IR 05000382/1988006

Insp Rept 50-382/88-06 on 880229-0304.No Violations or Deviations Noted.Concern Re Operation of Diesel Generator a Outside of Design Basis Noted.Major Areas Inspected:Diesel Generator Reliability/Operability & Tech Spec Reportability

ML20151M500
Person / Time
Site:	Waterford
Issue date:	04/12/1988
From:	Kelley D, Greg Pick, Seidle W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20151M485	List: IR 05000382/1988006 ML20151M482
References
50-382-88-06, NUDOCS 8804250067
Download: ML20151M500 (9)

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Il APPENDIX U.S. NUCLEAR REGULATORY COMMISSION

REGION IV

NRC Inspection Report: 50-382/88-06 -Operating License: HPF-48 Docket: 50-382 Licensee: Louisiana Power & Light Company (LP&L)

317 Baronne Street

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New Orleans, Louisiana 70160 Facility Name: Waterford 3 Steam Electric Station (W3 SES)

Inspection At: Taft, Louisianna Inspection Conducted: February 29 through March 4, 1988 Inspectors: I_ m /'n /PB Dat'e /

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DN. Kelley, Reac) tor Jhpeh, Test Programs Section, Division of\Deactor. Safety

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G. A. Pfik,' Feactor Inspector, Operational

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Prograts Stction, Division of Reactor Safety Accompanying Personnel: P. O. Chopra, D. L. Wigginton, and A. Notafrancesco, Nuclear Reactor Regulation Approved: # </h=///

W. C. Seidlq) Chief, Test Programs Section Date Division of Reactor Safety Inspection Summary Inspection Conducted February 29 through March 4, 1988 (Report 50-382/88-06)

Areas Inspected: Nonroutine, announced inspection of diesel generator

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reliability / operability and Technical Specifications reportabilit i, PDR ADOCK 05000382 O DCD

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i Results: Within the two areas inspected, no violations or deviations were identified; however, the inspection team members expressed their concern over LP&L's nonconservatism in regard to "A" diesel generator operation outside of-its design basis, f

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DETAILS Persons Contacted

• G. E. Wuller, Operational Licensing

• H. J. Meisner, Licensing Manager

• S. A. Alleman, Quality Assurance Manager

• P. V. Prasankumar, Assistant Plant Manager, Plant Technical Services

• N. S. Carnes, Nuclear Plant Manager

• R. P. Barkhurst, Vice President, Nuclear

• R. S. Starkey, Operations Superintendent

• D. E. Baker, Event Analysis Manager P. N. Backes, Assistant to Plant Manager, Special Projects C. R. Gains, Staff Assistant R. A. Legere, Plant Engineering, System Engineer

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K. McBee, Instrument and Control L. Laughlin, Licensing M. K. Smith, Electrical Supervisor The NRC inspector also interviewed other selected licensee personne * Denotes those licensee personnel attending the exit intervie . Diesel Generator Reliability / Operability A special Region IV inspection team composed of two Region IV reactor inspectors and three representatives from the Office of Nuclear Reactor ;

Regulation were dispatched to W3 SES on February 29, 1988. The team's

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objective was to assess the reliability of the "A" train diesel generator to perform its design safety function until the scheduled refueling outage in April 198 , Background W3 SES is equipped with two Cooper-Bessemer emergency diesel generators. The diesel generators are lined up in the emergency start mode during reactor power operatio The W3 SES Technical Specifications (TS) require certain periodic tests to be performed to demonstrate operability. Technical Specification 4.8.1.1.2-4(b)

specifies the starting methods for the tests. There are four start signals specified: manual, simulated loss-of-offsite power by itself, simulated loss-of-offsite power in conjunction with an emergency safety feature (ESF) actuation test signal, and an ESF actuation signal by itself. The last three start classifications are emergency starts. In the emergency start mode, all trips are bypassed except engine overspeed and generator high differential fault tri In the manual start mode, several other trips are active. One such trip is turbo charger low lube oil pressure. When-d

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the engine is started, all engine trips are bypassed for 15 second At the end of 15 seconds, in the manual start mode, all the engine trips are activ ,

In June 1987, during two consecutive days when the manual' start mode was used, the "A" diesel engine tripped aTtei the 15-second bypass timed out. The trips were annunciated as low turbo lube oil pressure. Each time it was restarted, the engine ran satisfactoril '

This trip circuit continued to degrade until in October 1987, and thereafter, the engine manual start had to be initiated twice each time a manual start was initiated. Consistently, the turbo charger low lube oil pressure would trip the engine on the first attempt to start. The subsequent start would result in satisfactory operatio b. Inspection I Because of the licensee's misinterpretation of the reporting requirements

, for valid and nonvalid failures, the gradual deterioration from the ,

design basis for the "A" diesel generator was not apparent to the i NRC. When the condition became known to the NRC, the question of l reliability and operability arose. Region IV determined that an immediate team inspection would be required to make these determination ,

The team identified above arrived on site on February 29, 198 Prior to the arrival of the team, the Region IV W3 SES docket file <

was searched for all Licensee Event Reports (LERs) and special l

reports from 1984 to the present. The results of the docket search revealed no new information and did not identify reports of these

diesel generator start problem The team met with the LP&L diesel generator system engineer and several technical support personnel. The team received a detailed briefing from the licensee's technical staff and reviewed in detail the electrical and pneumatic control system diagrams. These documents were Cooper-Bessemer Pneumatic Drawing KSV-36-11 and Control Wiring Diagram 65-553-110, Sheets 1-3 and 1 To verify that the oil pressure was indeed not an issue, the licensee started the "A" diesel generator in the emergency mode. There were three team members at the diesel generator to monitor the turbo charger lube oil pressure and the overall engine start process. Two team members were in the control room to observe the starting process l and monitor the remote instrumentation. The local condition l indication prior to engine start for the turbo charger oil pressure  !

was 3 psig. After engine start, the pressure rose to 7.5 psig (5 psig is minimum). As the engine warmed up, the pressure leveled !

out at 8.0 psig. The team also verified that the low turbo charger '

oil pressure trip and alann did not reset in 15 seconds as designed, i but did reset a short time late ;

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Additional discussion with the system test engineer and review of the I diesel generator outage schedule disclosed that the pneumatic control ,

system on the "A" diesel generator is going to be rebuil The control air system rebuilding and the diesel generator work will be l monitored by the NRC during the April 1988 refueling outag A review of licensee procedures was conducted by the NRC inspectors to determine if a program for identification and correction of adverse plant system and equipment conditions was in plac The procedures included in the review are listed below: i NPD-0005, Revision 1, "Corrective Action," dated October 26, 198 QAP-012, Revision 6 "Corrective Action," dated February 26, 198 UNT-5-002, Revision 7, "Condition Identification," dated July 7, 198 UNT-5-015, Revision 0, "Work Authorization Preparation and Implementation," dated July 20, 198 MD-1-014 Revision 2. "Conduct of Maintenance," dated l December 19, 198 ;

In addition to the above procedures, a series of Potential Reportable Events (PRE) from 1985 to 1988 were examined. The PRES selected were all identified problem occurrences with the emergency diesel <

generators. A list of the PRES examined is contained in Attachment 1 l to this repor I

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c. Findings I (1) Procedural Review

A system of adverse condition identification is in plac The identification system is use !

Provisions for scheduling of corrective maintenance are in l effec Directions for the production of detailed work instruction are provide *

The licensee also included the philosphy of timely correction of adverse condition l

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(2) Potential Reportable Events Associated With A Diesel Engine

The engine trip in the manual start mode is caused by a failure of the pneumatic control system to reset the turbo charger low oil pressure trip prior to the time out 15-second delay of the er'11ne trip *

The failure is probably caused by internal air leakage in the pneumatic control syste *

The low oil pressure tri) is completely bypassed when the diesel generator is in tie emergency start mode (this is the nonnal lineup when the reactor is in Modes 1, 2, 3, or 4).

There have been, from January 1986 to present, 58 emergency starts with one failure. The failure was due to an electrical component failure in the engine governor control syste Note: The "B" emergency diesel generator experienced air leakage problems of a different nature. A mini-outage to repair those air leakage problems was conducted in early February of this year and the problems were satisfactorily correcte Therefore this report does not address the "B" emergency diesel generato d. Conclusions The conclusions drawn by the team were that:

(1) The 'A' diesel generator will satisfactorily perform its safety '

functio (2) The present manual start problem does not pose a significant safety problem that would preclude continued power plant operation to the scheduled refueling outage in April 198 (3) The purpose of the manual start test surveillance requirements of TS 4.8.1.1.2.a is to verify the overall condition (not just the safety function) of EDG 'A'. This testing function has been defeated since June 198 (4) Although LP&L was aware of the spurious lube oil pressure trip problem and the operation of the diesel engine was different than the design basis, no corrective actions were taken to find the root cause and effect necessary repairs in a timely manne (5) The diesel generators at W3 SES have been start tested very I frequently. There.were a total of 104 starts for Diesel Generators "A" and "B" during the year 1987. Many of these l

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starts were performed as Actuation Signal (ESFAS) part of the subgroup Engineered relay Safety functional tes Feature The NRC inspectors believe the operability of these relays can be demonstrated without actually starting the diesel generator The licensee plans to reevaluate their test procedures to see if the operability of the ESFAS relays can be demonstrated without starting the emergency diesel generator ;

3. Technical Specifications Reportability The inspection team reviewed the PRES related to the diesel generators to !

detennine reportability as required by the Technical Specifications. The I NRC inspectors concluded that several of the PRE's should have been 1 reported in accordance with Technical Specification 4.8.1.1.3. This was previously identified in NRC Inspection Report 50-382/87-25 (Unresolved Item 382/8725-05) and will be followed up by the resident inspecto ,

The Region IV reactor inspectors reviewed the below listed PRES to determine whether their disposition was in agreement with the requirements of 10 CFR 50.73. The listing includes the PRE number, whether LP&L has ;

closed the PRE file and in which Plant Operations Review Connittee (PORC)

meeting the PRE was reviewed:

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PRE N Status PORC Meeting N '87-044 Open 87-123

,87-045 Closed 87-104 87-062 Closed 87-104 l

'87-063 Open 87-100 I 87-066 Closed 87-100  ;87-067 Closed 87-153 )87-080 Closed 87-123 l 87-082 Closed 87-153 87-085 Closed 88-001 87-088 Open 88-010

,87-089 Closed 87-146  :

87-090 Closed 88-001 87-091 Closed 87-134

.87-104 Closed 87-149

87-114 Open 88-001

'87-115 Closed 88-010 The disposition by LP&L of the PRES listed above were determined to be in accordance with the requirements of 10 CFR 50.73. Review of the remaining PRES will be completed in later NRC inspections.

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No violations or deviations were identified.

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4. Exit Interview The Region IV reactor inspector sunnarized the inspection scope and findings on March 4, 1988, with the licensee representatives identified in paragroph 1,

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ATTACHMENT'1

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The following Potential Reportable Event (PRE) reports were reviewed that concerned diesel generator problems:

PRE N Report Subject 85-148 - EDG B wouldn't start following maintenance 85-201 LER 85-054 Loss of offsite power 85-208 SR 85-022 EDG A Surveillance Test Failure 86-007 EDG B Tripped 86-020 EDG A Tripped 86-036 SR 86-004 EDG A Tripped 86-105 EDG A Turbo bearing sei:ed during .

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,86-113 EDG A Tripped on overspeed 87-013 EDG B Fuel Injector Leak 87-047 EDG A Test Failure due to air leak l

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1. 87-059 EDG A Trip - Lo Turbo charger lube oil pressure

1. 87-061 EDG A Trip - Lo Turbo charger lube ;

oil pressure  ;

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'87-073 EDG A Spurious Bearing Temperature Trip  ;87-086 EDG B Failed control circuit fuses

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1. 87-106 EDG A Trip - Lo Turbo charger lube ,

oil pressure

1. 8'-113 EDG A Trip - Lo Turbo charger lube oil pressure

1. 88-005 EDG A Trip - Lo Turbo charger lube oil pressure

1. 88-015 EDG A Trip - Lo Turbo charger lube oil pressure

1. 0ccurred on manual diesel engine start J