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MONTHYEARML20149F0031988-02-0101 February 1988 Informs of Intent to Submit Formal Rept Re Vibration Surveillance Program for Tdi Diesel Generators.Actions to Be Taken in Future to Monitor Diesels for Vibration Listed Project stage: Other ML20149G9931988-02-10010 February 1988 Requests for Listed Addl Info to Complete Review of Adequacy of Corrective Actions to Reduce Diesel Vibrations,Per 871215 Exit Interview Project stage: Approval ML20148A1651988-03-10010 March 1988 Discusses Effort to Ensure Dependable Operation of New Tdi Diesel Generators by Undertaking Exhaustive Testing.Tdi Diesel Generators Declared Operable in Preparation for Entering Heatup Cooldown Mode Project stage: Other ML20148E4421988-03-21021 March 1988 Forwards Info on NRC Concerns Re Supports for B2 Tdi Diesel Generator Components & B2 Diesel Exhaust Shroud.Completion of Mods on Piping,Restraints & Support Configuration Prior to Startup from Next Refueling Outage Intnded Project stage: Other ML20151A5171988-03-28028 March 1988 Discusses Util Completion of Work Required for Tdi Diesel Generators in Preparation for Restart,Per Restart Conditions Set Forth at Commissioners 880322 Meeting.Tdi Diesel Generators Declared Operable Per Tech Spec 3.7.1 Project stage: Meeting ML20150F2851988-03-28028 March 1988 Safety Evaluation Supporting Resolution of Tdi Diesel Engine Vibration Problems at Facility Project stage: Approval ML20150F2801988-03-28028 March 1988 Forwards Safety Evaluation Addressing Mods Made to Tdi Diesel Engines to Reduce Vibrations & Acceptability of Resultant Vibration Level.Considers Diesel Vibration Issues Resolved Project stage: Approval 1988-03-10
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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20211H7921999-08-13013 August 1999 Safety Evaluation Supporting Amend 126 to License DPR-54 ML20198G8271997-08-22022 August 1997 Safety Evaluation Supporting Amend 125 to License DPR-54 ML20045B9051993-06-16016 June 1993 Safety Evaluation Re Order Approving Decommissioning Plan & Authorizing Decommissioning of Rsngs,Unit 1,SMUD.Concludes That Reasonable Assurance That Health & Safety of Public Will Not Be Endangered by Decommissioning Option,Provided ML20029B6721991-02-22022 February 1991 Safety Evaluation Supporting Proposed Rev to Emergency Plan & Granting Exemption from 10CFR50-54(q) Requirements ML20059G9621990-09-10010 September 1990 Safety Evaluation Supporting Amend 115 to License DPR-54 ML20247B3611989-07-17017 July 1989 Safety Evaluation Supporting Amend 112 to License DPR-54 ML20245E1161989-06-20020 June 1989 Safety Evaluation Supporting Amend 111 to License DPR-54 ML20245A1991989-06-0909 June 1989 Safety Evaluation Supporting Amend 110 to License DPR-54 ML20248B6321989-06-0505 June 1989 Safety Evaluation Supporting Amend 108 to License DPR-54 ML20248B9361989-06-0505 June 1989 Safety Evaluation Supporting Amend 107 to License DPR-54 ML20248B9621989-06-0505 June 1989 Safety Evaluation Supporting Amend 109 to License DPR-54 ML20247P1761989-05-30030 May 1989 Safety Evaluation Accepting Generic Ltr 83-28,Item 4.5.2 Re on-line Testing of Reactor Trip Sys ML20247K7261989-05-23023 May 1989 Safety Evaluation Supporting Amend 105 to License DPR-54 ML20247M9231989-05-23023 May 1989 Safety Evaluation Supporting Amend 106 to License DPR-54 ML20247K6871989-05-16016 May 1989 Safety Evaluation Supporting Amend 104 to License DPR-54 ML20246F4671989-05-0404 May 1989 Safety Evaluation Re Inservice Testing Program & Requests for Relief Re ASME Class 1,2 & 3 Pumps & Valves.Program Acceptable ML20245F9041989-04-18018 April 1989 Safety Evaluation Supporting Amend 103 to License DPR-54 ML20248E9371989-03-29029 March 1989 Safety Evaluation Supporting Amend 102 to License DPR-54 ML20155D3131988-09-28028 September 1988 Safety Evaluation Supporting Amend 100 to License DPR-54 ML20151L5511988-07-14014 July 1988 Redistributed Safety Evaluation Supporting Amend 99 to License DPR-54 ML20151A2771988-07-13013 July 1988 SER Supporting Util Actions to Prevent Failure of Ammonia Tanks Which May Result in Incapacitation of Control Room & Technical Support Ctr Personnel ML20195C5571988-06-0808 June 1988 SER Supporting Util Responses to Generic Ltr 83-28,Item 2.1 (Part 1) Re Equipment Classification (Reactor Trip Sys Components) ML20195C9311988-06-0808 June 1988 SER Accepting Util Response to Generic Ltr 83-28,Item 2.1 (Part 2) Re Vendor Interface Programs (Reactor Trip Sys) ML20150F2851988-03-28028 March 1988 Safety Evaluation Supporting Resolution of Tdi Diesel Engine Vibration Problems at Facility ML20148J8611988-03-17017 March 1988 Safety Evaluation Supporting Amend 98 to License DPR-54 ML20153B2911988-03-15015 March 1988 Safety Evaluation Supporting Amend 97 to License DPR-54 ML20055E3041988-02-12012 February 1988 Safety Evaluation Supporting Util 871223 & 880111 Proposed Changes to Tech Specs,Including Reducing Lower Limits of Detection for Liquid Radioactive Effluents ML20149L6961988-02-12012 February 1988 Safety Evaluation Supporting Amend 95 to License DPR-54 ML20149L2761988-02-0909 February 1988 Safety Evaluation Supporting Amend 94 to License DPR-54 ML20148C7321988-01-0505 January 1988 Safety Evaluation Supporting Amend 93 to License DPR-54 ML20237B4141987-12-0707 December 1987 Safety Evaluation Supporting Amend 92 to License DPR-54 ML20236X1771987-12-0303 December 1987 Safety Evaluation Supporting Amend 91 to License DPR-54 ML20236X1111987-11-13013 November 1987 Safety Evaluation Supporting Amend 90 to License DPR-54 ML20236Q2461987-11-10010 November 1987 Safety Evaluation Supporting Util & Related Submittals Re Design Mods to Emergency Electrical Distribution Sys (Ref Tdi Diesel Generators) ML20236J2671987-11-0303 November 1987 Safety Evaluation Supporting Amend 89 to License DPR-54 ML20245C7831987-10-27027 October 1987 Safety Evaluation Supporting Amend 88 to License DPR-54 ML20245C7051987-10-27027 October 1987 Safety Evaluation Supporting Amend 87 to License DPR-54 ML20236G8791987-10-23023 October 1987 Safety Evaluation Supporting Amend 86 to License DPR-54 ML20236D1361987-10-23023 October 1987 Safety Evaluation Supporting Util 870826 Request to Use Repair & Replacement Program Contained in ASME Section XI 1983 Edition Including Addenda Through Summer 1983 ML20238D4151987-09-0303 September 1987 Evaluation of Engineering Rept ERPT-E0220 Re Reactor Regulation of Util Approach to Compliance W/Reg Guide 1.75 for New Diesel Generator Installation at Plant.Licensee Approach to Demonstrating Compliance Acceptable ML20238B1771987-08-27027 August 1987 Safety Evaluation Supporting Amend 85 to License DPR-54 ML20236E3731987-07-24024 July 1987 Safety Evaluation Supporting Existing & Proposed Mods to Meteorological Program & W/Planned Improvements,Facility Will Satisfy Min Meteorological Emergency Preparedness Requirements of 10CFR50.47 & 10CFR50,Apps E & F ML20205T3021987-03-31031 March 1987 Safety Evaluation Supporting Amend 84 to License DPR-54 ML20205R7871987-03-26026 March 1987 Safety Evaluation Concluding Util 831104 Response to Generic Ltr 83-28,Item 4.5.2, Reactor Trip Sys Reliability On-Line Testing Permits on-line Functional Testing of Sys,Including Diverse Trip Features of Reactor Trip Breakers ML20205C3951987-03-13013 March 1987 Safety Evaluation Re Fracture Toughness Requirements for Protection Against PTS Events (10CFR50.61).Util 860123 Submittal Re Matl Properties & Fast Neutron Fluence of Reactor Vessel Acceptable ML20206B6561987-03-13013 March 1987 Corrected SER Re Fracture Toughness Requirements for Protection Against PTS Events (10CFR50.61).Util 860123 Submittal Re Matl Properties & Fast Neutron Fluence of Reactor Vessel Acceptable ML20205J0971987-03-11011 March 1987 Safety Evaluation Re Sys Selected for Facility Sys Review & Test Program.Sys Constitutes Adequate Scope for Sys Review & Test Program ML20211P2601987-02-19019 February 1987 Safety Evaluation Accepting Util 860116 Request for Amend to License DPR-54,redefining Fire Area Boundaries Required to Be Operable to Separate safety-related Fire Areas & Reassessing Adequacy of Components in Fire Area Assemblies ML20210D1011987-02-0303 February 1987 Safety Evaluation Supporting Issuance of Amend 83 to License DPR-54 ML20215N6881986-11-0404 November 1986 Safety Evaluation Supporting Util Responses to Generic Ltr 83-28,Item 4.4 Re Improvements in Maint & Test Procedures for B&W Plants 1999-08-13
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20211H7921999-08-13013 August 1999 Safety Evaluation Supporting Amend 126 to License DPR-54 ML20195D1901999-05-0606 May 1999 Annual Rept ML20195H8571998-12-31031 December 1998 1998 Annual Rept for Smud. with ML20155D4801998-10-27027 October 1998 Amend 3 to Rancho Seco DSAR, Representing Updated Licensing Basis for Operation of Permanently Shutdown & Defueled Rancho Seco Nuclear Facility During Permanently Defueled Mode ML20248C4301998-05-0606 May 1998 Annual Rept, Covering Period 970507-980506 ML20249A7831997-12-31031 December 1997 1997 Smud Annual Rept ML20198G8271997-08-22022 August 1997 Safety Evaluation Supporting Amend 125 to License DPR-54 ML20217D3271997-07-30030 July 1997 Update of 1995 Decommissioning Evaluation for Rancho Seco Nuclear Generating Station ML20140A6371997-05-0606 May 1997 Annual Rept, Covering Period 960507-970506 ML20140G4481997-05-0101 May 1997 Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby Diesel Generator Sys.Recommends That Springs Be Inspected on Periodic Basis,Such as During Refueling Outages ML20137W8151997-03-20020 March 1997 Amend 1 to Post Shutdown Decommissioning Activities Rept ML20141J2711996-12-31031 December 1996 Smud 1996 Annual Rept ML20138L1231996-11-13013 November 1996 Smud Rancho Seco Incremental Decommissioning Action Plan, Rev 0,961113 ML20129E7151996-10-14014 October 1996 Defueled SAR for Rancho Seco ML20029D3561994-03-31031 March 1994 Update of 1991 Decommissioning Cost for Rancho Seco Nuclear Generating Station ML20059H6821994-01-17017 January 1994 Revised Rancho Seco Quality Manual ML20058K3841993-12-0909 December 1993 Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby DG Sys,Regarding Potential Problem W/ Subcover Assembled Atop Power Head ML20056E5171993-08-31031 August 1993 Technical Review Rept, Tardy Licensee Actions ML20045B9051993-06-16016 June 1993 Safety Evaluation Re Order Approving Decommissioning Plan & Authorizing Decommissioning of Rsngs,Unit 1,SMUD.Concludes That Reasonable Assurance That Health & Safety of Public Will Not Be Endangered by Decommissioning Option,Provided ML20059K1981993-05-0606 May 1993 Annual Rept, Covering Period from 920501- 930506,consisting of Shutdown Statistics,Narrative Summary of Shutdown Experience & Tabulations of Facility Changes, Tests & Experiments,Per 10CFR50.59(b) ML20034F7031993-02-25025 February 1993 Amend 1 to Enterprise Rept 162 Re Defect on Starting Air Distributor Housing Assembly,As Followup to 930115 Final Rept.Addl Listed Part Numbers Discovered Which Are Higher Level Assemblies of Housing ML20128C9641993-02-0202 February 1993 Informs Commission of Status of Open Issues & Progress of Specified Facilities Toward Decommissioning ML20127H2301993-01-15015 January 1993 Part 21 Rept Re Potential Defeat in Component of Dsrv & Dsr Enterprise Standby DG Sys.Starting Air Distributor Housing Assemblies Installed as Replacement Parts at Listed Sites ML20126B0421992-12-17017 December 1992 Final Part 21 Rept Re Potential Problem W/Steel Cylinder Heads.Initially Reported on 921125.Caused by Inadequate Cast Wall Thickness at 3/4-inch-10 Bolt Hole.Stud at Location Indicated on Encl Sketch Should Be Removed ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl ML20127P5861992-11-23023 November 1992 Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl ML20126E6771992-08-0303 August 1992 Rev 7 to Rancho Seco Quality Manual ML20029A7511991-02-28028 February 1991 Suppl to Special Rept 90-13:on 901224,25,29 & 910113,listed Meteorological Instrumentation Inoperable for More than 7 Days.Work Request Initiated & Instrumentation Channels Declared Operable on 910116 ML20029B6721991-02-22022 February 1991 Safety Evaluation Supporting Proposed Rev to Emergency Plan & Granting Exemption from 10CFR50-54(q) Requirements NL-90-451, Monthly Operating Rept for Oct 1990 for Rancho Seco Nuclear Generating Station1990-10-31031 October 1990 Monthly Operating Rept for Oct 1990 for Rancho Seco Nuclear Generating Station ML17348B5061990-10-0909 October 1990 Part 21 Rept Re Zener Diode VR2 on Power Supply Board 9 1682 00 106 Possibly Being Installed Backwards ML20059G9621990-09-10010 September 1990 Safety Evaluation Supporting Amend 115 to License DPR-54 NL-90-443, Monthly Operating Rept for Aug 1990 for Rancho Seco1990-08-31031 August 1990 Monthly Operating Rept for Aug 1990 for Rancho Seco ML20217A5711990-08-28028 August 1990 Final Engineering Rept,Assessment of Spent Fuel Pool Liner Leakage NL-90-439, Monthly Operating Rept for Jul 1990 for Rancho Seco Nuclear Generating Station1990-07-31031 July 1990 Monthly Operating Rept for Jul 1990 for Rancho Seco Nuclear Generating Station 05000312/LER-1990-002, :on 900614,Step 6.9.3.1 of Liquid Waste Discharge Permit Checked R-15017A as Inoperable & Two Independent Samples Not Performed.Caused by Personnel Error. Caution Will Be Added to Step 6.9.21990-07-20020 July 1990
- on 900614,Step 6.9.3.1 of Liquid Waste Discharge Permit Checked R-15017A as Inoperable & Two Independent Samples Not Performed.Caused by Personnel Error. Caution Will Be Added to Step 6.9.2
ML20055F8591990-07-16016 July 1990 Special Rept 90-11:on 900613,06,25,18,21 & 28,fire Barriers Breached More than 7 Days & Not Made Operable in 14 Days. Corrective Actions:Operability of Fire Detectors Verified on One Side of Breached Barriers NL-90-423, Monthly Operating Rept for June 1990 for Rancho Seco Nuclear Generating Station1990-06-30030 June 1990 Monthly Operating Rept for June 1990 for Rancho Seco Nuclear Generating Station NL-90-355, Monthly Operating Rept for May 1990 for Rancho Seco Nuclear Plant1990-05-31031 May 1990 Monthly Operating Rept for May 1990 for Rancho Seco Nuclear Plant ML20055C6301990-05-21021 May 1990 Special Rept 90-09:on 900424,25,30,31 & 0502,fire Barriers Inoperable for More than 7 Days,Per Tech Spec 3.14.6.2 Requirement.Hourly Fire Watches Established & Penetrations & Doors Returned to Operable Status ML20055C6291990-05-21021 May 1990 Special Rept 90-08:on 900419,fire Pump Batteries Inoperable When Surveillance Procedure SP.206 Not Performed by Due Date.Caused by Test Frequency Incorrectly Changed from Weekly to Monthly.Surveillance Schedule Revised ML20058B6521990-05-0404 May 1990 Rev 0 to ERPT-M0216, Property Loss Study for Rancho Seco Nuclear Generating Station in Long Term Defueled Mode ML20033G6011990-03-30030 March 1990 Rev 1 to Defueled Requalification Training Program for NRC Licensed Operators ML20042E6921990-03-30030 March 1990 Special Rept 90-06:on 900301,06 & 14,listed Fire Barrier Penetrations That Failed Surveillance Test Not Restored to Operable Status within 7 Days as Required by Tech Spec 3.14.6.2.Operability of Fire Detectors Verified ML20033G6031990-03-30030 March 1990 Rev 1 to Defueling Training Programs for NRC License Candidates ML20042E6931990-03-30030 March 1990 Special Rept 90-07:on 900228,high Temp Detector Circuit for Zone 53 Not Restored to Operable Status within 14 Days When Circuit Failed Surveillance Test SP.345 & Would Not Alarm. Fire Watch Established.Detector Found Operable on 900316 NL-90-054, Monthly Operating Rept for Feb 1990 for Rancho Seco Nuclear Generating Station1990-02-28028 February 1990 Monthly Operating Rept for Feb 1990 for Rancho Seco Nuclear Generating Station ML20006F4181990-02-0909 February 1990 Special Repts 90-1,90-2,90-3 & 90-4:on 900110,16,18,19,30 & 31,fire Barriers Breached for More than 7 Days.All Fire Barrier Penetrations & Fire Doors Returned to Operable Status NL-90-035, Monthly Operating Rept for Jan 1990 for Rancho Seco Nuclear Generating Station1990-01-31031 January 1990 Monthly Operating Rept for Jan 1990 for Rancho Seco Nuclear Generating Station ML20006A3611990-01-17017 January 1990 Part 21 Rept 152 Re Potential Defect in Component of Dsr or Dsrv Standby Diesel Generator Sys Supplied to Listed Sites by Cooper Industries.Qualified Replacement Valve in Process of Being Specified.Info Will Be Available by 900215 1999-08-13
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RESOLUTION OF TDI DIESEL ENGINE VIBRATION PROBLEMS RANCHO SECO NUCLEAR GENERATING STATION NECHANICAL ENGINEERING BRANCH DIVISION OF ENGINEERING & SYSTEMS TECHNOLOGY
1.0 INTRODUCTION
During pre-operational testing of two newly installed Transamerican Delaval, Inc. (TDI) emergency diesel engine generators (A2 and B2) at Rancho Seco, excessive vibration effects were observed in both units. These effects were significant in several auxiliary piping systems and components in-cluding the turbocharger and air starting system, the exhaust shroud, the jacket water supply system, the lube oil system and the fuel oil system.
j These systems were also designed and ir. stalled by TDI.
The major effects were characterized by various pipe and support failures, by excessive vibration of the turbochargers and the jacket-water-return-header / exhaust shroud structures, and by high pressure pulses in the lube oil systems. Aftr.r 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> of testing operation, SMUD evaluated the test results and concluded that the vibration levels were unacceptable. TDI was contracted to resolve the turbocharger vibration problems, and a third party consultant Duke Engineering and Services, Inc., (DES), was centracted to resolve the general 1
vibration problems with the piping systems. Anotherconsultant(Engineering i
Dynamics, Inc.) was also contracted to assist with the resolution of vibration t
1 problems in the lube oil systems and the return lines of the jacket water supply systems.
2.0 EVALUATION The root causes of the vibration problems were determined to be the vibration of the engines themselves and the turbochargers.
In addition, the rotary gear pumps in the lube oil systems induced fluid pulsations in this piping, which
$$0 N O K 0 P
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. were amplified by their geometry and the location of the control valves.
The location and the adjustment of these valves were determined to be of critical importance in reducing the magnitude of the vibration.
The combined motion of the engines and the turbochargers induced considerable vibratioa in the jacket water return headers which are attached to the exhaust shrouds; this vibration caused cracking in some of the supports of the return headers and excessive vibration of the shrouds, which were determined to be poorly con-structed and supported. Likewise, turbocharger vibration was attributed to be the cause of broken turbocharger lube oil supply and return lines.
Substantial modifications have been made by TDI and SMUD to reduce this vibration. The vibration of the turbochargers was reduced by installing large strut supports, and other smaller supports. The vibration in the lube oil systems was reduced by modifying the piping geometry, adding pulsation dampers and relocating the control valves.
The vibration of the exhaust shrouds and the jacket water return headors was reduced by stiffening the shrouds and the header supports, or by replacement with flexible pipe segments. Similar measures were taken to reduce the vibra-tion in the piping of other systems.
However, although these modifica-tions were successful for the "A2" engine, the "B2" engine shroud still l
l experienced cracking and internal leaking.
This was attributed to local 1
1 vibration of the shroud plates induced by impact of the exhaust pipes on certain internal shroud diaphragms.
l l
C.
_e
. All piping systems and components on both angines which experienced excessive vibration problems have been reevaluated, modified and retested at 3000 KW.
The "A2" engine was run for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> without any adverse effects, and was found to satisfy the prescribed vibration acceptance criteria.
The "B2" engine has also completed a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test run, but cracks were found on some supports and on the shroud. The licensee perfonned an evaluation of these failures and the function of the shroud, and concluded that the "82" engine could operate without the shroud, by applying insulation to the exhaust pipes.
The supports of the jacket water return header were modified and attached directly to the engine. The "B2" engine was rerun for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> without adverse effects and found to satisfy all vibration criteria.
Several interim reports (Reference 1 and subsequent submittals) were submitted by SMUD to the staff describing the installed modifications, the engineering calculations and a comparison of measured vibration quantities (velocities or displacements) with the corres-ponding acceptance criteria. The licensee demonstrated that the measured vibration levels at the 3000 KW 1evel were within the acceptance criteria envelope.
The staff has reviewed these modifications, the supporting cal-culations and the vibration data, and has found that they are in accordance with current engineering practice and design methodology and are therefore acceptable, j
i The acceptance criteria for vibration testing acceptability were initially specified by DES. These criteria were reviewed by the staff and found to be less conservative than the vibration criteria b'ased on trethods stated intheindustrystandardOM-3,1982(Reference 2)andtherefore,unaccep-i table.
This standard has recently been revised to produce even more i
4
i
. conservativevibrationcriteria(Reference 3). However, the current criteria (based on OM-3, 1982) have been determined by the staff to be acceptable if continuous surveillance and vibration monitoring of the diesel engines and connected syste is performed during future operation of these er.gines.
The tests which ve been performect to demonstrate operability have satisfied this requirement and have therefore been found to be acceptable.
In a letter dated February 1,1988 (Reference 4) the licensee committed to implement a TOI Owners Group maintenance and surveillance program, which includes hourly checks of piping for leaks during diesel engine operation, inspection of various jacket water nozzle welds, measurement of turbocharger and diesel engine vibration during 24-hour surveillance runs and subsequent comparison to baseline data.
These 24-hour surveillance runs will be per-formed at each refueling interval.
The licensee has also stated that a site-wide maintenance program, which monitors the vibrations of major equipment on 90-day intervals and ensures that unanticipated increases in vibration levels are detected in a timely manner, will include the TDI diesel generators. Additionally, the staff requires that during any operation of the diesel engines longer than about 15 minutes, the vibration levels of the piping and components be closely monitored and remain below the established acceptance criteria, and that all piping systems and com-ponents be continuously checked for leaks and cracks.
6
I j
5-The licensee has also committed to perform an evaluation of the entire design
]
of the TDI diesel piping and auxiliary skid arrangement.
This evaluation will be performed after restart and completed prior to the next refueling outage, l
to determine if an alternate design is more advantageous.
In Reference 5, the licensee comitted to use Reference 3 as the basis for the acceptance criteria for this evaluation. The staff finds this proposed long term evaluation accep-table.
l
3.0 CONCLUSION
The staff has evaluated the test data and results at 3000 XW submitted by the licensee and finds that the TDI diesel engine vibration levels are within acceptable limits.
These engines have also successfully completed 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> operation tests without any significant adverse effects.
Based on the fore-going considerations, including the licensee commitments regarding maintenance and surveillance of the TDI diesels and the auxiliary systems and components, the staff finds the test results to be acceptable for plant restart, subject to the staff requirement stated above regarding surveillance and vibration monitoring during all diesel engine operation, provided the 3000 KW 1evel is not exceeded, j
i 4.0 REFEPENCES 1.
Letter AGM/TA 88-080 from B. G. Croley, SMUD, to F. J. Miraglia, Jr.,
NRC, dated March 4, 1988, with attachments, i
C
i 1 t 4
1 i
3 2.
ANSI /ASME DM3-1982, "Requirements for Preoperational and Initial a
l Start-up Vibration Testing of Nuclear Power Plant Piping Systems."
l American Society of Mechanical Engineers, New York, NY.
t i
3.
ANSI /ASME OM3-1986, or latest draft. -
4 4.
Letter GCA 88-032 from C. Andognini, SMUD, to F. J. Miraglia, Jr.,
i NRC, dated February 1,1988.
1 5.
Letter GCA 88-193 from C. Andognini, SMUD, to F. J. Miraglia, Jr.,
t NRC, dated March 21, 1988.
i l
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