ML20214L767

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Monthly Operating Repts for June 1986
ML20214L767
Person / Time
Site: Hatch  Southern Nuclear icon.png
Issue date: 06/30/1986
From: Gucwa L, Kilroy T
GEORGIA POWER CO.
To:
NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
0537C, 537C, SL-973, NUDOCS 8609100364
Download: ML20214L767 (11)


Text

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NARRATIVE REPORT UNIT 1 June 1st 0000 Maintaining approximately 99%

Rated Thermal Power (RTP) with 105% core flow.

June 3rd 2030 Control Rod Pattern adjustment in progress.

June 4th 0500 Control Rod Pattern adjustment complete. Holding power at approximately 730 GMWe and 2270 CMWt due to Condensate Demin.

problems.

June 12th 2210 Reducing load for cold shutdown to repair leaks on drywell pneumatic system.

June 13th 0140 Reactor manually scrammed for repair of leaks on drywell pneumatic system.

1348 Reactor in cold shutdown.

June 15th 2225 Reactor declared critical.

June 16th 1258 Main Turbine tied to line.

Ramping to rated power.

June 18th 1100 Unit back at rated Maximum Dependable Capacity (MDC).

June 20th 2202 Reducing load for weekly turbine testing.

June 21st 0300 Testing complete. Back at rated MDC.

June 29th 0000 Reducing load for weekly turbine testing.

0200 Testing complete. Back at rated MDC.

June 30th 2400 Unit at 798 GMWe and 2416 CMWt.

No major equipment problems.

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8609100364 860630 PDR R

ADOCK 05000321 PDR

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OPERATING DATA REPORT

  • DOCKET NO.. 50-321 DATE 07-10-86 COMPLETED BY: Tom Kilroy TELEPHONE (912) 367-7851 x 2882 OPERATING STATUS
1. Unit Name: E. I. Hatch Nuclear Plant Unit 1
2. Reporting Period: 06-86
3. Licensed Thermal Power (MWt): 2436
4. Nameplate Rating (Gross MWe): 809.3
5. Design Electrical Rating (Net MWe): 777.3
6. Maximum Dependable Capacity (Gross MWe): 801.2
7. Maximum Dependable Capacity (Net MWe): 768.0
8. If changes occur in capacity ratings (Items Number 3 through 7) since last report, give reasons: N/A
9. Power level to which restricted, if any (Net MWe): No Restrictions
10. Reasons for restrictions, if any: N/A This Month Yr-t o-Date Cumulative
11. Hours In Reporting Period 720 4343 92014
12. Number of Hours Reactor was Critical 651.2 1311.1 63437.4
13. Reactor Reserve Shutdown Hours 0 0 0
14. Hours Generator On-Line 636.7 1026.4 59587.5
15. Unit Reserve Shutdown Hours 0 0 0
16. Gross Thermal Energy Generated (MWH) 1478712 2170656 126802146
17. Gross Electrical Energy Generated (MWH) 477750 690200 40932330-
18. Net Electrical Energy Generated (MWH) 455238 634535 38848623
19. Unit Service Factor (%) 88.4 23.6 64.8
20. Unit Availability Factor (%) 88.4 23.6 64.8
21. Unit Capacity Factor (% Using MDC Net) 82.3 23.6 55.0
22. Unit Capacity Factor (% Using DER Net) 81.3 18.8 54.3
23. Unit Forced Outage Rate 11.6 12.4 17.4
24. Shutdowns scheduled over next 6 months (Type, Date, and Duration of Each): N/A
25. If shutdown at end of report period, estimated date of startup: N/A
26. Units in Test Status (Prior to Commercial Operation): N/A E 1-2

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AVERAGE DAILY UNIT POWER LEVEL .

DOCKET NO. 50-321 DATE:- _07-10-86 COMPLETED BY: Tom Kilroy TELEPHONE (912);367-7851 x 2882-MONTH 06-86 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) ( MWe-Net )

1 747 17 462 -

2 744 18 713 3 729 19 749 4 687 20 740 5 705 21 751 6 706 22 755 7 703 23 756 8 715 24 754 9 751 25 .. 755 10 752 26 756 11 753 27 753 12 735 28 754 13 0 29 752 14 0 30 752 15 0 16 66 E 1-3

s UNIT SHUTDOWNS AND POWER REDUCTIONS -

DOCKET NO. 50-321 UNIT NAME HATCH ONE COMPLETED BY Tom Kilroy TELEPHONE (912) 367-7851 (2882) DATE JULY 10,1986 REPORT MONTH JUNE R S E Y T A MCTHOD OF LICENSEE SC Y S SHUTTING EVENT TO CAUSE & CORRECTIVE P DURATION O DOWN REPORT ED COMPONENT ACTION TO NO. DATE E (HOURS) N REACTOR NUMBER ME CODE PREVENT RECURRENCE 86-014 860601 F 68.50 A 5 N/A RC CONROD Rod Pdttern adjustment.

due to weak rod pattern 86-015 860603 S 8.50 A 5 N/A RC CONROD Rod Pattern adjustment due to weak rod pattern 86-016 860604 F 113.167 A 5 N/A HG DEMINX Backwash and precoat

-of condensate demineralizer.86-017 860608 F 95.58 A 5 N/A CH ZZZZZZ High feedwater inlet temperature & Low Condenser vacuum.86-018 860612 F 3.20 A 5 N/A XX VALVEX Derating to Scram.

F: Forced Reason: Method: Events reported involve S: Scheduled A-Equipment Failure (Explain) 1-Manual a greater than 20% reduction B-haintenance or Test 2-Manual Scram in average daily power level C-Ref ueling 3-Automatic Scram for the preceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

D-Regulatory Restriction 4-Continuations E-Operator Training & License 5-Load Reduction Examination 9-Other (Explain)

F-Administrative G-Operational Error (Explain)

H-Other (Explain)

E l-4

UNIT SHUTDOWNS AND POWER REDUCTIONS -

DOCKET NO. 50-321 UNIT NAME HATCH ONE COMPLETED BY Tom Kilroy TELEPHONE (912) 367-7851 (2882) DATE JULY 10,1986' REPORT MONTH JUNE R S E Y T A METHOD OF LICENSEE SC Y S SHUTTING EVENT TO CAUSE & CORRECTIVE P DURATION O DOWN REPORT ED COMPONENT ACTION TO NO. DATE E (HOURS) N REACTOR NUMBER ME CODE PREVENT RECURRENCE 86-019 860613 F 83.3 A 2 N/A XX VALVEX Scram to fix leaks of T48-F319 & 20.86-020 860616 F 46.03 A 5 N/A XX VALVEX Ramping from above scram.86-021 860620 S 4.97 B 5 N/A HA TURBIN Weekly turbine testing 86-022 860629 s 2.0 B 5 N/A HA TURBIN Weekly turbine testing F: Forced Reason: Method: Events reported involve-S: Scheduled A-Equipment Failure (Explain) 1-Manual a greater than 20% reduction B-Maintenance or Test 2-Manual Scram in average daily power level C-Refueling 3-Automatic Scram for the preceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

D-Regulatory Restriction 4-Continuations E-Operator Training & License 5-Load Reduction Examination 9-Other (Explain)

F-Administrative G-Operational Error (Explain)

H-Other (Explain) s E l-5

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NARRATIVE REPORT UNIT 2 June 1st 0000 Unit maintaining 85% Rated Thermal Power (RTP).

June 8th 0255 Reducing load for control rod exercise.

0330 Back at 85% RTP.

June 13th 2354 Reducing lead for control rod exercise.

June 14th 0300 Back at 85% RTP.

June 21st 2l00 Reducing load for weekly turbine testing.

-June 22nd 0500 Back at 85% RTP.

June 27th 2l00 Power reduction for steam leak repair.

June 28th 0938 Autonatic scram while reducing power for steam leak repair.

June 30th 2400 Unit in hot shutdown for steam leak repair.

Expected startup date: July 03, 1986.

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e OPERATING DATA REPORT -

DOCKET NO. 50-366 DATE 07-10-86 COMPLETED BY: Tom Kilroy TELEPHONE (912) 367-7851 x 2882 OPERATING STATUS

1. Unit Name: E. I. Hatch Nuclear Plant Unit 2 1 2. Reporting Period: 06-86
3. Licensed Thermal Power (MWt): 2436
4. Nameplate Rating (Gross MWe): 817.0
5. Design Electrical Rating (Net MWe): 784.0
6. Maximum Dependable Capacity (Gross MWe): 803.9
7. Maximum Dependable Capacity (Net MWe): 777.0 j 8. If changes occur in capacity ratings (Items Number 3 through 7) since last report, give reasons: N/A
9. Power level to which restricted, if any (Net MWe) No Restrictions t 10. Reasons for restrictions, if any: N/A

)

This Month Yr-to-Date Cumulative

11. Hours In Reporting Period 720 4343 59640
12. Number of Hours Reactor was Critical 657.7 4127.5 41699.1
13. Reactor Reserve Shutdown Hours 0 0 0
14. Hours Generator On-Line 657.7 4052.3 39920.5 i
15. Unit Reserve Shutdown Hours 0 0 0
16. Gross Thermal Energy Generated (MWH) 1345992 8288200 86471406 j 17. Gross Electrical Energy Generated (MWH) 425710 2692310 28473810
18. Net Electrical Energy Generated (MWH) 403113 2562785 -27101439 j 19. Unit Service Factor (%) 91.3 93.3 66.9
20. Unit Availability Factor (%) 91.3 93.3 66.9
21. Unit Capacity Factor (% Using MDC Net) . 72.1 75.9 58.5 l 22. Urait Capacity Factor (% Using DER Net) 71.4 75.3 58.0 0.0 5.3 10.4
23. Unit Forced Outage Rate
24. Shutdowns scheduled over next 6 months (Type, Date, and Duration. of Each):

! Refueling Outage, September 08, 1986 8 weeks

25. If shutdown at ead of report period, estimated date of startup: N/A
26. Units in Test Status (Prior to Commercial Operation): N/A E 2-2

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l AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.- 50-366 DATE: 07-10-86 COMPLETED BY: Tom Kilroy TELEPHONE (912) 367-7851 x 2882

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MONTH 06-86

. DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL l- (MWe-Net) (MWe-Net) 1 624 17 620 2 627 18 622 j 3 627 19 618 4 626 20 619 5 626 21 610

6 625 22 618 I

, 7 625 23 -620 8 621 24 621 1 9 625 25 619 j 10 622 26 617 l 11 622 27 591.

! 12 619 28 71-13 622 29 .0 14 623 30 0'

{ 15 623

+

16 622 S

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-366 UNIT NAME HATCH TWO COMPLETED BY Tom Kilroy TELEPHONE (912) 367-7851 (2882) DATE JULY 10, 1986 REPORT MONTH JUNE R S E Y 2 A METHOD OF LICENSEE SC Y S SHUTTING EVENT TO CAUSE & CORRECTIVE P DURATION O DOWN REPORT ED COMPONENT ACTION TO NO. DATE E (HOURS) .I REACTOR NUMBER ME CODE PREVENT RECURRENCE 86-036 860601 S 170.9 H 5 N/A ZZ ZZZZZZ Management decision to reduce power to 85% in order to reduce offgas activity in Rx. and Turbine building caused by leaking f uel.86-037 860608 S 0.6 B 5 N/A RC CONROD Control rod exercise.86-030 860608 S 140.40 H 5 N/A ZZ ZZZZZZ See 86-036.

F: Forced Reason: Method: Events reported involve S: Scheduled A-Equipment Failure (Explain) 1-Manual a greater than 20% reduction B-Maintenance or Test 2-Manual Scram in average daily power level C-Refueling 3-Automatic Scram for the preceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

D-Regulatory Restriction 4-Continuations E-Operator Training & License 5-Load Reduction Examination 9-Other (Explain)

F-Administrative G-Operational Error (Explain)

H-Other (Explain)

E 2-4

] UNIT SHUTDOWNS AND POWER REDUCTIONS .'

i DOCKET NO. 50-366 UNIT NAME HATCH TWO COMPLETED BY Tom Kilroy TELEPHONE (912) 367-7851 (2882) DATE JULY 10, 1986 REPORT MONTH JUNE

R S v y

. T A METHOD OF LICENSEE SC I

Y S SHUTTING EVENT TO CAUSE & CORRECTIVE l P DURATION O DOWN REPORT ED COMPONENT ACTION TO NO. DATE E (HOURS) N REACTOR NUMBER' ME CODE PREVENT RECURRENCE l -

l 86-039 860613 S 3.1 B 5 N/A RC CONROD Control rod exercise .

l 86-040 860614 S 186.0 H 5 N/A ZZ ZZZZZZ See 86-036.86-041 860621 S 8.0 B 5 N/A HA TURBIN heekly turbine testing i 86-042 860622 S 136.0 H 5 N/A ZZ. ZZZZZZ See 86-036.

i 86-043 860627 S 12.6 A 5 N/A CH ZZZZZZ Reducing power for cold shutdown, i

j 86-044 860628 S 62.4 A 3 028612 CH ZZZZZZ Scram to repair steam j leaks.

1 l F: Forced Reason: Method: Events reported involve l S: Scheduled A-Equipment Failure (Explain) 1-Manual a greater than 20% reduction B-Maintenance or Test 2-Manual Scram in average daily power level'

! C-Pefueling 3-Automatic Scram for the preceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

1 D-Regulatory Restriction 4-Continuations

{ E-Operator Training & License 5-Load Reduction Examination 9-Other (Explain)

! F-Administrative G-Operational Error (Explain)

H-Other (Explain)

]

E 2-5

b Georgis Power Company 333 Piedrnont Avenue Atlanta, Georgia 30308 Telephone 404 5264526 Mailing Address:

Fest Office Box 4545 Atlanta, Georgia 30302 Georgia Power L T. Gucws the southem e!&fnc system Manager Nuclear Safety and Licensing Nuclear Operations NRC Monthly Operating Report File: X7GJ10-H000 Log: SL-973 Director Office of Management and Program Analysis U. S. Nuclear Regulatory Commission Washington, D. C. 20555

Dear Sir:

Enclosed is the NRC Monthly Operating Report for Hatch Unit 1, Docket Number 50-321, and for Hatch Unit 2, Docket Number 50-366 This report is submitted pursuant to Technical Specifications Section 6.9.1.10 c

Sincerely,

/f*9cs L. T. Gucwa LGB/lc Enclosure c: Georgia Power Company Nuclear Regulatory Commission hr, d. P. O'Reilly Dr. J. N. Grace, Regional Administrator 1r. J. T. Beckliam, Jr. Senior Resident Inspector

c. H. C. Nix, Jr.

S-NORMS i

0537C 19