condenser yacuum due to steam jet air ejecter failure 8022 800615 F 15 A 1 NA .

IIG DEMINX Condensate demins problems - low dP on suction valves 8023 800616 F 12 D 1 NA RB CONR00 Drop load due to control rod pattern adjustment - load drop st startup rarsp i 2 3 4 F: Forced Itcason: Method: Exhibit G Instruttions S: Scheduled A Equipment Failure (Explain) 1. Manual for Preparation of Data li-Maintenance of Test 2 Manual Scram. Entsy Sheets for Licensee C.ltefueling 3. Automatic Scram. Event Report (LERi rele (NUREG.

D-Itegulatory Restriction . 4 Other (Explain) 0161)

I'.-Operator Training & License Examination F.Administ rative 5

. G Operational Eirur (Explain) Exhibit I- Same Source (9/77) Il-Other (Explain)

o 6 .

fm . .

e DOCKETNO. 50-321  ;

' UNIT SilVTDOWNS AND POWER REDUCTIONS UNIT NAME flatch 1 .

DATE 7-10-Pn .,

' COMPLETED fiY R. M. Is l ackw<. l l 1

'." REPORT MONTil 6-P.0 TELErl10NE 912-367-7/81 I

I *

. e "t -

w o c Cause & Currecilve

.$ E }'., "Yh Licensee G t, c%

D Action to Nii. Date H

( 3g dE 5 3g5 "gI Event Report #

F'E tE U O

!O Prevent Re.urrence e .

c5 i F 50 A 1 NA IIC ZZZZZ Considerable load reduction due to  !

80-24 800617 loss of condenser vacuum - SJAE proportional bands off. .

NA IIA TURBIN Weekly turb test on 6 extensive 80-25 800621 S 1 D 1 check 6f bypass valves. ,

~

3 1-80-69 CJ VALVEX llPCI 06t of service - probs. with

  • 80-26 800626 F 103 A electronic and hydraulic systems *

. ~

1

+ 3 4 I 2 Method: Exhibit G Instructions F: Forced Reason: for Preparation of Data

1. Manual

- S: Scheduled A 1:ituipment Failure (Explain) Entry Sheets for Lt.ensee .

24f anual Scrarn.  !

ll M.iintenance of Test Event Report (LER) File (NUREG-C Itefucting 3. Automatic Scram.

0161)

D Itegulatory Restriction 4 Other(Explain)

E Operator Training & License Examinailon 5

- F. Administrative Exhibil1 Same Source .

G. Operational Error (Explain)

  • Il-Other (Explain)

(9/77) ~'

i

?,

NARRATIVE REPORT UNIT 1 June 1st Unit I remained shutdown due to inop RHR valve E11-F017. Shutdown was continued from 5-24.

Valve repaired and returned to service on 6-12.

June 8th Mechanical snubbers, having been locked up, were replaced on 6-8.

June 14th Loas of condense vacuum at 9:06. SJAE was not ejecting non-condensables. Load was reduced and normal vacuum was resumed.

June 15th Reduced load due to condensate demin problems.

Low dP on suction valves ceased. Load brought back up after valve checks.

June 15th Dropped load at 12:20 on 6-16 for control rod pattern adjustment.

June 17th toss of condenser vacuum at 8:00 on 6-17 due to SJAE proportional band being off. Bands adjusted ad SJAE returned to service 17:27 on 6-18.

June 21st Load reduced at 20:50 on 6-21 for weekly turbine testing. Extensive bypass valve checks and CIV checks proved satisfactory.

June 26 Rx scram at 6:49 on 6-26 due to a spike on the PRT relay, falsely indicating high reactor water level. However, startup Jas halted by HPCI failure. The problems were found in HPCI's electrical and hydraulic systems. The high pressure coolant injaction system remains down as o f 6-3 0-80.

There was no single release of radioactivity or single radiation exposure which accounts for more than 10% of the allowable annual values during June of 1980.

HATCH 1 SAFETY - RELATED MAINTENANCE REQUESTS TO BE REPORTED FOR JUNE 1980 NUMBER DATE COMPLETED DESCRIPTION 80-3073 6-23-80 Performed ultrasonic testing on elbow and welds of G31-6001 80-2553 5-29-80 Replaced ramp generator and EGM control box Cleaned and replaced gasket on 80-1527 6-16-80 steam line drain pot valve 80-2366 6-13-80 Disassembled RCIC trip and throttle valve yoke and yoke nut and slide nut. Tested and repaired 80 1935 6-16-80 Installed new RCIC exhaust rupture disk 80-3001 6-19-80 Replaced old compressor in control room air circulation unit and added freon 80-2462 6-19-80 Replaced RPIS probe on control rod #18-27 80-3148 6-19-80 Installed new 1/4" svagelok fitting on reactor water sample line isolation valve 80-3161 6-20-80 Replaced FIII valve on HCU #26-35 80-3162 6-20-80 Replaced FIII valve on HCU #26-19 80-3163 6-20-80 Replaced FIII valve on HCU #38-47 80-3164 6-20-80 Replaced isolation valve 111 on HCU 38-15 80-2677 6-16-80 Balanced SCR outputs wide load by connecting resistor bank to DC switch gear through spare breaker on lA & IB station battery chargers 80-2622 6-16-80 Repaired card readers at door at east intake D-130 80-2292 6-16-80 Replaced thermocouple on multi-point temp indicator

80-2101 6-16-80 Control building supply for 7C calibrated switches and checked dampers 80-1504 6-16-80 Ell-117 replaced NAIC with cotter pin and adjusted hanger to support pipe 80-693 6-16-80 Repaired 34-27 changing water isolation valve 80-1114 6-16-80 Repaired relief valve Cll-F012 on scram discharge 80-1772 6-16-80 Replaced RPIS probes for #10-19,

  1. 18-27 and #34-11 HCU 80-1815 6-18-80 Replaced RPIS ,-robe HCU #14-43 80-2434 6-18-80 Repaired RSCS group 14-07 80-2457 6-16-80 Replaced blown fuse on SRM drive 80-2620 6-16-80 Repaired Fill IBI valve on IC11-HCU-02-23 .

80-2621 6-16-80 Repaired F111 valve on ICll-10-19 80-2586 6-16-80 Replaced broken drive cable on Rx building stack rod monitor recorder 80-2575 6-16-80 Repaired CRD accum #18-03 IBI valve 80-472 6-12-80 Installed test valves on main steam line press, switch 80-2703 6-11-80 Pressurized line and torqued bolts to 790 lb. on 21" gate valve 80-806 6-6-80 lE11-109 installed stiffner plate 80-4: 4 6-4-80 Tightened nuts on hinges to Cl1-CRD-HT009 80-48 6-5-80 Tested shell side discharge valve on "B" heat exchanger 80-3186 6-18-80 Inspected station battery chargers 80-3180 6-18-80 Performed monthly P/M on 250 VDC LFCI inverters "A a

y . . :. -

  • 8 80-3'22 6-19-80 Repaired scram pilot valve on CRD 14-11 80-3110 6-19-80 Repaired 111 valve on CRD 1146-23 6-19-80 Replaced Cll-POOL valve on HCU 80-3109 42-07 6-19-80 Repaired CRD accum. valve 80-3074 ICll-F111 I

80-3073 '6-19-80 Replaced ICll-Fill ISC valve 80-3051 6-19-80 Repaired 130' elev, airlock doors to Rx building repaired latches 4

80-3040 6-19-80 Replaced CRD accum 0-35 Flll valve F111 valve was repaired on HCU 80-3029 6-19-80 18-27 Repaired flow controller to 80-2868 6-19-80

- RHP-SW pump 1D 80-2844 6-16-80 RHR serv water pump D discharge pressure indicator was calibrated 80-2748 6-19-80 C SRM CPS indicator adjusted 80-2699 6-16-80 Balanced SCR outputs on emergency station battery chargers

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