HL-5805, Monthly Operating Repts for June 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With
| ML20209H130 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 06/30/1999 |
| From: | Shannon Rogers, Sumner H SOUTHERN NUCLEAR OPERATING CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| HL-5805, NUDOCS 9907200139 | |
| Download: ML20209H130 (7) | |
Text
.. .
. 14wis Sumner Southern Nuclear Vice President Operating Company. lac.
Hatch Project Support 40 invemess Parkway Post Office Box 1295 Binningham. Alabama 35201 Tel 205.992.7279 l Fax 205.992.0341 SOUTHERN h COMPANY Energy to Serve YourWorld" July 14, 1999 Docket Nos. 50-321 50-366 11L-5805 U.S. Nuclear Regulatory Commission A~ITN: Document Control Desk Washington, D. C. 20555 Edwin I.11atch Nuclear Plant Monthly Operatina Renons Ladies and Gentlemen:
I Enclosed are the June 1999 Monthly Operating Reports for Edwin 1. Hatch Nuclear Plant Unit 1, 1 Docket No. 50-321, and Unit 2, Docket No. 50-366. These reports are submitted in accordance with Technical Specifications 5.6.4.
Respectfully submitted, 6'tM ;
II. L. Sumner, Jr.
IFL/eb 1
Enclosures:
- l. June Monthly Operating Report for Plant llatch Unit 1
- 2. June Monthly Operating Report for Plant Hatch Unit 2 1
cc: Southern Nuclear Oneratinn Comnany Mr. P. H. Wells, Nuclear Plant General Manager SNC Document Management (R-Type A02.001)
U. S. Nuclear Reculatory Commission. Washington D. C.
- Mr. L. N. Olshan, Project Manager - liatch
\
U. S. Nucigar Reculatory Commission. Region 11
\
'~
Mr. L. A. Reyes, Regional Administrator 'E !
Mr. J. T. Munday, Senior Resident inspector - Hatch
/g hy Utility Data Institute. Inc.
Ms. Barbara Lewis - McGraw-liill Companies n n n :> ~
9907200139 990630 PDR ADOCK 05000321 R PDR
Enclosure 1 Plant Hatch Unit I l Monthly Operating Report June 1999 Table of Contents Pace Operating Data Report El-1 Unit Shutdowns and Power Reductions El-2
~
OPERATING DATA REPORT Docket No.: _50-321 Unit Name: E.1. Hatch Unit 1 Date: July 6,1999 Completed By- S. B. Rogers Telephone: (912) 367-7781 x2878 Operating _ Status
- 1. Reporting Period: JUNE 1999
- 2. Design Electrical Rating (Net MWe): 864.6
- 3. Maximum Dependable Capacity (Net MWe): 838 ThisRooth YeaLIo3 ate Cumulative .
- 4. Numbe of Hours ReactorWas Critical: 720.0 3,005.7 161,746.0
- 5. Hours Generator On Line: 620.1 2,736.7 156,054.3
- 6. Unit Reserve Shutdown Hours: 0.0 0.0 0.0
- 7. Net Electrical Energy Generated: 519,021 2,140,448 110,184,605 CHALLENGES TO MAIN STEAM SAFETY / RELIEF VALVES Date Tag No. Event Desenption No challenges this month.
I E1-1
UNIT SHUTDOWNS Docket No.: _50-321 Unit Name: E. l. Hatch Unit 1 Date: July 6,1999 Completed By: S. B. Rogers Telephone: (912) 367-7781 x2878 Reporting Period: JUNE 1999 Type Method of F: Forced Duration Shutting Cause/ Corrective Actions No. Date s; sen. oui.o (Hours) Reason (1) Down (2) Comrnents99-005 990623 F 99.9 A 5 The Main Generator was removed from the grid to repair a steam leak on the "A" Moisture Separator Reheater drain piping. The leak was repaired and the unit was returned to approximately 98.5% of rated thermal power. Reactor power was maintained at approximately 11% of rated while the generator was offline.
. (1) Reason: (2) METHOD A-Equipment Failure (Explain) 1-Manual B-Maintenance or Test 2-Manual Trip / Scram C-Refueling 3-Automatic Trip / Scram D-Regulatory Restriction 4-Continuation E-Operator Training / License Examination 5-Other (Explain)
F-Administrative G-Operational Error (Explain)
H-Other (Explain)
CAUSE/ CORRECTIVE ACTION / COMMENTS:
NARRATIVE REPORT
. Unit 1 began the month of June operating at rated thermal power. Shift reduced load to approximately 830 GMWe on 6/1/99 to perform a rod pattern adjustment. The unit was returned to rated thermal power later that day.
Shift briefly reduced load to approximately 895 GMWe on 6/17/93 to atddress a high level alarm in the "A" 8'th Stage Feedwater Heater. Shift began reducing load on 6/22/99 to remove the generator from the grid and repair a steam leak on the "A" Moisture Separator Reheater drain piping. The unit was removed from the grid on 6/23/99.
The unit was retumed to the grid on 6/27/99 and attained approximately 97.5% of rated thermal power on 6/28/99.
Shift reduced load to approximately 755 GMWe on 6/28/99 to perform a rod pattern adjustment. Shift began power ascension on 6/29/99. Ascension was terminated on 6/30/99 with the unit at approximately 98.5% of rated thermal power due to concerns with main condenser vacuum paranieters. Shift continued to maintain rpproximately 98.5% of rated thermal power for the remainder of the month.
E12 i
l .
i Enclosure 2 Plant Hatch Unit 2 Monthly Operating Report June 1999
)
Table of Contents Page i
Operating Data Report E2-1 Unit Shutdowns and Power Reductions E2-2 l
l l
l
7 OPERATING DATA REPORT Docket No.: _50-366 Unit Name: E. l. Hatch Unit 2 Date: July 6,1999 Completed By: S. B. Rogers Telephone: (912) 367-7781 x2878 Operating. Status
- 1. Reporting Period: JUNE 1999
- 2. Design Electrical Rating (Net MWe): 859
- 3. Maximum Dependable Capacity (Net MWe): 855 Ihis]Aootb YeaLTADate Cumulative
- 4. Number of Hours Reactor Was Critical: 5193 3,931.0 138,077.9
- 5. Hours Generator On Line: 476.3 3,756.8 133,855.8
- 6. Unit Reserve Shutdown Hours: 0.0 0.0 0.0__
- 7. Net Electrical Energy Generated: 388,785~ 3,211,275 95,847,447 CHALLENGES TO MAIN STEAM SAFETY / RELIEF VALVES Date Tag No. Event Description 990615 2B21-F013A Shift inserted a manual scram and tripped the main turbine at 265 GMWe , following 2B21-F013B a load reduction from 2710 CMWT. The unit was shutdown due to a loss of vacuum 2821-F013C in the main condenser. Following the scram, the condensate pumps and condensate 2B21-F013D booster pumps were not available; therefore, the reactor feedpumps could not be 2B21-F013E used to control reactor water level. The reactor core isolation cooling (RCIC) 2B21-F013F system was used to make up water to the reactor vessel and the safety / relief 2B21-F013G val as were actuated manually to control reactor pressure. During the event, no 2B21-F013H safety relief valves were required to have opened automatically, and none did so.
2B21-F013K (reference Licensee Event Report 99-006) 2B21-F013L 2B21-F013M I
l E2-1 L 1
UNIT SHUTDOWNS Docket No.: 50-366 Unit Name: E.1. Hatch Unit 2 Date: . July 6,1999 Completed By: S. B. Rogers Reporting Period: JUNE 1999 Telephone: (912) 367 7781 x2878 Type Method of F; Forced Duration Shutting Cause/ Corrective Actions No. Date s: sen.omo (Hours) Reason (1) Down (2) Comments99-004 990615 F 184.4 H 2 Shift inserted a manual ceram and tripped the main turbine at 265 GMWe, following a load reduction from 2710 CMWT. The unit was shutdown due to a loss of vacuum in the main condenser, which occurred when the condenser became unable to reject heat at a rate sufficient to accommodate full power steam flow. (continued below)99-005 990628 F 59.3 G 3 An automatic scram occurred on low reactor water level. The low reactor water level occurred as a result of personnel failing to perform a required valve lineup. (continued below(
(1) Reason: (2) METHOD A-Equipment Failure (Explain) 1-Manual B-Maintenance or Test 2-Manual Trip / Scram C-Refueling 3-Automatic Trip / Scram D-Regulatory Restriction 4-Continuation E-Operator Training / License Examination 5-Other (Explain)
F-Administrative G-Operational Error (Explain)
H-Other (Explain)
CAUSE/ CORRECTIVE ACTION / COMMENTS:
99-004 (continued) Corrective actions include the issuance of an operating order, on both units, which establishes operating limits for several parameters that affect condenser vacuum and the addition of a level instrument in the circulating water pump suction pit.
(reference Licensee Event Report 99-006)99-005 (continued) while filling and venting the "B" cold reference leg keepfill system. Corrective actions include disciplining involved personnel and changing the calibration of a level instrument. (reference Licensee Event Report 99-007)
NARRATIVE REPORT Unit 2 began the month of June operating at approximately 2708 CMWT. Shift began reducing load on 6/15/99 due to decreasing vacuum in the main condenser. Despite this effort, condenser vacuum continued to decrease.
Shift inserted a manual scram on 6/15/99 in anticipation of a turbine trip on low condenser vacuum. Shift brought the reactor critical on 6/22/99 and tied the generator to the grid on 6/23/99. The unit attained 2708 CMWT on 6/25/99. Shift reduced load to approximately 845 GMWe on 6/25/99 to perform a rod pattern adjustment. The unit was retumed to 2708 CMWT later the same day. The unit experienced an automatic reactor scram on low r: actor water level on 6/28/99. (see description of event 99-005 for details). Shift brought the reactor critical on 6/29/99. Shift tied the main generator to the grid on 6/30/99 and began ascension to 2708 CMWT. Shift continued ascension to 2708 CMWT with the unit at approximately 40% of rated thermal power at the end of this reporting period.
E2-2