ML20115G745
| ML20115G745 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 03/31/1985 |
| From: | David Griffin, Nix H GEORGIA POWER CO. |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| GM-85-356, NUDOCS 8504220320 | |
| Download: ML20115G745 (14) | |
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NARRATIVE REPORT UNIT 1 March 1st 0000 At Rated Power.
1838 Preparing to reduce power to perform rod pattern adjustment.
1920 Reducing Power.
2032 At 500 MWE doing SRV and SV testing prior to pulling rods..
March 2nd 0120 Rod pattern adjustment complete increasing power; slow ramp due to high xenon transient.
March 10th 0008 KG8 Relay jumped out to clear GP.I AI trip, turbine testing and Control Rod Excercise.
0106 Turbine testing and Control Rod Excercise.
0200 Turbine Testing Complete.
0230 Hold due to feedwater heater problems.
0442 Ramping to rated.
March 16th 2300 Load reduction for HNP-1-3939 and Turbine Testing.
March 17th 0110 Turbine Test and 3939 complete.
March 19th 1000 Began reducing power to 35%
before manual scram to repair high floor drain leakage.
1242 Rx. Manually scrammed.
March 22nd 0712 Rx. Critical.
1955 Generator tied to line.
March 23rd 0430 Stopped scram recovery due to problems with RMCS.
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NARRATIVE REPORT UNIT 1 March 23rd 0820 Resumed Pulling Rods.
1458 Performing TSV Tests.
1548 TSV Test Complete.
1745 "D" Tip Stuck at core top.
March 24th 0405
'D" Tip machine fixed; resumed pulling rods.
0538 Resumed pulling rods; on preconditioning ramp to rated.
March 25th 0000 Plant Status: Preconditioning ramp to rated power.
0630 Plant now at 758 GNWe; 2313 CMWT.
March 26th 0000 Operating at 799 MWe; 2413 CMWT.
2306 Control Room Annunciator test completed (HNP-1-3075).
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March 29th 2150 Decreasing load to 500 MWe via Recirc. Flow for Rod Pattern Adjustment and cleaning of circulating water screens.
March 30th 0000 Reactor Load at 475 MWe.
0241 Began pulling rods and increasing load by small increments via recire.
March 31st 0000 Power holding at 600 GMWe due to "C" tip machine broken.
l 0716 Load increases via recirc. in progress. Power increasing back to rated.
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NARRATIVE REPORT UNIT 2 March 1st 0000 Rx. at Rated Power.
March 2nd 0010 Dropping load to 750 MWe to perform control rod exercise and turbine testing.
0055 Testing Complete.
March 7th 1018 Rx. manually scrammed to repair drywell equipment drain sump pump "2A".
March 9th 0603 Rx. Critical.
1533 Cenerator tied to line.
1758 Hold at 25% due to CRS failure.
1945 Resume ramp to rated.
March 10th 0020 Turbine test in progress.
0123 Turbine test complete.
0509 On preconditioning ramp to rated.
March 15th 2248 Reducing load to perform control rod exercise and HNP-2-3007.
March 16th 0045 Testing complete; increasing back to rated.
March 17th 0710 2nd stage MSR's out of service.
March 22nd 2329 Began load reduction for HNP-2-3939 and turbine testing.
March 23rd 0000 Ramping to rated after Turbine test.
0800 Plant now operating at rated power.
March 30th 0100 Dropping load to perform turbine testing.
0346 Turbine testing complete.
Power increased back to rated for continuation of month.
HATCH 1 SAFETY-RELATED MAINTENANCE REQUESTS TO BE REPORTED FOR MARCH 1985 NUMBER DATE COMPLETED DESCRIPTION 85-1409 02-19-85 Removed stem connecting Plate from MSIV in Steam Chase.
Drilled and Tapped for 3/8 set screw to stop stem rotation while in service.
DCR # 84-322 FCR i 84-322-2 MPL # 1B21-F022A 85-1410 02-19-85 Removed stem connecting Plate from MSIV in Steam Chase.
Drilled and Tapped for 3/8 set screw to stop stem rotation while in service.
DCR # 84-322 FCR # 84-322-2 MPL i 1B21-F0228 85-1411 02-19-85 Removed stem connecting Plate from MSIV in Steam Chase.
Drilled and Tapped for 3/8 set screw to stop stem rotation while in service.
DCR # 84-322 FCR # 84-322-2 MPL # IB21-F028A 85-1412 02-19-85 Removed stem connecting Plate from MSIV in Steam Chase.
Drilled and Tapped for 3/8 set screw to stop stem rotation while in service.
DCR # 84-322 FCR # 84-322-2 MPL i IB21-F028C 85-1413 02-19-85 Removed stem connecting Plate from MSIV in Steam Chase.
Drilled and Tapped for 3/8 set screw to stop i
stem rotation while in service.
DCR # 84-322 l
FCR # 84-322-2 MPL # 1821-F028B l
84-7241 12-14-85 Repair Recire. Steel Piping weld 1B31-28-B-3 per Nutech overlay design drawing (XGP-09-138) & HNP-1-10174.
DCR # 84-251.
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HATCH 1 SAFETY-RELATED MAINTENANCE REQUESTS TO BE REPORTED FOR MARCH 1985 NUMBER DATE COMPLETED DESCRIPTION 85-639 02-19-85 Terminate cable H11-P924-RP11B-C003 from Terminals AA-34,35,36 and relocate at AA-33,34,35 in Panel H11-P924 per FCR 81-138-398. Then close links AA-33,34,35 & 36. DCR 81-138R1 FCR # 81-138-398 MPLi B31-N0790.
84-6725 12-27-84 Remove existing support Ell-RHRH-6 per FCR 82-75-128.
Add new piping support E11-RHRH-712. DCRf 82-75 FCRf 82-75-128 WPS #
82-75-M040.
84-6047 12-19-85 Install / Remove Hardware in H11 and H21 Panels so that DCR 81-138 can be implemented.
WPSf T011-1 WPS f T011-2 MPL i A71.
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a-HATCH 2 SAFETY-RELATED MAINTENANCE REQUESTS TO BE REPORTED FOR MARCH 1985 NUMBER OATE COMPLETE 0 DESCRIPTION 85-1318 09-05-84 Complete installation of new H -02 Analyzer system 2
per OCR 81-165.
Also reference WPSi 81-165-C003, E008 - E0ll, E013-E015 thru E021, -E023, -E024, -J002 &
-P003.
84-4759 8-30-84 Remove existing switches install new switches and make wiring changes per FCR 81-165-107 & -108.
All work done in compliance with HNP-6921.
Redline all wiring changes.
MPL#
2P338-S25A & B.
OCR #
81-165.
85-1167 03-09-85 Investigate and repair Orywell Equipment Orain Sump Pump 2Gil-C006A.
Clearance
- 2-85-165.
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OPERATING DATA REPORT DOCKET NO.
50-321 DATE 04-10-85 CO N TED BY: D. Griffin TELEPHONE (912) 367-7781 x. 203 OPERATING STATUS Notes
- 1. Unit Name: E. I. Hatch Nuclear Plant Unit 1
- 2. Reporting Period: 03-85
- 3. Licensed Thermal Power (MWt): 2436
- 4. Nameplate Rating (Gross MWe): 809.3
- 5. Design Electrical Rating (Net MWe): 777.3
- 6. Maximtsn Dependable Capacity (Gross MWe): 801.2
- 7. Maximum Dependable Capacity (Net MWe): 752.2
- 8. If Changes Occur in Capacity Ratings (Items Number 3 through 7) Since Last Report, Give Reasons:
- 9. Power Level to Which Restricted, If Any (Net MWe)
- 10. Reasons for Restrictions, If Any:
This Month Yr-to-Date Cumulative i
- 11. Hours In Reporting Period 744 2160 81071
- 12. Number of Hours Reactor was Critical 701.5 1635.8 56799.8
- 13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0
- 14. Hours Generator On-Line 666.8 1486.6 53354.5
- 15. Unit Reserve Shutdown Hours 0.0 0.0 0.0 l
- 16. Gross Thermal Energy Generated (MWH) 1512024 3071023 112440213
- 17. Gross Electrical Energy Generated (MWH) 499350 1009950 36265670
- 18. Net Electrical Energy Generated (MWH) 477444 959289 34417135
- 19. Unit Service Factor 89.6 68.8 65.8
- 20. Unit Availability Factor 89.6 68.8 65.8
- 21. Unit Capacity Factor (Using MDC Net) 85.3 59.0 56.4
- 22. Unit Capacity Factor (Using DER Net) 82.6 57.1 54.6
- 23. Unit Forced Outage Rate 10.4 19.7 18.1
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
- 25. If Shutdown at End of Report Period, Estimated Date of Startup:
- 26. Units in Test Status (Prior to Commercial Operation):
Forecast Achieved l
INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION i
AVERA E DAILY UNIT POWER LEVEL-4 i
DOCKET NO.
50-321 DATE:
04-10-85 COWLETED BY: D. Griffin TELEPHOE (912) 367-7781 x. 203 MONTH 03-85 t
i DAY AVERAE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 711 17 764 2
686 18 776 3
775 19 360 4
771 20
-16 5
771 21
-16 6
779 22 3
7 776 23 321 8
776 24 566 9
770 25 741 10 762 26 763 11 772 27 767 12 766 28 765 e
13 775 29 742 14 767 30 555
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15 773 31 599 16 774 1
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OPERATING DATA REPmT DOCKET NO.
50-366 DATE 04-10-85 COWLETED BY: D. Griffin TELEPHONE (912) 367-7781 x 203 OPERATING STATUS Notes 1.
Unit Name: E. I. Hatch Nuclear Plant Unit 2 2.
Reporting Period: 03-85 3
Licensed Thermal Power (MWt): 2436 4
Nameplate Rating (Gross MWe): 817.0 5.
Design Electrical Rating (Net MWe): 784.0 6.
Maximim Dependable Capacity (Gross MWe): 803.9 7.
Maximum Dependable Capacity (Net MWe): 747.9 8.
If Changes Occur in Capacity Ratings (Items Number 3 through 7) Since Last Report, Give Reasons:
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Power Level to Which Restricted, If Any (Net MWe):
- 10. Reasons for Restrictions, If Any i
t This Month Yr-to-Date Cumulative i
- 11. Hours In Reporting Period 744 2160 48697
- 12. Number of Hours Reactor was Critical 700.3 2084.8 32264.8
- 13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0
- 14. Hours Generator On-Line 690.8 2057.9 30682.0
- 15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
- 16. Gross Thermal Energy Generated (MWH) 1637472 4807056 66008638
- 17. Gross Electrical Energy Generated (MWH) 545910 1608930 21768410
- 18. Net Electrical Energy Generated (MWH) 522516 1542098 20704547
- 19. Unit Service Factor 92.8 95.3 63.0
- 20. Unit Availability Factor 92.8 95.3 63.0
- 21. Unit Capacity Factor (Using M)C Net) 93.9 95.5 56.8
- 22. Unit Capacity Factor (Using DER Net) 89.6 91.1 54.2 j'
- 23. Unit Forced Outage Rate 7.2 4.7 12.3
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
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- 25. If Shutdown at End of Report Period, Estimated Date of Startup:
- 26. Units in Test Status (Prior to Commercial Operation):
Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY ComERCIAL OPERATION
AVERAT DAILY UNIT POWER LEVEL DOCKET NO.
50-366 DATE:
04-10-85 COWLETED BY: D. Griffin TELEPHOE (912) 367-7781 x 203 MONTH 02-85 OAY AVERAT DAILY POWER LEVEL DAY AVERAT DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 780 17 778 2
776 18 774 3
778 19 782 4
788 20 781 5
775 21 774 6
781 22 772 7
273 23 759 8
-17 24 777 9
44 25 780 10 572 26 782 11 755 27 778 12 768 28 775 13 776 29 771 14 772 30 763 15 772 31 770 16 770 (9/77) i
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50-36 DOCKET NO. Ha tc h 2 UNIT SilUTDOWNS AND FOWER REDUCTIONS UNIT NAMg DATE An t 11 in inac s,. o., -
COMPLETED sy M i e h a.1 March REFORT MONTH TELEPHONE ey t _ >ooo 5
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'Cause & Corrective
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$.!;"I; Licensco E.s;,
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No.
" Date -
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- 7. *
- 3 3 0, &
Event y
Eh Psevent Recurscnce
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6-c5 85-20 03-01-85 S
1 B
5 N/A HA TURBIN Turbine test anil control rod
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exercise 85-21 03-07-85 F
53.3 A
2 N/A CJ PUMPXX Load rehuction and manual scram to repair drywell equipment drain sump pump "2A" j
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85-22 03-09485 S
13.6 B
5 N/A CJ
'UMPXX Scram r.ecovery and turbine testing.
85-23 03-11-85 S
25 8
5, N/A RC (XXXXX Preconditioning ramp 85-24 b3-15-85 5
4 B
5 N/h RC
- 0NROD Control Rbd exercise 85-25 03-22-85 S
7 B
5 N/A RC
- 0NROD Control rod exercise and turbine t e s t i n g,.
3.
85-26 03-30-85 S
2.8 8
5 N/A HA TURBIN Turbine: testing.
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Exhibit C. Instructions F: Forced Reason:
1-)!1nu 1 D rfor Preparation of Data S: Scheduled ACluip:n-nt'Failue:(Explain) 2 m nealSen m.
Entry Sheets for Licensee W fr Event Report (LE RI File tNUREG-B4.lsinter.ance of Test J Autumatic Scram.
C. Refueling 4 -Continuations 6 ' ',
0161)
D Regulatory Restriction E Opetator Training & Ucense Examination 5-Ioad Peduction F Administrative 9-Other (Explain) 5
( >I Exhibit I Same Source G Operational Error (Explain)
J (9/77)
Il Other(Explain)
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l UNIT S!!UTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-32 Hatch 1 UNIT NAME l
DATE ADril 10. 1 Q R c; COMPLETED 8Y Mi chaal M < R a s, March 2887 '
REFORT MONTH TELEPHONE e x t.
'Cause & Corrective Licensec
$3,
$"3 5;
3
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Event u '2 n3 y
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' Date,
35 8
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P'"' R '8""
Repori*
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l 85-27 03-01-85 S
8 B
5 N/A RC-CONROD Rod pattein adjustment; SV &
SRV testing.
i 85-28 03-02-85 F
10.6 8
5 N/A RC XXXXXX Holding load during ramp because of high xenon content 85-29 03-:'l-85 S
'l B
5 N/A HA TURBIN Weekly '[drbine test and control rod exercise B5-30 03-16-85 5
4 8
5 N/A HA TURBIN Weekly.. turbine tes.t and control O
rod exerc.ise B5-31 03-19-85 F
81.9 A
2 N/A CB PUMPXX Load redu'ction and manual scram due t'o,high' floor drain leakage Scram, rec'overy 35-32 03-22-85 S
8.6 A
5 N/A CB 3 MPXX B5-33 03-23-85 F
3.8 A
5 N/A RB 20NROD Stopped iod movements following scram due to nrnblame with Dur
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Exhibit G -Instructions 3
I PMn) j.{
l Ser:m.
nt Sh eis fo L nsee f.. n'ce Event Report (LER) File INUREG.
( Te r'-
J. Automatic Scram.
C. Refueling 4 -Continuations
- 4. 1 0161)
D. Regulatory Restriction I.
E Operator Training & Ucense Examination 5-Ioad peduction
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h.5 F. Administrative 9-Other (Explain)
I Exhibit 1.Same Source G.Operattunal Error (Explain)
(9/77)
Il Other(Explain) t 3
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UNIT LIUTDOWNS AND FOWE t !! EDUCTIONS DOCKET NO. 5 0-171 UNIT N A. f E R2 + c h 1 DATE Anril in_ tong urnmu COMPLETED BY M i c h = = t i
March TELEPHONE ex t 7887 REPORT MONTy Licensec E r, b.-
' Casas & Corrective
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3 Yk Action to
- s j! s 5 Event uf No.
" Date -
k Prevent Recurrence dN
[
u jag Repori
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B5-34 03-23-85 S
1 B
5 N/A HF VALVEX Stopped increasing load due TSV fast closure testing 85-35 03-23-85 F
10.4 A
5 N/A RC CRDRVE
'D' ' tip inachine stuck at core t
top.
Precondhioningramp 85-36
'03-24-85 S
26.4 B
5 N/A RC XXXXXX 85-37 03-29-85 S
50.2 B
5
- N/A RC CONROD Rod Pattern adjustment 4
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' 4 Exhibit G Instructions I
2 Plethod:
F: Forced Reason:
1 F!2nual 7 trar Preparation orData S: Scheduled A.E:tuipm:nt'Failur:(Explain)
N.!anual Ser:m.
Entry Sheets for Licensee G.mintenance of Test J.Autumatic Scram.
H,, 6-Event Report (LERI File (NUREG-
- c. Refueling 4 -Continuations b
01611 D. Regulatory Resirletion E Opesatur Tralning & Ucense Examineilon 5-Ioad Pcduction
?
L 5 F. Administrative 9.-Other (Dcplain) t y s.
Exlilble 1.Same Source 4
G Operational Error (Explain)
(9/77)
II.Other (Emplain)
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Georgia Power Company Post offica Brx 439
' Bixity, Georgia 31513 Telephone 912 367-7781
-912 537-9444 Georgia Pbwer Edwin 1. Hatch Nuclear Plant April 8, 1985 GM-85-356 PLANT E.
I. HATCH NRC Monthly Operating Report Director Office of Inspection and Enforcement United States Nuclear Regulatory Commission Region II Suite 3100 101 Marietta Street Washington, D. C.
20555
Dear Sir:
Per Tech Specs section 6.9.1.6 please find attached the NRC Monthly Operating Report for Hatch Unit 1, Docket #50-321, and for Hatch Unit 2, Docket #50-366..
k H. C. Nix General Manager HCN/C(J/SMM/EZW/DRG/bb l
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