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#REDIRECT [[HL-5805, Monthly Operating Repts for June 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With ]]
| number = ML20209H130
| issue date = 06/30/1999
| title = Monthly Operating Repts for June 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With
| author name = Rogers S, Sumner H
| author affiliation = SOUTHERN NUCLEAR OPERATING CO.
| addressee name =
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05000321, 05000366
| license number =
| contact person =
| document report number = HL-5805, NUDOCS 9907200139
| title reference date = 07-14-1999
| document type = MONTHLY OPERATING ANALYSIS REPORT, TEXT-SAFETY REPORT
| page count = 7
}}
 
=Text=
{{#Wiki_filter:..    .
        .          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)    Comrnents 99-005 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)  Comments 99-004 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.
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