DCL-02-076, June 2002 Monthly Operating Report for Diablo Canyon Power Plant Units 1 and 2

June 2002 Monthly Operating Report for Diablo Canyon Power Plant Units 1 and 2

ML022040008
Person / Time
Site:	Diablo Canyon
Issue date:	07/12/2002
From:	Becker J Pacific Gas & Electric Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
50-275-OL, 50-323-OL, DCL-02-076, GL-97-002
Download: ML022040008 (6)

Text

and Pacific Gas Pacific Gas and Electric Company James R. Becker Diablo Canyon Power Plant Mail Code 104/5/504 Station Director PO. Box 56 Avila Beach, CA 93424 July 12, 2002 805.545.3462 Fax: 805.545.4234 PG&E Letter DCL-02-076 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Docket No. 50-275, OL-DPR-80 Docket No. 50-323, OL-DPR-82 Diablo Canyon Units 1 and 2 Monthly Operating Report for June 2002

Dear Commissioners and Staff:

Attached is the Monthly Operating Report for Diablo Canyon Power Plant, Units 1 and 2, for June 2002. This report is submitted in accordance with Technical Specification 5.6.4 and NRC Generic Letter 97-02.

rIr1l 713/R0232694 Enclosures cclenc: Paul R. Fox, American Nuclear Insurers Robert D. Glynn, Jr.

Barbara Lewis, McGraw Hill Ellis W. Merschoff, NRC Regional Administrator, Region IV David L. Proulx, NRC Senior Resident Inspector Gregory M. Rueger Girija S. Shukla, NRC Project Manager INPO Record Center A member of the STARS (Strategic Teaming and Resource Sharing) Afliance Cattawav

• Comanche Peak

• Diablo Canyon

• Pato Verde

• South Texas Proiect e Wolf Creek

Enclosure 1 PG&E Letter DCL-02-076 JUNE 2002, OPERATION SUMMARIES DIABLO CANYON POWER PLANT UNITS 1 AND 2 Summary of Unit 1 Operation Unit 1 began June in Mode 1 (Power Operation) at approximately 65 percent power, coming out of the eleventh refueling outage. On June 1, 2002, after reaching approximately 70 percent power, operators performed an unplanned power reduction to approximately 27 percent power in response to an electro hydraulic fluid leak on a main steam line high pressure stop valve. On June 3, 2002, while operating at approximately 86 percent power, a failed valve positioner air manifold caused a feedwater regulating valve to close, resulting in an unplanned automatic reactor trip on low-low steam generator water level. On June 5, 2002, after replacing the manifold, operators paralleled the unit to the grid. On June 5, 2002, while at approximately 23 percent reactor power, operators rapidly ramped the unit to approximately 15 percent reactor power and manually tripped the main generator, due to finding oil in the generator. The reactor remained above 8 percent power. Later in the day, after resolving the problem, operators again paralleled the unit to the grid. On June 10, 2002, operators completed ramping the unit to approximately 100 percent power.

Summary of Unit 2 Operation Unit 2 began June in Mode 1 at approximately 100 percent power. On June 18, 2002, operators began ramping the unit to approximately 55 percent power for a planned curtailment to clean circulating water tunnel 2-1 and to search for tube leaks in the condenser. On June 21, 2002, after completing circulating water tunnel cleaning and repairing several condenser tube leaks, the unit was ramped to approximately 100 percent power.

Actuations of Safety or Pressurizer Power Operated Relief Valves There were no challenges to the pressurizer power operated relief valves, pressurizer safety valves, or steam generator safety valves.

Enclosure 2 PG&E Letter DCL-02-076 OPERATING DATA REPORT DOCKET NO.: 50-275 UNIT NAME: Diablo Canyon Unit 1 DATE: 07/01/2002 COMPLETED BY: R. L. Russell TELEPHONE: (805) 545-4327 REPORT MONTH: June 2002

1. Design Electrical Rating (MWe - Net):

• 1,103

2. Maximum Dependable Capacity (MWe - Net): 1,087 This Month YTD Cumulative

3. Number of Hours Reactor Critical: 695.3 3,627.5 131,047.5

4. Number of Hours Generator On-Line: 668.5 3,563.4 129,605.7

5. Unit Reserve Shutdown Hours: 0.0 0.0 0.0

6. Net Electrical Energy Generated (MWH): 687,165 3,812,302 133,970,391 1

Enclosure 2 PG&E Letter DCL-02-076 UNIT SHUTDOWNS DOCKET NO.: 50-275 UNIT NAME: Diablo Canyon Unit 1 DATE: 07/0112002 COMPLETED BY: R. L. Russell TELEPHONE: (805) 545-4327 REPORT MONTH: June 2002 NO. DATE TYPE DURATION (HOURS) REASON' METHOD OF & CORRECTIVE CAUSEACTIONS (YYMMDD)

S(Scdul) SHUTTING DOWN2 COMMENTS 020603 F 35.8 A 3 A valve positioner air manifold failed resulting in a loss of air to the operator of a main feedwater regulating valve. The valve closed causing an automatic reactor trip on low-low steam generator water level. Refer to NRC Event Number 38961, Licensee Event Report 1-2002-004 2 020605 F 15.7 A 1 The unit was rapidly ramped from 23-15%,

then the main generator was tripped. The reactor remained at Mode 1, above 8 % reactor power.

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 from Previous Month E-Operator Training/License Examination 5-Other F- Administrative G-Operational Error (Explain)

H-Other (Explain) 2

Enclosure 2 PG&E Letter DCL-02-076 OPERATING DATA REPORT DOCKET NO.: 50-323 UNIT NAME: Diablo Canyon Unit 2 DATE: 07/01/2002 COMPLETED BY: R. L. Russell TELEPHONE: (805) 545-4327 REPORT MONTH: June 2002

1. Design Electrical Rating (MWe - Net): 1119

2. Maximum Dependable Capacity (MWe - Net): 1087 This Month YTD Cumulative

3. Number of Hours Reactor Critical: 720.0 4,311.1 126,992.9

4. Number of Hours Generator On-Line: 720.0 4,306.0 125,530.0

5. Unit Reserve Shutdown Hours: 0.0 0.0 0.0

6. Net Electrical Energy Generated (MWH): 751,1011 4,589,574 131,995,506 3

Enclosure 2 PG&E Letter DCL-02-076 UNIT SHUTDOWNS DOCKET NO.: 50-323 UNIT NAME: Diablo Canyon Unit 2 DATE: 07101/2002 COMPLETED BY: R. L. Russell TELEPHONE: (805) 545-4327 REPORT MONTH: June 2002 NO. DATE TYPE S(Forced) DURATION (HOURS) REASON1 METHOD OF CAUSE &

CORRECTIVE (YYlMDD) S (Scheduled) SHUTTING ACTIONS DOWN2 COMMENTS N/A There were no shutdowns this month.

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 from Previous Month E-Operator Training/License Examination 5-Other F- Administrative G-Operational Error (Explain)

H-Other (Explain) 4