ML20205D696

Monthly Operating Repts for May 1986

ML20205D696
Person / Time
Site:	Hatch
Issue date:	05/31/1986
From:	Gucwa L, Koerber G GEORGIA POWER CO.
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
SL-861, NUDOCS 8608180154
Download: ML20205D696 (13)

Text

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NARRATIVE REPORT UNIT 1 Date Time Event May lat 0000 Final preparations for startup in progress.

May 3rd 1116 Reactor declared critical.

May 13th 0450 Tied to the grid following numerous required post outage tests.

May 15th 0225 At 35% rated thermal power (RTP);

increasing power.

0820 Reactor scram due to MSIV closure.

1637 Reactor declared critical.

2155 Tied to the grid.

May 18th 1130 scram time testing completer increasing power.

May 19th 0800 At 430 MWe.

1420 "A" recire. pump tripped. Some rods manually inserted to comply with specifications.

1840 Power ascension resumed.

May 20th 0212 Began preconditioning ramp at 633 NWe.

May 21st 1330 At 92% RTP, reactor scrammed on MSIV closure.

May 22nd 0435 Reactor declared critical.

1322 Tied to the grid.

2250 At 440 MWe; began establishing ramp.

May 25th 2230 Achieved 98% RTP with 105% core flow.

kDR kh0CK05000321 54 860531 R

1 of 2 5g

NARRATIVE REPORT (Continued)

UNIT 1 Date Time Event May 30th 2100 Began reducing load to 650 MWe to perform control rod pattern adjustment.

May 31st 0200 Load increased to 750 MWe following pattern adjustment; began ramp to full power.

0900 Achieved 1001 RTP.

2400 Maintaining approximately 994 RTP with 105%

core flow.

4 5

1 2 of 2

OPERATING DATA REPORT i

UNIT 1 DOCKET NO.:

50-321 DATE:

06-10-86 COMPLETED BY: Gary Koerber TELEPHONE:

(912) 367-7851 r 2882 Operating Status 1.

Unit name: E. I. Hatch Nuclear Plant Unit 1 2.

Reporting period:

05-86 3.

Licensed thermal power (MWt):

2436.0 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 (item numbers 3 through 7) since last report, give reasons:

9.

Power level to which restricted, if any (net MWe):

No restrictions

10. Reasons for restrictions, if any:

N/A Current Month Yr-to-Date Cumulative

11. Hours in reporting period 744 3623 91294

12. Number of hours reactor was critical 659.9 659.9 62786.1

13. Reactor reserve shutdown hours 0

0 0

14. Hours generator on was line 389.7 389.7 58950.8

15. Unit reserve shutdown hours 0

0 0

16. Gross thermal energy generated (MWh) 691944 691944 125323434

17. Gross electrical energy generated (MWh) 212450 212450 40565680

18. Net electrical energy generated (MWh) 195861 179297 38393385

19. Unit service factor (t) 52.4 10.8 64.6

20. Unit availability factor (t) 52.4 10.8 64.6

21. Unit capacity factot (t using MDC Net) 34.3 6.4 54.8

22. Unit capacity f actor (t using DER Net) 33.9 6.4 54.1

23. Unit forced outage rate 13.6 13.6 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

~

AVERAGE DAILY UNIT POWER LEVEL UNIT I DOCKET NO.:

50-321 DATE:

06-10-86 COMPLETED BY: Gary Koerber TELEPHONE:

(912) 367-7851 x 2882 MONTH: 05-86 Average Daily Power Level Average Daily Power Level Day (MWe-Net)

Day (MWe-Net) 1 0

17 184 2

0 18 220 3

0 19 382 4

0 20 566 5

0 21 353 6

0 22 120 7

0 23 484 8

0 24 636 9

0 25 727 10 0

26 741 11 0

27 737 12 0

28 734 13 85 29 737 14 130 30 719 15 62 31 737 16 0

t

~

J 1

UNIT SHUTDOWNS AND POWER REDUCTIONS (SHEET 1 OF 2)

DOCKET NO.:

50-321 UNIT NAME:

Hatch Unit 1 COMPLETED BY: Gary M. Koerber TELEPHONE: (912) 367-7851 (2882) DATE:

June 10,1986 REPORT MONTH - MAY R

S E

Y T

A METHOD OF LICENSEE SC Y

S SHUTTING EVENT TO CAUSE AND CORRECTIVE P

DURATION O

DOWN REPORT ED COMPONENT ACTION TO NUMBER DATE E

(hours)

N REACTOR NUMBER ME CODE PREVENT RECURRENCE 86-005 860501 S

292.83 C

4 N/A RC FUELXX Extended refueling outag e.86-006 860513 S

51.50 C

5 N/A RC FUELXX Outage recovery and testing.86-007 860515 F

37.58 A

3 1-86-23 CC VALVEX Automatic scram on MSIV closure.86-008 860516 S

64.42 A

5 N/A CC VALVEX Scram recovery and outage recovery testing.86-009 860519 F

6.42 A

5 N/A CB PUMPXX Recirc Pump A tripped.

LEGEND NOTE j

l l

F = Forced Reason:

Method:

Events reported involve S = Scheduled A = Equipment f ailure (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 E license 5 = Load reduction examination 9 = Other (explain)

F = Administrative G = Operational error (explain)

H = Other (explain)

U"IT SHUTDOWNS AND POWER REDUCTIONS (SHEET 2 OF 2)

DOCKET NO.:

50-321 UNIT NAME:

Hatch Unit 1 COMPLETED BY: Gary M. Koerber TELEPHONE:

(912) 367-7851 (2882) DATE June 10, 1986 REPORT MONTH - MAY R

S E

Y T

A METHOD OF LICENSEE SC Y

S SHUTTING EVENT TO CAUSE AND CORRECTIVE P

DURATION O

DOWN REPORT ED COMPONENT ACTION TO NUMBER DATE E

(hours)

N REACTOR NUMBER ME CODE PREVENT RECURRENCE 86-010 860519 S

40.75 A

5 N/A CC VALVEX Continued outage Recovery.86-011 860521 F

23.87 A

3 1-86-18 CC VALVEX Automatic scram on MSIV closure.86-011 860522 S

82.66 A

5 N/A CC VALVEX Scram recovery.86-013 860530 F

8.00 B

5 N/A RC CONROD Rod pattern adjustment due to weak rod pattern.

LEGEND NOTE 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)

NARRATIVE REPORT UNIT 2 Date Time Event May 1st 0000 Maintaining 85% rated thermal power (RTP).

May 3rd 2235 Reduced load to 600 MWe for weekly surveillances.

May 4th 0150 Power increased to 85% RTP following testing.

May 10th 2345 Reduced load to 600 MWe for weekly surveillances.

May lith 0020 Power increased to 85% RTP following testing.

1105 Reduced load by 6.0 MWe to investigate main turbine bearing vibration problem.

1500 Power increased to 85% MWe RTP following resolution of bearing vibration problem..

May 18th 0022 Load increased to 335 MWe for various surveillances and for cleaning of circulating water screens.

1711 Power increase to 85% RTP.

May 25th 0015 Load reduced to 600 MWe for weekly surveillance.

0110 Testing completed; load increased; returning to 85% RTP.

May 31st 2400 steady-state operation continuing at 85% RTP.

OPERATING DATA REPORT UNIT 2 DOCKET NO.:

50-366 DATE:

06-10-86 COMPLETED BY: Gary Koerber TELEPHONE:

(912) 367-7851 x 2882 Operating Status

1. Unit name: E. I. Hatch Nuclear Plant Unit 2

2. Reporting period:

05-86

3. Licensed thermal power (MWt):

2436.0

4. Nameplate rating (gross MWe):

817.0

5. Design electrical ratire (net me):

784.0

6. Maximum dependable capacity (gross MWe):

803.9

7. Maximum dependable capacity (net me):

777.0

8. If changes occur in capacity ratings (item numbers 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 Current Month Yr-to-Date Cumulative

11. Hours in reporting period 744 3623 58920

12. Number of hours reactor was critical 744.0 3469.9 41041.4

13. Reactor reserve shutdown hours 0

0 0

14. Hours generator was on line 744.0 3394.7 39262.8

15. Unit reserve shutdown hours 0

0 0

16. Gross thermal energy generated (wh) 1523856 6942208 85125414

17. Gross electrical energy generated (MWh) 487840 2266600 28048100

18. Net electrical energy generated (wh) 465389 2159672 26698326

19. Unit service factor (s) 100.0 93.7 66.6

20. Unit availability factor (s) 100.0 93.7 66.6

21. Unit capacity factor (t using MDC net) 80.5 76.7 58.3

22. Unit capacity f actor (t using DER net) 79.8 76.0 57.8

23. Unit forced outage rate 0.0 6.3 10.6

24. Shutdowns scheduled over next 6 months (type, date, and duration of each): N/A Refueling outage, September 6, 1986: 8 weeks

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 L

~.:

. AVERAGE DAILY UNIT POWER LEVEL UNIT 2 DOCKET NO.:

50-366 DATE:

06-10-86 COMPLETED BY: Gary Koerber TELEPHONE:

(912) 367-7851 x 2882 i

i

]

I MONTH: 05-86 I

Average Daily Power Level Average Daily Power Level g

(MWe-Net) g (MWe-Net)

I 1

636 17 627 l

2 633 18 496 1

3 638 19 625 1

4 634 20 626 5

634 21 628 l

6 633 22 630 7

631 23 629 8

630 24 628

)

9 625 25 627 10 638 26 629 11 630 27 626 12 631 28 625 13 630 29 626 14 631 30 627 15 630 31 627 16 631

UNIT SHUTDOWNS AND POWER REDUCTIONS (SHEET 1 OF 3)

DOCKET NO.:

5D-366 UNIT NAME:

Hatch Unit 2 COMPLETED BY: Gary M. Koerber TELEPHONS: (912) 367-7851 (2882) DATE JUNE 10, 1986 REPORT MONTH - MAY i

R S

E Y

T A

METHOD OF LICENSEE SC Y

S SHUTTING EVENT TO CAUSE AND CORRECTIVE P

DURATION O

DOWN REPORT ED COMPONENT ACTION TO NUMBER DATE E

(hours)

N REACTOR NUMBER ME CODE PREVENT RECURRENCE 86-025 860501 S

71.37 H

5 N/A ZT ZZZZZZ Management decision to reduce power to 85%.

Due to high offgas activity in Rx. and Turbine j

Buildings caused by leaking fuel.86-026 860503 S

4.63 a

5 N/A HA TURBIN Reducing power for I

weekly turbine testing.86-027 860504 S

128.92 H

5 N/A ZZ ZZZZZZ See 86-025.

LEGEND NOTE F = Forced Reason:

Method:

Events reported involve j

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)

UNIT SHUTDOWNS AND POWER REDUCTIONS (SHERT 2 OF 3)

A DOCKET NO.:

50-366 UXIT NAME:

Hatch Unit 2 COMPLETED BY: Gary M. Koerber TELEPHONE: (912) 367-7851 (2882) DATE June 10, 1986 REPORT MONTH - MAY R

S E

Y T

A METHOD OF LICENSEE SC Y

S SHUTTING EVENT TO CAUSE AND CORRECTIVE P

DURATION O

<DOWN REPORT ED COMPONENT ACTION TO NUMBER DATE E

(hours)

N REACTOR NUMBER.

ME CODE PREVENT RECURRENCE 86-028 860509-F 3.08 A

5 N/A CH RELAYX 7th stage A F/W heater flooded due to relay 2N31-K5B short.86-029 860509 s

31.67 H

5 N/A ZZ ZZZZZZ See 86-025.86-030 860510 S

3.33 B

5 N/A HA TURBIN Reducing power for weekly trubine testi ng.86-031 860511 S

164.75 H

5 N/A ZZ ZZZZZZ See 86-025.86-032 860517 F

18.25 B

5 N/A CB XXXXXX Reducing power to clean circ. water screens.

LEGEND NOTE F = Forced Reason:

Method:

Events reported involve S = ScheduHed 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)

UNIT SHUTDOWNS AND POWER REDUCTIONS (SHEET 3 OF 3) 8 DOCKET NO.:

50-366 UNIT NAME:

Hatch Unit 2 COMPLETED BY: Gary M. Koerber TELEPHONE: (912) 367-7851 (2882) DATE June 10, 1986 REPORT MONTH - MAY I

R S

E Y

T A

METHOD OF LICENSEE SC Y

S SHUTTING EVENT TO Ct.USE AND CORRECTIVE P

DURATION O

DOWN REPORT ED COMPONENT ACTION TO NUMBER DATE E

(hours)

N REACTOR NUMBER ME CODE PREVENT RECURRENCE 86-033 860518 S

150.25 H

5 N/A ZZ ZZZZZL See 86-025.

I 86-034 8605:25 S

1. 17 B

5 N/A HA TURBIN Weekly turbine testing and control rod exercise.86-035 860525 S

166.58 H

5 N/A ZZ ZZZZZZ See 86-025.

4 LEGEND l

NOTE l

F = Forced Reason:

Method:

Events reported involve S = Scheduled A = Equipment failure (explain) 1 = Manual a greater than 20% reduction i

a = 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 3 = Operator training & license 5 = Load reduction examination 9 = Other (explain)

? = Administrative l

G = Operational error (explain)

H = Other (explain)

I

Georgia Fower Company 333 Piedmont Avenue Atlanta, Georgia 30308 Telephone 404 526-6526 Mailing Address:

Post Office Box 4545 Atlanta, Georgia 30302 Georgia Power (Fe southe n Rwc sfrom w

L T.oucwa Manager Nuclear Safety and Licensing June 10,1986 Nuclear Operations NRC Monthly Operating Report File: X7GJ10-H000 Log: SL-861 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 Sincerely,

/f %

L. T. Gucwa LGB/lc Enclosure c: Georgia Power Company Nuclear Regulatory Commissio:

Mr. d. P. O'Reilly Dr. d. N. Grace, Regional Adijiinistrator Mr. J. T. Beckham, Jr.

Senior Resident inspector Mr. H. C. Nix, Jr.

GO-NORMS b

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