ML18018B849

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Forwards Emergency Diesel Generator Equipment & Vols 1-4 of Tdi Diesel Generator Design Review & Quality Revalidation Rept.
ML18018B849
Person / Time
Site: Harris Duke Energy icon.png
Issue date: 12/20/1984
From: CUTTER A B
CAROLINA POWER & LIGHT CO.
To: DENTON H R
Office of Nuclear Reactor Regulation
Shared Package
ML18018B850 List:
References
NLS-84-490, NUDOCS 8501170185
Download: ML18018B849 (791)


Text

REGULATOR INFORMATION DISTRIBUTION S<M (BIDS)AGCESSION NBR:8501170165 DOC+DATE: 84/12/20 NOTARIZED:

NO FACIL:50"400 Shearon Harr is Nuclear Power Plant~Unit 1, Carolina AUTH BYNAME AUTHOR AFFILIATION CUTTER,A,B, Carolina Power 8 Light Co.REC I P~NAME RECIPIENT AFFILIATION DENTONgH~Ri Office of Nuclear Reactor Regulationp Director

SUBJECT:

Forwards"Emergency Diesel Generator Equipment" L Vols 1-4 of"TDI Diesel Generator Design Review L Quality Revalidation Rept'~" DOCKET¹05000400 DISTRIBUTION CODE: B031D COPIES RECEIVED:LTR 5 ENCL J SIZE: ,a+lit'.TITLE: Tr ansamer i ca Del aval i Inc, (TDI)Diesel Gener ator Owners Group NOTES: RECIPIENT ID CODE/NAME NRR LB3 LA INTERNAL: ACRS AEOO CHIRAMAL,M ASLBP GC NRR BERL INGER g C NRR MURPHEYgE NRR SELLERS D NRR SPANOgA NRR TREHANgN OP ONED G FI 04 EXTERNAL;LPDR 03 NSIC 05 COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 l~1 1~NRC PDR 02 REC IPIENT ID CODE/NAME BUCKLEYiB 01 ADM/LFMB ASLAP ELD/HDS1 IE KRIESSEL NRR MICHAELSqT NRR PERS INKO NRR SHAl']g H NRR TOMLINSONg E NRR NRIGHTg R PA RGN2 COPIES LTTR ENCL 1 li TOTAL NUMBER OF COPIES REQUIRED: LTTR 34 ENCL

!q I~1(bl, Jl;l f~(, i s 1 t'I H tl l' Carolina+ower

&Light Company SIC g:p]gg~SERIAL-NLS-84-490 Mr.Harold R.Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NO+1-DOCKET NO.50-400 EMERGENCY DIESEL GENERATORS

Dear Mr.Denton:

The Transamerica DeLaval Inc.(TDI)Owners'roup was formed in late 1983 to address and resolve technical concerns related to the TDI diesel generators.

Carolina Power&Light Company (CP6L)is a participant in thi.s Owners'roup program as a result of procuring and installing TDI diesels for the Shearon Harris Nuclear Power Plant (SHNPP)~The Owners'roup program has addressed the generic engine components in reports submitted directly to the NRC.Plant specific components are discussed in reports provided to the individual utilities.

The plant-specific reports are referred to as Phase II DR/QR Reports.These Phase II reports also address the generic items applicable to each specific plant.Attachment A is a brief report which summarizes the status of the SHNPP diesel generators and the Company's plan for placing the equipment into operation.

The report also discusses the SHNPP resolution of the Owners'roup's Phase I generic equipment issues and discusses the results of the inspections conducted to date.The analysis and evaluation performed during the Owners'roup Phase I program has shown that, with some modifications, the TDI diesel generator units are capable of performing their safety function at their full-load rating.Attachment B is the SHNPP Phase II DR/QR report as prepared by the Owners'roup.

The Company endorses the maintenance and surveillance program recommended by the Owners'roup.

Several preliminary clarifications to the Phase II recommendations are presented in Attachment A.If additional clarifications are required to address updated information for SHNPP, we will submit them in subsequent correspondence.

8501170185 841220 PDR ADOCK 05000400 8 PDR pqg I 411 Fayettevilte Street~P, O.Bex 1551~Raleigh.N.C.27602 t 1 I c I~ll A a 1 v k A E Mr.Harold R.Dentoid The implementation of the Owners'roup's confirmatory Phase II recommendations, as described in Attachment A, will provide further assurance that the diesel generators are capable of reliably performing their intended safety function.Should you have any questions concerning this letter, please contact Mr.Sherwood R.Zimmerman at (919)836-6242.Yours very trul A.B.Cutter-Vice esident Nuclear Engineering

&Licensing ABC/DLD/crs (889SRZ)Attachments CC~Mr.C.A.Barth (NRC)*Mr.C.H.Berlinger (NRC)(8)*Mr~B.C.Buckley (NRC)*Mr.G.F.Maxwell (NRC-SHNPP)*

Mr.J.P.O'Reilly (NRC-RII)*

Mr.Travis Payne (KUDZU)Mr.Daniel F.Read (CHANGE/ELP)

Chapel Hill Public Library*Wake County Public Library*Mr.Wells Eddleman*Mr.John D.Runkle Dr.Richard D.Wilson Mr.G.0.Bright (ASLB)Dr.J.H.Carpenter (ASLB)Mr.J.L.Kelley (ASLB)*Mr.W.W.Laity (PNL)(2)**Denotes Recipients of Attachment B

~"~t 4 7 C 4 1 TDI DIESEL GENERATOR DESIGN REVIEW AND QUALITY REVALIDATION REPORT Prepared For CAROLINA POWER S.LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT By TDI DIESEL GENERATOR OWNERS GROUP g goo Sec~4~go l(7o (8>,.Cpa~HP VOLUME 3

~

How To Use This Re ort Tabs in this report identify the following categories:

Turbo, Intake, Intercooler 8 Exhaust Lube Oil Engine Base&Bearing Caps Crankshaft 8 Bearings Cylinder Block, Liners 8 Water Manifold Air Start 8 Barring Device Connecting rods Pistons Camshaft 8 Valve Train Idler Gear Assembly&Front Gear Case Flywheel Engine Instrumentation

&Wiring Overspeed Trip 8 Governor Engine Shutdown 8 Equipment Jacket Water Cylinder Heads&Valves Fuel Oi 1 Injection Generator Control Panel Assembly Engine 8 Auxiliary Sub-Base&Foundation Bolts These categories have been defined to allow the reader to review a complete diesel generator subsystem in a convenient manner.Within each category tabs identify Shearon Harris specific component numbers.A given component report can be found by: a)If the component number is known-use the alpha-numberic index which identifies the volume number and category in which the compon-ent report is located.b)If only the component name is known-Section 3.2 may be used as a cross-reference to find the volume number where the component report may be found.Some reports address more than one component.

a tab is provided for each component.

However, some components are combined under one report.Slip sheets are provided where required to reference back to the appropriate tab.Some components required more than one report.These are identified by the abbreviation LB-Large Bore and SB-Small Bore on the component number tabs.SH2651 INDEX (continued)

Component Component Number Descri tion F-068 Intercooler MP022/23 Turbocharger Cate or Turbo, Intake Intrclr.8 Exhaust Turbo, Intake, Intrclr.8 Exhaust Volume No.00-420 02-CFR 02-305A 02-305C 02-3050 02-307A 02-307B 02-307D 02-310A 02-310B 02-310C 02-311A Lube Oil Pressure Regulating Valve Turbocharger Thrust Bearing Lubricant System Base and Bearing Caps: Base Assembly Base and Bearing Caps: Main Bearing Studs 8 Nuts Base and Bearing Caps: Main Bearing Caps Lube Oil Fittings: Internal-Headers Lube Oil Fittings: Internal-Tube 8 Fittings Lube Oil Fittings Internal: Supports Cr ankshaf t Crankshaft and Bearings: Main Bearings Crankshaft 8 Bearings: Thrust: Bearing Rings.Crankcase:

Crankcase Assy Lube Oil Turbo, Intake, Intrclr.8 Ex-haust Engine Base 8 Bearing Caps Engine Base 8 Bearing Caps Engine Base&Bearing Caps Lube Oil Lube Oil Lube Oil Crankshaft

&Bearings Crankshaft 8 Bearing Crankshaft

&Bearing Crankshaft

&Bearing SH2651 Rev.1 Entire Page Revised INDEX (continued)

Component Number 02-311D 02" 315A 02"315C 02-315D 02-315E 02-315F 02-315G 02" 316A 02-316B 02-316C 02" 317A 02-317B 02-317C Component Oescri tion Crankcase:

Crankcase Mounting Hardware Cylinder Block Liners 8 Water Manifold: Cylinder Block Cylinder Block Liners&Water Manifold-Cylinder Liner Water Mani fold: Jacket Water Manifold 8 Piping Cylinder Block Liners 8 Water Manifold: Studs Cylinder Block Liners&Water Manifold: Cylinder Head Nuts Cylinder Block Liners 8 Water Manifold: Seals 8 Gaskets Jacket Water Inlet Manifold: Manifold Assembly W/Hardware and Coupling and Gaskets Jacket Water Inlet Manifold: Coupling and Gaskets Jacket Water Inlet Manifold: Vent line to Discharge Manifold Jacket Water Discharge Manifold/Piping Jacket Water Discharge Manifold: Couplings and Seals Water Discharge Manifold: Supports Cate or Crankshaft 8 Bearings Cyl.Block&Liners 8 Water Mani fold Cyl.Block 8 Liners 8 Water Mani fold Cyl.Block 8 Liners&Water Manifold Cyl.Block 8 Liners 8 Water Manifold Cyl.Block 8 Liner 8 Water Manifold Cyl.Block 8 Liners 8 Water Manifold Jacket Water Jacket Water Jacket Water Jacket Water Jacket Water Jacket Water Volume No.SH2651 Rev.1 Entire Page Revised

INOEX (continued)

Component Number 02-330A 02-330B 02-335B 02-340A 02-340B Component Descri tion Flywheel Flywheel-Bolting Front Gear Case: Gaskets and Bolting Connecting Rods: Connecting Rods 8 Bushings Connecting Rods: Bearing Shells Cate or Flywheel Flywheel Idler Gear As-sembly 8 Front Gear Case Connecting Rods Connecting Rods Volume No.02-341A 02-341B 02-341C 02-345A 02-345B 02-345C 02-350A 02-350B 02-350C 02" 355A 02-355B 02-355C Pistons: Pistons Pistons: Rings Piston: Pin Assembly Tappets and Guides: Intake 8 Exhaust Tappet Assembly Tappets and Guides: Fuel Tappet Assembly Tappets and Guides: Fuel Pump Base Assembly Camshaft: Camshaft Assembly Camshaft: Camshaft Bearing Camshaft: Supports, Bolting and Gear Idler Gear Assemble: Crank To Pump Gear Idler Gear Assembly: Idler Gear Assembly Idler Gear Assembly: Bolting and Gaskets Pistons Pistons Pistons Camshaft 8 Valve Train Camshaft 8 Valve Train Camshaft 8 Valve Train Camshaft&Val ve Train Camshaft 8 Valve Train Camshaft 8 Valve Train Idler Gear As-sembly 8 Front Gear Case Idler Gear As-sembly 8 Front Gear Case Idler Gear Assembly&Front Gear Case 3 SH2651 iv Rev.1 Entire Page Revised INOEX (continued)

Component Number 02-359 02-360A 02"360B 02-360C 02-360O 02-362A 02-365A 02-365B 02"365C 02" 3650 02-371A 02-371B 02-375 02"380A 02-3808 Component Oescri tion Air Start Valve Cylinder Head and Valves: Cylinder Head Cylinder Head and Valves: Intake 8 Exhaust Valves Cylinder Head and Valves: Bolting and Gaskets Cylinder Head and Valves: Springs 8 Retainers Cylinder Head Covers-Subcover Assembly Fuel Injection Equipment:

Fuel Injection Pump Fuel Injection Equipment-Fuel Injection Tips Fuel Injection Equipment-Tube Assembly Fuel Injection Equipment:

Supports Fuel Pump Linkage: Linkage Assembly and Bearing Fuel Pump Linkage: Linkage Assembly and Bearing Air Intake Manifold and Piping Exhaust Manifold-Manifold Exhaust Manifold: Gasket and Bolting Cate or Air Start&Barring Oevice Cylinder Heads 8 Valves Cylinder Heads 8 Valves Cylinder Heads&Valves Cylinder Heads&Valves Camshaft 8 Valve Tr ain Fuel Oil In-jection Fuel Oil In-jection Fuel Oil In-jection Fuel Oil In-jection Fuel Oi 1 In-jection Fuel Oil In-jection Turbo, Intake, Intrclr.8 Ex-haust Turbo, Intake, Intrclr.8 Ex-haust Turbo, Intake, Intrclr.8 Ex-haust Volume No.SH2651 Rev.1 Entire Page Revised

INDEX (continued)

Component Number Component Oescri tion Cate or Volume No.02-385B Cylinder Block Covers: Gaskets and Bolting Cyl.Block 8 Liner s 8 Water Manifold 02-386B Crankcase:

Crankcase Gaskets and Mounting Hardware Crankshaft 8 Bearings 02-390A Intake 8 Intermedi ate and Exhaust Rocker Shaft Assembly Camshaft 8 Valve Train 02-390B Intake 8 Intermediate and Exhaust Rocker Shaft Assembly Camshaft 8 Valve Train 02-390C 02-390D 02-390E 02-390F Main and Connector Pushrods Rocker Arms and Pushrods: Pushrods Connector.

Rocker Arms and Pushrods: Bushings Rocker Arms and Pushrods: Misc.Bolts and Drive Studs Camshaft 8 Valve Train Camshaft&Valve Train Camshaft 8 Valve Train Camshaft 8 Valve Train 02-410A Overspeed Trip: Governor Overspeed Trip 8 Governor 02-4108 Overspeed Trip: Governor and Accessory Drive Assembly Overspeed Trip 8 Governor 02-410C 02-4100 Overspeed Trip: Coupling (Flexible 8 Spider)Overspeed Trip Vent Valve Overspeed Trip 8 Governor Overspeed Trip 8 Governor 02-411A Governor Drive: Governor 8 Tachometer Drive Gear and Shaft Overspeed Trip&Governor 02-4118 Governor Drive: Couplings, Pins&Keys Overspeed Trip 8 Governor SH2651 v1 Rev.1 Entire Page Revised INDEX (continued)

Component Number Component Descri tion Cate or Vol ume No.02-413A Governor Linkage Overspeed Trip 8 Governor 02-413B 02-415A 02-415B 02-415C 02"420 02-425A 02-435A 02"435B 02-435C 02-436A Fuel Pump Linkage: Automatic Shutdown Governor Assembly: Woodward Governor Governor Assembly-Booster Servomotor Governor Assembly-Heat Exchangers Lube Oil Pump Jacket Water Pump Jacket Water Fittings: Pipe&Fittings Jacket Water Fittings-Supports Jacket Water Inlet Fittings-Valves Inter cooler Piping Fuel Oil Injection Overspeed Trip&Governor Overspeed Trip 8 Governor Overspeed Trip 8 Governor Lube Oi 1 Jacket Water Jacket Water Jacket Water Jacket Water Turbo, Intake Intercooler

&Exhaust 02-436B Intercooler Piping Coupling, Gaskets, Bolting Turbo, Intake Intercooler

&Exhaust 02-437 02-441A 02-441B 02-441C SH2651 Turbo Water Piping: Pipe 8 Fittings Starting Air Manifold: Piping, Tubing and Fitting Starting Air Manifold: Valves, Filters, and Strainter Starting Air Manifold: Supports vii Jacket Water Air Start 8 Barring Device Air Start 8 Barring Device Air Start&Bar ring Device Rev.1 Entire Page Revised INDEX (continued)

Component Number 02-442A 02"442B 02-445 02"450A 02"450B 02-455A 02-455B 02-455C 02-465A 02-465B 02-465C 02-465D 02-467A 02-467B Component Descri tion Starting Air Distributor:

Distributor Assembly Starting Air Distributor:

Tubing, Fittings, Gaskets Fuel Oil Booster Pump Fuel Oil Header: Piping/Tubing Fuel Oil Header: Fuel Oil Header Supports Fuel Oil Filters 8 Strainers:

Fuel Oil Filters Fuel Oil Filters 8 Strainers:

Strainers Fuel Oil Filters 8 Strainer: Mounting Hardware Lube Oil Lines External: Tubing, Fittings, Couplings Lube Oil Lines-External Supports Lube Oil Lines-Exter nal Val ves Lube Oil System-Lube Oil Keepwarm Strainer Turbocharger:

Lube Oil Fitting-Pipe, Tubing, Fittings 8 Flexible Coupling Turbocharger:

Lube Oil Fittings-Supports Cate or Air Start 8 Barring Device Air Star t 8 Barring Device Fuel Oil In-jection Fuel Oi 1 In-jection Fuel Oil In-jection Fuel Oil In-jection Fuel Oil In-jection Fuel Oil In-jection Lube Oi 1 Lube Oil Lube Oil Lube Oil Lube Oil Lube Oil Volume No.SH2651 v111 Rev.1 Entire Page Revised INDEX (continued)

Component Number 02-475A 02-475B 02-475C 02-500A 02-500F 02-500G 02-500H 02-500J 02-500K 02-500M 02-500N 02"540A 02-540B 02-540C Component Descri tion Turbocharger:

Bracket Air Butterfly Valve Assembly Turbocharger:

Bracket-Bolting&Gaskets Control Panel Assembly: Cabinet/System Control Panel Assembly Accumulator Control Panel Assembly Valves Control Panel Assembly Pressure Switch Control Panel Assembly: Relays Control Panel Assembly: Solenoid Valves Miscellaneous Equipment:

Piping, Tubing, Fittings Control Panel Assembly: Terminal Boards/Switches/

Wiring Lube Oil Sump with Strainer Assembly and Mounting Hardward Lube Oil Sump Tank: Misc.Fittings, Gaskets, Pipe&Bolting Material, Valves Lube Oil Sump Tank: Mount,ing Hardware Cate or Turbo, Intake, Intrclr.&Ex-haust Turbo, Intake, Intrclr.8 Ex-haust Turbo, Intake, Intrclr.&Ex-haust Control Panel Assembly Control Panel Assembly Control Panel Assembly Control Panel Assembly Control Panel Assembly Control Panel Assembly Control Panel Assembly Control Panel Assembly Lube Oi 1 Lube Oi 1 Lube Oil Volume No.SH2651 ix Rev.1 Entire Page Revised INOEN (continued)

Component Number Component Oescri tion Cate or Volume No.02-550 Foundation Bolts: Anchors, Bolts, Misc.Hardware Engine 8 Aux.Sub Base 8 Foundation Bolts 02-630A 02-630B Pyrometer Conduit Assembly: Conduit Pyrometer Conduit Assembly: Conduit Fittings Engine Instru-mentation 8 Wiring Engine Instru-mentation 8 Wiring 02-630C 02"6300 Pyrometer Conduit Assembly: Support Pyrometer Conduit Assembly Thermocouple Engine Instru-mentation 8 Wiring Engine Instu-mentation 8 Wiring 02-650A Generator Generator 02-650B"Generator-Generator Control Generator 02-650C Generator-Shaft 8 Bearing Generator 02-688A" Engine 8 Aux Module Wiring Material-Conduit 8 Fittings;Pyrometer Assembly-Conduit, Fitting, Supports Engine Instru-mentation&Wiring 02-688B 02"688C 02-6880 Engine&Aux.Module Wiring Material: Wiring 8 Terminations Engine 8 Aux.Module Wiring Material: Boxes 8 Terminals Engine Alarm Sensors Temperature and Level Switches Engine Instru-mentation&Wiring Engine Instu-mentation 8 Wiring Engine Instru-mentation&Wiring 02-689 SH2651 Off Engine Alarm Sensors Sensors Level 8 Pressure Switches Engine Instru-mentation&Wiring Rev.1 Entire Page Revised INDEX (continued)

Component Number 02-695A 02-695B 02-695C 02-700A 02-700B 02-700C 02-700E 02-700F 02-717A 02-717B 02-717D 02-717E 02-717F Component Descri tion Engine Shutdown Equipment:

Tubing/Fittings 8 Supports Engine Shutdown Equipment:

Valves, Regulator, Orifices Engine Shutdown Trip Switches Jacket Water Standpipe:

Pipe, Fittings, Gaskets Jacket Water Standpipe:

Valves Jacket Water Standpipe:

Supports Jacket Water Standpipe:

Switches Jacket Water Standpipe:

Misc.Bolting Mat.Auxi 1 i ary Ski d.Aux Sub Base&Oil 8 Water Piping-Jacket Water: Valves Aux Sub Base&Oil 8 Water Piping-Jacket Water: Pipe, Couplings, Fittings, Orifices, Y-Strainers Sub Base 8 Oil 8 Water Piping-Jacket Water: Gaskets 8 Bolting Aux.Sub Base 8 Oil&Water Piping-Jacket Mater Supports Cate or Engine Shut-down 8 Equip-ment Engine Shut-down&Equip-ment Engine Shut-down 8 Equip-ment Jacket Water Jacket Water Jacket Water Jacket Water Jacket Water Engine 8 Auxiliary Sub-Base 8 Founda-tion Bolts Jacket Water Jacket Water Jacket Mater Jacket Water Volume No.SH2651 xi Rev.1 Entire Page Revised INDEX (continued)

Component Component Number Descri tion Cate or Volume No.02-717H 02-717I 02"717J 02-717K 02-717M 02-717P 02-805B Aux Sub Base 8 Oil 8 Water Piping-Lube Oil: Piping 8 Fittings Aux Sub Base 8 Oil 8 Water Piping-Lube Oil: Valves Aux Sub Base 8 Oil 8 Water Piping-Lube Oil: Gaskets&Bolting Aux Sub Base&Oil 8 Mater Piping-Lube Oil: Supports 8 Mounting Hardware Aux Sub Base&Oil&Water Piping-Fuel Oil-Piping&Fittings Aux Sub Base 8 Oil 8 Water Piping-Fuel Oil-Gaskets 8 Bolting'ntake Air Filter Lube Oi 1 Lube Oi 1 Lube Oil Lube Oi 1 Fuel Oil Fuel Oil Turbo, Intake, Intercooler 8 Exhaust 02-805C Intake Air Silencer 02-805D Flex Connections Turbo, Intake, Intercooler

&Exhaust Turbo, Intake, Intercooler

&Exhaust 02-810A 02" 810C 02-810D 02-810E Misc.Equipment-Heater, Jacket Water Heat Exchanger, Jacket Mater Jacket Water Standby Heater Pump Jacket Water: Thermostatic Valve Jacket Water Jacket Water Jacket Water Jacket Water SH2651 X11 Rev.1 Entire Page Revised INDEX (continued)

Component Number 02-820A 02-820B 02-820C 02-820D 02-820E 02-820F 02-820G 02-825A 02-8350 Component Oescri tion Lube Oil Full Pressure Strainer Heat Exchanger, Lube Oil Misc.Equipment-Heater, Lube Oil Sump Tank Lube Oil System-Aux Lube Oil Pump Full Flow Lube Oil Filter Lube Oil Keep Warm Pump Lube Oil Keep Warm Filter Fuel Oil Day Tank Starting Air Tank Cate or Lube Oil Lube Oi 1 Lube Oil Lube Oi 1 Lube Oi 1 Lube Oil Lube Oil Fuel Oil Air Start&Barring Device Vol ume No.SH2651 X111 Rev.1 Entire Page Revised Page 1 of 2 COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 COMPONENT Air Start Valves UTILITY Carolina Power 8 Li ht Com an GROUP PARTS LIST NO.02-359 TASK DESCRIPTION NO.DR-02" 02-359-0 SNPS GPL NO.03-359 CLASSIFICATION TYPE A TASK DESCRIPTIONS Design review for this component is not required based on the following:

A review of the EDG Component Tracking System indicated that there was no significant applicable industry and/or site experience, other than that already addressed in the lead engine report.~A review of the lead engine DR/gR reports (Shoreham and Comanche Peak).~Similarities between Shearon Harris component and the lead engines components.

The following maintenance recommendation from the lead engines DR/gR reports should be implemented:

Remove, inspect and, if necessary, clean the air start valves during every refueling outage.The inspection should include inspection of the piston/cap and guide/housing sliding surfaces to evaluate severity of wear and corrosion present.This recommendation is based on discussions with TDI.~Ensure that the dryer between the compressor after cooler and air receiver is functioning properly by blowing down the air receivers daily and noting any moisture content.Appropriate action should be taken if moisture is noted.The following TDI SIMS should be implemented:

~SIM 329, copper gasket between valve and head~SIM 360, capscrew length and torque requirements

'The following guality inspections should be performed:

~Verify initial and hot torque values for hold down capscrews (Engine lA-SA and 1B-SB).SH2223/1

COMPONENT DESIGN REVIEM CHECKLIST TASK DESCRIPTION (continued)

Page 2 of 2 DR-02-02-359-0 All other equality inspections have been completed and are considered satis-factory.PRIMARY FUNCTION Not required ATTRIBUTE TO BE VERIFIED Not required SPECIFIED STANDARDS Not required REFERENCES Not required DOCUMENTATION RE VIREO Not required GROUP CHAIRPERSON PROGRAM MANAGER SH2223/2 COMPONENT UALITY REVALIDATION CHECKLIST Page 1 of 4 02-02-359 COMPONENT Air.Start Valve GPL NO.02-359 SNPS GPL NO.03-359 Carolina Power 8 Light Shearon Harris Nuclear UTILITY Power Plant-Unit 1 REV.NO.2 TASK DESCRIPTIONS 2.3.Assemble and review existing documentation including 10CFR21 response.Perform a visual inspection to verify that adequate seating exists between the valve and valve ring.Perform a visual inspection to verify that no carbon deposits exist on the valve internals.

4.Verify the intial and hot torque values for the hold down capscrews (two per bank).,5., Perform a dimensional check of the hold down capscrews.

6.Perform a material comparator test on the hold down capscrews.

Same as Engine 1A-SAATTRIBUTES TO BE VERIFIED En ine 1A-SA l.guality status of Component Document Package 2.Proper seating of valve to valve ring SH1726/1 COMPONENT UALITY REVALIDATION CHECKLIST Page 2 of 4 02"02-359 ATTRIBUTES TO BE VERIFIED (continued)

En ine lA-SA 3.Lack of carbon deposits on the valve internals 4.Proper torqu'e values 5.Length of capscrews 6.Material of capscrews Same as Engine 1A-SA ACCEPTANCE CRITERIA 1.Satisfactory Document Package 2.A continuous metallic appearing ring exists on the valve ring contact surface.3.No carbon deposits exist on the valve internals.

4.Torque values are in accordance with the TDI Instruction Manual.5-6.Review of inspection report by Design Group Same as Engine lA-SA REFERENCES l.(CI No.52 2-6.Approved Site NDE Procedures, TDI Instruction Manual'Same as Engine 1A-SA SH1726/2

COMPONENT UALITY REVALIDATION CHECKLIST Page 3 of 4 02-02"359 DOCUMENTATION RE UIRED 1.Document Summary Sheet 2-6.Inspection Report En ine 1B-SB Same as Engine-SA GROUP CHAIRPERSON PROGRAM MANAGER COMPONENT REVIEW 1.No EDGCTS site experience documents are in evidence.2.A visual inspection was performed on the valve seat area for cylinder heads 1L and 8R.The valve seat area on cylinder head R8 exhibited some minor pitting while no defects were in evidence on the valve seat area for cylinder head 1L.This was reported by TER¹02-016.3.A visual inspection was performed on the valve internals for the air start valves on cylinder heads 8R and 1L with satisfactory results.This was reported by TER¹02-016.4.No inspection report has been received which fulfills this requirement.

5.A dimensional check was performed on twenty hold down capscrews.

This was reported by TER¹02-016.6.A material comparator test was performed on all hold down capscrews with no known sample used.Comparator reading results were reported by TER¹02-016.A subsequent material comparator test was performed on the hold down capscrews for cylinders 3R, 6R, 3L, and 6L using a known sample.Satisfactory results were reported by TER¹02-093.En ine 1B-SB1.All EDGCTS site experience documents were assembled and reviewed with unsatisfactory results.NCR No.84-1634 remains open.2.A vi sual inspection was performed on the val ve seat area for cyl inder heads 8L and 5R with sati s factory resul ts.Thi s was reported by TER¹02-079.SH1726/3

COMPONENT UALITY REVALIDATION CHECKLIST Page 4 of 4 02-02-359 COMPONENT REVIEW (continued) 3..A visual inspection was performed on the valve internals for the air start valves on cylinder heads 8L and 5R with satisfactory results.This was reported by TER¹02-079.4.No inspection report has been received which fulfills this requirement.

5.A dimensional check was performed on twenty hold down capscrews with satisfactory results.This was reported by TERS02-079.6.A material comparator test was performed on all hold down capscrews with no known sample used.Comparator reading results were reported by TER¹02-079.RESULTS AND CONCLUSION En ine 1A-SA The guality Revalidation effort with respect to this component, as out-lined above, is complete.The results have been forwarded to the Design Review Group for their evaluation and conclusions in support of the final report.Same as Engine 1A-SA GROUP CHAIRPERSON

<c (c>PROGRAM MANAGERSH1726/4

COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER STATION-UNIT 1 Page 1 of 2 Starting Air Manifold Piping, Tubing, 8 Fittings COMPONENT Lar e Bore Sco e Onl GROUP PARTS LIST NO.02-441A SNPS GPL NO.03-441A UTILITY Carolina Power 8 Li ht Com an TASK DESCRIPTION NO.DR-02-02-441A-0 CLASSIFICATION TYPE TASK DESCRIPTIONS Design review for this component is not required based on the following:

~A review of the EDG Component Tracking System indicated that there was no significant applicable industry or site experience.

~A review of the lead engine DR/gR reports (Shoreham/Comanche Peak).The support modifications (see 02-441C)listed in the below referenced letter are incorporated.

There were no modification or maintenance recommendations made on the lead engine DR/gR report.guality Revalidation is not required for this component.

PRIMARY FUNCTION Not required ATTRIBUTE TO BE VERIFIED Not required SPECIFIED STANDARDS Not required SH2446/1 REFERENCES COMPONENT DESIGN REVIEW CHECKLIST Page 2 of 2 DR-02-02"441A"0 Letter from R.Markovich/G.

Shears (Impell)to J.Kammeyer (SMEC),"Recommended Design of Piping Components 02-441A and 02-441C for Shearon Harris", dated 10/24/84.DOCUMENTATION RE UIRED Not reqUired GROUP CHAIRPERSON PROGRAM MANAGER~C X(~-SH2446/2

COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Page 1 of 2 Starting Air Manifold: Piping, Tubing and Fittings COMPONENT Small Bore Sco e Onl UTILITY Carolina Power 8 Li ht Co.GROUP PARTS LIST NO.02-441A SNPS GPL NO.03-441A TASK DESCRIPTION NO.DR-02-02-441A-0 CLASSIFICATION TYPE A TASK DESCRIPTIONS A design review is not required for this component based on a review of applicable industry and site experience, the lead engine DR/gR report (Comanche Peak)and a field walkdown.The review of the applicable industry and site experience indicates that no generic or significant problems exist which affect the integrity of this component.

A field walkdown was performed at Shearon Harris.However, a portion of tubing at each cylinder head was not installed at the time of the walkdown.Therefore, component acceptability and any subsequent recommendations shall be based upon the lead engine reports.The uninstalled portion of tubing is considered essentially the same based on comparison between Comanche Peak, Grand Gulf and Catawba.The lead reports for this component contain no maintenance recommendations.

The lead reports for this component contain no modification recommendations concerning the uninstalled portion of tubing.Therefore, by comparison this portion of tubing is considered acceptable.

However, the lead engine reports do address support additions/modifications which concern-the installed portions of the tubing.Similar additions/modifications for Shearon-Harris are now included in DR/gR report 02-441C.The field walkdown indicates that this component will maintain its functional capability for all normal and earthquake loadings provided the supports are modified as indicated in DR/gR report 02-441C.guality Revalidation for this component is not deemed necessary.

SH2232/1

PRIMARY FUNCTION Not required COMPONENT DESIGN REVIEW CHECKLIST Page 2 of 2 DR-02-02-441A" 0 ATTRIBUTE TO BE VERIFIED Not required SPECIFIED'STANDARDS Not required REFERENCES Not required DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGER C-SH2232/2 COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Page 1 of 2 Starting Air Manifold: COMPONENT Valves Strainers 8 Filters UTILITY Carolina Power 8 Li ht Co.GROUP PARTS LIST NO.02"441B TASK DESCRIPTION NO.DR-02" 02-441B" 0 SNPS GPL NO.03-441B CLASSIFICATION TYPE A TASK DESCRIPTIONS Design review for this component is not required based on the following:

~A review of the EDG Component Tracking System indicated that there was no significant applicable industry and/or site experience, other than those previously addressed in the lead engine report.A review of the lead engine DR/gR reports (Shoreham and Comanche Peak)The components used at Shearon Harris have been used on the lead engines with the exception of two solenoid valves, which are similar to lead engine valves, but which have a manual override.In addition, review of TDI Instruction Manual Volume II, Group Parts List for 02-441 indicates Shearon Harris engines have a starting air manifold purge line from intake manifold (TDI SIM 323)installed.

The following maintenance from the applicable lead engine reports should be implemented at Shearon Harris:~At each refueling outage: The starting air admission valve has an 0-ring and a screened fit-ting, susceptible to wear and fouling.The 0-ring should be replaced and the screened fitting cleaned.The starting air valves should be disassembled, cleaned, inspected, lubricated, and reassembled to prevent fouling.They will be tested to assure leak tightness.

Inspect for tightness of fittings and bolts and apply locking com-pound, as.required, during reassembly of component.

SH2218/1 COMPONENT DESIGN REVIEM CHECKLIST TASK DESCRIPTION (continued)

Page 2 of 2 DR-02-02-441B-0 The shuttle valve has an 0-ring susceptible to wear.The 0-ring will be replaced.~In addition, the filter element should be inspected and clean/replaced, on a monthly basis.~In accordance with the manufacturer's recommendation, the filter should be changed before the maximum pressure drop of 25 psi.The strainer is recommended to be blown down daily and cleaned and inspected monthly.If-the strainer-is excessively dirty, the frequency of cleaning and inspect-ing should be increased.

The following modification should be made~In accordance with TDI recommendation, free flowing drains should be added to the air distributor filter.This is a design improvement which will help maintain a cleaner supply of starting air.guality Revalidation is not required for this component.

PRIMARY FUNCTION Not required ATTRIBUTE TO BE VERIFIED Not required SPECIFIED STANDARDS Not required REFERENCES Not required DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGER SH2218/2

  • .<

COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Page 1 of 2 Starting Air Mani fold Supports COMPONENT Lar e Bore Sco e Onl GROUP PARTS LIST NO.02-441C SNPS GPL NO.03-441C UTILITY Carolina Power&Li ht Com an TASK DESCRIPTION NO.DR-02-02-441C" 0 CLASSIFICATION TYPE TASK DESCRIPTIONS Design review for this component is not required based on the following:

~A review of the EDG Component Tracking System indicated that there was no significant applicable industry or site experience.

~A review of the lead engine DR/gR reports (Shoreham/Comanche Peak).~The items listed in the below referenced letter are incorporated.

The following modification recommendations made on the lead engine DR/gR report should be implemented:

The two U-bolt supports adjacent to the strainers require stiffening of their support members in the later'al direction.

The 10 support members on the two headers running parallel to the length of the engine require reinforcement of support members and bolt hole elongations in the east-west direction.

The support located on the riser north of the valves (left bank)and the support located on the riser south of the valves (right'ank) require reinforcement of support members and bolt hole elongations in the north-south direction.

~The support located on the riser south of the valves (left bank)and the support located on the riser north of the valves (right bank)require reinforcement of support members.There are no maintenance recommendations for this'component.

guality Revalidation is not required for this component.

SH2445/1 PRIMARY FUNCTION Not required COMPONENT DESIGN REVIEW CHECKLIST Page 2 of 2 DR-02-02-441C-0 ATTRIBUTE TO BE VERIFIED Not required SPECIFIED STANDARDS Not required REFERENCES Letter from R.Markovich/G.

Shears (Impell)to J.Kammeyer (SWEC),"Recommended Design of Piping Components 02-441A and 02-441C for Shearon Harris", dated 10/24/84.DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGERSH2445/2 TDI OWNERS GROUP for SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 STARTING AIR MANIFOLD" SUPPORTS SMALL BORE SCOPE ONLY COMPONENT PART NO.02"441C I INTRODUCTION The TDI Emergency Diesel Generator Owners Group Program for the Shearon Harris Nuclear Power Plant requires Design and equality Revalidation reviews of the structural adequacy of the star ting air manifold tubing supports to withstand the effects of normal operating and earthquake loadings.The primary function of these supports is to provide adequate restraint of the starting air manifold tubing components.

I I OBJECTIVE The objective of this review was to perform an engineering evaluation of the tubing supports to assure that the component will perform its intended design function during normal operating and earthquake loadings.III METHODOLOGY In order to meet the stated objective, the following methods were used:~The TDI Emergency Diesel Generator Component Tracking System was reviewed for the Shearon Harris site, nuclear, and non-nuclear industry experience.

See Appendix C for results.~The equality Revalidation Checklist results were reviewed for acceptability.

~Comparison with the lead engine reports (Comanche Peak, Grand Gulf, Catawba).Refer to the review procedures as described in Reference 1 for a detailed methodology of this evaluation.

IV RESULTS AND CONCLUSIONS The tubing supports, as defined by this Component Design Review, have been evaluated in accordance with Reference 1 and have been found acceptable with modifications.

The conclusions of this report are based on the com-SH2369/1

Page 2 of 2 bination of a field walkdown and a review of the lead engine reports since portions of this component were not installed at the time of the walkdown.There are no TERs associated with this component.

The guality Revalidation Inspection results identified in Appendix B have been reviewed and considered in the performance of this design review, and the results are consistent with the final conclusions of this report.Based on the above review, it is concluded from References 1 and 2 that the tubing supports will perform their intended design function at Shearon Harris under all normal operating and earthquake loadings if the following recommended modifications are implemented as detailed in Reference 3: Existin Su ort Chan es-En ine lA The existing two-direction lateral support on the air supply to distribu-tor tubing located adjacent to the r ight bank filter requires replacement since it does not provide sufficient structural capacity to withstand the loadings.Su ort Additions-En ine 1B In order to support the piping/tubing of Component 02-441A, it is recom-mended that a two-direction lateral restraint should be added on the distributor air supply tubing on the right bank lines between the header, filter and distributor to reduce the unsupported span length and filter nozzle loadings and also to maintain consistency with Engine lA.V REFERENCES l."Engineering Review Criteria Document for the Design Review of TDI Diesel Small Bore Piping, Tubing, and Supports for the TDI Owners'roup," Report No.11600.60-DC-02, Revision 0.2.Stone&Webster Calculation number 11600.60-NP(B)-0201-XH.

3.Memo No.6451 from C.Malovrh/SWEC to J.Kammeyer/SWEC dated 10/29/84.SH2369/2 APPENDIX A COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Page Al of 2 Starting Air Manifold Tubing Supports COMPONENT Small Bore Sco e Onl GROUP PARTS LIST NO.02"441C SNPS GPL NO.03-441C UTILITY Carolina Power 8 Li ht TASK DESCRIPTION NO.DR-02" 02-441C-0 CLASSIFICATION TYPE A TASK DESCRIPTIONS Pe~form an engineering review of the tubing supports to provide additional assurances that the component will perform its intended design function during normal operating and earthquake loading.PRIMARY FUNCTION Provide adequate restraint to the starting air manifold tubing components.

ATTRIBUTES TO BE VERIFIED Structural adequacy of the tubing supports due to the effects of normal operating and earthquake loadings.SPECIFIED STANDARDS IEEE 387 REFERENCES"Engineering Review Criteria Document for the Design Review of TDI Diesel Small Bore Piping, Tubing, and Supports for the TDI Owners'roup" Report No.11600.60-DC-02, Revision 0.SH2253/1 COMPONENT DESIGN REVIEW CHECKLIST DOCUMENTATION RE UIRED Page A2 of 2 DR-02-02" 441C-0 Delaval design documentation (specifications, calculations, drawings, etc.).In lieu of information from Delaval, the following information is required: verified support sketches and piping isometrics, material specifications, pipe size and schedule, and operating parameters (pressure, temperature, load combinations).

GROUP CHAIRPERSON PROGRAM MANAGER SH2253/2 A endix B COMPONENT UALITY REVALIDATION CHECKLIST Page Bl of 3 02-02-441C Starting Air Manifold-COMPONENT Su orts GPL NO.02-441C SNPS GPL NO~03-441C Carolina Power 8 Light Shearon Harris Nuclear UTILITY Power Plant-Unit 1 REV.NO.1 TASK DESCRIPTIONS 1.Assemble and review existing documentation.

2.Obtain sufficient data to support the design review effort.This may be accomplished by developing quality verified as-builts in accor-dance with Procedure DG-7, or by the Design Group performing a field walkdown.En ine 1B-SB Same as Engine lA-SA ATTRIBUTES TO BE VERIFIED En ine lA-SA 1.guality status of Component Document Package 2.Information necessary for the design review effort Same as Engine lA-SA SH1763/1 ACCEPTANCE CRITERIA En ine 1A-SA COMPONENT UALITY REVALIDATION CHECKLIST Page B2 of 3 02-02"441C 1.Satisfactory Document Package 2.Review of detailed information by the Design Group En ine 1B-SB Same as Engine 1A-SA 4 REFERENCES 1.gCI N0.52 2.Procedure DG-7 Same as Engine 1A-SA DOCUMENTATION RE UIRED 1.Document Summary Sheet 2.equality verified as-built isometric drawings for the supports if available from the Owner.En ine 1B-SB Same as Engine 1A-SA GROUP CHAIRPERSON PROGRAM MANAGER QC.Hc~"" i'-~SH1763/2

COMPONENT REVIEW COMPONENT UALITY REVALIDATION CHECKLIST Page 83 of 3 02-02-441C 1.No EDGCTS site experience documents are in evidence.2.The Design Group will be responsible for closing out the as-built drawings as per Procedure DG-7.The as-built drawings will be guality verified by the appropriate site guality organization.

The performance of an engineering walkdown by the Design Group, precludes the issuance of a quality verified as-built drawing or sketch.En ine 18-SB Same as Engine 1A-SA RESULTS AND CONCLUSION The guality Revalidation effort with respect to this component, as out-lined above, is complete.The results have been forwarded to the Design Review Group for their evaluation and conclusions in support of the final report.En ine 18-SB Same as Engine lA-SA GROUP CHAIRPERSON PROGRAM MANAGER DC l(c~~'~~c.i SH1763/3

~Aendix C Page Cl of 1 EDG COMPONENT TRACKING SYSTEM: SHEARON HARRIS SITE NUCLEAR AND NON"NUCLEAR INDUSTRY EXPERIENCE

SUMMARY

COMPONENT NO.02-441C Effective Printout Date Shearon Harn s: 10/15/84 Industry: 09/17/84 COMPONENT TYPE: Startin Air Manifold-Tubin Su orts EXPERIENCE SHEARON HARRIS None NUCLEAR None NON-NUCLEAR None REFERENCE DOCUMENTS SHEARON HARRIS STATUS SH2369/3 COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER, PLANT" UNIT 1 Page 1 of 2 Starting Air Distributor:

COMPONENT Distributor Assembl GROUP PARTS LIST NO.02"442A SNPS GPL NO.03"442A UTILITY Carolina Power 8 Li ht Com an TASK DESCRIPTION NO.DR-02-02-442A-0 CLASSIFICATION TYPE A TASK DESCRIPTIONS Design review is not required for this component, based on the Comanche Peak lead engine DR/gR report which establishes the acceptability of the distributor assembly.The parts under review are the same as those of the lead engine, with the exception of the timing shaft.The timing shaft assembly at Shearon Harris utilizes an adjustable cam arrangement, per TDI Service Information Memo (SIM)No.311.A review of the Component Tracking System indicates no significant applicable

~~~~~~~~~~~~~~~~~~industry or site experience.

In addition to the normal maintenance tasks of water removal and filter re-placement for the starting air system, the following maintenance recommendation from the lead engine DR/gR report should be implemented:

~Maintain surveillance inspections to assure that the starting air manifold vent remains open and effective.

~Perform an inspection of the poppet valves and cams on all engines during refueling outages, to assess the degree of wear.There are no modifications recommendations for this component.

The following guality inspections are recommended to be performed on engines lA and 1B.~Verify the proper timing of the air start distributor as described in the TDI Manual.~After verifying the correct timing of each starting air distributor, as described in the TDI Manual, the evaluation of wear on the cam and valve contacts should be performed as follows: 1.Remove the distributor from the engine 2.Visually inspect the wear marks on the cam lobes.SH2092/1 Note the position and orientation of the lube oil jet.Oil flow from the jet should cover the wear mark region on the cam lobe.

5~

COMPONENT DESIGN REVIEW CHECKLIST TASK DESCRIPTIONS (continued)

Page 2 of 2 DR"02-02-442A-0 3.Visually inspect the wear marks on the end of each valve spool where it slides on the cam.Measure the average diameter of the"flat" worn area on the end of each spool to the nearest 1/64-inch.

If the largest of these measurements is more than 1.5 times the smallest, an engineering evaluation of the observed wear should be performed and a superficial hardness measurement should be made on the end"wear flat" of each valve spool.If the hardness of any spool end is significantly below 30 Rc, it should replaced.-Verify-the installation of the follower lobe on the camshaft (one engine only)PRIMARY FUNCTION Not required ATTRIBUTE TO BE VERIFIED Not required SPECIFIED STANDARDS Not required REFERENCES Not required DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGER C.SH2092/2 COMPONENT UALITY REVALIDATION CHECKLIST Page 1 of 3 02-02"442A Starting Air Distributor-COMPONENT Distributor Assembl Carolina Power 8 Light Shearon Harris Nuclear UTILITY Power Plant-Unit 1 GPL NO.02-442A REV.NO.1 SNPS GPL NO.03"442A TASK DESCRIPTIONS 1.Assemble and review existing documentation 2.Verify the proper timing of the air start distributor as described in the TDI Manual.3~After verifying the correct timing of each starting air distributor, as described in the TDI Manual, the evaluation of wear on the cam and valve contacts should be performed as follows: a.Remove the distributor from the engine b.Visually inspect the wear marks on the cam lobes.Note the position and orientation of the lube oil jet.Oil flow from the jet should cover the wear mark region on the cam lobe.C.Visually inspect the wear marks on the end of each valve spool where it slides on the cam.Measure the average diameter of the"flat" worn area on the end of each spool to the nearest 1/64-inch.

If the largest of these measurements is more than 1.5 times the smallest, an engineering evaluation of the observed wear should be performed and a superficial hardness measurement should be made on the end"wear flat" of each valve spool.If the hardness of any spool end is significantly below 30 Rc, it should be replaced.4.Verify the installation of the follower lobe on the camshaft (one engine only)Same as Engine lA-SA SH1918/1 A1 ATTRIBUTES TO BE VERIFIED En ine 1A-SA l.guality status of Component Document Package 2, Timing of the air start distributor.

Page 2 of 3 02-02-442A 3.Proper lubrication of poppets by lack of scoring or wear on poppet surface.4..--Proper installation of the follower lobe on the camshaft.En ine 1B-SB Same as Engine 1A-SA ACCEPTANCE CRITERIA En ine 1A-SA 1.Satisfactory Document Package 2.Timing in accordance with TDI Manual.3-4.Review of inspection report by Design Group.Same as Engine 1A-SA REFERENCES 1.gCI No.52 2.Approved Site NDE Procedures, TDI Instruction Manual, TER¹99-020 3.Approved Site NDE Procedures, TDI Instruction Manual, TER¹99-020 4.Approved Site NDE Procedure, TDI Instruction Manual Same as Engine 1A-SA SH1918/2 DOCUMENTATION RE UIRED Page 3 of 3 02-02-442A 1.Document Summary Sheet 2-4.Inspection Report Same as Engine 1A-SA GROUP CHAIRPERSON rW'l.'ROGRAM MANAGER.C.X4.COMPONENT REVIEW En ine 1A-SA En ine 18-SB RESULTS AND CONCLUSION En ine 18-SB GROUP CHAIRPERSON PROGRAM MANAGER SH1918/3 COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Page 1 of 1 Starting Air Distributor:

COMPONENT Tubin Fittin s.Gaskets GROUP PARTS LIST NO.02-442B SNPS GPL NO.03-442B UTILITY Carolina Power 8 Li ht Com an TASK DESCRIPTION NO.DR-02-02" 442B" 0 CLASSIFICATION TYPE A TASK DESCRIPTIONS The tubing, fittings, and gaskets for this component are considered under Component Nos.02-441A/C and 02-307B.PRIMARY FUNCTION Not required ATTRIBUTE TO BE VERIFIED Not required SPECIFIED STANDARDS Not required REFERENCES Not required DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON ROGRAM MANAGER~SH2212/1

COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Page 1 of 2 COMPONENT Startin Air Tank GROUP PARTS LIST NO.02-835D SNPS GPL NO.02-835D UTILITY Carolina Power&Li ht Com an TASK DESCRIPTION NO.DR-02-02-8350" 0 CLASSIFICATION TYPE A TASK DESCRIPTIONS Design review of this component for Shearon Harris is not required based on the following:

~A review of the lead engine DR/gR reports (Shoreham/Comanche Peak).~A review of the EDG Component Tracking System indicated no significant applicable industry and/or site experience.

A detailed dynamic analysis was performed to seismically qualify the skid (Ref.2).The tank is similar in configuration to the Grand Gulf tank but is qualified to ASME III (instead of ASME VIII).Special maintenance requirements identified in the lead engine design reviews (Comanche Peak and Shoreham), do not have to be implemented at Shearon Harris.The Shearon Harris air start tank is an ASME III tank for which a corrosion allowance was required.Air drying equipment is used, thus no special checks for moisture content need to be made for the starting air tank.Note, however, that the requirement for daily checks for moisture at the drain valve or float trap is required to ensure proper operation of other components such as the float trap or air start distributor.

guality Revalidation is not required for this component.

PRIMARY FUNCTION Not required ATTRIBUTE TO BE VERIFIED SH2555/1

SPECIFIED STANDARDS Not required COMPONENT DESIGN REVIEW CHECKLIST Page 2 of 2 DR"02-02-835D"0 REFERENCES l.Ebasco Specification 8 216-73-Tb, Rev.3, 4-25-78,"Diesel Engine Generator Unit and Control Panel for Carolina Power 8 Light Company,.-Shearon Harris Nuclear Power Plant Units 1, 2, 3, and 4, Wake County, North Carolina.2.Final Report Volume II, Analytic Modeling of Engine Auxiliaries Seismic gualification of TDI Diesel Generator Sets, Serial Numbers 74046/53 for Carolina Power 8 Light Company, Shearon Harris Nuclear Power Plant Units 1, 2, 3, and 4,Section I, Starting Air Receiver.DOCUMENTATION RE UI RED Not required GROUP CHAIRPERSON PROGRAM MANAGER~C XC SH2555/2 COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Page 1 of 2 Connecting Rods: COMPONENT Rods and Bushin s UTILITY Carolina Power&Li ht Com an GROUP PARTS LIST NO.02-340A TASK DESCRIPTION NO.DR-02-02-340A-2 SNPS GPL NO.03-340A CLASSIFICATION TYPE TASK DESCRIPTIONS Design review for this component is not required based on the following;

~A review of the EDG Component Tracking System indicated that there was no site experience and, no significant applicable nuclear or non-nuclear industry experience that was not previously addressed.

A review of the Comanche Peak and Shoreham DR/gR reports which establish the acceptability of the connecting rod assembly for its intended purpose.Maintenance recommendations based on the Comanche Peak DR/gR report to ensure proper performance under normal operating condit'ions are as follows:~Perform a clearance check at the link rod/link pin connection to verify the zero clearance when the specified bolt torque of 1050 ft-lb is applied.This is a one time check.~At the first 5 year overhaul visually inspect the rack teeth surfaces for signs of fretting.It is recommended that an eddy current examination be performed on the rod box female threads and cast impressions be taken and examined to ensure the tears (shallow cracks)in the threads do not propagate.

This is to be done at the next refueling outage not exceed 200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> of additional engine operation per I.O.C.(G.Derbalian to D.Pasquale).

The purpose of this reinspection is to insure that these cracks are benign and will not propagate under engine operating loads.Upon satisfactory results of the reinspection the engine can be operated to the first major overhaul with reinspections scheduled at subsequent major overhauls.

It is recommended that wrist pin bushings R28 and L48 be replaced upon engine reassembly because they failed to meet acceptance criteria.This is reported by NCR 1570 which remains open.It is recommended that connecting rod bolt lA-6-4 be replaced upon engine reassembly as it failed liquid penetrant and magnetic particle examinations as reported by TER 02-014.Additional quality inspections performed to date have been reviewed and are considered sati s f actory.SH2631/1 REV 1 COMPONENT DESIGN REVIEW.CHECKLIST Page 2 of 2 DR-02-02-340A"2 The fol lowing equality Reval i dati on Inspection recommendations are made to ensure proper component quality and performance, and should be performed on both diesel engines: Per form a visual inspection of the rack teeth surfaces for signs of fretting and prior to reassembly inspect mating surfaces to verify that the minimum manufacturers recommended percent contact surface is obtained.~Perform a clearance check of the link rods and link pins for proper alignment.

Perform a visual inspection of all connecting rod bolt washers and contact surfaces for signs of galling.Verify that the torque loads on all connecting rod bolts are in accordance with the latest TDI recommended values.Verify the proper fit-up for the serrated joint of the connecting rods.I There are no modification recommendations for this component.

PRIMARY FUNCTION Not required ATTRIBUTE TO BE VERIFIED Not required SPECIFIED STANDARDS Not required REFERENCES Not required DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSO SH2631/2 PROGRAM MANAGER QC 4(REV.1 Page Bl of 8 02-02-340A COMPONENT UALITY REVALIDATION CHECKLIST Carolina Power 8 Light Connecting Rods-Shearon Harris Nuclear COMPONENT Connectin Rods 8 Bushin s UTILITY Power Plant-Unit 1 GPL NO.02-340A SNPS GPL NO.03-340A REV.NO.4 TASK DESCRIPTIONS En ine 1A"SA 1.Assemble and review existing documentation.

2.Perform a material comparator test on the connecting rods (sample of 4).Use spares if available.

3.Perform a hardness test on the connecting rods (sample of 4).Use spares if available.

4.Perform Eddy Current test on all rod box female threads.I 5.Perform a Magnetic Particle test on all connecting rod bolts.6.Perform a visual inspection of all connecting rod bolt washers and contact surfaces for signs of galling.7.Verify that the torque loads on all connecting rod bolts are in accordance with the latest TDI recommended values.8.Perform a Liquid Penetrant test on the surface of the internal'iameter of all the wrist pin bushings.9..Perform a visual inspection of the rack teeth connection for signs of fretting.10.Perform a clearance check of the link rods and link pins for proper alignment.

ll.Verify the proper fit-up for the serrated edge of the connecting rods.En ine 18-SB 1.Assemble and review existing documentation.

SH1745/1 REV.I Page B2 of 8 02-02-340A TASK DESCRIPTIONS (continued)

En ine 1B-SB-2.3.4.5.Perform an Eddy Current test on all rod box female threads..Perform a Magnetic Particle test on all connecting rod bolts.Perfrom a visual inspection on all connecting rod bolt washers and contact surfaces for signs of galling.Verify that the torque loads on all the connecting rod bolts are in accordance with the latest TDI recommended values.6.7.8.Perform a Liquid Penetrant test on the surface of the internal diameter of all wrist pin bushings.Perform a visual inspection of the rack teeth connection for signs of fretting.Perform a clearance check of the link rods and link pins for proper alignment.

9.Verify the proper fit-up for the serrated edge of the connecting rods.ATTRIBUTES TO BE VERIFIED En ine 1A-SA 1.equality status of Component Document Package 2.'aterial of the connecting rods and bushings 3.Hardness of the connecting rods and bushings 4.Surface integrity of the rod box female threads 5.Surface integrity of the connecting rod bolts 6.Surface integrity of the connecting rod bolt washers and contact surfaces 7.Proper torque loads are applied to the connecting rod bolts 8.Surface integrity of the wrist pin bushings 9.Surface integrity of the rack teeth connection SH1745/2 Page B3 of 8 02-02-340A ATTRIBUTES TO BE VERIFIED (continued)

~('10.Proper clearance of the link rods and link pins ll.Proper fit-up for the serrated edge.2.3.guality status of Component Document Package Surface integrity of the rod box female threads Surface integrity of the connecting rod bolts 4.Surface integrity of the connecting rod bolt washers and contact surfaces 5.6.7.8.9.Proper torque loads are applied to the connecting rod bolts Surface integrity of the wrist pin bushings Surface integrity of the rack teeth connection Proper clearance of the link rods and link pins Proper fit-up for the serrated edge.ACCEPTANCE CRITERIA En ine 1A-SA 2" 3.4" 5.Satisfactory Document Package Material to be AISI-4140 Review of inspection report by the Design Group 6.No signs fo galling on the connecting rod bolt washers and contact surfaces 7~Torque loads on the connecting rod bolts are in accordance with the TDI Instruction Manual 8.Absence of linear indications on the internal diameter (bottom dead center a15 only)of the wrist pin bushings (see Attachment A)9.No signs of fretting on the rack teeth connection SH1745/3 Page 84 of 8 02-02-340A ACCEPTANCE CRITERIA (continued) 10.Proper clearance of the link rods and link pins 11.75K minimum rack teeth surface contact 1.Satisfactory Document Package 2-3.Material to be AISI-4140 4.No signs of galling on the connecting rod bolts washers and contact surfaces 5.Torque loads on the connecting rod bolts are in accordance with the TDI Instruction Manual.6.Absence of linear indications on internal diameter (bottom dead center a15'nly)of the wrist pin bushings (see Attachment A).7.No signs of fretting on the rack teeth connection 8.Clearance dimension must be zero when the specified torque of 1050 f t.-lb.is applied.9.75K minimum rack teeth surface contact REFERENCES 1.gCI No.52 2-6.Approved Site NDE Procedures 7.TDI Instruction Manual 8-9.Approved Site NOE Procedures 10.TDI Instruction Manual ll.Approval Site NDE Procedures, TER¹99-034 SH1745/4 REV 1

REFERENCES En ine 1B-SB 1.gCI No.52 2-4.Approved Site NDE Procedures 5.TDI Instruction Manual 6-7.Approved Site NDE Procedures 8.TDI Instruction Manual 9.Approved Site NDE Procedures, TER¹99-034 DOCUMENTATION RE UIRED Page B5 of 8 02-02-340A 1.Document Summary Sheet 2-11.Inspection Report 1.Document Summary Sheet 2-9.Inspection port GROUP CHAIRPERSON rf: PROGRAM MANAGE COMPONENT REVIEW En ine lA-SA 1.No EDGCTS site experience documents are in evidence.2.A material comparator test was performed on connecting rods 3,5,7 and 8.The results were reported by TER¹02-014.3.A hardness test was performed on connecting rods 3, 5, 7 and 8.The results were reported by TER¹02-014.4.An Eddy Current test was performed on all left bank connecting rod box female threads.The results were reported by TER¹02-014.SH1745/5 COMPONENT REVIEW (continued)

Page B6 of 8 02-02-340A 5.6"7.A Magnetic Particle test was performed on all upper connecting rod bolts.The results were reported by TER¹02-014.No inspection reports have been received which fulfill these requirements.

8.9-11.Note: A Liquid Penetrant test was performed on all wrist pin bushings for connecting rods 5, 6, 7, and 8.Some indications were noted outside the critical area.The results were reported by TER¹02-014.No inspection repor ts have been recei ved which ful f i 1 1 these requirements.

a)A dimensional check of the master and link rods was performed to determine the amount of centerline bow.Results were reported by TER¹02-031.En ine 1B-SA An Eddy Current test was performed on all left bank connecting rod box female threads.In addition, an Eddy Current test was performed on the connecting rod oil holes for cylinders 3 and 7.Results were reported by TER¹02-059.1.All EDGCTS site experience documents were assembled and reviewed with~~~~~~~~unsatisfactory results.NCR No.84-1570 remains open.2.3.A Magnetic Particle test was performed on all connecting rod bolts.Indications were noted on cylinder 7.Results were reported by TER¹02"059.4-5.No inspection reports have been received which fulfill these requirements.

6.7" 9.Note: A Liquid Penetrant test was performed on the rod eye bushings.Results were reported by TER¹02-059.No inspection report has been received which fulfills this requirement.

a)A dimensional check of the master and link rods was performed to determine the amount of centerline bow.Results were reported by TER¹02-038.SH1745/6 COMPONENT REVIEW (continued)

Page B7 of 8 02"02"340A b)A hardness test was performed on four connecting rods.Results were reported by TERS,02-059.

c)Material Comparator tests were~performed on four connecting rods.This was reported by TERS02-059.RESULTS AND CONCLUSION

-A The guality Revalidation effort with respect to this component, as out-lined above, is complete.The results have been forwarded to the Oesign Review Group for their evaluation and conclusions in support of the final report.En ine 1B-SB Same as Engine 1A-SA.GROUP CHAIRPERSON 0 Ac f~'.(Qkc Pc.PROGRAM MANAGER~A SH1745/7 0

ATTACHMENT A COMPONENT UALITY REVALIDATION CHECKLIST Page BS of 8 02-02-340A LI UIO PENETRANT ACCEPTANCE CRITERIA Acceptance criteria are gener ally included in the code or specification which establishes the required examination.

Such specified criteria shall be used to determine the specific type, size and location of observed discontinuities.

When acceptance criteria is not specified in the documentation estab-lishing the requirement for the examination, the following relevant indications are unacceptable.

Only indications with major dimensions greater that 1/16 inch shall be considered relevant.a.)Wrou ht For ed or Welded Items: l.Any crack or linear indication Rounded indications with dimensions greater than 1/8 inch for thickness less than 5/8 inch and greater than 3/16 inch for thickness of 5/8 inch and greater.e Four or more indications in line separated by 1/16 inch or less edge to edge.4.Ten or more indications in any 6 square inches of area whose major dimension is no more than 6 inches with the dimensions taken in the most unfavorable location relative to the indications being evaluated.

b.)Bolts and Boltin Material Greater than 1 inch Normal Size 1.Any linear nonaxial indications.

2.Linear axial indications greater than 1 inch.SH1745/8 REV.I COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT" UNIT 1 Page 1 of 2 COMPONENT Connectin Rod Bearin Shells UTILITY Carolina Power 8 Li ht Co.GROUP PARTS LIST NO.02-340B TASK DESCRIPTION NO.DR" 02-02" 340B-0 SNPS GPL NO.03-340B CLASSIFICATION TYPE A TASK DESCRIPTIONS Design review for this component is not required based on the following:

A review of the Comanche Peak and Shoreham DR/gR reports which establishes the acceptability of the bearing shells for their intended purpose.The applicable engine dimensions and operating parameters at Shearon Harris are identical or very similar to those for the same component at Comanche Peak (lead engine).A review of the Component Tracking System nuclear and non-nuclear experience, and site experience listed below which does not appear in the CTS.Maintenance recommendations based on the Comanche Peak DR/gR report to ensure proper performance under normal operating conditions are as follows:~Inspect and measure the connecting rod bearing shells to verify lube oil maintenance which affects wear rate.The visual and dimensional'nspection of the bearing shells should be conducted at the fuel outage which precedes 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> of operation by at least the sum of hours of oper ation in a LOOP/LOCA event plus the expected hours of operation between outages.~Perform an X-ray examination on all bearing shells using a procedure with sufficient resolution to implement recommendations for acceptance criteria as documented in the TDI Owners Group connecting rod bearing shells Phase I Report.No modifications are recommended for this component.

The guality Revalidation requirements for this component have been completed.

Engine 1A has two outstanding NCR nos.84-1271 and 84-1639.Engine 1B has two outstanding NCR nos.84-1271 and 84-1640.It is recommended that all three outstanding NCRs be closed during reassembly of the engines.SH2293/1

PRIMARY FUNCTION Not required COMPONENT DESIGN REVIEW CHECKLIST Page 2 of 2 DR-02" 02-340B-0 ATTRIBUTE TO BE VERIFIED Not required SPECIFIED STANDARDS Not required REFERENCES Not required DOCUMENTATION RE VIREO Not required GROUP CHAIRPERSON PROGRAM MANAGER DC SH2293/2 COMPONENT UALITY REVALIDATION CHECKLIST Page 1 of 7 02-02-340B Connecting Rod Bearing COMPONENT Shells GPL NO.02"340B SNPS GPL NO.03"340B Carolina Power 8 Light Shearon Harris Nuclear UTILITY Power Pl ant-Uni t 1 REV.NO.2 TASK DESCRIPTIONS En ine 1A-SA l.Assemble and review existing documentation.

2.Perform a visual inspection of'he connecting rod bearing shells.3.Perform a Liquid Penetrant test on the connecting rod bearing shells.4.Perform a dimensional check of the connecting rod bearing shells.5.Peform a Radiographic inspection of the connecting rod bearing shells.6.Perform an Eddy Current test as required to identify discontinuities.

surface Same as Engine 1A-SA ATTRIBUTES TO BE VERIFIED En ine 1A-SA 2 3~5" 6.guality status of Component Document Package Surface integrity of bearing shells Proper bearing shell dimensions Integrity of the bearing shells SH1904/1 COMPONENT UALITY REVALIDATION CHECKLIST ATTRIBUTES TO BE VERIFIED (continued)

En ine 1B-SB Same as Engine 1A-SA Page 2 of 7 02"02"340B ACCEPTANCE CRITERIA 2" 3.5.6.Satisfactory Document Package Review of inspection report by the Design Group Dimensions are in accordance with the TDI Instruction Manual See Attachments A&B.Review of inspection report by the Design GroupEn ine 1B-SB Same as Engine lA-SA REFERENCES En ine 1A-SA 1.(CI No.52 2-3.Approved Site NDE Procedure 4.TDI Instruction Manual or applicable drawing 5.FaAA NDE Procedure 9.3, TERS99-011 6.Approved site NDE Procedures Same as Engine 1A-SA SH1904/2 COMPONENT UALITY REVALIDATION CHECKLIST DOCUMENTATION RE UIRED Page 3 of 7 02-02-340B En ine lA-SA 1.Document Summary Sheet 2-6.Inspection Report En ine 1B-SB Same as Engine lA-SA GROUP CHAIRPERSON PROGRAM MANAGER~'-COMPONENT REVIEW En ine lA-SA l.All EDGCTS site experience documents were assembled and reviewed with unsatisfactory results.NCR Nos.84-1271 and 84-1639 remain open.2.A visual inspection was performed on various connecting rod bearing shells.The results were reported by TER¹02-032.3.A Liquid Penetrant test was performed on all connecting rod bearing shells with satisfactory results.This was reported by TER¹02-094.4.A dimensional check of all connecting rod bearing shells was performed with the exception of the top shell of bearing no.7 which was rejected because of cracking.The results were reported by TER¹02-032.5.A Radiographic test was performed on the connecting rod bearing shells with indications reported on the No.7 lower shell.This was reported by TER¹02-094.6.An Eddy Current test was performed on various bearing shells with satisfactory results.This was reported by TER¹02-094.En ine 1B-SB l.All EDGCTS site experience documents were assembled and reviewed with unsatisfactory results.NCR Nos.84-1271 and 84-1640 remain open.2.A visual inspection was performed on various connecting rod bearing shells.The results were reported by TER¹02-039.SH1904/3 COMPONENT UALITY REVALI DATION CHECKLIST COMPONENT REVIEW (continued)

Page 4 of 7 02"02-3408 3.A Liquid Penetrant test was performed on the bearing shells with satisfactory results.This was reported by TER¹s02-087 and 02-094.4.A dimensional check was performed on bearing shells Nos.1, 4, 6, and 8, top bearing No.2 and the bottom shells of bearing Nos.3 and 7.'he remaining bearing shells were rejected due to either cracking or foreign material indications.

The results were reported on TER¹02-039.5.A Radiographic inspection was performed on the bearing shells with unsatisfactory results.This was reported by TER¹02-087.6.An Eddy Current test was performed on most bearing shells with satisfactory results.This was reported by TER¹s02-087 and 094.RESULTS AND CONCLUSION En ine lA-SA The guality Revalidation effort with respect to this component, as outlined above, is complete.The results have been forwarded to the Design Review Group for their evaluation and conclusions in support of the final report.Same as Engine lA-SA GROUP CHAIRPERSON c.PROGRAM MANAGER SH1904/4

Attachment A COMPONENT UALITY REVALIDATION CHECKLIST Page 5 of 7 02-02-340B Component:

Examination:

Examination:

Area Acceptance:

~~Criteria Connecting Rod Bearing Shells, Upper and Lower.X-ray, FaAA NDE 9.2 (R-48);FaAA NDE 9.3 (V-12, V-16, V-20).U er Bearin Shell, see attached figures: R-48: 0.050 inch area, 0.4 inch inward from each side to a line 1.4 inches inward from each side, extending circumferentially 2.5 inches on either side of the oil hole.This is the critical area.V-12, V-16, V-20: 0.050 inch area, 0.4 inch inward from each side to a line 1.4 inches inward from each side, extending circumferentially 5.0 inches on either side of the center of the bearing.This is the critical area.0.250 inch area, remainder of bearing..Lower Bearin Shell: 0.250 inch area, all of bearing.The following are unacceptable, based on 3/4 inch reference radiographs of ASTM E-155, for aluminum.UPPER BEARING UPPER 8(LOWER BEARING 0.050 INCH AREA 0.250 INCH AREA Gas Holes Gas Porosity (Rounded)Gas Porosity (Elongated)

Shrinkage Sponge Foreign Material Less Dense Foreign Material More Dense Cracks Shrinkage Cavity 0.050 diameter Grade 5 Grade 3 Grade 3 0.050 diameter 0.050 diameter Unacceptable Unacceptable Grade 5 Grade 7 Grade 5 Grade 4 Grade 3 Grade 4 Unacceptable 0.250 SH1904/5 Attachment A COMPONENT UALITY REVALIDATION CHECKLIST Page 6 of 7 02-02-340B Note: Mottling/segregation and micro sht inkage shall not be evaluated for rejection.

4 Radiographic features that are associated with the babbitt (lead alloy)layer on the bearing I.D.shall not be evaluated for rejection.

For further clarification of these criteria, please contact the Owner s Group.SH1904/6

~Grltlcal Area 4N t.4'.0'~~~Critical Area 0 0.0'1.4'l fTl D'w C7 w Cl n n-I lEAANCES UNLESS OTIIEANISE SPECIFIED x-i DRANN CIIECKED DEARlNG SIIELL CRlTICAL AREA TDl Y-12, Y-t6, Y-20 Ref: FaAA NDE 9.3 Fatlore Analysts Assoctates 2225 East t3ayslIore Road P.o.Box 5)470 Palo Alto, California 94303 navr-O Q~CO I LQ O I bJ W O C)M U7 Page 1 of 2 COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 COMPONENT Pistons GROUP PARTS LIST NO.02-341A SNPS GPL NO~03-341A UTILITY Carolina Power 8 Li ht Com an TASK DESCRIPTION NO.DR-02-02-341A" 2 CLASSIFICATION TYPE A TASK DESCRIPTIONS Design review for this component is not required based on a review of the Shoreham and Comanche Peak DR/gR reports, the Phase I report and the reported industry experience.

There is no site experience in the EDG Component Tracking System.CP&L is in the process of changing from AN to AE pistons at Shearon Harris..The AE piston incorporates design changes and has not been observed to crack in service.The stud boss region of the AE is considerably thicker than the AN.The rib has also been thickened and blended more smoothly into the wrist pin bosses, thereby considerably strengthening the rib area in this design.There are no maintenance or modification recommendations for this component.

guality inspections have been completed and the results were found to be satisfactory.

PRIMARY FUNCTION Not required ATTRIBUTE TO BE VERIFIED Not required SPECIFIED STANDARDS Not requiredSH2134/1 REFERENCES Not required COMPONENT DESIGN REVIEW CHECKLIST Page 2 of 2 DR-02-02-341A-2 DOCUMENTATION RE VIREO Not required GROUP CHAIRPERSON PROGRAM MANAGER C.KK SH2134/2

COMPONENT UALITY REVALIDATION CHECKLIST Page 1 of 5 02-02-341A COMPONENT Piston GPL NO.02-341A SNPS GPL NO.03-341A Carolina Power 8 Light, Shearon Harris Nuclear UTILITY Power Plant-Unit 1 REV.NO.3 TASK DESCRIPTIONS En ine lA-SA 1.Assemble and review existing documentation, 2.Prior to installation, perform a Liquid Penetant test on the piston skirts.Map all linear indications in the stud boss area and document with photographs.

In addition,"AN" pistons should be inspected adjacent to the wrist pin boss.3.If Liquid Penetrant test results from task¹2 reveal indications greater than 1/32 inch length, one of the following tasks should be performed:

a)Remove the indications by surface conditioning; or b)Perform an Eddy Current test to determine if the indications must be removed.4.Perform Liquid Penetrant test on the rib area on the rib at the intersection of the wrist indications in the casting ("AE" pistons sketch.near the wrist pin and pin boss to check for only).See attached Same as Engine 1A-SA NOTE:'f no rejectable indications are found, performed on one station engine only.inspections should beSH1040/1

COMPONENT UALITY REVALIDATION CHECKLIST Page 2 of 5 02"02-341A ATTRIBUTES TO BE VERIFIED En ine lA-SA l.guality status of Component Document Package 2-3.Surface integrity of the piston skirts 4.Surface integrity of the rib and rib area En ine 18-SB Same as Engine-lA-SA ACCEPTANCE CRITERIA En ine 1A-SA 1.Satisfactory Document Package 2-4.Review of inspection report by the Design Group Same as Engine lA"SA REFERENCES En ine lA-SA l.gCI No.52 2.Approved Site NDE Procedures 3.Approved Site NDE Procedures, TER¹99-027 4.Approved Site NDE Procedures, TER¹99-010 Same as Engine 1A-SA SH1040/2 COMPONENT UALITY REVALIDATION CHECKLIST Page 3 of 5 02-02-341A DOCUMENTATION RE UIRED En ine 1A-SA 1.Document Summary Sheet 2-4.Inspection Report En ine 1B-SB Same as Engine 1A-SA GROUP CHAIRPERSON PROGRAM MANAGER COMPONENT REVIEW En ine lA-SA No EDGCTS site experience documents are in evidence.2.3.Liquid Penetrant tests were performed on all"AE" replacement piston skirts in the stud boss areas as indications were noted on the¹8 skirt.Results were reported by TER¹02-099.No inspection report has been received which fulfills this requirement.

Magnetic Particle tests were performed on all"AE" replacement piston skirts at the rib to wrist pin boss intersection.

Results were reported by TER¹02-099.En ine 1B-SB 2-4.No EDGCTS site experience documents are in evidence.No inspection reports have been received which fulfill these requirements.

SH1040/3

COMPONENT UALITY REVALIDATION CHECKLIST Page 4 of 5 02"02-341A RESULTS AND CONCLUSION The gual i ty Reval i dati on ef fort wi th respect to thi s component, as outlined above, is complete.The results have been forwarded to the Design Review Group for their evaluation and conclusions in support of the final report.Same as Engine 1A-SA PROGRAM MANAGERSH1040/4 COMPONENT UALITY REVALIOATION CHECKLIST Page 5 of 5 02-02-341A COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Page 1 of 2 COMPONENT Piston: Rin s GROUP PARTS LIST NO.02-341B UTILITY Carolina Power&Li ht Com an TASK DESCRIPTION NO.DR" 02" 02"341B-0 SNPS GPL NO.03"341B CLASSIFICATION TYPE A TASK DESCRIPTIONS Design review for this component is not required based on the following:

~A review of the Comanche Peak and Shoreham DR/gR reports which establishes the acceptability of the piston rings for their intended purpose.~The applicable engine dimensions and operating parameters at Shearon Harris are identical or very similar to those for the same component at Comanche Peak (lead engine).~A review of the Component Tracking System indicated that there was no significant applicable industry or site experience.

Maintenance recommendations based on the Comanche Peak DR/gR report to ensure proper performance under normal operating conditions are as follows: Inspect and measure replacement piston rings in accordance with TDI inspection and maintenance records.To assure freedom from harmful scuffing, the cylinder liners should be inspected at each fuel outage to evaluate liner wear and coke deposits.Ring replacements and cylinder liner honing should be performed in accordance with TDI maintenance procedures.

When replacing engine oil use H.D.oil that exceeds series 3 standards.

The base stock should be more resistant to thermal degradation and coke formation.

The additive package should provide high detergent dispersant properties with high alkalinity and a high level of antiwear additive such as zinc dithiophosphate.

Total Base Number (TBN)should be 12 to 15 for use with 02 fuel oil and a sulfated ash content of 1.5X to 2.0X is preferred.

An engine oil with such properties, Mobil-Guard 412 or equivalent product may be used to ensure improved lubrication.

135 fuel oil spr ay tips may be used if inspections results indicate a need for additional action to improve lubrication and reduce coke buildup.SH2107/1 COMPONENT DESIGN REVIEW CHECKLIST Page 2 of 2 DR-02-02" 3418-0 The following guality Revalidation inspection is recommended to ensure component quality:~Verify piston ring installation is in compliance with TDI assembly requirements for all station engines.There are no modification recommendations for this component.

PRIMARY FUNCTION Not required ATTRIBUTE TO BE VERIFIED Not required S PECIFIED STANDARDS Not required REFERENCES Not required DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGER e K(~SH2107/2 COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Page 1 of 3 COMPONENT Piston Pin Assembl UTILITY Carolina Power 8 Li ht Com an GPL NO.02-341C TASK DESCRIPTION NO.DR" 02-02-341C-0 SNPS GPL NO.03" 341C CLASSIFICATION TYPE A TASK DESCRIPTIONS Design review for this component is not required based on review of the lead engine DR/gR reports (Shoreham/Comanche Peak)and the reported applicable industry experience.

There is no reported site experience in the EDG Component Tracking System.Presently Shearon Harris uses spiral ring retainers (P/N F-108-030) to prevent lateral movement of the wrist pin.For increased engine reliability as stated in the Shoreham DR/gR report it is recommended that:~The present spiral ring retainers be replaced with Waldes snap ring retainers (P/N GE-003-067) at the first fuel outage.guality inspections conducted to date have been reviewed.Three wrist pins, R-2 and R-5 from engine 1A-SA, and R-2 from engine 1B-SB displayed either linear indications, chrome blistering or chrome chipping.These three pins have all been rejected (Refs.1, 2 and 3)and wrist pin R-2 from engine 1B-SB was sent back to TDI to be re-chromed.

Hardness tests were performed on two separate occasions, the second time extra caution was taken to ensure the tested surface was thoroughly clean.Results indicated that two wrist pins had values slight-ly higher than specification.

This is not of concern since a certain loss of accuracy can be expected when performing one type of hardness test and convert-ing the values to another measuring system.Also, the wrist pins are induction hardened and since the test was performed on the ends of the pins, the results may not be representative of the load bearing surface.Material comparator tests were performed on all thir ty-two wrist pins.All of the wrist pins were satisfactory, with the exception of wrist pin L-4 from engine lA-SA, which varied from the known sample by 70 units.Based on the results of the quality inspections, the following recommendations are made:~Either return wrist pins R-2 and R-5 from engine lA-SA to TDI for reworking, or replace with acceptable wrist pins.SH2405/1 COMPONENT DESIGN REVIEW CHECKLIST Page 2 of 3 DR-02-02-341C" 0 TASK DESCRIPTIONS (continued)

Re-test by material comparator method wrist pin L-4 from engine 1A-SA, making sure the surface being tested is clean and dry, and the probe tip is clean.Make certain the test is performed on the same location of the pin that the other tests were taken.If the result of the material comparator test are satisfactory, the wrist pin is acceptable for use.If the results of the re-test are unsatisfactory the wrist pin should be replaced with an acceptable one.The.following maintenance inspections are recommended for this component:

'I~Visually inspect all pins for chrome plate damage.~Inspect end plugs and reroll or replace any that are loose.NOTE: The above inspections should be performed during major engine overhauls and also whenever the pistons are removed and disassembled to an extent that such inspections are possible.Perform a liquid penetrant test or a magnetic particle test on all new or replacement pins before installation in engines.The following guality inspection is recommended for engines lA-SA and 18-SB:~Visually inspect the rolled-in oil plugs for proper installation.

PRIMARY FUNCTION Not required ATTRIBUTE TO BE VERIFIED Not required SPECIFIED STANDARDS Not requiredSH2405/2

REFERENCES

.COMPONENT DESIGN REVIEW CHECKLIST Page 3 of 3 DR-02-02-341C-0 1.NCR 84-1672 8(TER 02-033 2.NCR 84-1776 8(TER 02-033 3.NCR 84-1570 8 TERs02-040 8 02-084 DOCUMENTATION RE VIREO Not reqvired GROUP CHAIRPERSON PROGRAM MANAGER QCSH2405/3 0

COMPONENT UALITY REVALIDATION CHECKLIST Page 1 of 5 02"02"341C COMPONENT Piston-Pin Assembl GPL NO.02"341C Carolina Power 8 Light Shearon Harris Nuclear UTILITY Power Plant-Unit 1 REV.NO.2 SNPS GPL NO.03-341C TASK DESCRIPTIONS 1.Assemble and review existing documentation.

2.Perform a material comparator test on one wrist.pin and one spare.3.Perform a hardness test on one wrist pin and one spare.4.Visually inspect the rolled-end oil plug installations.

5.Visually inspect the wrist pins for signs of distress.6.Perform a dimensional check of one spare wrist pin.1.Assemble and review existing documentation.

2.Visually inspect the rolled-end oil plug installations.

3.Visually inspect the wrist pins for signs of distress.4.Perform a dimensional check of one spare wrist pin.NOTE: Inspections to be performed on four wrist pins-except where noted.(Engine lA-SA and 1B-SB)SH1903/1 COMPONENT UALITY REVALIDATION CHECKLIST ATTRIBUTES TO BE VERIFIED En ine 1A-SA 1.guality status of Component Document Package 2.Material of the wrist pins 3.Hardness of the wrist pins 4.Proper installation of rolled-end oil plugs 5.Su'rface'integrity of the wrist pins 6.Proper wrist pin dimensions Page 2 of 5 02-02-341C 1.guality status of Component Document Package 2.Proper installation of the rolled-end oil plugs 3.Surface integrity of the wrist pins 4.Proper wrist pin dimensions ACCEPTANCE CRITERIA 1.Satisfactory Document Package 2.Material to be AISI-8630 3.Review of inspection report by Design Group 4.Piston pin assembly installed in compliance with the TDI Instruction Manual.5-6.Review of inspection report by Design Group En ine 1B-SB Satisfactory Document Package 2.3-4.Piston pin assembly is installed in compliance with the TDI Instruc-tion Manual.Review of inspection report by Design Group ,, SH1903/2

REFERENCES En ine lA-SA COMPONENT UALITY REVALIDATION CHECKLIST Page 3 of 5 02-02-341C l.gCI No.52 2 3~5-6.Approved Site NDE Procedures Approved Site NDE Procedures, TDI Instruction Manual Approved Site NDE Procedures En ine 1B-SB gCI No.52 2.Approved Site NDE Procedures, TDI Instruction Manual 3-4.Approved Site NDE Procedures DOCUMENTATION RE UIRED 1.Document Summary Sheet 2-6.Inspection Report En ine 1B-SB 1.Document Summary Sheet 2-4.Inspection Report GROUP CHAIRPERSON PROGRAM MANAGER COMPONENT REVIEW En ine lA-SA 1.All EDGCTS site experience documents were assembled and reviewed with unsatisifactory results.NCR Nos.84-1672 and 84-1776 remain open.SH1903/3 Fg fl, C OMPONENT UALITY REVALIDATION CHECKLIST Page 4 of 5 02-02-341C COMPONENT REVIEW (continued) 2.A mater ial comparator test was performed on piston pin L4 with unsatisfactory results.This was reported by TER¹02-033.3.A hardness test was performed on all wrist pins with unsatisfactory results reported for pins R3 and RS.This was reported by TER¹02-033 and dispositioned by NCR-84-1840.

4.No inspection report has been received which fulfills this requirement.

5.A visual inspection was performed on all wrist pins with unsatisfac-tory results reported for pin R2.This was reported by TER¹02-033 and dispositioned by NCR-84-1672.

6.A dimensional inspection was performed on four wrist pins.The results were reported by TER¹02-033.En ine 1B-SB 1.All EDGCTS site experience documents were assembled and reviewed with unsatisfactory results.NCR No.84-1570 remains open.2.No inspection report has been received which fulfills this requirement.

3.A visual inspection was performed on all wrist pins with various indications noted.The results were reported by TER¹02-040.4.A dimensional inspection was performed on all wrist pins.The results were reported by TER¹02-040.Note: a)Two hardness tests were performed on the wrist pins.Results were reported by TER¹s02-084 and 060.b)A material comparitor test was performed on the wrist pins.Results were reported by TER¹02-060.RESULTS AND CONCLUSION En ine 1A-SA The guality Revalidation effort with respect to this component, as outlined above, is complete.The results have been forwarded to the Design Review Group for their evaluation and conclusion in support of the final report.SH1903/4 COMPONENT UALITY REVALIOATION CHECKLIST RESULTS AND CONCLUSION (continued)

Page 5 of 5 02-02"341C Same as Engine 1A-SA GROUP CHAIRPERSON PROGRAM MANAGERSH1903/5 COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Page 1 of 2 Tappets and Guides: Intake COMPONENT 8 Exhaust Ta et Assembl GROUP PARTS LIST NO.02"345A SNPS GPL NO.03-345A UTILITY Carolina Power 8 Li ht Com an TASK DESCRIPTION NO: DR-02" 02-345A-0 CLASSIFICATION TYPE A TASK DESCRIPTIONS Design review for this component is not required based on the review of appli-cable industry experience and the lead engine DR/gR report ,(Comanche Peak).There is no reported site experience for this component in the EDG Component , Tracking System.The following routine maintenance is recommended for this component:

~Verify that the intake and exhaust tappet rollers are free to rotate, and that there is no measurable clearance between the cam rollers and roller pins.This inspection should take place at each outage using TDI inspection and maintenance record form 345-1-1.There are no modification recommendations for this component.

The following quality inspection is recommended to be performed on Engine 1A-SA and 1B-SB: Verify that the intake and exhaust rollers are free to rotate and that no measurable clearance exist between the pin and roller.PRIMARY FUNCTION Not required ATTRIBUTE TO BE VERIFIED Not required SH2191/1 SPECIFIED STANDARDS Not requred COMPONENT DESIGN REVIEM CHECKLIST Page 2 of 2 DR-02-02-345A-0 REFERENCES Not required~DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGERSH2191/2 COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Page 1 of 2 Tappets and Guides: COMPONENT Fuel Ta et Assembl GROUP PARTS LIST NO.02-345B SNPS GPL NO.03"345B UTILITY Carolina Power&Li ht Com an TASK DESCRIPTION NO: DR-02-02-345B-0 CLASSIFICATION TYPE ATASK DESCRIPTIONS Design review for this component is not required based on the review of appli-cable industry experience and the lead engine DR/gR report (Comanche Peak).There is no reported site experience for this component in the EDG Component Tracking System.The following routine maintenance is recommended for this component:

~Verify that the fuel tappet rollers are free to rotate and that there is no measurable clearance between the cam roller and roller pin.This inspection should take place at each outage.The are no modification recommendations for this component.

The following equality inspection is recommended to be performed on Engine lA-SA and 1B-SB:~Verify that the fuel tappet rollers are free to rotate and that no measurable clearance exists between the pin and roller.PRIMARY FUNCTION Not required ATTRIBUTE TO BE VERIFIED Not required SPECIFIED STANDARDS Not required SH2188/1

'REFERENCES Not required COMPONENT DESIGN REVIEW CHECKLIST Page 2 of 2 DR-02-02-3458-0 DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGER i SH2188/2

COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Page 1 of 2 Tappets and Guides-Fuel COMPONENT Pum Base Assembl GROUP PARTS LIST NO.02-345C SNPS GPL NO.03-345C UTILITY Carolina Power L Li ht Com an TASK DESCRIPTION NO.DR-02-02-345C-0 CLASSIFICATION TYPE TASK DESCRIPTIONS Design review of this component for Shearon Harris is not required based on a review of the lead engine DR/QR reports (Shoreham/Comanche Peak)and a review of applicable industry and site experience as listed in the EDG Component Tracking System.The fuel pump base assembly (assembly O'A-6167), is similar to that used at Comanche Peak, Grand Gulf and San Onofre, (assembly 8 IA-3443), with the only difference being the diameters of the center push rod hole and surrounding base.The Catawba engines use the same pump base.The Catawba engines have each operated for approximately 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> with no reported diffi-culties with the fuel pump base.No special maintenance or modification requirements were identified in the lead engine design reviews.Initial bolt torque should be as specified in the TDI Manual.Quality Revalidation is not required for this component.

PRIMARY FUNCTION Not r equired ATTRIBUTE TO BE VERIFIED Not requiredSPECIFIED STANDARDS Not required SH2558/1 REFERENCES COMPONENT DESIGN REVIEW CHECKLIST Page 2 of 2-DR" 02-02-345C" 0 1.TDI Drawing No.02-345-05-AF,"Base, Fuel Pump" (listed in the Shearon Harris Parts list as the base for the fuel pump base assembly¹IA-6167)DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGER-3C~SH2558/2

COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT" UNIT 1 Page 1 of 2 COMPONENT Camshaft: Camshaft Assembl UTILITY Carolina Power and Li ht Co.GROUP PARTS LIST NO.02-350A TASK DESCRIPTION NO: DR-02-02-350A-0 SNPS GPL NO.03-350A CLASSIFICATION A TASK DESCRIPTIONS Design review for this component is not required based on the following:

~A review of the Comanche Peak and Shoreham DR/gR Reports which establishes the acceptability of the cam shaft assembly for its intended purpose.~The applicable engine dimensions and operating parameters at Shearon Harris are identical or very similar to those for the same component at Comanche Peak (Lead Engine).~A review of the Component Tracking System indicated that there was no significant applicable industry or site experience.

Maintenance recommendations based on the Comanche Peak DR/gR Report to ensure proper performance under normal operating conditions are as follows:~Perform a visual inspection of all cam lobe surfaces for signs of cracking, pitting or spalling, at each outage.Any signs of cracking, pitting or spalling shall be followed by a detailed analysis to evaluate the expected life based on the size and extent of surface distress and any corrective measures shall be implemented as indicated by this analysis.Signs of spalling shall result in immediate replacement of the cam.The following guality Revalidation inspection is recommended to ensure component quality:~After 100 hour0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> s run or pre-operational testing visually inspect cam lobes for indications of premature wear on all station engines.There are no modification recommendations for this component.

PRIMARY FUNCTION Not required I SH2093/1 COMPONENT DESIGN REVIEW CHECKLIST ATTRIBUTE TO BE VERIFIED Not required Page 2 of 2 DR-02-02-350A-0 SPECIFIED STANDARDS Not required REFERENCES Not required DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGER.-SH2093/2

COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Page 1 of 1 COMPONENT Camshaft: Camshaft Bearin GROUP PARTS LIST NO.02"350B SNPS GPL NO.03-350B UTILITY Carolina Power 8 Li ht Co.TASK DESCRIPTION NO.DR-02-02-350B-0 CLASSIFICATION TYPE A TASK DESCRIPTIONS:

Design review is not required for this component based on the Shoreham and Comanche Peak lead engine DR/gR reports which establish the acceptability of the camshaft bearings.A review of the Component Tracking System indicates no significant applicable site or industry experience.

equality revalidation is not required for this component.

There are no maintenance or modification recommendations for this component.

PRIMARY FUNCTION Not required ATTRIBUTE TO BE VERIFIED Not required SPECIFIED STANDARDS Not required REFERENCES Not required DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON SH2004/1 PROGRAM MANAGER

COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT" UNIT 1 Page 1 of 3 COMPONENT Gear Train Assembl UTILITY Carolina Power 8 Li ht Co.DR-02-02"350C-0 02-350C DR-02"02-355A-0 GROUP PARTS LIST NO.02"355A 02-355B TASK DESCRIPTION NO.DR"02-02-355B-0 03"350C SNPS GPL NO.03-355A 03-355B CLASSIFICATION TYPE A TASK DESCRIPTIONS Design review is not required for this component based on the lead engine DR/gR report (Comanche Peak)which established the acceptability of the gear train assembly.The component parts which are considered in this review are the same, except for the inlet and exhaust cams and a longer roll pin.Also, differences in the crankshaft/flywheel/generator shaft assembly have been considered, as they affect gear tooth loads.Resulting changes in gear tooth loads caused by the above differences are determined to be insignificant.

A review of the EDG Component Tracking System indicates no significant site or industry experience.

The following maintenance recommendations are made to ensure reliability of the components:

02-350C Camshaft-Su orts Boltin and Gears:~The number of No.9167 bolts, torqued at 70 (-20,+20)ft lbf, should be increased from 4 to 6.OR The initial torque in the four No.9167 bolts which connect the cam gear to the cam hub should be increased to 80 (-0+10)ft-lbf.In addition, the above discussion is based upon the assumption that it is possible to line up the cotter pin with the hole in the bolt within the prescribed torque range.If the cam gear and hub are disassembled and reassembled it is recommended that the nut be re-locked at a position within the prescribed torque range.Inser-tion of the cotter pin must be accomplished at a torque greater than 50 ft-lbf and less than 90 ft-lbf for the 6-bolt arrangement, and at a torque greater than 80 ft-lbf and less than 90 ft-lbf for the 4-bolt arrangement.

If insertion is not possible, another bolt and/or nut and/or washer should be used.SH2385/1 COMPONENT DESIGN REVIEW CHECKLIST Page 2 of 3 OR" 02-02" 350C-0 DR"02"02-355A-0 OR"02-02-355B-0 TASK DESCRIPTIONS (continued)

~The surveillance maintenance/inspection procedures should be modified to inspect the cam gear at every refueling outage.02-355A Idler Gear Assembl-Crank to Pum Gear:~The crank to pump gear should be inspected during each refueling outage.The inspection should be directed at potential pitting.Any abnormal indications or progressive pitting should be reported for an engineering evaluation.

02-355B Idler Gear Assembl~The idler gear and especially the jacket water pump gear should be inspected at all scheduled fuel outages, with any progressive pitting being reported for an engineering evaluation.

A photographic record of these inspections should be maintained at the site to assist in this evaluation.

Note: If the idler gear and hub are disassembled and reassembled, it is recommended that the nut be relocked at a position within the prescribed torque range of 70 (-20,+20)ft-lbf.Insertion of the cotter pin must be accomplished at a torque greater than 50 ft-lbf and less that 90 ft-lbf.If this is not possible, another bolt and/or nut and/or washer should be used.There are no modification recommendations for this component.

guality inspections that have been conducted to date have been reviewed and are considered satisfactory.

It is recommended that the guality inspections listed below be performed:

02-350C Camshaft-Su orts Boltin and Gears:~Verify that the proper torque values are applied to the bolts (cam to cam gear)on Engines lA-SA and 1B-SB.~Perform a visual inspection of the cam gear for signs of wear, pitting or any other discontinuities on Engine 1A-SA.02-355A 8 B Idler Gear Assembl-Crank to Pum 8 Idler Gears:~Perform a visual inspection on the crank to pump gear set teeth and idler gear teeth for signs of wear, pitting, or any other discontinu-ities, on engine 1A-SA.SH2385/2 PRIMARY FUNCTION Not required COMPONENT DESIGN REVIEW CHECKLIST Page 3 of 3 OR-02" 02-350C-0 DR" 02-02-355A-0 DR-02-02" 355B-0 ATTRIBUTE TO BE VERIFIED Not required SPECIFIED STANDARDS Not required REFERENCES Not required DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGERSH2385/3 COMPONENT UALITY REVALIDATION CHECKLIST Page 1 of 4 02-02-350C Camshaft-Supports, COMPONENT Boltin and Gears GPL NO.02"350C Carolina Power&Light Shearon Harris Nuclear UTILITY Power Plant-Unit 1 REV.NO.2 SNPS GPL NO.03"350C TASK DESCRIPTIONS

~E 1.Assemble and review existing documentation.

2.Verify that the proper torque values are applied to the bolts (cam to cam gear).3.Perform a visual inspection of the cam gears for sign of wear, pitting or any other discontinuities.

4.Determine the hardness of the cam gears.5.Determine the material of the cam gears.l.Assemble and review existing documentation.

2.Verify that the proper torque values are applied to the bolts.3~Perform a visual inspection of the cam gear for sign of wear, pitting or any other discontinuities.

ATTRIBUTES TO BE VERIFIED En ine 1A-SA l.guality status of Component Document Package 2.Proper torque loads are applied to the bolts.SH1722/1 COMPONENT UALITY REVALIDATION CHECKLIST ATTRIBUTES'TO BE VERIFIED (continued)

Page 2 of 4 02-02-350C 3.Surface integrity of the cam gears 4.Hardness of the cam gears 5.'at'erial of the cam gears'.-'-1.::-guality"status at Component Document Package 2.Proper torque loads are applied to the bolts 3.Surface integrity of the cam gears ACCEPTANCE CRITERIA En ine 1A-SA Satisfactory Document Package 2.Tor que values are in accordance with the TDI Instr uction Manual.3-4.5.Review of inspection report by Design Group Material.of the cam gear is AISI-4340 En ine 1B-SB Satisfactory Document Package 2.3.Torque values are in accordance with the TDI Instruction Manual.Review of inspection report by Design Group REFERENCES

~E l.gCI No.52 2.Approved Site NDE Procedures, TDI Instruction Manual SH1722/2

'Ltt"&T ,I COMPONENT UALITY REVALIDATION CHECKLIST REFERENCES (continued)

Page 3 of 4 02"02-350C 3-4.5.Approved Site NDE Procedures Approved Site NDE Proceudres, TER¹99-013 En ine 1B-SB 1.gCI No.52 2.3.Approved Site NDE Procedures, TDI Instruction Manual Approved Site NDE Procedures DOCUMENTATION RE VIREO1.Document Summary Sheet 2-5.Inspection Report En ine 18-SB 1.Document Summary Sheet 2-3.Inspection Report GROUP CHAIRPERSON PROGRAM MANAGER COMPONENT REVIEW En ine lA-SA No EDGCTS site experience documents are in evidence.2" 3.4.5.No inspecti on report has'een recei ved which f ul f i 1 l s thi s requirement.

A hardness test was performed on both cam gears.The results were reported by TER¹02-015.A material comparator test was used to determine the material of both cam gears.The results were reported by TER¹02-015.SH1722/3

COMPONENT UALITY REVALIDATION CHECKLIST COMPONENT REVIEW (continued)

En ine 1B-SB 1.No EDGCTS site experience documents are in evidence.Page 4 of 4 02-02-350C 2.No inspection report has been received which fulfills this requirement.

3.A visual inspection was performed on both the right and left cam gears.Results were reported by TER¹02-041.Note: a)A hardness test was performed on the right and left cam gears.Results were reported by TER¹02-061.b)A Material Comparator test was performed on the right and left cam gears.This was reported by TER¹02-061.RESULTS AND CONCLUSION En ine 1A-SA The equality Revalidation effort with respect to this component, as out-lined above, is complete.The results have been forwarded to the Design Review Group for their evaluation and conclusions in support of the final report.Same as Engine 1A-SA GROUP CHAIRPERSON PROGRAM MANAGER~C.I SH1722/4 COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Page 1 of 2 COMPONENT Subcover UTILITY Carolina Power 8 Li ht Com an GROUP PARTS LIST NO.02-362A TASK DESCRIPTION NO.DR-02-02-362A-1 SNPS GPL NO.03-362A CLASSIFICATION TYPE 8 TASK DESCRIPTIONS Design review for this component is not required based on the review of applicable industry and site experience and the lead engine DR/gR reports (Shoreham and Comanche Peak).There are no modification recommendations for this component.

A visual inspection on the web area of the subcover assembly was performed to examine for indications of cracking (four per engine).The results were satisfactory and were reported by TER 02-018, 02"045.The following equality Revalidation inspections are recommended to assure component quality and apply to both engines:~Perform a liquid penetrant test on all the remaining subcovers on the machined surfaces of the rocker shaft assembly bolt boss (pedestal) for evidence of linear indications (These inspection have been performed on four subcovers for engine 18-SB with satisfactory results as reported on TER¹02-088).guality inspections conducted at Catawba and Comanche Peak identified several cracked subcover pedestals.

The majority of cracked pedestals were located near the intermediate rocker arm assembly.The pedestals here are counterbored 1/2 inch deep to accept hollow dowels (bushings) that keep the rocker arm shafts from moving laterally under the loads generated by the connector pushrods.The reported pedestals each had a tight crack running down through the web between the counterbore and the machined surface.This type of cracking could be initiated by improper disassembly/assembly of the rocker shaft or an excessive interference fit between the rocker shaft dowel and the subcover pedestal counterbore (TDI drawings specify a clearance of.000 to.0015 inch).Metallurgical examination indicates that the crack, once initiated, may propagate by fatigue.Although there is no documentation of engine failure directly attributed to cracked subcover pedestals, cracks that extend into the threaded portion of the hole for the rocker arm capscrews could cause a decrease in bolt torque.To prevent this possibility, the following inspection is recommended:

SH2105/1 REV 1

COMPONENT DESIGN REVIEW CHECKLIST TASK DESCRIPTION (continued)

Page 2 of 2 DR-02-02"362A-0 Perform a liquid penetrant test on the top and vertical machined surfaces of the subcover pedestals (connector pushrod side only)for signs of cracking at the counterbores.

Note-This inspection is to be performed in conjunction with the rocker arm bushing inspections when the rocker arm shafts are removed from the subcovers.

Subcovers with pedestal cracks that extend through the counterbore web down to the threads should be replaced.This inspection should be performed at major engine overhauls (5 years).PRIMARY FUNCTION Not required ATTRIBUTE TO BE VERIFIED Not required SPECIFIED STANDARDS Not required REFERENCES Not required DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGER C%A~SH2105/2 COMPONENT UALITY REVALIDATION CHECKLIST Page 1 of 3 02-02-362A Cylinders Head Covers COMPONENT Subcover Assembl GPL NO.02-362A SNPS GPL NO.03"362A Carolina Power&Light Shearon Harris Nuclear UTIILITY Power Plant-Unit 1 REV.NO.2 TASK DESCRIPTIONS A-A l.Assemble and'review existing documentation.

2.Perform a visual inspection on the web area of the subcover assembly and examine for indications of cracking (four per engine).3.Perform a Liquid Penetrant test of the subcovers on the machined surfaces in the rocker shaft assembly bolt boss area[vertical and top machined surfaces]for evidence of linear indications.

En ine 1B-SB Same as Engine 1A-SA ATTRIBUTES TO BE VERIFIED 1.guality status of Component Document Package 2.Structural integrity of the subcovers 3.Evidence of linear indications in the bolt boss area Same as Engine 1A-SA SH1727/1 COMPONENT UALITY REVALIDATION CHECKLIST Page 2 of 3 02-02-362A ACCEPTANCE CRITERIA En ine 1A-SA 1.Satisfactory Document Package 2-3.Review of inspection report by the Design Group Same as Engine lA-SA REFERENCES En ine 1A-SA 1.(CI No.52 2-3.Approved Site NDE Procedures En ine 1B-SB Same as Engine lA-SA DOCUMENTATION RE VIREO~*1.Document Summary Sheet 2-3.Inspection Report En ine 1B-SB Same as Engine 1A-SA GROUP CHAIRPERSON PROGRAM MANAGER C V(~COMPONENT REVIEW 1.No EDGCTS site experience documents are in evidence.SH1727/2 i

COMPONENT UALITY REVALIDATION CHECKLIST Page 3 of 3 02-02-362A COMPONENT REVIEW (continued) 2.A visual inspection was per formed on subcovers 3R, 3L, 6R and 6L with satisfactory results.This was reported by TER¹02-018.3.No inspection report has been received which fulfills this requirement.

En ine 1B-SB 1.No EDGCTS site experience documents are in evidence.2.A visual inspection was performed on subcovers 3R, 3L, 6R and 6L with satisfactory results.This was reported by TER¹02-045.3.A Liquid Penetrant test was performed on subcovers 3L, 6L, 3R, and 6R with satisfactory results.This was reported by TER¹02-088.RESULTS AND CONCLUSION En ine 1A-SA The guality Revalidation effort with respect to this component, as outlined above, is complete.The results have been forwarded to the Design Review Group for their evaluation and conclusions in support of the final report.Same as Engine 1A-SA GROUP CHAIRPERSON c PROGRAM MANAGER.C.SH1727/3 8

Page 1 of 2 COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT" UNIT 1 Rocker Shaft Assemblies:

Intake/Intermediate COMPONENT 8 Exhaust UTILITY Carolina Power 8 Li ht Com an GROUP PARTS LIST NO.02-390A&B TASK DESCRIPTION NO.DR" 02-02-390A8(B-0 SNPS GPL NO.03"390A8B CLASSIFICATION TYPE TASK DESCRIPTIONS Design review for this component is not required based on the following:

A review of the Comanche Peak and Shoreham (lead engines)DR/gR Reports which establish the acceptability of the rocker shaft assemblies for their intended purpose.~A review of nuclear and non-nuclear industry experience listed in the EDG Component Tracking System indicated there had been no design related failures associated with this component.

There is no re-ported site experience in the EDG Component Tracking System.Visual inspections performed on Engines lA and 1B identified several pushrod sockets that did not meet the acceptance criteria because of minor irregularities and were dispositioned by CP8L as acceptable.

guality inspection performed at other sites also found cracked or chipped sockets and swivel pads, but they did not seriously impair engine operation.

Hardness and material comparator tests on the rocker arm shafts for Engine lA verified proper material specifications but hardness tests on Engine 1B indicated all eight of the rocker arm shafts tested were too soft (220 average Brinell hardness vs.specifications of 260-331).The comparator tests indicate proper material for these shafts and the hardness readings are thought to be incorrect.

However, to assure proper component quality and performance, it is recommended that the hardness tests be repeated for these shafts.There are no maintenance or modification recommendations for this component.

PRIMARY FUNCTION Not required SH2386/1 8 kW i 0 COMPONENT DESIGN REVIEW CHECKLIST ATTRIBUTE TO BE VERIFIED Not required Page 2 of 2 DR"02-02-390A&B-0 SPECIFIED STANDARDS Not required REFERENCES Not required DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGER SH2386/2 4

Page 1 of 3 02"02-390A COMPONENT UALITY REVALIDATION CHECKLIST Rocker Arms 8 Pushrods-Intake and Intermediate COMPONENT Rocker Shaft Assembl Carolina Power 8 Light Shearon Harris Nuclear UTILITY Power Plant-Unit 1 GPL NO.02-390A REV.NO.2 SNPS GPL NO~03-390A TASK DESCRIPTIONS 1.Assemble and review existing documentation.

2.Perform a visual inspection of the intake and intermediate rocker arm assembly for signs of distress, linear indications and chipped pieces , in the outer lips of the pushrod cups.3.'etermine the material of one intake and intermediate rocker arm shaft.1.Assemble and review existing documentation.

2.Perform a visual inspection of the intake and intermediate rocker arm assembly for signs of distress, linear indications, and chipped pieces in the outer lips of the pushrod cups.ATTRIBUTES TO BE VERIFIED En ine lA-SA l.guality status of Component Document Package 2.Surface integrity of the rocker arm assembly 3.Material of rocker arm shafts l.guality status of Component Document Package 2.Surface integrity of the rocker arm assembly SH1719/1 C OMPONENT UALITY REVALIDATION CHECKLIST Page 2 of 3 02"02-390A ACCEPTANCE CRITERIA 1.Satisfactory Document Package 2.No linear indications/chipped pieces in the outer lips of the pushrod CUPS 3.Mater ial to be AISI-4142 1.Satisfactory Document Package 2.No linear indications/chipped pieces in the outer lips of the pushrod CUPS.REFERENCES En ine lA-SA 1.(CI No.52 2-3.Approved Site NDE Procedures En ine 1B-SB 1.gCI No.52 2.Approved Site NDE Procedures DOCUMENTATION RE UIRED 1.Document Summary Sheet 2-3.Inspection Report En ine 1B-SB l.Document Summary Sheet 2.Inspection R port GROUP CHAIRPERSON PROGRAM MANAGER SH1719/2

%4 COMPONENT UALITY REVALIDATION CHECKLIST Page 3 of 3 02"02-390A COMPONENT REVIEW 1.No EDGCTS site experience documents are in evidence.2.A visual inspection was performed on various intake and intermediate rocker arm assemblies with various irregularities noted.The results were reported by TER¹02-020.3.Material comparator and hardness tests were performed on four intake rocker arm shafts.The results were reported by TER¹02-020.1.No EDGCTS site experience documents are in evidence 2.A visual inspection was performed on the intake and intermediate rocker arm assemblies with various irregularities noted.The results were reported by TER¹02-067.Note: a)A hardness test was performed on four rocker arm shafts.The results were reported by TER¹02-067.b)A material comparator test was performed on four rocker arm shafts.Results were reported by TER¹02-067.RESULTS AND CONCLUSION En ine 1A-SA The guality Revalidation effort with respect to this component, as out-lined above, is complete.The results have been forwarded to the Design Review Group for their evaluation and conclusions in support of the final report.Same as Engine 1A-SA GROUP CHAIRPERSON

/~c'c4:fiz PROGRAM MANAGER C i SH1719/3 Page 1 of 2 COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Rocker Shaft Assemblies:

Intake/Intermediate COMPONENT 8 Exhaust UTILITY Carolina Power 8 Li ht Com an GROUP PARTS LIST NO.02-390ALB TASK DESCRIPTION NO.DR" 02-02-390'(B-0 SNPS GPL NO.03-390A8B CLASSIFICATION TYPE TASK DESCRIPTIONS Design review for this component is not required based on the following:

A review of the Comanche Peak and Shoreham (lead engines)DR/gR Reports which establish the acceptability of the rocker shaft assemblies for their intended purpose.~A review of nuclear and non-nuclear industry experience listed in the EDG Component Tracking System indicated there had been no design related failures associated with this component.

There is no re-ported site experience in the EDG Component Tracking System.Visual inspections performed on Engines lA and 1B identified several pushrod sockets that did not meet the acceptance criteria because of minor irregularities and were dispositioned by CP&L as acceptable.

guality inspection performed at other sites also found cracked or chipped sockets and swivel pads, but they did not seriously impair engine operation.

Hardness and material comparator tests on the rocker arm shafts for Engine 1A verified proper material specifications but hardness tests on Engine 1B indicated all eight of the rocker arm shafts tested were too soft (220 average Brinell hardness vs.specifications of 260-331).The comparator tests indicate proper material for these shafts and the hardness readings are thought to be incorrect.

However, to assure proper component quality and performance, it is recommended that the hardness tests be repeated for these shafts.There are no maintenance or modification recommendations for this component.

PRIMARY FUNCTION Not required SH2386/1

COMPONENT DESIGN REVIEW CHECKLIST ATTRIBUTE TO BE VERIFIED Not required Page 2 of 2 DR-02-02-390A&B"0 SPECIFIED STANDARDS Not required--REFERENCES Not required DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGER SH2386/2

Page 1 of 4 02-02-390B COMPONENT UALITY REVALIDATION CHECKLIST Rocker Arms&Pushrods-Exhaust Rocker COMPONENT Shaft Assembl Carolina Power 8 Light Shearon Harris Nuclear UTIILITY Power Plant-Unit 1 GPL NO.02-390B SNPS GPL NO.03-390B REV.NO.2 TASK DESCRIPTIONS 1.Assemble and review existing documentation.

2.Perform a visual inspection of the intake and intermediate rocker arm assemblies for signs of distress, linear indications, and chipped pieces in the outer lips of the pushrod cups.3.Determine the material of one rocker arm shaft.En ine 1B-SB 1.Assemble and review existing documentation.

2.Perform a visual inspection of the intake and intermediate rocker arm assemblies for signs of distress, linear indications, and chipped pieces in the outer lips of the pushrod cups.ATTRIBUTES TO BE VERIFIED l.guality status of Component Document Package 2.Surface integrity of the rocker arm assembly 3.Material of rocker arm shaft SH1720/1

COMPONENT UALITY REVALIDATION CHECKLIST Page 2 of 4 02-02-390B ATTRIBUTES TO BE VERIFIED (continued)

En ine 1B-SB 1.guality status of Component Document Package 2.Surface integrity of the rocker arm assemblies ACCEPTANCE CRITERIA 1.Sati s factory Document Package 2.No linear indications/chipped pieces in the outer lips of the pushrod CUPS.3.Material to be AISI-4142 1.Satisfactory Document Package 2.No linear indications/chipped pieces in the outer lips of the pushrod CUPS.REFERENCES 1.(CI No.52 2-3.Approved Site NDE Procedures En ine 1B-SB 1.(CI No.52 2.Approved Site NDE Procedures SH1720/2 COMPONENT UALITY REVALIDATION CHECKLIST Page 3 of 4 02"02-390B DOCUMENTATION RE UIRED En ine 1A-SA 1.Document Summary Sheet 2-3.Inspection Report 1.Document Summary Sheet 2.Inspection Report GROUP CHAIRPERSON PROGRAM MANAGE COMPONENT REVIEW 1.No EDGCTS site experience documents are in evidence.2.A visual inspection was performed on the exhaust rocker arm assemblies with various irregularites noted.The results were reported by TER¹02-021.3.Material comparator and hardness tests were performed on four of-the exhaust rocker arm shafts.The results were reported by TER¹02-021.1.No EDGCTS site experience documents are in evidence.2.A visual inspection was performed on the exhaust rocker arm assemblies with various irregularities noted.The results were reported by TER¹02-068.Note: a)A hardness test was performed on four of the exhaust rocker arm shafts.The results were reported by TER¹02-068.b)A material comparator test was performed on four of the rocker arm shafts.This was reported by TER¹02-068.SH1720/3 COMPONENT UALITY REVALIDATION CHECKLIST Page 4 of 4 02"02-390B RESULTS AND CONCLUSION En ine 1A-SA The equality Revalidation effort with respect to this component, as out-lined above, is complete.The results have been forwarded to the Design Review Group for their evaluation and conclusions in support of the final report.En ine 1B-SB Same as Engine 1A-SA GROUP CHAIRPERSON 44 f'<PROGRAM MANAGER~~K~SH1720/4 e

COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT" UNIT 1 Page 1 of 2 COMPONENT Main and Connector Pushrods UTILITY Carolina Power and Li ht Co.GROUP PARTS LIST NO.02-390C8(D SNPS GPL NO.03-390CKD TASK DESCRIPTION NO.DR-02-02-390C&D-1 CLASSIFICATION TYPE B TASK DESCRIPTIONS Design review for this component is not required based on the following:

A review of the Comanche Peak and Shoreham DR/gR Reports, which establishes the acceptability of the friction welded pushrods for their intended purpose.A review of the nuclear and non-nuclear industry experience listed in the Component Tracking System indicated that there had been no design related failures associated with friction welded pushrods.There are no modification or maintenance recommendations for this component.

4 All guality inspection have been performed and found satisfactory.

For future purchases of pushrods, it is recommended that the purchase order specify destructive verification of weld quality by sectioning random samples from each manufacturing lot.PRIMARY FUNCTION Not required ATTRIBUTE TO BE VERIFIED Not required SH2090/1 COMPONENT DESIGN REVIEW CHECKLIST SPECIFIED STANDARDS Not required Page 2 of 2 DR-02-02-390C&D-1 REFERENCES Not required DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGER~H SH2090/2 COMPONENT UALITY REVALIDATION CHECKLIST Page 1 of 3 02-02-390C&D Carolina Power&Light Rocker Arms&Pushrods: Shearon Harris Nuclear COMPONENT Pushrods-Main and Connector UTILITY Power Plant-Unit 1 GPL NO.02-390C&D SNPS GPL NO.03"390C&D REV.NO.4 TASK DESCRIPTIONS 1.2.3.Assemble and review existing documentation.

Verify that the main and connector pushrods are friction welded.Perform a Liquid Penetrant or Magnetic Particle test on all main and connector pushrods.If the above NDE inspections cannot be per-formed, a visual inspection is acceptable if the surface is thorough-ly cleaned to remove any coatings or deposits.En ine 1B-SB Same as Engine 1A-SA ATTRIBUTES TO BE VERIFIED En ine 1A-SA l.equality status of Component Document Package 2.Main and connector pushrods are friction welded.3.Surface integrity of all main and connector pushrods.En ine 1B-SB Same as Engine lA-SA ACCEPTANCE CRITERIA En ine 1A-SA 1.Satisfactory Document Package SH1940/1 COMPONENT UALITY REVALIDATION CHECKLIST Page 2 of 3 02-02-390C8(D ACCEPTANCE CRITERIA (continued)

~Ei-A (2.Main and connector pushrods are friction welded.3.No surface cracks allowed along the bond line between the rod end and the tube.'ame as Engine lA-SA REFERENCES En ine 1A-SA 1.gCI No.52 2.Approved Site NDE Procedures 3.Approved site NDE Procedures, TERS99-017, TERS99-035 Same as Engine lA-SA DOCUMENTATION RE UIRED En ine lA-SA 1.Document Summary Sheet 2-3.Inspection Report En ine 1B-SB Same as Engine lA-A'7/GROUP CHAIRPERSON

/PROGRAM MANAGER~h4 COMPONENT REVIEW En ine 1A-SA 1.No EDGCTS site experience documents are in evidence.SH1940/2 COMPONENT UALITY REVALIDAT ION CHECKLIST COMPONENT REVIEM (continued)

En ine lA-SA Page 3 of 3 02-02"390CLD 2.Friction welded pushrods, were installed as verified through a visual inspection.

This was reported by TERS 02"101.3.A Magnetic Particle test was performed on all main and connector pushrods with no indications found.This was reported by TERS02-101.1.No EDGCTS site experience documents are in evidence.2.Friction welded pushrods were installed as verified during a visual inspection.

This was reported by TERS02-078.3.A Magnetic Particle test was performed on all main and connector pushrods with no indications found.This was reported by TERS 02"101.RESULTS AND CONCLUSION The guality Revalidation effort with respect to this component, as outlined above, is complete.The results have been forwarded to the Design Review Group for their evaluation and conclusions in support of the final report.En ine 1B-SB GROUP'CHAIRPERSON PROGRAM MANAGER DC&SH1940/3 TDI OWNERS GROUP fol SHEARON HARRIS NUCLEAR POWER PLANT Rocker Arms and Pushrods: Pushrods Connector COMPONENT PART NO.: 02-39OD See Component Part No.02-390C Page 1 of 2 COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR PLANT" UNIT 1 Rocker Arms&COMPONENT Pushrods:Bushin s GROUP PARTS LIST NO.02-390E SNPS GPL NO.03-390E UTILITY Carolina Power&Li ht Com an TASK DESCRIPTION NO.DR-05-02-390E-1 CLASSIFICATION TYPE B TASK DESCRIPTIONS Design review for this component is not required based on the following:

~A review of the Comanche Peak and Shoreham DR/gR Reports which establishes the acceptability of the bushings for their intended purpose.The applicable engine dimensions and operating parameters at Shearon Harris are identical or very similar to those for the same component at Comanche Peak (Lead Engine).~A review of the Component Tracking System indicated that there was no site experience and no significant applicable nuclear or non-nuclear industry experience.

Maintenance recommendations based on the Comanche Peak DR/gR Report to ensure proper performance under normal conditions are as follows:~Visually inspect and measure the intake, intermediate, and exhaust rocker arm bushings.The periods of engine operation to wear the bushings from an initial clearance of 0.0045 inch (diametral) to 0.010 inch (value at which bushings should be replaced)were calculated to be: 2300 hour0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br />s-Intake, 730 hour0.00845 days <br />0.203 hours <br />0.00121 weeks <br />2.77765e-4 months <br />s-Intermediate, and 1300 hour0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br />s-Exhaust.It is recom-mended that an inspection be conducted at the fuel outage which precedes the applicable number of engine hours of operation by at least the sum of the expected hours of operation in a LOOP/LOCA event plus the expected hours of operation between outages.The inspection schedule may be revised after the first or subsequent inspections if the inspection results justify a longer period of engine operation between inspections.

No guality revalidation is required for this component.

No modifications are recommended for this component.

PRIMARY FUNCTION Not required SH2085/1 REV.I COMPONENT DESIGN REVIEW CHECKLIST ATTRIBUTE TO BE VERIFIED Not required Page 2 of 2 DR"02-02-390E"0 SPECIFIED STANDARDS Not required REFERENCES Not requiredDOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGER SH2085/2 COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Page 1 of 2 Rocker Arms and Pushrods-COMPONENT Misc.Bolts and Drive Studs UTILITY Carolina Power 8 Li ht Com an GROUP PARTS LIST NO.02-390F SNPS GPL NO.03-390G TASK-DESCRIPTION NO.DR-02-02-390F-0 CLASSIFICATION TYPE B TASK DESCRIPTIONS Design review for this component is not required based on the applicable industry experience, the Phase I report, and the lead engine DR/gR report (Comanche Peak).There is no site experience in the EDG Component Tracking System for this component.

The industry experience of rocker arm bolt failures has been attributed to insufficient preloading.

The maintenance recommendations for this component are as follows:~Verify that the proper torque is applied to the rocker arm hold down bolts (365 ft-lbs).~Verify that the rocker arm drive studs are tight and intact.These inspections should be performed at each outage.There are no modification recommendations for this component.

equality inspections performed to date have been reviewed and found satisfactory.

The following quality inspections should be performed on Engine 1A-SA: Perform a magnetic particle test on the thread root area of all capscrews for linear indications; Verify that the proper torque loads are applied to the rockerarm capscrews by either reviewing existing documentation or performing a physical inspection.

SH2190/1 COMPONENT DESIGN REVIEW CHECKLIST Page 2 of 2 DR-02-02-390F" 0 The following quality inspections should be performed on Engine 1B-SB:~Verify that the proper torque loads are applied to the rockerarm capscrews by either reviewing existing documentation or performing a physical inspection.

PRIMARY FUNCTION Not required ATTRIBUTE TO BE VERIFIED Not required SPECIFIED STANDARDS Not required REFERENCES Not required DOCUMENTATION RE UI RED Not required GROUP CHAIRPERSON ROGRAM MANAGER CH SH2190/2 COMPONENT UALITY REVALI DATION CHECKLIST Page 1 of 4 02"02"390F Rocker Arms 8 Pushrods-COMPONENT Misc.Bolts&Drive studs GPL NO.02-390F SNPS GPL NO.03-390F Carolina Power 8 Light Shearon Harris Nuclear UTILITY Power Plant-Unit 1 REV.NO.2 TASK DESCRIPTIONS 2.Assemble and review existing documentation Perform a Magnetic Particle test on the thread root area of all capscrews for linear indications.

3.Perform a visual inspection on the drive studs for signs of i rregul ari ty..4.Verify that the proper torque loads are applied to the rocker arm capscrews by reviewing existing documentation.

5.Determine the material of four bolts.6.Determine the hardness of four bolts.~E Same as Engine 1A-SA ATTRIBUTES TO BE VERIFIED 1.guality status of Component Document Package 2.Surface integrity of the thread root area of all capscrews 3.Surface integrity of the drive studs 4.Proper torque loads are applied.SH1723/1 COMPONENT UALITY REVALIDATION CHECKLIST ATTRIBUTES TO BE VERIFIED (continued)

Page 2 of 4 02-02-390F 5.Material of capscrews 6.Hardness of capscrews~E Same as Engine lA-SA ACCEPTANCE CRITERIA 1.Satisfactory Document Package~2.No linear indications in the thread root area of the capscrews 3.No movement of the drive stud in the rocker arm 4.Torque loads are in accordance with the TDI Instruction Manual.5-6.Material is AISI 4140.Same as Engine lA-SA REFERENCES 1.(CI No.52 2-3.Approved Site NDE Procedures 4.TDI Instruction Manual 5-6.Approved Site NDE Procedures En ine 1B-SB Same as Engine 1A-SA SH1723/2

COMPONENT UALITY REVALIDATION CHECKLIST DOCUMENTATION RE UIRED Page 3 of 4 02-02"390F En ine 1A-SA 1.Document Summary Sheet 2-6.Inspection Report En ine 1B-SB Same as Engine 1A-SA GROUP CHAIRPERSON PROGRAM MANAGER CN+~~'OMPONENT REVIEW En ine lA-SA 1.No EDGCTS site experience documents are in evidence.2.No inspection report has been received which fulfills this requirement.

'I 3.No movement was detected in any of the drive studs on all of the rocker arms assemblies.

This was reported by TER¹02-035.4.No inspection report has been received which fulfills this requirement.

5.A material compara'tor test was performed on the capscrews from four cylinders.

Results were reported by TER¹02-027.6.A hardness test was performed on the capscrews from four cylinders.

Results were reported by TER¹02-027.En ine 1B-SB 1.No EDGCTS site experience documents are in evidence.2.A Magnetic Particle test was performed on the capscrews of cylinders 3L, 6L, 3R and 6R with satisfactory results.This was reported by TER¹02-083.3.No movement was detected in any of the drive studs on all of the rocker arm assemblies.

This was reported by TER¹02-047.4.No inspection report has been received which fulfills this requirement.

SH1723/3 COMPONENT UALITY REVALIDATION CHECKLIST Page 4 of 4 02-02-390F 5.A material comparator test was performed on the capscrews from four cylinders with satisfactory results.This was reported by TER¹02-069.6.A hardness test was performed on the capscrews from four cylinders.

Results were reported by TER¹02-069.RESULTS AND CONCLUSION En ine 1A-SA The equality Revalidation effort with respect to this component, as out-'-'ined above, is=-complete.

The results have been forwarded to the Design Review Group for their evaluation and conclusions in support of the final report.En ine 1B-SB Same as Engine 1A-SA GROUP CHAIRPERSON PROGRAM MANAGER 5C-Kcxsi~~-

p.~SH1723/4

COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Page 1 of 2 Front Gearcase: COMPONENT Boltin and Gasket GROUP PARTS LIST NO.02-335B SNPS GPL NO.03"335B UTILITY Carolina Power 8 Li ht Com an TASK DESCRIPTION NO.DR-02" 02-335B-1 CLASSIFICATION TYPE TASK DESCRIPTIONS Design review for this component is not required based on the following:

A review of the EDG Component Tracking System indicated no significant applicable industry and/or site experience.

~A review of the lead engine DR/gR reports (Shoreham/Comanche Peak).~The Shearon Harris gearcase and bolting are the same as that used at Comanche Peak.The Comanche Peak bolting was found acceptable in the Comanche Peak design review.There are no special maintenance requirements identified in the lead engine report, however, a gC inspection of the bolts at Shearon Harris (CP8 L NCR 84-1777)showed two bolts internal to the gearcase that were not evident on the parts manual drawing.These two bolts are part of the perimeter bolt pattern that attaches the cover to the block but are internal and must be accessed by removing a cover plate or the Governor supporting assembly.These bolts must be torqued the same as the other bolts.The CP8L inspection found that no positive means of locking was provided.Considering the damage these bolts could cause if they loosen, it is recommended that these bolts be inspected, positive locking features (bent tab or lockwire)be added, and then be properly torqued in accordance with the TDI Manual.The following guality inspection is recommended to be performed:

Verify bolting installation and torque.PRIMARY FUNCTION Not required ATTRIBUTE TO BE VERIFIED Not required SH2556/1 REV.I SPECIFIED STANDARDS Not required COMPONENT DESIGN REVIEW CHECKLIST Page 2 of 2 DR" 02-02-335B" 0 REFERENCES Not required DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGER SH2556/2

COMPONENT UALITY REVALIDATION CHECKLIST Page 1 of 1 02"02"335B Front Gear Case COMPONENT Gasket and Boltin GPL NO.02-335B SNPS GPL NO.03-335B Carolina Power 8 Light Shearon Harris Nuclear UTILITY Power Plant-Unit 1 REV.NO.2 TASK DESCRIPTIONS No further review of component 02-335B i s required for the fol l owing reasons: a)Component was reviewed on two lead engines with satisfactory results.b)There is no industry or site experience reported for this component.

c)Type C component-Failure has little bearing on the effective use or operation of D.G.GROUP CHAIRPERSON PROGRAM MANAGERSH1912/1 COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Page 1 of 3 COMPONENT Gear Train Assembl UTILITY Carolina Power 8 Li ht Co.DR"02-02"350C-0 02-350C DR-02-02-355A-0 GROUP PARTS LIST NO.02-355A 02" 355B TASK DESCRIPTION NO.DR-02-02-355B-0 03"350C SNPS GPL NO.03-355A 03-355B CLASSIFICATION TYPE ATASK DESCRIPTIONS Design review is not required for this component based on the lead engine DR/gR report (Comanche Peak)which established the acceptability of the gear train assembly.The component parts which are considered in this review are the same, except for the inlet and exhaust cams and a longer roll pin.Also, differences in the crankshaft/flywheel/generator shaft assembly have been considered, as they affect gear tooth loads.Resulting changes sn gear tooth loads caused by the above differences are determined to be insignificant.

A review of the EDG Component Tracking System indicates no significant site or industry experience.

The following maintenance recommendations are made to ensure reliability of the components:

02-350C Camshaft-Su orts Boltin and Gears:~The number of No.9167 bolts, torqued at 70 (-20,+20)ft lbf, should be increased from 4 to 6.OR The initial torque in the four No.9167 bolts which connect the cam gear to the cam hub should be increased to 80 (-0+10)ft-lbf.In addition, the above discussion is based upon the assumption that it is possible to line up the cotter pin with the hole in the bolt within the prescribed torque range.If the cam gear and hub are disassembled and reassembled it is recommended that the nut be re-locked at a position within the prescribed torque range.Inser-.tion of the cotter pin must be accomplished at a torque greater than 50 ft-lbf and less than 90 ft-lbf for the 6-bolt arrangement, and at a torque greater than 80 ft-lbf and less than 90 ft-lbf for the 4-bolt arrangement.

If insertion is not possible, another bolt and/or nut and/or washer should be used.SH2385/1 COMPONENT DESIGN REVIEW CHECKLIST Page 2 of 3 DR-02-02-350C-0 DR-02"02-355A-0.DR-02"02"355B"0 TASK DESCRIPTIONS (continued)

~The surveillance maintenance/inspection procedures should be modified to inspect the cam gear at every refueling outage.02-355A Idler Gear Assembl-Crank to Pum Gear:~The crank to pump gear should be inspected during each refueling-outage...

The inspection should be directed at potential pitting.Any abnormal indications or progressive pitting should be reported for an engineering evaluation.

02-355B Idler Gear Assembl~The idler gear and especially the jacket water pump gear should be inspected at all scheduled fuel outages, with any progressive pitting being reported for an engineering evaluation.

A photographic record of these inspections should be maintained at the site to assist in this evaluation.

F Note: If the idler gear and hub are disassembled and reassembled, it is recommended that the nut be relocked at a position within the prescribed torque range of 70 (-20,+20)ft-lbf.Insertion of the cotter pin must be accomplished at a torque greater than 50 ft"lbf and less that 90 ft-lbf.If this is not possible, another bolt and/or nut and/or washer should be used.There are no modification recommendations for this component.

guality inspections that have been conducted to date have been reviewed and are considered satisfactory.

It is recommended that the guality inspections listed below be performed:

02-350C Camshaft-Su orts Boltin and Gears:~Verify that the proper torque values are applied to the bolts (cam to cam gear)on Engines 1A-SA and 1B-SB.~Perform a visual inspection of the cam gear for Signs of wear, pitting or any other discontinuities on Engine 1A-SA.02-355A&B Idler Gear Assembl-Crank to Pum 8 Idler Gears:~Perform a visual inspection on the crank to pump gear set teeth and idler gear teeth for signs of wear, pitting, or any other discontinu-ities, on engine lA-SA.SH2385/2 PRIMARY FUNCTION Not required COMPONENT DESIGN REVIEW CHECKLIST Page 3 of 3 DR-02"02-350C"0 DR-02-02-355A-0 DR-02-02-355B-0 ATTRIBUTE TO BE VERIFIED Not required SPECIFIED STANDARDS Not required REFERENCES Not required DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGER SH2385/3 COMPONENT UALITY REVALIDATION CHECKLIST Page 1 of 4 02-02-355A 8L B Idler Gear Assembly-Crank COMPONENT to Pum Gear 5 Idler Gears GPL NO.02"355A 4 B SNPS GPL NO.03-35SA 8(B Carolina Power 8 Light Shearon Harris Nuclear UTILITY Power Plant-Unit 1 REV.NO.2 TASK DESCRIPTIONS En ine lA-SA l.Assemble and review existing documentation.

2.Perform a visual inspection on the crank to pump gear set teeth and idler gear teeth for signs of wear, pitting, or any other disconti-nuities.3~Determine the hardness of the crank to pump gear and idler gears.4.Determine the material of the crank to pump gear and idler gears.1.Assemble and review existing documentation.

2.Perform a visual inspection on the crank to pump gear set teeth and idler gear teeth for signs of wear, pitting, or any other discontinuities.

ATTRIBUTES TO BE VERIFIED En ine lA-SA 1.guality status of Component Document Package 2.Surface integrity of the crank to pump gear and idler gears 3.Hardness of the gear 4.Material of the gear SH1732/1 COMPONENT UALITY REVALIDATION CHECKLIST Page 2 of 4 02-02"355A 5 B ATTRIBUTES TO BE VERIFIED (continued)

En ine 1B-SB 1.guality status of Component Document Package 2.Surface integrity of the crank to pump gear and idler gears ACCEPTANCE CRITERIA 1.Satisfactory Document Package 2.Review of inspection report by Design Group 3.Hardness to be 380-405 Brinnel 4.a)Material to be AISI-4340-Idler Gear b)Material to be AISI-4130-Crank to Pump Gear 1.Satisfactory Document Package 2.Review of inspection report by Design Group REFERENCES En ine 1A-SA 1.gCI No.52 2-4.Approved Site NDE Procedures En ine 1B-SB l.gCI No.52 2.Approved Site NDE Procedures SH1732/2 COMPONENT UALITY REVALIDATION CHECKLIST Page 3 of 4 02"02"355A 8[B DOCUMENTATION RE UIRED 1.Document Summary Sheet 2-4.Inspection Report 1.Document Summary Sheet 2.Inspection Report GROUP CHAIRPERSON PROGRAM MANAGER COMPONENT REVIEM En ine 1A-SA 1.No EDGCTS site experience documents are in evidence.2.No inspection report has been received which fulfills this requirement.

3.A hardness test was performed on the left and right idler gears.The results were reported by TER¹02-026.In addition, a hardness test was performed on the crank to pump gear.The results were reported by TER¹02-025.A Material Comparator test was performed on the left and right idler gears.The results were reported by TER¹02-026.No inspection report has been received which verifies the material of the crank to pump gear.En ine 1B-SB 1.No EDGCTS site experience documents are in evidence.2.A visual inspection was performed on the crank to pump gear with satisfactory results as reported by TER¹s02-042 and 02-077.In addition, a visual inspection was performed on the right and left idler gears.Some scoring was in evidence on the left idler gear which was attributed to a foreign material.These results were reported by TER¹02-043.Note: a)A hardness test was performed on the crank to pump gear.The results were reported by TER¹02-063.SH1732/3 COMPONENT UALITY REVALIDATION CHECKLIST Page 4 of 4 02-02-355A 8I 8 COMPONENT REVIEW (continued) b)A Material Comparator test was performed on the left and right idler gears.The results were reported by TER¹02-062.c)A hardness test was performed on the left and right idler gears.The results were reported by TER¹02-062.RESULTS AND CONCLUSION The equality Revalidation effort with respect to this component, as outlined above, is complete.The results have been forwarded to the Design Review Group for their evaluation and conclusions in support of the final report.En ine 1B-SB Same as Engine lA-SA GROUP CHAIRPERSON,'

~IA PROGRAM MANAGER, SH1732/4 TDI OWNERS GROUP for SHEARON HARRIS NUCLEAR POWER PLANT Idler Gear Assembly: Idler Gear Assemb1y COMPONENT PART NO: 02-355B See Component Part No.02-350C 8 02-355A COMPONENT UALITY REVALIDATION CHECKLIST Page 1 of 3 02"02"355C Idler Gear Assembly-COMPONENT Bol tin and Gaskets GPL NO.02"355C SNPS GPL NO.03-355C Carolina Power 8 Light Shearon Harris Nuclear UTILITY Power Plant-Unit 1 REV.NO.2 TASK DESCRIPTIONS 1.Assemble and review existing documentation.

2.Visually inspect the bolting and gaskets for signs of distress.Same as Engine 1A-SA ATTRIBUTES TO BE VERIFIED 1.guality status of Component Document Package 2.Conditions of bolting and gaskets Same as Engine 1A-SA ACCEPTANCE CRITERIA1.Satisfactory Document Package 2.Review of inspection report by the Design Group SH1914/1 COMPONENT UALITY REVALIDATION CHECKLIST Page 2 of 3-02-02-355C ACCEPTANCE CRITERIA (continued)

En ine 1B-SB Same as Engine 1A-SA REFERENCES En ine 1A-SA 1.gCI No.52 2.Approved Site NDE Procedures Same as Engine 1A-SA DOCUMENTATION RE UIRED 1.Document Summary Sheet 2.Inspection Report Same as Engine-SA I GROUP CHAIRPERSON PROGRAM MANAGER-C Yi~~'COMPONENT REVIEW En ine 1A-SA 1.No EDGCTS site experience documents are in evidence.2.No inspection report has been received which fulfills this requirement.

SH1914/2 COMPONENT UALITY REVALIDATION CHECKLIST Page 3 of 3 02-02-355C COMPONENT REVIEW (continued)

En ine 1B-SB 1.No EDGCTS site experience documents are in evidence.2.The bolt heads were free from deformation and the bolt markings were identified.

The gaskets were inaccessible, however, there was no apparent leakage.This was reported by TER¹s02-044 and 089.Note: a)The bolt markings were reported by TER¹02-044.RESULTS AND CONCLUSION En ine 1A-SA The equality Revalidation effort with respect to this component, as outlined above, is complete.The results have been forwarded to the Design Review Group for their evaluation and conclusions in support of the final report.Same as Engine lA-SA GROUP CHAIRPERSON iclA k W~PROGRAM MANAGER.I'cpu~~"~SH1914/3 COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Page 1 of 2 I COMPONENT Fl heel GROUP PARTS LIST NO.02-330A SNPS GPL NO.03-330A UTILITY Carolina Power 8 Li ht Com an TASK DESCRIPTION NO: DR-02-02-330A-0 CLASSIFICATION TYPE A TASK DESCRIPTIONS Design review for this component is not required based on the following:

There is no relevant nuclear or non-nuclear experience listed in the Component Tracking System.The DR/gR report for Comanche Peak indicated a sufficiently large factor of safety for the flywheel to cover the larger diameter flywheel used at Shearon Harris (90 inch versus 68 inch).~~~~There are no maintenance or modification recommendations for this component.

guality Revalidation for this component is not required.PRIMARY FUNCTION Not required ATTRIBUTE TO BE VERIFIED Not required SPECIFIED STANDARDS Not required REFERENCES I Not required SH2088/1 DOCUMENTATION RE UIRED Not required COMPONENT DESIGN REVIEW CHECKLIST Page 2 of 2 DR"02"02-330A"0 GROUP CHAIRPERSON ROGRAM MANAGER C N~'SH2088/2

.COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Page 1 of 2 COMPONENT Fl heel-Boltin GROUP PARTS LIST NO.02-330B SNPS GPL NO.03-330B UTILITY Carolina Power 8 Li ht Com an TASK DESCRIPTION NO.DR" 05" 02-330B-0 CLASSIFICATION TYPE TASK DESCRIPTIONS Design review for this component is not required based on the review of the Comanche Peak lead engine DR/gR report, design information furnished in TDI Parts Manual Vol.II (Ref.2), and the EDG Component Tracking System for appli-cable industry and site exper ience (Refs.3 and 4).The Component Tracking System cited TDI Service Information Memo No.64H for an increase in torque load for the in-line engine flywheel bolts;the memo, however, does not apply to the V-16 engines and therefore has no impact on the Shearon Harris site.The flywheel assembly for Shearon Harris has the identical quantity (12)and part numbers (97253 and F-090-038 for bolt and nut, respectively), as well as bolt torque requirement (4,500 ft-lb)for the flywheel bolting components as those for the Comanche Peak Station (Ref.5).However, the design of the flywheels is different with the engine flywheels for the Shearon Harris site being considerably larger.At both Comanche Peak and Shearon Harris, the flywheel is assembled to the engine crankshaft flange and the generator flange with the mating surfaces lubricated with"anti-seize lubricant; the flywheel bolts are lubricated and fitted to the bolt-holes.

Assuming that the peak torque transient for all TDI V-16 engines does not vary significantly, the flywheel assembly procedure indicated results in a favorable ratio of the torque transmission capability over the peak torque transient.

Review of Comanche Peak DR/gR Report (Ref.1)further indicates that a large design margin exists, and that two, bolts would be adequate to carry the applied shear load from the peak transient torque.The flywheel bolting at Shearon Harris should therefore be adequate for its intended application.

There are no modification or maintenance recommendations for this component.

guality Revalidation is not required for the flywheel bolting.SH2457/1

PRIMARY FUNCTION Not required COMPONENT DESIGN REVIEW CHECKLIST Page 2 of 2 DR-02-02-330B"0 ATTRIBUTE TO BE VERIFIED Not required SPECIFIED STANDARDS Not required REFERENCES 1.Comanche Peak Steam Electric Station-Unit 1, DR/gR Report for Group Parts List No.02-330B 2.TDI Parts Manual, Volume II, for Model DSRV-16-4 Diesel Engine/Generator, Shearon Harris Nuclear Power Plant, Units 1, 2, 3, and 4, Parts List No.02-33-0-01-14 and Drawing No.02-330-01 3.Emergency Diesel Generator Component Tracking System-Nuclear and Non-Nuclear Industry Experience dated October 15, 1984 4.Emergency Diesel Generator Component Tracking System-Shearon Harris Nuclear Power Plant dated October 15, 1984 5.TDI Parts Manual, Volume II, for Model DSRV-16-4 Diesel Engine/Generator, Comanche Peak Power Station, Parts List 02-330-02-05 and Drawing No.101505 DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON ROGRAM MANAGER~C cC'SH2457/2 COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Page 1 of 2 Engine and Auxiliary Module Wiring Material and Fittings;Pyrometer Conduit Assembly Conduit, Fittings, COMPONENT and Su orts 02-688A 8 GROUP PARTS LIST NO.02"630A B C SNPS GPL NO.03-688A&03-630A B C UTILITY Carolina Power 5 Li ht Com an DR-02-02" 688A-0 TASK DESCRIPTION NO.DR-02"02"630A B C-0 CLASSIFICATION TYPE A TASK DESCRIPTIONS Design review for this component is not required based on the following:

~A review of the EDG Component Tracking System indicated that there was no significant applicable industry and/or site experience.

A review of the lead engine DR/gR report (Comanche Peak).A review of as-built sketches for the engines.~A review of Specification No.CAR-SH-E-ll, Rev.9 The detailed modifications listed in lead engine DR/gR report (Comanche Peak)are not applicable to Shearon Harris because of the differences in the conduit layout and conduit supports.However, based on past experience, it is recommended to perform an upgrade to tighten/fix, replace or add missing conduit supports as required.The results of analysis (Gale.Nos.11600.60/C5-11 and 11600.67/C5-13) using input from the design specification (Spec.No.CAR-SH-E-ll, Rev.9)and as-built sketches showed that supports are required for flexible conduits at two locations for both Engine lA and 1B and for rigid conduits at two locations for Engine 1A (Ref.Memo from A.Y.C.Wong to J.C.Kammeyer dated ll/08/84).

Ther e are no maintenance recommendations for this component.

guality revalidation is not required for this component.

PRIMARY FUNCTION Not required SH2442/1

COMPONENT DESIGN REVIEW CHECKLIST ATTRIBUTE TO BE VERIFIED Not required Page 2 of 2 DR"02"02-688A 8c DR"02 02-630A,B,C-O SPECIFIED STANDARDS Not required REFERENCES Not required DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGER~C Ma.~~~SH2442/2

TDI OWNERS GROUP for SHEARON HARRIS NUCLEAR POWER PLANT Pyrometer Conduit Assembly: Conduit Fittings COMPONENT PART NO.: OP 63OB See Component Part No.O2-63OA TDI OWNERS GROUP for SHEARON HARRIS NUCLEAR POWER PLANT Pyrometer Conduit Assembly: Support COMPONENT PART NO: 02-630C See Component Part No.02-630A COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR STATION-UNIT 1 Page 1 of 2 Pyrometer Conduit Assembly COMPONENT Thermocou les GROUP PARTS LIST NO.02"630D UTILITY Carolina Power 8 Li ht TASK DESCRIPTION NO.DR-02-02" 630D-O SNPS GPL NO.03"630D CLASSIFICATION TYPE B TASK DESCRIPTIONS Design review for this component is not required based on the following A review of the lead engine (SNPS), which establishes the acceptability of the thermocouple for its intended purpose.A review of the Component Tracking System indicates that there was no significant applicable site, nuclear or non-nuclear experience.

The applicable engine dimensions and operating parameters at Shearon Harris are identical or very similar to those for the same component at Shoreham.Maintenance recommendations, based on the SNPS DR/gR report, to ensure proper performance of the thermocouples during normal operation are as follows~Check that each thermocouple's indicated temperature is consistent with the engine s ambient temperature when the engine is cold.Any inconsistent reading traced to the thermocouple should result in replacement of the thermocouple.

This is to be conducted during each refueling outage.Remove, clean and inspect each thermocouple and thermocouple shield for indications of fatigue.Any indications of fatigue should result in replacement of the thermocouple and/or thermocouple shield.This will be conducted during alternate refueling outages.guality Revalidation is not required for this component.

There are no modification recommendations for this component.

SH1977/1 l E~rw n

'RIMARY FUNCTION Not required COMPONENT DESIGN REVIEW CHECKLIST Page 2 of 2 DR"02-02-630D-O ATTRIBUTE TO BE VERIFIED Not required SPECIFIED STANDARDS Not required REFERENCES Not required DOCUMENTATION RE UI RED Not required GROUP CHAIRPERSON PROGRAM MANAGER 4k'I is v~SH1977/2 TDI OWNERS GROUP fol SHEARON HARRIS NUCLEAR POWER PLANT Engine 5 Aux Module Wiring Material-Conduit 5 Fittings;Pyrometer Assembly-Conduit, Fitting, Supports COMPONENT PART NO.: 02-688A See Component Part No.02-630C COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT" UNIT 1 Page 1 of 2 Engine 8 Auxiliary Module Wiring Mat'1: COMPONENT Wirin 8 Terminations GROUP PARTS LIST NO~02-688B SNPS GPL NO.03-688B UTILITY Carolina Power 8 Li ht Com an TASK DESCRIPTION NO.DR-02" 02-688B-0 CLASSIFICATION TYPE A TASK DESCRIPTIONS Design review for this component is not required based on the following:

~A review of the lead engine DR/gR report for Shoreham and Comanche Peak.~A review of the Phase I Report for this component (see References).

~A review of the EDG Component Tracking System indicated that there was no significant applicable industry and/or site experience that had not been addressed in the Phase I report.There are no maintenance/modification recommendations from the lead engine DR/gR reports for this component.

The visual inspection called for on the CgRC has been previously performed as part of the Phase I effort and has been documented in the Phase I report (see References).

No further guality Revalidation is required for this component.

PRIMARY FUNCTION Not required ATTRIBUTE TO BE VERIFIED Not required.SH2233/1 SPECIFIED STANDARDS None COMPONENT DESIGN REVIEW CHECKLIST Page 2 of 2 DR-02" 02-688B-O REFERENCES"Emergency Diesel Generator Auxiliary Module Control Miring and Termination gualification Review," prepared by Stoner&Mebster Engineering Corporation, July, 1984.DOCUMENTATION RE UIRED None GROUP CHAIRPERSON PROGRAM MANAGERSH2233/2 COMPONENT UALITY REVALIDATION CHECKLIST Page 1 of 1 02"02"688C Eng.&Aux-Module Wiring COMPONENT Mat'1-Boxes 8 Terminals GPL NO.02-688C SNPS GPL NO.03-688C Carolina Power&Light Shearon Harris Nuclear UTILITY Power Plant-Unit 1 REV.NO.1 TASK DESCRIPTIONS No further revi ew of component 02-688C is required for the fol 1 owing reasons: a)Boxes and terminals were reviewed on the lead engine (Shoreham) and inspection results were satisfactory.

In addition, terminals were reviewed as part of component 02-688B.b)There is no site or industry experience reported for this component.

GROUP CHAIRPERSON Mvt, PROGRAM MANAGER SH1816/1 COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT" UNIT 1 Page 1 of 2 COMPONENT On-En ine Alarm Sensors UTILITY Carolina Power L Li ht Com an GROUP PARTS LIST NO.02"688D TASK DESCRIPTION NO.DR"02-02-688D-0 SNPS GPL NO.03-690 CLASSIFICATION TYPE B TASK DESCRIPTIONS The on-engine alarm sensors used on Shearon Harris are supplied by different manufacturers, but are of comparable quality to those used on on Comanche Peak.-The application of these instruments on Shearon Harris is similar to Comanche Peak.Thermocouples F-540-146 are used to sense jacket water and lube oil temperatures for high/low alarms.The thermocouples will operate within ambient temperatures of-100 F to 300'F and are of adequate design to perform their intended functions.

Sensilevel switches F-528-027 operate in the lube oil system to provide a low lube oil sump level alarm.These level switches will operate within ambient temperatures of-65 F to 200 F and are of adequate design to perform their intended function.Shearon Harris also uses Barksdale pressure switches, F-577-044, to sense lube oil pressure for auto control of the auxiliary lube oil pumps.These pressure switches-will operate within ambient temperatures of-204F to 1654F and are of adequate design to perform their intended function.There is no Shearon Harris site, nuclear or non-nuclear industry experience listed in the EDG Component Tracking System for the on-engine alarm sensors.There are no maintenance or modification recommendations required for the on-engine alarm sensors.A equality Revalidation of the on engine alarm sensors is not deemed necessary.

Based on the above, a design review for the on engine alarm sensors is not required for Shearon Harris.SH2130/1 PRIMARY FUNCTION Not required COMPONENT DESIGN REVIEW CHECKLIST Page 2 of 2 DR"02-02-688D-O ATTRIBUTE TO BE VERIFIED Not required SPECIFIED STANDARDS Not required REFERENCES Not required DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGERSH2130/2 Cl COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT" UNIT 1 Page 1 of 2 COMPONENT Off-En ine Alarm Sensors GROUP PARTS LIST NO.02-689 SNPS GPL NO.99-691A UTILITY Carolina Power L Li ht Com an TASK DESCRIPTION NO.DR-02-02-689-0 CLASSIFICATION TYPE B TASK DESCRIPTIONS The application of the off engine alarm sensors used on Shearon Harris is similar to that used on Comanche Peak, with the exception of the Magnetrol level switch (TDI Part No.F-528-042).

This level switch is used to provide a high or high/high output condition to control the fuel oil day tank inlet valve and to start/stop the fuel oil transfer pumps.Also, Shearon Harris uses a liquid level transmitter (TDI Part No.74046-206) to provide a high/low output signal to activate alarms on the annunciator.

A review of vendor information shows that these components are of adequate design to perform their intended~~~f unct>on.There is no Shearon Harris site, nuclear or non-nuclear industry experience listed in the EDG Component Tracking System for the off-engine alarm sensors.There are no maintenance or modification recommendations required for the off-'ngine alarm sensors.guality Revalidation of the off engine alarm sensors is not deemed necessary.

Based on the above, a design review for the off engine alarm sensors is not required for Shearon Harris.PRIMARY FUNCTION Not required ATTRIBUTE TO BE VERIFIED Not required SH2131/1 SPECIFIED STANDARDS Not required COMPONENT DESIGN REVIEW CHECKLIST Page 2 of 2 DR-02-02-689-0 REFERENCES Not required DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGER DC.SH2131/2 Page 1 of 2 COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 COMPONENT Overs eed Tri: Governor UTILITY Carolina Power&Li ht Co.GROUP PARTS LIST NO.02-410A TASK DESCRIPTION NO.DR-02-02-410A-0 SNPS GPL NO.03"410A CLASSIFICATION TYPE A TASK DESCRIPTIONS Design Review is not required for this component, based on the Shoreham lead engine DR/gR report, which establishes the acceptability of the overspeed trip governor.A review of the Component Tracking System indicates no significant applicable nuclear, non-nuclear or site experience.

The following quality inspections are recommended to ensure component quality and performance:

~Verify p~oper installation and calibration of the governor over speed trip'n accordance with the Installation and Oil Supply Topic of Woodward Documentation, TDI Manual.~Verify that proper operational procedures are used on the over-speed trip governor, in accordance with Woodward Documentation, TDI Manual.The-following:maintenance items, from the lead engine DR/gR report (Shoreham), are recommended for Shearon Harris to ensure reliability of the overspeed trip governor:~Modify the surveillance testing procedures to include verification that the overspeed trip is correctly set to an over speed trip setting of 518+/-5 rpm at every refueling outage, ensuring that both the electric governor and the mechanical backup governor are properly returned to their normal settings following the overspeed test.The test is to be performed with no load on the engine by increasing the normal governor's speed setting(s) until a trip occurs.After several inspection periods, the history of the required adjustments should be reviewed to evaluate and possibly modify the testing interval.~After setting the overspeed governor, the adjustment screw positions should be mar ked with Torque-Seal to reveal any unintended changes in the set positions.

There are no modification recommendations for this component.

SH2005/1 PRIMARY FUNCTION Not required COMPONENT UALITY REVALIDATION CHECKLIST Page 2 of 2 DR-02-02-410A-0 ATTRIBUTE TO BE VERIFIED Not re'quired SPECIFIED STANDARDS Not required REFERENCES Not required DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGER.~SH2005/2 Page 1 of 2 COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Overspeed Trip: Governor COMPONENT and Accessor Drive Assembl UTILITY Carolina Power 8 Li ht Com an GROUP PARTS LIST NO.02"4108 SNPS GPL NO.03-410B TASK DESCRIPTION NO: DR" 02" 02-410B-0 CLASSIFICATION TYPE A TASK DESCRIPTIONS Design review is not required for this component, based on the Comanche Peak lead engine DR/gR.report which establishes the acceptability of the overspeed trip and accessory drive gear and shafting.The component parts under review are identical.

A review of the Component Tracking System indicates no significant applicable nuclear, non-nuclear or site experience.

guality Inspections that have been conducted to date are considered

~~~acceptable.

The following guality Inspections are recommended to be performed:

Perform a dimensional inspection to determine the shaft'to bearing clearance..Visually ,inspect the accessory drive gear for signs of cracking.Perform a liquid penetrant test on the governor shaft.Perform a visual inspection on the governor shaft.Perform a dimensional check of the governor shaft.There are no maintenance or modification recommendations from the lead DR/gR report for this component.

PRIMARY FUNCTION Not required ATTRIBUTE TO BE VERIFIED Not required SH2076/1 a"

SPECIFIED STANDARDS Not required COMPONENT DESIGN REVIEW CHECKLIST Page 2 of 2 DR-02" 02-410B-0 REFERENCES Not required DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGER),SH2076/2

>>COMPONENT UALITY REVALIDATION CHECKLIST Page 1 of 4 02-02-410B Overspeed Trip: Governor COMPONENT&Accessor Drive Assembl Carolina Power 8 Light Shearon Harris Nuclear UTILITY Power Plant-Unit 1 GPL NO.02-410B SNPS GPL NO.03"410B REV.NO.2 TASK DESCRIPTIONS

~E l.Assemble and review existing documentation.

2.Determine the material of the accessory drive gear by a comparator test.3.Determine the hardness of the overspeed trip drive gear.This inspection is to be performed on the outer gear tooth flat.4.Perform a dimensional inspection to determine the shaft to bearing clearance.

5.Visually inspect the accessory drive gear for signs of cracking.6.Perform a Liquid Penetrant test on the governor shaft.7.Perform a visual inspection on the governor shaft.8.Perform a dimensional check of the governor shaft.1.Assemble and review existing documentation.

ATTRIBUTES TO BE VERIFIED En ine lA-SA 1.guality status of Component Document Package , 2.Material of gear SH1902/1

, COMPONENT UALITY REVALIDATION CHECKLIST ATTRIBUTES TO BE VERIFIED (continued)

~('Page 2 of 4 02-02-410B 3.4.5.6-7.8.Hardness of gear Shaft to bearing clearance Surface integrity of the gear.Surface integrity of the governor shaft.Proper shaft dimensions.

~E 1.guality status of Component Document Package ACCEPTANCE CRITERIA 1.Satisfactory Document Package 2.Material to be AISI 4340 3-8.Review of inspection report by the Design Group 1.Satisfactory Document Package REFERENCES 1.gCI No.52 2-8.Approved Site NDE Procedures l.gCI No.52 SH1902/2 I

COMPONENT UALITY REVALIDATION CHECKLIST Page 3 of 4 02"02-410B DOCUMENTATION RE UIRED l.Document Summary Sheet 2-8.Inspection Report En ine 1B-SB 1.Document S mary Sheets GROUP CHAIRPERSON

'l/~L.PROGRAM MANAGER~K two 8 j COMPONENT REVIEW En ine 1A-SA 2.No EDGCTS site experience documents are in evidence.A material comparator test was performed on the accessory drive gear.This was reported by TER¹02-028.3.4" 8.A hardness test was performed on the accessory drive gear.Results were reported by TER¹02-028.No inspection reports have been received which fulfill these requirements.

En ine 1B-SB No EDGCTS site experience documents are in evidence.Note: a)A material comparator test was performed on the accessory drive gear.This was reported by TER¹02-070.b)A hardness test was performed on the accessory drive gear.This was reported by TER¹02-070.RESULTS AND CONCLUSION En ine 1A-SA The guality Revalidation effort with respect to this component, as outlined above, is complete.The results have been forwarded to the Design Review Group for their evaluation and conclusions in support of the final report.SH1902/3 COMPONENT UALITY REVALIDATION CHECKLIST RESULTS AND CONCLUSION (continued)

En ine 1B-SB Same as Engine 1A-SA Page 4 of 4 02"02"410B GROUP CHAIRPERSON PROGRAM MANAGER-.M Kerr SH1902/4 COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Page 1 of 2 COMPONENT Over s eed Tri: Cou 1 in s UTILITY Carolina Power 8 Li ht Com an GROUP PARTS LIST NO.02-410C SNPS GPL NO.03-410C TASK DESCRIPTION NO: DR-02" 02-410C-0 CLASSIFICATION TYPE A TASK DESCRIPTIONS Design review for this component is not required based on the review of the Comanche Peak lead engine DR/gR report which establishes the acceptability of the overspeed trip couplings.

The parts under review are the same as those of the lead engine.A review of the Component Tracking System indicates no significant applicable industry or site experience.

The following maintenance recommendations should be implemented to improve the~~~~~~re 1 i abi 1 i ty of the Shear on Harri s des i gn:~Either modify the maintenance specifications to replace the Lovejoy coupling spiders at every fuel outage, or, during the fuel outages, test the coupling elastomer for hardness and replace if it has exceeded the coupling manufacturer's specification.

Discontinue use of Loctite 680 on heavy interference fits, but use Loctite 609 in a manner prescribed by TDI SIM¹363 during assembly.Modify the maintenance specifications to check for coupling shaft looseness during fuel outages.~At the next refueling outage, remove the present Lovejoy couplings and replace with new units.The shafts upon which each half are to be mounted should be measured and machining modifications made to the coupling halves to keep the interference fit below 0;0005 inch.Other procedures outlined in SIM 363 should be followed, except with using Loctite 609 in place of 680 when reassembled.

There are no modification recommendations for this component.

The following guality inspection is recommended to be performed:

~Visually inspect the couplings for proper installation and signs of deterioration, on all station engines.SH2102/1 PRIMARY FUNCTION Not required COMPONENT DESIGN REVIEW CHECKLIST Page 2 of 2 DR"02-02-410C-0 ATTRIBUTE TO BE VERIFIED Not required SPECIFIED STANDARDS Not required REFERENCES Not required DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGERSH2102/2 COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Page 1 of 2 COMPONENT Overs eed Tri Vent Valve UTILITY Carolina Power&Li ht Com an GROUP PARTS LIST NO.02-410D SNPS GPL NO.03-410D TASK DESCRIPTION NO.DR-02-02" 410D-O~CLASSIFICATION TYPE A TASK DESCRIPTIONS Design review for this component is not required based on the following:

A review of the EDG Component Tracking System indicated that there was no significant applicable industry or site experience.

~A review of the lead engine DR/gR reports (Shoreham and Comanche Peak)~Similarity between Shearon Harris and lead engine components The following maintenance from the Lead Engine DR/gR Report should be implemented.

~Replace valve 0-rings every 5 years There are no modifications required for this component.

No equality revalidation is required for this component.

PRIMARY FUNCTION Not r equired ATTRIBUTE TO BE VERIFIED Not required'SH2230/1

'SPECIFIED STANDARDS Not required COMPONENT DESIGN REVIEW CHECKLIST Page 2 of 2 DR-02-02-410B-0 REFERENCES Not required DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGERSH2230/2 COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT" UNIT 1 Page 1 of 2 Governor Drive: Governor&Tach-COMPONENT ometer Drive Gear and Shaft GROUP PARTS LIST NO.02-411A SNPS GPL NO.03-402A UTILITY Carolina Power 8 Li ht Com an TASK DESCRIPTION NO.DR-02-02-411A-0 CLASSIFICATION TYPE A TASK DESCRIPTIONS Design review for this component is not required based on the Comanche Peak lead-engine DR/gR report which establishes the acceptability of the governor drive gears and shafts.A review of the Component Tracking System indicates no significant applicable industry or site experience.

'E There are no modifications or maintenance recommendations for this component.

~~~~~~~guality inspections conducted to date have been reviewed and are considere The ,following quality inspection is recommended to be performed on Engine 1A-SA: d satisfactory, with the except>on of a hardness test of the governor drsve gears which gave inconclusive results.This hardness inspection is not required in the Component guality Revalidation Checklist; the visual inspection recommendation outlined in the Preventive Maintenance Matrix will accommodate the need for wear inspection on these gears.~Perform a liquid penetrant test of the governor drive gear'and shaft for fatigue cracks in the following areas: 'a 0 b.C.d.Gear and'haft contact surfaces and surfaces immediately adjacent Gear pins and bores Vertical shaft to gear keyway Reduced shaft diameter of coupling PRIMARY FUNCTION Not required ATTRIBUTE TO BE VERIFIED Not required SH2168/1 COMPONENT DESIGN REVIEW CHECKLIST SPECIFIED STANDARDS Not requir ed Page 2 of 2 DR-02-02-411A" 0 REFERENCES Not required DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGER X~~~-.~aSH2168/2 COMPONENT UALITY REVALIDATION CHECKLIST Page 1 of 3 02-02"411A Governor Drive-Governor and Tach COMPONENT Drive Gear 8 Shaft Carolina Power 8 Light Shearon Harris Nuclear UTILITY Power Plant-Unit 1 GPL NO.02-411A REV.NO, 2 SNPS GPL NO.03-402A TASK DESCRIPTIONS

~Ei*-A l.Assemble and review existing documentation.

2.Determine the material of the governor drive and governor driven gears.3.Perform a Liquid Penetrant test of the governor drive gear and shaft for fatigue cracks in the following areas: b.C.d.a.Gear and shaft contact surfaces and surfaces immediately adjacent Gear pins and bores Vertical shaft to gear keyway Reduced shaft diameter of coupling l.Assemble and review existing documentation.

ATTRIBUTES TO BE VERIFIED En ine lA-SA1.guality status of Component Document Package 2.Material of governor drive and governor driven gears 3.Surface integrity of the governor drive gear and shaft SH1724/1 COMPONENT UALITY REVALIDATION CHECKLIST ATTRIBUTES TO BE VERIFIED (continued)

Page 2 of 3 02"02-411A 1.guality status of Component Document Package ACCEPTANCE CRITERIA 1.Satisfactory Document Package 2.Material to be AISI-4142 3.Review of inspection report by Design Group 1.Satisfactory Document Package REFERENCES nd: l.gCI No.52 2-3.Approved Site NDE Procedures, TDI DWG.02-411-7015 l.gCI No.52 DOCUMENTATION RE UIRED En ine lA-SA l.Document Summary Sheet 2-3.Inspection Report 1.Document Sum ary Sheet-GROUP CHAIRPERSON PROGRAM MANAGER C.K SH1724/2 f~W A t I COMPONENT REVIEW COMPONENT UALITY REVALIDATION CHECKLIST Page 3 of 3 02-02-411A 1.No EDGCTS site experience documents are in evidence.2.A material comparator test was performed on the horizontal and vertical governor drive gears.Results were reported by TER¹02-022.3.No inspection report has been received which fulfills this requirement.

Note: a)A hardness test was performed on the horizontal and vertical governor drive gears.Results were reported by TER¹02"022.1.No EDGCTS Note: a)site experience documents are in evidence.A material comparitor test was performed on the horizontal and vertical governor drive gears.This was reported by TER¹02-071.

b)A har dness test was performed on the horizontal and vertical governor drive gears.This was reported by TER¹02-071.c)A visual inspection was performed on Woodward governor and tach gears with satisfactory results.This was report by TER¹02" 071.RESULTS AND CONCLUSION En ine 1A-SA The'equality Revalidation effort with respect to this component, as out-lined above, is complete.The results have been forwarded to the Design Review Group for their evaluation and conclusions in support of the final report.Same as Engine lA-SA GROUP CHAIRPERSON.kite 4 S~~~PROGRAM MANAGER , SH1724/3 COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Page 1 of 2 N Governor Drive: COMPONENT Cou lin s Pins and Ke s UTILITY Carolina Power&Li ht Com an GROUP PARTS LIST NO.02-411B TASK DESCRIPTION NO.DR-02-02-411B-1 SNPS GPL NO.03"402B CLASSIFICATION TYPE A TASK DESCRIPTIONS Design review is not required for this component based on a review of industry and site experience in the EDG Component Tracking System and the lead engine DR/gR report (Comanche Peak).The following maintenance items are recommended to ensure reliability of this component:

Replace the present neoprene inserts in the Koppers couplings before placing the engines in emergency standby service.~Modify the maintenance schedule to include checking the coupling tightness at refueling outages.If the coupling is found loose, it should be removed, all mating surfaces cleaned, and the unit reassembled using Loctite 609 on the mating surfaces.Replace the elastomeric insert at refueling outages.There are no modification recommendations for this component.

The following equality inspections are recommended to be performed on all station engines: Verify that the elastomeric insert of the Koppers couplings is made of neoprene, by reviewing existing documentation.

Verify that the set screw and drive pins are locked in place in accordance with installation instructions.

SH2201/1 REV.I PRIMARY FUNCTION Not required COMPONENT DESIGN REVIEW CHECKLIST Page 2 of 2 DR-'02-02-411B-0 ATTRIBUTE TO BE VERIFIED Not required SPECIFIED STANDARDS Not required REFERENCES Not required DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGER CAWSH2201/2 COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Page 1 of 3 COMPONENT Governor Linka e GROUP PARTS LIST NO.02-413A SNPS GPL NO.03-413 UTILITY Carolina Power 8 Li ht Com an TASK DESCRIPTION NO.DR" 02-02-413A-0 CLASSIFICATION TYPE A TASK DESCRIPTIONS Design review for this component is not required based on the review of the Comanche Peak lead engine DR/gR report and the EDG Component Tracking System, which indicates no significant applicable site experience.

The Component Tracking System industry experience, however, reported one incident of loosening governor linkage components, a valid concern in the absence of positive locking devices at the lever clamp screws.The-required preventive measure is addressed under maintenance/modification recommendations below.Component No.02-413A includes the following items (Ref.2): Item Part No.Lever, Governor Extensive Link Assembly Cross-shaft Assembly 02-413-10-AL 1A-5779 1A-6133 The cross-shaft assembly includes the fuel control shaft, bearings, and the actuating levers which consist of the cross-shaft lever 02-413-11-AG, connecting to the extensible link assembly, the fuel control levers 02-413-11AB, and the shutdown lever 02-413-09-AF.

The governor linkage and cross-shaft assemblies are identical for both Shearon Harris and Comanche Peak and, based on the review for Comanche Peak, are satisfactory for the seismic and operational loads.The cross-shaft bearings are oil lubricated, sleeve-type, bronze bearings, similar to Comanche Peak design.However, there are some differences in the design details for maintaining oil supply to the wicking felt.The arrangement at Shearon Harris (Ref.3)is a later design apparently having a large lubricant holding volume but without the washer immediately above the felt.The following maintenance and modification recommendations stated in the Comanche Peak lead engine DR/gR report should be implemented:

~The cross-shaft bearings should be lubricated monthly, and all rod-end fittings should be greased at each outage to maintain proper service.SH2377/1 COMPONENT DESIGN REVIEW CHECKLIST TASK DESCRIPTION (continued)

Page 2 of 3'R-02" 02-413A-0~To prevent loosening of governor linkage components, a periodic inspection for loose'parts should be performed and suitable locking hardware be added to the lever bolts and roll pins experiencing such problems.The following guality inspections as described in the Component equality Revalidation Checklist and Task Evaluation Report TER No.99-021, should be'erformed on all the station engines: Visual inspection on the governor linkage to detect signs of corrosion, wear, pitting, and discoloration.

Verification of the installation of roll pins to hold the fuel control levers to the cross-shaft.

PRIMARY FUNCTION Not required ATTRIBUTE TO BE VERIFIED Not required SPECIFIED STANDARDS Not requiredSH2377/2 REFERENCES COMPONENT DESIGN REVIEW CHECKLIST Page 3 of 3 DR" 02-02" 413A" 0 1.Comanche Peak Steam Electric Station-Unit 1, DR/gR Report for Component Part No.02-413A.2.TDI Parts Manual Volume II, Model DSRV-16-4 Diesel Engine/Generator.

Shearon Harris Power Station-Units 1, 2, 3, and 4.3.TDI Parts Drawings 02-413-12, 02-41312, 02-413-3693, 02-413-3841, and 02"413-4933.

4.Emergency Diesel Generator Component Tracking System-Nuclear and Non-Nuclear Industry experience dated October 15, 1984.5.Emergency Diesel Generator Component Tracking System-Shearon Harris Nuclear Power Station dated October 15.1984.DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON ROGRAM MANAGER C.ECSH2377/3 Page 1 of 2 COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Governor Assembly: COMPONENT Woodward Governor GROUP PARTS LIST NO.02-415A UTILITY Carolina Power 8 Li ht Com an TASK DESCRIPTION NO.DR-02-02-415A-0 SNPS GPL NO.03"415A CLASSIFICATION

'TYPE A TASK DESCRIPTIONS Design review is not required for this component, based on the lead engine DR/gR report for Comanche Peak, which establishes the acceptability of the Woodward governor.A review of the Component Tracking System indicates no significant applicable industry or site experience.

The following maintenance recommendations should be implemented to improve component reliability:

Modify the surveillance testing procedures to include an evaluation of the governor settings.Tests, once under joint electrical and mechanical governor control and once under only mechanical governor control, off the grid in the isochronous mode, are to include examination of the engine speed transients under both start and transient loading conditions.

They are to regularly ensure that the governor settings are appropriate to avoid the critical speed resonance at 496 rpm, specifically, that the overshoot of the 450 rpm set speed is no more than 7.5 percent or a maximum speed of 484 rpm, either during a start or when unloaded by 1400 kW.Augment the setting adjustment procedures, as described in the Woodward manuals, to include tests of the governor response during an engine start to ensure agreement with the specifications indicated above.Modify the maintenance schedules to ensure that the hydraulic actuator is vented per the Woodward Instructions when more than a half quart of oil is added to the unit.Modify the cleanness control specification to ensure that appropriate procedures are followed when adding or changing the governor oil so as not to contaminate fresh oil and the interior of the governor.There are no modification recommendations for this component.

SH2106/1 COMPONENT DESIGN REVIEW CHECKLIST TASK DESCRIPTION (continued) equality Revalidation is not required for this component.

Page 2 of 2 DR-02-02-415A-0 PRIMARY FUNCTION Not required ATTRIBUTE TO BE VERIFIED Not required SPECIFIED STANDARDS Not required REFERENCES Not required DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGER SH2106/2 Page 1 of 2 COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Governor Assembly COMPONENT Booster Servomotor GROUP PARTS LIST NO.02"415B UTILITY Carolina Power L Li ht Com an TASK DESCRIPTION NO.DR" 02-02-415B" 1 SNPS GPL NO.03"415B CLASSIFICATION TYPE TASK DESCRIPTION Design review for this component is not required based on the applicable industry experience and the lead engine DR/gR reports (Shoreham/Comanche Peak).There is no site experience in the EDG Component Tracking System for this component.

There are no maintenance or modification recommendations for this component.

The results of the guality inspections have been reviewed.These inspections revealed that the outlet lines of the servomotors are not the size as called out in the Woodward manual.Per a conversation with Woodward Governor MFG., the existing 3/8" lines on the servomotor outlets are acceptable and need not be changed to the>4" size previously recommended.

The remaining guality inspections on Engines lA-SA and 1B-SB have yielded satisfactory results.The following guality inspection is recommended to be performed on Engine 1B" SB:~Verify that installation criteria are met on the booster servomotor Oil lines should slope upward from'he booster to the governor and should have a minimum number of loops or bends.PRIMARY FUNCTION Not required ATTRIBUTE TO BE VERIFIED Not required SH2638/1

SPECIFIED STANDARDS Not required COMPONENT DESIGN REVIEW CHECKLIST Page 2 of 2 OR-02-02" 415B-1 REFERENCES Telecon: J.Carbonaro (SWEC)to D.Brown (Woodward)"Adequacy of 3/8 Inch Outlet on Booster Servomotor".

DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGER SH2638/2 COMPONENT UALITY REVALIDATION CHECKLIST Page 1 of 3 02" 02-415B Governor Assembly-COMPONENT Booster Servomotor.GPL NO.02-415B SNPS GPL NO.03-415B Carolina Power&Light Shearon Harris Nuclear UTILITY Power Plant-Unit 1 REV.NO.2TASK DESCRIPTIONS En ine 1A-SA 1.Assemble and review existing documentation.

2.Verify the following installation criteria are met on the booster servomotor:

a)Booster.servomotor is mounted at a lower level than governor.b)The inlet booster line is 3/8" and the outlet booster line is 1/41 I c)Oil lines should slope upward from the booster to the governor and should have a minimum number of loops or bends.En ine 1B-SB Same as Engine 1A-SA ATTRIBUTES TO BE VERIFIED En ine 1A-SA l.guality status of Component Document Package 2.Installation criteria on the booster servomotor are met.Same as Engine 1A-SA SH1915/1 ACCEPTANCE CRITERIA En ine 1A-SA COMPONENT UALITY REVALIDATION CHECKLIST Page 2 of 3 02" 02" 415B 1.Satisfactory Document Package 2.Review of inspection report by the Design Group Same as Engine 1A-SA REFERENCES En ine lA-SA 1.gCI No.52 2.TER¹99"008 Same as Engine 1A-SA DOCUMENTATION RE UIRED 1.Document Summary Sheet 2.Inspection Report Same as Engine-SB n GROUP CHAIRPERSON PROGRAM MANAGER SH1915/2 COMPONENT UALITY REVALIDATION CHECKLIST Page 3 of 3 02" 02" 415B COMPONENT REVIEW En ine 1A-SA 1 No EDGCTS site experience documents are in evidence.2.The booster servomotor was verified to be mounted below the governor.The dimension of the inlet diameter of the booster line was satis-factory while the outlet dimension was found unsatisfactory.

The number of loops and bends in the oil lines was recorded.These results were reported by TER¹02-036.En ine 1B-SB 1.No EDGCTS site experience documents are in evidence.2.The booster servomotor was verified to be mounted below the governor.Both inlet and outlet booster lines are 3/8" diameter.This was reported by TER¹02-102.RESULTS AND CONCLUSION The guality Revalidation effort with respect to this component, as outlined above, is complete.The results have been forwarded to the Design Review Group for their evaluation and conclusions in support of the final report.En ine 1B-SB Same as Engine 1A-SA GROUP CHAIRPERSON K~'"+PROGRAM MANAGER SH1915/3 COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR f OWER PLANT-UNIT 1 Page 1 of 2 Governor Assembly-COMPONENT Heat Exchan er GROUP PARTS LIST NO.02-415C SNPS GPL NO.03-415C UTILITY Carolina Power&Li ht Com an TASK DESCRIPTION NO.DR-02-02-415C-0 CLASSIFICATION TYPE A TASK DESCRIPTIONS Design review for this component is not required based on the following:

A review of the EDG Component Tracking System indicated that there was no significant applicable industry and/or site experience, with the exception of cooler location.~A review of the Lead Engine DR/gR Report (Comanche Peak).~~This component was found to be similar to that used on Comanche Peak.No special maintenance or modifications are recommended for this component.

The following guality inspection is recommended to be performed.

~Verify that the cooler is mounted below the oil level in the governor, on each station engine.PRIMARY FUNCTION Not required ATTRIBUTE TO BE VERIFIED Not required SPECIFIED STANDARDS Not required SH2228/1 REFERENCES Not required COMPONENT DESIGN REVIEW CHECKLIST Page 2 of 2 DR-02-02-415C" 0 DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGER~~KSH2228/2

TDI OWNERS GROUP for SHEARON HARRIS POWER PLANT-UNIT 1 ENGINE SHUTDOWN E UIPMENT-TUBING/FITTINGS 5 SUPPORTS SMALL BORE SCOPE ONLY COMPONENT PART NO.02-695A I INTRODUCTION The TDI Emergency Diesel Generator Owners Group Program for the Shearon Harri s Nuclear Power Plant requires Design and gual i ty Reval i dati on reviews of the structural adequacy of the engine shutdown equipment-tubing/fittings and supports to withstand the effects of normal operating and earthquake loadings.The primary function is to maintain the capabil-ity to effect engine shutdown.I I OBJECTIVE The objective of this review was to perform an engineering evaluation of the tubing and supports to assure that the component will perform its intended design function during normal operating and earthquake loadings.III METHODOLOGY In order to meet the stated objective, the following methods were used: The TDI Emergency Diesel Generator Component Tracking System was reviewed for the Shearon Harris site, nuclear, and non-nuclear industry experience.

See Appendix C for results.~The equality Revalidation Checklist results were reviewed for acceptability.

~Comparison with the lead engine reports (Comanche Peak, Grand Gulf and Catawba).Refer to the review procedures described in Reference 1 for a detailed methodology of this evaluation.

IV RESULTS AND CONCLUSIONS The tubing and supports, as defined by this Component Design Review, have been evaluated in accordance with Reference 1 and have been found accept-able with the modifications.

The conclusions of this report are based on a combination of the field walkdown and the review of the lead engine re-SH2370/1 Page 2 of 2 ports as portions of this component were not installed at the time of the walkdown.Based on the above review, it is concluded from References 1 and 2 that the tubing and supports will perform their intended design function at Shearon Harris under all normal operating and'earthquake loadings with the provision that the following recommended modifications be implemented as detailed in Reference 3.It is recommended that two-way supports be added to the following lines, such that the between-support spans are limited to a maximum of 4 feet 6 inches:~Line E33, left bank turbo oil pressure, between the cross connection at the sight glass assembly and the first support downstream.

~Line E16, high temperature jacket water, between the water discharge manifold (governor end)and the gearcase area below.It is recommended that two-way supports be added to the following lines as indicated:

~Lines E31R and E31L, starting air pressure indication, midway between the air start header connection and cylinder No.8 (right and left banks).Locations of supports should accommodate thermal expansion by provid-ing a minimum of 6-inch tubing offset around elbows.All additions/modifications apply to Engines 1A&1B unless otherwise specified.

It is recommended that supports be modified to the following lines as indicated:

The tubing lines which run along the right bank just above the crankcase access doors (gearcase to flywheel)are insufficiently restrained in the horizontal direction because of excessive clearance in the brackets.Therefore it is recommended that these seven supports be modified to provide two-direction lateral restraint (Engine 1B only).V REFERENCES l."Engineering Review Criteria Document for the Design Review of TDI Diesel Small Bore Piping, Tubing, and Supports for the TDI Owners'roup," Report No.11600.60-DC-02, Revision 0.2.Stone 8 Webster Calculation No.11600.60-NP(B)-0201-XH.

3.Memo No.6451 from C.Malovrh/SWEC to J.Kammeyer/SWEC dated 10/29/84.SH2370/2

APPENDIX A COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Page A1 of 2 Engine Shutdown-Equipment Tubing/Fittings COMPONENT Small Bore Sco e Onl GROUP PARTS LIST NO.02-695A SNPS GPL NO.03-695A UTILITY Carolina Power 8 Li ht TASK DESCRIPTION NO.DR-02"02-695A-0 CLASSIFICATION TYPE TASK DESCRIPTIONS Perform an engineering review of the tubing and supports to provide additional assurances that the components will perform their intended design function during normal operating and earthquake loading.~~~~PRIMARY FUNCTION Maintain capability to affect engine shutdown.ATTRIBUTES TO BE VERIFIED Structural adequacy of the tubing and supports due to the effects of normal operating and earthquake loadings.SPECIFIED STANDARDS IEEE 387 REFERENCES"Engineering Review Criteria Document for the Design Review of TDI Diesel Small Bore Piping, Tubing, and Supports for the TDI Owners'roup" Report No.11600.60-DC-02, Revision 0.SH2257/1 COMPONENT DESIGN REVIEW CHECKLIST DOCUMENTATION RE UIRED Page A2 of 2 DR-02-02-695A-0 Delaval design documentation (specifications, calculations, drawings, etc.).In lieu of information from Delaval, the following information is required: verified support sketches and piping isometrics, material specifications, pipe size and schedule, and operating parameters (pressure, temperature, load combinations).

GROUP CHAIRPERSON PROGRAM MANAGER C l SH2257/2

Appendix B COMPONENT UALITY REVALIDATION CHECKLIST Page Bl of 3 02-02-695A Engine Shutdown Equipment-COMPONENT Tubin and Fittin s UTILITY Carolina Power 8 Light GPL NO.02-695A SNPS GPL NO.03-695A REV.NO.1 TASK DESCRIPTIONS

~E 1.Assemble and review existing documentation.

2.Obtain sufficient data to support the design review effort.This may be accomplished by developing quality verified as-builts in accordance with Procedure DG-7, or by the Design Group performing a field walkdown.~E Same as Engine 1A-SA ATTRIBUTES TO BE VERIFIED 1.guality status of Component Document Package 2.Information necessary for the design review effort.Same as Engine 1A-SA SH1753/1 ACCEPTANCE CRITERIA En ine lA-SA COMPONENT UALITY REVALIDATION CHECKLIST Page 2 of 3 02"02-695A 1.Satisfactory Document Package 2.Review of detailed information by the Design Group~E Same as Engine 1A-SA REFERENCES En ine lA-SA 1.gCI No.52 2.Procedure DG-7 Same as Engine 1A-SA DOCUMENTATION RE UIRED l.Document Summary Sheet 2.equality verified as-built isometric drawings for the tubing and fittings if available from the Owner.En ine 1B-SB Same as Engine 1A-SA GROUP CHAIRPERSON PROGRAM MANAGER KiA-'"~.e i SH1753/2 COMPONENT REVIEM COMPONENT UALITY REVALIDATION CHECKLIST Page 3 of 3 02-02-695A 1.No EDGCTS site experience documents are in evidence.2.The Design Group drawings as per equality verified performance of an the issuance of a will be responsible for closing out the as-built Procedure DG-7.The as-built drawings will be by the appropriate site guality organization.

The engineering walkdown by the Design Group, precludes quality verified as-built drawing or sketch.Same as Engine 1A-SA RESULTS AND CONCLUSION En ine lA-SA The guality Revalidation effort with respect to this component, as outlined above, is complete.The results have been forwarded to the Design Review Group for their evaluation and conclusions in support of the final report.En ine 1B-SB Same as Engine 1A-SA GROUP CHAIRPERSON PROGRAM MANAGER~~K~~SH1753/3 A endix C Page Cl of 2 EDG COMPONENT TRACKING SYSTEM: SHEARON HARRIS SITE NUCLEAR AND NON-NUCLEAR INDUSTRY EXPERIENCE

SUMMARY

COMPONENT NO.02"695A Effective Printout Dates Industry: 9/17/84 Shearon Harris: 10/15/84 COMPONENT TYPE: En ine Shutdown E ui ment-Tubin/Fittin s EXPERIENCE SHEARON HARRIS None NUCLEAR Diesel tripped because of high jacket water temperature caused by low lube oil level.Engine ran successfully after oil was added.Instrument line to cooling jacket water line was leaking.Cause found to be a crack in>4-inch nipple.Air leak found on pres-sure gauge sensing line.Fittings were tightened and diesel operated properly.Engine tripped due to air leak on line to fuel shutoff pistons.REFERENCE DOCUMENTS North Anna 2 LER 339-83054, 830704 Palisades LER 255-77000, 770211 Zion 2 LER 304-75000,.750507 Zion 1 LER 295-80028, 800524 SHEARON HARRIS STATUS Shutdown system worked properly.Does not affect component design or integrity.

This is an isolated event and has not occurred at Shearon Harris.Does not affect component design or integrity.

This failure probably re-sulted from improper tightening of fittings during installation and has not occurred at Shearon Harris.Does not affect component design or integrity.

Thi s event probably re-sulted from improper tightening of fittings during installation and has not occurred at Shearon Harris.Does not affect component design or integrity.

SH2370/1

~Aendix C Engine failed to start because of clogged orifice in air relay system.Diesel tripped due to a split pipe nipple in the 30 psig control air system.The nipple had cracked due to cyclic fatigue.Nipple was replaced and operability d.demonstrate NON-NUCLEAR None EXPERIENCE Diesel tripped because of a leak in a line to the master shutdown cylinder.Pipe nipple was replaced.REFERENCE DOCUMENTS Zion 2 LER 304"77000, 770S06 Monticello NPRDS 770411 Zion 2 EP RI" NP" 2433 Page C2 of 2 SHEARON HARRIS STATUS This probably resulted from inadequately sup-ported piping.The design report for this component concludes that the Shearon Harris lines are adequate-ly supported with modifi-cations.This is a maintenance item and does not affect compo-nent design integrity.

Pipe nipples used at Shearon Harris are are schedule 80, which should preclude fatigue cracking due to vibration.

SH2370/2

COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Page 1 of 2 Engine Shutdown Equipment-Valves, Regulators, COMPONENT Orifices UTILITY Carolina Power 8 Li ht Com an GROUP PARTS LIST NO.02"695B SNPS GPL NO.03-695B TASK DESCRIPTION NO.DR-02" 02-695B-0 CLASSIFICATION TYPE A TASK DESCRIPTIONS The engine shutdown equipment valves, regulators, and orifices used on Shearon Harris are identical to Comanche Peak, with regard to manufacturer and application.

In addition, the configuration of this equipment on Shearon Harris in the pneumatic shutdown system to trip on engine overspeed and to propagate the shutdown signal is also identical to Comanche Peak.There is no Shearon Harris site or non-nuclear industry experience listed in EDG Component Tracking System for this component.

The nuclear industry experi-ence listed does not show any significant problems applicable to Shearon Harris design.To minimize fouling of the engine shutdown equipment valves, regulators and orifices, it is recommended that the equipment be inspected and cleaned and the elastomeric parts be replaced during each refueling outage.This recommended maintenance interval should be reassessed depending on the degree of system fouling.There are no ,recommended modifications for the engine shutdown equipment valves, regulators and orifices.A guality Revalidation for the engine shutdown equipment valves, regulators and orifices is not deemed necessary.

Based on the above, a design review for the engine shutdown equipment valves, regulators, and orifices is not required for Shearon Harris.PRIMARY FUNCTION Not required ATTRIBUTE TO BE VERIFIED Not required SH2132/1

\~Ie I'PECIFIED STANDARDS Not required COMPONENT DESIGN REVIEW CHECKLIST Page 2 of 2 DR-02"02"695B"0 REFERENCES Not required DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGERSH2132/2

COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POMER PLANT-UNIT 1 Page 1 of 2 COMPONENT En ine Shutdown Tri Switches GROUP PARTS LIST NO.02"695C SNPS GPL NO.03-695C UTILITY Carolina Power 8 Li ht Com an TASK DESCRIPTION NO.DR-02" 02" 695C-0 CLASSIFICATION TYPE A TASK DESCRIPTIONS The application and manufacturer of the engine shutdown trip switches used on Shearon Harris are identical to those on Comanche Peak with the exception of a low pressure trip switch, F-573-378.

This California Controls pressure switch is installed in the jacket water system and actuates to trip the diesel on low pressure.The switch has a narrow trip range and, therefore, is sensitive to the lower pressur es in the jacket water system.There is no Shearon Harris site experience listed in the EDG Component~~~~~~~~~Tracking System for the engine shutdown trip switches.The applicable nuclear and non-nuclear industry experiences listed do not indicate any generic or significant problems with the trip switches.There are no maintenance or modification recommendations required for the engine shutdown trip switches.A guality Revalidation of the engine shutdown trip switches is not deemed necessary.

Based on the above, a design review for the engine shutdown trip switches is not required for Shearon Harris.PRIMARY FUNCTION Not required ATTRIBUTE TO BE VERIFIED Not required.SH2133/1 SPECIFIED STANDARDS Not required COMPONENT DESIGN REVIEW CHECKLIST Page 2 of 2 DR-02-02-695C-0 REFERENCES Not required DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGER MCkSH2133/2 TDI DIESEL GENERATOR DESIGN REVIEW AND QUALITY REVALIDATION REPORT Prepared For CAROLINA POWER S.LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT By TDI DIESEL GENERATOR OWNERS GROUP VOLUME 4 i

How To Use This Re or t Tabs in this report identify the following categories:

Turbo, Intake, Intercooler

&Exhaust Lube Oil Engine Base 8 Bearing Caps Crankshaft

&Bearings Cylinder Block, Liners 8 Water Manifold Air Start 8 Barring Device Connecting rods Pistons Camshaft 8 Valve Train Idler Gear Assembly 8 Front Gear Case Flywheel Engine Instrumentation 8 Wiring Overspeed Trip 8 Governor Engine Shutdown 8 Equipment Jacket Water Cylinder Heads 8 Valves Fuel Oil Injection Generator Control Panel Assembly Engine 8 Auxiliary Sub-Base&Foundation Bolts These categories have been defined to allow the reader to review a complete diesel generator subsystem in a convenient manner.Within each category tabs identify Shearon Harris specific component numbers.A given component report can be found by: a)If the component number is known-use the alpha-numberic index which identifies the volume number and category in which the compon-ent report is located.b)If only the component name is known-Section 3.2 may be used as a cross-reference to find the volume number where the component report may be found.Some reports address more than one component.

a tab is provided for each component.

However, some components are combined under one report.Slip sheets are provided where required to reference back to the appropriate tab.Some components required more than one report, These are identified by the , abbreviation LB-Large Bore and SB-Small Bore on the component number tabs.SH2651 INDEX (continued)

Component Component Number Descri tion F-068 Intercooler MP022/23 Turbocharger Cate or Turbo, Intake Intrclr.8 Exhaust Turbo, Intake, Intrclr.&Exhaust Volume No.00-420 02-CFR 02-305A 02-305C 02-305D 02-307A 02"3078 02-307D 02-310A 02-310B 02-310C 02-311A Lube Oil Pressure Regulating Valve Turbocharger Thrust Bearing Lubricant System Base and Bearing Caps: Base Assembly Base and Bearing Caps: Main Bearing Studs 8 Nuts Base and Bearing Caps: Main Bearing Caps Lube Oil Fittings: Internal-Headers Lube Oil Fittings: Internal-Tube 8 Fittings Lube Oil Fittings Internal: Supports Crankshaft Crankshaft and Bearings: Main Bearings Crankshaft

&Bearings: Thrust: Bearing Rings.Crankcase:

Crankcase Assy Lube Oil Turbo, Intake, Intrclr.&Ex-haust Engine Base 8 Bearing Caps Engine Base&Bearing Caps Engine Base 8 Bearing Caps Lube Oil Lube Oil Lube Oil Crankshaft

&Bearings Crankshaft 8 Bearing Crankshaft

&Bea~ing Crankshaft

&Bearing SH2651 Rev.1 Entire Page Revised INDEX (continued)

Component Number 02-311D 02-315A 02-315C 02-315D 02-315E 02-315F 02-315G 02-316A 02-316B 02" 316C 02-317A 02-317B 02-317C Component Oescri tion Crankcase:

Crankcase Mounting Hardware Cylinder Block Liners 8 Water Manifold: Cylinder Block Cylinder Block Liners 8 Water Manifold-Cylinder Liner Water Manifold: Jacket Water Manifold 8 Piping Cylinder Block Liners 8 Water Manifold: Studs Cylinder Block Liners 8 Water Manifold: Cylinder Head Nuts Cylinder Block Liners&Water Manifold: Seals&Gaskets Jacket Water Inlet Manifold: Manifold Assembly W/Hardware and Coupling and Gaskets Jacket Water Inlet Manifold: Coupling and Gaskets Jacket Water Inlet Manifold: Vent line to Discharge Manifold Jacket Water Discharge Manifold/Piping Jacket Water Discharge Manifold: Couplings and Seals Water Discharge Manifold: Supports Cate or Crankshaft 8 Bearings Cyl.Block&Liners 8 Water Manifold Cyl.Block&Liners 8 Water Manifold Cyl.Block 8 Liners 8 Water Manifold Cyl.Block 8 Liners 8 Water Manifold Cyl.Block&Liner 8 Water Mani fol d Cyl.Block&Liners 8 Water Manifold Jacket Water Jacket Water Jacket Water Jacket Water Jacket Water Jacket Water Volume No.SH2651 Rev.1 Entire Page Revised INDEX (continued)

Component Component Number Descri tion Cate or Volume No.02-330A 02-330B 02-335B 02-340A 02-340B 02-341A 02-341B 02-341C 02-345A 02-345B 02-345C 02-350A 02-350B 02"350C Flywheel Flywheel-Bolting Front Gear Case: Gaskets and Bolting Connecting Rods: Connecting Rods 8 Bushings Connecting Rods: Bearing Shel ls Pistons: Pistons Pistons: Rings Piston: Pin Assembly Tappets and Guides: Intake 8 Exhaust Tappet Assembly Tappets and Guides: Fuel Tappet Assembly Tappets and Guides: Fuel Pump Base Assembly Camshaft: Camshaft Assembly Camshaft: Camshaft Bearing Camshaft: Supports, Bolting and Gear Flywheel Flywheel Idl er Gear As-sembly 8 Front Gear Case Connecting Rods Connecting Rods Pistons Pistons Pistons Camshaft 8 Valve Train Camshaft 8 Val ve Train Camshaft&Valve Train Camshaft 8 Valve Train Camshaft 8 Val ve Tr ain Camshaft 8 Valve Train 02"355A Idler Gear Assemble: Crank To Pump Gear Idl er Gear As-sembly 8 Front Gear Case 02-355B Idler Gear Assembly: Idler Gear Assembly Idler Gear As-sembly 8 Front Gear Case 02-355C SH2651 Idler Gear Assembly: Bolting and Gaskets iv Idler Gear Assembly&Front Gear Case Rev.1 Entire Page Revised INDEX (continued)

Component Component Number Descri tion 02-359 Air Start Valve t Cate or Air Start&Barring Device Volume No.02-360A 02-360B 02-360C 02-360D 02-362A 02-365A 02-365B 02-365C 02-3650 02-371A 02-371B 02-375 Cylinder Head and Valves: Cylinder Head Cylinder Head and Valves: Intake&Exhaust Valves Cylinder Head and Valves: Bol ting and Gaskets Cyl inder Head and Valves: Springs&Retainers Cylinder Head Covers-Subcover Assembly Fuel Injection Equipment:

Fuel Injection Pump Fuel Injection Equipment-Fuel Injection Tips Fuel Injection Equipment-Tube Assembly Fuel Injection Equipment:

Supports Fuel Pump Linkage: Linkage Assembly and Bearing Fuel Pump Linkage: Linkage Assembly and Bearing Air Intake Manifold and Piping Cylinder Heads&Valves Cylinder Heads&Valves Cylinder Heads&Valves Cylinder Heads&Valves Camshaft&Valve Train Fuel Oil In-jection Fuel Oi 1 In-jection Fuel Oil In-jection Fuel Oil In-jection Fuel Oil In-jection Fuel Oil In-jection Turbo, Intake, Intrclr.&Ex-haust 02-380A Exhaust Manifold-Manifold 02-380B Exhaust Manifold: Gasket and Bolting Turbo, Intake, Intrclr.&Ex-haust Turbo, Intake, Intrclr.&Ex-haust SH2651 Rev.1 Entire Page Revised

INDEX (continued)

Component Component Number Descri tion Cate or Volume No.02-385B Cyl inder Bl ock Covers: Gaskets and Bolting Cyl.Block 8 Liners 8 Water Manifold 02-386B Crankcase:

Crankcase Gaskets and Mounting Hardware Crankshaft 8 Bearings 02-390A 02" 390B Intake 8 Intermediate and Exhaust Rocker Shaft Assembly Intake 8 Intermediate and Exhaust Rocker Shaft Assembly Camshaft 8 Valve Train Camshaft&Valve Train 02-390C Main and Connector Pushrods Camshaft 8 Valve Train 02-390D Rocker Arms and Pushrods: Pushrods Connector.

Camshaft 8 Valve Train 02-390E Rocker Arms and Pushrods: Bushings Camshaft 8 Valve Tr ain 02-390F Rocker Arms and Pushrods: Misc.Bolts and Drive Studs Camshaft 8 Valve Train 02-410A Overspeed Trip: Governor Overspeed Trip&Governor 02-410B Overspeed Trip: Governor and Accessory Drive Assembly Overspeed Trip 8 Governor 02-410C Overspeed Trip: Coupling (Flexible&Spider)Overspeed Trip 8 Governor 02-410D Overspeed Trip Vent Valve Overspeed Trip 8 Governor 02-411A Governor Drive: Governor 8 Tachometer Drive Gear and Shaft Overspeed Trip 8 Governor 02-411B Governor Drive: Couplings, Pins 8 Keys Over speed Trip 8 Governor SH2651 vi Rev.1 Entire Page Revised INDEX (continued)

Component Component Number Descri tion 02-413A Governor Linkage Cate or Overspeed Trip&Governor Volume No.02-413 B Fuel Pump Linkage: Automatic Shutdown Fuel Oil Injection 02-415A 02-415B 02"415C 02-420 02-425A 02-435A 02-435B 02-435C 02-436A Governor Assembly: Woodward Governor Governor Assembly-Booster Servomotor Governor Assembly-Heat Exchangers Lube Oil Pump Jacket Water Pump Jacket Water Fittings: Pipe&Fittings Jacket Water Fittings-Supports Jacket Water Inlet Fittings-Valves Intercooler Piping Overspeed Trip 8 Governor Overspeed Trip 8 Governor Overspeed Trip&Governor Lube Oil Jacket Water Jacket Water Jacket Water Jacket Water Turbo, Intake Intercooler

&Exhaust 02-436B Intercooler Piping Coupling, Gaskets, Bolting Turbo, Intake Intercooler 8 Exhaust 02-437 02-441A 02-441B Turbo Water Piping: Pipe 8 Fittings Starting Air Manifold: Piping, Tubing and Fitting Starting Air Manifold: Valves, Filters, and Strainter Jacket Water Air Start 8 Barring Device Air Start&Barring Device 02-441C SH2651 Starting Air Manifold: Supports vii Air Start 8 Barring Device Rev.1 Entire Page Revised INDEX (continued)

Component Number 02-442A 02"442B 02-445 02-450A 02-450B 02-455A 02-455B 02-455C 02"465A 02-465B 02-465C 02-465D Component Descri tion Starting Air Distributor:

Distributor Assembly Starting Air Distributor:

Tubing, Fittings, Gaskets Fuel Oil Booster Pump Fuel Oil Header: Piping/Tubing Fuel Oil Header: Fuel Oil Header Supports Fuel Oil Filters 8 Strainers:

Fuel Oil Filters Fuel Oil Fi 1 ters 8 Strainers:

Strainers Fuel Oil Filters 8 Strainer: Mounting Hardware Lube Oil Lines External: Tubing, Fittings, Couplings Lube Oil Lines-External Supports Lube Oil Lines-External Valves Lube Oil System-Lube Oil Keepwarm Strainer Cate or Air Start&Barring Device Air Start 8 Barring Device Fuel Oil In-jection Fuel Oi 1 In-jection Fuel Oil In-jection Fuel Oil In-jection Fuel Oil In-jection Fuel Oil In-jection Lube Oi 1 Lube Oil Lube Oil Lube Oi 1 Volume No.02"467A 02"467B Turbocharger:

Lube Oil Fitting-Pipe, Tubing, Fittings&Flexible Coupling Turbocharger:

Lube Oil Fittings-Supports Lube Oil Lube Oil SH2651 vi 1 1 Rev.1 Entire Page Revised

INDEX (continued)

Component Number 02-475A 02-475B 02-475C 02-500A 02-500F 02-500G 02-500H 02"500J 02-500K 02-500M 02-500N 02-540A 02"540B.02-540C Component Descri tion Turbocharger:

Bracket Air Butterfly Valve Assembly Turbocharger:

Bracket-Bolting 8 Gaskets Control Panel Assembly: Cabinet/System Control Panel Assembly Accumulator Control Panel Assembly Valves Control Panel Assembly Pressure Switch Control Panel Assembly: Re 1 ays Control Panel Assembly: Solenoid Valves Miscellaneous Equipment:

Piping, Tubing, Fittings Control Panel Assembly: Terminal Boards/Switches/

Miring Lube Oil Sump with Strainer Assembly and Mounting Hardward Lube Oil Sump Tank: Misc.Fittings, Gaskets, Pipe&Bolting Material, Valves Lube Oil Sump Tank: Mounting Hardware Cate or Turbo, Intake, Intrclr.8 Ex-haust Turbo, Intake, Intrclr.&Ex-haust Turbo, Intake, Intrclr.&Ex-haust Control Panel Assembly Control Panel Assembly Control Panel Assembly Control Panel Assembly Control Panel Assembly Control Panel Assembly Control Panel Assembly Control Panel Assembly Lube Oil Lube Oil Lube Oi 1 Volume No.SH2651 ix Rev.1 Entire Page Revised INDEX (continued)

Component Number Component Descri tion Cate or Volume No.02-550 Foundation Bolts: Anchors, Bolts, Misc.Hardware Engine 8 Aux.Sub Base 8 Foundation Bolts 02-630A 02-630B Pyrometer Conduit Assembly: Conduit Pyrometer Conduit Assembly: Conduit Fittings Engine Instru-mentation&Wiring Engine Instru-mentation 8 Wiring 02-630C 02" 630D 02-650A 02-650B Pyrometer Conduit Assembly: Support Pyrometer Conduit Assembly Thermocouple Generator Generator-Generator Control Engine Instru-mentation 8 Wiring Engine Instu-mentation&Wiring Generator Generator 02-650C Generator-Shaft 8 Bearing Generator 02-688A Engine 8 Aux Module Wiring Material-Conduit&Fittings;Pyrometer Assembly-Conduit, Fitting, Supports Engine Instru-mentation 8 Wiring 02-688B 02"688C Engine 8 Aux.Module Wiring Material: Wiring 8 Terminations Engine 8 Aux.Module Wiring Material: Boxes 8 Terminals Engine Instru-mentation 8 Wiring Engine Instu-mentation 8 Wiring 02-688D Engine Alarm Sensors Temperature and Level Switches Engine Instru-mentation&Wiring 02-689 Off Engine Alarm Sensors Sensors Level 8 Pressure Switches Engine Instru-mentation 8 Wiring SH2651 Rev.1 Entire Page Revised INDEX (continued)

Component Number 02-695A 02-695B 02-695C 02-700A 02-700B 02-700C 02-700E 02-700F 02-717A 02-717B 02-717D 02-717E 02-717F Component Descri tion Engine Shutdown Equipment:

Tubing/Fittings 8 Supports Engine Shutdown Equipment:

Valves, Regulator, Orifices Engine Shutdown Trip Switches Jacket Water Standpipe:

Pipe, Fittings, Gaskets Jacket Water Standpipe:

Valves Jacket Water Standpipe:

Supports Jacket Water Standpipe:

Switches Jacket Water Standpipe:

Misc.Bolting Mat.Auxiliary Skid Aux Sub Base 8 Oil 8 Water Piping-Jacket Water: Valves Aux Sub Base 8 Oil 8 Water Piping-Jacket Mater: Pipe, Couplings, Fittings, Orifices, Y-Strainers Sub Base 8 Oil&Water Piping-Jacket Water: Gaskets 8 Bolting Aux.Sub Base 8 Oil&Water Piping-Jacket Mater Supports Cate or Engine Shut-down&Equip-ment Engine Shut-down 8 Equip-ment Engine Shut-down 8 Equip-ment Jacket Water Jacket Water Jacket Water Jacket Water Jacket Water Engine 8 Auxiliary Sub-Base 8 Founda-tion Bolts Jacket Water Jacket Water Jacket Mater Jacket Water Volume No.SH2651 xi Rev.1 Entire Page Revised INDEX (continued)

Component Component Number Descri tion Cate or Volume No.02" 717H 02-717I 02-717 J 02-717K 02-717M 02-717P 02-805B 02-805C 02-8050 02-810A 02"810C 02-810D 02-810 E Aux Sub Base 8 Oil 8 Water Piping-Lube Oil: Piping 8 Fittings Aux Sub Base 8 Oil 8 Water Piping-Lube Oil: Valves Aux Sub Base 8 Oil 8 Mater Piping-Lube Oil: Gaskets 8 Bolting Aux Sub Base 8 Oil&Water Piping-Lube Oil: Supports 8 Mounting Hardware Aux Sub Base 8 Oil 8 Water Piping-Fuel Oil-Piping 8 Fittings Aux Sub Base&Oil 8 Mater Piping-Fuel Oil-Gaskets 8 Bolting Intake Air Filter Intake Air Silencer Flex Connections Misc.Equipment-Heater, Jacket Water Heat Exchanger, Jacket Water Jacket Water Standby Heater Pump Jacket Water: Thermostatic Valve Lube Oil Lube Oil Lube Oil Lube Oil Fuel Oil Fuel Oi 1 Turbo, Intake, Intercooler 8 Exhaust Turbo, Intake, Intercooler 8 Exhaust Turbo, Intake, Intercooler 8 Exhaust Jacket Water Jacket Water Jacket Water Jacket Water SH2651 xi 1 Rev.1 Entire Page Revised INDEX (continued)

Component Component Number Descri tion Cate or Volume No.02-820A 02-820B 02-820C 02-8200 02"820E 02-820F 02-820G 02-825A 02-835D Lube Oil Full Pressure Strainer Heat Exchanger, Lube Oil Misc.Equipment-Heater, Lube Oil Sump Tank Lube Oil System-Aux Lube Oil Pump Full Flow Lube Oil Filter Lube Oil Keep Warm Pump Lube Oil Keep Warm Filter Fuel Oil Day Tank Starting Air Tank Lube Oil Lube Oil Lube Oil Lube Oil Lube Oil Lube Oil Lube Oil Fuel Oil Air Start 8 Barring Device SH2651 xi 1 1 Rev.1 Entire Page Revised

TDI OWNERS GROUP for SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 JACKET WATER INLET MANIFOLD-MANIFOLD ASSEMBLY WITH HARDWARE AND COUPLING AND GASKETS LARGE BORE SCOPE ONLY COMPONENT PART NO.02-316A&B I INTRODUCTION The TDI Emergency Diesel Generator Owner s Group Program for the Shearon Harris Nuclear Power Plant requires Design and equality Revalidation reviews of the structural adequacy of the jacket water inlet manifold assembly with hardware and couplings and gaskets for the effects of normal operating and earthquake loadings.The primary function of the manifold assembly with hardware is to supply jacket water to the jacket water inlet manifold and to support the subject piping in the intended load directions for the loading conditions specified The primary function of the couplings and gaskets is to seal jacket water and accommodate thermal expansion.

The scope of piping embraced by this report includes the large bore (greater than 2"inch diameter)piping components noted on the as-built information transmitted to Impell and obtained during Impell field verifi-cation (Ref.1).Piping components are defined as piping spool pieces, elbows, tees, flanges, Dresser couplings, and the interconnecting welds.This scope is uniquely defined in terms of Transamerica Delaval, Inc.(TDI)part numbers in Reference 1.I I OBJECTIVE The objective of this review was to verify the adequacy of the subject piping components and supports for normal operating and earthquake load-ings, and also, to verify that couplings and gaskets are sufficient for sealing and resistance to aging.III METHODOLOGY The evaluation of the piping components and supports is performed in accordance with the philosophy and intent of the ASME Code Section III, for Class 3 Nuclear Piping and AISC.Towards this end, a criteria document was developed,"Design Criteria for Diesel Generator Large SH2262/1 Page 2 of 3 Diameter Piping for Shearon Harris," which describes the background and provides the techniques for evaluating the subject piping and supports.These criteria are presented in their entirety in Reference 2.guality Revalidation Checklist results were reviewed for acceptability.

The TDI Emergency Diesel Generator Component Tracking System was reviewed for the Shearon Harris site, nuclear and non-nuclear industry experience.

IV RESULTS AND CONCLUSIONS All piping stresses were within the design allowables specified by the ASME Section III Code.The second support west of the 6" TDI Custom Flanges requires stiffening in the lateral direction to accommodate the total support loads (Reference 3).The movements at the Dresser coupling (Style 38)are within the manufac-turer's end movement requirements (Ref.4).There are no service life constraints (Ref.5)because this style of coupling has no significant history of failure.Shelf life (Ref.5)is unlimited as long as the gaskets remain packaged and protected from the elements (light, water, etc.).The coupling is adequate with respect to manufacturer's service condition limits.guality Revalidation Inspection results identified in Appendix B have been reviewed and considered in the performance of this Design Review, and the results are consistent with the final conclusions of this report.There are no TERs associated with this component.

All pipe loads on the engine were tabulated and issued for evaluation.

Based on the above review, it is concluded that the subject piping compo-nents with the modification mentioned above, are adequate for their intended design function at Shearon Harris.V REFERENCES 1."Supporting Calculations for the Evaluation of Shearon Harris Diesel Generator Large Diameter Piping and Support," Impell Report No.02-0630-1259, Rev.0, October 1984.2."Design Criteria for Diesel Generator Large Diameter Piping for Shearon Harris" Impell Report No.02-0630-1258, Rev.0, October 1984.This is included in Appendix III of the final DR/gR report.SH2262/2 REV I

Page 3 of 3 3.Letter from R.Markovich/G.

Shears (Impell)to J.Kammeyer (SWEC),"Required Modifications for Validation of Impell's Design Revi'ew for Component No.02-316AM-Shearon Harris," dated October 10, 1984.4.Dresser Pipe Couplings, Pipe Fittings, and Pipe Repair Products Catalog, No.63.5.Telephone conversation between A.Palumbo and M.Riley of Dresser Manufacturing Company, June 5, 1984.SH2262/3 APPENDIX A COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Page Al of 2 Jacket Water Manifold Manifold Assembly with Hardware, Coupling and COMPONENT Lar e Bore Onl GROUP PARTS LIST NO.02-316'(B SNPS GPL NO.99-316'(B Gaskets UTILITY Carolina Power 8 Li ht Com an TASK DESCRIPTION NO.DR-02-02-316'(B-1 CLASSIFICATION TYPE B TASK DESCRIPTIONS Evaluate structural integrity of the jacket water inl et mani fol d"mani fol d assembly with hardware piping spool pieces, fittings, and supports for the effects of normal operating and earthquake loadings by (a)comparison to previous analyses, (b)review of previous qualification documentation, and/or (c)actual performance of stress evaluation in accordance with the intent and philosophy ASME III Class 3, Impell Design Criteria and AISC.Review information provided on TER.Review the compliance of operating environment parameters with Dresser specifications.

PRIMARY FUNCTION Piping-to supply jacket water to the jacket water inlet manifold.Supports-to provide adequate restraint to the large bore.piping system, in the intended support load directions, for the loading conditions specified.

Coupling and gasket-Seal jacket water and accommodate thermal expansion.

ATTRIBUTE TO BE VERIFIED Structural integrity of large bore (greater than 2 in.dia.)piping spool pieces, fittings, and supports to withstand the effects of normal operating and earthquake loadings.Sufficient strength for sealing parameters and resistance to aging.SPECIFIED STANDARDS None SH2150/1 COMPONENT DESIGN REVIEW CHECKLIST Page A2 of 2 DR-02-02-316A-1 REFERENCES"Design Criteria for Diesel Generator Large Diameter Piping for Shearon Harris," Impell Report No.02-0630-1258, Rev.0, October 1984.Dresser specifications for couplings:

Dresser pipe couplings, pipe fittings, and pipe repair catalog, No.63.DOCUMENTATION'E UIRED Verified piping isometric.

and support sketches, material specification, size and schedule, design parameters (temp., pressure), contents, insulation fitting and gasket design parameters, and support design loading conditions.

GROUP CHAIRPERSON PROGRAM MAMAGERM SH2150/2 Cl I, QJb%qyV s A endix 8 COMPONENT UALITY REVALIDATION CHECKLIST Page B1 of 3 02-02" 316A Jacket Water Inlet Mani fold-Mani fold COMPONENT Assembl with Hardware GPL NO.02-316A SNPS GPL NO.99-316A Carolina Power 8 Light Shearon Harris Nuclear UTILITY Power Plant-Unit 1 REV.NO.1 TASK DESCRIPTIONS En ine 1A-SA l.Assemble and review existing documentation.

2.Obtain sufficient data to support the design review effort.This may be accomplished by developing quality verified as-builts in accordance with Procedure DG-7, or by the Design Group performing a field walkdown.En ine 1B-SB Same as Engine lA-SA ATTRIBUTES TO BE VERIFIED En ine 1A-SA l.guality status of Component Document Package 2.Information necessary for the design review effort~Ei-B Same as Engine 1A-SA ACCEPTANCE CRITERIA En ine lA-SA 1;'Satisfactory

'Document Package 2.Review of.detailed information by the Design Group SH1770/1 COMPONENT UALITY REVALIDATION CHECKLIST Page B2 of 3 02" 02-316A ACCEPTANCE CRITERIA (continued)

~Ei 1B-B Same as Engine lA-SA REFERENCES

~Ei 1-l.QCI N0.52 2.Procedure DG-7~E Same as Engine 1A-SA DOCUMENTATION RE UIRED~Ei A-E 1.Document Summary Sheet, 2.Quality verified as-built isometric drawings for the inlet manifold assembly if available from the Owner.En ine 1B-SB Same as Engine 1-SA GROUP CHAIRPERSON PROGRAM MANAGER COMPONENT REVIEW En ine 1A-SA 1.No EDGCTS site experience documents are in evidence.2.The Design Group will be responsible for closing out the as-built drawings as per Procedure DG-7.The as-built drawings will be Quality verified by the appropriate site Quality organization.

The performance of an engineering walkdown by the Design Group, precludes the issuance of a quality verified as-built'rawing or sketch.SH1770/2 COMPONENT UALITY REVALIDATION CHECKLIST COMPONENT REVIEW (continued)

~Ei IB-EB Same as Engine 1A-SA Page B3 of 3 02-02-316A RESULTS AND CONCLUSION En ine.1A-SA The equality Revalidation effort with respect to this component, as outlined above, is complete.The results have been forwarded to the D'esign Review Group for their evaluation and conclusions in support Bof the final report..I~Bi EB-EB Same as Engine 1A-SA GROUP CHAIRPERSON PROGRAM MANAGER SH1770/3 A endix C Page Cl of 1 EDG'OMPONENT TRACKING SYSTEM: SHEARON HARRIS SITE NUCLEAR AND NON-NUCLEAR INDUSTRY EXPERIENCE

SUMMARY

COMPONENT NO.02-316A&B Effective Printout Date: 10/09/84 Jacket Water Inlet Manifold-Manifold Assembly with Hardware COMPONENT TYPE: and Cou lin and Gaskets EXPERIENCE SHEARON HARRIS None NUCLEAR Internal crack in the jacket water header.NON-NUCLEAR None REFERENCE DOCUMENTS Service Report TPC Nuclear Plant No.3 Maanshan 12/09/83 SHEARON HARRIS STATUS Appears to be an isolated failure and not industry-wide.No effect on the subject structural evalu-ation.The associated subject design meets the intent and philosophy of ASME III design.SH2262/1

TDI OWNERS GROUP for SHEARON HARRIS NUCLEAR POWER PLANT" UNIT 1 JACKET WATER INLET MANIFOLD" MANIFOLD ASSEMBLY WITH HARDWARE AND COUPLING AND GASKETS LARGE BORE SCOPE ONLY COMPONENT PART NO.02-316'(B I INTRODUCTION The TDI Emergency Diesel Generator Owners GroUp Program for the Shearon Harri s Nucl ear Power Pl ant requires Design and gual i ty Reval i dati on reviews of the structural adequacy of the jacket water inlet manifold assembly with hardware and couplings and gaskets for the effects of normal operating and ear thquake 1 oadings.The primary function of the manifold assembly with hardware is to supply jacket water to the jacket water inlet manifold and to support the subject piping in the intended load directions for the loading conditions speci f i ed The primary function of the couplings and gaskets is to seal jacket water and accommodate thermal expansion.

The scope of piping embraced by this report includes the large bore (greater than 2-inch diameter)piping components noted on the as-built information transmitted to Impell and obtained during Impell field verifi-cation (Ref.1).'Piping components are defined as piping spool pieces, elbows, tees, flanges, Dresser couplings, and the interconnecting welds.This scope is uniquely defined in terms of Transamerica Delaval, Inc.(TDI)part numbers in Reference 1.II OBJECTIVE The objective of this review was to verify the adequacy of the subject piping components and supports for normal operating and earthquake load-ings, and also, to verify that couplings and gaskets narc sufficient for sealing and resistance to aging.III METHODOLOGY The evaluation of the piping components.

and supports is performed in accordance with the ph'ilosophy and intent of the ASME Code Section III,'for'lass 3 Nuclear Piping and AISC.Towards this end, a criteria document was developed,"Design Criteria for Diesel Generator Large SH2262/1 I

Page 2 of 3 Diameter Piping for Shearon Harris," which describes the background and provides the techniques for evaluating the subject piping and supports.These criteria are presented in their entirety in Reference 2.guality Revalidation Checklist results were reviewed for acceptability.

The TDI Emergency Diesel Generator Component Tracking System was reviewed for the Shearon Harris site, nuclear and non-nuclear industry experience.

IV RESULTS AND CONCLUSIONS All piping stresses were within the design allowables specified by the ASIDE Section III Code.The second support west of the 6" TDI Custom Flanges requires stiffening in the lateral direction to accommodate the total support loads (Reference 3).The movements at the Dresser coupling (Style 38)are within the manufac-turer's end movement requirements (Ref.4).There are no service life constraints (Ref.5)because this style of coupling has no significant history of failure.Shelf life (Ref.5)is unlimited as long as the gaskets remain packaged and protected from the elements (light, water, etc.).The coupling is adequate with respect to manufacturer's service condition limits.guality Revalidation Inspection results identified iri Appendix B have been reviewed and considered in the performance of this Design Review, and the results are consistent with the final conclusions of this report.There are no TERs associated with this component.

All pipe loads on.the engine were tabulated and issued for evaluation.

Based on the above review, it is concluded that the subject piping compo-nents with the modification mentioned above, are adequate for their intended design function at Shearon Harris.V REFERENCES 1."Supporting Calculations for the Evaluation of Shearon Harris Diesel Generator Large Diameter Piping and Support," Impell Report No.02-0630-1259, Rev.0, October 1984.2."Design Criteria for Diesel Generator Large Diameter Piping for Shearon Harris" Impell Report No.02-0630-1258, Rev.0, October 1984.This is included in Appendix III of the final DR/gR report.SH2262/2-'EV I Page 3 of 3 3.Letter from R.Markovich/G.

Shears (Impell)to J.Kammeyer (SMEC),"Required Modifications for Validation of Impell's Design Review for Component No.02-316AEB-Shearon Harris," dated October 10, 1984.4.Dresser Pipe Couplings, Pipe Fittings, and Pipe Repair Products Catalog, No.63.5.Telephone conversation between A.Palumbo and M.Riley of Dresser Manufacturing Company, June 5, 1984.SH2262/3 A endix B Page Bl of 3 02-02-316B COMPONENT UALITY REVALIDATION CHECKLIST Jacket Water Inlet Manifold-COMPONENT Cou lin and Gaskets GPL NO.02-316B SNPS GPL NO.99-316B Carolina Power 8 Light Shearon Harris Nuclear UTILITY Power Plant-Unit 1 REV.NO.1 TASK DESCRIPTIONS

..~Ei A-EA 1.Assemble and review existing documentation.

2.Verify the type of Dresser coupling installed.

~Ei B-B Same as Engine lA-SA ATTRIBUTES TO BE VERIFIED~Ei IA-EA 1.guality status of Component Document Package 2.Type of Dresser coupling installed~E Same as Engine lA-SA ACCEPTANCE CRITERIA~Ei IA-A 1.Satifactory Document Package ,2.Dressercoupling is 2"-90 Dresser Style 65.SH1768/1 Cl COMPONENT OUALITY REVALIDATION CHECKLIST ACCEPTANCE CRITERIA (continued)

~Ei B-B Same as Engine lA-SA Page B2 of 3 02-02-316B REFERENCES En ine lA-SA l.gCI No.52 2.Dresser Manual, TDI Instruction Manual~Ei B-EB Same as Engine 1A-SA DOCUMENTATION RE UIRED~Ei-E 1.Document Summary Sheet 2.Inspection Report~Ei E-B Same as Engine lA-SA GROUP CHAIRPERSON PROGRAM MANAGER QCK~'j-COMPONENT REVIEW En ine 1A-SA 1.No EDGCTS site experience documents are in evidence.2.No inspection report has been received which fulfills this require-ment.~Ei B-EB Same as Engine lA-SA SH1768/2 COMPONENT EQUALITY REVALIDATION CHECKLIST Page B3 of 3 02-02-316B RESULTS AND CONCLUSION

~Ei-SA The guality Revalidation effort with respect to this component, as outlined above, is complete.The results have been forwarded to the Design Review Group for their evaluation and conclusions in support of the final report.En ine 1B-SB Same as Engine lA-SA GROUP CHAIRPERSON

!4 wWW PR0GRAM MANAGER DC 5(SH1768/3 Cl COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Page 1 of 2 Jacket Water Inlet Manifold-COMPONENT Vent Line To Dischar e Manifold GROUP PARTS LIST NO.02-'316C SNPS GPL NO.99-316C UTILITY Carolina Power 8 Li ht Co.TASK DESCRIPTION NO.DR-02" 02" 316C-0 CLASSIFICATION TYPE B TASK DESCRIPTIOMS A design review is not required for this component based on a review of applicable industry and site experience and a comparison with the lead engine DR/gR report (Comanche Peak).There is no site or industry experience for this component in the EDG Component Tracking System.A field walkdown was performed at Shearon Harris.However, a review of this component was not possible due to its uninstalled condition at the time of the walkdown.Therefore, component acceptability and any subsequent recommendations shall be based upon the lead engine DR/gR report.This component is considered essentially the same based on a comparison of assembly drawings from each of the TDI parts manuals (Vol.II).Reference Dwg.No'.02"316-04.

The lead engine DR/gR report for this component contains no maintenance recommendations.

However, the lead engine report does address a support modification..

Specifically, the report recommended the provision of a more suitable type of moment connection at the support to structural steel interface.

Therefore, based on the above review, it is concluded that t'his component will perform its intended design function at Shearon Harris under all normal operating and earthquake loadings with the provision that the supports are verified or modified to have sufficient moment connection at the support to structural steel interface.

guality revalidation for this component is not deemed necessary.

PRIMARY FUNCTION Not required SH2220/1

COMPONENT DESIGN REVIEW CHECKLIST'TTRIBUTE TO BE VERIFIED H Not required l Page 2 of 2 DR"02-02-316C"0 SPECIFIED STANDARDS Not required REFERENCES Not required DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON ROGRAM MANAGER CK e SH2220/2 8

COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Page 1 of 2 Jacket Water Discharge Manifold/Piping COMPONENT Lar e Bore Onl GROUP PARTS LIST NO.02-317A&B SNPS GPL NO.03-317A&B UTILITY Carol ina Power&Li ht Com an TASK DESCRIPTION NO.DR-02-02-317A&B-0 CLASSIFICATION TYPE B TASK DESCRIPTIONS Design Review for this component is not.required based on the foll'owing:

~A review of the component tracking system indicated that there was no significant applicable industry or site experience.

~A review of the.lead engine DR/gR Reports (Shoreham/Comanche Peak)~A comparison of the jacket water discharge manifold and piping spool pieces and fittings for Shearon Harris with Comanche Peak.~~~The fol 1 owing maintenance modi fi cati ons r ecommendations made on the Lead Engine DR/gR Report should be implemented:

~The Style 65 Dresser couplings are to be replaced with Style 90 or Style 165 Dresser couplings should leaks develop.There are no modification recommendations for this component, however during the Impell field verification several pipe supports were disassembled.

All jacket water manifold supports should be verified for proper installation.

guality Revalidation is not required for this component.

PRIMARY FUNCTION Not required ATTRIBUTE TO BE VERIFIED Not required SH2138/1 0

SPECIFIED STANDARDS Not required COMPONENT DESIGN REVIEW CHECKLIST Page 2 of 2 DR-02-02-317'(B-0 REFERENCES Not required DOCUMENTATION RE UIRED Not required , GROUP CHAIRPERSON

~+ROGRAM MANAGER'SH2138/2

,

TDI OWNERS GROUP for SHEARON HARRIS NUCLEAR POWER PLANT Water Discharge Manifold: Coupling 8 Seals COMPONENT PART NO.: O2-317B'ee Component Part No.02-317A

Page 1 of 2 COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Water Discharge Manifold: COMPONENT Su orts (Lar e Bore Onl GROUP PARTS LIST NO.02-317C SNPS GPL NO.03-317C UTILITY Carolina Power 8 Li ht Com an TASK DESCRIPTION NO.DR-02-02-317C-1 CLASSIFICATION TYPE B TASK DESCRIPTIONS Design Review for this component is not required based on the following:

~A review of the EDG Component Tracking System indicated that there was no significant applicable site or industry experience.

~A review of the lead engine DR/gR Reports (Shoreham/Comanche Peak)~A comparison of the water discharge manifold supports for Shearon Harris with Comanche Peak.There are no maintenance recommendations for this component.

The following modification recommendations made on the lead engine DR/gR report should be implemented:

~Ensure that the supports pads (item No.6 on TDI drawing 02-317-18, Rev.8), for the supports on each of the 5-inch jacket water discharge headers, have a minimum weld of 1/4-inch (3 inches long)between the engine block and the longer sides of the support pad.Also, ensure that the welds between the engine block and the shorter sides of the support pad are 1/4-inch (min.).guality revalidation is not required for this component.

PRIMARY FUNCTION Not required ATTRIBUTE TO BE VERIFIED Not required SH2139/1 REV 1 SPECIFIED STANDARDS Not required COMPONENT DESIGN REVIEW CHECKLIST Page 2 of 2 DR-02-02-317C-0 REFERENCES Not required DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGER C K SH2139/2 Page 1 of 3 COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Engine Driven COMPONENT Jacket Water Pum UTILITY Carolina Power 8 Li ht Com an GROUP PARTS LIST NO.02-425A TASK DESCRIPTION NO.DR-02-02-425A-0 SNPS GPL NO.03-425A CLASSIFICATION TYPE A TASK DESCRIPTIONS

~~Design review for this component is not required based on the.following:

A review of the EDG Component Tracking System indicated that ther e was no site experience.

Significant applicable industry experience was previously addressed in the lead engine report.~A review of the lead engine DR/QR report (Comanche Peak).The engine driven jacket water pumps at Shearon Harris and Comanche Peak are of the same design, but the impellers on the Shearon Harris pump are cut to smaller diameters for lower design flows so that the torques, and consequently the stress levels, are lower.The following maintenance recommendations from the lead engine DR/QR should be implemented.

It is recommended that the key to keyway interface be checked for a tight fit on both the pump shaft and the impeller during pump reassembly.

This, along with the drive fit of the impeller onto the shaft, will preclude past problems where relative motion between shaft and impeller caused fretting and upset of the keyway sides.It is also recommended that the key to keyway interface be checked for a tight fit on both the spline and the pump shaft during pump reassembly.

This, along with the drive fit of the impeller onto the shaft, will preclude past problems where relative motion between spline and pump shaft caused fretting and upset of the keyway sides.The castle nut that drives the external spline on its taper does not have a maximum specified torque"not to be exceeded." It is recommended that the minimum and maximum torque values of 120 ft-lb and 660 ft-lb respectively be included in the Shearon Harris maintenance procedures.

There are no modifications required for the pump, based on the lead engine DR/QR report.'\All Quality Revalidation inspections which have been performed to date have been reviewed and were found to be satisfactory.

SH2603/1

~=l J' COMPONENT DESIGN REVIEW CHECKLIST Page 2 of 3 OR-02" 02-425A" 0 TASK DESCRIPTION (continued)

The following quality inspections have not been performed to date and are recommended:

~Perform a visual inspection of the pump shaft for signs of excessive galling wear or scoring.Document any questionable items with photographs (Engine 1A-SA).~Perform a visual inspection of the pump driven gears for signs of pitting or galling.Document any questionable items with photographs (Engine 1A-SA).~'erfrom a Liquid Penetrant test on'he gear teeth and transition area (gear to shaft)(Engine 1A-SA).Perform a visual inspection on the wear ring for evidence of galling or excessive wear (Engine 1A-SA).PRIMARY FUNCTION Not required ATTRIBUTE TO BE VERIFIED Not required SPECIFIED-'STANDARDS Not required SH2603/2 REFERENCES Not required COMPONENT DESIGN REVIEW CHECKLIST Page 3 of 3'R-02-02-425A-0 DOCUMENTATION RE VIREO Not required GROUP CHAIRPERSON OGRAM MANAGER SH2603/3

COMPONENT UALITY REVALIDATION CHECKLIST Page 1 of 4 02-02"425A COMPONENT Jacket Water Pum GPL NO.02-425A SNPS GPL NO.03-425A Carolina Power 8 Light Shearon Harris Nuclear UTILITY Power Plant-Unit 1 REV.NO.1 TASK DESCRIPTIONS

~Ei A-A 1.Assemble and review existing documentation.

2.Perform a visual inspection of the pump shaft for signs of excessive galling wear or scoring.Document any questionable items with photographs.

3.Perform a visual inspection of the pump driven gears for signs of pitting or galling.Document any questionable items with photographs.

4.Perform a Liquid Penetrant test on the gear teeth and transition area (gear to shaft).5.Perform a visual inspection on the wear ring fot evidence of galling or excessive wear.En ine 18-SB 1.Assemble and review existing documentation.

2.Determine the hardness of the pump shaft.3.Determine the material of the pump shaft.ATTRIBUTES TO BE VERIFIED En ine 1A-SA l.guality status of Component Document Package SH2097/1 O I 4l' COMPONENT UALITY REVALIDATION CHECKLIST ATTRIBUTES TO BE VERIFIED (continued)

~di-EA E 1 d)Page 2 of 4 02-02-425A 2.Lack of excessive galling wear or scoring on the pump shaft 3.Lack of pitting or galling on the pump driven gears 4.5.Surface integrity of the gear teeth and transition area\Lack of scoring, galling or reduction of cross-sectional area on wear ring~di B-1~1.Quality status of component document package 2.Hardness of the jacket water pump shaft 3.Material of the jacket water pump shaft ACCEPTANCE CRITERIA En ine 1A-SA 1.Satisfactory Document Package 2-5.Review of inspection report by Design Group~di EB-B 1.Satisfactory Document Package 2.Review of inspection report by the Design Group 3.Shaft material to be 303SS REFERENCES En ine 1A-SA 2-5.QCI No.52 Approved Site NDE Procedures En ine 1B-SB ,.QCI.No.52 2-3.Approved Site NDE Procedures SH2097/2 COMPONENT UALITY REVALIDATION CHECKLIST DOCUMENTATION RE UIRED~E" i EA-EA 1: Document Summary Sheet 2-5.Inspection Report En ine 1B-SB 1.Document Summary Sheet 2-3.Inspection R port Page 3 of 4 02-02-425A GROUP CHAIRPERSON PROGRAM MANAGER..C COMPONENT REVIEW~Ei A-1.No EDGCTS site experience documents are in evidence.2-5.No inspection reports have been'eceived which fulfill these requirements.

En ine 1B-SB 1.No EDGCTS site experience documents are in evidence.2.A hardness te'st was performed on the pump shaft.The results were reported by TER¹02-072.3.A material comparator test was performed on the pump shaft.The results were reported by TER¹02-072.RESULTS AND CONCLUSION

~Ei!A-EA The equality Revalidation effort with respect to this component, as outlined above, is complete.The results have been.forwarded to the Design Review Group for their evaluation and conclusions in support of the final report.SH2097/3

COMPONENT UALITY REVALIDATION CHECKLIST RESULTS AND CONCLUSION (continued)

~Ei BB-B Same as Engine lA-SA Page 4 of'02"02-425A GROUP CHAIRPERSON

"./,/: L 0<PROGRAM MANAGER.SH2097/4 0"

COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Page 1 of 2 Jacket Water Fittings-Pipe and Fittings COMPONENT Small Bore Sco e Onl GROUP PARTS LIST NO.02-435A SNPS GPL NO.03"435A UTILITY Carolina Power 8 Li ht Com an TASK DESCRIPTION NO.DR-02-02-435A-0 CLASSIFICATION TYPE 8 TASK DESCRIPTIONS A design.review is not required for this component based on a review of applicable industry and site experience, the lead engine DR/gR report (Comanche Peak)and a field walkdown..

The review of the applicable industry and site experience indicates that no generic or significant problems exist which affect the integrity of this component.

The lead engine DR/gR report for this component contains no maintenance

~~~~~~~~~~~~~~~~~~~recommendations or recommended modifications.

This component will maintain its functional capability for all normal and earthquake loadings based upon the field walkdown and a comparison of piping configurations for Comanche Peak.guality Revali'dation for this component is not deemed necessary.

PRIMARY FUNCTION ,Not required ATTRIBUTE TO BE VERIFIED Not required SPECIFIED STANDARDS Not r equired SH2261/1 COMPONENT DESIGN REVIEM CHECKLIST Page 2 of 2 DR-02-02-435A"0 REFERENCES Not required DOCUMENTATION RE UIRED Not requi,red GROUP CHAIRPERSON

  • PROGRAM MANAGER-(SH2261/2 TDI OWNERS GROUP for SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 JACKET WATER FITTINGS.-

PIPE AND FITTINGS LARGE BORE SCOPE ONLY COMPONENT PART NO.02-435A I INTRODUCTION (The TDI Emergency Diesel Generator Owners Group Program for the Shearon Har ri s Nucl eat Power Pl ant r equires Desi gn and equal ity Reval idati on reviews of.the structural

'adequacy of the jacket water pipe and fittings for.the effects of normal operating and earthquake loadings.The primary function of the jacket water pipe and fittings is to carry jacket water from the engine pump discharge to the auxiliary skid jacket water piping.The scope of piping embraced by this report includes the large bore.(greater than 2-.inch diameter)piping components noted on the as-built information transmitted to Impell and obtained during Impell field verifi-cation (Ref.1).Piping components are defined as piping spool pieces, elbows, tees, flanges, and the interconnecting welds.This scope is uniquely defined in terms of Transamerica Delaval, Inc.(TDI)part numbers in Reference l.I I OBJECTIVE The objective of this review was to verify the adequacy of the subject piping components for normal operating and earthquake loadings.III METHODOLOGY The evaluation of the piping components is performed in accordance with the philosophy and intent of the ASME Code Section III, for Class 3 Nuclear Piping.Towards this end, a criteria document,"Design Criteria for Diesel Generator Large Diameter Piping for Shearon Harris," was developed, which describes the background and provides the techniques for evaluating the subject piping and supports: These criteria are presented in their entirety in Reference 2.guality Revalidation Checklist results were reviewed for acceptability.

(SH2028/2 Page 2 of 2 The TDI Emergency Diesel Generator Component Tracking System was reviewed for the Shearon Harris site, nuclear, and non-nuclear industry experience.

RESULTS AND CONCLUSIONS All piping stresses were within the design allowables specified by the ASME Section III Code.Allpipe loads on the engine were tabulated and issued for evaluation.

All supports require reinforcement of their support members.Details on these modifications are-summarized in Reference 3.guality Revalidation Inspection results identified in Appendix B have been reviewed and considered in the performance of this Design Review arrd the results are consistent with the final conclusion of this report.There are no TERs associated with this component.

Based on the above review, it is concluded that the subject piping compo-nents, with the modifications mentioned above, are adequate for their intended design function at Shearon Harris.V REFERENCES

-"Supporting Calculations for the Evaluation of Shearon Harris Diesel Generator Large Diametet Piping and Support," Impell Report No.02-0630-1259, Rev.0, October 1984.'."Design Criteria for Diesel Generator Large Diameter Piping for Shearon Harri s," Impell Repor t No.02-0630-1258, Rev.0, October 1984.This is included in Appendix III of the final DR/gR report.3.Letter from R.Markovich/G.

Shears (Impell)to J.Kammeyer (SWEC),"Required Modifications for Validation of Impell's Design Review for Component No.02-435A-Shearon Harris," dated October 10,1984.SH2028/3 APPENDIX A COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT" UNIT 1 Page Al of 2 Jacket Water Fittings-Pipe and Fittings COMPONENT Lar e Bore Onl GROUP PARTS LIST NO.02-435A SNPS GPL NO.03-717D UTILITY Carolina Power 8 Li ht Com an TASK DESCRIPTION NO.DR"02" 02-435A" 0 CLASSIFICATION TYPE B TASK DESCRIPTIONS

" Evaluate structural integrity of the jacket water fittings piping spool pieces and fittings for effects of normal operating and earthquake loadings by (a)comparison to previous analyses, (b)review of previous qualification documentation, and/or (c)actual performance of stress evaluation'a accordance with intent and philosophy of'ASME III Class 3 and Impell Design Criteria.'eview information provided on TERs.PRIMARY FUNCTION Carry jacket water from the engine pump discharge to the auxiliary skid jacket water piping.ATTRIBUTE TO BE VERIFIED Structural integrity of large bore (greater than 2 inches in diameter)piping spool pieces and fittings due to the effects of normal operating and earthquake loadings.SPECIFIED STANDARDS None REFERENCES

'"Design Criteria for Diesel Generator Large Diameter Piping for Shearon (Harris," Impell Report No.02-0630-1258, Rev.0, October 1984.SH2151/1 S

COMPONENT DESIGN REVIEM CHECKLIST Page A2 of 2 DOCUMENTATION RE UIRED Verified piping isometric, material specification, size and schedule, design parameters (temperature, pressure), contents, additives, insulation, fitting and gasket design parameters.

GROUP CHAIRPERSON PROGRAM MANAGERSH2151/2 A endix B COMPONENT UALITY REVALIDATION CHECKLIST Page Bl of 3 02-02-435A Jacket Mater Fittings-COMPONENT Pi e and Fittin s GPL NO.02-435A SNPS GPL NO.03-435A I Carolina Power 8 Light Shearon Harris Nuclear UTILITY Power Plant-Unit 1 REV.NO.1 TASK DESCRIPTIONS' En ine 1A-SA 1.Assemble and review existing documentation.

2.I Obtain sufficient data to support the design review effort.This may be accomplished by developing quality verified as-builts in accor-dance with Procedure DG-7, or.by the Design Group performing a field walkdown.~Ei IB-EB Same as Engine lA-SA ATTRIBUTES TO BE VERIFIED En ine 1A-SA 1.equality status of Component Document Package 2.Information necessary for the design review effort~Ei BB-BB Same as Engine 1A-SAACCEPTANCE CRITERIA~Ei IA-EA T" 1.Sati'sfactory Document Package 2.Review of detailed information by the Design Group E A SH1807/1 COMPONENT UALITY REVALIDATION CHECKLIST ACCEPTANCE CRITERIA (continued)

~Ei AB-EB Same as Engine lA-SA Page B2 of 3 02"02"435A REFERENCES

~Ei IA-EA A...l..." gCI.No.52 2.Procedure DG-7~Ei 11-EB Same as Engine 1A-SA (--DOCUMENTATION RE UIRED~Ei AA-EA 1.Document Summary Sheet S 2.gual i ty veri f i ed as-bui 1 t i sometri c drawing for the piping and fittings if available from the Owner.En ine 1B-SB Same as Engine 1A-A GROUP CHAIRPERSON PROGRAM MANAGER'.~NAY (COMPONENT REVIEW En ine 1A-SA 1.No EDGCTS site experience documents are in evidence.2.The Design Group will be responsible for closing out the as-built drawings as per Procedure DG-7.The as-built drawings will be guality verified by the appropriate site guality organization.

The performance of an engineering walkdown by the Design Group, precludes the issuance of a quality verified as-built drawing or sketch.SH1807/2 COMPONENT UALITY REVALIDATION CHECKLIST COMPONENT REVIEW (continued)

~Ei 1B-EB Same as Engine lA-SA Page B3 of 3 02"02-435A RESULTS AND CONCLUSION En ine lA-SA The guality Revalidation effort with respect to this component, as out-lined above, is complete.The results have been forwarded to the Design Review Group for their evaluation and conclusions in support of the final repor t.~Ei 1B-EB Same as Engine lA-SA (GROUP CHA?RPERSON 4 BE.PROGRAM MANAGER SH1807/3 A endix C Page Cl of 2 EDG COMPONENT TRACKING SYSTEM: SHEARON HARRIS SITE NUCLEAR AND NON-NUCLEAR INDUSTRY EXPERIENCE

SUMMARY

COMPONENT NO.02-435A Effective Printout Date 10/09/84 COMPONENT.

TYPE: Jacket Water Fittin s-Pi e and Fittin s EXPERIENCE SHEARON HARRIS None NUCLEAR Flow testing of heat exchanger found inadequate.

Inspection revealed'restric-tion in cooling water pipi.ng upstream/downstream of heat exchanger.

Cooling lines flushed.REFERENCE-DOCUMENTS LER Brown's Ferry 3, 296"80016-1, 800513 SHEARON HARRIS STATUS Flushing of clogged or restricted lines is a maintenance concern and: does not affect, nor is affected by, the struc-tural evaluation of piping.During surveillance testing a jacket water leak was identified on 1C diesel.Crack found on 3/8-inch~pipe nipple.Apparent cause of this occurrence was fa-tigue stress caused by vibra-tion of 3/8-inch carbon steel, pipe nipple.Leaking gasket on jacket water cooling discharge header required repair.LER Sal em 1 272"77000, 771117 EPRI" NP-2433, 6/82 Calvert Cliffs 2 318-80003-1i 800110 Refer to small bore piping report'(02-435A).

Maintenance concern.Not related to the subject structural evaluation.

SH2028/1

'

A endix C EXPERIENCE During the monthly performance test on containment spray pump 2C, a cooling water hose on the diesel engine broke.NON"NUCLEAR None REFERENCE DOCUMENTS LER Zion 2 304-78071, 781108 Page C2 of 2 SHEARON HARRIS STATUS Concern is for a cooling water hose.Shearon Harris diesel does not use hoses.not applicable.

SH2028/2 COMPONENT DESIGN REVIEM CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT" UNIT 1 Page 1 of 2'Jacket Mater Fittings: COMPONENT Su orts Lar e Bore Onl GROUP PARTS LIST NO.02"435B SNPS'PL NO.03-4358 UTILITY Carolina Power 8 Li ht Com an TASK DESCRIPTION NO.DR-02-02" 435B-0 CLASSIFICATION TYPE B TASK DESCRIPTIONS Design Review for this component is not required based on the following:

A review of the EDG Component Tracking System indicated that there was no significant applicable industry or site experience.

A review of the lead engine DR/gR Reports (Shoreham/Comanche Peak)Based on previous experience, supports appear to be adequate provided that the analysis of corresponding piping component No.02-435A does not mandate modifi-cations.If the piping analysis warrents modifications to the supports, these.modifications will be addressed in the DR/gR,report for Component No.02-435A.~~~~~~~~~~~~~There are no maintenance recommendations for this component.

'quality revalidation is not required for this component.

PRIMARY FUNCTION Not required ATTRIBUTE TO BE VERIFIED Not required SPECIFIED STANDARDS Not required SH2142/1' REFERENCES Not required COMPONENT DESIGN REVIEW CHECKLIST Page 2 of 2 DR"02"02-435B"0 DOCUMENTATION RE UIRED'ot required GROUP CHAIRPERSON PROGRAM MANAGER (SH2142/2 COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Page 1 of 2 Jacket Water Inlet COMPONENT Fittin s: Valves GROUP PARTS LIST NO.02"435C SNPS GPL NO..99"435A UTILITY Carolina Power 8 Li ht Com an TASK DESCRIPTION NO.DR"02-02-435C-0 CLASSIFICATION TYPE B TASK DESCRIPTION Design review for this component is not required based on a review of the applicable industry and site experience listed in the EDG Component Tracking System and the lead engine DR/gR report (Comanche Peak).There are no maintenance or modification recommme'ndations for this component.

equality revalidation of this component is not required.(-PRIMARY FUNCTION Not required ATTRIBUTE TO BE VERIFIED Not required SPECIFIED STANDARDS Not required REFERENCES Not required SH2699/1 COMPONENT DESIGN REVIEW CHECKLISTDOCUMENTATION RE UIRED Not required Page 2 of 2 DR-02"02-435C-0 GROUP CHAIRPERSON

~PROGRAM MANAGER ((SH2699/2

(-

COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Page 1 of 2 Turbo Water Piping COMPONENT Lar e Bore Onl GROUP PARTS LIST NO.02-437 SNPS GPL NO.03-437A UTILITY Carolina Power 8 Li ht Com an TASK DESCRIPTION NO.DR" 02-02"437-0 CLASSIFICATION TYPE B TASK DESCRIPTIONS Design Review for this compooent is not required based on the following:

~A review of the EDG Component Tracking System indicated that there was no significant applicable industry experience.

0 A review of the lead engine DR/gR Reports (Shoreham/Comanche Peak)~A comparison of the turbo water piping spool pieces and fittings for Shearon Harris with Comanche Peak.T here are no maintenance/modification recommendations made based on the Lead Engine DR/gR Report.guality revalidation is not required for this component.

PRIMARY FUNCTION Not required ATTRIBUTE TO BE VERIFIED Not required SPECIFIED STANDARDS Not requir ed REFERENCES Not required SH2144/1~,,

COMPONENT DESIGN REVIEW CHECKLIST DOCUMENTATION RE UIRED Not required Page 2 of 2 DR-02-02"437-0 GROUP CHAIRPERSON PROGRAM MANAGER ((SH2144/2

COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-'NIT 1 Page 1 of 2 Turbo Water Piping: Pipe and Fittings COMPONENT Small Bore Sco e Onl GROUP PARTS LIST NO.02-437 SNPS GPL NO.03-437A UTILITY Carolina Power 8 Li ht Com an TASK DESCRIPTION NO.OR-02-02-437" 0 CLASSIFICATION TYPE B TASK DESCRIPTIONS Design review for this component is not required based on the review of the lead engine DR/gR report (Comanche Peak)and the applicable industry experi-ence.There is no site experience for this component in the EDG Component Tracking System.There are no maintenance or modification recommendations for this component.

A field walkdown was performed in accordance with the small bore piping criteria document (Ref.1)and indicates that this component will maintain its functional'capability for normal and earthquake loading.guality revalidation for this component is not required.PRIMARY FUNCTION Not required ATTRIBUTE TO BE VERIFIED Not required SPECIFIED STANDARDS Not requiredSH2175/1

REFERENCES COMPONENT DESIGN REVIEW CHECKLIST Page 2.of 2 DR" 02-02-437-0"Engineering Review Criteria Document for the Design Review of TDI Diesel Small Bore Piping, Tubing, and Supports for the TDI Owners'roup," report No.11600.60-DC-02, Revision 0.DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGER C SH2175/2

Page 1 of 2 COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Jacket Water Standpipe:

COMPONENT Pi e Fittin s Gaskets GROUP PARTS LIST NO 02-700A SNPS GPL NO.00-700A UTILITY Carolina Power&Li ht Com an TASK DESCRIPTION NO.DR-02-02-700A-0 CLASSIFICATION TYPE B TASK DESCRIPTIONS A design review is not required for this component based on a review of applicable industry and site experience, the lead engine DR/gR report (Comanche Peak)and a field walkdown.The review of the applicable industry and site experience indicates that no generic or significant problems exist which affect the integrity of this component.

The lead engine DR/gR report for this component contains no maintenance recommendations.

A field walkdown was performed at'Shearon Harris.'owever, a review of this component in its entirety was not possible since portions of piping and tubing were not installed at the time of.the walkdown.Therefore, component acceptability and any subsequent recommendations shall be based upon the lead engine reports (Comanche Peak, Grand Gulf and Catawba).The lead engine reports address.the need for modifications..Specifically, the addition of a three-directional restraint on the standpipe overflow line to ensure vertical support of the riser and the addition of an anchor on the standpipe fill line to isolate the seismic skid piping from the non-seismic off skid piping.It was also recommended that jacket water vent lines be installed in accordance with TDI DWG.No.100546 to prevent accumulation of air in the jacket water system.Therefore, based on the above review it is concluded that this component will perform its intended design function at Shearon Harris under all normal operating and earthquake loadings with the provision that upon-installation the components are verified or modified as follows: SH2263/1 COMPONENT DESIGN REVIEW CHECKLIST TASK DESCRIPTION (continued)

Page 2 of 2 DR-02-02-700A-I

~A three-directional restraint on the standpipe overflow line to ensure vertical support of the riser.~Install an anchor on the standpipe fi 11 line to isolate seismic skid piping from the non-seismic off-skid piping;or if the off-skid piping is seismically designed (or temporarily connected) then the nozzle loading at the TDI (skid)to off-skid interface should be verified to be within the allowable nozzle loading as specified in the TDI piping analysis report, volume II, part 2, page 3.~Jacket water vent lines (air bubble removal system)are installed in accordance with TDI DWG.No.09-810-74046.

guality revalidation for this component is not deemed necessary.

PRIMARY FUNCTION Not required ATTRIBUTE TO BE VERIFIED Not required SPECIFIED STANDARDS Not r equired REFERENCES Not required DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGE C, SH2263/2 REV I COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Page 1 of 2 Jacket Water Standpipe:

COMPONENT Valves GROUP PARTS LIST NO.02-700B SNPS GPL NO.03-700B UTILITY Carolina Power 8 Li ht Com an 4 TASK DESCRIPTION NO.DR" 02-02"7008-0 CLASSIFICATION TYPE B TASK DESCRIPTIONS Design review for this component is not required based on the following:

~A review of the EDG Component Tracking System indicated that there was no significant applicable industry or site experience.

~A review'of the lead engine DR/gR report (Comanche Peak)~Similarity between Shearon Harris and Comanche Peak components

~~~~~~The following maintenance recommendations from the lead engine DR/gR should be implemented:

~Inspect the valves for packing leakage monthly~Replace elastomeric parts every 5 years There are no modifications recommended for this component.

No guality Revalidation is required for this component.

PRIMARY FUNCTION Not required.ATTRIBUTE TO BE VERIFIED Not required SH2226/1 SPECIFIEO STANDARDS Not required COMPONENT DESIGN REVIEW CHECKLIST'age 2 of 2 DR-02-02-700B-0 REFERENCES Not required DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGER C SH2226/2

Page 1 of 2 COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Jacket Water Standpipe:

COMPONENT Pi e Su orts UTILITY Carolina Power L Li ht Co.GROUP PARTS LIST NO.02-700C SNPS GPL NO.00-700C TASK DESCRIPTION NO.DR-02-02-700C-0 CLASSIFICATION TYPE B TASK DESCRIPTIONS A design review is not required for this component based on a review of applicable industry and site experience, the lead engine DR/gR report (Comanche Peak)and a field walkdown.The review of the applicable industry and site experience indicates that no generic or significant problems exist which affect the integrity of this component.

The Lead Engine DR/gR Report for this component contains no maintenance recommendations.

A field walkdown was performed at Shearon Harris.However, a review of this component in its entirety was not possible since portions of piping and tubing were not installed at the time of the walkdown.Therefore, component acceptability and any subsequent recommendations shall be based upon the Lead Engine Reports (Comanche Peak, Grand Gulf and Catawba).The Lead Engine Reports address the need for modification.

Specifically, five tubing supports on the jacket water vent lines did not provide either a minimum of two-directions of restraint or sufficient moment connection between the support members and the supporting structure.

It was also recommended that the 1/4 inch dia.U-bolts used in the support of the standpipe overflow line be increased to 3/8 in.dia.with suitable locking devices installed.

Therefore, based on the above review it is concluded that this component will perform its intended design function at Shearon Harris under all normal operating and earthquake loadings with the, provision that upon installation the tubing supports are'erified or modified to have as a minimum two-directions of restraint and sufficient moment connection.

Also, the U-bolts used in the support of the standpipe overflow line should be a minimum of 3/8 in.in diameter and that suitable locking devices should be installed.

guality Revalidation for this component is not deemed necessary.

SH2264/1 COMPONENT DESIGN REVIEW CHECKLIST PRIMARY FUNCTION Not required ATTRIBUTE TO BE VERIFIED Not required Page 2 of 2 DR"02-02"700C-0 SPECIFIED STANDARDS Not required REFERENCES Not required DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGER SH2264/2

Page 1 of 2 COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Jacket Water COMPONENT Stand i e: Switches UTILITY Carolina Power 8 Li ht Com an GROUP PARTS LIST NO.02-700E SNPS GPL NO.00-700E TASK DESCRIPTION NO: DR" 02" 00" 700E" I CLASSIFICATION TYPE B TASK DESCRIPTIONS The jacket water standpipe switch used at Shearon Harris is similar to that used at Comanche Peak with regard to manufacturer and application, and both are identified as TDI Part No.F-577-066.

The Shearon Harris site differs from Comanche Peak in the model number and operating range of the Dwyer Instruments low differential pressure switch used for low level alarming on the jacket water standpipe.

Shearon Harris uses a Dwyer 0/P switch, Model 1823-80, with operating range of 9 to 85 inches W.C.(set point established at level of 36 inches W.C.-falling).Comanche Peak has a Dwyer D/P switch, Model 1823-40, with operating range of 5 to 44 in.W.C.(set point is at 37 in.W.G.-falling).The sensor tap, located 43 in.below the centerline of the inlet flange on the jacket water standpipe, is piped to the differential pressure switch identi-cally for both Shearon Harris and Comanche Peak sites, The exact additives to be used in the jacket water system at Shearon Harris have not yet been identified, however, information received from site repre-sentatives indicates that the TDI recommendation of sodium dichromate and disodium phosphate treatment shall be'sed.Based on the above, the design function of the jacket water standpipe switch is adequate for its intended service at Shearon Harris.If Shearon Harris chooses different additives in the cooling water, the effects on the jacket water standpipe switch must be evaluated at that time.There is no Shearon Harris site experience, or nuclear or non-nuclear industry experience listed in the EDG Component Tracking System for this component.

There are no maintenance or modification recommendations for this component.

guality Revalidation for this component is not deemed necessary.

Based on the above information, a design review is not required for the jacket water standpipe switches at Shearon Harris.SH2135/1 REV I PRIMARY FUNCTION Not required.COMPONENT DESIGN REVIEW CHECKLIST Page 2 of 2 DR-02-00-700E-0 ATTRIBUTE TO BE VERIFIED Not required SPECIFIED STANDARDS Not required REFERENCES-Not required DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGER CA SH2135/2.

COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Page 1 of 2 Jacket Water Standpipe COMPONENT and Misc.Boltin GROUP PARTS LIST NO.02-700F SNPS GPL NO.03-700F UTILITY Carolina Power&Li ht Com an TASK DESCRIPTION NO.DR" 02-02"700F-0 CLASSIFICATION TYPE TASK DESCRIPTIONS Design review of this component for Shearon Harris is not required based on the following:-

~A review of applicable industry and site experience in the EDG Component Tracking System indicated that no experience items have been reported.~The standpipe and installation at Shearon Harris is very similar to that at Comanche Peak which was previously reviewed and found acceptable.

A review of the lead engine DR/gR reports (Shoreham/Comanche Peak).~A detailed anlysis was performed to seismically qualify the standpipe, Ref.3.No special maintenance or modification requirements were identified in the lead engine design reviews.The following guality inspection is recommended to be performed:

~Verify the as-built bolting conditions to be per design.PRIMARY FUNCTION Not required ATTRIBUTE TO BE VERIFIED Not required SH2554/1 SPECIFIED STANDARDS Not required COMPONENT DESIGN REVIEW CHECKLIST Page 2 of 2 DR-02-02-700F-0 REFERENCES TDI Drawings Nos.101856, 102112, 02-700-Ol-DR 2.3.Ebasco Specification 8 216-73-Tb, Rev.3, 4-25-78,"Diesel Engine Generator Unit and Control Panel for Carolina Power 8 Light Company, Shearon Harris Nuclear Power Plant Units 1 and 2, 3, and 4, Wake County North Carolina.Final Report Volume II, Analytic Modeling of Engine Auxiliaries Seismic gualification of TDI Diesel Generator Sets, Serial Numbers 74046/53 for Carolina Power 8 Light Company, Shearon Harris Nuclear Power Plant Units 1, 2, 3, and 4,Section V, Jacket Water Standpipe.

DOCUMENTATION RE VIREO Not required GROUP CHAIRPERSON PROGRAM MANAGER C X(c~~SH2554/2

COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT" UNIT 1 Page 1 of.2 Aux.Sub Base 8 Oil 8 Water COMPONENT Pi in-Jacket Water: Valves UTILITY Carolina Power 8 Li ht Com an GROUP PARTS LIST NO.02-717B SNPS GPL NO.03-717B TASK DESCRIPTION NO.DR-02" 02-717B-0 CLASSIFICATION TYPE A TASK DESCRIPTION Design review for this component is not required based on the following:

~A review of the EDG Component Tracking System indicated that there was no significant applicable industry and/or site experience.

~A review of the lead engine DR/gR reports (Comanche Peak)~Similarjty between Shearon Harris and Comanche Peak components The following maintenance recommendation from the lead engine DR/gR report should be implemented:

~Inspect the valves for packing leakage monthly.There are no modifications recommended for this component.

No guality Revalidation is required for this component.

PRIMARY FUNCTION Not required ATTRIBUTE TO BE VERIFIED Not required SH2225/1 SPECIFIED STANDARDS Not required COMPONENT DESIGN REVIEW CHECKLIST Page 2 of 2 DR-02-02" 717B" 0 REFERENCES Not required DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGER CK SH2225/2

COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Page 1 of 2 Aux.Sub Base 8 Oil 8 Water Piping-Jacket Water: Pipe, Couplings, Fittings, Orifices, Y-Strainers COMPONENT Lar e Bore Sco e.Onl GROUP PARTS LIST NO.02-717D SNPS GPL NO.03-717D UTILITY Carolina Power 8 Li ht Com an TASK DESCRIPTION NO.DR-02-02-717D-1 CLASSIFICATION TYPE TASK DESCRIPTIONS Design review for this component is not required based on a review of the applicable industry and site experience in the EDG Component Tracking System and the lead engine DR/gR report (Comanche Peak).There are no maintenance recommendations for this component.

However, the lead engine report does address site specific modifications to the skid piping and/or supports.Generic application of these modifications is not required for Shearon Harris since the Comanche Peak modifications were not required for piping operability.

The lead engine modifications were recommended in order to meet the intent and philosophy of the ASME Code for the boundary conditions and assumptions used in the Owners Group analysis.These boundary conditions and assumptions may be somewhat different from those used in the original manufacturer's analysis.Lead engine skid mounted large bore pipe modifica-tions, as they apply to equipment nozzle loads, are addressed, if necessary, in the individual equipment design reviews.guality Revalidation for this component is not required.PRIMARY FUNCTION Not required ATTRIBUTE TO BE VERIFIED Not requir ed SH2640/1 8~W SPECIFIED STANDARDS Not required COMPONENT DESIGN REVIEW CHECKLIST Page 2 of 2 OR-02-02-7170-1 REFERENCES Not required DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON ROGRAM MANAGERSH2640/2

~" t Page 1 of 2 COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Auxiliary Sub-Base 8 Oil 8 Water Piping-Jacket Water: Pipe, Couplings, Fittings, Orifices, Y-Strainer s COMPONENT Small Bore Sco e Onl UTILITY Carolina Power 8 Li ht Co.GROUP PARTS LIST NO.02"717D SNPS GPL NO.03"717D TASK DESCRIPTION NO.DR" 02-02"717D"0 CLASSIFICATION TYPE B TASK DESCRIPTIONS A design review is not required for this component based on a review of applicable industry and site experience, the lead engine DR/gR report (Comanche Peak)and a field walkdown.There is no site experience for this component in the EDG component tracking system.The industry experience, specifically Cleveland Electric, indicates that piping supplied with the diesel did not meet the ASME III code as required.The following discussion concludes that this component.

will meet its intended design function at Shearon Harris, but does not specifically assure any code compliance as this responsibility rests with the utility.A review of the remaining industry experience indicates that no generic or significant pro" blems exist which affect the integrity of this component.

The Lead Engine DR/gR Report for this component contains no maintenance recommendations.

A field walkdown was performed at Shearon-Harris.

However, a review of this component in its entirety was not possible since portions of the piping were not installed at the time of the walkdown.Therefore, component acceptability and any subsequent recommendations shall be based upon the lead engine report.The Lead Engine Report addresses the need for modification.

Specifically, the addition of supports is recommended in order to reduce the unsupported tubing span lengths of the jacket water vent system.The lead engine report recommends no modifications concerning the small bore piping.Therefore, based on the above review it is concluded that this component will perform its intended function at Shearon Harris under all normal operating and earthquake loadings with the provision that upon installation the following criteria are met: SH2216/1

COMPONENT DESIGN REVIEW CHECKLIST TASK DESCRIPTION (continued)

Page 2 of 2 DR-02-02-717D-0 The location of two and/or three directional restraints is such that the unsupported tubing spans do not exceed a maximum of 4 ft.-6 in.~The location of restraints allow for thermal expansion by providing a minimum of 6 inch offset around elbows.guality Revalidation for this component is not deemed necessary.

PRIMARY FUNCTION Hot required ATTRIBUTE TO BE VERIFIED Not required SPECIFIED STANDARDS Not required REFERENCES Not required DOCUMENTATION RE UERED.Not required GROUP CHAIRPERSON PROGRAM MANAGER SH2216/2

COMPONENT UALITY REVALIDATION CHECKLIST Page 1 of 1 02-02" 717 E Aux.Sub Base&Oil 8 Water Piping-COMPONENT J.W.: Gaskets 8 Boltin GPL NO.02-717E SNPS GPL NO.03-717F Carolina Power 8 Light Shearon Harris Nuclear UTILITY Power Plant-Unit 1 REV.NO.1~TASK OESCRIPTIONS No further revi ew of component 02-717E i s required for the f o1 1 owing reasons: a)Component was reviewed on two lead engines with satisfactory results.b)There is no significant industry experience and no site experience reported for this component.

PROGRAM MANAGER AC X4 SH1910/1

COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT" UNIT 1 Page 1 of 2 Aux.Sub Base 8 Oil 8 Water Piping-Jacket Water: Supports COMPONENT Lar e Bore Sco e Onl UTILITY Carolina Power&Li ht Com an GROUP PARTS LIST NO.02-717F SNPS GPL NO.03-717G TASK DESCRIPTION NO.DR-02-02-717F-1 CLASSIFICATION TYPE TASK DESCRIPTIONS Design review for this component is not required based on a review of the applicable industry and site experience in the EDG Component Tracking System and the lead engine DR/gR report (Comanche Peak).There are no maintenance recommendations for this component.

However, the lead engine report does address site specific modifications to the skid piping and/or supports.Generic application of these modifications is not required for Shearon Harris since the Comanche Peak modifications were not required for piping operability.

The lead engine modifications were recommended in orde~to meet the intent and philosophy of the ASME Code for the boundary conditions and assumptions used in the Owners Group analysis.These boundary conditions and assumptions may be somewhat different from those used in the original manufacturer's analysis.Lead engine skid mounted large bore pipe modifications, as they apply to equipment nozzle loads, are addressed, if necessary, in the individual equipment design reviews.guality Revalidation for this component is not required.PRIMARY FUNCTION Not required ATTRIBUTE TO BE VERIFIED Not requiredSH2639/1

SPECIFIED STANDARDS Not required COMPONENT DESIGN REVIEW CHECKLIST Page 2 of 2 DR" 02-02-717F-1 REFERENCES Not required DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGER SH2639/2 8 V.V Page 1 of 2 COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-'NIT 1 Auxiliary Sub-Base 8 Oil 8 Water Piping-Jacket Water Supports COMPONENT Small Bore Sco e Onl COMPONENT PART NUMBER 02-717F UTILITY Carolina Power 8 Li ht Com an TASK DESCRIPTION NO.DR-02-02" 717F-0 SNPS GPL NO.03-717F CLASSIFICATION TYPE B TASK DESCRIPTIONS A design review is not requir ed for thi s component based on a r evi ew of appl i cabl e industry and s i te experience, the l ead engine DR/gR repor t (Comanche Peak)and a field walkdown.There's no site experience for this component in the EDG'Component Tracking System.The industry experience, specifically Cleveland Electric, indicates that supports supplied with the diesel did not meet the ASME III code as required.The following discussion concludes that this component will meet its intended design function at Shearon Harris, but does not specifically assure any code compliance as that responsibility rests with the utility.There is no other industry experience for this component.

The lead engine DR/gR report for this component contains no maintenance recommendations.

A field walkdown was performed at Shearon Harris however, a review of this component in its entirety was not possible since portions of piping/tubing and supports were not installed at the time of the walkdown.Therefore, component acceptability and any subsequent recommendations shall be based upon the lead engine report.The lead engine report addresses the need for modification.

Specifically, it involves a jacket water cooler drain line anchor which required additional weld and an increase in member/plate stiffness.

All other piping and tubing supports required no modification.

Therefore, based upon the above review,, it is concluded that this component will perform its intended design function at Shearon Harr is under all normal operating and earthquake loadings with the provision that upon installation the jacket water cooler drain line supports are verified or modified to have sufficient stiffness and weld.SH2213/1 C~p+I'pEW II

.COMPONENT DESIGN REVIEW CHECKLIST~~~guality Revalidation for this component is not deemed necessary.

Page 2 of 2 DR" 02-02-717F-0 PRIMARY FUNCTION Not required ATTRIBUTE TO BE VERIFIED Not required SPECIFIED STANDARDS Not required REFERENCES Not required DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGER SH2213/2

Page 1 of 1 02-02-810A COMPONENT UALITY REVALIOATION CHECKLIST Carolina Power 8 Light Miscellaneous Equipment-Shearon Harris Nuclear COMPONENT Heater Jacket Water UTILITY Power Plant-Unit 1 GPL NO.02-810A SNPS GPL NO.03-800A REV.NO.2 TASK OESCRIPTIONS No further review of component 02-810A is required for the following reasons: a)There is no site or industry experience reported for this component.

b)Component was reviewed on the lead engines (Shoreham).

The following recommendations, made in the Shoreham DR/gR report should be followed by Shearon Harris.)I Preventive maintenance included in the TDI manual should be accomplished.

Inspections scheduled at 18-month intervals should consist of the following.

Measure heater insulation resistance and replace heate~if degradation of insulation resistance is noted.Thoroughly clean heater element of deposits and inspect for signs of deterioration.

Check calibration and inspect condition of thermostat and recalibrate or replace thermostat when necessary.

GROUP CHAIRPERSON PROGRAM MANAGER C.%ca SH1814/1 REV I

Page 1 of 2 COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 COMPONENT Jacket Water Heat Exchan er UTILITY Carolina Power 8 Li ht Com an GROUP PARTS LIST NO.02"810C TASK DESCRIPTION NO.DR-02-02-810C-1 SNPS GPL NO.10-103 CLASSIFICATION TYPE B TASK DESCRIPTIONS Design review for this component is not required based on the following:

~A review of the EDG Component Tracking System indicated that there was no significant applicable industry and/or site experience, except that already addressed in lead engine report.~A review of the lead engine DR/gR report (Comanche Peak).The jacket water heat exchangers at both Comanche Peak and Shearon Harris are single pass, tube and shell design ASME III heat exchangers.

At Comanche Peak the jacket water heat exchanger was manufactured by Thermchanger while at Shearon Harris it was manufactured by American Standard.American Standard has been manufacturing exchangers for many industrial appli-cations since 1917.The following maintenance recommendation from the lead engine DR/gR report should be implemented:

~Periodic flushing of the heat exchanger to prevent fouling and corrosion.

As an alternative, service water chemistry control may be used to maintain heat exchanger performance and integrity.

~Leakage through the packing that is visible can be eliminated by careful bolt adjustment to compress the neoprene packing.It is recommended that the packing rings be replaced and not reused if head removal is required, due to work hardening of the packing.There are no modifications recommended based on the lead engine DR/gR report.No guality Revalidation is required for this component.

PRIMARY FUNCTION Not required SH2269/1 REV.I COMPONENT DESIGN REVIEW CHECKLIST ATTRIBUTE TO BE VERIFIED Not required Page 2 of 2 DR-02" 02-810C" 0 SPECIFIED STANDARDS.'.....".:Not,required REFERENCES Not required DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGER CASH2269/2

COMPONENT UALITY REVALIDATION CHECKLIST Page 1 of 1 02-02-810D Jacket Water Standby COMPONENT Heater Pum GPL NO.02-810D SNPS GPL NO.10-107 Carolina Power&Light Shearon Harris Nuclear UTILITY Power Plant-Unit 1 REV.NO.1TASK DESCRIPTIONS No further review of component 02-810D is required for the following reasons: a)Component was reviewed on two lead engines with satisfactory results.b)There is no significant industry experience and no site experience reported.for this component.

c)Type C component-Failure has little bearing on the effective use or operation of D.G.GROUP CHAIRPERSON PROGRAM MANAGER SH1911/1

COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT" UNIT 1 Page 1 of 2 Jacket Water: COMPONENT Thermostatic Valve GROUP PARTS LIST NO.02-810E SNPS GPL NO.03-515 UTILITY Carolina Power 8 Li ht Co.TASK DESCRIPTION NO.DR-02-02-810E" 1 CLASSIFICATION TYPE B TASK DESCRIPTIONS Design review for this component is not required based on the following:

~A review of the EDG Component Tracking System indicated that there was no significant applicable industry and/or site experience, except that previously addressed in the lead engine report.~A review of the lead engine DR/gR report (Comanche Peak).Both Comanche Peak and Shearon Harris have AMDT Controls Corp.Model BOAS valves.The following maintenance recommendations from the lead engine DR/gR report should be implemented:

~Replace the thermal power element at 3 to 5 year intervals.

'In addition the following inspection should be performed:

~Proper orientation of the valve should be verified by field inspection (i.e., exhaust ports should be centerline horizontal, if not, adequate vent lines must be installed).

No modifications are required pending results of above inspection.

equality Revalidation is not required for this component.

PRIMARY FUNCTION Not required ATTRIBUTE TO BE VERIFIED Not required SH2207/1 REV I SPECIFIED STANDARDS Not required COMPONENT DESIGN REVIEW CHECKLIST Page 2 of 2 DR-02-02-810E-0 REFERENCES Not required DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGER SH2207/2 Cl COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Page 1 of 2 COMPONENT C linder Heads UTILITY Carolina Power 8 Li ht Com an GROUP PARTS LIST NO.02"360A TASK DESCRIPTION NO.DR-02-02-360A-1 SNPS GPL NO.03-360A CLASSIFICATION TYPE A TASK DESCRIPTIONS Design review for this component is not required based on review of the lead engine DR/QR reports (Shoreham/Comanche Peak), the August 1984 Phase I cylinder head report, and the reported applicable industry experience.

There is no reported site experience in the EDG Component Tracking System.Quality inspections conducted to date have been reviewed and are considered satisfactory with the exception of six heads rejected for having fire deck thicknesses below the minimum acceptable value.For increased engine reliability CP8 L is replacing all sixteen heads on Engine 1A-SA and three cylinder heads on Engine 1B-SB with acceptable cylinder heads from engines originally purchased for SHNPP Unit 2.Once this replacement is incorporated, all Shearon Harris cylinder heads will be of the improved Group III design.A description of the design improvements from one Group to another is given in the Phase I report.Additional inspections performed by CPCL on Unit 2 engine A revealed a cracked exhaust valve guide on cylinder head L3.Because of this, CP&L borescopically inspected all of the Unit 1 exhaust valve guides and found no others to be cracked.Since all sixteen cylinder heads are being replaced on Engine 1A-SA, it is recommended that the following Quality inspections as delineated in the CQRC be performed on four of these replacement heads (25K sample plan).Perform a liquid penetrant test of the valve seating surfaces.~Perform a magnetic particle test on the fire deck area excluding the valve seating area.~Determine the thickness of the fire deck area by performing an Ultrasonic test at six locations on the deck.The same Quality inspections described above should also be performed on one of the three replacement cylinder heads for Engine 1B-SB.There are no modification recommendations for this component, however, the following maintenance items are recommended:

SH2382/1 REV 1

"~

COMPONENT DESIGN REVIEW CHECKLIST Page 2 of 2 DR-02" 02-360A-0 Blow-over the engine after each operation of the engine to ensure against harmful effects of water leaks.In the event that water is detected as a result of a cylinder head leak, the cylinder head should be replaced.Visually inspect the fuel injection port on each cylinder head for water 1eaks during the normal monthly engine run.If water leakage is detected, the cylinder head should be replaced.PRIMARY FUNCTION Not required ATTRIBUTE TO BE VERIFIED Not required SPECIFIED STANDARDS Not required REFERENCES"Not required DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGER C&SH2382/2

COMPONENT UALITY REVALIDATION CHECKLIST Page 1 of 5 02-02-360A Cylinder Head Valves-COMPONENT C linder Heads GPL NO.02-360A SNPS GPL NO.03-360A Carolina Power 8 Light Shearon Harris Nuclear UTILITY Power Plant-Unit 1 REV.NO.2 TASK DESCRIPTIONS En ine lA-SA 1.Assemble and review existing documentation.

2.Perform a Liquid Penetrant test of the valve seating surfaces.3.Perform a Magnetic Particle test on the fire deck area excluding the valve seating area.4.Determine the thickness of the fire deck area by performing an Ultrasonic test at six locations on the deck (See Attachment A).~Ei ll-1 Same as Engine 1A-SA NOTE: For.cylinder heads fabricated prior to September 1980, NDE inspections are to be performed on a 100K sample plan.For cylinder heads fabricated after September 1980, NDE inspections are to be performed on a 25K sample plan.ATTRIBUTES TO BE VERIFIED~Ei EA-EA l.guality status of Component Document Package 2 3A Surface integrity of the valve seats and fire deck area4.Thickness of the fire deck ar ea~E Same as Engine 1A-SA S01744/1 Page 1 of 5 02-02-360A COMPONENT UALITY REVALIDATION CHECKLIST Cylinder Head Valves-COMPONENT C linder Heads GPL NO.02-360A SNPS GPL NO.03"360A Carolina Power 8 Light Shearon Harris Nuclear UTILITY.Power Plant-Unit 1 REV.NO.2TASK DESCRIPTIONS

~Ei lA-SA 1.Assemble and review existing documentation.

2.Perform a Liquid Penetrant test of the valve seating surfaces.3.Perform a Magnetic Particle test on the fire deck area excluding the valve seating area.4.Determine the thickness of the fire deck area by performing an Ultrasonic test at six locations on the deck (See Attachment A).~Ei 1B-B Same as Engine 1A-SA NOTE: For cylinder heads fabricated prior to September 1980, NDE inspections are to be performed on a 100K sample plan.For cylinder heads, fabricated after September 1980, NDE inspections are to be performed on'a 25K sample plan.ATTRIBUTES TO BE VERIFIED En ine 1A-SA 1.guality status of Component Document Package 2-3.Surface integrity of the valve seats and fire deck area 4.Thickness of the fire deck.area~Ei-8 Same as Engine 1A-SA S 01744/1

ACCEPTANCE CRITERIA~Ei 1A-EA COMPONENT UALITY REVALIDATION CHECKLIST Page 2 of 5 02-02-360A 1.Satisfactory Document Package 2.3.No cracks-allowed in the seating surface.Pin holes that do not exceed 1/32" diameter numbering 3 or less in one surface and not closer to-each other than 1/8", are'cceptable.

Acceptance criteria standard is ASTM E-125 for a Magnetic Particle test.A)Relevant indications are: 1)Hot tears and cracks, linear indications that exceed ASTM E-125, Class I-l.2)Shrink that exceeds ASTM E-125, Class II-1.3)Inclusions that exceed ASTM E-125, Class III-1.4)Porosity that exceeds ASTM E-125, Class V-1.B)C)Any inclusion, shrink or porosity that exceeds ASTM E-125 is a reportable indication and shall be reported to the Design Group.In addition, linear indications exceeding 1/4" shall also be reviewed by the Design Group.I Indications that do not exceed the ASTM E-125 as described in 3A are acceptable.

4.All fire deck thickness readings to be recorded.Nominal fire deck thickness is 0.500";Minimum thickness is 0.400".~Ei-EB Same as Engine 1A-SA REFERENCES

~Ei BA-EA l.gCI No.52 2-4.Approved Site NDE Procedures, TERS99-001, TERS99-012'01744/2

COMPONENT UALITY REVALIDATION CHECKLIST Page 3 of 5 02"02-360A REFERENCES (continued)

~Ei EB-EB Same as Engine 1A-SA DOCUMENTATION RE UIRED~Ei IA-EA 1.Document Summary Sheet 2-4.Inspection Report En ine 1B-SB Same as Engine 1-SA GROUP CHAIRPERSON PROGRAM MANAGERCOMPONENT REVIEW En ine 1A-SA All EDGCTS site experience documents were assembled and reviewed with unsatisfactory results.NCR No.84-1635 remains open.2 3.4.No inspection report has been received which fulfills this requirement.

An Ultrasonic test was performed with unsatisfactory results.The thickness on five of the cylinder heads was less than.400" and.were recommended to be replaced.This was reported by TERS02-017.En ine IB<<SB 1.No EDGCTS site experience documents are in evidence.2.3.A Liquid Penetrant test was performed on the valve seating surfaces of cylinder heads R3, R6, L3 and L6.This was reported by TEfS02-064.1 A Magnetic Particle.test was performed on the fire decks of cylinders R3, R6, L3, and L6.This was reported by TERS02-064.S01744/3

COMPONENT UALITY REVALIDATION CHECKLIST Page 4 of 5 02-02-360A COMPONENT REVIEW (continued) 4.An Ultrasonic test was performed with unsatisfactory results.The thickness of cylinder head L8 was less than.400" and was recommended to be replaced.This was reported by TEIL 02-064.RESULTS AND CONCLUSION En ine lA-SA The guality Revalidation effort with respect to this component, as outlined above, is complete.The results have been forwarded to the Design Review Group for their evaluation and conclusions in support of the final report.~Ei 8-SB Same as Engine 1A-SA GROUP CHAIRPERSON PROGRAM MANAGER CS 01744/4 COMPONENT UAI ITY REVALIDATION CHECKLIST Page 5 of 5 02-02-360A Ul TRA~Qi~l!C Ti:.i QF)I-l B.QTlQQ AP gyL 0%~~~~~0.0 0~0~0 0-0~~0 0 COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Page 1 of 2 Cylinder Head Valves: COMPONENT Intake and Exhaust Valves UTILITY Carolina Power 8 Li ht Com an GROUP PARTS LIST NO.02-360B TASK DESCRIPTION NO.DR-02-02" 360B-0 SNPS GPL NO.03-3608 CLASSIFICATION TYPE B TASK DESCRIPT ONS Design review for this component is not required based on the following:

A review of the Comanche Peak and Shoreham DR/gR reports, which establish the acceptability of the cylinder head valves for their intended purpose.~~A review of site, nuclear, and non-nuclear industry experience indicated that there had been no design related failures associated with this component.

The cylinder head valves are identical on all the Owners Group TDI diesel engines (TDI Part No.03-360-02"OD).

The primary nuclear and non-nuclear industry experiences associated with this component have been chrome plate flaking, scuffing, and scoring, and exhaust gas blowby due to lack of concentricity of the valve and seat.Because of the small, number of hours nuclear service diesels are expected to operate between inspections,'uch problems will not noticeably affect engine performance.

The valve inspections outlined in the DR/gR reports also applies to the engines at Shearon Harris.This inspection should be performed for all new or reworked cylinder heads after an initial 500-600 hours of operation:

~Remove the subcover bonnet and inspect the interior for soot which indicates valve blowby.Corrective action should be taken if this situation is found to exist.There are no modifications recommended for this component.

All quality inspections that have been performed to date have been reviewed.Unsatisfactory conditions have been dispositioned by the utility.The following equality Revalidation inspection recommendations are made to ensure proper component performance and quality and should be performed on both engines:~Perform a visual inspection to verify adequate valve seating.There should be a unifo'rm linear metallic ring on each valve ring.SH2089/1 I~

COMPONENT DESIGN REVIEW CHECKLIST TASK DESCRIPTIONS (conti nued)Page 2 of 2 DR" 02" 02-360B-0~Perfor m a visual examinati on of the valve and valve ring for scuffing and erosion on valve ring or valve seat area.~Perform a dimensional check of the valve to valve guide clearance.

~Perform a vi sual examination of the top of the val ve stems for scuffing and pitting.-'--=.'-.--'=-In'addi.tion.

the..fo1:lowing-quality inspection is required to be-performed on.."..-engine lA-SA.~Perform a liquid penetrant test on the blended radius of the stem head for cracking.PRIMARY FUNCTION Not required ATTRIBUTES TO BE VERIFIED Not required SPECIFIED STANDARDS Not required REFERENCES Not required DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON ROGRAM MANAGER SH2089/2 COMPONENT UALITY REVALIDATION CHECKLIST Page 1 of 4 02-02-360B Cylinder Head Valves: COMPONENT Intake 8 Exhaust Valves Carolina Power 8 Light Shearon Harris Nuclear UTILITY Power Plant-Unit 1 GPL NO.02-360B REV.NO.2 SNPS GPL NO.03-360B TASK DESCRIPTIONS En ine 1A-SA 1.Assemble.and review existing documentation.

2.Perform a visual inspection to verify adequate valve seating.3.Perform a 4.Perform a visual examination of the valve and valve ring.visual examination.of the valve stems.5.Perform a dimensional check of the valve to valve guide clearance.

6.Perform a visual examination of the top of the valve stems.7.Perform a Liquid Penetrant test on the blended radius of the stem head.En ine 1B-SB Same as Engine lA-SA ATTRIBUTES TO BE VERIFIED En ine 1A-SA 1.guality status of Component Document Package 2.Linear metallic appearing ring on valve ring 3.Surface integrity of the valve and valve ring 4.Integrity of the valve stem surface SH2098/1 c.~

Page 2 of 4 02-02-360B ATTRIBUTES TO BE VERIFIED (continued)

~di 1A-EA E 1 d)5.Proper valve to valve guide clearance 6.Surface integrity of the valve stems 7.Surface integrity of the stem head~di B-EB Same as Engine 1A-S$ACCEPTANCE CRITERIA~di EA-EA 1.Satisfactory Document Package 2.Appearance of a uniform linear metallic ring on valve ring 3.No scuffing erosion on valve ring or valve seat area 4.No scuffing or scoring of chrome plate on valve.stems 5.Review of inspection report by Design Group 6.Lack of scuffing and-pitting on top of the valve stems 7.No cracking at the blended radius between the valve stem and valve head En ine 1B-SB Same as Engine lA-SA SH2098/2 REFERENCES En ine 1A-SA COMPONENT UALITY REVALI DATION CHECKLIST Page 3 of 4 02-02-3608 1.gCI No.52, 2-7.Approved Site NDE Procedures, TDI Instructions Manual~Ei B-EB Same as Engine 1A-SA DOCUMENTATION RE UIRED~Ei EA-EA 1.Document Summary Sheet 2-7.Inspection Report En ine 18-SB Same as Engine 1A-SA GROUP CHAIRPERSON.V'ROGRAM MANAGER~C Xg COMPONENT REVIEW.~Ei BA-A 1.No EDGCTS site experience documents are in evidence.2 70 No inspeGti on requirements.

reports have been recei ved whi ch f ul fill these En ine 18-SB 1.No EDGCTS site experience documents are in evidence.2-6.No inspection requirements.

reports have been received which fulfill theseSH2098/3 COMPONENT UALITY REVALIDATION CHECKLIST COMPONENT REVIEW (continued)

En ine 1B-SB Page 4 of 4 02"02-360B 7.Liquid Penetrant tests were performed on the blended radius of the stem head with indications noted on the 3L exhaust valve and 3R intake and exhaust valves.RESULTS AND CONCLUSION

~Ei 1A-SA~The guality Revalidation effort with respect to this component, as out-lined above, is complete.The results have been forwarded to the Design Review Group for their evaluation and conclusions in support of the final report.En ine 1B-SB Same as Engine lA-SA GROUP CHAIRPERSON f c+PROGRAM MANAGER C g SH2098/4 COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Page 1 of 2 Cylinder Head And COMPONENT Valves: Boltin And Gaskets UTILITY Carolina Power 8 Li ht Com an GROUP PARTS LIST NO.02-360C SNPS GPL NO.03-360C TASK DESCRIPTION NO.DR-02-02-360C-0 CLASSIFICATION TYPE B TASK DESCRIPTIONS Design review for this.component is not required based on the review of the lead engine DR/gR report (Comanche Peak)'nd the applicable industry experience.

There is no site experience in the EDG Component Tracking System for this component.

There are no modification or maintenance recommendations for this component.

The following guality Revalidation inspections should be performed on all station engines:~'Verify that the proper gaskets are installed in accordance with specification requirements;

~Perform a visual inspection of the gasket for signs of distress.PRIMARY FUNCTION Not required ATTRIBUTE TO BE VERIFIED Not required SPECIFIED STANDARDS Not requir ed REFERENCES Not requiredSH2192/1 COMPONENT DESIGN REVIEW CHECKLIST DOCUMENTATION RE UIRED Not required Page 2 of 2 DR-02-02-360C-0 GROUP CHAIRPERSON PROGRAM MANAGERSH2192/2 COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Page 1 of 2 Cylinder Head COMPONENT and Valves: S rin s GROUP PARTS LIST NO.02"360D SNPS GPL NO.03-360D UTILITY Carolina Power and Li ht Co.TASK DESCRIPTION NO.DR-02-02" 360D-0 CLASSIFICATION TYPE B TASK DESCRIPTIONS Design review for this component is not required based on the following:

~A review of the Comanche Peak and Shoreham DR/gR Reports, which establishes the acceptability of the valve spring for its intended purpose.A review of the nuclear and non-nuclear industry experience listed in the Component Tracking System indicated that there had been no design related failures associated with this component.

The valve springs are identical on all the Owners Group TDI diesel engines (TDI Part No.03-360-02-0M).

Ther e have been several non-nuclear experiences where improperly shot peened springs were installed on some TDI engines.These springs failed during service and in some cases caused engine damage.Inspections performed on engine 1B did not find any defective springs.The results were reported on TER 02-080.There are no modification or maintenance recommendations for this component.

The followi.ng equality Revalidation inspection is made to ensure component quality and should be performed on engine 1A:~Visually inspect and document the'Color code of the valve springs.There should be no grey springs with brown stripes.'RIMARY FUNCTION Not required ,SH2095/1

COMPONENT DESIGN REVIEW CHECKLIST Page 2 of 2 DR" 02" 02-360D" 0 ATTRIBUTE TO BE VERIFIED Not required SPECIFIED STANDARDS Not required REFERENCES Not required DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGER SH2095/2 COMPONENT UALITY REVALIDATION CHECKLIST Page 1 of 3 02-02-360D COMPONENT Valve S rin GPL NO.02-360D SNPS GPL NO.03-360D Carolina Power 8 Light Shearon Harris Nuclear UTILITY Power Plant-Unit 1 REV.NO.1 TASK DESCRIPTIONS En ine 1A-SA 1.Assemble and review existing documentation.

2.Visually inspect and document the color code of the valve springs.~Ei 1B-EB Same as Engine 1A-SA ATTRIBUTES TO BE VERIFIED En ine lA-SA 1.guality status of Component Document Package 2.Proper color coding of the valve springs~Ei 1B-1 Same as Engine 1A-SA ACCEPTANCE CRITERIA En ine IA-SA 1.Satisfactory Document Package 2.No gray springs with brown stripes exist.SH2278/1 COMPONENT UALITY REVALIDATION CHECKLIST Page 2 of 3 02"02"360D ACCEPTANCE CRITERIA (continued)

~~EB-BB Same as Engine lA-SA REFERENCES En ine lA-SA 1.(CI No.52 2.Approved Site NDE Procedures, TDI Parts Manua1 En ine 1B-SB Same as Engine 1A-SA DOCUMENTATION RE UIRED En ine 1A-SA 1.Document Summary Sheet 2.Inspection Report~Ei'-BB Same as Engine-A GROUP CHAIRPERSON PEB AN NAN E E N'OMPONENT REVIEW En ine 1A-SA 1.No EDGCTS site experience documents are in evidence.2.No inspection report has been received which fulfills this requirement.

SH2278/2

COMPONENT UALITY REVALIDATION CHECKLIST Page 3 of 3 02-02-360D COMPONENT REVIEW (continued)

~Ei ll-EA 1.No EDGCTS site experience documents are in evidence.2.A visual inspection of.the valve springs was performed with satisfactory results.This was reported by TEfS02-080.RESULTS AND CONCLUSION

'Ei lA-EA The-guality Revalidation effort with respect to this component, as outlined above, is complete.The results have been forwarded to the Design Review Group for their evaluation and conclusions in support of the final report.En ine 1B-SB Same as Engine lA"SA E GROUP CHAIRPERSON

~%tee~g+Ec f>>PR,OGRAM MANAGER C.'\.SH2278/3 COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Page 1 of 2 COMPONENT Fuel In ection Pum GROUP PARTS LIST NO.02-365A SNPS GPL NO.03-365A UTILITY Carolina Power 8 Li ht Co.TASK DESCRIPTION NO.DR" 02" 02" 365A-1 CLASSIFICATION TYPE B TASK DESCRIPTIONS Design review for this component is not required based on the following:

~A review of the Component Tracking System indicated that there was no significant applicable industry and/or site experience, except that previously addressed in the lead engine report.~A review of the lead engine DR/gR reports (Shoreham/Comanche Peak).~The component is identical to the lead engine component.

The following maintenance recommendations from the lead engine DR/gR should be implemented:

To augment the maintenance procedures, it is recommended that the utility inspect this component for leaks during the routine engine walk-around and that one pump be disassembled, inspected and tested during alternate refueling outages.Based on the results, a decision can be made regarding the necessity to examine the remainder of the pumps.Because the pump relies on very close clearances and tolerances on the operating parts it is essential that the fuel oil be clean.No modifications are required for this component.

guality Revalidation is not required for this component.

PRIMARY FUNCTION Not required ATTRIBUTE TO BE VERIFIED Not required SH2210/1 REV.I SPECIFIED STANDARDS Not required COMPONENT DESIGN REVIEW CHECKLIST Page 2 of 2 DR"02"02"365A"0 REFERENCES Not required DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGER SH2210/2 COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT" UNIT 1 Page 1 of 2 Fuel Injection Equipment:

COMPONENT Fuel In ection Ti s GROUP PARTS LIST NO.02-365B SNPS GPL NO.03-365B UTILITY Carolina Power L Li ht Com an TASK DESCRIPTION NO.DR-02-02-365B-1 CLASSIFICATION TYPE B TASK DESCRIPTIONS Design review for this component is not required based on the following:

~A review of the EDG Component Tracking System indicated that there was no significant applicable industry or site experience, except that previously addressed in the lead engine report.~A review of the lead engine DR/QR report (Comanche Peak).~The component is identical to the lead engine component.

The following maintenance recommendations from the lead engine DR/QR report should be implemented:

~TDI SIM Nos.107 and 108 should be incorporated in the Shearon Harris maintenance procedures.

It is recommended that the utility inspect this component for leaks during the monthly engine test run.At each refueling outage, it is recommended that each assembly be disassembled, inspected, cleaned, and reassembled.

At this time, each assembly should be pop tested and have the spray pattern checked.No modifications are recommended for this component.

Quality revalidation is not required for this component.

PRIMARY FUNCTION Not required SH2202/1 REV.1 COMPONENT DESIGN REVIEW CHECKLIST ATTRIBUTE TO BE VERIFIED Not required Page 2 of 2 DR-02" 02-365B-0 SPECIFIED STANDARDS Not required REFERENCES Not required DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON

~PROGRAN NANAGER M SH2202/2 Page 1 of 3COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT" UNIT 1 Fuel Injection Equipment COMPONENT Tube Assembl ,GROUP PARTS LIST NO.02-365C UTILITY Carolina Power 8 Li ht Com an TASK DESCRIPTION NO.DR-02-02"365C"0 SNPS GPL NO.03"365C CLASSIFICATION TYPE B TASK DESCRIPTIONS Design review for this component is not required based on the review of the EDG Component Tracking System for applicable industry and site experience (Refs.2 and 3)and the lead engine DR/gR reports (Shoreham/Comanche Peak).The fuel oil injection lines transfer fuel from the high pressure fuel injection pumps to the fuel inject'ors for the engine cylinders.

The injection lines experience the extreme pulsating pressure of the plunger operated injection pumps.For TDI nuclear standby diesel generators, the pressure pulses are 3 ksi minimum pressure to 14.5 ksi maximum pressure.It was~~~~~~~~~~~~~~~~determined from fracture mechanics and fatigue analyses that flaws on the inner surface of the tubing potentially cause fatigue failure of the tubing from pulsating fuel pressure (Ref.1).Industry experience (Rev.2)indicates a number of fuel leakage incidents involving the high pressure fuel oil tube assemblies.

Such incidents are related to either failures or loosening of attachment fittings during engine operation, or tube failures because of manufacturing flaws on the inner surface exceeding the critical limit.All TDI fuel injection tubing is 1/2 in.SAE 1008 or" SAE 1010 steel manufactured to identical specification and is found to be suitable for nuclear standby diesel generator service (Ref.1)when manufacturing flaws on the inner surfaces are below the critical limit.The following maintenance recommendations for this component from the lead engine DR/gR report for Shoreham.site should be performed monthly while the engine is operating:

Inspect.compression fittings at both ends of each fuel injection.line..There are no modification recommendations for this component.

SH2376/1 0 d/+l COMPONENT DESIGN REVIEW CHECKLIST Page 2 of 3 DR-02-02" 365C-0 TASK DESCRIPTION (continued)

The following guality inspections as described on the Component guality Review Checklist should be performed on all station engines:~All high pressure fuel lines are to be completely examined by an eddy.current test (Ref.4).PRIMARY FUNCTION Not required ATTRIBUTE TO BE VERIFIED Not required SPECIFIED STANDARDS Not required REFERENCES 1.Emergency Diesel Generator Fuel Oil Injection Tubing qualification Analysis prepared for TDI Emergency Diesel Generator Owners Group April 1,-1984.2.Emergency Diesel Generator Computer Tracking System-Industry Experienpe dated October 15, 1984.3..Emergency Diesel Generator Computer Tracking System-Shearon Harris Nuclear Power Plant dated October 15, 1984.4.Failure Analysis Assoc.NDE Procedure 11.10"Eddy Current Inspection Procedure-High Pressure Fuel Lines-Carbon Steel." SH2376/2 COMPONENT DESIGN REVIEW CHECKLIST DOCUMENTATION RE UIRED Not required Page 3-of 3 DR"02-02-365C-0 GROUP CHAIRPERSON PROGRAM MANAGER5H2376/3 1 COMPONENT UALITY REVALI DATION CHECKLIST Page 1 of 3 02-02-365C Fuel Injection Equipment COMPONENT Tube Assembl GPL NO.02-365C SNPS GPL NO.03-365C Carolina Power&Light Shearon Harris Nuclear UTILITY Power Plant-Unit 1 REV.NO.2TASK DESCRIPTIONS

~Ei EA-A l.Assemble and review existing documentation.

2.Perform an Eddy Current test on the inside diameter of all the fuel injection tubing.En ine 1B-SB Same as Engine 1A-SA ATTRIBUTES TO BE VERIFIED~E" i BA-EA 1..guality.status of Component Document Package 2.Integrity of the fuel injection tubing~E" i 1B-EB Same as Engine 1A-SAACCEPTANCE CRITERIA~Ei lA-EA 1.Satisfactory Document Package 2.The minimum detectable flaw size is rejectable (0.003" t 0.0005").SH1002/1

COMPONENT UALITY REVALI DATION CHECKLIST ACCEPTANCE

'CRITERIA (continued)

~E'11-EB Same as Engine 1A-SA Page 2 of 3 02"02-365C REFERENCES En ine lA-SA 1.gCI No.52 2.Approved Site NDE Procedures, TElS99-006, FaAA NDE procedure 11.10 En ine 1B-SB Same as Engine 1A-SADOCUMENTATION RE UIRED~Ei EA-EA 1.Document Summary Sheet 2.Inspection Report~Ei 1B-EB-Same as Engine 1-SA GROUP CHAIRPERSON PROGRAM MANAGERCOMPONENT REVIEW En ine 1A-SA 1.No EDGCTS site experience documents are in evidence.2.An Eddy Current test was performed on all fuel injection tubing except where the tubing's inner diameter was too small to be examined.All tubing that was tested showed no relevant indications.

This was reported by TERS02-082.SH1002/2 COMPONENT UALITY REVALIDATION CHECKLIST COMPONENT REVIEW (continued)

~Ei lA-SA Page 3 of 3 02-02-365C NOTE: a)A visual inspection of the tubing was performed with satisfactory results.This was reported by TERS02-082.En ine 1B-SB No EDGCTS site experience documents are in evidence.2.NOTE: An Eddy Current test was per for med on al 1 fuel injecti on tubing except where the tubing's inner diameter was too small to be examined.Results for tubing on cylinder$L was found to be unsatis-factory.This was reported by'TERS02-082.a)A vi sual inspecti on of the tubing was.performed wi th satisfactory results.This was reported by TEfbF 02-046.RESULTS AND CONCLUSION En ine 1A-SA The guality Revalidation effort with respect to this component,'s outlined above, is complete.The results have been forwarded to the Design Review Group for their evaluation and conclusions in support of the final report.En ine 1B-SB ,Same as Engine 1A-SA GROUP CHAIRPERSON.V PROGRAM MANAGER SH1002/3

'COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-'NIT 1 Page 1 of 2 Fuel Injection Equipment:

Supports COMPONENT Small Bore Sco e Onl GROUP PARTS LIST NO.02-365D SNPS GPL NO.03-365D UTILITY Carolina Powe~8 Li ht Com an TASK DESCRIPTION NO.DR-02-02" 365D-1 CLASSIFICATION TYPE B TASK'ESCRIPTIONS Design review for this component is not required based on the review of the lead engine DR/gR report (Comanche Peak)and the applicable industry experi-ence.There is no site experience for this component in the EDG Component Tracking System.There are no modification recommendations for this component.

A visual inspection of the support elastomer for signs of deterioration or degradation should be performed at each refueling outage.Any inserts found~~~~~unsat'isfactory should be replaced.A fi el d wal kdown was per formed in accordance with the smal 1 bore piping criteria document (Ref.1)and indicates that this component will maintain its functional capability for normal and earthquake loading.guality revalidation for this component is not required.PRIMARY FUNCTION Not required ATTRIBUTE TO BE VERIFIED Not required SPECIFIED STANDARDS SH2176/1 COMPONENT DESIGN REVIEW CHECKLIST Page 2 of 2 DR-02"02"365D-1 R EFERENCES"Engineering Review Criteria Document for the Design Review of TDI Diesel Small Bore Piping, Tubing, and Supports for the TDI Owners'roup," report No.11600.60-DC-02, Revision 0.DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGERSH2176/2

'COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Page 1 of 2 Fuel Control Rod COMPONENT Linka e&Bearin s GROUP PARTS LIST NO.02-371A&B SNPS GPL NO.03"371A&B UTILITY Carolina Power&Li ht Com an TASK DESCRIPTION NO.DR"02-02-371A&B-1 CLASSIFICATION TYPE A~TASK DESCRIPTIONS Design review for this component is not required based on the following:

A review of the EDG Component Tracking System indicated that there was no significant applicable industry and/or site experience, except that already addressed in the lead engine report.~A review of the lead engine DR/gR report (Comanche Peak).~Component is identical to lead engine report.~~~~~~.The following maintenance recommendations from the lead engine DR/gR report should be implemented:

~To maintain proper control shaft alignment, it is recommended that the oil cups be inspected and filled on a monthly basis.No modifications are required for this component.

All inspections that have been completed were found to be satisfactory.

The following guality inspections should be performed:

~Inspect linkage and bearings for freedom of movement.~Determine the'ardness of the shaft.PRIMARY FUNCTION Not required SH2206/1

i.

I COMPONENT DESIGN REVIEW CHECKLIST ATTRIBUTE TO BE VERIFIED Not required Page 2 of 2 DR-02-02-37108-1 SPECIFIED STANDARDS Not required REFERENCES Not required DOCUMENTATION RE VIREO.Not required GROUP CHAIRPERSON PROGRAM MANAGER&C SH2206/2 Page 1 of 3 02-02" 371A COMPONENT UALITY REVALIDATION CHECKLIST Fuel Pump Linkage-COMPONENT Fuel Pum Control Shaft GPL NO.02"371A SNPS GPL NO.03"371A Carolina Power 8 Light Shearon Harris Nuclear UTILITY Power Plant-Unit 1 REV.NO.T SK DESCRIPTIONS En ine 1A-SA l.Assemble and review existing documentation.

2.Determine the hardness of the shaft.~Ei 1B-EB 1.Assemble and review existing documentation.

ATTRIBUTES TO BE VERIFIED En ine 1A-SA 1.guality status of Component Document Package 2.Hardness of the shaft~E" i 11-EB 1.guality status of Component Document Package ACCEPTANCE CRITERIA En ine 1A-SA 1.Satisfactory Document Package 2.Review of inspection report by the Design Group SH1003/1 COMPONENT UALITY REVALI DATION CHECKLIST ACCEPTANCE CRITERIA (continued)

B-BB 1.Satisfactory Document Package Page 2 of 3 02-02"371A REFERENCES En ine lA-SA l.(CI No.52 2.Approved Site NDE Procedures

~Ei 1-BB 1.gCI No.52.DOCUMENTATION RE UIRED~Ei EA-BA 1.Document Summary Sheet.2.Inspection Report~Ei B-B 1.Document Su ary Shee-GROUP CHAIRPERSON PROGRAM MANAGER COMPONENT REVIEW En ine 1A-SA 1.No EDGCTS site experience documents are in evidence.2.No inspection report has been received which fulfills this requirement..Note: a)A Material Comparatot test was performed on the fuel pump linkage.Results were reported by TEfS02-019.SH1003/2

~~

COMPONENT UALITY REVALIDATION CHECKLIST Page 3 of 3 02-02-371A COMPONENT REVIEW (continued) b)A hardness test was performed on the fuel pump linkage.Results were reported by TEIL 02-019.En ine 1B-SB 1.No EDGCTS site experience documents are in evidence.Note: a)A Material Comparator test was performed on the fuel pump linkage.Results were reported by TEiS02-066.b)A hardness test was performed on the fuel pump linkage.Results were reported by TEIL 02-066.RESULTS AND CONCLUSION

~Ei 1A-SA The guality Revalidation effort with respect to this component, as outlined above, is complete.The results have been forwarded to the Design Review Group for their evaluation and conclusions in support o'the final report.En ine 1B-SB Same as Engine 1A GROUP CHAIRPERSON

~c-&~4 PROGRAM MANAGER C-SH1003/3 TDI OWNERS GROUP for SHEARON HARRIS NUCLEAR POWER PLANT Fuel Pump Linkage: Linkage Assembly and Bearing COMPONENT PART NO.: O2-371B See Component Part No.02-371A COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR STATION" UNIT 1 Page 1 of 2 Fuel Pump Linkage: Automatic COMPONENT Shutdown C linder GROUP PARTS LIST NO.02-413B SNPS GPL NO.03-371C UTILITY Carolina Power 8 Li ht Co.TASK DESCRIPTION NO.DR-02-02-413B" 0 CLASSIFICATION TYPE B TASK DESCRIPTIONS I Design review for this component is not required based on the following~A review of the Component Tracking System indicated that there was no significant applicable industry experience and/or site experience.

~The applicable engine dimensions and operating parameters at Shearon Harris are identical or very similar to those for the same component at Comanche Peak (lead engine).No maintenance recommendations, modification recommendations'r guality~~~~~~~~~~~~Revalidation review is required for this component.

PRIMARY FUNCTION Not required ATTRIBUTE TO BE VERIFIED Not required SPECIFIED STANDARDS Not required SH1978/1 8

REFERENCES Not required COMPONENT DESIGN REVIEW CHECKLIST Page 2 of 2 DR-02-02-413B-0 DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGER C SH1978/2 Page 1 of 2 COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 COMPONENT Fuel Oil Booster Pum GROUP PARTS LIST NO.02-445 SNPS GPL NO.03-445 UTILITY Carolina Power 8 Li ht Com an TASK DESCRIPTION NO.DR-02" 02-445-0 CLASSIFICATION TYPE A TASK DESCRIPTIONS Design review for this component is not required based on the following:

A review of the EDG Component Tracking System indicated that there was no significant applicable industry and/or site experience.

~A review of the lead engine DR/gR reports (Comanche Peak).~Both Comanche Peak and Shearon Harris fuel oil booster pumps are Roper Model 18-AM-27, Type 1.There are no maintenance items or modifications recommended

'based on the lead~~~~engine report.guality revalidation is not deemed necessary for this component.

/PRIMARY FUNCTION Not required ATTRIBUTE TO BE VERIFIED Not required SPECIFIED STANDARDS Not required SH2265/1

REFERENCES Not required COMPONENT DESIGN REVIBf CHECKLIST Page 2 of 2 DR-02-02" 445-0 DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGER SH2265/2

Page 1 of 2 COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Fuel Oil Header: COMPONENT Pi in/Tubin GROUP PARTS LIST NO.02-450A UTILITY Carolina Power 8 Li ht Co.TASK DESCRIPTION NO.DR-02"02-450A-0 SNPS GPL NO.03-450B CLASSIFICATION TYPE A TASK DESCRIPTIONS A design review is not required for this component based on a review of applicable industry and site experience, the lead engine DR/gR report (Comanche Peak)and a field walkdown.The review of the applicable industry and site experience indicates that fuel oil line failures have occur red at Grand Gulf and Catawba.These failures were located at a tee connection on the fuel oil header.Cause of failure has been attributed to vibration.

The field walkdown indicates that a 3/4 inch threadolet was used as the-method of connecting the 1-inch fuel oil supply tubing (branch side)to the 3/4 inch front crossover header.This could result in stress concentration at the fitting to run pipe juncture, because of the abrupt change in wall thickness.(Fitting O.D.exceeds run pipe O.D.)Therefore, it.is recommended that the 3/4 inch threadolet be changed to a socket welded tee to preclude the possibility of fatigue failure from long term vibration stresses.The lead engine DR/gR report for this component contains no maintenance recommendations.

A field walkdown was performed at Shearon Harris.However, a review of this component in its entirety was not possible since portions of the piping and tubing were not installed.at the time of the walk5own.Therefore, component acceptability and any subsequent recommendations shall be based upon the lead engine reports (Comanche Peak, Grand Gulf and Catawba).The lead engine reports address the need for modification, specifically, suppor t additions and modifications.

Similar additions/modifications for Shearon Harris are now included in DR/gR report 02-450B.Therefore, based on the above review it is'concluded that this component will perform its intended design function at Shearon-Harris under all normal operating and earthquake loading provided that supports are added/modified as indicated in DR/gR report 02-450B, and provided the threadolet mentioned above is replaced with a socket welded tee.guality Revalidation is not deemed necessary.

SH2222 1 PRIMARY FUNCTION Not required COMPONENT DESIGN REVIEW CHECKLIST Page 2 of 2 DR-02-02"450A"0 ATTRIBUTE TO BE VERIFIED Not required SPECIFIED STANDARDS Not required REFERENCES Not required DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGER C EC SH2222/2

TDI OWNERS GROUP for SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 FUEL OIL HEADER-FUEL OIL SUPPORTS SMALL BORE SCOPE ONLY COMPONENT PART NO.02-450B I INTRODUCTION The TDI Emergency'iesel Gener ator Owners Group Program for the Shearon Harris Nuclear Power Plant requir es Design and gual i ty Reval i dation reviews of the structural adequacy of the fuel oil header small bore piping/tubing supports to withstand the effects of normal operating'and earthquake loadings.The primary function of these supports is to provide adequate restraint of the small bore piping/tubing system in the intended support load direction.

I I OBJECTIVE The objective of this review was to perform an engineering evaluation of the small bore piping/tubing supports to assure that the component will perform its intended design function during normal operating and earthquake loadings.III METHODOLOGY In order to meet the stated objective, the following methods wer e used:~The TDI Emergency Diesel Generator Component Tracking System was reviewed for the Shearon Harris site, nuclear, and non-nuclear industry experience.

See Appendix C for results.The equality Revalidation Checklist results were reviewed for acceptab'ility.'

Comparison with the lead engine reports (Comanche Peak, Grand Gulf, Catawba).Refer to the review procedures as described in Reference 1 for a detailed methodology of this evaluation.

IV RESULTS AND CONCLUSIONS The small bore piping/tubing supports, as defined by this Component Design Review, have been evaluated in accordance with Reference 1 and have been found acceptable with modifications.

The conclusions of this report are based on the combination of a field walkdown and a review of the lead engine reports as portions of this component were not installed at the time of the walkdown.SH2368/1 8 J' Page 2 of 3 There are no TERs associated with this component.

The guality Revalidation Inspection results identified in Appendix B have been reviewed and considered in the performance of this design review, and the results are consistent with the final c'onclusions of this report.Based on the above review, it is concluded from References 1 and 2 that the small bore piping/tubing supports will perform their intended design function at Shearon Harris under all normal operating and earthquake loadings if the following recommended modifications as detailed in Reference 3 are implemented:

~The support located above-the ejector assembly on Engine 1A should be modified to restrain a two-directional, lateral loading in order to reduce the unsupported span length.Also, this support appears to have been damaged by welding at the time of installation.

In order to support the piping/tubing of Component 02-450A it is recommended that: For each fuel oil drip header (2 per engine), one of the existing two-directional r estraints per header be modified to a three-directional restraint in order to provide axial restraint of the header and to minimize the effects on all associated tubing.The ejector assembly and adjacent 1-inch diameter tubing be resupported/anchored in order to minimize the imposed loading and stress concentration on the ejector assembly nozzles.Upon installation, an anchor (six-way restraint) be added on the fuel-oil-to-day-tank return piping (two lines per engine)in order to reduce the unsupported span length and to minimize the effects from the off-engine piping.This recommendation is based on the lead engine reports.A three-directional restraint be added on the 4-inch diameter drip header to ejector tube (Engine 1A left bank only)in order to reduce the unsupported span length.A two-direction lateral restraint be added on Engine 1A only on the 1-inch ejector tubing (2 lines)approximately 2 feet-6 inches below the supply and circulation rear crossover headers in order to reduce the unsupported span lengths and to maintain consistency with Engine 18.The recommendations above apply to both the Engines 1A and 1B unless otherwise.

specified.

SH2368/2 8

Page 3 of 3~~~~~~~~~~~~V REFERENCES 1."Engineering Review Criteria Document for the Design Review of TDI~Diesel Small Bore Piping, Tubing, and Supports for the TDI Owners Group," Report No.11600.60-DC-02, Revision 0.2.Stone 8 Webster Calculation number 11600.60-NP(B)-0201-XH.

3.Memo no.6451 from C.Malovrh/SWEC to J.Kammeyer/SWEC dated 10/29/84.SH2368/3

~A l APPENDIX A COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Page A1 of 2 Fuel Oil Headers and Tubing Supports COMPONENT Small Bore Sco e Onl GROUP PARTS LIST NO.02-450B SNPS GPL NO.03-450D UTILITY Carolina Power 8 Li ht TASK DESCRIPTION NO.DR-02-02" 450B" 0 CLASSIFICATION TYPE TASK DESCRIPTIONS

~~Perform an engineering review of the small bore piping/tubing supports to provide additional assurances that the component will perform its intended design function during normal operating and earthquake loading.PRIMARY FUNCTION~~Provide adequate restraint of the small bore piping/tubing system in the intended support load directions.

ATTRIBUTES TO'E VERIFIEB Structural adequacy of the pipe/tube supports due to the effects of normal operating and earthquake loadings.SPECIFIED STANDARDS IEEE 387 REFERENCES"Engineering Review Criteria Document for the Design Review of TDI Diesel Small Bore Piping, Tubing;and Supports for the TDI Owners'roup" Report No.'11600.60-DC-02, Revision 0SH2254/1 COMPONENT DESIGN REVIEW CHECKLIST Page A2 of 2 DR-02-02"450B-0 DOCUMENTATION RE UIRED Delaval design documentation (specifications, calculations, drawings, etc.).In lieu of information from Delaval, the following information is required: verified support sketches and piping isometrics, material specifications, pipe size and schedule, and operating parameters (pressure, temperature, load combinations)

GROUP CHAIRPERSON PROGRAM MANAGER C 4a.~SH2254/2 A endix B COMPONENT UALITY REVALIDATION CHECKLIST Page Bl of 3 02-02-450B

~Fuel Oil Header-COMPONENT Fuel Oil Su orts GPL NO..02-450B SNPS GPL NO.03-450D Carolina Power&Light Shearon Harris Nuclear UTILITY Power Plant-Unit 1 REV.NO.1 TASK DESCRIPTIONS En ine lA-SA 1.Assemble and review existing documentation.

2.Obtain sufficient data to support the design review effort.This may be accomplished by developing quality verified as-builts in accordance with Procedure DG-7, or by the Design Group performing a field walkdown.~Ei 1B-EB Same as Engine 1A-SA ATTRIBUTES TO BE VERIFIED~Ei A-EA 1.guality status of Component Document Package 2.Information necessary for the design review effort~Ei 1B-EB'Same as Engine lA-SA SH1760/1

COMPONENT UALITY REVALIDATION CHECKLIST A CCEPTANCE CRITERIA~Ei EA-SA 1.Satisfactory Document Package 2.Review of detailed information by the Design Group~Ei B-S Same as Engine lA-SA Page B2 of 3 02-02-450B REFERENCES

~Ei 1A-E l.gCI No.52 2.Procedure DG-7~Ei 1-SB Same as Engine 1A-SA DOCUMENTATION RE UIRED~Ei 1A-SA 1.Document Summary Sheet 2.equality verified as-built isometric drawings for the supports if available from the Owner.En ine 18-SB Same as Engine 1A-SA GROUP CHAIRPERSON PROGRAM MANAGER~L(~~v SH1760/2 l r r E~COMPONENT REVIEW I~Ei A-EA COMPONENT UALITY REVALIDATION CHECKLIST Page 83 of 3 02-02"4508 1.No EDGCTS site experience documents are in evidence.2.The Design Group will be responsible for closing out the as-built drawings as per Procedure DG-7.The as-built drawings will be guality verified by the appropriate site guality organization.

The performance of an engineering walkdown by the Design Group, precludes the issuance of a quality verified as-built drawing or sketch.~Ei IB-EB Same as Engine 1A-SA RESULTS AND CONCLUSION En ine 1A-SA The equality Revalidation effort with respect to this component, as outlined above, is complete.The results have been forwarded to the Design Review Group for their evaluation and conclusions in support of the final report.En ine 18-SB Same as Engine 1A"SA GROUP CHAIRPERSON PROGRAM MANAGER C KC(i~vi SH1760/3

A endix C Page Cl of 1 EDG COMPONENT TRACKING SYSTEM: SHEARON HARRIS SITE NUCLEAR AND NON-NUCLEAR INDUSTRY EXPERIENCE

SUMMARY

COMPONENT NO.02"450B Effective Printout Dates Shearon Harris: 07/05/84 Industry: 09/17/84 COMPONENT TYPE: Fuel Oil Header-Fuel Oil Su orts EXPERIENCE SHEARON HARRIS None'UCLEAR None NON-NUCLEAR None REFERENCE DOCUMENTS SHEARON HARRIS STATUSSH2368/1 COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Page 1 of 2 Fuel Oi 1 Filters 8 COMPONENT Strainers:

Filters GROUP PARTS LIST NO.02-455A SNPS GPL NO;03-455A UTILITY Carolina Power 8 Li ht Com an TASK DESCRIPTION NO.DR-02-02-455A" 0 CLASSIFICATION TYPE B TASK DESCRIPTIONS Design review for this component is not required based on the following:

~A review of the EDG Component Tracking System indicated that there was no significant applicable industry and/or site experience, except that previously addressed in the lead engine report.~A review of the lead engine DR/gR reports (Shoreham/Comanche Peak).The fuel oil filters at Shearon Harris are the same model from the same manufacturer as those used at Comanche Peak.The following maintenance recommendations from the lead engine DR/gR should be implemented:

~The filter differential pressure should be checked monthly and procedures should be established for replacing the filter cartridges at or before the manufacturers specified maximum of 20 psid.~Air should be purged from the filters after maintenance.

There are no modifications required for this component.

guality Revalidation is not required for this component.

PRIMARY FUNCTION Not required ATTRIBUTE TO BE VERIFIED Not required SH2211/1 SPECIFIED STANDARDS Not required COMPONENT DESIGN REVIBI CHECKLIST Page 2 of 2 DR" 02-02" 455A" 0 REFERENCES Not required DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGER SH2211/2

COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Page 1 of 2 Fuel Oil Filters 8 COMPONENT Strainers:

Strainers GROUP PARTS LIST NO.02-455B SNPS GPL NO.03"455B UTILITY Carolina Power 8 Li ht Com an TASK DESCRIPTION NO.DR" 02-02"455B-0 CLASSIFICATION TYPE B TASK DESCRIPTIONS Design review for this component is not required based on the following:

~A review of the EDG Component Tracking System indicated that there was no significant applicable industry and/or site experience, except that already addressed in the lead engine report.~A review of the lead engine DR/gR report (Comanche Peak).~Both Shearon Harris and Comanche Peak use an Air Maze Model D3J24XDL, which provides 46 micron (300 mesh)filtration.

The following maintenance from the lead engine DR/gR report should be implemented:

The strainer elements should be cleaned or replaced at 5 psid maximum'.~Air should be purged from the strainer after maintenance.

~Bolt torques of 120-150 in-lbs should be utilized during reassembly.

The following modification from the lead engine DR/gR report should be considered:

The strainer should be replaced with a coarser design that would require less maintenance, but would still satisfy the filtration requirement for the booster pump, which is 100-200 mesh.This recommendation is made to enhance operation but is not required for system operation.

guality revalidation is not required for this component.

SH2413/1 PRIMARY FUNCTION Not required COMPONENT DESIGN REVIEW CHECKLIST Page 2 of 2 DR-02-02-455B-0 ATTRIBUTE TO BE VERIFIED Not required SPECIFIED STANDARDS Not required REFERENCES Not required DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGER DC SH2413/2

Page 1 of 2 COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Fuel Oil Filters 8 Strainers COMPONENT Mountin Hardware UTILITY Carolina Power 8 Li ht Com an GROUP PARTS LIST NO.02"455C TASK DESCRIPTION NO.DR" 02-02-455C-0 SNPS GPL NO.03"455C CLASSIFICATION TYPE A TASK DESCRIPTIONS Design review of this component is not required based on the r'eview of the Comanche Peak lead engine DR/gR report (Ref.1), TDI Parts Manual Volume II (Ref.2), TDI Associated Publications Manual Volume III (Ref.3), and the EDG Component Tracking System, which indicates no applicable industry and'site exper ience (Refs.4 and 5).The duplex strainers (Part No.F-044-117) for the motor driven fuel oil booster pumps at Comanche Peak are not applicable to Shearon Harris Station since redundant fuel oil supply is not applicable to the Shearon Harris design.Both Shearon Harris and Comanche Peak Stations have identical parts lists (Parts List 02-455-02-01 dated February 11, 1977)for the fuel oil filters and strainers and the associated mounting hardware.At both locations, the fuel oi 1 fil ters (Part No.SC-011-000) are Model 511-150-1 Dupl ex Hyf1 ow Flui d Filters manufactured by the Hilliard Corporation, and the fuel oil strainers (F-044-117) are Model D3J-24IDL duplex filters manufactured by the Air-Maze Corporation.

The mounting hardware-brackets, cap screws, nuts, etc.-are likewise identical.

Review of the amplified acceleration spectra for Shearon'arris (Ref.6)indicates that the seismic loadings are more favorable than those at the Comanche Peak Station.The maximum stresses resulting from normal, seismic, and piping loads on the mounting hardware are anticipated to be similar for both stations.Based on the Comanche Peak DR/gR Report which identified acceptable margins of safety in the stress analysis of the mounting hardware (Ref.1), the mounting hardware for the fuel oil filters and strainers at Shearon Harris Station should be adequate for its intended service.There are no maintenance or modification recommendations applicable to this component.

guality Revalidation is not required for this component.

SH2387/1 fW," w~%/)C , 1 PRIMARY FUNCTION Not required COMPONENT DESIGN REVIEW CHECKLIST Page 2 of 2 DR-02-02-455C-0 ATTRIBUTE TO BE VERIFIED Not required SPECIFIED STANDARDS~+Not required>REFERENCES 1.Comanche Peak Steam Electric-Unit 1, DR/gR Report for Group Parts List No.02"455C.2.TDI Manual Volume II, for Model DSRV-16-4 Diesel Engine/Generator, Shearon Harris Nuclear Power Plant, Units 1, 2, 3, and 4, Parts List 02-455-02-01.

3.'TDI Manual Volume III for Model DSRV-16-4 Diesel/Generator, Shearon Harris Nuclear Power Plants, Units 1, 2;3, and 4, Part Nos.F-044-117 and SC"011-000.

4.Emergency Diesel Generator Component Tracking System-Nuclear and Non-Nuclear Industry Experience dated October 15, 1984.5.6.Emergency Diesel Generator Component Tracking System-Shearon Harris Nuclear Power Station dated October 15, 1984.Ebasco Services, Inc.Project CAR-SH-E-11, Specification 216-73-Tb for Diesel Engine Generator Unit and Control Panel for Nuclear Power Plants, Rev.7 dated September 14, 1981, Addendum A,"Seismic Considerations for Mechanical Equipment,"-Response Acceleration Spectra Curves (12 sheets)Revised December 26, 1978.DOCUMENTATION RE VIREO Not required GROUP CHAIRPERSON SH2387/2 PROGRAM MANAGER C COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Page 1 of 2 Auxiliary Sub-Base 8 Oil 8 Water Piping-Fuel Oil: Piping and Fittings COMPONENT Small Bore Sco e Onl GROUP PARTS LIST NO.02-717M SNPS GPL NO.03-717M UTILITY Carolina Power 8 Li ht Co.TASK DESCRIPTION NO.DR"02-02-717M" 0 CLASSIFICATION TYPE B TASK DESCRIPTIONS A design review is not required for this component based on a review of applicable industry and site exper ience, thy lead engine DR/gR report (Comanche Peak)and a field walkdown.There is no site experience for this component in the EDG Component Tracking System.The industry experience, specifically Cleveland Electric, indicates that piping supplied with the diesel did not meet the ASME III code as required.The following discussion concludes that this component will meet its intended design function at Shearon Harris, but does not specifically assure any code compliance as this responsibility rests with the utility.A review of the remaining industry experience indicates that no generic or significant pro-blems exist which affect the integrity of this component.

The lead engine DR/gR Report for this component contains no maintenance recommendations.

A field walkdown was performed at Shearon Harris.However, a review of this component in its entirety was not possible since portions of the piping were not installed at the time of the walkdown.Therefore, component acceptability and any subsequent recommendations shall be based upon the lead engine report.The lead engine reports (02-717', M)indicate that there were no modifications related to the small bore piping/tubing and supports.Therefore, based on the above review it is concluded that this component will perform its intended function under all normal operating and earthquake loadings.guality Revalidation for this component is not deemed necessary.

SH2217/1

PRIMARY FUNCTION Not requir ed COMPONENT DESIGN REVIEW CHECKLIST Page 2 of 2 DR-02-02" 717M-0 ATTRIBUTE TO BE VERIFIED Not required SPECIFIED STANDARDS~+Not required REFERENCES Not required DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGER DC KSH2217/2

Page 1 of 1 COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT" UNIT 1 Auxiliary Sub Base-Oil 8 Water Piping-Fuel COMPONENT Oil: Boltin and Gaskets GROUP PARTS LIST NO.02-717P SNPS GPL NO.03-717P UTILITY Carolina Power 8 Li ht Co.TASK DESCRIPTION NO.DR-02-02-717P-0 CLASSIFICATION TYPE B TASK DESCRIPTIONS.

Design review for this component is not required based on the review of applicable industry experienc'e and the lead engine DR/gR reports (Shoreham/Comanche Peak).There is no site experience for this component.

There are no maintenance or modification recommendations for this component.

guality revalidation for.this component is not required.PRIMARY FUNCTION Not required ATTRIBUTE TO BE VERIFIED Not required SPECIFIED STANDARDS Not required REFERENCES Not required DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGER SH2292/1

COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Page 1 of 2 COMPONENT Fuel Oil Da Tank GROUP PARTS LIST NO.02-825A UTILITY Carolina Power 8 Li ht Com an TASK DESCRIPTION NO.DR-02-02-825A-1 SNPS GPL NO.99-825A CLASSIFICATION TYPE A TASK DESCRIPTIONS A detailed design review of the fuel oil day tank is not necessary for Shearon Harris.The tank was manufactured by PX Engineering, Woburn Mass.The tank=was seismically analyzed in detail by TDI.(Ref.2)and is designed and fabricated in accordance with ASME III.No inherent design flaws have been identified in TDI supplied fuel oil day tanks.The results of the ASME III qualification program for the Comanche Peak fuel oil day tank were reviewed, and no deficiencies were found.k There is one experience item reported for this tank at Shearon Harris in the EDG Component Tracking System.It involves welds which are deficient with respect to ASME III criteria.This has been resolved.There are no nuclear or non-nuclear experience items reported.No special maintenance requirements were identified for this component in the lead engine design review (Comanche Peak).There is no quality revalidation required for this component.

PRIMARY FUNCTION Not required ATTRIBUTE TO BE VERIFIED Not required SPECIFIED STANDARDS Not required SH2599/1 REV.1 REFERENCES COMPONENT DESIGN REVIEW CHECKLIST Page 2 of 2 DR-02-02-825A-0 1.Ebasco Specification 216-'73-Tb, Rev.3, 04-25-78,"Diesel Engine Generator Unit and Control Panel for Carolina Power and Light Company Shearon Harris Nuclear Power Plant Units 1 and 2, 3 and 4.2.Final Report Volume II, Analytic Modeling of Engine Auxiliaries Seismic'ualification of TDI Diesel Generator Sets, Serial Numbers 74046/53 for Carolina Power and Light Company, Shearon Harris Nuclear Power Plant Units 1, 2, 3, 8 4,Section II, Fuel Oil Day Tank.DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGER&ChalSH2599/2

Page 1 of 3 02-02"825B COMPONENT UALITY REVALIDATION CHECKLIST Fuel Oil System-Fuel COMPONENT Oil Du lex Strainer GPL NO.02-825B SNPS GPL NO.99-825E Carolina Power 8 Light Shearon Harris Nuclear UTILITY Power Plant-Unit 1 REV.NO.1 TASK DESCRIPTIONS

~En inc IA No further review of component 02-825B is required for the following reasons a)There is no site or industry experience reported for this component.

b)Component was reviewed on the lead engi.nes (Shoreham) with satisfactory results.GROUP CHAIRPERSON

+Mur PROGRAM MANAGER SH1906/1 TDI OWNERS GROUP for SHEARON HARRIS NUCLEAR POWER PLANT" UNIT 1 EMERGENCY DIESEL GENERATOR COMPONENT PART NO.02-650A I INTRODUCTION The TDI Emergency Diesel Generator Owners Group Program for the Shearon Harri s Nucl ear Power Pl ant (SHNPP)r equir es Desi gn and equal ity Revalidation reviews of.the generator to determine its adequacy for its intended use at Shearon Hart-is.The primary function o$the'enerator (AC Synchronous Generators, serial nos.17408432/33, manufactured by Electric Products Division, Portec, Inc.)is to supply all safety related loads in the event of loss of offsite power., which will provide for the safe shutdown of the plant and subsequent continuation of safe shutdown conditions.

SHNPP Unit 1 has two diesel generators to supply the ESF loads of Divisions A and B.These diesel generators are each rated at 6500 kW and are supplied by TDI.The units have been installed but have not been site tested to date.I I OBJECTIVE The objective was to verify the generator's ability to maintain emergency bus voltage under emergency loading conditions.

III METHODOLOGY

'he maximum coincident demand on the diesel generators was compared with the continuous and short-term ratings of the generator.

NRC Safety Guide 9.0 (Ref.1), Regulatory Guide 1.9 (Ref.2);and IEEE Standard 387-1977 (Ref.3)were reviewed regarding the ratings.The sequential loading of the generators as specified in the procurement specifications (Ref.4)was examined.Using the generator parameters determined by the vendor's shop tests (Ref.5), minimum generator voltage was computed for each step of the sequential load.Calculations (Ref.6)were performed to verify that the minimum generator terminal voltage is in excess of 75 percent of the rated voltage, as required in Reference 2.The qualification tests were reviewed to verify that the voltage recovers to 90 percent of the rated voltage in less than two seconds because of the action of the voltage regulator, as required in Reference 2.SH2471/1 Page 2 of 3 Shearon Harris site experience, as reported in Component Tracking System printouts, was reviewed.In addition, nuclear and non-nuclear industry experience was reviewed.The design of the brush arrangement was reviewed for adequacy (Ref.6).Comparison was made with the brush arrangement at Shoreham.The generator maintenance program was reviewed with regard to brushes and slip rings (Ref.5).The procurement specification, CAR-SH-E-11 (Ref.4), was reviewed in the light of IEEE Std.387-1977, NRC Regulatory Guide 1.9, and Safety, Guide 9.0.IV guality Revalidation Checklist results were reviewed for acceptability.

RESULTS AND CONCLUSIONS The maximum coincident demand on the diesel generators will be during loss of offsite power.The estimated maximum continuous ESF loads are 6265 kW for Division A and 6261 kW for Division B (SHNPP FSAR, Amendment 3, Tables 8.3.1-2[aj and fb]).Each generator has a continuous rating of 6500 kW and a 2-hour rating of 7150 kW.It is concluded, therefore, that the rating of each diesel generator is adequate.Recent reductions in continuous ESF loads have lowered the total load to 5677 kW for each diesel generator, thereby making this analysis conservative.

Cal cul ati ons (Ref.6)show that the maximum vol tage of the generator during automatic sequencing in the event of loss of offsite power will not drop below 79.5 percent of the rated voltage.gualification tests (Ref.7)show that the generator terminal voltage recovers to 90 percent of the rated voltage within 0.3 seconds.Based upon the calculations and qualification tests results, the performance of the generator is acceptable with regard to the specified minimum voltage (75 percent of the rated voltage as per Reference 2)and recovery time.Shearon Harris, nuclear and non-nuclear industry experience listed in the Component Tracking System (dated September 17, 1984)was reviewed.The results of the review are given in Appendix C of this report.It was found that the incidents were not of a generic nature and do not impact the conclusions of this report.Evaluation of the design of the brushes and brush holders at Shearon Harris and comparison with those at Shoreham show that the brushes and brush holders are selected and designed adequately for both generators (Ref.5).No cases of failure of the brushes or slip rings have been reported at Shearon Harris.Maintenance procedures recommended by the manufacturer (Ref.5)are adequate.SH2471/2 I'(,

Page 3 of 3 e The procurement specifications (Ref.4)reflect the relevant standards (Refs.1, 2, and 3).The information provided on TER 02-074 dated 10/15/84 has been reviewed and is consistent with the final conclusions of this report.gual ity Reval i dati on Inspecti on resul ts identified in Appendi x B have been reviewed and considered in the performance of this design review and the results are consistent with the final conclusions of this report.Based on the above review, it is concluded that the emergency diesel generator is acceptable for its intended use at Shearon Harris.V REFERENCES 1.NRC Safety Guide 9.0,"Selection of Diesel Generator Set Capability for Standby Power Supplies," dated 03/10/71.2.NRC Regulatory Guide 1.9,"Selection, Design and gualification of Di esel-Generator Uni ts used as Standby (Onsi te)El ectri cal Power Systems of Nuclear Power Plants," Rev.2, December 1979.3.IEEE Std.387-1977,"Criteria for Diesel Generator Units Applied as Standby Power Supplies for Nuclear Power Generating Stations." 4.EBASCO Technical Specification for Standby Diesel Generators for CPEL Co., Shearon Harris Nuclear Power Plant Unit 1, No.CAR" SH-E-11.5.Portec Instruction Manual Operation, Maintenance and Parts List for AC Synchoronous Generator S.N.17408432/33 and Portec Test Report, April, 1981.6.Support Package FaAA-SP-84-6-45 (f).7.gual i f i cati on Test for TDI Generator Set CP8 L, Shearon Harri s Nuclear Power Plant Units 1-4, April 10, 1981.SH2471/3' a>

APPENDIX A Page A1 of 2 COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER STATION-UNIT I COMPONENT Emer enc Diesel Generator UTILITY Carolina Power 8 Li ht Co.GROUP PARTS LIST NO.02-650A SNPS GPL NO.03"650A TASK DESCRIPTION NO.: DR-02-02-650A" 0 CLASSIFICATION TYPE A TASK DESCRIPTIONS Verify the adequacy of the continuous and short-term rating to meet the worst case loads on thy 4.16 KV ESF buses of Divisions A and B.Verify that the drop in the generator terminal voltage.during the sequential loading of the generator does not exceed the specified value as per relevant IEEE Standards and NRC Regulatory Guides.Identify and resolve any recurrent patterns.of component failure listed on the Emergency Diesel Generator Component Tracking System.Verify the adequacy of the design of the brush arrangement and compare it with that at Shoreham Nuclear Power Station (SNPS).Review the generator maintenance program with regard to brushes and slip rings.Verify that the generator procurement specifications reflect the relevant NRC Regulatory Guides and IEEE Standards and that the shop tests are in compliance with the IEEE Standards.

Review the guality Revalidation Checklist results for acceptability.

Review.information provided on TERs.PRIMARY FUNCTION Supply all safety related electrical loads in the event of loss of offsite power.ATTRIBUTES TO BE VERIFIED Ability to maintain emergency bus voltage under emergency loading condit'ions.

SH1999/1 APPENDIX A SPECIFIED STANDARDS Page A2 of 2 DR-02-02-650A-0 ANSI Standard C50.10"General Requirements for Synchronous Machines." ANSI Standard C50.12"General Requirements for Sal i ent Pole Synchr onous Generator s." IEEE No.115"Test Procedures for Synchronous Machines." NEMA MG-1"NEMA Standard for Motors and Generators." IEEE 323 (General Guide for qualifying Class I Electrical Equipment for Nuclear Generating Stations).

IEEE Std.387-1977 (Criteria for Diesel-Generator Units'Applied'as Standby Power Supplies for Nuclear Powe~Generating Stations).

REFERENCES Diesel generator procurement specification.

DOCUMENTATION RE UIRED~~~Site information on the generator exciter including:

1.Manufacturers instruction, operation, and maintenance manual.2.Diesel generator procurement specification.

3.gualification'est data.4.Diesel generator onsite test data.5.Single line diagram for emergency bus system.6.Nameplate data for emergency bus loads.Manufacturer's information including generator data sheet.GROUP CHAIRPERSON PROGRAM MANAGER.~SH1999/2 A endix B Page B1 of 3 02-02-650A COMPONENT UALITY REVALIDATION CHECKLIST COMPONENT Generator GPL NO.02-650A SNPS GPL NO.03"650A Car ol ina Power&Light Shearon Harris Nuclear UTILITY Power Plant-Unit 1 REV.NO.1 TASK DESCRIPTIONS En ine 1A-SA 1.Assemble and review existing documentation.

~Ei 18-88 Same as Engine lA-SA ATTRIBUTES TO BE VERIFIED AA-EA 1.guality status of Component Document Package~Ei'-88 Same as Engine 1A-SA ACCEPTANCE CRITERIA~Ei AA-EA 1.Satisfactory Document Package~8" i 18-88 Same as Engine lA-SA SH1756/1 COMPONENT UALITY REVALIDATION CHECKLIST REFERENCES En ine lA-SA 1.gCI No.52~Ei B-EB Page B2 of 3 02-02"650A Same as Engine 1A-SA DOCUMENTATION RE UIRED.~Ei 1-EA 1.Document Summary Sheet~Ei 1B-EB Same as Engine 1A-SA GROUP CHAIRPERSON PROGRAM MANAGER COMPONENT REVIEW~Ei AA-A l.All EDGCTS site experience documents were assembled and reveiwed with unsatisfactory results.DDR No.1819 remains open.~E" i 11-EB Same as Engine 1A-SARESULTS AND CONCLUSION En ine lA-SA The guality Revalidation effort with respect to this component, as outlined above, is complete.The results have been forwarded to the Design Review Group for their evaluation and conclusions in support of the final report.S 81756/2 COMPONENT UALITY REVALIDATION CHECKLIST RESULTS AND CONCLUSION (continued)

~Ei BB-BB Same as Engine lA-SA Page B3 of 3 02-02-650A GROUP CHAIRPERSON PROGRAM MANAGERSH1756/3 A endix C Page Cl of 5 EDG COMPONENT TRACKING SYSTEM: SHEARON HARRIS SITE NUCLEAR AND NON-NUCLEAR INDUSTRY EXPERIENCE

SUMMARY

COMPONENT NO.02-650A Effective Printout Date 09/17/84 COMPONENT TYPE: Emer enc Diesel Generator EXPERIENCE SHEARON HARRIS Generator (1A-SA and 1B-SB)Deficiencies noted: 1.Starter bottom dimensions and missing rotor blades.2.Electrical items.L~3.Wel ds not in com-pliance with Portec Specification No.EQ.l.5.2.NUCLEAR When diesel generator A was started, a high pitch vibration was noted.Rotor pole cap was thrown clear of rotor.Diesel generator failed to accept load.Cause was undersized generator leads.REFERENCE DOCUMENTS RCR/DCN 1, 2, DDR No.1819 RIR 3-DDR No.1692 NRC (DDR).3"DDR No.1751 LER Robinson 2, 261-70000 SER St.Lucie 1, 12"80, 800317 SHEARON HARRIS STATUS 1.Insufficient informa-tion at present about the resolution of this item.2.Insufficient inform-ation at present about the resultion of this item.3.Welding items have been resolved.Analysis by vendor showed adequacy of the welds.Most welds are for assembly, not for structural strength.Equipment not made by TDI or Portec.No impact on the conclusions of this report.Equipment not made by TDI or Portec.No relevance to the conclusions of this report.SH2471/1 A endix C EXPERIENCE REFERENCE DOCUMENTS Page C2 of 5 SHEARON HARRIS STATUS Brushes looked white hot while running.EOG-1 slip ring repair.During test, generator stator high temperature alarm was received.During electrical switch-ing operations, the El diesel breaker to the Unit 3 emergency bus failed to close because linkage in the breaker cubicle elevator mechanism cell switch ,was bent.NPRDS Davis-Besse 1, 810318, Hit 24 NPRDS Davis-Besse 1, 81-4-2, Hit 91 LER Prairie Island 1, 282-7400 740809 EPRI Peach Bottom 3 062775 DG-El Equipment not made by TDI or Portec.No impact on the conclusions of the report.Equipment not made by TDI or Portec.No impact on the conclusions of this repor t.Equipment not made by TDI or Portec.No impact on the conclusions of'his report.Equipment not made by TOI or Portec.No impact on the conclusions of this report.OG-El tripped on"A" phase differential re-lay after generator had been paral 1 cled.EPRI Peach Bottom 2 121977 DG-E1 False trip of protective relays.Does not concern the issues addressed in the report.Short between one coil to stator caused by loose laminations.

EPRI Pilgrim 1, 101178, DG-1B Diesel generator brush NPROS Brunswick 2, rigging damaged by arcing.830203 Hit 212 Equipment not made by TOI or Portec.No impact on the conclusions of this report.Equipment not made by TDI or Portec.No impact on the conclusions of this report.480 V ground due to grounded stator lead.NPRDS~10CFR50.55E.San Onofre 1, 760609, Hit 196 Equipment not made by TDI.or Portec.No impact on the conclusions of this report.SH2471/2

A endix C Page C3 of 5 EXPERIENCE Engine reached full speed and unit breaker tripped.Cause: broken ring type lug in the CT circuit.Detroit"Edison experi-ienced high vibrations on its diesel generator.

Auxi1 iary generator drive pulley failed.Cause: Original vleld failed.Failure of breaker to close because of bent linkage.Diesel generator inoperable because of overheating of ventila-tion cowling.Diesel generator failed to accept load because of undersized exciter leads.Diesel generator inoperable because of.overheating of ventila-tion cowling.Generator stator coils burned.REFERENCE DOCUMENTS NPRDS Millstone 1, 820913, Hit 179 ISE FERMI, Notice 83-51, 05/28/83 NPRDS San Onofre 1, 760114, Hit 189 NPRDS Peach Bottom 2 750627, Hit 187 NPRDS Fitzpatrick, 820819, Hit 228 MP8(L 83"024 10/22/83 NPRDS Fitzpatrick 820819, Hit 227 Service Report TPC Nuclear Plant No.3 Maanshan, dated 12/09/81 (Fil e T-45)SHEARON HARRIS STATUS Problem with relay circuit.Does not concern the issues addressed in the report.Equipment not made by TDI or Portec.Equipment not made by TDI or Portec.No impact on the conclusions of this report.Equipment not made by TDI or Portec.No impact on the conclusions of this report.Problem with circuit breaker.Does not concern the issues addressed in the report.Equipment not made by TDI or Portec.Equipment not made by TDI or Portec.No impact on the conclusions of this report.Equipment not made by TDI or Portec.No impact on the conclusions of this report.Equipment not made by TDI or Portec.No impact on the conclusions of this report.Equipment not made by TDI or Portec.No impact on the conclusions on this report.SH2471/3 af A endix C Page C4 of 5 EXPERIENCE REFERENCE DOCUMENTS SHEARON HARRIS STATUSDG-lA lost excitation voltage to the gener ator field.Loss of the generator field automatically opened the D/G breaker.The auxil-iary operator then manually tripped the diesel.A GM-EMD Part No.8283002 spring coil assembly, which holds a generator brush in place, vibrated loose.380-V ground due to grounded stator lead.During surv.testing, D-G E4 breaker failed to close.NON-NUCLEAR Maine-Yankee 309"82040 821211 San Onofre 1 760609, Hit 196 Peach Bottom 2, 102175 DG-Eg Thi s i s an i sol ated inci dent.Equipment not made by TDI or Portec.No impact on the conclusions of the report.One lead in the 600-kW auxiliary generator was grounded.The lead was replaced and the generator was returned to service.Equipment was not made by TDI or Portec.No impact on the conclusions of this report.Circuit breaker problem.Not related to the issues addressed in this report.Equipment was not made by Portec'r TDI.No'mpact on conclusions of the report.One incoming line of generator suffered a cable lug failure which arced out and cracked an insulator in the generator terminal box.Rafha/Saudi Arabia.Telex from Bailey (TDI)to Delaval HQ (File T-33)Isolated incident.Failure does not impact the con-clusions of this report.Fatigue failure of generator terminal lug.Rafha/Saudi Arabia.IOC from Bailey (TDI)to G.King (TDI)dated 05/12/81 (File T.-42)Isolated incident.Failure does not impact the con-clusions of this report.SH2471/4 A endix C EXPERIENCE REFERENCE DOCUMENTS Page C5 of 5 SHEARON HARRIS STATUS'oloit Power System, IKE Sitka, Alaska, generator Circular 80-23 l ost i ts f i el d because'itka, Al as ka a lead between collector rings and field coils shorted to rotor.Equipment not made by TDI or Portec.No impact on conclusions of this report.SH2471/5 TDI OWNERS GROUP for SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 GENERATOR CONTROLS COMPONENT PART NO.02"650B I INTRODUCTION The TDI Emergency Diesel Generator Owners Group Program for the Shearon Har ri s Nuc 1 ear Power Pl ant r equires Desi gn and equal i ty Reval i dati on reviews of the generator controls (manufactured.

by Electric Pr oducts Division, Portec, Inc.), Part No.72-10200-100; to determine the adequacy of the design for the intended use at Shearon Harris.The primary func-tions of the generator controls are to provide field current for the generator and to regulate the voltage of the 4.16-kV emergency bus.This is accomplished by the static exciter, which is the subject of this report.The static exciter consists of the following subcomponents:

~The diode bridge rectifier assembly and diverter silicon controlled rectifiers (SCRs), which together supply the field current.The voltage regulator, which controls the SCR firing circuits such that generator output voltage is maintained constant.The SCR firing circuits, which supply fi~ing pulses to the diverter SCRs.The field flashing circuit which ensures self excitation of the generator.

~The power potential transformer (PT), current transformers (CTs)and linear reactors, which supply the required ac voltage to the rectifi-er bridge and SCRs.The generator control cabinets as discussed in this report consist of a double depth set of cabinets, three cabinets wide.The bridge rectifier assembly, the voltage regulator, the SCR firing circuits, and the field flashing circuit are contained in the left front cabinet.This cabinet will be referred to as the exciter cabinet in the balance of this report.The power PT is in the right rear cabinet (behind right front cabinet).The power CTs and linear reactors are mounted in the left rear and center rear cabinets.'The governor controls, relaying, and meters are contained in the center front and right front cabinets and are not addressed in this report.SH2562/1 I J Page 2 of 14 I~~~~~~~~I I OBJECTIVE The objective of this review'is to verify the adequacy of the design and construction of'the static exciter for its intended use at Shearon Harris.I I I METHODOLOGY The Emergency Diesel Generator Component Tracking System (Ref.1)was reviewed for industry experience and the following subcomponents were identified for a detailed design review:~The diode bridge rectifier assembly and the diverter SCRs.~The voltage regulator.

~The motor-driven potentiometer.

~The field flashing circuit.~Linear reactors in the power circuit.Detailed design review calculations (Ref.2)were performed for the above'ubcomponents.

Specifically, calculations were made to verify the adequa-cy of the following:

~Continuous and surge current ratings of the.diodes and the SCRs.~The ratings of the components of the motor-driven potentiometer circuit.The ratings of the components of the field flashing circuit.~Thermal design of the linear reactors.The design of the voltage regulator was evaluated qualitatively (Ref.2)..The diesel generators at Shearon Harris were inspected on September 26, 1984 (Ref.3): Construction details, arrangement and mounting of the subcomponents of the static exciter were studied.Recommendations for maintenance procedures or modifications are made to address the various design and construction deficiencies found in the above subcomponents-of the static exciter.Other failure incidents reported in the EDG Component Tracking System printouts not involving the above subcomponents were reviewed and the results are given in Appendix C of this report.guality Revalidation Checklist results were reviewed for acceptability.

Applicable TERs were'reviewed.

SH2502/2

Page 3 of 14 The Emergency Diesel Generator Component Tracking System does not list any incidents related to operation of the generator controls at Shearon Harris.However, Shearon Harris DDR No.2028 is listed in the Component Tracking System and indicates that various construction deficiencies were found during the initial inspection of the generator control panels.This DDR has been reviewed as part of the design review process.All of the deficiencies reported in the DDR are construction deficiencies rather than electrical design deficiencies.

One of the deficiencies is the result of'oor wiring practices and is addressed in this design review.In the nuclear and non-nuclear industry experience, there are 70 incidents relating to the generator controls.Seventeen of the 70 incidents involve failures of the following subcomponents:

diodes of the bridge rectifier assembly and the diverter SCRs;the voltage regulator; the field flash" ing circuit;the motor-driven potentiometer.

The remaining 53 incidents are random failures and do not present any pattern indicating design problems.Design review'alculations (Ref..2)made for the above subcomponents reveal the following:

The diodes and the SCRs are adequately rated to conduct the maximum continuous and surge currents if there is free air convection in the exciter (left front)cabinet.,Recommendations for temperature monitoring are included in Attachment 1;The field flashing relay is inadequately rated.This is a relay operated from the 125-V (nominal)battery source and closes its contacts to supply, the field flashing current.Failure of the relay to close would make the diesel generator unavailable to supply the safety related loads.Procurement specifications (Ref.4)state that the voltage of the dc source may vary between 90 V and 140 V.The FF relay would fail to close its contacts when the source voltage is 90 V.Discussions with the relay manufacturer and with Portec confirm this fact.Results of analysis and copies of correspondence with Portec on this subject are enclosed in Reference 2.It is recom-mended that this relay be replaced by an appropriately rated relay.Detailed recommendations are given in Attachment 1 of this report.SH2502/3 T l.

Page 4 of 14~Thermal calculations for the linear reactors that supply current to.the exciter show that the temperature rating of the coil insulation will be exceeded if additional cabinet ventilation is not provided.The reactor coils are built with Class F insulation, which is rated for 155 degrees C (311 degrees F).Procurement specifications (Ref.4)require that the generator controls operate with a maximum ambient air temperature in the diesel room of 120 degrees F or about 50 degrees C.Calculations (Ref.2)show that at rated current and a surrounding air temperature of 50 degrees C the internal t'emperature of the coils is 157 degrees C.However, the reactors are mounted inside the left rear and center rear generator control cabinets, which are vented but not force ventilated.

The heat generated by the reactors themselves will cause a temperature rise of at least 10 degrees C.The coils will, therefore, operate very closely to the temperature rating of the insulation if ventilation is not provided.Detailed recommendations for ventilation of the cabinets are dis-cussed in Attachment 1.gualitative evaluation of the design of the voltage regulator indicates that although this subcomponent can perform its intended functions, several desirable features that ensure high reliability and performance have not been incorporated in the design.These features are power supply bypassing, coating of all adjustable potentiometer spindles with Glyptol lacquer, using MIL style multiturn sealed potentiometers, soldering i.ntegrated circuits to the printed circuit board (PC)directly instead of mounting in sockets, using double-sided PCs, conformal coating of the PC boards, and shielding signal leads.Detailed recommendations to incorpo-rate these features are made in'ttachment 3 of this report.When the recommendations are implemented the long-term reliability and performance of the voltage regulator will be enhanced.As the voltage regulator in its present state is adequate to meet its intended functions, implementa-tion of the recommendations of Attachment 3 is left to the discretion of.-CPKL.At Shearon Harris there is a spare voltage regulator board which can be switched in if the original voltage regulator fails.Therefore, redesign of the voltage regulator, although desirable, is not mandatory.

Inspection of the subcomponents reviewed in this report (Ref.3)revealed the following construction and mounting inadequacies:.

~The diodes of the bridge rectifier assembly are mounted on the heat sinks by tapped holes, contrary to the manufacturer's recommenda-tions.The SCRs of the bridge rectifier assembly are mounted with nuts.However, the Portec assembly drawings call for a tapped hole in the heat sink.During the inspection, it was not possible to determine whether the hole is tapped or has been drilled out.Two leading manufacturers specifically advise against mounting by tapped holes.~The generato~control cabinets are inadequately ventilated.

SH2502/4 g h~ill'~

Page 5 of 14 Power cables are terminated with up to three lugs on one stud, contrary to good wiring practice.These deficiencies do not presently endanger the diodes and SCRs.But for continued safe operation, these deficiencies should be remedied to ensure proper thermal and electrical contact with the heat sinks, to prevent loosening of the diodes by vibration, and to ensure proper contact at all cable terminations.

Remedial measures are recommended in the form of maintenance and modification procedures as detailed in Attachment 1 of this report, and design and construction modifications as detailed in Attachment 2 of this report.The recommendations of.Attachment 1 may be implemented without significant modification of the existing equipment.

These recommendations will allow monitoring on the temperature of the.diodes and the SCRs.The recommendations of Attachment 2 involve remount-ing of the.diodes, installing cooling fans in the exciter cabinet and redesign of the cable terminations.

These recommendations may be imple-mented at the first refueling outage of the plant or earlier at the dis-cretion of CP&L.Recommendations to remedy the design and construction deficiencies are organized as follows:~Attachment 1-the recommendations are to be implemented prior to placing the engine in emergency standby service to enable monitoring of the diodes.Recommendations are also made concerning the field flashing relay, linear reactors, heat sink wiring, and voltage regulator.

~Attachment 2-the recommendations are to be implemented at the first refueling outage of the plant.or earlier at the discretion of CPCL to alleviate the need for the maintenance procedures in Sections IA, IB, and IC of Attachment 1.~Attachment 3-the recommendations are to be implemented at the discretion of CP8L to enhance the long-term reliability and perfor-mance of the voltage regulator.

Other incidents of failures reported in the EDG Component Tracking System not involving the subcomponents considered in this report were reviewed.The results are given in Appendix C of this report.It was found that the failures were not of generic nature and do not impact the conclusions of this report.I The information provided on TER 02-074, dated 10/15/84, has been reviewed and is consistent with the final conclusions of this report.guality Revalidation Inspection results identified in Appendix B of this report have been reviewed and considered in the performance of this design review and the results are consistent with the final conclusions of this r epor t.SH2502/5

Page 6 of 14 Based upon the above review, it is concluded that the generator controls are adequate for their intended use at Shearon Harris if all the recommen-dations of Attachment 1 of this report are adopted.The recommendations of Attachment 2 of this report should be implemented at the first refueling outage or earlier at the discretion of CPEL so that the re-commendations in Sections IA, IB, and IC of Attachment 1 are no longer necessary.

Recommendations of Attachment 3 of this report may be imple-mented at the discretion of CPEL to improve the long-term reliability.

V REFERENCES 1.Component Tracking System printout for Shearon Harris Nuclear Power Plant, Component Part No.02-650B, dated 09/17/84.2.FaAA design review support package SP-84-6-46 (F).3.Alexander Kusko, Inc.Trip Report, Shearon Harris Nuclear Power Plant, dated 09/26/84.4.EBASCO Procurement Specification 216-73Tb dated April 25, 1978, Rev.3.SH2502/6'

Page 7 of 14 Attachment 1 Shearon Harris Nuclear Power Plant-Unit 1 Maintenance and Modification Procedures

-Generator Controls I BRIDGE RECTIFIER ASSEMBLY A.~0i M Monitor the maximum temperature attained by the diodes by placing a temperature-sensitive label on the most visible face of the hexagonal body of the diode..2~The temperature-sensitive Abel should be of the type that permanently blackens when its temperature has been reached.or exceeded.3.4.The temperature rating of the labels shall be 275 degrees F.Omega brand model BE-275 or equivalent (Ref.1)is recommended.

The label shall be inspected before and after each running of the emergency generator.

5.6.I f the temperature l abel indi cates that the speci f i ed temper a-ture has been exceeded, perform an electrical test of the diode (Ref.2), remove the diode from the heatsink and inspect the mounting threads of the heatsink and the diode.Replace the diode and the heatsink as required to assure that proper mounting tightness, 360 in-lbs (Ref.3)and thread condition is maintained.

B.~KR-M 1.Monitor the SCR maximum temperature as in I.A above.2.Use Omega brand model BE 220 or equivalent (Ref.1)for 220 degrees F.3.Tighten to 360 in-lbs (Ref.4).C.Heatsink 1.Coat the side of the lugs and mounting bolt for the lugs that attach to the bottom of the diode and SCR Heatsinks with Glyptol lacquer (Ref.5).2...Apply the Glyptol on a readily visible side so that relative motion of the lugs with respect to one another or with respect to the mounting bolt can be detected.SH2502/7

Page 8 of 14 3.Inspect the connections after each monthly test of the emergency generator.

4.Retighten connections that appear to have loosened.Remove old Glyptol and reapply if connections are retightened.

II VOLTAGE REGULATOR BOARDS A.Ad ustment Potentiometers 1.Coat one.side of the adjustment screw for each of the five adjustment potentiometers on the printed circuit board of the voltage regulator with Glyptol lacquer.2.'f adjustments are needed, remove the Glyptol.and reapply when the adjustment procedure is complete.B.Printed Circuit Board 1.At each refueling outage, remove the covers of the voltage regulator enclosures and inspect the components mounted on the printed circuit boards.Check for cleanliness and proper mounting of components.

Report any abnormal conditions to engineering for evaluation.

C.~5P l.It is recommended that an adequate supply of spare parts be maintained.

III FIELD FLASHING RELAY A.Replace the FF relay (a dc contactor, class P10 Cat.No.P102D12 made by Gould Distribution and Control Division (Ref.6)by an equivalent

'c contactor rated as follows: Coil voltage,90-140 V;contact voltage, 140 V dc;contact current, 70A dc.The relay should be on the enclosed type to prevent particles of dirt from.being deposited on the contacts.It may be necessary to install a voltage regulation circuit to permit the use of a contactor with a conventional coil voltage range.IV POWER CIRCUIT LINEAR REACTORS A.The left rear and center rear cabinets must be ventilated or cooled so that the air temperature in the cabinet does not exceed 50 degrees C (120 degrees F).SH2502/8 0'

Page 9 of 14~~~V REFERENCES 1.1983 Omega Temperature Measurement Handbook, Omega Engineering, Inc., p.005.2.Portec Static Exciter Voltage Regulator Model 72-10200-100 Instruc-tion Manual.3.Westinghouse Power Semiconductor Manual pp R35-R38.4.Westinghouse Power Semiconductor Manual pp 541-544.5.Gerber Electronics Catalog, p.585-General Cement Production Bulletin.6.Ported Dwg.D72-10200-710.

SH2502/9

+I, JSj+

Page 10 of 14Attachment 2 Shearon Harris Nuclear Power Plant-Unit 1 Recommendations for Desi n and Construction Modifications

-Generator Controls I Brid e Rectifier Assembl A.Exciter Cabinet Ventilation 1.The bridge rectifi'er assembly in the exciter cabinet (left front cabinet)must be ventilated so that the air temperature inside the cabinet does not exceed a temperature of 60 degrees C (140 degas ees F).2.Ventilation may be accomplished by supplying chilled air into the cabinets, by installing exhaust fans or by other means.If chilled air is used, care must be taken to avoid condensation within the cabinet.B.~BMM M 1.The diodes should be mounted on the heatsinks with drilled holes, nuts, and lockwashers, and tightened to the proper torque (Ref.1).M~ddd M 1.The SCR's should be mounted on the heatsinks with drilled holes, nuts, and lockwashers, and tightened to the.proper torque (Ref.2).D.Heatsink Connections 1.The bolted on lug arrangement must be redesigned so that there are no more than two lugs on each bolt.2.Heatsink anodizing must be removed in the co'ntact areas of all bolts and bus bar studs.3.Current-carrying surfaces of lugs must not be separated by washers or nuts.II VOLTAGE REGULATOR BOARDS Any integrated circuit which is in the TO-5 (metal can)package shall be replaced with those of the DIP (Dual-in-Line) or Mini-DIP package.Both RCA (Refs.3 and 4)and National Semiconductor Corporation (Ref.5)manufacture IC's in TO-5 and Mini-DIP (or DIP)packages, which are pin compatible with each other.SH2502/10 Page 11 of 14 III POWER CIRCUIT REACTORS ,One, terminal of the reactors has 3 lugged wires attached to it.The lug arrangement should be modified so that there are no more than two lugs on any one bolt.IV REFERENCES 1.Westinghouse Power Semiconductor Manual pp R33-R38.2.Westinghouse Power Semiconductor Manual pp 541-544.3.Spec Sheet-RCA Linear Integrated Circuits, Type CA3094.4.Spec Sheet-RCA Linear Integrated Circuits, Type CA723T.5.Spec Sheet-National Semiconductor Corporation Operational Amplifier, Type LM741.SH2502/11 l4 J J"%II Page 12 of 14 Attachment 3 Shearon Harris Nuclear Power Plant-Unit 1 Modifications Recommended to Im rove Lon-Term Reliabilit

-Generator Controls I VOLTAGE REGULATOR A.~Ci i 0 1.Power Su l B assin The purpose of power supply bypassing is to prevent ac noise voltage generated outside the voltage regulator circuit from interfering with its operation and to prevent voltages generated by the circuit itself from propagating in the circuit.Inspec-tion of the PC board and the voltage regulator schematic shows that power supply bypassing has been almost completely neglected in the circuit design.The following modifications are recommended:

.a.The power supply terminals of each individual integrated circuit (IC)should be bypassed with a 0 01-0 1 pF ceramic capacitor from its supply terminals to ground (Ref.1).The high current buffers (U3, U5, U7, Portec Drawing No.D72-13000-710 Rev.B, Schemati c-SVS Regulator with paralleling) require bypassing capacitors of 0.1 pF so that transients will not get back to the ICs (Ref.2).2.b.In addition to the high frequency bypass capacitor, a large.value capacitor (approximately 10 pF)is required for voltage regulator op amp U1, Portec Drawing No.D72-13000-710, Schematic-SVS Regulator with paralleling.

This is because of the presence of CR31 and R73.Shieldin and Routin of External Si nal LeadsShielding and proper routing of signal leads external to the PC board is intended to prevent electromagnetically induced noise voltages from entering the signal leads.This is done by using shielded signal leads and by routing the leads so as to maximize the distance between the signal and high current leads.These techniques have been neglected in the wiring of the voltage regulator.

The following modifications are recommended:

a.Shielded signal leads should be used for the connections between the motor-driven potentiometer and the voltage regulator.

SH2502/12 Page 13 of 14 b.A high frequency bypass capacitor providing an in-circuit low frequency cutoff of no less than 1.kHz be installed to reduce high frequency noise on the feedback signal without interfering with the feedback loop operation.

c.The leads for the SCR gate signals should be run in sepa-rate bundles away from the current carrying leads.3.'urrent Feedback Si nal The purpose of the current feedback signal is to improve the closed loop response of.the voltage regulator.

The current feedback signal is derived from a sensing transformer which measures one of the diode currents in the bridge rectifier.

The following modification should be made to improve the stability of the voltage regulator while providing the same performance.

Replace the single-phase current sensing circuit with a three-phase current sensing circuit.This requires the use of a three-phase sensing transformer and a three-phase bridge recti-fier circuit on the PC board.Additional stability is provided by reducing the filtering requirements of the feedback signal, which are presently provided by a resistance-capacitance filter on the PC board.B.Construction 1.Vibr ati on Protecti on Reliable mounting of components on the PC board and the proper selection of components is necessary to ensure that the voltage regulator can withstand the vibration encountered during seismic events, construction or maintenance.

However, the design of the board does not appear to be adequate for.these conditions.

At a minimum, the following modifications should be made: ao b.The nine integrated circuits on the PC board which are presently mounted in sockets should be soldered directly to the PC board (Ref.3).The voltage range and stability adjustment potentiometer (R4 and R5)are unsealed, one turn commercial grade devic-es.General recommendations in Reference 4 suggest that NIL style components should be used in such Class 1E applications.

These potentiometers should be replaced with MIL style, sealed, multitur n potentiometers to improve the reliability and stability of these components.

SH2502/13 Page 14 of 14 2.Printed Circuit Board Construction It is essential that the PC board construction be suitable for the reliability, mechanical, environmental and electromagnetic requirements of the Class lE application.

The following modifi-cations should be made to ensure adequacy of the design: a 0 b.C.d.The board material has not been identified at this time.A NEMA grade G-10 glass epoxy board material should be used.The present PC board is a single-sided board (i.e., copper circuit on one side and components on the other).Double-sided PC boards are commonly used in noise sensitive applications and where high reliability is necessary.

The extra copper layer provides additional bypassing of high frequency AC noise.The PC board should be conformally coated as a final step in manufacturing.

Conformal coating prevents humidity and airborne particles from affecting the operation of'he circuitry.

Components should be soldered directly to the PC board.If sockets are used, retaining mechanisms must be provided to hold the components in the sockets.II REFERENCES 1.Roberge, J.K.,"Operational Amplifiers

-Theory and Practice," p.444, John Wiley 8 Sons, Inc., New York 1975.2.Stout D., and M.Kaufman,"Handbook of Operational Amplifier Circuit Design," p.3-27, McGraw-Hill Book Co., New York 1976.3."IEEE Trial-Use Guide for Class 1E Control Switchboards for Nuclear Power Generating Stations," IEEE Std.420-1973, p.8, Sec.4.1.2.4."IEEE Standard: Criteria for Protecting Systems for Nuclear Power Generating Stations," IEEE Std.279-1971, p.8, Sec.7.3.SH2502/14 Jp e E APPENDIX A Page Al of 2 COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER STATION-UNIT 1 COMPONENT Emer enc Generator Controls UTILITY Carolina Power 8 Li ht Co.GROUP PARTS LIST NO.02-650B SNPS GPL NO.03-650B TASK DESCRIPTION NO.DR-02-02-650B-0 CLASSIFICATION TYPE A TASK DESCRIPTIONS The design review of the generator controls focuses on the generator exciter.Specific steps to the design review are: Review the site experience reported in the Component Tracking System.Contact site personnel to obtain additional background information on the exciter.Identify Component Tracking System events that're related to the design of the equipment.

Perform a site inspection to gather additional information on the construction, installation, operation, and enviro'nment of the equipment.

These inspections constitute the quality revalidation effort for this component.

The exciter is typically organized as three assemblies:

1)the bridge rectifier assembly, consisting of diodes and thyristors; 2)the voltage regulator consisting of one or more printed circuit boards;and 3)a motor driven potentiometer.

Design review calculations are performed to verify the adequacy of these assemblies.

Recommend maintenance procedures or modifications as needed to assure the adequacy of the exciter.Verify that all'design related events listed in the Component Tracking System are addressed by the design review.Review information provided on TERs.PRIMARY FUNCTIONProvides field current for the generator and regulates the generator AC output voltage.SH2002/1

+tl"l Yi Page A2 of 2 DR-02-.02-650B-O A TTRIBUTES TO BE VERIFIED Diodes'in bridge assemblies:

cooling, current and voltage rating.Diode surge current ratings.Bridge assembly construction and wiring.Silicon Controlled Rectifier s ,in bridge assembly: cooling, current and voltage ratings.Voltage.t egulator design and construction.

Motor driven potentiometer component ratings.Potential Tranformer's, Current Transformer's, and 1'inear reactors: mounting and cooling SPECIFIED STANDARDS Not required REFERENCES Diesel generator procurement specification.

DOCUMENTATION RE UIRED Site information on the generator exciter including:

1.'anufacturer s instruction manual.2.Diesel generator procurement specification.

3.Diesel generator onsite test data.Manufacturer' information including:

1.Electrical schematics for the exciter, all assemblies and sub-assemblies within the exciter.2.A description of the exciter's circuit configuration.

3.Industry standard part numbers for all power handling components, integrated circuits and other parts purchased by the manufacturer."Heat sink configurations for the major power semiconductors.

Design data for the power handling magnetic components.

GROUP CHAIRPERSON SH2002/2 PROGRAM MANAGER<hvVW>%(

A endix B Page Bl of 3 02-02-650B COMPONENT UALITY REVALIDATION CHECKLIST Generator-COMPONENT Generator Control GPL NO.02-650B SNPS GPL NO.03"650B Carolina Power 8 Light Shearon Harris Nuclear UTILITY Power Plant-Unit 1 REV.NO.2 TASK DESCRIPTIONS En ine 1A"SA l.Assemble and review existing documentation.

~Ei 8-88 1.Assemble and review existing documentation.

2.Visually inspect the three phase voltage regulator to identify the specific components.

3.Visually inspect the voltage regulator bridge rectifier to check the method of bonding the diodes to the heat sinks.4.Visually inspect the , exciter to determine the wiring and construction method used.ATTRIBUTES TO BE VERIFIED~Ei 1A-EA 1.guality status of Component Document Package~Ei 18-8 1.guality status of Component Document Package 2.Specific components of three phase voltage regulator 3.Method by which diodes were bonded to the heat sinks SH1755/1 VPp'l" COMPONENT UALITY REVALIDATION CHECKLIST Page B2 of 3 02"02-650B

, ATTRIBUTES TO BE VERIFIED (continued)

~di 8-88 (I 8)4.Wiring and construction method used on exciter.ACCEPTANCE CRITERIA En ine 1A-SA 1.Satisfactory Document Package~di IB-EB 1.Satisfactory Document Package 2-4;Review of inspection report by the Design Group REFERENCES En ine lA-SA 1.QCI No.52~di IA-EB 1.QCI No.52 2-4.Appr oved NDE Procedures, TERS'9-014 DOCUMENTATION RE UIRED~di IA-EA 1.Document Summary Sheet~di-8 1.Document Summary Sheet 2-4.Inspection port GROUP CHAIRPERSON PROGRAM MANAGER SH1755/2 COMPONENT UALITY REVALIDATION CHECKLIST Page B3 of 3 02-02-650B COMPONENT REVIEM En ine 1A-SA 1.All EDGCTS site experience documents were assembled and reviewed with unsatisfactory results.DDR No.2028 remains open.En ine 1B-SB l.All EDGCTS site experience documents were assembled and reviewed with unsatisfactory results.DDR No.2028 remains open.2.A trip report was received transmitting the results for the required inspections.

Results were reported by TERO.02-074..RESULTS AND CONCLUSION En ine 1A-SA The guality Revalidation effort with respect to this component, as outlined above, is complete.The results have been forwarded to the Design Review Group for their evaluation and conclusions in support of the final report.~Bi BB-BB Same as Engine 1A-SA'-GROUP CHAIRPERSON PROGRAM MANAGER~MY SH1755/3 4 J V A endix C Page Cl of 9 EDG COMPONENT TRACKING SYSTEM: SHEARON HARRIS SITE NUCLEAR AND NON-NUCLEAR INDUSTRY EXPERIENCE

SUMMARY

COMPONENT NO.02-650B E f f ecti ve Printout Date 09/17/84 COMPONENT TYPE: Generator ControlsEXPERIENCE SHEARON HARRIS Generator control panels found to have electrical items not in compliance with EBASCO Dwg.1364-45124 through 1364-45131.

NUCLEAR Generator tripped because of failur e of diode in voltage regulator motor operated potentiometer.

Deficiency in test proce-dure.New procedure developed.

Generator failed to excite or startup because of unused relay target.Problem with residual voltage relaying.New relay installed.

Faulty lead on generator monitoring instrumentation.

REFERENCE DOCUMENTS DDR No.2028 EPRI Pilgrim 1 073074 DG"1B Alco Engine Div.LER North Anna 2 339-82013$

820308 Ser.62-82, Fairbanks-Morse.Oyster Creek 219-78031, 781130, GM-EMD LER North Anna 2 339-82018, 820427 Fairbanks-Norse LER North Anna 2 339-80003,.800528 Fairbanks-Morse SHEARON HARRIS STATUS Equipment was installed or wired improperly.

Not a design related incident.This incident is a random failure and does not pose a pattern of concern for Shearon Harris.This incident is a result of operator error or a proce-dural problem and is not related to a design defici-ency of the equipment.

Equipment was installed or wired improperly.

Not a design related incident.This incident ha's no relationship to the design of the equipment at Shearon Harris.This incident is a random failure and does not pose a pattern of concern for Shearon Harris.SH2502/1 8h]!1 ,l l A endix C EXPERIENCE

~Generator did not pick up load.Worn brushes on motor-driven potentiometer.

REFERENCE~DOCUMENTS LER Kewaunee 305"74000, 740719 NPRDS"Hit 232, GM-EMC Page C2 of 9 SHEARON HARRIS STATUS This sncsdent has no relationship to the design of the equipment at Shearon Harr is.Generator failed to excite because of loose fuse holder in exciter.Generator tripped because of increase in main generator voltage.Operator caused mis-match between main generator and diesel generator.

Generator tripped.Generator tripped while running.Diodes failed.LER Calvert Cliffs 1 317"7700, 771010 Fairbanks-Morse LER Calvert Cliffs 1 318-78000, 780110'PRI" NP-3933 6/82 Fairbanks-Morse LER Millstone 2 336-77000, 771109 Fairbanks-Morse LER Big Rock Point 155-700000 700B06.Caterpillar This incident is a random failure and does not pose a pattern of concern for Shearon Harris.This incident is a result of operator error or a procedural problem and is not related to a design deficiency of the equip-ment.Thi s inci dent i s a res ul t of operator error or a procedural problem and is not related to a design deficiency, of the equip-ment.Failures in the bridge rectifier circuit are addressed in the report.Maintenance items and design changes are recom-mended.Generator voltage could not be adjusted from the control room because of a loose fuse clip.Generator voltage dropped while running.SCR's failed in voltage regulator.

Generator tripped on start of RHR pump due to design error-1981 modification.

EPRI Pilgrim 1 032574 DG-1B Alco Engine Div.Grand Gulf Report Number 83-024, 9/22/83 TDI SER squad Cities 1 78"82 6/22/82 GM-EMD This incident is a random failure and does not pose a pattern of concern for Shearon Harris.Failures in the voltage regulator are addressed in the report.Maintenance items and design changes are recommended.

This incident has no relationship to the design of the equipment at Shearon Harris.SH2502/2 f"k ,~V A endix C Page C3 of 9 EXPERIENCE REFERENCE DOCUMENTS SHEARON HARRIS STATUS Potential logic problem noted during design review.Breaker failed to operate because of uncharged spring.Design deficiency found;time delays being installed.

SER Palisades 59"82 8/27/82 Alco Engine Div.SER Fort St.Vrain 38-82 05/01/82 Cater pi 1 1 ar SER North Anna 1.55-80 11/14/80 SOER 81-10'airbanks-Morse This incident has no relation-ship to the design of the equipment at Shearon Harris.This incident is a result of operator error or a procedural problem and is not related to a design deficiency of the equipment.

This incident has no relation-ship to the design of the equipment at Shearon Harris.Offsite power,not restored owing to design error in breaker circuit.Design change made.Voltage regulator failed owing to water leak.~~~~Generator did not excite owing to dirty relay contacts in FF circuit.Generator voltage spiked to'greater than 5200 V owing to bad solder joint on voltage regulator printed circuit board.Diesel tripped from wrong frequency setting.Generator voltage dropped to 3000 V and oscillated owing to bad amplifier in voltage regulator.

SER Almaraz 1 79"82, 10/13/81 SOER 83-6 EPRI Peach Bottom 2 012474-DC-4 Fairbanks-Morse LER Dresden 2 237-75000, 750319 EPRI-NP-2433, 6/82 NPRDS-Hit 145, GM-EMD LER Zion 1 295-78002, 780103 EPRI-NP-2433, 6/82 Cooper-Bessemer.

NPRDS Dresden 2 7707712 Hit 125 GM-EMD LER Zion 2 304-79017, 790310 EPRI" NP-2433 6/82 Cooper-Bessemer This incident has no relation-ship to the design of the equipment at Shearon Harris.Thi s inci dent has no re 1 ati on-ship to the design of the equipment at Shearon Harris.Failures in the field flashing circuit are addres-sed in the report.Design changes are recommended.

Failures in the voltage regulator are addressed in the report.Design changes are recommended.

This incident is a result of operator error or procedural problem and is not related to a design deficiency of the equipment.

Failures in the voltage regulator are addressed in the report.Maintenance items and design changes are recommended.

SH2502/3 1

A endix C Page C4 of 9EXPERIENCE Gener ator vol tage oscillates between 3000-4000 V because of drift of voltage regulator stability circuit.Generator voltage rose to 4300 volts and could not be lowered during test due to bad K-1 relay.Voltage regulator failed because of miswound paralleling transformer.

Generator failed to excite because of dirt in FF relays.No output voltage from generator.

Ground short because of chafing of leads.Generator paralleled out of phase.Diodes in regulator circuit failed.REFERENCE DOCUMENTS LER Zion 2 304"78041, 780517 EPRI-NP-2433 6/82 Cooper-Bessemer LER Zion 2 304-78005,'780106 EPRI"NP-2433 6/82 Cooper-Bessemer Grand Gulf Report Number 83-024 9/22/83 TDI LER Peach Bottom 2 277-75000, 75042B EPRI-NP-2433 6/82 042818-DG E2 NPRDS-Hit 188 Fairbanks-Morse LER Zion 1, 295 75000, 750118 EPRI" NP-2433, 6/82 NPRDS Pilgrim 1 780802, Hit 93 EPRI-08278 DG-1B Alco Engine Div.SHEARON HARRIS STATUS Failures in the voltage regulator are addressed in the report.Maintenance items and design changes are recommended.

This incident is a random failure and does not pose a pattern of concern for Shearon Harris.'quipment was installed or wired improperly.

Not a design related incident.Failures in the field flashing circuit are addressed in the report.Design changes are recom-mended.This incident is a random failure and does not pose a pattern of concern for Shearon Harris.This incident is a,random failure and does not pose a pattern of concern for Shearon Harris.Generator tripped.Rectifier assembly failed.NPRDS Salem-1 771104 Hit 85 Alco Engine Div.Failures in the bridge rectifier circuit are addressed in%he report.Maintenance items and design changes are recommended.

Generator failed because of inverter failure.Generator voltage cutout failed because of sticky relay contacts.LER Cook 1 315-82076$

820823 NPRDS Trojan 1 830418, Hit 259 GM-EMD This incident has no relation-ship to the design of the equipment at Shearon Harris.This incident is a random failure and does not pose a pattern of concern for Shearon Harris.SH2502/4

'1t A endix C Page C5 of 9 EXPERIENCE REFERENCE DOCUMENTS SHEARON HARRIS STATUS Over-excitation alarm actuated on shutdown because of defective relay.NPRDS Trojan 1 830268, Hit 260 GM-EMD This incident has no relation-ship to the design of the equipment at Shearon Harris.Following SCRAM, generator EPRI Brunswick 2 could not be put on bus 021378 DG-1 because of failure of Norberg loss of excitation relay.Procedure revised.This incident is a result of operator error or a procedural problem and is not related to a design deficiency of the equip-ment.Instrument inverter fail ed.EPRI Zion 1 081179 Inv.114 DG-0 This incident has no relationship to the design of the equipment at Shearon Harris.Generator tripped.Suspected bad potential transformer.

NPRDS Pilgrim 1 800 505 Hit 2 and 92 Alco Engine Div.This incident is a random failure and does not pose a pattern of concern for Shearon Harris.Generator failed to'ield flash because of burned out rectifier.

Generator overloaded because of operator"er ror.Generator did not excite because of failed coil.NPRDS guad Cities 1 770425, Hit 158 GM"EMD NPRDS Zion 2 760919$Hit 238 Cooper-Bessemer

'V NPRDS Brunswick 2 810629, Hit 211 Norber g Failures in the field flashing circuit are addressed in the report.Design changes are re-commended.

This incident is a result of operator error or a procedural problem and is not related to a design deficiency of the equipment.

Failures in the field flashing circuit have been addressed in the report.Design changes are recommended.

Generator field flashing NPRDS Brunswick 1 relay failed on startup.*820726 Hit 205 Norberg Failures in the field flashing circuit are addressed in the report.Design changes are recommended.

SH2502/5 I p J A endix C Page C6 of 9 EXPERIENCE REFERENCE DOCUMENTS SHEARON HARRIS STATUS Generator started because of false undet voltage condition.

Generator failed to energize bus because of broken wire lug.Generator failed to operate with proper voltage and frequency because of failed fuse.Rectifier found to be disconnected.

Repair made.Generator tripped because of shorted resistor in logic circuit.EPRI Brunswick 2 010976 DG-1 Norberg EPRI Davis Besse 060478, OG-1-1 NPTOS Hit 90~GM-EMO ICE Notice 83-51 Clinton NP 05/20/83 Louis-Allis NPRDS Brunswick 1 810708, Hit 204 Norberg Equipment was installed or wired improperly.

Not a design related incident.This incident is a random failure and does not pose a pattern of concern for Shearon Harris.Equipment was installed or wired improperly.

Not a design related incident.This incident has no relationship to design of the equipment at Shearon Harris.Generator field failed to flash because of dirty relay contacts.NPRDS San Onofre 1 821123, Hit 262 TDI Failures in the field flashing circuit are addressed in the report.Design changes are recommended.

Voltage regulator did not.control generator voltage because of failed.source cir cui.t breaker.NPRDS Arkansas NUC 1 830413, Hit 269 GM-EMD This incident is a random failure and does not pose a pattern of concern for Shearon Harris.Generator did not respond to.manual voltage control because of failed K-1 relay.EPRI Zion 1 072204 DG lA, B Cooper-Bessemer This incident is a random failure and does not pose a pattern of concern for Shearon Harris.Relay burned up in control panel because of coil failure.NPROS Kewaunee 750730, Hit 233 GM-EMD This incident is a random failure and does not pose a pattern of concern for Shearon Harris.Diesel generator tripped on overspeed because of SCR failure in inverter.EPRI Cook 1.120976 OG-CD Worthington This incident has no relationship to the design of the equipment at Shearon Harris.SH2502/6

A endix C EXPERIENCE Diesel generator failed to star t because of faulty switch.Switch repaired.Control circuit breaker tripped because of slow blow fuses.Generator tripped'ecause of shorted resistor in logic.REFERENCE DOCUMENTS LER Dresden 1 010-78013, 780304 EPRI-NP-2433 LER Zion 1 295-80012, 800312 NPRDS Zion 1 800312 Hit 47 Cooper-Bessemer DPRDS Brunswick 1 810614, Hit 204 Norber g Page C7 of 9 SHEARON HARRIS STATUS This incident is a random failure and does not pose a pattern of concern for Shearon Harris.This incident has no relationship to the design of the equipment at Shearon Har ris.This incident has no relationship to the design of the equipment at Shearon Harris.Voltage regulator failed LER MPHIL;83-140 because of burned out GGNS DG Reliability SCR.SCR repl aced.Report 10/26/83 Fai,lures in the voltage regulator are addressed in the report.Mainten-ance items and design changes are recommended.

Blow PT fuse alarm because of CFVB relay malfunction.

NPRDS Arkansas Nuc 1-1 750423, Hit 264 GM-EMD This incident is a random failure and does not pose a pattern of concern for Shearon Harris.Generator tripped lock out relay and loss of excitation relay because of blocking device.Generator tripped"not available" alarm.High main-tancence caused vibra-tions.The vibrations caused differential relays of Phase A to C to trip.Potentiometers in NGV relays defective.

LER Arkansas Nuc 1, 313-81007"1, 810427 GM-EMD EPRI Brunswick 2 0220679 DG 1 GM"END Shoreham LER 322 78000 780301 TDI This incident is a random failure and does not pose a pattern of concern for Shearon Harris.This incident is a random failure and does n'ot pose a pattern of concern for Shearon Harris.Vendor defect.Not related to components in review.SH2502/7 A endix C Page C8 of 9 EXPERIENCE REFERENCE DOCUMENTS SHEARON HARRIS STATUS Generator did not respond to manual control.Regulator with dirty contact.Voltage regulator board found defective during inspection.

Field Crea'ker would not cl ose.Failed field diode.EPRI Zion 1, 072874, DG 1A and 1B NPRDS Arkansas Nuclear 1 780130, Hit 226, GM-EMD NPRDS guad Cities 1, 771128, Hit 157 GM"EMD Failures in the voltage regulator are.addressed in the report.Main-tenance items and design changes are recommended.

Failures in the voltage regulator are addressed in the report.Main-tenance items and design changes are recommended.

~+This incident has no relationship to the design of the equipment at Shearon Harris.Generator field failed to flash.Shorted capacitor in field flashing circuit.Malfunction because of a shorted selenium rectifier in the generator field circuit.Short was caused by build up of dirt.Generator field failed to flash.Shorted capacitor in field flashing circuit.Generator tripped on overspeed.

Fuse in clip unsprung causing poor con-tact.LER Dresden 3, 249-77000, 770322 NPRDS Hit 149 GM"EMD LER Dresden 2 237-76000, 760930 NPRDS Hit 123 EPRI-NP-2433 6/82 GM-EMD NPRDS Dresden 2 750405 Hit 146 GM-EMD NPRDS Browns.Ferry 3 770919 GM-EMD This equipment is not made by TDI.Fail-lure of a similar capacitor in the Shearon Harris system would not prevent the generator from field flashing.This incident is a ran-dom failure and does not pose a pattern of concern for Shearon Harris.This equipment is not made by TDI.Failure of a similar capacitor would not prevent the generator from field flashing.This incident is a random dom failure and does not pose a pattern of concern for Shearon Harris.SH2502/8 A endix C EXPERIENCE Design deficiency in application of Westinghouse ECT.current transform-er operated outside rated temperature.

Diesel generator tripped oh loss of field..DG-El tripped on A-phase differ-ential after par-alleling with E12 4-kV bus.no problem found.NON-NUCLEAR None.REFERENCE DOCUMENTS 10CFR40, 55E Wash Pub Supply System 12/15/81 TDI LER Indian Point 2 247-74000, 740315 Alco Engineering Division.Peach Bottom 2 121977 EPRI DG-E1 Fairbanks-Morse Page C9 of 9 SHEARON HARRIS STATUS The corresponding CT used in the Shearon Har ris static exciter is different from the one reported in the failure.Insufficient information tion in reference documents for evaluation.

This incident is a random failure and does not pose a pattern of concern for Shearon Harris.SH2502/9 COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Page 1 of 2 Generator:

COMPONENT Shaft 8 Bearin s GROUP PARTS LIST NO.02-650C SNPS GPL NO.03-650C UTILITY Carolina Power 5 Li ht Com an TASK DESCRIPTION NO.DR-02-02-650C-0 CLASSIFICATION TYPE ATASK DESCRIPTION Design review for this component is not required based on:~The static lateral and dynamic torsional loadings were computed and used to evaluate both the generator shaft factor of safety, for yielding and fatigue, and the bearing operating characteristics.

The resulting bearing operating characteristics are within accepted industry allowables and the factors of safety are comparable to the lead engines at Shoreham and Comanche Peak.~A rpview of the EDG Component Tracking System indicates that there have been no design related problems associated with component.

Shearon Harris site experience reports some cases of non-compliance with dimensional tolerances and weld criteria for the bearing pedestal.The pedestal was dispositioned by the Utility as acceptable and has no impact on the acceptability of the generator.

shaft and bearing.There are no maintenance or modification recommendations for this component other than those specified by TDI.guality revalidation for this component is not required.PRIMARY FUNCTION Not required ATTRIBUTE TO BE VERIFIED Not required SH2664/1 SPECIFIED STANDARDS Not required COMPONENT DESIGN REVIEW'HECKLIST Page 2 of 2 DR-02-02-650C-0 REFERENCES Not required DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGER SH2664/2 Page 1 of 2 COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT" UNIT 1 Control Panel Assembly COMPONENT Cabinet/S stem GROUP PARTS LIST NO.02"500A SNPS GPL NQ.03-500A UTILITY Carolina Power 8 Li ht Com an TASK DESCRIPTION NO.DR-02-02-500A-0

'LASSIFICATION TYPE A TASK DESCRIPTIONS The application of the electropneumatic control system used on Shearon Harris to stai t, stop, operate, protect, and monitor the diesel is essentially identical to Comanche Peak design.The logic design and controls used on Shearon Harris ta bypass all Group I and Group II trips during an emergency condition and to provide maintenance/opera-tional mode control are identical to Comanche Peak design.Shearon Harris differs from Comanche Peak in the pneumatic logic design to disable the Group II trips on diesel startup and trip on diesel malfunction.

The addition of a two-way, quick release pressure actuated valve provides rapid venting action of the pneumatic logic board and corresponding shutdown of the Shearon Harris diesel.Shearon Harris site experience listed in the EDG Component Tracking System shows discrepancies between site inspection and TDI drawings.These problems have satisfactorily been resolved and TDI drawings are being revised.Nuclear and non-nuclear industry experience listed does not show any signifi-cant or generic problems associated with the type of electropneumatic system used on Shearon Harris.There are no maintenance or modification recommendations required for the contt ol panel assembly cabinet/system.

A guality Revalidation of the control panel assembly cabinet/system is not deemed necessary.

Based on the above, a design review of the control panel assembly cabinet/system is not required for Shearon Harris.SH2123/1

.PRIMARY FUNCTION~~Not required COMPONENT DESIGN REVIEW CHECKLIST Page 2 of 2 DR-02-02-500A-0 ATTRIBUTE TO BE VERIFIED Not r equired SPECIFIED STANDARDS Not required REFERENCES Not required DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGER SH2123/2

COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-'UNIT 1 Page 1 of 2 Control Panel Assembly-COMPONENT Accumulator GROUP PARTS LIST NO.02"500F SNPS GPL NO.03-500F UTILITY Carolina Power 8 Li ht Com an TASK DESCRIPTION NO.DR-02-02-500F-0 CLASSIFICATION TYPE A TASK DESCRIPTIONS The application of the Bimba accumulators used on Shearon Harris is similar to those used on Comanche Peak.Shearon Harris differs from Comanche Peak in.that a 10.6 cu.in.accumulator, F-573-323, is used in conjunction with a 19.6 cu.in.accumulator, F-573-326, to increase the Group II lockout timing during engine startup.Comanche Peak design requires a single 19.6 cu.in.accumulator, F-573-326, for this purpose.I There is no Shearon Harris site, nuclear.or non-nuclear industry experience

~~~~~~~~~~~~~~listed in the EDG Component Tracking System for this component.

There are no maintenance or modification recommendations required for the accumulators.

A guality Revalidation of the accumulators is not deemed necessary.

Based on the above, a design review for the accumulators is not required for Shearon Harris.PRIMARY FUNCTION Not required ATTRIBUTE TO BE VERIFIED Not required SPECIFIED STANDARDS Not required I SH2120/1

REFERENCES Not required COMPONENT DESIGN REVIEW CHECKLIST Page 2 of 2 DR-02-02-500F-0 DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGER SH2120/2 Page 1 of 2 COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-'UNIT 1 COMPONENT Control Panel Valves UTILITY Carol ina Power&Li ht Com an GROUP PARTS LIST NO.02-500G TASK DESCRIPTION NO.DR" 02" 02-500G-0 SNPS GPL NO.03-500G CLASSIFICATION TYPE A TASK DESCRIPTIONS The control panel val ves used on Shearon Harri s are i denti cal in val ve application and manufacturer to.those on Comanche Peak, with the exception of 3-way valve F-573-090 and 2-way valve F-573-156.

Shearon Harris uses manually actuated ARO 3-way valves F-573-090 to direct the flow of control air providing fuel oil tank level indication, lube oil tank level indication and annunciation on a manual start.Shearon Harris also uses a pressure actuated California Controls 2-way, quick release valve, F-573-156, to disable the Group II trips during diesel startup and provide rapid venting action of the logic board to shut down the diesel on a malfunction.

The above valves~~~~~operate in the compressed air system at 60 psi and are adequate for their intended service.There is no Shearon Harris site experience listed in the EDG Component Tracking System for the control panel valves.The industry experience listed does not show any significant experience relating to the control panel valves.To minimize fouling of the control panel valves, it is recommended that the valves be inspected and cleaned during each refueling outage.This recommended maintenance interval should be reassessed depending on the degree of system fouling.A guality Revalidation of the control panel valves is not deemed necessary.

Based on the above, a design review for the control panel valves is not required for Shearon Harris.r PRIMARY FUNCTION Not required'ATTRIBUTE TO BE VERIFIED Not required SH2126/1

,'F~,

SPECIFIED STANDARDS Not required COMPONENT DESIGN REVIEW CHECKLIST Page 2 of 2 DR-02" 02" 500G" 0 REFERENCES Not required DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGER C.h4 SH2126/2 COMPONENT DESIGN REVIEM CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT" UNIT 1 Page 1 of 2 Control Panel Assembly COMPONENT Pressure Switches GROUP PARTS LIST NO.02-500H SNPS GPL NO.03-500H UTILITY Carolina Power 8 Li ht Com an TASK DESCRIPTION NO.DR-02-02-500H-0 CLASSIFICATION TYPE B TASK DESCRIPTIONS The pressure switches used on Shearon Harris are identical to those used on Comanche Peak in regard to manufacturer and application.

There is no Shearon Harris site or non-nuclear industry experience listed in the EDG Component Tracking System for this component.

The nuclear, industry experience listed does not show any generic or significant problems with the pressure switches.There are no maintenance or modification recommendations required for the~~~~pressure switches.A guality Revalidation of the pressure switches is not deemed necessary.

Based on the above, a design review for pressure switches is not required for Shearon Harris.PRIMARY FUNCTION Not required ATTRIBUTE TO BE VERIFIED Not required SPECIFIED STANDARDS Not required 5H2127/1

REFERENCES Not required COMPONENT DESIGN REVIEW CHECKLIST Page 2 of 2 DR-02-02-500H-0 DOCUMENTATION RE UIREO Not required GROUP CHAIRPERSON PROGRAM MANAGERSH2127/2 COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Page 1 of 2 Control Panel Assembly.COMPONENT Control Rela s GROUP PARTS LIST NO.02"500J SNPS GPL NO.03-500J UTILITY Carolina Power 8 Li ht Com an TASK DESCRIPTION NO.DR-02" 02-500J-0 CLASSIFICATION TYPE A TASK DESCRIPTIONS The application of the.control relays used on Shearon Harris to start/stop the diesel generator and to monitor its integrity is similar to Grand Gulf except for the use of Air Pax tachometer relay (TDI Part No.F-594"048).

This relay is powered by 24 Vdc and is used to energize the field flash solenoid valves at 200 rpm, to indicate"diesel running".status at 430 rpm, and in combination with a 95 percent rated voltage signal to provide a"ready to load" signal at 430 rpm.A review of the vendor's information for this relay shows that it meets design requirements.

There is no Shearon Harris site or non-nuclear industry experience identified in the EDG Component Tracking System.Nuclear industry experience listed showed that most of the experience items are not applicable to relay type, service condition, or are otherwise unrelated to TDI design, and therefore, are not applicable to this component.

There are no maintenance or modification recommendations required for the control panel assembly control relays.equality Revalidation for the control panel assembly control relays is not deemed necessary.

Based on the above, a design review for the control relays is not required for Shearon Harris.PRIMARY FUNCTION Not required ATTRIBUTE TO BE VERIFIED Not required/SH2128/1

SPECIFIED STANDARDS Not required COMPONENT DESIGN REVIEW CHECKLIST Page 2 of 2 DR-02-02-500J-0 REFERENCES Not required DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGERSH2128/2 Page 1 of 2COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Control Panel Assembly COMPONENT Solenoid Valves UTILITY Carolina Power 8 Li ht Com an GROUP PARTS LIST NO.02-500K TASK DESCRIPTION NO.DR-02" 02-500K-0.SNPS GPL NO.03"500K CLASSIFICATION TYPE A TASK DESCRIPTIONS The control panel assembly solenoid valves used at Shearon Harris are identical to those used at Shoreham with regard to manufacturer and application.

The Shearon Harris site control panel assembly solenoid valves are employed for control of maintenance mode selection, return to operational, shutdown system active, stop, shutdown deactivate, field flash, ready to load, D.C.power and running functions.

At Shearon Harris, the solenoid valves are located on a Humphrey, six-station, manifold assembly (Part No.74046-203) and a Humphrey, nine-station, manifold assembly (Part No.74046-204) for the above functions.

The Circle Seal Controls solenoid valves used as pilot valves for the California Controls Co."Start Air Admission Valves" (TDI Part No.KR-001-000, KR-004-001 and KR-004-002) in the starting air system at Shearon Harris are identical to Comanche Peak design.There are no maintenance or modification recommendations required for the control panel assembly solenoid valves.A guality Revalidation for the control panel assembly solenoid valves is not deemed necessary.

There is no Shearon Harris site experience or non-nuclear industry experience listed in the Emergency Diesel Generator Component Tracking System for this component.

The nuclear industry experiences have been reviewed with regard to Shearon Harris, and no generic or significant problems are apparent.Based on'the above information, a design review is not required for the control panel assembly solenoid valves at Shearon Harris.'H2129/1 PRIMARY FUNCTION Not required COMPONENT DESIGN REVIEM CHECKLIST Page 2 of 2 DR"02"02-500K-0 ATTRIBUTE TO BE VERIFIED Not required SPECIFIED STANDARDS Not required REFERENCES Not required DOCUMENTATION RE UIRED ,Not required GROUP CHAIRPERSON PROGRAM MANAGER SH2129/2

COMPONENT UALITY REVALIDATION CHECKLIST Page 1 of 1 02-02-500M Control Panel Assembly-COMPONENT Pi in Tubin Fittin s GPL NO.02"500M SNPS GPL NO.03-500M Carolina Power&Light Shearon Harris Nuclear.UTILITY Power Plant-Unit 1 REV.NO.1 TASK DESCRIPTIONS

~En inc 1A No further revi ew of component 02-500M i s required for the fol 1 owing reasons: a)Component was reviewed on two lead engines with satisfactory results.b)There is no significant industry..or site experience for this component.

GROUP CHAIRPERSON

+PROGRAM MANAGER C SH1813/1 COMPONENT UALITY REVALIDATION CHECKLIST Page 1 of 1 02-02-500N Control Panel Assembly Terminal Boards/COMPONENT Switches Wirin GPL NO.02"500N SNPS GPL NO.03-500N Carolina Power L Light Shearon Harris Nuclear UTILITY Power Plant-Unit 1 REV.NO.1 TASK DESCRIPTIONS No further review of component 02-500N is required for the following reasons: a)There is no site experience.

or signi f i cant industry experience reported for this component.

b)Component was reviewed on-the lead engines (Shoreham) with satisfactory results.GROUP CHAIRPERSON P PROGRAM, MANAGER SH1812/1

Page 1 of 2 COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Foundation Bolts-Anchor Bolts, Miscellaneous COMPONENT Hardware UTILITY Carolina Power&Li ht Com an GROUP PARTS LIST NO.02"550 TASK DESCRIPTION NO.DR" 02-02-550" 0 SNPS GPL NO.03-550 CLASSIFICATION TYPE'TASK DESCRIPTION The design review of this component is not required based on the following comparisons of Comanche Peak diesel engine DSRV-16-4 and Shearon Harris diesel engine DSRV-16-4:

A)All foundation bolts for engine, J.W.standpipe, barring device, auxiliary base, J.W.cooler and L.O.cooler are of the same TDI part numbers (Ref.1 and 2)except the generator foundation bolts (part no.00-550-01-CM) which are designed with embedded anchor plates rather than the embedded J bolts (part no.00-550-02-AD) installed at Comanche Peak.B)The amplified response spectrum curves for Shearon Harris (Ref.3)show more favorable seismic loadings as compared with those at the Comanche Peak Station.C)All bolt torque values of corresponding foundation bolts are recommended equivalently per References 1 and 2.Moreover, the industry experience and site experience reported no adverse experience for Shearon Harris.It is therefore concluded that the subject foundation bolts at Shearon Harris are adequate as designed for their intended use.The following maintenance recommendation is made for this component:

The generator foundation bolts should be retorqued to 480 ft-lb after each generator short circuit occurrence if they have not previously been torqued to 600 ft-lb.There are no modification recommendations for this component.

guality Revalidation for this component is not required.~~J SH2611/1

'a/I+

PRIMARY FUNCTION Not required COMPONENT DESIGN REVIEW CHECKLIST Page 2 of 2 OR-02-02-550

-0 ATTRIBUTE TO BE VERIFIED Not required SPECIFIED STANDARDS Not required REFERENCES 1.'DI Manual Volume II, for Model DSRV-16-4 Diesel Engine/Generator, Shearon Harris Nuclear Power Plant, Units 1, 2, 3, and 4, Parts List Nos.02-550 (for 74046)and 02-550-03-04, and Drawing No.R-4051.2.TDI Manual Volume II for Model DRSV-16-4 Diesel Engine/Generator, Comanche Peak Steam Electric Station-Unit 1, Parts List Nos.02-550 (for 76001), and 02-550-03-04, and Drawing No.R-3943.3.Ebasco Services, Inc., Project CAR-SH-E-11, Specification 216-73-TB for Diesel Engine Generator Unit and Control Panel for Nuclear Power Plants, Rev.7, dated September 14, 1981, Addendum A,"Seismic Considerations for Mechanical Equipment,"-Response Acceleration Spectra Curves (12 sheets)Revised December 26, 1978.DOCUMENTATION RE UIRED.Not required GROUP CHAIRPERSON PROGRAM MANAGER MCA SH2611/2 Cl COMPONENT DESIGN REVIEW CHECKLIST SHEARON HARRIS NUCLEAR POWER PLANT-UNIT 1 Page 1 of 2 COMPONENT Auxiliar Skid GROUP PARTS LIST NO.02-717A SNPS GPL NO.03-717A UTILITY Carolina Power 8 Li ht Com an TASK DESCRIPTION NO.DR-02-02-717A" 0 CLASSIFICATION TYPE TASK DESCRIPTIONS

~+Design review far this component is not.required based on the following:

A review of the lead engine DR/gR reports (Shoreham/Comanche Peak).~A review of the EDG Component Tracking System indicated no significant applicable industry and/or site experience.

~A'detailed dynamic analysis was performed to seismically qualify the skid (Ref.2).The Parts Manual for Shearon Harris lists the auxiliary sub-base as an ASME III component.

It is evidently intended that the skid should be an NF Support for the skid mounted ASME III components.

However, the seismic qualification report (Ref.2)says that the auxiliary base is non ASME III.A similar situation existed at Comanche Peak where Gibbs and Hill attempted to backfit an NF qualification for the skid.The skid was found acceptable, but it did not fully satisfy NF.The seismic models and drawings are different between Comanche Peak and Shearon Harris and thus the Gibbs and Hill analyses would not be directly applicable to Shearon Harris.The CTS for Shearon Harris does list one problem with ASME III weld deficiencies on auxiliary skid pipe supports, but does not list any deficiencies with ASME III auxiliary skid qualifications.

Given the experience at Comanche Peak, it is recommended that CP8L snvestigate the adequacy of the ASME III qual.ifications as they apply to the auxiliary skid.There are no maintenance recommendations from the lead engine beyond those recommended in the TDI Instruction Manual.-There are no modifications recommended for this component.

guality Revalidation is not required for this component.

, SH2557/1

,~'RIMARY FUNCTION Not required COMPONENT DESIGN REVIEW CHECKLIST Page 2 of 2 DR-02-02-717A-0 ATTRIBUTE TO BE VERIFIED Not required SPECIFIED STANDARDS Not required REFERENCES l.Ebasco Specification

¹216-73-Tb, Rev.3, 4-25-78,"Diesel Engine Generator Unit and Control Panel for Carolina Power 8 Light Company, Shearon Harris Nuclear Power Plant Units 1, 2, 3, and 4, Wake County, North Carolina.'inal Report Volume II,'nalytic Modeling of Engine Auxiliaries Seismic gualification of TDI Diesel Generator Sets, Serial Numbers 74046/53 for Carolina Power 8 Light Company, Shearon Harris Nuclear Power Plant Units 1, 2, 3, and 4,Section X, Auxiliary Sub-Base.DOCUMENTATION RE UIRED Not required GROUP CHAIRPERSON PROGRAM MANAGER SH2557/2

TDI OWNERS GROUP for SHEARON HARRIS NUCLEAR POWER PLANT MAINTENANCE REVIEW APPENDIX-II I INTRODUCTION The purpose of this Appendix is to provide Shearon Harris with a set of maintenance and surveillance recommendations for diesel generator compo-nents which have been developed by TDI and/or the Owners Group as a result of the overall Owners Group Program.This Appendix is intended to supplement the existing TDI Instruction Manual, Volume I and Volume III, which will maintain the qualification of the diesel generators for the life of the plant.II METHODOLOGY During the implementation of the Owners Group Program Plan, the Owners Group Technical Staff reviewed many sources of information regarding the maintenance, and surveillance for the diesel generator components identi-fied in this Appendix.These sources included TDI Instruction Manuals, Service Information Memos (SIMS), and TDI correspondence on specific components.

This review along with Technical Staff input regarding the adequacy of the recommendations found in the sources mentioned above, and additional maintenance recommendations identified during the DR/gR review, forms the basis for the content of this matrix.III RESULTS AND CONCLUSIONS Proper maintenance is important in ensuring long, reliable and satisfacto-ry service of the emergency diesel generators.

Maintenance work, in order to be effective, must be carried out thoroughly and regularly.

It is for these reasons that a detailed schedule of maintenance service has been laid out by the Owners Group for the TDI Diesel Generators at Shearon Harris Nuclear Power Plant.The schedule details specific components requiring maintenance on a regular basis.This schedule separates the maintenance activities into a daily, monthly, outage, alternate outage (every other), 5-year and 10-year frequencies.

It should be noted here that the duration time between outages at Shearon Harris is assumed to be 18 months.SH2401/1

Page 2 of 3 Those less significant diesel generator system components with which standard engineering pr actice and maintenance will ensure continued operation, are not specifically addressed in the matrix.Standard mainte-nance practices are briefly discussed below.The engine and generator should be kept clean and dry at all times.Oil and water leakage should be wiped off the unit as quickly as possible in order to assist in locating the source of leakage, prevent potential equipment damage and maintain a safe working environment.

Leaking pipes, gaskets and packing glands should be attended to promptly so as not to impair the reliability and/or operation of the system.Flanged gasketed connections may be retightened to stop leaks and any abnormal engine noises or vibrations.

Actions required to correct any abnormal conditions should be carried out in a timely manner.Loose bolts and electrical terminals should be attended to in a safe, practical manner.Specific items to be maintained on a DAILY basis consist of the following:

l.Observe and record lubricating oil and jacket water temperatures (keep warm pump running).2.Drain all low point water collectors, and air receiver tank float traps in the air start system.3.Check engine and auxiliary equipment and piping connections for oil, water, and fuel oil leaks.4.Check level of lubricating oil in the governor, sump tank and ped-estal bearing.Add oil as needed.5.Check fuel oil pump rack for freedom of movement through full limit of travel.Do not disconnect from governor.6.Check turbocharger bearing lubricating oil system sight glass for oil f 1 ow.7.Drain water from crankcase vent piping drip legs.8.Verify all controls in proper position for standby mode.9.Check all governor knob settings.Load Maximum Droop Zero Speed To provide mechanical governor control at 460 rpm.SH2401/2 Revision 1 Page 3 of 3 10.Visually inspect lube oil heat exchanger and jacket water heat exchanger for signs of leakage from the lantern ring leakoff ports, indicating leaking packing r ings.The following Preventive Maintenance Recommendation Matrix was designed to assist the Maintenance Department in determining the scope of work re-quired to maintain the intended design function of the diesel generators at Shearon Harris on a planned schedule basis.It should be followed closely and referred to often.SH2401/3 SHEARON HARRIS HAINTENANCE MATRIX Component Component Number Identification PH Recommendation l~lo nthl Al t.~Outa e~Outa e 5 Year 10 Year Comments F-068 Intercoolers HP-022/3 Turbocharger l.Evaluate heat exchanger X performance by checking engine operating parameters.

2.Clean/inspect shell and tube sides every outage or as necessary.

3.Visually inspect for external leaks.4.The low-point drain con-nection downstream of the intercooler should be verified open, and cleaned daily.1.Measure vibration and check with base line data.2.Clean impeller and diffuser.Ref: Lead engine OR/0R Report 8F-068 (Items 2, 3, 4)Ref: 7/26/84 IOC from J.Cadogan to H.HcGerigle, Ref: 08/14/84 letter to C.Ray from H.Lowrey To be performed daily.To be accomplished during 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test run.SH2401/4 3.Measure rotor end play (axial clearance) to identify trends of in-creasing clearance, i.e;thrust bearing degradation.

Revision 1 Review thrust bearing axial clearances after inspection to determine if a trend exists.Any trend toward increasing axial clearance could signify thrust bearing degradation.

Ref: Lead engine OR/0R Report 8HP-022/3 Component Number Component Identification PH Recommendation SHEARON HARRIS HAINTENANCE MATRIX Al t.a~hathi~Outa e~outa e 5 Year 10 Year Cameuta 00-420 Lube Oil Pressure Regulating Val ve 4.Perform visual and blue check inspections of the thrust bearing.5.Disassemble inspect and refurbish.

6.Perform a spectro-chemical engine oil analysis to assist the bearing monitoring program.To further expand/clarify chemical analysis, ferrographic analysis may be utilized.Particular attention shall be paid to copper level, and particulate size, which could signify thrust bearing degradation.

l.Oi sassemble and clean.NOTE: Thrust bearing inspection should also be performed after 40 non-prelubed (automatic) fast starts.Ref: Lead engine OR/0R Report SHP-022/3.To be performed during the last monthly test run prior to oil change.NOTE: Sample to be drawn up stream of lube oil filter.Ref: Lead engine OR/IlR Report HP-022/3 If valve st>cks repeated ly, more frequent cleaning may be necessary.

If valve plugging becomes a problem, the dimensions of the valves'nternal parts should be checked to ensure proper clearance.

5H2401/5 SHEARON MARRIS MAINTENANCE MATRIX Component Number Component Identification PM Recosmendation

~Month1 Al t.I~Outa e~Outa e 5 Year 10 Year Comments 2.During initial startup after a major reassembly of Lube Oil piping, the L.O.regulating valve should be disassembled and cleaned until abnormal L.O.pressure excursions subside.Ref: Lead engine DR/gR Report 800-420 (Items 1 8 2)02-305A Base Assembly 02-305C Main Bearing Caps-Studs and Nuts 1.Perform a visual inspection of the base.The inspection should include the areas adjacent to the nut pockets of each bearing saddle and be conducted after a thorough wipe down of the surfaces, using good lighting.1.Upon removal of bearing caps, clean mating surfaces with a solvent prior to reassembly of the caps to the base.NOTE: Any cracks detected must be investigated furthe>before the engine is allowed to return to to service.The mating surfaces of'the base and cap shall be throughly cleaned with solvent before any reassembly.

Ref: Lead engine DR/IiR Report 802-305B Ref: Lead engine DR/gR Report N02-305C 5H2401/6 Component Number Component Identification PH Recommendation SHEARON HARRIS HAINTENANCE MATRIX Al t.~Honth1~Outa e O~uta e 5 Year 10 Year Comaea<j 02-307B Lube Oil Tubing and Fittings-Internal 1.Check tubing for dents or crimps.Items 1, 2;Ref: TOI Instruction Manual, Vol.I, Haintenance Schedule 02-310A Crankshaft 02-310B Hain Bearings Shells 2.Perform gear-train spray check.1.Heasure crankshaft web deflection.

2.Measure diameter of crank journals.1.Inspect and measure main bearing shell thickness.

Inspection shall evaluate bearing wear and evidence of harmful crankshaft misalignment.

If results Complete TOI Inspection and Maintenance Record Form No.310-1-1, TOI Instruction Hanual, Volume I, Section 6.Ref: TOI Instruction Manual, Vol.I, Hainten-ance Schedule Complete TOI Inspection and Haintenance Record Form No.310-3-1, TOI Instruction Manual, Volume I, Section 6.The first inspection should be performed at the first fuel outage and at alternate outages thereafter.

Complete TOI Inspection SH2401/7 Component Component Number Identification PH Recommendation SHEARON HARRIS MAINTENANCE MATRIX Al t.~uaathl~etta e~Outa e 5 Year 10 Year Comments 02-310C Thrust Bearing Ring SH2401/8 show evidence of mis-alignment, TOI recom-mendations for crankshaft realignment should be implemented.

1.Measure thrust bearing ring clearance via"bump check" method to be performed in conjunction with crankshaft web deflection measurements.

The following information should be recorded: Bate of inspection Hours of engine operation 4 Hours of engine operation since last bearing re-placement (Last bearing replaced: forward backT 4 Bearing clearance Revision 1 and Maintenance Record Form No.310-2-1, TOI Instruction Manual, Volume I, Section 6-one sheet for each main bearing.Use Volume I, Appendix III for clearance values.Ref: TOI Instruction Hanual, Vol.1, Maintenance Schedule, Ref: Lead engine OR/QR Report 802-310B Complete applicable sections of TOI Inspection and Main-tenance Record Form No.310-1-1 TOI Instruc-tion Manual, Volume I, Section 6.NOTE: If the clearance is greater than the maximum allowed in the TOI Instruction Hanual, then at least one bearing must be replaced.Bearings should also be replaced if they are cracked or gouged.Ref: Lead engine OR/QR Report f02-310C, Ref: 8/13/84 memo from G.HcCarthy to O.Pasquale Component Component Number Identification PM Recommendation SHEARON HARRIS MAINTENANCE MATRIX Al t.u~eutht~Outa e~Outa e 5 Year 10 Year Comments 02-311A Crankcase Assembly 02-315A Cyl inder Block 02-315C Cylinder Liners02-317'ater Discharge Manifold-Jacket Water Discharge Piping, Couplings and Seals 5H2401/9 2.Visually inspect thrust bearing ring for signs of cracks, gouges, wear or degradation.

1.Perform a visual inspection of the vertical portion of the crankcase arch wall to the nut pocket area for indications of cracking.1.Perform an inspection of the cylinder block per OR/IiR Report N02-315A.1.Perform a visual inspection of liners for potential progressive wear per Shearon Harris OR/gR Report N02-315C Task Description.

1.Visually inspect for leaks.X Note: In the event of a leak developing in the existing Dresser Style 65 To be performed simult-aneously with main bearing shell inspec-tion.Ref: Lead engine DR/gR Report N02-310C The first inspection to be performed'after 185 hours0.00214 days <br />0.0514 hours <br />3.058862e-4 weeks <br />7.03925e-5 months <br /> of at or near full load operation, may be used to justify the discontinua-tion of further inspect-tions.Ref: Lead engine DR/gR Report N02-311A Ref: DR/gR Report N02-315A Borescopic inspection is acceptable if heads are not removed.Complete TOI Inspection and Maintenance Record form No.315-1-1, TOI Instruction Manual, Volume I, Section 6.Ref: Lead engine OR/gR Report N02-341B This recommendation is made on the basis that the maximum suggested operating temperature of Revision 1 8

Component Number Component Identification PH Recommendation SNEARON HARRIS HAINTENANCE HATRIX Alt.H~onthl~OUta e~outa e 5 Year 10 Year Comments 02-340A/8 Connecting Rods, Bushings and Bearing Shells couplings, these couplings should be replaced with Dresser Style 90 couplings equipped with Viton gaskets.1.Inspect and measure connecting rod bearing shells to verify lube oil maintenance which affects wear rate.The visual and dimensional inspection of the bearing shells should be conducted at the fuel outage which precedes 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> of operation by at least the sum of hours of operation in a LOOP/LOCA event plus the expected hours of operation between outages, 2.Inspect and measure the connecting rods.150'F for the Style 65 coupling may be exceeded.The maximum suggested operating temperature of the Style 90 is 212~F.Ref: Letter dated 12/13/84 from C.L.Ray to J.George.Ref: DR/QR Report I/02-317ALB To be performed in conjunction with piston pin inspection.

Com-plete TDI Inspection and Haintenance Record Form No.340-1-1, TOI Instruction Hanual, Volume I, Section 6, Appendix III for clearance values.Ref: Lead engine OR/QR Report 802-340B Complete TDI Inspection Haintenance Record Form No.340-2-1, 2, TDI Instruction Hanual, Volume I, Section 6.5H2401/10 Revision 1 Component Component Number Identification PH Recommendation SHEARON HARRIS MAINTENANCE HATRIX Al t.M~onth)O~uta e O~uta e 5 Year 10 Year Comments 02-341A Pistons 3.Perform an x-ray examin-ation on all replacement bearing shells to acceptance criteria developed by Owners Group Technical Staff.4.Measure the clearance between the link pin and link rod in accordance with TDI SIH fI349.This clearance should be zero, i.en 5 nO meaSurable clearance when the speci-fied bolt torque of 1050 ft-lbs is applied.This should be performed with the engine assembled after a major disassembly.

5.At major engine overhauls visually inspect the rack teeth surfaces for signs o f f ret ting.1.Inspect and measure skirt and piston pin.This is to be performed prior to snstallatson of any replacement bearing shells.Ref: Lead engine OR/iiR Report if02-3408 This recommendation is required one time only.Ref: Lead engine OR/gR Report 802-340A If frett>ng has occured a further eng>neer>ng evaluation will be necessary.

Ref: OR/gR Report 802-340A Complete TOI Inspection and Haintenance Report Form No.341-1-1, TOI Manual, Volume I, Section 6.Use Volume 1, Section 8, 5H2401/11 Revision 1 SHEARON HARRIS HAINTENANCE HATRIX Component Number Component Identification PH Recommendation Alt.~ttuatht O~uta e~Outa e 5 Year 10 Year Comments 02-3418 Piston Rings l.Inspect and measure replacement piston rings.Appendix III for clear-ance values.To be performed>n conjunc-tion with piston pin inspection.

Complete TOI Inspection and Haintenance Record Form No.341-2-1, TOI Instruction Hanual, Volume I, Section 6.Use Volume I, Section 8, Appendix III for clearance values.To be perform-ed in conjunction with piston pin inspection.

SH2401/12 Revision 1-Carryover from previous page Component.Component Number ldentlffaatlon PH Recommendation SHEARON HARRIS MAINTENANCE MATRIX Al t.N~onthl~Outa e Outafle 5 Year 10 Year Comments 2.Visually inspect liners for wear.NOTE: Ring replacement and cylinder liner honing should be performed in accordance with TDI maintenance procedures.

3.135 fuel oil spray tips may be used if inspection results indicate a need for additional action to improve lubrication and reduce coke buildup.4.When replacing engine oil use H.O.oil that exceeds series 3 standards.

The base stock should be more resistant to thermal degradation and coke formation.

The additive package should provide high detergent disper sant properties with high Borescopic inspection is acceptible if heads are not removed.Com-plete TDI Inspection and Maintenance Record Form No.315-1-1, TOI instruction Manual, Volume I, Section 6.Use Volume I, Section 8, Appendix III for clearance values.Ref: Lead engine DR/gR Report N02-3418 (Item 2, 3, 4)Ref: 07/31/84 memo from L.Swanger to 0.Pasquale NOTE: Oo not mix L.O.brands or types.When changing L.O.replace the entire L.O.charge.Ref: 08/14/84 letter to C.Ray from H.Lowrey SH2401/13 Revision 1-Carryover from previous page Component Component Number Ident'Ifiaatinn PM Recommendation SHEARON HARRIS MAINTENANCE MATRIX Al t.~Nantbl~outa e~outa e 5 Year 10 Year cnmenta 02-341C Piston Pin Assembly SH2401/14 alkalinity and a high level of antiwear additive such as tine dithiophosphate.

Total Base Number (TBN)should be 12 to 15 for use with¹2 fuel oil and a sulfated ash content of 1.5X to 2.OX i s preferred.

An engine oil with such properties, Mobilguard 412 or equivalent product may be used to ensure improved lubrication.

1.Visually inspect for chrome plate damage.Replace pins which show chipped or blistered chrome.NOTE: All new or re-placement pins will be L.P.or M.P.inspected before installation in Owners Group engines.Also to be performed whenever pistons are-removed and disassembled to an extent that such inspection is possible.Ref: Lead engine OR/QR Report¹02-341C (Items 152), For details on acceptance criteria, Ref: 08/22/84 memo from W.Littmann to O.Pasquale HOTE: This inspection is to be performed whenever the engine is sufficantly dismantled to allow this inspection.

Ref: Lead engine OR/QR Report¹02-341C Revision 1-Carryover from previous page

SHEARON HARRIS MAINTENANCE HATRIX Component Component Number Identification PH Recommendation Al t.~unntnt~Outa e O~uta e 5 Year 10 Year Cnaaente 2.Inspect end plugs and reroll or replace any that are loose.02-345A Intake and Exhaust Tappet Assembly 02-345B Fuel Tappet Assembly SH2401/15 l.Inspect intake and exhaust tappet assembly condition.

2.Verify that cam rollers are free to rotate, and that that there is no measurable clearance between the cam rollers and the roller pins.1.Inspect fuel tappet assembly condition.

2.Verify that cam rollers are free to rotate, and that there is no measurable clearance between the cam rollers and the roller pins.Revision 1 Complete TDI Inspection and Maintenance Report Form No.345-1-1, TDI Instruction Manual, Volume I, Section 6.Ref: Lead engine OR/QR Report 802-345A Complete TOI Inspection and Maintenance Record Form No.345-1-1 TDI Instruction Manual, Vol.I, Section 6.Ref: Lead engine OR/QR Report 802-345A Complete TDI Inspection and Haintenance Report Form No.345-1-1, TDI Instruction Manual, Volume I, Section 6.Ref: Lead engine OR/QR Report 802-345B Complete TOI Inspection and Maintenance Record Form No.345-1-1 TOI Instruction Manual, Vol.I, Section 6.Ref: Lead engine OR/QR Report 002-345B SNEARON HARRIS HAINTENANCE MATRIX Component Number Component Identification PH Recommendation Month 1~Outa e Alt.~Outa e 5 Year 10 Year Comments 02-350A Cam Shaft Assembly 1.Perform a visual inspection of all cam lobe surfaces for signs of cracking, pitting or spalling.Any signs of cracking, p>tting or spalling shall be followed by a detailed analysis to evaluate the expected life based on the size and extent of surface distress and any corrective measures shall be implemented as indicated by this analysis.Signs of spalling shall result in immediate replacement of the cam.Ref: Lead engine OR/gR Report N02-350A 02-350B Cam Shaft Bearings 02-350C Cam Gear l.Inspect and measure cam shaft bearing shells.l.Visually inspect cam gear for chipped or broken teeth, pitting, excessive wear, or other abnormal conditions.

Complete TOI Inspection and Haintenance Record Form No.350-1-1, TOI Instruc-tion Manual, Volume I, Sec-tion 6.Use Volume I, Section 8, Appendix III.for clearance values.Ref: Memo from B.Bickford to E.Montgomery dated 6/23/84, Ref: Lead engine OR/gR Report 802-350C SH2401/16 Revision 1-Carryover from previous page SHEARON HARRIS MAINTENANCE MATRIX Component Number Component Identification PM Recommendation Alt.~Mehtht~Outa e~Outa e 5 Year 10 Year Comments 02-355A Crank to Pump Gear 2.Measure gear back lash.NOTE-if cam gear hub is removed, it is ESSENTIAL that the nut be relocked at the position corres-ponding to the pre-scribed torque range of 80 (-0+10)ft-lbs.Insertion of the cotter pin must be accomplished at a torque>80 ft-lbs force and<90 ft-lbs force.If this is not possible another bolt, nut or washer should be used.The above is applicable to 4-bolt arrangments only.The torque range for 6-bolt arrangements=

is 70 x 20 ft-lbs with the same restric-tions as described above for insertion of the cotter pins.l.Visually inspect crankshaft to lube oil pump gear for chipped or broken teeth, excessive wear, or progressive pitting or other abnormal conditions.

Complete applicable sections of TOI Inspec-tion and Maintenance Record, Form No.355-1-1, TOI Instruction Manual, Volume I, Section 8, Appendix III-1 for clearnance values.Ref: Lead engine OR/gR Report 802-350C Any abnormal situations or indications of progressive pitting should be reported for an engineering evaluation.

Ref: Lead engine OR/gR Report 802-355A SH2401/17 Revision 1-Carryover from previous page SNEARON HARRIS MAINTENANCE HATRIX Component Component Number Identification 02-355B Idler Gear Assembly PH'Recommendation 2.Heasure gear backlash.1.Visually inspect idler gears for chipped or broken teeth, excessive wear pitting, or other abnormal conditions.

2.Heasure gear backlash NOTE: If idler gear hub is removed, it is recommended that the nut be relocked at the posi-tion corresponding to the torque of 70 a20 ft-lbs.Insertion of the cotter pin must be accomplished at a torque>50 ft-lb and if this is not possible, another bolt, nut, or washer should be used.Al t.~haathl Outargue~Outa e 0 Year 10 Year Caaaeata Complete applicable sections of TDI Inspection and Hain-tenance Record Form No.355-1-1 TDI Hanual, Volume I, Section 6.Use Volume 1, Section 8, Appendix III-1 from clearance values.Ref: TDI Instruction Hanual, Vol.I, Hain-tenance Schedule Any abnormal indications should be reported for an engineering evaluation.

Ref: Lead engine OR/QR Report 802-3558 Complete applicable sections of TOI Inspec-tion and Haintenance Record Form No.355-1-1, TOI Manual, Volume I, Section 6.Use Volume I, Section 8, Appendix I II-l for values.Ref: TOI Instruction Manual, Vol.I, Main-tenance Schedule, Ref: Lead engine DR/QR Report 802-355B SH2401/18 Revision 1-Carryover from pr vious page

Component Component Number Identification PM Recommendation SHEARON HARRIS MAINTENANCE MATRIX Al t.M~teethl~Outa e O~ta e 5 Year 10 Year Comments02-359 Air Start Valves 1.Remove, clean and inspect air start valves.(Replace copper valve-to-head gasket)2.Inspect the piston, cap, guide and housing sliding surfaces to evaluate wear or corrosion.

Ensure valve installation includes retorque requirements.

Ref: DR/QR Report 802-359 (Items 1, 2, 3)3.Ensure that the desiccant dryer between the air compressor after cooler and the air receivers is working properly by blowing down the air receivers daily and monitoring the moisture content.To be performed daily.Ref: DR/QR Report 802-359 02-360A Cylinder Head 5H2401/19 1.Visually inspect cylinder heads (all cylinders).

2.Record cold compression pressures and maximum firing pressures.

Complete TOI Inspection and Maintenance Record Form No.360-1-1, TOI Instruction Manual, Volume I, Section 6.One sheet for each head.If so indicated remove cylinder heads, grind valves and reseat.Ref: TOI Instruction Manual, Volume I, Sec-tion 6 Revision 1-Carryover from previous page SHEARON HARRIS MAINTENANCE MATRIX Component Number Component Identification PM Recommendation 3.Blow-over the engine per TOI maintenance require-ments, Volume I or at appropriate intervals after shutdown of the engine to ensure against harmful effects of water leaks.M~hhthl Al t.~Outa e~Outa e 5 Year 10 Year Comments In the event water is detected, the cylinder head should be replaced or returned to the vendor for repair.Ref: Lead engine OR/gR Report 802-360A 4.Visually inspect the fuel in)ection port on each cylinder head"during" the normal monthly engine run for water leaks.If water leakage is detected, the head(s)should be replaced.Ref: Lead engine OR/IlR Report 802-360A 02-360B Cylinder Head-Intake and Exhaust Valves l.Visually inspect intake and exhaust valve, discs, stems and seats for wire drawing, pitting, distortion, concentricity, or any abnormal condition.

2.Visually inspect subcovers for evidence of valve guide blowby (Soot).This is a one time only inspection to be per-formed after 500-600 hrs.of engine operation after rebuild of the cylinder head.Ref: Lead engine OR/gR Report 802-360B 5H2401/20 Revision 1-Carryover from previous page SNEARON HARRIS HAINTENANCE MATRIX Component Number Component Identification PH Recommendation H~onth1 Al t.O~uta e O~uta e 5 Year 10 Year Comaents 02-362A Cylinder Head Covers-Subcover Assembly 3.Measure intake and exhaust valves head thickness.

4.Measure intake and exhaust valves-valve-to-guide clearances.

1.Perform a liquid pene-trant examination of the rocker arm pedestals top and vertical machined surfaces (connector pushrod side only).Complete applicable sections of TOI Inspection and Main-tenance Records Form 360-2-1, TDI Instruction Manual,-Volume I, Section 6.One sheet for each cylinder.Use Section 8, Appendix III for clearance values.(Items 3,4)Complete applicable sections of TOI Inspection and Main-tenance Record Form 360-2-1, TOI Instruction Manual, Volume I, Section 5.One sheet for each cylinder.Use Section 8, Appendix III for clearance values.This inspection is to be performed in conjunc-tion with the rocker arm bushing inspections when the rocker arm shafts are removed from the subcovers (Ref: Lead engine OR/gR Report 802-390E)or when the rocker arm shaft assembly is SM2401/21 Revision 1-Carryover from previous page

Component Number Component Identification PH Recommendation SHEARON HARRIS HAINTENANCE HATRIX Al t.~ueutul O~uta e~Outa a 5 Year 10 Year Comments 02-365A Fuel Injection Pumps l.Visually check pressure bleed screws for erosion.2.Tear down one pump for inspection.

3.Complete fuel injection pump inspection in accordance with TOI Instruction and Main-tenance Hanual, Volume I.removed.Subcovers with pedestal cracks that extend through the counter bore web down to the threads should be replaced.Ref: Lead engine DR/gR Report 802-362A To be performed on all sixteen pumps.Use representative pump to determine need to overhaul other pumps.Ref: TOI Instruction Hanual, Volume I, Maintenance Schedule Based on inspection re-sults and operating parameters.

NOTE-Oisassembly of fuel injection pumps should be performed by a Bendix Corp.representative.

Complete TOI Instruction and Maintenance Record Form No.365-1-1, Section 6 (Items 1, 2).Ref: TOI Instruction Hanual, Volume I, Haintenance Schedule 5H2401/22 Revision 1-Carryover from previous page Component Component Number Identification PM Recommendation SNEARON HARRIS HAINTENANCE MATRIX Al t.~ueatul O~uta e~Outa e 5 Year 10 Year Comments 02-365B Fuel Infection Nozzles 1..Remove, inspect and clean ti ps.2.Check nozzle pop pressure.3.Check spray pattern.for Item 3, Ref: Lead engine OR/QR Report 802-365A (Items 243)Ensure that a new copper gasket is used upon reinstallation of nozzle into head.Complete TOI Inspection and Haintenance Record Form 365-2-1 Instruction Manual, Volume I, Section 6.Ref: TOI Instruction Hanual, Vol.I Section 5 Maintenance Schedule, Ref: Lead engine OR/QR Report N02-365B (Items 1-4)02-365C Fuel In)ection Tubing SH2401/23 4.Check assembly for leakage.1.Check tubing for leaks at compression fittings.All fuel oil leak in-spections to be perform-ed while the engine is running or whenever the compression fittings have been disturbed.

Ref: Lead engine OR/QR Report 802-365C Revision 1-Carryover from nrevious page SHEARON HARRIS MAINTENANCE MATRIX Component Component Number Identification PM RecoRmsendation Al t.R~outhl~Outa e~Outa e 5 Year 10 Year Comments 2.Visually inspect tubing X lengths for F.O.leaks or cracks.Fitting inspection for leaks to be performed at first engine opera-tion following the installation of tubing.Subsequent inspections to be performed period-ically as indicated.

Fuel oil leakage from shrouded fuel oil lines can be detected at the leakoff ports in the base nuts, which are provided for this purpose.Ref: IOC dated 8/14/84 from W.Smith to O.Pasquale.02-3650 5H2401/24 Fuel Oil Injection Lines: Supports l.Visually inspect support elastomer inserts for deterioration or degredation.

Revision 1-Any inserts found to be unsatisfactory shall be replaced with new inserts prior to reassembly of F.O.lines.This inspection can be per-formed prior to reassembly of the F.O.lines in conjunction with the cylinder liner inspection.

Ref: Lead engine OR/gR Report 002 3100~t-louder Liners, Ref: San Onofre OR/gR Report 802-3650 Task Oescription.

Carryover from previous page SHEARON HARRIS MAINTENANCE MATRIX Component Number 02-371A 02-3718 02-375 Component Identification Fuel Pump Control Shaft Fuel Pump Linkage Assembly and Bearings Intake Hani fold PH Recoamendation 1.Check lube oil cups and fill as necessary.

1.Grease swivel link on F.O.pump assemblies, all cylinders.

1.Care should be exercised in assembly of cylinder heads onto the engine, to avoid cracking of the intake manifold elbows.~Hant hl Alt.~Outa e~Outa e 5 Year 10 Year Comments Ref: 5/17/84 IOC from T.Fritsch to Paul Hartin If required, other castings may be tried to achieve an acceptable fit, or bolt hole diameters may be increased to 1/8" oversize.Component should under no circumstances be 5acked to fit.Ref: Lead engine OR/gR Report 802-375 02"380A Exhaust Hanifold l.Visually and HT examine a sampling of circum-ferential pipe welds and corresponding heat affected zones.This examination is to be performed in accordance with Impell memo from G.Shears to J.Kammeyer dated 08/13/84.To be performed during the first refueling outage and alternate outages thereafter.

However, diesel operation should not exceed 200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> be-tween inspections.

Ref: Lead engine OR/iiR Report 802-380A 02-386A Crankcase Relief Valve 1.Clean flame arrestors.

Ref: 3/26/84 IOC from H.Wehmeyer to J.Kammeyer SH2401/25 Revision 1-Carryover from previous page SHEARON HARRIS MAINTENANCE NATRIX Component Number Component Identification PH Recommendation 2.Inspect seat and disc.Al t.~uonthl~Outa e~nota e 5 Year 10 Year Coaaaenta 02-390E Rocker Arm Bushings 02"390F Rocker Arm Capscrews, Drive Studs (Pop Rivets)l.Visually inspect and measure intake rocker arm bushings.2.Visually inspect and measure exhaust rocker arm bushings.3.Visually inspect and measure intermediate rocker arm bushings.l.Verify capscrew torque values.The visual and dimensional inspection of the rocker arm bushings should be conducted at the fuel outage which precedes 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> of operation by at least the sum of expected hours of operation in a LOOP/LOCA event plus the expected hours of operation between outages.Ref: Lead engine OR/gR Report 802-390E (Items 1, 2, 3)Not to exceed 1300 maximum hours of engine operation between inspections as described above.Not to exceed 730 maximum hour s of engine operation between inspection as described above.Use TOI Instruction Hanual, Volume I, Section 8, Appendix IV for proper torque values.SH2401/26 Revision 1-Carryover from previous page Component Component Number Identification PM Recommendation SHEARON HARRIS MAINTENANCE MATRIX Al t.~taeetht~Outa e o~uta e 5 Year 10 Year Comments 02-410A Overspeed Trip Governor 2.Verify that rocker arm drive studs are intact and tight.1.Check trip set point-adjust as required.Ref: Lead engine DR/QR Report 802-390G (Items 1, 2)Mod>fy the surve>1 lance testing procedure to include verification that the overspeed trip is correctly set to an overspeed trip setting of 518 rpm xl X every outage.Ensure that the electric governor and the mechanical backup governo~setting are properly returned to their normal settings following the overspeed test.The test is to be performed with no load on the engine by increasing the normal governor speed setting(s) until a trip occurs.After several inspection periods, the history of the required adjustments should be reviewed to evaluate and possibly modify the testing interval.Ref: Lead engine OR/QR Report 802-410A SH2401/27 Revision 1-Carryover from previous page Component Component Number Identification PH Recommendation SNEARON HARRIS HAINTENANCE HATRIX Alt.~Honthl n~uta e~outa e 5 Year 10 Year comente 02-4108 Overspeed Trip Governor and Accessory Drive Note: After setting the over-speed governor, the ad-justment screw settings should be marked with Torque Seal to reveal any unintended changes in the set positions.

1.Remove plugs from housing and check for magnetic particles.

2.Check shafts for excessive radial and axial movement.Ref: IOC dated 03/17/84 from H.Weymeyer to N.Cooperrider.(Items 1, 2, 3)3.Visually inspect accessory drive gear for excessive wear.02-410C Overspeed Trip Drive Couplings 1.Remove the present L-110 Lovejoy couplings and replace them with new units in accordance with SIH 363 and OR/0R Report recommendations.

To be completed at the first refueling outage.2.Verify that coupling is tight on shaft.Ref: 6/24/84 Nemo from O.Limbert to E.Hontgomery SN2401/28 Revision 1 SHEARON HARRIS MAINTENANCE MATRIX Component Component Number Identification PM Recommendation H~onthl~Outa e Alt.Outacue 5 Year 10 Year Comments 02-410D Overspeed Trip Vent Valve 02-411A Governor Drive-Governor and Tachometer Drive Gear and Shaft 3.Replace the Lovejoy coupling spiders or test coupling elastomer for hardness.1.Disassemble and replace"0" rings.l.Visually inspect drive gear and shaft for signs of wear.Replace elastomer if hardness is greater than 90 Shore A.Ref: Lead engine OR/ilR Report 802-410C (Items 1,2,3)Ref: Lead engine DR/IlR Report 802-4100 Ref: Task Description for Shearon Harris com-ponent fif02-411A, Ref: TOI Instruction Manual, Vol.I, Section 5 Maintenance Schedule 02-411B Governor Drive-Couplings, 1.Check that coupling is Pins and Keys tight on shaft.2.Replace the present neoprene insert in the Koppers coupling.If the coupling is found to be loose, it should be removed, all mating surfaces cleaned, and the unit reassembled using Loctite 609 on the mating surfaces.Ref: Lead engine DR/iiR Report 802-411B (Items 1, 2)To be performed prior to placing the engine in the emergency standby mode.SH2401/29 Revision 1 Component Number Component Identi f ication PH Recommendation SHEARON HARRIS HAINTEHANCE HATRIX Al t.a~hathi~Outa e~Outa e 5 Year 10 Year Cnaeenta 02-413A Governor Linkage 3.Replace the elastomeric insert each refueling outage.l.Install positive locking hardware to the lever arm clamp bolt heads and shaft roll pins.NOTE: To be performed as necessary after tightening gov-ernor linkage hardware to design torque specifi-cations.2.Inspect for loose parts X on the linkage assembly.3.Lubricate cross shaft bearings cups.Ref: Lead engine OR/iiR Report 802-413A (Items 384)4.Grease the rod end fittings, especially those at the ends of the cross shaft.02-413B Fuel Pump Linkage: Automatic Shutdown Cylinder 1.Check cylinder for extension and return.2.Check tailrod vent for air leakage.To be accomplished during control system check.To be accomplished during control system check.Items 1, 2;Ref: IOC dated 3/26/84 from H.Wehmeyer to R.Kaklec SH2401/30 Revision 1 Component Component Number Identification PH Recommendation SNEARON HARRIS HAINTENANCE MATRIX Alt.M~euthl~Outa e Outeeue 5 Year 10 Year Comments 02-415A Woodward Governor 1.Drain, flush, refill and vent actuator oil system with new oil from a clean container ensuring the appropriate cleanliness procedures are followed.2.Disassemble, clean and refurbish the actuator.3.Replace flex element for governor drive coupling.4.Verify all governor control knob settings are in appropriate positions:

LOAD-Maximum DROOP-Zero Speed" To provide mechan-ical governor con-trol at 460 rpm.NOTE: Venting the hydraulic actuator shall be performed per the Woodward manual if more than a half quart of oil is added.Ref: Lead engine DR/gR Report 02-415A Items 1, 2, 3;Ref: 03/27/84 IOC from H.Wehmeyer to N.Cooperrider Ref: TDI Instruction Hanual, Volume I, Section 5 Maintenance Schedule Ref: Lead engine DR/gR Report 802-4118 Governor Drive Couplings All knob settings should be secured with a commercially available product such as Torque-Seal.

5H2401/31 Revision 1-Carryover from previous page Component Nutter Component Identification PM Recommendation SHEARON HARRIS MAINTENANCE MATRIX Al t.h~uatht haute e hutatue e5 Year 10 Year Comments 5.Modify the surveillance testing procedures to include an evaluation of the governor settings be means of the two test below: (a)Perfrom a test of the governor settings while under mechanical

/electrical governor control, with the diesel generator off the grid in the isochronous mode.(b)Perform a test of the governor settings while under mechanical (only)governor control, with the diesel generator off the grid in the isochronous mode.NOTE: These tests shall include examinations of the engine speed transi-ents during start and transient loading condi-tions.Included as part of the above tests is the verification that the engine set speed of 450 rpm is not exceeded by more than 7.5 percent (484 rpm max.)either during an engine start or during the largest single load reduction.

Ref: Lead engine OR/gR Report 802-415A 6.Augment the setting adjustment procedures as'described in the Woodward manuals, to include a test of the governor response, during an engine start to ensure agreement with the specification as detailed in Item N5 above.Ref: Lead engine OR/gR Report 802-415A SH2401/32 Revision 1-Carryover from previous page Component Number Component Identification PH Recommendation SHEARON HARRIS HAINTENANCE HATRIX Alt.t~tuntat~outa e OuteeLe 5 Year 10 Year cuuuente 02-415B 02-415C 02-425A 5H2401/33 Governor Booster Servomotor Governor Heat Exchanger Jacket Water Pump-Gear 1.Clean, inspect, and replace"0" rings , and gaskets.1.Clean and inspect.1.Visually inspect)acket water pump gear for chipped or broken teeth, excessive wear, or potential/progressive pitting or other abnormal conditions.

2.Check the key to keyway interface for a tight fit on both the pump shaft to impeller and the spline to pump shaft during pump reassembly.

3.It is recommended that the castle nut that drives the external spline on its taper, have minimum and maximum torque values of 120 ft-lbs and 660 f t-lbs respectively.

Revision 1 Ref: 3/27/84 IOC from H.Wehmeyer to J.Kammeyer Any abnormal situations or indications of pro-gressive pitting should be reported for an engineering evaluation.

Ref: Lead engine OR/gR Report 802-355A This along with the drive f i t of the impeller on to the pump shaft, will pre-clude past problems where relative motion between both the shaft and impeller, and the spline and pump shaft caused fretting and upset of the keyway sides.Ref: OR/gR Report N02-425A Ref: OR/gR Report 802-425A SHEARON HARRIS MAINTENANCE HATRIX Component Number Component Identification PH Recommendation monthly Al t.~Outa e~Outa e 5 Year 10 Year Comments 02-435A 02"437 Jacket Water Fittings-Pipe and Fittings (Small Bore Scope Only)Turbo Water Piping-Pipe and Fittings l.Visually inspect for leaks.X Note: In the event of a leak developing in the existing Dresser Style 65 couplings, these couplings should be replaced with Dresser Style 90 couplings equipped with Viton gaskets l.Visually inspect for leaks.X Note: In the event of a leak developing in the existing Dresser Style 65 couplings, these couplings should be replaced with Dresser Style 90 couplings equipped with Viton gaskets This recommendation is made on the basis that the maximum suggested operating temperature of 150 F for the Style 65 coupling may be exceeded.The maximum suggested operating temperature of the Style 90 is 2124F.Ref: Letter dated 12/13/84 from C.L.Ray to J.George.This recommendation is made on the'asis that the maximum suggested operating temperature of 150 F for the Style 65 coupling may be exceeded.The maximum suggested operating temperature of the Style 90 is 212 F.Ref: Letter dated 12/13/84 from C.L.Ray to J.George.02-441A Starting Air Hanifold: Air Vent 1.Ensure that the starting X air manifold vent is open and effective.

Ref: 08/27/84 Hemo from W.Littmann to J.Cadogan, Ref: Lead engine OR/gR Report 802-442A (STAD)02-4418 Air Filter to Starting Air Distributor 1.Inspect filter elements.X Ref: TDI Instruction Hanual, Vol.I, Hain-tenance Schedule SN2401/34 Revision 1

Component Number Component Identification PM Recommendation SHEARON HARRIS MAINTENANCE MATRIX Al t.~Honthl~OUta e~OUta e 5 Year 10 Year Comments 2.Replace filter elements.Strainer-Starting Air System 3.Blow down strainer DAILY.4.Clean and inspect strainer X monthly.It is also recommended that the filter be changed whenever the manufacturers recom-mended maximum dif-ferential pressure is achieved..

Ref: Lead engine OR/(iR Report 802-4418 (Items 1&2)Ref: Lead engine OR/iiR Report N02-4418 (Items 3&4)If the strainer is excessively dirty, the frequency of cleaning and inspecting should be increased.

Air Start Block Valves 5.Clean, refurbish valves-replace"0" rings and clean the screened fitting.Ensure leak tightness after reassembly.

6.Inspect for tightness of fittings and bolts and apply locking com-pound, as required during reassembly of components.

Ref: Lead engine OR/gR Report 802-4418 (Items 5, 6, 7)5H2401/35 Revision 1-Carryover from previous page SHEARON HARRIS MAINTENANCE MATRIX Component Number Component Identification PM Recoaeendation 7.Replace"0" rings of the shuttle valve.Al t.0~natal~Outa e~Outa e 0 Year 10 Year Cnmaenta 02-442A Starting Air Valves Starting Air Distributor Assembly 8.Disassemble clean, inspect and lubricate valves to prevent fouling.Test to assure leak tightness upon reassembly.

l..Visually inspect the poppet valve spool ends and timing cam of the starting air distributor.

2.Ensure that the starting X air manifold vent is open and unobstructed.

Ref: Lead engine DR/iiR Report 802-441B.Evaluate the degree of wear to determine whether existing condition would have an adverse effect on timing and the specified ability to start the engine.Ref: Lead engine DR/gR Report 100-442A (STAO), Items 1 4 2 02-455A Fuel Oil Filter 1.Record filter d/p.Change filter elements when filter d/p reaches the manufacturers recom-mended maximum differen-tial pressure.Purge entrapped air from the filter canister using the vent valve provided, and divert some fuel oil into the newly replaced cartridge.

After air has been 5H2401/36 Revision 1 Component uuaher Component Identification PM Recommendation SHEARON HARRIS MAINTENANCE MATRIX Al t.M~eutht O~uta e~Outa e 5 Year 10 Year Comnents 02-455B Fuel Oil Strainers 2.Inspect canister gaskets and replace as necessary.

3.Inspect tubing and mech-X anical connections for tightness and/or leaks.1.Record strainer d/p.2.Purge air from stand-by strainers purged close vent valve and return handle to previous operating position.Ref: Lead engine OR/QR Report¹02-455A To be performed during change out of filter elements.Ref: 3/27/84 IOC from M.Wehmeyer to J.OiMare, Ref: TOI Instruction Manual, Volume I Shift/clean element if manufacturers recom-mended maximum dif-ferential pressure is achieved.Bolt torques of 120-150 in-lbs should be utilized during reassembly.

Ref: Lead engine OR/QR Report¹02-455B As required.5H2401/37 Revision 1-Carryover from previous page SHEARON HARRIS MAINTENANCE MATRIX Component Number Component Identification PM Recommendation

~Mont hl Alt.~Outa e Outacue 5 Year 10 Year Comments 03-465A External Lube Oil Lines 1.Ensure that a minimum installation gap of 0.171 inches is maintained between pipe ends at the 12-inch Dresser coupling.To be performed whenever piping is installed or reinstalled.

Ref: DR/QR Report 802-465A 02-465D Lube Oil Keep-Warm Strainer 2.Replace the 12-inch Dresser coupling gasket with a VITON gasket should leaks develop.1.Check strainer differen-tial pressure DAILY.Ref: Shearon Harris DR/QR Report 802-465A Task Description.

Clean and/or replace the element when the manu-facturer's recommended maximum differential pressure is achieved.Ref: Shearon Harris DR/QR Report 402-4650 Task Description.

02-467A Turbocharger Lube Oil Fittings Pipe, Tubing, Fittings, and Flexible Coupling (Small Bore Scope Only)l.Visually inspect for leaks.X Note: In the event of a leak developing in the existing Dresser Style 65 couplings, these couplings should be replaced with Dresser Style 90 couplings equipped with Viton gaskets This recommendation is made on the basis that the maximum suggested operating temperature of 150~F for the Style 65 coupling may be exceeded.The maximum suggested operating temperature of the Style 90 is 212'F.Ref: Letter dated 12/13/84 from C.L.Ray to J.George.5H2401/38 Revision 1 Component Number Component Identification PH Recommendation SHEARON HARRIS HAINTENANCE HATRIX Al t.a~hathi~Outa e~outa e 5 Year 10 Year tomeute 02-475A,C Turbocharger:

Bracket Bolting and Gaskets 1.Each month for the first months of commercial operation these screws should be inspected to assure that no screw has loosened because of engine operating loads.If during these inspections none of the screws are found loosened or damaged, from then on inspections are to be conducted on a yearly basis (or during plant shutdown).

But if any time during inspection any screw is found loosened or damaged, it must then be replaced (if damaged)and all screws retorqued as follows;125 ft-lbs for the bracket to engine screws and 75 ft-lbs for the bracket to turbo base screws.Note: To avoid damage to bracket to engine, and/or bracket to turbo, base screws, the proper torques as delinated above should be utilized for each respective bracket bolting application.

Re fr: OR/gR Reports 802-475A,C 02-4758 Air Butterfly Valve 5H2401/39 1.Lube valve shaft via grease fittings.Revision I Ref: IOC dated 3/28/84 from H.Wehmeyer to J.OiHare.If oil cups are used, this should be completed monthly.

SHEARON HARRIS HAINTENANCE HATRIX Component Number Component Identification PH Recommendation 2.Check valve disc for freedom of movement.M~anthl Al t.~outa e~Outa e 5 Year 10 Year Comments Check by visually observ-ing valve/actuator oper-ation.Re f: 04/16/84 from R.Jaquinto to R.Johnson 02-500A Engine Control Cabinet 3.Verify that associated X locking devices (jam nuts and lock washers)are tight.1.Inspect interior of cabinet for cleanliness and clean as required.2.Visually check wiring for insulation degradation.

Ref: DR/iiR Report I/02-4758 Ref: 3/29/84 IOC from H.Wehmeyer to T.Jacobs for Items 1-5, Ref: 07/30/84 IOC from J.Cadogan to K.Horelik for Items 1-6 3.Visually check instrument tubing for leaks.4.Functionally check cabinet heater and calibration of thermostat.

SH2401/40 5.Test pneumatic S/0 board logic.6.Replace"0" rings, gaskets and filter in pressure regulator.

Revision 1 Carryover from orevinus page Component Number Component Identification PN Recommendation SHEARON HARRIS MAINTENANCE NATRIX Al t.~uontht~outa e~Outa e 5 Year la Year conaento 02-500C Circuit Breakers and Contact Blocks 1.Check all terminals clean/tighten.

2.Visually check wiring insulation for degradation.

3.Trip check circuit breakers.To be accomplished during panel clean/inspection.

To be accomplished during panel clean/inspection.

02-500G Control Panel Valves 02-500J Control Panel Assembly: Relays 1.Inspect and clean control panel valves.2.Inspect and clean the 200 mesh screen in the check valve.1.Inspect contacts and clean as required.2.Visually check condition of wiring and tightness of terminations.

This recommendation in-terval should be reas-sessed depending on the degree of system fouling.Ref: Lead engine DR/ilR Report 802-500G Ref: Lead engine DR/gR Report 802-500G Ref: 08/10/84 IOC from K.Horelik to J.Cadogan 02-500N Control Panel Switches Terminal Boards and Wiring 1.Clean terminal boards and switch contacts.Ref: IOC dated 3/29/84 to J.Kammeyer from H.Wehmeyer for Items 1, 2, 3.2.Visually check wire insul-ation and terminals for tightness and degradation.

SH2401/41 Revision 1-Carryover from previous page

Component Number Component Identification PH Recommendation SNEARON HARRIS HAINTENANCE HATRIX Al t.M~eatat~Outa e~Outa e 5 Year 10 Year Caaaeata 3.Inspect for arcing and overheating.02-550 Foundation Bolts l.Visually inspect founda-tion for breaks in the bond between the sole plates and grout.Ref: TDI Instruction Hanual, Maintenance Schedule, Section 5 02-630D Thermocouples 2.Check foundation bolts for correct torque.Retorque as necessary then recheck crankshaft web deflections.

3.Generator foundation bolts are to be retorqued after a generator short circuit if the bolts were initially torqued to 480 ft-lbs.If initial bolt torque was 600 ft-lb no retorque is required.1.Check that thermocouple indicates ambient engine temperature when the engine is cold.2.Clean and inspect thermocouples and thermo-couple shields.Use TDI Instruction Hanual, Volume I, Section 8, Appendix IV for proper torque values.Ref: Lead engine DR/QR Report 802-550 An inconsistant reading traced to thermocouple trouble should result in replacement of the thermocouple.

Indications of fatigue should result in re-placement of the thermo-SN2401/42 Revision 1 Component Component Number Identification PH Recomaendation SHEARON HARRIS HAINTENANCE HATRIX Al t.e~eaathl~Outa e~Outa e 5 5ueee 10 Year Comments couple and/or thermo-couple shield.Ref: 7/31/84 Hemo from S.Riess to W.Littmann 02-650A Emergency Generator 3.Pyrometer wiring-check that terminations are tight.1.Check operation of brushes and slip rings.2.Clean/inspect all accessible parts of the generator.

3.Hegger rotor and stator.To be accomplished during control panel check-out and initial operation inspection.

Items 1, 2, 3;Ref: 07-30-84 IOC from J.Cadogan to S.Riess Ref.IOC dated 03/30/84 M.Wehmeyer to O.Hercald (Items 1-5).02-6508 Emergency Generator Control Panel 5H2401/43 4.Verify operation of space heaters.5.Measure vibration and check against base line data.1.Inspect panel for cleanliness and clean as required.2.Check terminal boards for loose wiring.Items 1-5;Ref: 3/30/84 IOC from H.Wehmeyer to D.Hercaldi Revision 1-Carryover from previous page Component Number Component Identification PH Recosmendation SHEARON HARRIS NAINTENANCE NATRIX Al t.h~entht~Outa e~Outa e 0 Year 10 Year Cuauenta 3.Visually check condition of wire insulation for degradation.

4.Clean and inspect relay contacts.5.Check meter calibrations.

6.Bridge rectifier assembly.and SCR mounting.Ref: DR/gR Report 802-650B, Attach.1 NOTE: The recommendations detailed for Item 6 are only necessary if the modifications specified in Attachment 2 of DR/gR Report 802-650B are NOT implemented.

a.Inspect the temperature X sensitive label placed on the most visible face of the hexagonal body of the diodes and the SCR.These labels shall be inspected before and after each running of the engine.If either of the labels permanently blacken the maximum temperature of the diode and/or SCR has been exceeded requiring an electrical inspection and an inspection of the mounting threads of the heat sinks and diode and/or SCR.5H2401/44 Replace the diode and/or SCR and the heat sinks as needed and assure that proper mounting tightness of 300 in-lbs (diode)and 275 in-lbs (SCR)and proper thread condi-tions are maintained.

Revision I-Carryover from previous page SHEARON HARRIS MAINTENANCE MATRIX Component Component Number Identification PM Recommendation

~Nanthl Alt.~Outa e~Outa e 5 Year 10 Year Comments b.Inspect glyptol applied X to the side of the lugs and mounting bolt for the lugs which attach to the bottom of the diode and the SCR heatsinks for signs of relative motion.To be performed after each monthly test run.Retighten any loose connections, remove old glyptol and reapply if connections are retightened.

7.Adjustment potentiometers

-X inspect glyptol applied to the the side of the adjustment screws for each of the five adjustment potentiometers on the printed circuit board of the voltage regulator for signs of relative motion.To be performed after each monthly test run.If adjustments are needed, remove glyptol and reapply when the adjustment procedure is complete.8.Printed circuit boards-X check for cleanliness and proper mounting of components.

02-650C Emergency Generator Pedestal 1.Check ring oilers Bearing for proper operation and verify oil level.To be performed after each monthly test run.Report any abnormal conditions to engineer-ing for evaluation.

To be accomplished during every test run of the engine.Ref: 3/30/84 IOC from M.Wehmeyer to N.Cooperrider (Items 1-4)SH2401/45 Revision 1-Carryover from previous page SNEARON HARRIS HAINTENANCE HATRIX Component Number Component Identification PH Recommendation 2.Drain flush refill bearing housing.3.Measure bearing housing insulation resistance.

Al t.~eeonthl~Outa e~0llta e 5 Year la Year Comaenta 02-695B Engine Control Air Pressure Regulator 4.Disassemble and inspect bearing and check clearances.

1.Inspect and clean engine shutdown equipment.

2.Replace elastomeric parts and gaskets in the pressure regulator.

NOTE: This recommenda-tion should be assessed depending on the degree of system fouling Ref: Lead engine OR/ilR Report N02-695B (Items 1')02-695C 02-7008 Engine Control Pneumatic Trip Switches Jacket Water Standpipe:

Valves 1.Check switch set points.2.Replace elastomeric parts.1.Replace elastomeric parts in circle seal valves.Pressure switches.Ref: 3/30/84 IOC from H.Wehmeyer to J.OiHare Ref: Lead engine OR/gR Report N02-7178 02-7178 5N2401/46 Auxiliary Sub-base 6 Oil 6 Water 1.Inspect the valves for X Piping-Jacket Water: Valves packing leakage.Replace as necessary.

Ref: Lead engine DR/gR Report N02-7178 Revision 1-Carryover from previous page SHEARON HARRIS HAINTENANCE HATRIX Component Number Component Identification PH Recoamendation M~onthl Al t.Outacue~Outa e 5 Year 10 Year Comments 02-7170 02-717H Auxiliary Sub-Base 6 Oil 8 Water Piping-Jacket Water: Pipe, Couplings, Fittings, Orifices, Y-Strainers (Small Bore Scope Only)Auxiliary Sub-Base Lube Oil Pipe and Fittings 1.Visually inspect for leaks.X Note: In the event of a leak developing in the existing Dresser Style 65 couplings, these couplings should be replaced with Dresser Style 90 couplings equipped with Viton gaskets.Visually inspect pipe and joints for leakage.Note: In the event of a leak developing in the existing Dresser Style 65 couplings, these couplings should be replaced with Dresser Style 90 couplings equipped with Viton gaskets.This recommendation is made on the basis that the maximum suggested operating temperature of 150'F for the Style 65 coupling may be exceeded.The maximum suggested operating temperature of the Style 90 is 212'F.Ref: Letter dated 12/13/84 from C.L.Ray to J.George.This recommendation is made on the basis that the maximum suggested operating temperature of 150OF for the Style 65 coupling may be exceeded.The maximum suggested operating temperature of the Style 90 is 212oF.Ref: Letter dated 12/13/84 from C.L.Ray to J.Geroge.SH2401/47 2.Clean and inspect L.O.keep-warm pump suction strainer.Revision 1 Complete when L.O.tank is drained.Ref: 04/16/84 letter from R.Jaquinto to R.Johnson Component Number Component Ident(fication PH Recommendation SHEARON HARRIS HAINTENANCE MATRIX Al t.H~onthl~Outa e~OUta e 5 Year 10 Year Comments 02-717I Auxiliary Sub-Base Lube Oil Valves 1.Disassemble, lubricate, inspect and refurbish.

2.Dissassemble, clean and check relief valve lift pressure.Ref: IOC dated 4/6/84 from H.Wehmeyer to J.DiHare.Ref: Lead engine OR/QR Reports f02-717G Ref: 07/31/84 IOC to H.McGerigle from J.Cadogan, Ref: 08/16/84 IOC f rom H.HcGeri g1 e to J.Cadogan, Ref: Lead engine OR/QR Report 802-717G (Items 1 8 2)02-805B Intake Air Filters l.Inspect air intake filters every 3 to 6 months.Replace if necessary.

Ref: Lead engine OR/QR Report 802-805B 02-805D Flex Connection 02-810A Jacket Water Heaters l.Visually inspect for evidence nf cuts, holes, or dents.1.Heasure heater insulation resistance.

2.Clean and inspect heater elements.3.Check calibration and inspect thermostat.

Replace heater if degradation of insulation resis-tance is noted.Ref: 5/10/84 IOC from M.HcGerigle to W.Brown for Items 1, 2, 3 5H2401/48 Revision 1-Carryover from previous page Component Number Component Identification PH Recoaeendation SNEARON HARRIS HAINTENANCE MATRIX Alt.t~tontnl~outa e~outa e 5 Year 10 Year Comenta 02-810C Jacket Water Neat Exchanger 1.To avoid corrosion and fooling, jacket water heat exchanger and associated service water piping should be flushed on a periodic basis (continuous service flow is sufficient).

Alternatively, ser vice water chemistry control can be used to maintain heat exchanger performance and integrity.

2.Perform a daily visual inspection for leakage at pycking whenever the engine is in the Emergency Standby Mode.Verify that no leakage is present through the leak-off ports of the lantern ring.3.Record heat exchanger perfor-mance by checking engine operating parameters.

4.Evaluate heat exchanger performance data.Ref: Lead engine OR/gR Report 102-810C, Ref: 04/20/84 IOC from H.Wehmeyer to R.Kadlec To be performed daily.Ref: 07/19/84 Tel econ O.Pasquale and R.Chii Use for trend data SH2401/49 Revision 1.

Component Number Component Identification PM Recommendation SHEARON HARRIS MAINTENANCE MATRIX Al t.~montnt~puta e o~uta e 5 Year le Year Comments 5.Inspect tubes and tube sheet for fouling and errosion-remove entrance and exit channel covers.Ref: TOI Instruction Manual, Volume I, Maintenance Schedule 02-810E Thermostatic Valves Replace packing rings at floating tube sheet after tube inspection.

6.Inspect and clean lantern ring.Verify leak-off holes are not plugged.7.Replace packing rings.1.Replace thermal power elements.2.Visually inspect valve X body for evidence of leakage.Ref: Lead engine OR/QR Report¹02-810C Replace/rework lantern ring as necessary to ensure concentricity prior to reinstall-ation.Replace packing when packing becomes hard or leakage at the packing is noted and cannot be stopped by tightening.

Ref: Lead engine OR/QR Report¹02-810C Ref: Lead engine OR/QR Report¹02-810D (Items 1, 2)To be accomplished during monthly test run.Ensure that SH2401/50 Revision 1-Carryover from previous page Component Component Number Identification PM Recommendation SHEARON HARRIS MAINTENANCE MATRIX Alt.~tteatht~Outa e 0~tata e 5 Year 10 Year Comments any replacement valves have cast steel valve bodies.02-820A Full Pressure Lube Oil Strainer 1.Record strainer d/p.2.Inspect and clean elements.3.Lube oil strainer pressure gauge-cali-bration check.Use for trend data Inspect/clean when strainer differential pressure rises signi-ficantly.Ref: Lead engine OR/QR Report f02-820M, Ref: TOI Instruction Manual, Volume I, Main-tenance Schedule 02-8208 Lube Oil Heat Exchanger 1.Perform a daily visual inspection for leakage at packing.Verify that no leakage is present through the leak-off ports of the lantern ring.Ref: Shoreham OR/QR Report 10-104 Re f: 06/12/84 IOC from R.Chii to P.Martia, Ref: 04/02/84 IOC from M.Wehmeyer to R.Kadlec 2.Record heat exchanger perfor-mance by checking engine operating parameters.

Use for trend data 5H240U51 Revision 1-Carryover from previous page Component Component Number Identification PH Recommendation SHEARON HARRIS MAINTENANCE HATRIX Al t.~uoutat~putt e O~uta e 5 Year 10 Year Couoeote 02-820C SH2401/52 Lube Oil Sump Tank Heaters 3.Evaluate heat exchanger performance data.4.Inspect tubes and tube sheet for erosion and fouling-remove entrance and exit channel covers.5.Inspect and clean lantern ring.Verify leak-off holes are not plugged.6.Replace packing rings at the floating tube sheet during reassembly after each inspection.

7.Perform a spectro chemical analysis of the lube oil.Particular attention shall be given to percent moisture content.1.Heasure heater insulation resistance.

2.Inspect and clean heater elements.Ref: TOI Instruction Manual, Volume I, Maintenance Schedule Re f: 07/19/84 Tel econ D.Pasquale and R.Chii Replace/rework lantern ring as necessary to ensure concentricity.

When packing becomes hard or leakage at the packing is noted and cannot be stopped by tightening.

To be performed at approximate quarterly intervals.

Ref: Lead engine OR/gR Report 802-820G Replace heater if de-gradation of insulation resistance is noted.To be accomplished during tank inspection.

Revision 1-Carryover from previous page SHEARON HARRIS MAINTENANCE MATRIX Component Number Component Identification PH Recomnendation H~onthl~Outa e Al t.~Outa e 5 Year 10 Year Comments 02-820E Full Flow Lube Oil Filters 3.Check calibration and inspect condition of thermostat.

1.Record filter d/p.2.Drain water and/or sludge from lubri-cating oil full flow filter.Ref: 05/10/84 IOC from H.HcGerigle to W.Brown for Items 1, 2, 3 Use for trend data, Ref: 04/02/84 IOC from M.Wehmeyer to J.OiHare, Ref: TOI Instruction Manual, Volume I, Maintenance Schedule 3.Replace filter cartridges and perform a visual inspection to determine the nature of the material caught in the filter.4.Lube oil filter gauge-calibra-tion check.To be performed before the filter d/p reaches the manufacturers recommended maximum differential pressure.Ref: 05/30/84 IOC from M.HcGerigle to B.Brown, Ref: Lead engine OR/OR Report 802-820F, Ref: 07/31/84 IOC from J.Cadogan to H.McGerigle SH2401/53 Revision 1-Carryover from previous page SHEARON HARRIS MAINTENANCE MATRIX Component Number 02-820F Component Identification Lube Oil Keep-Warm Pump PH Recommendation 1.Check operation of pump/motor bearings.2.Check mechanical seal leakage.3.Check coupling alignment.

4.Record pump discharge pressure.5.Measure unit vibra-tion (pump/motor) 6.The pump should be inspected for signs of leakage and corrective modifications (addition of flexible piping connections) be implemented as required honthly Alt.~Outa e~Outa e 5 Year 10 Year Coaments Items 1-5;Ref: 04/05/84 IOC from H.Wehmeyer to T.Fritsch Use for trend data To be performed daily Ref: DR/gR Report 802-820C 02-820G Lube Oil Keep-Warm Filter SN2401/54 1.Record filter d/p.2.Change filter elements.Revision I Ref: 04/05/84 IOC from H.Wehmeyer to J.DiHare To be performed before the filter d/p reaches the manufacturers recom-mended maximum differen-tial pressure.Ref: Lead engine OR/gR Report 802-820E SMEARON HARRIS HAINTENANCE MATRIX Component Number 02-835A Component Identification Oiesel Starting Air Compressors PH Recommendation 1.Check operating oil pressure.2.Overall visual inspection.

3.Clean fins on inter and after coolers.4.Replace intake filter element.5.Change compressor oil.6.Check belt tension.~Honth1 Al t.~Outa e~Outa e 5 Year 10 Year Comments All items;Ref: 04/02/84 IOC with attached Maintenance Char t from H.Wehmeyer to J.Kammeyer.02-835C Air Dryers and Moisture Traps 7.Check pulley clamp bolts/set screws tight.8.Inspect filter felts on unloader system.1.Blow down trap sediment bowls.2.Inspect and service moisture traps.Replace as necessary.

Ref: 04/05/84 IOC from H.Wehmeyer to J.Kammeyer, Ref: TOI Instruction Manual, Volume I, Haintenance Schedule 5H2401/55 Revision 1-Carryover from previous page SHEARON HARRIS MAINTENANCE MATRIX Component Number Component Identification PH Recommendation 3.Check proper operation of desiccant dryer.M~anthl Al t.~Outa e Outacue 5 Year 10 Year Comments Replace desiccant charge as required.Ref: 04/16/84 letter from R.Jaquinto to R.Johnson 02-835D Starting Air Tank l.Drain air receiver float traps or drain valves DAILY and monitor the quantity of moisture produced at the float traps or drain valves.2.Disassemble and clean the float trap.3.Starting air tank pressure gauges-calibration check.If quantity of moisture is excessive correct immediately.

Check air dryer operation.

Ref: Lead engine DR/gR Report N02-835J Ref: IOC dated 05/08/84 from P.Titus to P.Hartin (Items 1 8 2)4.Starting air tank pressure switches-calibration check.Jacket Mater System 1.Check pN.factor of jacket water and correct as recom-mended by chemical supplier.Ref: TDI Instruct>on Manual, Volume I, Hain-tenance Schedule 5H2401/56 Revision 1-Carryover from previous page Component Component Number Identification PH Recommendation SHEARON HARRIS HAINTENANCE HATRIX Al t.M~onthl O~uta e O~uta e 5 Year 10 Year Comments Lube Oil System 2.Replace elastomeric parts in jacket water valves.1.Check lubricating oil with a viscosi-meter for fuel oil dilution.Send a sample of oil to laboratory for analysis.Ref: TOI Instruction Hanual, Volume I, Hain-tenance Schedule, Items 1, 2 2.Drain lubricating oil system and clean sump tank.Depending on the results of lube oil analysis, refill with new oil.When replacing engine oil use H.D.oil that meets or exceeds series 3 standards.

The base stock should be more resistant to thermal degradation and coke formation.

The additive package should provide high detergent dispersant properties with high alkal>nity and a high level of antiwear additive such as zinc dithiophosphate.

Total Base Number (TBN)should be 12 to 15 for use with 82 fuel oil and a sulfated ash content of 1.5X to 2.0X is preferred.

An engine oil with such properties, Hobilguard 412 or equivalent product may be used to insure improved lubrication.

SH2401/57 Revision 1-Carryover from previous page Component Number Component Identification PM Recommendation SHEARON HARRIS MAINTENANCE MATRIX Al t.t~tanthl 0~tata e~Outa e 5 Year 10 Year Cneeaentt System Operation Piping System 3.Visually inspect lube oil sump tank level switch floats.Check switch set points.4.Perform a spectro-chemical analysis of the lube oil.1.Record all operating parameters.

Compare with base line data to ensure engine is operating properly.1.Conduct a detailed visual and audible inspection of all fuel, air, oil, and water piping and valves for leakage.To be performed after lube oil has been drained from sump.To be per formed at approximately quar terly intervals.

Ref: TDI Instruction Manual, Volume I, Maintenance Schedule.To be performed during monthly engine test run.Tighten, repair or replace as required.Ref: TDI Instruction Manual, Volume I, Maintenance Schedule 2.Inspect, clean and as applicable, lubricate manual valves on skid.5H2401/58 Revision 1-Carryover from previous page SHEARON HARRIS HAINTENANCE HATRIX Component Component Number Identification PH Recommendation Alt.~mentht~Outa e~Outa e 5 Year 10 Year Comments Hiscell-anceous Engine Internals Engine Hounted Pressure Switches Gear Train 1.Remove alternate left side doors and examine the inside of the engine for any" abnormal conditions.

Check with a good light for evidence of babbit flakes.1.Replace elastomeric parts.l.Inspect gears for general condition.

2.Measure gear back lash on all gears.If excessive water, sludge or any indication of bearing failure is present, drain crankcase, deter-mine cause, and take necessary action.Replace worn gears exceeding maximum clearance.

Complete TOI Inspection and Haint nance Form No.55-1-1 TOI Instr ction Manual, Vol.I, Section 5.Use Vol.I, Section 8 Appendix III-I for clearance values.Ref: 04/16/84 letter from R.Jaquinto to R.Johnston 5H2401/59 Revision I-Carryover from previous page ENGINEERING REVIEW CRITERIA DOCUMENT FOR THE DESIGN REVIEW OF THE TDI DIESEL SMALL BORE PIPING, TUBING AND SUPPORTS FOR THE TDI OWNERS GROUP Re ort No.11600.60-DC-02 Revision 0 Prepared by Stone L Webster En ineerin Co oration Boston, Massachusetts August 1984 , TDI1154 TABLE OF CONTENTS Section 1.0 Title INTRODUCTION

~Pa e 2.0 APPLICABILITY 3.0 OBJECTIVE 4.0 4.1 4.2 4.3 REVIEW METHODS REVIEW OF EXISTING TDI DOCUMENTATION REVIEW OF SMALL BORE PIPING REVIEW OF TUBING REVIEW OF SMALL BORE PIPING AND TUBING SUPPORTS REVIEW OF ENGINE INDUCED VIBRATION 5.0 5.1 5.'2 SPECIAL COMPONENTS DRESSER COMPRESSION COUPLINGS PIPING FLANGES TDI1154 V"~~IO TDI OWNERS GROUP ENGINEERING REVIEW CRITERIA DOCUMENT FOR THE DESIGN REVIEW OF THE TDI DIESEL SMALL BORE PIPING, TUBING AND SUPPORTS FOR THE TDI OWNERS GROUP

1.0 INTRODUCTION

The TDI Emergency Diesel Generator Owners Group Program requires Design and guality Revalidation reviews.'to independently verify the structural adequacy of the small bore piping, tubing and associated supports to withstand the effects of normal operating and earthquake loadings.This report provides the criteria to be used to perform the review.2.0 APPLICABILITY The requirements of the review contained in this report are applicable to all TDI supplied small bore piping and tubing systems including associated supports contained in-the diesel engine and its skid, unless specifically excluded by.an approved Task Description in.accordance with TDI Diesel Generator Owners Group Procedure DG-3.3.0 OB JECTIVE The objective of this report is to provide the criteria to be utilized to verify that the small bore piping, tubing and supports will perform their intended function under all normal and earthquake loadings.4.0 REVIEW METHODS 4.1 Review of Existin TDI Documentation The initial method to be utiTized in determining a component's acceptability is to perform a review of all existing small bore pipe stress and support documentation provided by TDI.The documentation will be reviewed to determine if it provides an adequate design basis in accordance with the appropriate codes as delineated by the individual utilities design specification for the diesel engine, The review shall also compare the as built piping and support condition to the existing design basis to determine compatability.

TDI1154/1 T gl C Page 2 If, after completing the review, the engineer determines that the component is acceptable, based on the existing documentation, the Component Design Report will be issued stating the conclusion of acceptability.

If TDI documentation is not available, or if it is determined that the available documentation does not readily lead to a conclusion of accpetability the engineer will alternatively continue the review as outlined in the following paragraphs.

4.2 Review of Small Bore Pi in for Acce tabilit In cases where the review of TDI documentation does not lead to component acceptability, the engineer will judge if the component will perform its intended function under all normal and earthquake loadings.This judgment will be based on a review of the following information:

guality approved as built piping isometrics System operating parameters Physical piping data Site specific amplified response spectra System function In addition to reviewing the above information, a physical walkdown of the engine and skid piping may be required.The walkdown would include a review of the piping to determine pipe support type and function, as well as a review for the following:

l Thermal fl exibi 1 it: The engineer will determine i f sufficient flexibility exists for each between support section of small bore piping.The thermal movement imparted by the supports onto the piping will also be considered.

Deadwei ht s ans: The deadweight spans between supports will be reviewed by the engineer and acceptability will be based on judgment.T the engineer and acceptability will be based on judgment.The engineer's judgment will consider the site specific amplified response spectra and all components, fittings and branch connections.

Engine induced vibration will also be considered in determining acceptability of seismic spans and is further discussed in paragraph 4.5.The engineer will document the reviews of the individual components by a written trip report.The trip report will serve as a summarization of the engineering walkdown.TD I 1154/2 REV I Page 3 In cases where the engineer judges that the component will perform its intended design function the Component Design Report will be issued stat-ing the conclusion of acceptability.

In cases where the engineer judges that a modification may be required to assure functional capability, a recommendation for the modification will be stated in the conclusions of the Component Design Review.The analyst may perform calculations to support the judgment in cases where it is not apparent that a modification is required.The object of these calculations is not to provide code compliance, but specific codes may be referenced for guidance.4.3 Review of Tubin.for Acce tabilit A field walkdown of all critical tubing components will be required.The same methods as outline in paragraph 4.2 for small bore piping review will.be employed for tubing.4.4 Review of Small Bore Pi in and Tubin Su ort In cases whe~e the review of TDI documentation, as outlined in paragraph 4.1, does not lead to component acceptability the engineer must continue the review based on the following:

1)guality approved as built support sketches, if available.

r 2)Physical support data 3)Anticipated support loads In addition to, or in'conjunction with, reviewing the above information, a physical walkdown of the engine and skid supports may be required.The walk-down would consist of a review of the following support components so that the engineer may judge if the support will perform its intended function: 1)Structural members 2)Structural bolts and base plates 3)Welds The engineer will document the review and recommend modifications as outlined in paragraph 4.2.4.5 En ine Induced Vibration The effects of engine induced vibration will be considered in determing the adequacy of the piping spans for dynamic loading.Specifically, the engi'neer TDI1154/3 Page 4 will determine if the existing piping spans may cause the piping to respond at the resonant frequency of the engine.This determination may be based on calculation or review of the vibration test results obtained at Shoreham and Comanche Peak.Another acceptable method of considering engine induced vibra-tion is to compare the specific engine small bore piping or tubing with proven acceptable design experience.

The documentation of acceptability or recommendation of modifications will be in accordance with paragraph 4.2.5.0 SPECIAL COMPONENTS 5.1 Dresser Com ression Cou lin Based on review of the small bore Dresser couplings at Shoreham, it is not required to perform qualifying calculations for the coupling on the remaining engines.The couplings are inherently qualified based on acceptability of the attached piping.5.2'Pi Fi Based on review of the small bore pipe flanges at Shoreham, it is not required to perform qualifying calculations for the flanges on the remaining engines.The flanges are inherently qualified based on acceptability of the attached piping.TD I 1154/4 DESIGN CRITERIA FOR DIESEL GENERATOR LARGE DIAMETER PIPING FOR SHEARON HARRIS Submitted to TDI Owners Group Charlotte, North Carolina Prepared by Impell Corporation 225 Broad Hollow Road Melville, New York 11747 Report No.02-0630-1258 Rev.A Job No.0630-037-1641 October, 1984.SH2666 TABLE OF CONTENTS 1.0 2.0 2.1 2.2 2.2.1 2.2.2 2.2.3 2.2.4 2.2.5 2.3 2.4 3.04.0 5.0 5..1 5.2 5.3 5.3.1 5.3.2 5.3.3 Title Page Table of Contents PURPOSE APPLICABLE CODES Diesel Generator Specification Requirements Code Requirements DEMA Standards American Bureau of Ships Building Codes.ANSI B31;1 and 831.3 ANSI B31.7 ASME Code Section III Applicable Code Acceptance Criteria Conclusion ACCEPTANCE PHILOSOPHY LOADING CONSIDERATION SPECIAL COMPONENT CONSIDERATIONS

.,Mitered Joints Unreinforced Branches Pressure Retaining Buttwelds Weld Penetration Considerations Weld Joint Capacity Stress Intensification Factor SH2666

TABLE OF CONTENTS (continued) 5.4 Dresser and Compression Couplings 5.4.1 Code Acceptability of Dresser and Compression Couplings 5.4.2 5.4.3 5.5 5.6 5.6.1 5.6.2 6.0 Coupling Validation Effects of Couplings on Pipe Stress Analysis Pipe and Equipment Supports Pipe Flanges Standard Flanges Non-Standard Flanges REFERENCES SH2666 "Ql ij'.

1.0 PURPOSE'he purpose of this document is to provide structural acceptance criteria for evaluation of the Transameri ca Del aval, Inc.(TDI), 1 ar ge di ameter, di esel generator skid.mounted piping at the Shearon Harris Nuclear Power Plant Unit.No.1, (SHNPP).This criteria was based primarily upon the philosophy embodied in industry accepted Codes and Standards for design of nuclear power station piping.2.0 APPLICABLE CODES 2.1 Diesel Generator S ecification Re uirements According to Reference 1, ASME III-Class 3 (Ref.2)is invoked for the subject piping at SHNPP.2.2 Code Re uirements 2.2.1 Diesel En ine Manufacturers Association DEMA Standards The DEMA Standard (Ref.3)extensively covers the detailed performance requirements of systems and subsystems for diesel engine driven electric power generating units, but does not cover analytical requirements or allowable stresses for piping systems.It relies on other codes for these requirements but does not specifically reference any.2.2.2 American Bureau of Shi s Buildin Code Section 36 of the American Bureau of Ships Building Code (Ref.4)discusses requirements for pumps and piping systems.This code presents very few design requirements, providing specific analytical formulas only for pipe wall thick-ness versus piping design pressure.The code makes no specific provisions for analysis for deadweight, thermal expansion, or dynamic effects.Piping materi-als and allowable membrane stresses are addressed in, this code.For example, ASTM A53 Grade B and A106 Grade B are approved materials.

It is noted that.this code provides tab'ulated membrane stress allowables which are the same as for B31.1 (Rpf.5)and ASME III Class 3 and 2 (Refs.2 and 6).2.2.3 ANSI B31.1 and 831.3 The general philosophy of ANSI B31.1 (Ref.5)and B31.3 (Ref.7)is to parallel those provisions of Section I"Power Boilers" of the ASME Boiler and Pressure Vessel Code, as they can be applied to piping systems functioning at elevated pressures and temperatures.

These codes are conservative, reflecting the general need for long service life and maximum reliability in power, chemical, and petroleum refinery installations.

SH2666/1

~4iV I'4 tV Xp V Page 2B31.1 and B31.3 are quite similar, except that 831.3 allowable stresses are somewhat more permissive than B31.1 values.Both are all inclusive codes which set forth engineering requirements for design and construction of piping systems.These codes contain basic reference data and formulas deemed neces-sary for design, including the following:

(1)Material specifications and component standards which have been accepted for code usage;(2)The designation of proper dimensional standards for the elements compris-ing piping systems;(3)(4)Requirements for the design of component parts and assembled units, including necessary pipe supporting elements;Requirements for the evaluation and limitation of stresses, reactions, and movements associated with pressure, temperature, and external forces;(5)Requirements for the fabrication, assembly, and erection of piping systems.(6)Requirements for testing and inspection of elements before assembly or erection and of the completed systems after erection.2.2.4 ANSI B31.7~~~~~~~~ANSI B31.7"Nuclear Power Piping" (Ref.8)was the precursor of ASME III-Class 1 Subarticle NB-3600, which covers ASME Code Class 1 piping design, and embrac-es the same design philosophy as ASME III-Class 1 (Ref.9).2.2.5 ASME Code Section III The ASME Boiler and Pressure Vessel Code provides rules for the construction of boilers, pressure vessels, and nuclear components.

Section III of this Code addresses nuclear power plant components, and consists of two (2)divisions.

Division 2 covers concrete reactor vessels and containments and is not perti-nent here.Division 1 cohsists of the following subsections:

NCA NB NC ND NE NF NG Appendices General Requirements Class 1 Components Class 2 Components Class 3 Components Class MC Components Components Supports Core Support Structures SH2666/2 lab 4 Page 3 Each subsection is divided into articles as follows: Article 1000 Article 2000 Article 3000 Article 4000 Article 5000 Article 6000 Article 7000 Article 8000 Introduction and Scope.Material Design Fabrication and Installation Examination Testing Overpressure Protection Nameplates, Stamping and Reports The code recognizes that various components have different levels of importance associated with the components'unction, as related to the safe operation of the nuclear power plant.The code classes thus permit a choice of rules that provide assurance of structural integrity and quality commensurate with the relative importance assigned'to the individual items.Class 1 components are assigned the highest level of importance.

Reactor coolant pressure boundary components are examples of what is normally assigned as ASME III-Class l.Class 2 components are assigned the next lower level of importance.

Nuclear safety related components other than reactor coolant pressure boundary compo-nents are examples of what is normally assigned to ASME III-Class 2.Class 3 components are usually of the same level of importance as Class 2 components, but are assigned to ASME III-Class 3 by virtue of their moderate normal operat-ing temperatures and pressures.

ASME Code Section III does not provide guidance in the selection of component classification and places the responsibility of such component classification on the owner of the nuclear power plant.2.3 A licable Code Acce tance Criteria Those portions of the applicable building codes and standards which refer to structural integrity of the subject piping are addressed herein.The portions of these codes which provide requirements for documentation and other quality assurance related requirements, as well as adequacy of system design requirements such as overpressure protection adequacy, are not.part of this scope.Reference 1 invokes ASME-Class 3, (1974 edition, including addendums through winter 1976)for the SHNPP diesel generator piping.This classification is consistent with the moderate service temperatures and pressures associated with the subject piping.ASME III Class 3 applies specifically to nuclear safety related piping, having rigorous dnalytical requirements that are acceptable to the nuclear industry and the U.S.Nuclear Regulatory Commission.

ANSI B31.1 (Ref.5)and ANSI B31.3 (Ref.7)by virtue of its similarity, is also applica-bl e.SH2666/3 p%lp%,1 A L4~kr<<r Page 4 Since ASME III-Class 3 permits qualification to a'ore stringent code subsec-tion, it is permissible to provide ASME III-Class 2 (Ref.6)or ASME III-Class 1,(Ref.9)analysis for this purpose.ANSI B31.7 (Ref.8)is the predecessor to ASME III-Class 1 and is, therefore, similarly applicable.

ASME III-Class 1 has considerably higher allowable stresses for material such as ASTM A106 Grade B.However, this is applicable only if ASME III-Class 1 stress analysis is performed.

Note th'at ASME III-Class 1 analysis provides design rules for rigorous evaluation of fatigue life and must be used if the piping is justified on that basis.2.4 Conclusion It was concluded that the SHNPP diesel generator piping design utilizes the.philosophy and intent of ASME III-Class 3 design (Ref.2)to provide analyti-cal justification of piping design acceptability.

The other above referenced codes (References 5, 6, 7, 8&9)were also judiciously considered where applicable, as described in Section 3.0.3.0 ACCEPTANCE PHILOSOPHY The intent and philosophy of ASME III-Subsection ND design rules for Class 3 components (Ref.2)was utilized as the basis of acceptance.

The requirements of other codes and standards (Refs.5, 6, 7, 8 and 9)were also considered for applicability.

The analysis was performed in steps, as follows: 1.Pipe stress analysis was first performed in accordance with the design rules of ASME III-Class 3 (Ref.2), using conservative assumptions for modeling and stress intensification described in detail in 5.0 (below).2.If this analysis indicated excessive stresses, then the results were evaluated to determine if relaxing some of the conservatisms could be justified for the particular piping systems being considered.

For example, it was, at times beneficial to consider the more rigorous, ASME III-Class 1 analysis in an attempt to justify thermal expansion stresses on the basis of adequate thermal fatigue life.3.If pipe stress was still excessive after relaxing conservatisms, support modification was then considered.

4.The applicable piping system was then reanalyzed to reflect the above referenced analytical modification.

Or, as an alternative, hand calcula-tions were performed to account for.a highly localized effect.SH2666/4 v+"4k F' Page 5'i 4.0 LOADING CONSIDERATIONS The pipe stress analysis accounts for all loads due to deadweight, thermal expansion, and earthquake.

The effects of earthquake were determined by dynamic pipe stress analysis utilizing appropriate seismic response spectrum envelopes..

As noted in the Diesel Generator Seismic Criteria (Ref.10), Operating Basis Earthquake (OBE)and Safe Shutdown Earthquake (SSE or DBE)were considered.

Consistent with Reference 10, a three-directional earthquake was assumed.The effects of'each of the vertical and two horizontal earthquakes was first determined by combin-ing across modes by square root sum of squares (SRSS)with closely spaced modes considered by the ten percent method.The three directions of earthquake were then combined by SRSS to determine the seismic results.Seismic spectra was based on Reference 10.Damping values were selected consistent with Reference 10.Also, based upon data provided in Reference 11, the diesel and its supporting skid have first mode natural frequencies in the rigid range of the applicable response spec-trum.Therefore, consideration of the dynamic amplification of those compo-nents was not necessary and the floor spectra was used for all analyses.The analytical piping model for both thermal and seismic analyses included the pipe supports, which were modeled as springs whose spring constants were based on the as-built pipe support configuration of the Lead Diesel (Comanche Peak), where applicable.

When the Shearon Harris supports could not utilize spring constants from Comanche Peak, either spring constants were developed upon available information, or computer program default spring constants were used.In addition, to more accurately represent both the flexibility of equipment and its dynamic effect on the piping, the equipment was included in the analytical piping model using cross"sectional properties and component weights derived from the applicable equipment details.However, if a particular piece of equipment was apparently rigid, based on engineer ing judgement, then that equipment was not included in the analytical model.5.0 SPECIAL COMPONENT CONSIDERATIONS This section provides.discussions relating the analytical considerations of special configurations and components.

These include specialty items such as Dresser and Compression Couplings, flexible hose and pipe flanges, and also includes special configurations such as mitered joints, unreinforced branches, including unreinforced lateral connections, and.circumferential buttwelds.

5.1 Mitered Joints Mitered joints are permitted by ASME III-Class 1, 2 and 3 (Refs.2, 6, and 9), as well as B31.1 (Ref.5)and B31.3 (Ref.7).Flexibility characteristic (h), flexibility factor (k), and stress intensification factor (i), as tabulated in Figure NC-3673.2(b)-1 and Figure ND-3673-2(b)-1 in Ref.2 and 6, were utilized'for ASME III-Class 2 and 3 analyses, respectively.

SH2666/5 vW IP Al~~~~"4(

Page 6 Furthermore, to assure that the miter joint induced discontinuity stresses were acceptably low, equation 4(c), paragraph 304.2.3 of B31.3 (Ref 7)was evaluated to'determine the pressure capacity of the joint as compared with the normal operating pressure of the pipe in question.~5.2 Unreinforced Branches The use of unreipforced branch connections, including unreinforced lateral connections as used in the SHNPP diesel generator skid mounted piping, is permitted by ASME III-Class 1, 2 and 3, as well as by B31.1 and B31.3..Flexibility characteristic (h), flexibility factor (k)and stress intensifica-tion factor (i), as tabulated in Figure NC-3673.2(b)-1 arid Figure ND-3673.2(b)-l were utilized for ASME III-Class 2 and 3 respectively.

P Additiohal analysis.'was performed to confirm that the pipe is."sel f-, reinforcing" and that the rules for metal reinforcement requirements set forth in the codes (e.g., ASME III-NC-3643.3, et.al.)were satisfied.

It is noted that since the design pressure was small in relation to the actually furnished pipe wall thickness, there was considerable excess wall thickness available for self-reinforcing of the branch penetrations.

5.3 Pressure Retainin Buttwelds 5.3.1 Weld Penetration Considerations For the seamless on-engine piping, weld only in the bevel region was assumed.No weld penetration in the land region (assumed as 1/16 inch)was assumed.5.3.2 Weld Joint Ca acit Minimum wall thickness requirements dictated by design pressure (e.g.ASME III-NC-3641.1, Equation (3), et.al.)must be maintained at the circumferen-tial buttwelds, which join adjacent spool pieces.For the SHNPP diesel generator piping, it was conservatively assumed that the material available for design pressure requirements was equal to the pipe wall thickness minus 3/32 inch, to account for the worst possible minimum weld thickness.

Minimum weld thickness to minimum required pipe wall thickness ratios were determined for all of the subject pipe sections.The smallest ratio of (tw/tmin)was found to be 2.0 (or 200 percent of minimum required wall thickness).

Thus, these welds always met minimum Code requirements for pres-sure dependent pipe wall thickness.

This excess wall provides adequate generic margin against corrosion.

More specific data regarding corrosion is provided in the specific component reports where applicable.

SH2666/6 Page 7All pipe stress calculations, other than design pressure vs.wall thickness calculations, utilized the nominal pipe wall'hickness, since a local thinning of the pipe affects its pressure capacity but has a negligible effect on gross bending stresses.This is consistent with the philosophy of ASME III and ANSI codes.Applying this philosophy to the circumferential welds, it was thus assumed that for deadweight, thermal expansion and sei smi c loading stress analysi s, the available wall thickness was the nominal wall thickness minus the nominal flat landing of 1/16 inch.The evaluation of stresses at the circumferential buttwelds considered this reduction in section.If the stresses thus derived were adequately low, then strength capacity of the circumferential weld joints furnished for the subject piping was considered to be adequate.5.3.3 Stress Intensification FactorThe initial analysis utilized a stress intensification factor (SIF)of 1.8, which was the upper limit specified in ASME III-ND (1974 version including addenda through Winter 1976)Figure ND-3673.2(b)-1 for a mismatch of an as welded buttweld (which is in excess of 0.]., i.e, having a ratio of mismatch to pipe wall thickness[delta/t]).

This approach was a conservative necessity.

If it could easily be determined that the ratio (delta/t)is 0.1 or less, then the code permits an SIF of 1.0 for as welded or flush buttweld.However, since the pipe had independent I.D.,O.D., and'ut of round tolerances, it was not possible to determine the actual pipe wall mismatch (delta)between two adjacent spools by visual inspec-tion of the outside of the piping.Thus the conservative value of 1.8 was utilized.5.4 Dresser and Com ression Cou lin s Dresser Couplings (see Figure 1)and Compression Couplings (see Figure 1)were utilized throughout the SHNPP diesel generator skid mounted piping.These couplings provide a flexible, leak proof seal at the pipe spool piece inter-face, without pipe threading, or welding, and do not require precise spool piece end preparation or precise piping alignment.

These couplings have an 80 year record of successful service on all kinds of piping such as water mains, sewage treatment, and water filtration piping, and in all branches of the oil industry, and have been used extensively by TDI for other diesel generator installations.

SH2666/7 g]

Page 85.4.1 Code Acce tabilit of Dresser and Com ression C'ou lin s.ASME III-NC-3649 (for Class 2 components) and ASHE III-ND-3649 (for Class 3 components) permit the use of pressure retaining products not specifically covered in the code, which are shaped, proportioned, and sized similar to components that have been proven satisfactory by successful performance under comparable service conditions.

By virtue of their long record of satisfactory service for moderate pressure/temperature systems of this type of application, the Dresser Couplings meet the intent of ASIDE-III Class 2 and Class 3 (Refs.2 and 6)and were therefore acceptable components.

5.4.2 Cou lin Validation 1.Selection The Dresser catalog specifies limiting pressures and temperatures for the various couplings.

The subject service conditions were evaluated against these requirements and some couplings, because of the gaskets supplied, were slightly marginal with respect to the temperature requirements.

For these couplings, replacement with an upgraded model was specified if leaks developed.

2.Ois lacement Verification When acceptable piping/pipe support results are obtained, the relative transla-tions and rotations of the joined pipes were compared to the vendor allowables for the coupling to validate the analysis.5.4.3 Effects of Cou lin s on Pi e Stress Anal sis 1.Pressure Effects Pressure integrity of the piping is achieved by wedging the coupling gasket against the outside of the pipe and into the mating fitting (Reference Figures 1 and 2).However, this configuration permits axial pipe movements of the adjacent pipe spool pieces.Thus, when the pipe is pressurized, it would tend to slip out of the coupling and separate, if some external axial anchorage were not also furnished.

Pipe supports and terminal end connections were relied upon to prevent slipping.The pipe stress analysis included the effects of these resulting unbalanced pressure forces.2.Constraint of Thermal Ex ansion As shown in Figures 1 and 2, a gap is intended to be maintained between the two pipe spool pieces during installation.

This.would accommodate a modest amount of thermal pipe expansion.

However, if this gap is not maintained during the installation of the piping, then the thermal expansion relief is partially negated.SH2666/8

~l' Cou lin s Without Tie Rods Page 9 Pipes joined by couplings without ,tie rods have only the gasket and its frictional capacity to provide any mutual stiffening across the joint.Since this is very low, couplings without tie rods were analyzed as completely free to rotate and translate relatively.

Cou lin s With Tie Rods Couplings with tie rods were addressed according to the tendency of the joined pipes to separate or close the original installation gap under various loads.For the case where the joined pipes move to decrease the installation gap under thermal and internal pressure loadings, i.e., the tie rods becoming ineffective, the analyses were performed allowing all relative translations and rotations.

3..Seismic Interaction at the Cou lin s i Examination of Figures 1 and 2 indicates that modest translations and rotations between the two adjacent piping spool pieces are possible, by.virtue of the soft gaskets, and the gaps within the couplings.

For seismic analysis, it is not conservative to neglect this flexibility.

In order to account for this, seismic pipe stress analysis first conservatively assumed the piping systems to be completely separated at the coupling, thus taking no credit for any mutual stiffening across the coupling.If the seismic stresses were acceptable, then no further evaluation was performed.

5.5 Pi e and'ui ment Su orts Pipe and equipment supports were qualified on the basis of plant specific operating history as well as Impell's experience with the Shoreham and Comanche Peak Diesel Generators.

Engineering judgement was used in the qualification of supports.Since as-built details for supports were not provided, it was assumed that supports were installed as originally designed by TDI.Where previous support problems existed, either on the Grand Gulf engine or on similar engines, generic-type recommendations for modifications were made.Where piping analysis deemed support modifications (e.g., addition or removal of supports)necessary, recommendations to incorporate such changes were included in the final reports.Where there was no history of problems with a support nor any analytical basis for modification, that support was judged adequate for its intended purpose.SH2666/9 I,

Page 10 5.6~PI F1 5.6.1 Standard Flan es Flanges fabricated to standards listed in ASME III-NC-3132-1 (for Class 2)and ND-3132-1 (for Class 3)are acceptable for ASME III Class 2 and 3.For these flanges the established pressure/temperature rating was first compared with operating pressure/temperature to evaluate the flange selection..

Since the operating pressures for the subject piping systems were modest, the flange had excess capacity to carry mechanical loads imposed on the flange.This was confirmed by conservative hand calculations using techniques outlined in ASME III-Subsection ND 3658.5.6.2 Non-Standard Flan es At a number of locations within the SHNPP Diesel Generator skid mounted piping, square or rectangular, flat plate flanges were utilized.These flanges were analyzed as flat plates, using conservative assumptions.

6.0 REFERENCES

1.TDI Letter to Mr.F.Thompson from Mr..L.Duck, dated June 11, 1984.2.American Society of Mechanical Engineers (ASME)Boiler and Pressure Vessel Code,Section III,"Rules for Construction of Nuclear Power Plant Compo-nents" (ASME III)Subsection ND Class 3 Components (ASME III-Class 3).3.Diesel Engine Manufacturers Association (DEMA),"Standards and Practices for Low and Medium Speed Stationary Diesel and Gas Engines," 1972.4.American Bureau of Ships,"Rules for Buiding and Classing Steel Vessels," 1976.5.American National Standards Institute (ANSI)Document ANSI/ASME B31.1,"Power Piping" (B31.1).6.ASME III, Subsection NC, Class 2 Components (ASME III-Class 2).7.ANSI document ANSI/ASME B31.3,"Chemical Plant and Petroleum Refinery Piping" (B31.3).8.ANSI B31.7,"Nuclear Power Piping" (B31.7).9.ASME III, Subsection NB, Class 1 Components (ASME III-Class 1).10.Ebasco Speci f i cati on 216-73Tb (Pro ject Identi f i cati on No CAR-SH-E-11)"Diesel Engine-Generator Unit 8 Control Panel for Nuclear Power Plants", Addendum A, Revision 9, November 2, 1977.SH2666/10 Page 11 11.TDI Final Report Volume I-Seismic gualification of Transamerica Delaval DSRV-16-4 Diesel Generator Unit.Prepared for CP&L Shearon Harris Nuclear Power Plant.Section II: Modal Testing and Seismic gualification of the Engine.12.TDI Final Report Volume II-Seismic gualification of Transamerica Delaval Diesel Generator Sets-Serial Numbers 74046/53 for Carolina Power&Light Co., Shearon Harris Nuclear Power Plant, Units 1, 2, 3, and 4.Section X: Auxiliary Sub-base, dated April 16, 1984.SH2666/11

~\4 I~

Report No.02-0630-125P.

Rev.A MIODLR RIHO Style 38 and Style RQ Coupling Gasket ctoss section.This section furnished for Stab-38 and Stab-39:Covplings.

OUTRR RIM IHHKR RIM tl OisrRT g RRCKSS Cutaway view of Oresser Ccwpling, showing working principle and iilvstrating shape and relative po sitlon of component pans.Insets show details of parts.faa~~g Bk I'+l FIGURE IDRESSER COUPLING I tlat Report No.02-0630-1258 Rev.A 1.Q)>>0$~0~b~rl)'CoeeakA~w J'IGURE 2 COMPRESSION COUPLING

ATTACHMENT B TO NLS-85-l00 REVISION TO ATTACHMENT A TO NLS-N-190 DATED DECEMBER l7, l980 (1337PPC/mf)

Page 13 SECTION E MAINTENANCE R SURVEILLANCE PROGRAM As part of the TDI Diesel, Generator Owners'roup effort, a maintenance and surveillance matrix has been developed for the SHNPP equipment.

This matrix is provided in Appendix II of the DR/QR Report (see Volume 0).The maintenance matrix was developed utilizing TDI instruction manuals, TDI service information memos (SIMs), TDI correspondence on specific components, and Owners'roup technical staff input resulting from the development of the diesel generator reliability program.The DR/QR Maintenance Matrix will be used in lieu of the manufacturer's manuals.CPRL will implement the Owners'roup maintenance recommendations by incorporating them into the overall SHNPP maintenance program subject to the following clarifications:

1.Where five-year inspections are indicated, these will be performed at the first refueling outage following the completion of the fifth year of plant commercial operation.

2.Where ten-year inspections are indicated, these will be performed at the first refueling outage following the completion of the tenth year of plant commercial operation.

Regardless of the accumulation of engine operating hours, the first inspection requiring disabling of the diesel generator will be performed at the first refueling outage following plant commercial operation.

0.Subsequent to licensing of SHNPP, periodic testing of the diesel generators during normal plant operation will cause the equipment to run for about 00 to 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> during a fuel cycle.During the 1985 testing phase on this equipment, CPRL intends to operate one diesel generator for at least 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> more than the other diesel generator.

This unit will then be the"lead" diesel generator and will be disassembled and inspected as required by the maintenance matrix.The"follow" diesel generator inspection will be performed at the next refueling outage.The intent is to only perform major maintenance on one diesel during a particular outage.This is reasonable utilizing the"lead" engine concept.5.(Deleted)6.Page 55 of the matrix (component 02-835A, starting air compressors), recommendation number 8, discusses the inspection of filter felts on the unloader system.The filter felts were not included in the design or installation of the SHNPP equipment and the recommendation is not applicable.

(1337PPC/ccc

)

Page 15 SECTION F DISCUSSION OF OWNERS'ROUP SHNPP PHASE II DR/QR REPORT The TDI Diesel Generator Owners'roup SHNPP DR/QR Report represents a comprehensive review of the equipment procured for installation at the SHNPP site.It encompasses about 160 items as identified with an"X" in either the DR or QR column of Table 2-2 (see Volume I).On the basis of implementation of the recommendations contained within the DR/QR Report, it is concluded that the SHNPP diesel generators are fully capable of performing their intended safety function as described in the FSAR.As discussed elsewhere in this report, the engines have been disassembled, inspected, upgraded as deemed appropriate, and are presently being reassembled.

At this time, not all actions have been completed.

However, CPRL will satisfy the recommendations contained within the DR/QR Report, as discussed within this section, or will specifically perform engineering evaluations to justify deviation from the OG recommendations.

The purpose of this section is to identify clarifications needed in the SHNPP DR/QR Report based upon CPRL's review.This does not include editorial, or labeling, corrections that could be incorporated.

Further, as one item may appear in more than one place in the four-volume report, the following comments are identified by component number and apply in all applicable locations.

~~1.(Deleted)2.Component 02-385A: Relief valves are not included at SHNPP.Refer to Component 02-386A.3.(Deleted)0.(Deleted)5.(Deleted)(1337PPC/ccc)

Page 16 6.Component 02-300A: CPRL will inspect a sample on one engine at the first outage.Absent any problems, it is safer to leave the components undisturbed and avoid potential mechanical errors due to disassembly and reassembly than to MT the connecting rod bolts each outage.TDI has evaluated the IA-6-0 connecting rod bolt and determined that it is satisfactory.

It is to be reinstalled.

7.Component 02-700A: The vent line drawing used for the DR is not the correct drawing.This will need revisions.

3.(Deleted)9.Component 02-055B: The modifications are not necessary, based on engineering evaluation of the strainer installation.

10.Component 02-075B: TDI SIM 322 has been incorporated.

11.Component 02-689: Due to equipment layout/installation within the building, the liquid level transmitter design is being changed.The new design will satisfy the intent of the Owners'roup recommendations.

12.Component 02-315E: The studs will be installed using a graphite-oil lubricant and to a free length of 15+1/3 inches.Both of these parameters have been verbally approved by TDI.4 13.Component 02-310A: A torsiograph test will be performed on one engine.The main journal oil holes have been polished and inspected with satisfactory results.IO.Component 02-650B: Cabinet ventilation and other needed modifications will be pursued.Other recommendations may not be prudent due to existing equipment layout and mounting.15.Appendix II: The SHNPP commitment with respect to the maintenance and surveillance matrix is discussed in Section E of this report.16.Appendix III: The criteria documents presented reflect the generic methodology of how the tasks were performed.

These are provided for information only.(1337PPC/mf)

I, ATTACHMENT A TO NLS-85-I00 REVISION I TO DR/QR REPORT FOR THE SHEARON HARRIS DIESEL GENERATORS J$

TDI OWNERS GROUP APPENDIX-II GENERIC MAINTENANCE MATRIX TDI OWNERS GROUP GENERIC MAINTENANCE MATRIX APPENDIX-II OVERVIEW AND DEFINITIONS OPERATING AND STANDBY SURVEILLANCE PARAMETERS PART A TDI OWNERS GROUP GENERIC MAINTENANCE AND SURVEILLANCE PROGRAM APPENDIX-II I INTRODUCTION The purpose of this appendix is to provide the TDI Owners with a set of maintenance and surveillance recommendations for diesel generator com-ponents which have been developed by TDI and/or the Owners Group as a result of the overall Owners Group Program and including subsequent testing and inspections performed following the review conducted by the original program.This appendix is intended to enhance the existing TDI Instruction Manual, Volume I and Volume III, which will maintain the qualification of the diesel generators for the life of the plant.!I METHODOLOGY During the implementation of the Owners Group Program Plan, the Owners Group Technical Staff reviewed many sources of information regardi ng the maintenance and surveillance for the diesel generator components iden-tified in this appendix.These sources included TDI Instruction Manuals, Service Information Memos (SIMS), and TDI correspondence on specific components.

The basis of this matrix is formed by the following:

~Owners Group Technical Staff review of TDI Instruction Manuals, SIMs, and TDI correspondence on specific components.

Technical Staff input regarding the adequacy of recommendations found in sources mentioned above.Additional maintenance recommendations identified during the DR/gR review.~Results of subsequent testing and surveillance (i.e., Shoreham EDG103 750-hour endurance run and subsequent engine teardown)performed following the review conducted during the original program.~Additional review by the Owners Group representatives.

It should be noted that this revision in some cases modifies the original program results based on this additional information and review.II I RESULTS AND CONCLUSIONS Proper maintenance is important in ensuring long, reliable and satis-factory service of the emergency diesel generators.

Maintenance work, in order to be effective, must be carried out thoroughly and regularly.

It I I-A" 1 Revision 2 is for these reasons that a detailed schedule of maintenance service has been laid out by the Owners Group for the TDI Diesel Generators.

This schedule should be followed as closely as the operating conditions will permit.This maintenance service as specified supersedes previous general maintenance requirements, but is separate and does not supersede guality Revalidation and/or modifications previously recommended.

The schedule details specific components requiring maintenance on a regular basis.This schedule separates the maintenance activities into frequencies as set forth in the subsequent list of definitions.

Inspections, as outlined in this maintenance schedule, are to be performed and parts refurbished or replaced as required by the program or deemed necessary by the inspection.

Any adverse findings shall be investigated and corrective action, including amended inspection frequencies, shall be implemented unless sufficient justification is present to do otherwise.

This generic matrix, Parts A, B, C together with Part 0 entitled"Site-Specific Maintenance Matrix" and the sources defined in Section II form the TOI Maintenance Program.Note that component numbers used in the generic matrix are for Texas Utilities'omanche Peak Steam Electric Station-Unit 1.Part E provides a cross reference to identify corre-sponding components for other engines.Also note that a blank in the cross reference signifies that a component is not on a particular engine and thus that Owner would not perform that maintenance item.Tables 1 and 2 of Part A provide engine operating and standby surveillance parameters and frequencies.

It is recommended that the utility'ddress these tables in its operating and monitoring programs.Table 1 addresses operating parameters and is not duplicated in the maintenance schedules; these parameters are to be recorded and/or checked during the monthly-testing and any other period of operation.

Table 2 addresses the standby parameters that occur on a daily frequency and are not duplicated in the maintenance schedules.

OEFINITION OF TERMS Overhaul Frequency a)A complete engine teardown and inspection will be performed every 10 years.The utility has the flexibility to inspect one engine/reactor unit at the EOC prior to 10 years and the other engine at the EOC following 10 years.Alternately for PMR units, the inspection may be performed coincident with the 10-year reactor vessel in-service inspection.

This will permit both engines for each unit to be disassembled in parallel since one engine will not have to remain in service with the reactor vessel off loaded.(For reactor units having three engines, the inspections are to be carried out as above with the third engine to be inspected at the second EOC following 10 years).The 10-year interval will typically be taken from issuance of the Low Power Operating license or from subsequent teardown and inspection for plants already in operation.

I I"A-2 Revision 2 b)A one time inspection will be performed at the EOC closest to 5 years.For a unit, one engine may be inspected at the EOC prior to 5 years and the other at the EOC after 5 years to minimize plant outage length.(For reactor units having three engines, the inspections are to be car ried out as above with the third engine to be inspected at the second EOC'following 5 years).This inspection will generally involve the same components as the 10-year teardown;however, only a sample of items for some components will be inspected as set forth in the maintenance schedule.During this 5-year inspection any signifi-cant adverse findings of a particular component will result in an inspection of all such components of that engine to determine any adverse trends.Favorable findings will result in reassembly of the engine for service.2.Daily Frequency-To be performed once per day.3.Monthly Frequency-To be performed once in a month;normally during, before, or after test run per plant Technical Specifications.

4.EOC-(End of Cycle)-To be performed once during outage for refueling.

5.Alternate EOC-To be performed once every other outage for refueling.

6.Five Years-To be performed once at the EOC occuring nearest to the end of a recurring 5-year period.7.As Required-To be performed as often as good maintenance, site proce-dures, manufacturer's recommendations, or experience dictate as determined by site personnel.

8.Maintenance

-Monitoring and/or surveillance on a periodic frequency to assure the component will perform its intended function in a safe reliable manner.9.Accessible

-Any item on which the required function can be performed without disassembly of an engine component.

Removal of defined access cover is not considered disassembly.

10.Appropriate NDE-Nondestructive examination selected by site personnel that is most suitable to obtain the information sought by an individual inspection item;choice of NDE shall be made to assure that the technique will detect indications consistent with the acceptance criteria.Revision 2 TABLE 1 Diesel Engine Operating Surveillance Parameters and Frequency Com onent 1)Lube Oil Inlet Pressure to Engine2)Lube Oil Filter Differential Pressure 3)Lube Oil Temperature (engine inlet and outlet)4)Lube Oil Sump Level 5)Turbocharger Oil Pressure 6)Fuel Oil Filter Differential Pressure 7)Fuel Oil to Engine Pressure 8)Fuel Oil Day Tank Level 9)Jacket Mater Pressure (engine inlet)10)Jacket Mater Temperature (in, out)11)Engine Cylinder Temperature Exhaust-All (If temperature in any one cylinder exceeds 1050', refer to MP-022/023 Item 7'.)12)Manifold Air Temperature (RB, LB for DSRV Engines)13)Manifold Air Pressure (RB, LB for DSRV Engines)14)Starting Air Pressure (RB, LB for DSRV Engines)15)Crankcase Vacuum 16)Engine Speed 17)Hour Meter Fre uenc Log hourly Log hourly Log hourly Log hourly Log hour ly Log hour ly Log hourly Check hourly Log hourly Log hourly Log hourly Log hourly Log hour ly Check hourly Log hourly Log hourly Log hourly I I-A-4 Revision 2 TABLE 1 (Cont')Diesel Engine Operating Surveillance Parameters and Frequency Com onent Fre uenc 18)Kilowatt Load 19)Visual Inspection for Leaks, etc.Log hourly Check hourly Revision 2 TABLE 2 Diesel Engine Standby Surveillance Parameters and Frequency Com onent 1)Lube Oil Temperature (in, out)2)Lube Oil Sump Level 3)Check Operation of Lube Oil Keep-Warm Pump Motor 4)Monitor Lube Oil Keep-Warm Strainer and/or Filter Differential Pressure Log daily Log daily Daily Daily Fre uenc 5)Perform a visual inspection for leakage of the Lube Oil Heat Exchanger.

Verify that no leakage through the leak-off ports of the lantern ring is present.6)Fuel Oil Day Tank Level 7)Jacket Water Temperature (in, out)8)Perform a visual inspection for leakage at packing for Jacket Water Heat Exchanger whenever the engine is in the emergency STANDBY mode.Verify that no leakage through the leak-off ports of the lantern ring is present.9)Governor Oil Level 10)Verify proper oil level of , generator pedestal bearing 11)Starting Air Pressure 12)Drain air receiver float traps and/or drain Starting Air Storage Tank and monitor the quantity of moisture produced.If quantity of moisture is excessive, correct immediately.

Daily Log daily Log daily Daily Daily Daily Log daily Daily II-A-6 Revision 2 TABLE 2 (Cont')Diesel Engine Standby Surveillance Parameters and Frequency Com onent Fre uenc 13)Check Operation of Compressor Air Traps 14)Test Annunciators 15)Check Alarm Clear 16)Inspect for Leaks 17)Visually inspect intercooler for external leaks including intake manifold drain connection.

Daily Before Engine Operation Before Engine Operation Dai ly Dai ly Revision 2 TDI OWNERS GROUP APPENDIX-II GENERIC MAINTENANCE MATRIX PART B PHASE I COMPONENTS 0

GENERIC MAINTENANCE MATRIX-PHASE I Component Component Number=Identification HP-022/23 Turbocharger PH Recommendation 1.Heasure vibration and check with baseline data.2.Inspect impeller/diffuser and clean if necessary.

3.Heasure rotor end play (axial clearance) to identify trends of increasing clearance i.e., thrust bearing degradation.

4.Perform visual and blue check inspections of the thrust bearing.5.Disassemble, inspect, and refurbish.

~Honth1 EOC Al t.EOC 5 Year Overhaul Comments To be accomplished during 24-hour test run.Review thrust bearing axial clearances after inspection to determine if a trend exists.Any trend toward increasing axial clearance could signify thrust bearing degradation.

Note: Thrust bearing inspection should also be performed after experiencing each 40 non-prelubed (automatic) fast starts.In addi-tion, a one time inspec-tion should be completed after the first 100 engine starts.Note: During reassembly ensure that capscrews are properly installed with the recommended torque.If IiR inspection was performed prior to accu-mulating significant hours (ip., the number of hours accumulated during plant preopera-tional testing, approxi-mately 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />), the turbochargers should be reinspected at the next EOC.II-B-l Revision 2 GENERIC MAINTENANCE MATRIX-PHASE I Component Number Component Identification PH Recoamendation 6.The nozzle ring com-ponents and inlet guide vanes should be visually inspected for missing parts or parts showing distress.If such conditions are noted, the entire ring assembly should be re-placed.7.Honitor inlet tempera-ture to ensure gas tem-perature does not exceed manufacturer's recom-mendation of 12004F if exhaust temperature for any cylinder exceeds 1050 F (Refr: Table 1).~Month1 EOC Al t.EOC 5 Year Overhaul Comaents Also perform a visual inspection on one turbo-charger per nuclear unit at each EOC.Note: Discontinue inspec-tion with appropriate re-design.Honitoring may be per-formed using permanent in-line thermocouple, strap-on thermocouple, heat gun, or other suit-able means, that has been appropriately tested and calibrated per plant pro-cedures.Note: Also perform mon-itoring any time the engine operates in an unbalanced condition.

02-305A Base Assembly 1.Perform a visual inspec-tion of the base.The inspection should include the areas adjacent to the nut pockets of each bear ing saddle and be con-ducted after a thorough wipe down of the surfaces, using good lighting.X Note: Any cracks detected must be investigated further before the engine is allowed to return to service.The mating sur faces of the base and cap shall be thoroughly cleaned with solvent before any reassembly.

Perform on EOC basis for 3 cycles, then overhaul provided there are satisfactory results.Note: 3 EOC inspections may be eliminated by per-forming a metal analysis to confirm consistent to class 40 grey iron requirements; performing analysis does not elimi-nate need for overhaul inspections.

I1-0-2 Revision 2 GENERIC MAINTENANCE HATRIX-PliASE I Component Number Component Identification PH Recommendation H~onthl EOC Al t.EOC 5 Year Overhaul Comments 02-305C Hain Bearing Caps-Studs and Nuts 02-310A Crankshaft 1.The mating surfaces at the bearing cap/saddle interface should be inspected when dis-assembled to ensure the absence of sur-face imperfections that might prevent tight boltup.Note: Upon removal of bearing caps, clean mating'urfaces with a solvent prior to reassembly of the caps to the base.See site specific recommendations 02-315A Cylinder Block See site specific recommendations 02-315C Cylinder Liners 02-340A/B Connecting Rods, Bushings and Bearing Shells (Generic)1.Perform a visual inspection of liners for progressive wear.1..Inspect and measure all connecting rod bearing shells to verify lube oil maintenance, which affects wear rate.To be performed for first 2 EOCs following piston removal;then discon-tinue until next piston removal.Boroscopic inspection is acceptable if heads are not removed.Complete TDI Inspection and Haintenance Record Form No.315-1-1 as applicable, TDI In-struction Hanual, Volume I, Section 6.X Complete TOI Inspection and Maintenance Record Form No.340-1-1 as applicable, TOI In-struction Hanual, Vol-ume I, Section 6, Appendix III for-clearance values.Perform inspection at 5 years, on items acces-sible, consistent with Item 2 of this compo-nent.II-B-3 Revision 2 GENERIC MAINTENANCE MATRIX-PHASE I Component Number Component Identification PM Recommendation

~Monthl fOC Al t.EOC 5 Year Overhaul Comments Inspect and measure the connecting rods.Note: Perform inspection and measure four connecting rods for OSRVs and two for OSRs at random at one time 5-year inspection.

Perform an x-ray examin" ation on all replacement bearing shells to acceptance criteria developed by Owners Group Technical Staff.All connecting rod bolts, nuts, and washers should be visually inspected, and damaged parts should be replaced.The bolts should be HT inspected to verify the continued absence of cracking.No detectable cracks should be allowed at the root of the threads.X Complete TOI Inspection Haintenance Record Form No.340-2-1,-2 as applicable, TOI In-struction Hanual, Volume I, Section 6.'his is to be performed prior to installation of any replacement bearing shells as required.X Perform inspection at 5 years, on items acces" sible, consistent with Item 2 of this component.02-340 A/B Connecting Rods, Bushings OSRV's and Bearing Shells only Ouring any disassembly that exposes the inside diameter of a rod-eye (piston pin)bushing, the surface of the bushing should be LP inspected to verify the continued absence of linear indications in the heavily-loaded zone width il5 degrees of the bottom dead-center position.Heasure the clearance between the link pin and link rod.This clearance should be zero i.e., no measurable clearance when the specified bolt torque of 1,050 ft-lbs is applied.Perform inspect>on, as required and on items accessible, consistent with Item 2 of this component.

To be performed once for each connecting rod.II-B-4 Revision 2 GENERIC MAINTENANCE MATRIX-PNASE I Component Number Component Identification PM Recommendation

~Hoolh1 EOC Al t.EOC 5 Year Overhaul Comments 7.At the overhaul, gisuaily inspect the rack teeth surfaces for signs of fretting and at one time 5-year inspection for rods disassembled.

Inspect mating surfaces to verify that the minimum manufacturers'ecommended percent contact surface is available.

To be performed once for new and/or re-placement parts.10.If connecting rod bolt.stretch was measured ultrasonically during reassembly following the preservice inspection, the lengths of the two pairs of bolts above the connecting rod should be remeasured ultrasonically before the link rod box is disassembled.

If ultrasonic measurement was not previously used, begin use at next inspection that accesses the connecting rods.Measure bolt stretch before disassembly.

All connecting rod bolts should be visually inspected for thread damage (galling)and the two pairs of connect-ing rod bolts above the crankpin should be MT inspec-ted to verify the absence of cracking.All washers used with the bolts should be examined visually for signs of galling or cracking and replaced if damaged.A visual inspection should be performed of all external surfaces of the link rod box to verify the absence of any signs of service-included distress.'

Also to be performed at any time the connect-ing rod, is disassembled.

Perform inspection at 5 years, on items accessible, consistent with Item 2 of this component.

X Also to be performed at any time the connect-ing rod is disassembled.

Perform inspection at 5 years, on items accessible, consistent with Item 2 of this component.

X Also to be performed at any time the connect-ing rod is disassembled.

Perform inspection at 5 years, on items accessible, consistent with Item 2 of this component.

11-8-5 Rev>s>on 2 GENERIC MAINIENANCE MATRIX-PHASE I Component Number Component Identification PM Recommendation

~Monthl EOC Al t.EOC 5 Year Overhaul Comments 12.All of the bolt holes in the link rod box should be inspected for thread damage (galling)or other signs of abnormalities.

Bolt holes subject to the highest stresses (the pair immediately above the crankpin)should be examined with an appropriate non-destructive method to verify the absence of cracking.Any indications should be recorded for evaluation and corrective action.Also to be performed at any time the connect-ing rod is disassembled.

Perform inspection at 5 years, on items accessible, consistent with Item 2 of this component.

02-341A Pistons 02-360A Cylinder Head l.Inspect and measure skirt and piston pin.This item assumes that AE skirts are installed.

For other types, see site-specific recommendations.

l.Visually inspect cylinder heads (all cylinders).

Note: Inspection by boroscope is acceptable.

2.Record cold compression pressures and maximum firing pressures.

Complete TDI Inspection and Haintenance Report Form No.341-l-l as applicable, TDI Instruction Hanual, Volume I, Section 6.Use Volume I, Section 8, Appendix III for clear-ance values.To be performed at 5-year interval on sampling basis consistent with Component 02-340A/8-Connecting Rods.Complete TDI Inspection and Maintenance Record Form No.360-1-1 as applicable, TDI Instruction Hanual, Volume I, Section 6-one sheet for each head.To be performed at 5-year interval on sam-pling basis consistent with Component 02-340 A/B-Connecting Rods.If so indicated-remove cylinder heads, grind valves, and reseat.Refr: TDI Instruction Hanual, Volume I, Section 6.I 1-8-6 Revision 2 GENERIC MAINTENANCE NATRIX-PHASE I Component Number Component Identification PH Recommendation 3.'low-over the engine at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> but not more than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after engine shutdown.The cylinder cocks should be open for detection of water leakage into the cylinders.

A second air roll should be performed in the same manner approximately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after engine shutdown.In addition, the engine should be air rolled shortly before any planned start.H~onthl EOC Al t.EOC 5 Year Overhaul Comments In the event water is detected, the cylinder head should be replaced or returned to the vendor for repair.Delete, post-run air roll requirements for engines with Group III heads after one cycle with positive inspection results.02-365C Fuel Injection Tubing 4.Visually inspect the area X around the fuel injection port on each cylinder head during the normal monthly run for signs of leakage.1.Check tubing for leaks X at compression fittings.2.Visually inspect tubing X lengths for fuel oil leaks or cracks if tubing is unshrouded.

If shrouded, fuel oil leakage can be detected at the leak-off ports in the base nuts, which are provided for this purpose.If water leakage is detected, the head(s)should be replaced.All fuel oil leak in-spections to be per-formed while the engine is running or whenever the compression fittings have been disturbed.

Fitting inspection for leaks to be performed at engine operation following shutdown.Subsequent inspections to be performed period-ically as indicated.

Unshrouded tubing, used as, replacement, should be fully inspected con-sistent with FaAA NDE Procedure 11.10 prior to bending.II-B-7 Revision 2 GENERIC HAINTENANCE HATRIX-PHASE I Component Number Component Identification PH Recommendation

~Honth1 EOC Al t.EOC 5 Year Overhaul Comments 02-390C Push Rods Each push rod of the forged-head design should be inspected by liquid penetrant prior to installation or, if installed, at each overhaul.This should be repeated, until it has been deter-mined by 750 hours0.00868 days <br />0.208 hours <br />0.00124 weeks <br />2.85375e-4 months <br /> of operation at the load level used for surveil-lance testing that the push rod will not develop service-induced cracks.Push rods confirmed in this way need be examined only visually at subsequent overhauls.

Push rods of the forged-head design exhibiting cracks larger than 0.25 inch should be replaced, preferably with push rods of the friction-welded design.Each forged-head rod should also be visually inspec-ted one time to confirm that the head was fully inserted in the tube prior to welding.Each push rod of the fric-'tion-welded design should be inspected initially by liquid penetrant.

If this initial inspection was not performed prior to placing the push rods in service, it should be performed at the first overhaul.If the friction-welded push rod has been previously in-spected by liquid pene-trant, then visual exami-nation will suffice for future inspections.

All friction-welded push':"is with cracks should bu replaced, preferably with push rods of the same design.X Ref r: PNL-5600 X Ref r: PNL-5600.If initial inspection was not performed, perform on sampling basis at 5-year inspection consistent with Component 340A/8-Connecting Rods II-8-8 Revision 2 GENFRIC MAINTENANCE MATRIX-PNASE I Component Number 02-390G Component Identification Rocker Arm Capscrews, Drive Studs (Pop Rivets)PM Recommendation Verify capscrew torque values during IlR inspec-tion.If not performed at IiR, verify at next EOC, then as required at reassembly.

Verify that rocker arm drive studs are intact and tight during IlR inspection or EOCl, then as required at reassembly.

H~onthl EOC Al t.EOC 5 Year Overhaul Comments-Use TDI Instruction Manual, Volume I, Section 8, Appendix IV for proper torque values.02-425A Jacket Mater Pump-Gear Visually inspect jacket water pump gear for chipped or broken teeth, excessive wear, pitting or other abnormal conditions.

Check the key to keyway interface for a tight fit on both the pump shaft to impeller and the spline to pump shaft.during pump reassembly.

At next teardown, verify impeller is one piece, (i.e., without a bore insert).If it is not a one piece impeller, replace.It is recommended that the castle nut that drives the external spline on its taper have minimum and max--imum torque values of 120 ft-lbs and 660 ft-lbs respectively for DSRVs and a maximum torque value of 77 ft-lbs for DSRs.Any abnormal situations or indications of pro-gressive pitting should be reported for an engineering evaluation.

For engines with less than 750 hours0.00868 days <br />0.208 hours <br />0.00124 weeks <br />2.85375e-4 months <br />, also inspect by EOC2.X This along with the drive fit of the impeller onto the shaft will preclude past problems where relative motion between shaft and impeller caused fretting and upset of the keyway sides.II-B-9 Revision 2 TDI OWNERS GROUP APPENDIX" II GENERIC MAINTENANCE MATRIX PART C PHASE II COMPONENTS

GENERIC HAINTENANCE MATRIX-PHASE II Component Component Number Identification PH Recommendation N~onthl EOC Alt.EOC 5 Year Overhaul Comments F-068 Intercool ers Record the following temperatures during the monthly surveillance test of the engine: exhaust from cylinders and jacket cooling water supply.Compare these results with similar data from previous month to establish whether the trend is sufficient to warrant further action.CP-101A Emergency Generator Inspect shell and tube sides, and clean as required.Verify intake manifold X drain connection is open and clean.Perform leakage test of water side boundary for gross degradation.

Check operation of brushes and slip rings by visual examination during operation.

Inspect at EOC1 and EOC3 to verify Item 1 results are valid.Note: Refer to TOI SIH to be issued subsequent to Harch 1986.Inspect all accessible parts of the generator, and clean as required.3.Hegger.rotor and stator.Verify that space heaters X are on with engine shutdown.Heasure vibration and check against baseline data.CP-101B Emergency Generator Pedestal Bearing Orain, flush, refill bearing housing.Heasure bearing hou;i>u insulation resistance.

II-C-1 Revision 2 GENERIC HAINIENANCE HAIRIX" PHASE II Component Component Number Identification PH Recommendation

~Mon lhl E0C Al t.EOC 5 Year Overhaul Comments CP-102 Emergency Generator Control Panel 3.Disassemble and inspect bearing and check c 1earances.

l.Inspect panel for cleanliness and clean as required.2.Check terminal boards for loose wiring.3.Visually check condition of wire insulation for degradation.

4.Clean and inspect relay contacts.5.Check meter calibrations.

6.Bridge recti fier assembly.a.Inspect the temperature X sensitive label placed on the most visible face of the hexagonal body of the diodes.The label shall be inspected before and after each running of the engine.To be performed per appropriate site intervals for similar equipment.

Note: Inspections may be deleted after modif>cat>ons as prescribed in DR/gR Report.If the label permanently blackens, the maximum temperature of the diode has been exceeded, requiring an electrical inspection of the diode and an inspection of the mounting threads of the heat sink and diode.Replace the diode and the heat sink as needed and assure that proper mounting tightness of 300 in-lbs and proper thread condition is maintained.

11-C-2 Revision 2

GENERIC HAINTENANCE HATRIX-PHASE II Component Number Component Identification PH Recommendation

~ttonthl EOC Al t.EOC 5 Year Overhaul Comments b.Inspect glyptol applied to the side of the lugs and mounting bolt for the lugs which attach to the bottom of the diode and SCR heatsinks for signs of relative motion.Retighten any loose connections, remove old glyptol, and reapply if connections are retightened.00-420 Lube Oil Pressure Regulating Valve 7.Adustment potentiometers-inspect glyptol applied to the the side of the adjustment screws for each of the five adjustment potentiometers on the printed circuit board of the voltage regulator for signs of relative motion.8.Printed circuit boards-check for cleanliness and proper mounting of components.

9.Implement a procedure to monitor generator voltage at start.A manual reset of the exciter must be performed in the event of a failed start.l.Disassemble and clean.2.Ouring initial startup after a major reassembly of lube oil piping, abnormal lube oil pressure excursions-should be investigated and remedial action taken until excursions subside.If adjustments are needed, remove glyptol, and reapply when the adjustment procedure is complete.Report any abnormal conditions to engineer-ing for evaluation.

This recommendation is required until such time that modifications are made to the time delay relay latching logic in the generator control.X If valve sticks repeat-edly, more frequent cleaning may be necessary.

If valve plugging becomes a prob-lem, the dimensions of the valves internal parts should be checked to ensure proper clearance.

II-C-3 Revision 2 GENERIC HAINTENANCE MATRIX-PHASE II Component Number 00-442A Component Identification Starting Air Distributor Assembly PH Recommendation l.Visually inspect the poppet valve spool ends and timing cam of the starting air distributor.

Ensure that the starting air manifold vent is open and unobstructed by noting the escape of air during engine startup.N~onlhl EOC Al t.EOC 5 Year Overhaul Comments Evaluate the degree of wear to determine whether existing condition would have an adverse effect on timing and the specified ability to start the engine.Note: Inspect at EOC1 for sites that did not perform IiR Inspection after plant pre-opera-tional testing.02-3078 Lube Oil Tubing and Fittings-Internal 1.Check accessible tubing for dents or crimps after performing main-tenance in that area.To be performed as required.02-310B Main Bearings Shells 1.Inspect and measure thickness of all main bearing shells.Inspection shall evaluate bearing wear and evidence of harmful crankshaft misalignment.

If results show evidence of mis-alignment, TOI recom-mendations for crankshaft realignment should be implemented.

Note: Perform inspec-tion on bearings 5 8 7 for DSRVs and mains between 5 8 6, and 6 6 7 for OSRs on one engine/station at EOC2.At one time 5-year in-spection, inspect bearings 3 through 8 inclusive.

Complete TOI Inspection and Haintenance Record Form No.310-2"1 as applicable, TOI Instruction Hanual, Volume I, Section 6-one sheet for each main bearing.Use Volume I, Appendix I'Il for clearance values.Also inspect when removed consistent with inspections required for Component 02-310A.II-C-4 Revision 2 GENERIC HAINIENANCE HATRIX-PHASE II Component Component Number Identification 02-310C Thr ust Bearing Ring PH Recommendation 1.Heasure thrust bearing ring clearance by"bump check" method to be performed in conjunction with crankshaft web deflection measurements.

The following information should be recorded:~Nonthl EOC Al t,.EOC 5 Year Overhaul Comments Complete applicable sections of TOI Inspection and Hain-tenance Record Form No.310-1-1 TDI Instruc" tion Hanual, Volume I, Section 6.02" 311A Crankcase Assembly Date of inspection Hours of engine operation'ours of engine operation since last bearing re-placement Bearing clearance 2.Visually inspect thrust bearing ring for signs of wear or degradation.

1.Perform a visual inspection of the vertical portion of the crankcase arch wall to the nut pocket area for indications of cracking.2.Remove alternate left side doors and examine the inside of the engine for any abnormal conditions.

Check with a good light for evidence of babbit flakes.Note.If the clearance>s greater than the maximum allowed in the TDI Instruction Hanual, at least one bearing must be replaced.Bearings should a)so be replaced if they are cracked or gouged.To be performed at 10-year interval only (i.e., not at one time 5-year inspection).

The first inspection after 185 hours0.00214 days <br />0.0514 hours <br />3.058862e-4 weeks <br />7.03925e-5 months <br /> of at.or near full load opera-tion may be used to justify the discontinua-tion of such inspection until an overhaul.For engines with less than 185 hours0.00214 days <br />0.0514 hours <br />3.058862e-4 weeks <br />7.03925e-5 months <br /> operation at or near full load, inspect at each EOC until exceeds 185 hours0.00214 days <br />0.0514 hours <br />3.058862e-4 weeks <br />7.03925e-5 months <br />.If excessive water, sludge or any indication of bearing failure is present, drain crankcase, deter-mine cause, and take necessary corrective action.3.Check internals of block and base for leaks.II-C-5 Revision 2 GENERIC HAINIENANCE MATRIX-PHASE II Component Number 02-317ALB Component Identification Water Discharge Hanifold-Jacket Water Discharge Piping, Couplings and Seals PH Recommendation l.Visually inspect for leaks.H~onthl EOC Al t.EOC 5 Year Overhaul Comments 02-3418 Piston Rings l.Inspect and measure piston replacement rings.Complete TDI Inspection and Haintenance Record Form No.341-2-1 as applicable, TDI Instruc-tion Hanual, Volume I, Section 6.Use Volume I, Section 8, Appendix III for clearance values.To be performed as required.02-341C Piston Pin Assembly l.Visually inspect for chrome plate damage.Replace pins which show chipped or blistered chrome.Note: All new or re-placement pins should be LP or HP inspected before installation in Owners Group engines.Also to be performed one time at the 5-year inspection on sampling basis consistent with Component 340A/8-Connecting Rods.Note: HT may cause FE particulate accumulation.

02-345A Intake and Exhaust Tappet Assembly 2.Inspect end plugs and reroll or replace any that are loose.l.Visually inspect intake and exhaust tappet assembly condition, and verify that cam rollers are free to rotate and that there is no noticeable clearance be-tween the cam rollers and the roller pins.Do this by manually checking for excessive motion and visually observing for abnormalities on the mat-ing surfaces.Note: This inspection is also to be performed one time at 5-year interval on sampling basis consistent with Component 340A/8-Connecting Rods.Complete TDI Inspection and Haintenance Report Form No.345-1-1 as applicable, TDI Instruc-tion Manual, Volume I, Section 6.Refr: TDI Instruction Hanual, Volume I, Haintenance Schedule.Perform an additional inspection by EOC2 on exposed or accessible assemblies.

Also perform one time at 5 years consistent with Component 02-340 A/8 Item 2.II-C-6 Revision 2 GENERIC MAINTENANCE MATRIX" PNASE 11 Component Component Hnahar Idantificatinn PM Recommendation

~Hantht EOC Al t.EOC 5 Year Overhaul Comments 02-3458 Fuel Tappet Assembly 02-350A Cam Shaft Assembly 02-350B Cam Shaft Bearings l.Visually inspect fuel tappet assembly condition, and verify that cern rollers are free to rotate and that there is no notice-able clearance between the cam rollers and the roller pins.Oo this by manually checking for excessive motion and visually observing for abnormalities on the mating surfaces.1.Perform a visual inspection of all cam lobe surfaces for signs of cracking, pitting, or spalling.l.Inspect and measure cam shaft bearing shells.Complete TOI Inspection and Maintenance Report Form No.345-1-1 as applicable, TOI Instruc-tion Manual, Volume I, Section 6.Also perform one time at 5 years consistent with Component 02-340 A/B Item 2.Per-form an additional in-spection by EOC2 on exposed or accessible assemblies.

Any signs of cracking, pitting, or spalling shall be followed by a detailed analysis to evaluate the expected life based on the size and extent of surface distress.Any corrective measures shall be implemented as indicated by this analysis.Signs of spalling shall result in immediate replacement of the cam.Perform an additional inspection by EOC2 on exposed or accessible assemblies.

Refr: TOI Instruction Manual, Volume I, Maintenance Schedule.Also to be performed one time at 5 years consistent with Com-ponent 02-340 A/B.Complete TOI Inspection and Maintenance Record Form No.350-l-l as applicable, TOI Instruc-tion Manual, Volume I, Section 6.Use Volume I, Section 8, Appendix Ill for clearance values.II-C-7 Revision 2 GENERIC HAINTENANCE HATRIX-PIIASE II Component Component Number Identification PH Recommendation

~ttontbl EOC Al t.EOC 5 Year Overhaul Comments 02-350C Cam Gear 02-355A Crank to Lube Oil Pump Gear 1.Visually inspect cam gear for chipped or broken teeth, pitting, excessive wear, or other abnormal conditions.

At this in-spection, the gear is in immediate proximity to the spray nozzle which should also be visually inspected.

2.Heasure gear backlash.Note: If cam gear hub is removed, it is recommended that the nut be relocked at the position corresponding to the torque of 70120 ft-lbs.Insertion of the cotter pin must be accomplished at a torque>50 ft lbs and<90 ft-lbs.If this is not possible, another bolt, nut or washer should be used.l.Visually inspect crank-shaft to lube oil pump gear for chipped or broken teeth, excessive wear, or progressive pitting or other abnormal conditions.

Also at one time 5-year inspection for Component 02-340A/8 measure clear-ances per TOI on one bearing housing/camshaft.

For engines with less than 750 hours0.00868 days <br />0.208 hours <br />0.00124 weeks <br />2.85375e-4 months <br />, also inspect at EOC2.Complete applicable sect>ons of TOI Inspec tion and Haintenance Record Form No.355-1-1, TOI Instruction Hanual Volume I, Section 8, Appendix 111-1 for clearance values Note: Refer to TOI SIH to be issued sub-sequent to Harch 1986.A)so to be performed one time at 5 years consistent with Com-ponent 02-340 A/8.Any abnormal situations or indications of progressive pitting should be reported for an engineering evaluation.

For engines with less than 750 hours0.00868 days <br />0.208 hours <br />0.00124 weeks <br />2.85375e-4 months <br />, also inspect by'EOC2.11-C-8 Revision 2 GENERIC MAINTENANCE MATRIX-PHASE II Component Number Component Identification PH Recommendation 2.Heasure gear backlash.5~anti>l EOC Al t.EOC 5 Year Overhaul Ceeeeeta X Complete applicable sections of TDI Inspection and Hain-tenance Record Form No.355-1-1, TOI Instruction Hanual, Volume I Section 6 Use Volume 1, Section 8, Appendix III-l for clearance values.02-355B Idler Gear Assembly 02-359 Air Start Valves 02-360B Cylinder Head-Intake and Exhaust Valves l.Visually inspect idler gears for chipped or broken teeth, excessive wear pitting, or other abnormal conditions.

2.Heasure gear backlash.Note: If idler gear hub is removed, it is recom-mended that the nut be relocked at the position corresponding to the torque of 70120 ft-lbs.Insertion of the cotter pin must be accomplished at a torque>50 ft-lbs and<90 ft-Tbs.If this is not possible, another bolt, nut, or washer should be used.Remove, clean, and inspect air start valves.(Re-place copper valve-to-head gasket).2.Inspect the piston, cap, guide, and housing sliding surfaces to evaluate.wear or corrosion.

l.Visually inspect.intake and exhaust valves, keepers, stems and seats for 5 ire drawing, pitting, d>>tE r-tion, concentricity, and any abnormal condition.

Any abnormal indications should be reported for an engineering evaluation.

For engines with less than 750 hours0.00868 days <br />0.208 hours <br />0.00124 weeks <br />2.85375e-4 months <br />, also inspect at EOC2.X Complete applicable sections of TOI Inspec-tion and Haintenance Record Form No.355-1-1, TDI Manual, Volume I, Section 6.Use Volume I, Section 8, Appendix III-l for clearance values.Ensure valve>nstallat>on includes retorque re-quirements.

Refr.: TOI SIH 360.Also to be performed one time at 5 years on sam-pling basis consistent with Component 340A/B.II-C-9 Revision 2

GENERIC MAINTENANCE MATRIX-PHASE II Component Number 02-362A Component Identification Cylinder tiead Covers-Subcover Assembly h~onthl PH Recommendation 2.Visually inspect subcovers ,for evidence of valve guide blowby (soot).3.Measure intake and ex-haust valves head thickness.

4.Heasure intake and exhaust valves-valve-to-guide clearances.

II-C-10 1.Perform a liquid penetrant examination of the rocker arm pedestals top and vertical machined sur-faces (connector push-rod side only).EOC Al t.OOC 5 Year Overhaul Ceeeente This is a one-time-only inspection, to be performed after 500 or 600 hours0.00694 days <br />0.167 hours <br />9.920635e-4 weeks <br />2.283e-4 months <br /> of operation after rebuild of a cylinder head.Complete applicable sections of TOI Inspection and Hain-tenance Records Form 360-2-1, TOI Instruc-tion Hanual, Volume I, Section 6-one sheet for each cylinder.Use Section 8, Appendix III for clearance values.(Items 2 f 3).Also to be perfomed one time at 5 years on sampling basis consis-tent with Component 340A/B.Complete applicable sections of TOI Inspection and Hain-tenance Record Form 360-2-1, TOI Instruction Manual, Volume I, Section 5-one sheet for each cylinder.Use TOI SIH 336, Rev.1 for clear-ance values (acceptance criteria).

Also to be performed one time at 5 years on sampling basis consistent with Component 340A/B.Also to be performed one time at 5 years on a sampling basis con-sistent with Component 340A/B.Subcovers with pedestal cracks that extend through the counter bore web down to the threads should be replaced.Refr: OR/QR Report 802-362A.Revision 2 GENERIC HAINTENANCE MATRIX" PIIASE II Component Number 02-365A Component Identification Fuel Injection Pumps PH Recommendation 1.Tear down one pump for inspection.

2.Visually check pressure bleed screw for erosion on disassembled pump.H~onlhl fOC Al t.EOC 5 Year Overhaul Comments Use repr esentative pump to determine need to overhaul other pumps.Complete fuel injection pump inspection in accordance with TDI Instruction and Main-tenance Manual, Volume I, Section 6.Based on inspection results and operating parameters.

Complete TDI Instruction and Haintenance Record Form No.365-1-1 as applicable, for the pump disassembled.

02-365B Fuel Injection Nozzles 1.Remove, inspect, and clean tips.2.Check nozzle pop pressure.3.Check spray pattern.Ensure that a new copper gasket is used upon reinstallation of nozzle into head.Perform retorque requirement per TDI.Complete TDI Inspec-tion and Haintenance Record Form 365-2-1 as applicable, Instruction Hanual, Volume I, Section 6.Note: 135 fuel oil tips may be used if inspection results indicate a need for additional action to improve lubrication and reduce coke buildup.II-C-11 Revision 2 GENERIC HAINTENANCE HATRIX-PHASE Il Component Number Component Identification PH Recoaeendation n~ontnl EOC Al t.EOC 5 Year Ooernaol Connenta 02-3650 Fuel Oil Injection Lines: Supports 02-371A Fuel Pump Control Shaft 02-3718 Fuel Pump Linkage Assembly and Bearings 02-380A Exhaust Hanifold l.Visually inspect support elastomer inserts for deterioration or degrada-tion.1.Check and lubricate as required.1.Grease swivel link or otherwise lubricate all fuel oil pump assemblies.

1.Perform a visual examination of accessible pipe welds and corresponding heat-affected zones.Any inserts found to be unsatisfactory shall be replaced with new inserts prior to reassembly of fuel oil lines.This inspection can be per-formed prior to reassembly of the fuel oil lines in conjunction with the cylinder liner inspection.

To be performed at EOCl and alternate EOCs thereafter.

02-385A Crankcase Relief Valve 02-387A Crankcase Vacuum Fan 02-390E Rocker Arm Bushings 1.Clean flame arrestors.

2.Inspect seat and disc.l.Inspect fan and clean as necessary.

2.Check bearing for roughness.

l.Visually inspect and measure intake rocker arm bushings.2.Visually inspect and measure exhaust rocker arm bushings.3.Visually inspect and measure intermediate rocker arm bushings.X Also to be performed one time at 5 years on sampling basis con-sistent with Component 340A/B.X Also to be performed one time at 5 years on sampling basis con-sistent with Component 340A/B.X Also to be performed one time at 5 years on sampling basis consist-ent with Component 340A/8.II-C-12 Revision 2 GENERIC HAINTENANCE HATRIX-PHASE II Component Component Number Identification 02-390F Hydraulic Valve Lifters 02-410A Overspeed Trip Governor PH Recommendation 1.Check and adjust valve lash.2.Reinstall and adjust lifters.1.Check trip set point-ad3ust as required.~Hant hl E0C Al t.EOC 5 Year Overhaul Comments Also to be performed one time at EOC2 and at 5 years on a sampling basis consistent with Component 340A/B.Note: Ensure lifters are installed with the fill holes up.Verify condi-tion of lifters by com-parisonn of lifter leak" down rate (actual)to specifications noted on TDI Haintenance Hanual.Refr: TOI Haintenance Manual, Section 6-8-5.Hodify the surveillance testing procedure to include ver>fscat>on that the overspeed trip is correctly set to an overspeed trip setting of 517 a 5 rpm.Ensure that the electric governor setting is properly re-.turned to 450 rpm and the mechanical backup governor returned to the manu-facturer's specified interval following the overspeed test.The test is to be performed with no load on the engine by increasing the normal governor speed setting(s) until a trip occurs.After several inspection periods, the history of the required adjustments should be reviewed to evaluate and possibly modify the testing in-terval.Also perform at EOC2.II-C-13 Revision 2 GENERIC MAINTENANCE MATRIX-PNASE II Component Number Component Identification PM Recommendation

~Mon th)E0C Al t.EOC 5 Year Overhaul Comments Note: After setting the overspeed governor, the adjustment screw settings should be marked with Torque Seal or other positive means to reveal any unintended changes in the set positions.

02-4100 Overspeed Trip Governor and Accessory Drive 1.Remove plugs from housing and check for magnetic particles.

2.Check shafts for excessive radial and axial movement.3.Visually inspect accessory drive gear for excessive wear.02-410C Overspeed Trip Drive Couplings 1.Remove the present L-110 Lovejoy couplings in compliance with SIM 363.2.Verify that coupling is tight on shaft.3.Replace the Lovejoy coup-ling spiders or test coup-ling elastomer for hardness.To be completed by the first refueling outage.Replace elastomer if hardness is greater than 90 Shore A.02-4100 Overspeed Trip Vent Valve 02-411A Governor Drive-Governor and Tachometer Drive Gear and Shaft 02-411B Governor Drive-Couplings, (excluding Pins and Keys San Onofre-See Site Specific for San Onofre)l.Disassemble and replace"0" rings or replace valve.1.Visually inspect drive gear and shaft for signs of wear.1.Check that coupling is tight on shaft.X Also inspect one time at EOC nearest 5 years.For engine with less than 750 hours0.00868 days <br />0.208 hours <br />0.00124 weeks <br />2.85375e-4 months <br />, also inspect at EOC2.If the coupling is found to be loose, it should be removed, all mating surfaces cleaned, and the unit reassembled using Loctite 609 on the mating surfaces.II-C-14 Revision 2 GENERIC HAINTENANCE HATRIX-PHASE II Component Number Component Identification PH Recommendation 2.Replace the elastomeric insert in the Koppers coupling.~Honthl EOC Al t.EOC 5 Year Overhaul Comments 02-413A Governor Linkage 02-413A Governor Linkage (OSRVs only)l.Install positive locking hardware to the lever arm clamp bolt heads and shaft roll pins.2.Inspect for loose parts on the linkage assembly.3.Lubricate cross shaft bearings as required.4.Grease the rod end fittings, or lubricate oil wicks, especially those at the ends of the cross shaft.Note: To be performed as necessary after tightening governor linkage hardware to design torque specifications.

02-413B Fuel Pump Linkage: Automatic Shutdown Cy)inder 02-415A Woodward Governor 1.Check cylinder for extension and return.2.Check tai lrod vent for air leakage.l.Orain, flush, refill, and vent actuator oil system with new oil from a clean container ensuring the appropriate cleanliness procedures are followed.If contaminated oil is noted, increase frequency.

2.Disassemble, clean, and refurbish the actuator.To be accomplished when placing unit in main-tenance modes.To be accomplished during controls system check.Note: Ensure the hy-draulic actuator is pro-perly vented.3.Veri fy all governor control knob settings are in appropriate positions.

Note: Hechanical governor setting to be 470 rpm.II-C-15 Revision 2 GENERIC MAINTENANCE MATRIX-PHASE II Component Number Component Identification PM RecoEENEendation O~onthl EOC Al t.EOC 5 Year Oreraael Coeeeele 02-4158 Governor Booster Servomotor 02-415C Governor Heat Exchanger 02-435A'acket Water Fittings-Pipe and Fittings (Smail Bore Scope Only)Evaluate electric governor settings to verify overshoot of the 450 rpm set speed.is within plant-specific guidelines and to avoid critical speeds during start or when unl oa ded.Clean, inspect, and replace"0!'ings and gaskets.Clean and inspect.Visually inspect for leaks.An evaluation of the governor settings is to be performed during surveillance testing once under joint mechanical and electrical governor control.02-437 02-4418 Turbo Water Piping-Pipe and Fittings Air Filter to Starting Air Distributor Air Start Admission Valve Strainer Air Start Block Valves Visually inspect for leaks.Replace filter elements.If filter in a metal screen, cleaning with solvent is acceptable in lieu of replacement.

Clean and inspect strainer.Clean and refurbish valves-replace"0" rings and clean the screened fitting.Ensure leak tightness after reassembly.

Inspect for tightness of fittings and bolts and apply locking com-pound as required during reassembly of components.

Replace"0" rings of the shuttle valve.II-C-16 This can be modified so that the filter is to be changed at a maximum pressure drop of 25 psi for engines equipped with pressure monitoring devices.If the strainer is excessively dirty, the frequency of cleaning and inspecting should be increased.

Revision 2 GENERIC HAINTENANCE HATRIX-PHASE II Component Number 02-455A Component Identification Fuel Oil Filter PH Recommendation 1.Record filter differ-ential pressure.2.Inspect canister gaskets and replace as required.3.Inspect tubing and me-chanical connections for tightness and/or leaks.h~eathl EOC Al t.EOC 5 Year Overhaul Caeveeate Change filter elements when filter differeritiai pressure reaches 20 psid rise above the clean differential pressure.Purge entrapped air from the filter canister using the vent valve provided, and divert some fuel o'il into the newly replaced cartridge.

After air has been purged, close vent valve and return handle to pre-vious operating position.To be performed during change out of filter elements.Refr TDI Instruction Hanual, Volume I.02-455B Fuel Oil Strainers 1.Record strainer differ-X ential pressure or monitor supervisory alarm as applicable.

2.Purge air from stand-by strainers.

If greater than 5 psid-shift, clean element.Bolt torques of 120-150 in-lbs should be uti-lized during reassembly.

As required.02-467A 02-475A,C Turbocharger Lube Oil Fitting: Pipe, Tubing, Fittings, and Flexible Coupling (Small Bore Scope Only)Turbocharger:

Bracket Bol ting and Gaskets l.Visually inspect for leaks.X l.At each engine shutdown for the first three engine shut-downs of operation after turbo installation, these screws should be visually inspected to assure that no screw has loosened because of engine operating loads.If during these inspections none of the screws are found loosened or damaged, future II-C-I7 Revision 2 GENERIC MAINTENANCE MATRIX-PNASE Il Component Number Component Identification PM Recommendation M~onthl EOC Al t.EOC 5 5Yaa Overhaul Comments inspections are to be con" ducted on a yearly basis (or during plant shutdown).

But if any time during inspection any screw is found loosened or damaged, it must then be replaced (if damaged)and all screws retorqued as follows: 125 ft-lbs for the bracket-to-engine screws and 75 ft-lbs for the bracket-to-turbo base screws.02-4758 Air Butterfly Valve 02-500A Engine Control Cabinet Note: To avoid damage to bracket to engine, and/or bracket to turbo, the pro-per torques as delineated above should be utilized for each respective bracket bolting application.

Lubricate valve shaft via grease fittings.Check valve disc for freedom of movement.Verify that associated locking devices (jam nuts and lock washers)are tight.Inspect interior of cabinet for cleanliness, and clean as required.If oil cups are used, lubricate shaft monthly.Check by visually observ-ing valve/actuator oper-ation.If oil cups are used, this should be completed monthly.Visually check wiring for insulation degradation.

Visually check instrument tubing for leaks.Functionally check cabinet heater and calibration of thermostat.

II-C-18 Revision 2 GENERIC MAINTENANCE MATRIX-PNASE II Component Number Component Identification PM Recommendation H~onthl EOC Al t.EOC a Year Overhaul Coavaento 5.Replace"0" rings, gaskets, and filter in pressure regulator as required.6.Inspect filter surface for matter to determine if problems may exist down-stream.02-500C Circuit Breakers and Contact Blocks 7.Monitor control system air X pressure or supervisory alarm as applicable.

1.Check all terminals-clean and tighten.2.Visually check wiring insulation for degradation.

Accomplished during panel cleaning and inspection.

Accomplished during panel cleaning and inspection.

02-SOOG Control Panel Valves 3.Trip check circuit breakers.l.Inspect control panel valves for leaks.To be performed at appropriate site intervals for similar equipment.

02-500J Control Panel Assembly: Relays 2.Replace or refurbish pneumatic logic board.1.Inspect contacts and clean as required.02-SOON Control Panel Switches Terminal Boards and Miring 2.Visually check condition of wiring and tightness of terminations.

1.Clean terminal boards and switch contacts.2.Visually check wire insu-lation and terminals for tightness and degradation.

3.Inspect for arcing and overheating.

II-C-19 Revision 2 GENERIC MAINTENANCE MATRIX-PHASE I I Component Number 02-5258 Component Identification Barring Device Control Valve and Press Regulator PH Recommendation 1.Replace control valve"0" rings and lube shaft.2.Replace press regulator elastomeric parts.~Mont.hl EOC Al t.EOC 5 Year Overhaul Comments As required.As required.02-525C Barring Device Air Filter 02-5250 Barring Device-Mounting Bracket/Supports 02-540A Lube Oil Sump Tank 1.Replace filter element.2.Drain barring device air filter.1.Replace old cotter pin with new cotter pin after each reassembly.

1.Check lubricating oil with a viscosi-meter for fuel oil dilution.Send a sample of oil to laboratory for analysis.As required.As required.To be performed after each reassembly.

Ref r: TDI Instruction Manual, Volume I, Haintenance Schedule, Items 1, 2.2.Drain lubricating oil system and clean sump tank.Refill with new oil.To be performed based on sample analysis.Note: When replacing eng-ine oil use ND oil that meets or exceeds series 3 standards.

The base stock should be more resistant to thermal degradation and coke formation.

The additive package should provide high Qetergent dispersant properties with high alkalinity and a high level of antiwear additive such as zinc dithiophosphate.

Total Base Number (TBN)should be 12 to 15 for use with N2 fuel, oil and a sulfated ash content of 1.5X to 2.0X is preferred.

An engine oil with such properties, Hobi lguard 412 or equiv-alent product may be used to insure improved lubri-cation.Do not mix lube oil brands or types.When changing lube oil replace the entire charge.Re-place as required.II-C-20 Revision 2

GENERIC MAINTENANCE MATRIX-PMASE II Component Number Component Identification PM Recommendation Visually inspect lube oil sump tank level switch floats.Check switch set points.~hentht EOC Al t.EOC 5 Year Overhaul Ceeeeente To be performed per appropriate site intervals for similar equipment.

Perform a spectro-chemical engine oil analysis to assist the bearing monitoring program.To further expand or clarify chemical analysis, ferrographic analysis may be utilized.Particular attention shall be paid to copper level and particulate size, which could signify thrust bearing degradation.

Particular attention shall be given to percent mois-ture content.Note: Sample to be drawn upstream of lube oil filter.Items 1 and 4 can be performed using the same sample.02-550 Foundation Bolts Visually inspect founda-tion for breaks in the bond between the sole plates and grout.02-6300 Thermocoupl es Check foundation bolts for correct torque.Retorque as necessary, then recheck crankshaft web deflections.

Generator foundation bolts are to be retorqued after a generator short circuit if the bolts were initially torqued to 480 ft-lbs.If initial bolt torque was 600 ft-lbs, no retorque is required.Check that thermocouple indicates ambient engine temperature when the engine is cold.X Use TDI Instruction Manual, Volume I, Section 8 Appendix IV for proper torque values.An inconsistent reading traced to thermocouple trouble should result in replacement of the thermocouple.

II-C-21 Revision 2

GENERIC MAINTENANCE MATRIX-PNASE II Component Component Number Identification 02-6958 Engine Control Air Pressure Regulator PM Recommendation Clean and inspect thermocouples and thermocouple shields as required.Pyrometer wiring-check that terminations are tight.Inspect and clean engine control air pressure regulator when pressure gauge indicates abnormal pressure reduction during normal engine shutdown.H~onthl EOC Al t.OOC 5 Year Oeerhael Ceeeaente Indications of fatigue should result in re-placement of the thermo-couple and/or thermo-couple shield.To be accomplished dur-ing control panel check-out and initial operation inspections.

Note: This recommenda-tion should be reassessed depending on the degree of system fouling.02-695C 02-7008 02-700F Engine Control Pneumatic Trip Switches Jacket Water Standpipe:

Valves Jacket Water Standpipe and Hiscellanenous Bolting Replace elastomeric parts and gaskets in the pressure regulator.

Check switch set points per appropriate site interval.Replace elastomeric parts.Replace elastomeric parts in valves.Visually check jacket water standpipe, pump suction and engine return nozzle welds during each routine engine run and every 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> during extended engine runs.Check treatment (ph, etc.as applicable) of jacket water and correct as recommended by chem-ical supplier.As required.Pressure switches and temperature switches.As required.As required.Any visible cracking or minor jacket water leakage should result in rework of cracked nozzle welds.Also to be performed after adding makeup water.02-717B Auxiliary Sub-Base and Oil 8 Water Piping-Jacket Water: Valves Inspect the valves for packing leakage.Replace packing as necessary.

II-C-22 Revision 2 GENERIC HAINIENANCE HA'IRIX-PHASE II Component Number Component Identification PH Recomnendation

~Honthl EOC Al t.EOC 5 Year Overhaul Comments 02-717C 02-717F 02-717G/K Auxiliary Sub-Base and Oil 8 Water Piping-Jacket Water: Pipe, Couplings, Fittings Orifices, Y-Strainers (Small Bore Scope Only)Auxiliary Sub-Base Lube Oil Pipe and Fittings Auxiliary Sub-Base Lube Oil/Fuel Oil Valves Visually inspect for leaks.X Visually inspect pipe and joints for leakage.Clean and inspect lube oil keep-warm pump suction strainer as required.Disassemble, inspect, and refurbish off engine lube oil and fuel oil valves as required.Check relief valve lift pressure.Dis-assemble and clean if necessary.

Complete when lube oil tank is drained.02-805B Intake Air Filters 02-8050 Flex Connection (Exhaust)Inspect air intake/oil bath filters every 3 to 6 months.Visually inspect for evidence of cuts, holes, or dents.Replace with change oil if necessary.

If samp-ling is utilized, change based on analysis re-sults.02-810C Jacket Water Heat Exchanger Visually check for evidence of exhaust leakage.To avoid corrosion and fouling, jacket water heat exchanger and associated service water piping should be flushed on a periodic basis (continuous service flow is sufficient).

Alternatively, servic., water chemistry contiol can be used to maintain heat exchanger performance and integrity.

II-C-23 Revision 2

GENERIC HAINTENANCE MATRIX-PHASE II Component Number Component Identification PH Recommendation 2.Record heat exchanger parameters.

3.Evaluate heat exchanger performance data.4.Inspect tubes and tube sheet for fouling and erosion-remove en-trance and exit channel covers as required by trend data or at over-haul.Also review consistent with in-spections of other plant heat exchangers utilizing similar water chemistry.

5.Inspect and clean lantern ring as required.Verify leak-off holes are not plugged.6.Replace packing rings as required.~Honthl EOC Al t.EOC 5 Year Overhaul Ceenente Use for trend data.X Refr: TOI Instruction Hanual, Volume I, Haintenance Schedule.Replace or rework lantern ring as necessary to ensure concentricity prior to reinstalla-t,ion.Replace packing when packing becomes hard or leakage at the packing is noted and cannot be stopped by tightening.

02-8100 Thermostatic Valves 02-810E Jacket Mater Heaters 1.Replace thermal power elements as required.2.Visually inspect valve X bonnet for evidence of leakage.1.Check calibration and inspect thermostat.

To be accomplished during monthly test run.Ensure that any replacement valves have cast steel valve bodies.To be performed at appropriate plant interval for similar equipment.

Replace heater if degradation of insulation resistance is noted.II-C-24 Revision 2 GENERIC HAINTENANCE MATRIX-PHASE II Component Number 02-820A Component Identification Lube Oil Sump Tank Heaters PH Recommendation l.Inspect and clean heater elements as required by trend data.2.Check calibration and inspect condition of thermostat.

N~onl,hl EOC Al t.EOC 5 Year Overhaul Commenta Replace heater if de gradation of insulation resistance is noted.To be performed at appropriate site intervals for similar equipment.

02-820C Lube Oil Keep-Warm Pump 1.Check mechanical seal and piping connection for leakage.2.Verify pump discharge pressure is within manufacturer's specifi-cation.Use for trend data.02-8200 Lube Oil Keep-Warm Strainer 1.Clean or replace strainer element when the differential pressure change at the lube oil keep-warm strainer is 20 psid or for those plants not having this capability, clean or re-place when differential pressure of keep warm filter is 20 psid.02-820E Lube Oil Keep-Warm Filter 1.Record filter dif ferential X pressure.02-820F Full Flow Lube Oil Filters 2.Change filter elements as required.1.Record f il ter di f ferential X pressure.2.Replace filter cartridges and perform a visual inspection to determine nature of the material caught in the filter.To be performed when the filter differential pressure reaches 20 psid.For sites not equipped with differ-ential pressure gauge, inspect monthly and clean as necessary.

Use for trend data.Refr: TOI Instruction Hanual, Volume I, Haintenance Schedule.To be performed when the filter differential pressure reaches 20 psid.11-C-25 Revision 2 GENERIC HAINTENANCE HATRIX-PHASE II Component Number Component Identification PH Recommendation 3.Lube oil filter gauge-calibration check.H~anthl EOC Al t."EOC 5 Year Overhaul Comments To be performed at appropriate site intervals for similar equipment.

02-820G Lube Oil Meat Exchanger 1.Record heat exchanger parameters.

2.Evaluate heat exchanger performance data.3.Inspect tubes and tube sheet.X Use for trend data.X Refr: TOI Instruction Hanual, Volume I, Maintenance Schedule.02-820M 4.Inspect and clean lantern ring as required.Verify leak-off holes are not plugged.5.Replace packing rings at the floating tube sheet during reassembly.

Full Pressure Lube Oil Strainer 1.Monitor differential pressure of strainer and/or filter.2.Clean or replace strainer element when the differ-ential pressure change at the lube oil strainer is 20 psid.For those plants not having this capability, clean or replace when differential pressure of full pressure filter is 20 psid.3.Lube oil strainer pressure gauge-calibration check.Replace or rework lantern ring as necessary to ensure concentricity.

When packing becomes hard or leakage at the packing is noted and cannot be stopped by tightening.

Use for trend data.To be performed when the differential pressure across the strainer is-20 psid.Refr.TOI Instruction Hanual, Volume I, Haintenance'chedule.

To be performed per appropriate site intervals for s>m>1ar equ>pment II-C-26 Revision 2 GENERIC MAINTENANCE MATRIX-PHASE 11 Component Number Component Identification PM Recommendation

~hootht EOC Alt.EOC 5 Year Overhaul Coeeeota 02-8358 Diesel Starting Air Compressors 1.Check oil pressure and X oil level if compressor is so equipped.2.Overall visual inspection.

3.Clean fins on intercoolers and aftercoolers.

4.Inspect intake filter element if equipped and replace as neces-sary.5.Change compressor oil at each EOC, or if monthly sampling is performed change as required based on results.6.Check belt tension.02-8351 Air Dryers and Moisture Traps 02-835J Starting Air Storage , Tank 7.Check pulley clamp bolts and set screws tight.8.Inspect filter felts on unloader system.l.Inspect and service moisture traps.2.Check proper operation of dryer.1.Disassemble and clean the float trap if installed.

Replace as required, if so equipped.Replace desiccant charge or refrigerant as re-quired.11-C-27 Revision 2 GENERIC HAINTENANCE MATRIX-PHASE II Component Number Component Identification PH Recommendation H~onthl EOC Al t.EOC 5 Year Overhaul Comments Piping System (For items not previously covered)2.Starting air tank pressure gauges-calibration check.3.Starting air tank pressure switches-calibration check.1.Conduct a detailed vis-X ual and audible inspec-tion of all fuel, air, oil, and water piping and valves for leakage.To be performed per appropriate site intervals for similar equipment.

To be performed per appropriate site intervals for similar equipment.

Tighten, repair, or replace as required.Refr: TOI Instruction Hanual, Volume I, Haintenance Schedule.II-C-28 Revision 2 TDI OWNERS GROUP APPENDIX" I I SITE SPECIFIC MAINTENANCE MATRIX PART 0 SITE-SPECIFIC HAINTENANCE HATRIX Component Number 02-310A (Shearon)Harris)Component Identification Crankshaf t PH Recommendation 1.Heasure and record crank-shaft web deflections (hot and cold).Alt.H~anthl'OC EOC 5 Year Overhaul Caanenta Complete TOI Inspection and Haintenance Record Form No.310-1-1 as applicable, TOI Instruc-tion Hanual, Volume I, Section 6.Refr: TOI Instruction Manual, Volume 1, Haintenance Schedule.2.Examine the fillets and oil holes of three main bearing journals (4,6,h 8)using LP.If indications are evident, a more~thorough examination should be made using appropriate NOE methods.Also to be performed once at 5 years.Refr: PNL-5600.3.Examine the fillets and oil holes in three of the crankpin journals (choose 3 from Nos.3 through 8 inclusive) using LP.If indications are evident, a more thorough examina-tion should be made using appropriate NDE methods.4.Heasure diameter of crank-pin journals.Also to be performed once at 5 years.Refr: PNL-5600.X Complete TOI Inspection and Maintenance Record Form No.310-3-1 as applicable, TDI Instruc-tion Hanual, Volume I,.Sect i on 6.Also perform inspection at 5 years, on items accessible, consistent with this component and Component 02-340A/B.

I I-D-SH1 Revision 2 SITE-SPECIFIC HAINTENANCE HATRIX Component Number Component Identification PH Recommendation 5.Analyze the trends of cylinder pressure and temperature measurements to detect imbalances.

Note: To avoid the effects of the 4th order resonance, steady normal-loaded operation at speeds more than a few rpm below the rated speed~of 450 rpm should be'voided.

Appropriate precautions should be taken to prevent sus-tained engine operation with significant cylinder imbalance.

Lower speeds for testing and break-in are permissible.

Avoid resonance frequencies.

n~onthl EOC Al t.EOC 5 Year Overhaul Comments If an engine operates in a~eeuerel unbalanced conditzon, reinspect the oil holes for fatigue cracks within a time-frame determined by the utility considering the particular circumstances of the abnormal operation.

Refr: PNL"5600.Refr: PNL-5600.I I-D-SN2 Revision 2 SITE-SPECIFIC HAINTENANCE HATRIX Component Number 02-315A (Shearon Harris)Component Identification Cylinder Block PM Recommendation 1.Perform inspections per DR/gR Report 02-315A.2.Perform visual inspection for cracks.Note: Visual inspection not required if an appro-priate NDE is performed.

Al t.~Ho otal EOC EOC 5 5ataer Overhaul Cuneate I I-D-SII3 Revision 2 TDI OWNERS GROUP APPENDIX-II CROSS REFERENCE INDEX BY COMPONENT'ART E~Le end 1.Index sorted by component name.2.Component number listed or"nonum" indicates that the utility engine should perform the maintenance as described.

3.Blank indicates that utility is not required to perform maintenance indicated.

4.Maintenance or surveillance requirements for a'subcomponent should be disregarded for those engines not equipped with the subcomponent.

TDI COMPONENT NUMBER CROSS REFERENCE COMPONENT DESCRIPTION Air Butterfly Valve COMANCHE PEAK/SHOREHAM 02-475B/03-475B Air Filter to Starting Air Distributor Air Start Block Valves Air Start Valves, Auxiliary Sub-Base L Oil 8 Water Piping-Jacket Water: Pipe, Couplings, Fit-tings, Orifices, Y-Strainers (Small Bore Scope Only)02-441B/03-4418 NONUM/03-4418 02-359/03-359 02-717C/03-717C Air Dryers and Moisture Traps 02-835I/03-835H RANCfln SECO/SAN ONOFRE 03-475B/02-475B 03-835H/02-835F 03-441B/02-441B NONUM/NONUM 03-359/02-359 03-717D/02-717C PERRY/VOGTLE 02-475B/02-475B 02-835A/02-835G 02-441B/02-441B NONUM/NONUM 02-359/02-359 02-717C/02-717C RIVER BEND/GRAND GULF 03-475B/02-475B 03-835I/GG-115 03-441B/02-441B NONUM/NONUM 03-359/02-359 03-717D/02-717C CATAWBA/BELLEFONTE 02-475B/02-475B 02-835A/02-835C 02-441B/02-441B NONUM/NONUM 02-359/02-359 WNP-1/SHEARON HARRIS 02-475B/02-475B 02-835G/02-835C 02-441B/02-441B NONUM/NONUM 02-359/02-359 02-717C/02-717D Auxiliary Sub-Base 8 Oil L Water Piping-Jacket Water: Valves 02-717B/03-717B 03-717 B/02-717B 02-717B/02-717B 03-717B/02-717B 02-717B/02-717B 02-717B/02-717B Auxiliary Sub-Base Lube Oil Pipe and Fittings Auxiliary Sub-Base Lube Oil/Fuel Oil Valves 02-717F/03-717H 02-717G/K/

03-717I/N 03-717H/02-717F 03-717I/N/

02-717G/K 02-717F/02-717F 02-717G/K/

02-717G 03-717H/02-717F 03-717H/N/

02-717G/K NONUM/02-717F 02-717F/02-717H NONUM/02-717G/K/

02-717G/K 02-717 I TDI COMPONENT NUMBER CROSS REFERENCE COMPONENT DESCRIPTION Barring Device Air Filter COMANCHE PEAK/SHOREHAM 02-525C RANCHO SECO/SAN ONOFRE 03-525C PERRY/VOGTLE RIVER BEND/GRAND GULF WNP-1/CATAWBA/.SHEARON BELLEFONTE HARRIS Barring Device Control Val.ve and Press Regulator Base Assembly Cam Gear Camshaft Assembly Camshaft Bearings Circuit Breakers and Contact Blocks Connecting

'Rods, Bushings and Bearing Shells Control Panel Assembly: Relays Control Panel Switches Terminal Boards and Wiring 02-5258/03-5258 02-305A/03-305A 02-350C/03-350C 02-350A/03-350A 02-3508/03-3508 02-500C/03-500C-02-340A/8/

03-340A/8 02-500J/03-500J 02-500N/03-500N 03-5258/03-305A/02-305A 03-350C/02-350C 03-350A/02-350A 03-3508/02-3508 03-500C/02-500C 03-340A/8/

02-340A/8 03-500J/02-500J 03-500N/02-500N 02-5258/02-305A/02-305A 02-350C/02-350C 02-350A/02-350A 02-3508/02-3508 02-500C/02-500C 02-340A/8/

02-340A/8 02-500I/02-500J 02-500M/02-500N 03-5258/02-5258 03-305A/02-305A 03-350C/02-350C 03-350A/02-350A 03-3508/02-3508 03-500C/02-500C 03-340A/8/

02-340A/8 03-500J/02-500J 03-500N/02-500N/02-5258 02-305A/02-305A 02-350C/02-350C 02-350A/02-350A 02-3508/02-3508 02-500C/02-500C 02-340A/8/

02-340A/8 02-500J/02-500J 02-500N/02-500N 02-5258/02-305A/02-305A 02-350C/02-350C 02-350A/02-350A 02-3508/02-3508 02-500C/02-500C 02-340A/8/

02-340A/8 02-500J/02-500J 02-500N/02-500N II-E-2 TDI COMPONENT NUMBER CROSS REFERENCE COMPONENT DESCRIPTION Control Panel Valves Crank to Lube Oil Pump Gear Crankcase Assembly Crankcase Relief Valve (and covers)Crankcase Vacuum Fan Crankshaft Cylinder Block Cylinder Head Cylinder Head-Intake and Exhaust Valves Cylinder Head Covers-Subcover Assembly COMANCHE PEAK/SHOREHAM 02-500G/03-500G 02-355A/03-355A 02-311A/02-385A/03-385A 02-387A/02-310A/03-310A 02-315A/03-315A 02-360A/03-360A 02-360B/03-3608 02-362A/03-362A RANCHO SECO/SAN ONOFRE 03-500G/02-500G 03-355A/02-355A/02-311A 03-385A/02-385A/NONUM 03-310A/02-310A 03-315A/02-315A 03-360A/02-360A 03-360B/02-360B 03-362A/02-362A PERRY/VOGTLE 02-500G/02-500G 02-355A/02-355A 02-311A/02-311A 02-385A/02-385A 02-310A/02-310A 02-315A/02-315A 02-360A/02-360A 02-360B/02-360B 02-362A/02-362A RIVER BEND/GRAND GULF 03-500G/02-500G 03-355A/02-355A/02-311A 03-385A/02-385A/02-387A 03-310A/02-310A 03-315A/02-315A 03-360A/02-360A 03-360B/02-360B 03-362A/02-362A CATAWBA/BELLEFONTE 02-500G/02-500G 02-355A/02-355A 02-311A/02-311A 02-385A/02-385A 02-310A 02-310A 02-315A/02-315A 02-360A/02-360A 02-360B/02-360B 02-362A/-02-362A WNP-1/SHEA RON HARRIS 02-500G/02-500G'02-355A/02-355A 02-311A/02-311A 02-385A/02-386A 02-310A/02-310A 02-315A/02-315A 02"360A/02-360A 02-360B/02-360B 02-362A/02-362A I I-E-3 TDI COMPONENT NUMBER CROSS REFERENCE COMPONENT DESCRIPTION Cylinder Liners Diesel Starting Air Compressors Emergency Generator Emergency Generator Control Panel Emergency Generator Pedestal Bearing (and shaft)Engine Control Air Pressure Regulator (Valves, Orifices)Engine Control Cabinet Engine Control Pneumatic Switches Exhaust Manifold COMANCHE PEAK/SHOREHAM 02-315C/03-315C 02-835B/10-112 CP-101A/03-650A CP-102/03-6508 CP-101B/03-650C 02-695B/03-695B 02-500A/03-500A 02-695C/03-695C 02-380A/03-380A RANCHO SECO/SAN ONOFRE 03-315C/02-315C 03-835G/02-835A 03-650A/S0-101 03-650B/03-650C/S0-103 03-695B/02-695B 03-500A/02-500A 03-695C 02-695C 03-380A/02-380A PERRY/VOGTLE 02-315C/02-315C 02-835D/02-835A/02-650A/02-650B 02-650C/02-650C 02-695B/02-695B 02-500A/02-500A 02-695C/02-695C 02-380A/02-380A RIVER BEND/GRAND GULF 03-315C/02-315C 03-835D/GG-113/14 03-650A/GG-101A 03-6508/GG-119 03-650C/GG-1018 03-695B/02-695B ,03-500A/02-500A 03-695C/02-695C 03-380A/02-380A CATAWBA/BELLEFONTE 02-315C 02-315C NONUM/02-835B CN-119/BL-101A/BL-101B CN-119A BL-101C 02-695B/02-695B 02-500A/02-500A 02-695C/02-695C 02-380A/02-380A WNP-1/SHEARON HARRIS 02-315C/02-315C 02-8358/84-101A/02-650A 84-121/02-6508 84-1018/02-650C 02-695B/02-695B 02-500A/02-500A 02-695C/02-695C 02-380A/02-380A I I-E-4 TDI COMPONENT NUMBER CROSS REFERENCE COMPONENT DESCRIPTION Flex Connection Foundation Bolts Fuel Injection Nozzles Fuel Injection Pumps Fuel Injection Tubing Fuel Oil Filter Fuel Oil Injection Lines: Supports Fuel Oil Strainers Fuel Pump Control Shaft 02-805D/10-109 02-550/03-550 02-365B/03-365B 02-365A/03-365A 02-365C/03-365C 02-455A/03-455A 02-365D/03-365D 02-455B/03-455B 02-371A/03-371A 15-110/02-805C 03-550/02-550 03-365B/02-365B 03-365A/02-365A 03-365C/02-365C SC-014A 02-455A 03-365D/02-365D SC-042B/02-455B 03-371A/02-371A RANCHO COMANCHE SECO/PEAK/SAN SHOREHAM ONOFRE PERRY/VOGTLE 02-805D/02-805D 02-500/02-550 02-365B/02-365B 02-365A/02-365A 02-365C/02-365C 02-455A/02-455A 02-365D/02-365D 02-455B/02-455B 02-371A/02-371A RIVER BEND/GRAND GULF 03-805D/GG-ill 03-500/02-550 03-365B/02-365B 03-365A/02-365A 03-365C/02-365C 03-455A/02-455A 03-365D/02-365D 03-455B/02-455B 03-371A/02-371A CATAWBA/-BELLEFONTE CN-121/02-805A 02-500/02-550 02-365B/02-365B 02-365A/02-365A 02-365C/02-365C 02-455A/02-455A 02-365D/02-365D 02-455B/02-455B 02-371A 02-371A WNP-1/SHEARON HARRIS 84-114/02-805D 02-500/02-550 02-365B/02-365B 02-365A/02-365A 02-365C/02-365C 02-455A/02-455A 02-365D/02-365D 02-455B/02-455B 02-371A/02-371A II-E-5 TDI COMPONENT NUMBER CROSS REFERENCE COMPONENT DESCRIPTION Fuel Pump Linkage Assembly and Bearings Fuel Pump Linkage: Automatic Shutdown Cylinder Fuel Tappet Assembly COMANCHE PEAK/SHOREHAM 02-371B/03-371B 02-413B/03-371C 02-345B/03-345B Full Pressure Lube Oil Strainer Flywheel Bol ting Gear Train 02-820H 03-820C/03-330B Full Flow Lube Oil Filter(s)02-820F/10-106 RANCHO SECO/SAN ONOFRE 03-371B/02-371B 03-371C/02-4138 03-345B/02-345B 03-820E/02-820C 03-820C/SE-014/02-330B NONUM PERRY/VOGTLE 02-371B/02-371B 02-413B/02-413B 02-345B/02-345B 02-820F/02-717S 02-820C/SE-025 RIVER BEND/GRAND GULF 03-371B/02-371B 03-371C/02-413B 03-345B/02-345B 03-820B/GG-820B 03-460A/SE-025 CATAWBA/BELLEFONTE 02/371B 02-371B 02-413B/02-413 B 02-3458/02-345B CN-110/02-820D SE-025/02-820C WNP-1/SHEARON HARRIS 02-371B/02-371B 02-413B/02-413B 02-345B/02-345B 84-115/02-820E SE-025/02-820A Governor Booster Servomotor Governor Drive-Couplings, Pins and Keys Governor Drive-Governor and Tachometer Drive Gear and Shaft 02-415B/03-415B 02-411B/03-402B 02-411A/03-402A 03-415B/02-415B 03-402B/02-411B 03-402A/02-411A 02-415B/02-415B 02-411B/02-411B 02-411A/02-411A 03-415B/02-415B 03-402B/02-411B 03"402A/02-411A 02-415B/02-415B 02-411B/02-411B 02-411A/02-411A 02-415B/02-415B 02-411B/02-411B 02-411A/02-411A II-E-6 TDI COMPONENT NUMBER CROSS REFERENCE COMPONENT DESCRIPTION Governor Heat Exchanger Governor Linkage Hydraulic Valve Lifters Idler Gear Assembly Intake Air Filters Intake and Exhaust Tappet Assembly Intercoolers Jacket Water Fittings-Pipe and Fittings (Small Bore Scope Only)Jacket Water Heat Exchanger Jacket Water Heaters COMANCHE PEAK/SHOREHAM 02-415C/03-415C 02-413A/03-413 02-390F/03-390F 02-355B/03-355B 02-805B/10-114 02-345A/03-345A F-068/F-068 02-435A/03-435A 02-810C/10-103 02-810E/03-800A RANCHO SECO/'AN ONOFRE 03-415C/NONUM 03-413/02-413A/02-390F 03-355B/02-355B 03-805B/02-805B 03-345A/02-345A NB-002/41-127A 03-435A/02-435A 03-810C/02-810 PERRY/VOGTLE 02-415C/02-415C 02-413A/02-413A 02-390F/02-355B/02-355B 02-805B/02-805A 02-345A/02-345A F-068/F-068 02-435A/02-435A 02-810B/02-717Q 02-810D/02-717N RIVER BEND/GRAND GULF 03-415C/02-415C 03-413/02-413A/02-390F 03-355B/02-355B 03-805B/GG-118 03-345A/02-345A F-068/F-068 03-435A/03-810A/GG-103 03-800A/02-810A CATAWBA/BELLEFONTE 02-415C/02-415C 02-413A/02-413A CN-120/02-810A CN-128/02-810D/02-390F 02-355B/02-355B CN-106/02-805C 02-345A/02-345A F-068/F-068/02-435A WNP-1/SHEARON HARRIS 02-415C/02-415C 02-413A/02-413A 02-390F/02-717N/02-810C 02-810B/02-810A 02-355B/02-355B 84-111/02-805B 02-345A/02-345A F-068/F-068 02-435A/02-435A II-E-7 TDI COMPONENT NUMBER CROSS REFERENCE COMPONENT DESCRIPTION Jacket Water Pump-Gear Jacket Water Standpipe and Miscellaneous Bolting Jacket Water Standpipe:

Valves Lube Oil Heat Exchanger Lube Oil Keep-Warm Filter Lube Oil Keep-Warm Pump Lube Oil Keep-Warm Strainer Lube Oil Pressure Regulating Valve Lube Oil Sump Tank Heaters Lube Oil Sump Tank COMANCHE PEAK/SHOREHAM 02-425A/03-425A 02-700F/02-700B/00-700B 02-820G/10-104 02-820E/10-117 02-820C/03-820C 02-820D/00-420/00-420 02-820A/03-800B 02-540A/03-540A RANCHO SECO/SAN ONOFRE 03-425A/02-425A 03-700F/02-700F 03-717B/02-700B 03-820D/02-8208 03-820G/02-820E 03-820F/02-820D 03-820H/00-420/00-420 03-820B/02-820 03-540A/02-540A PERRY/VOGTLE 02-425A/02-425/~02-00F 02-700B/02-700B 02-820G/02-717R 02-820E/02-717V 02-8208/02-717U 02-820D/00-420/00-420 02-820A/02-717 P 02-540A/02-540A RIVER BEND/GRAND GULF 03-425A/02-425A/00-700F 00-700B/00-700B 03-820A/GG-104 03-820D/GG-121 03-820C/GG-109 00-420/00-420 03-800B/02-820A 03-540B/02-540A CATAWBA/BELLEFONTE 02-425A/02-425A/02-700F 02-700B/02-700B CN-111/02-820A CN-122/02-820E CN-109/02-820G 00-420/00-420 02-540D/02-540A/02-540A WNP-1/SHEARON HARRIS 02-425A/02-425A 02-700E/02-700F 02-700B/02-700B 02-717D/02-820B 02-717S/02-820G 02-717R/02-820F 02-717V/02-465D 00-420/00-420 02-820A/02-820C 02-540A/02-540A I I-E-8 TDI COMPONENT NUMBER CROSS REFERENCE COMPONENT DESCRIPTION COMANCHE PEAK/SHOREHAM RANCHO SECO/SAN ONOFRE PERRY/VOGTLE RIVER BEND/GRAND GULF CATAWBA/BELLEFONTE WNP-1/SHEARON HARRIS Lube Oil Tubing and Fittings-Internal Main Bearing Caps-Studs and Nuts Main Bearings Shells 02-3078/03-3078 02-305C/03-305C 02-3108/03-3108 Overspeed Trip Governor Overspeed Trip Governor and Accessory Drive Overspeed Trip Vent Valve Piping System Piston Pin Assembly Piston Rings 02-410A/03-410A 02-4108/03-4108 02-410D/03-410D NONUM/NONUM 02-341C/03-341C 02-3418/03-3418 Overspeed Trip Drive Couplings 02-410C/03-410C 03-3078/02-3078 03-305C/02-305C 03-3108/02-3108 03-410C/02-410C 03-410A/02-410A 03-4108/02-4108 03-410D/02-410D NONUM/NONUM 03-341C/02-341C 03-3418/02-3418 02-3078/02-3078 02-305C/02-305C 02-3108/02-3108 02-410C/02-410C 02-410A/02-410A 02-4108/02-4108 02-410D/02-410D NONUM/NONUM 02-341C/02-341C 02-3418/02-3418 03-3078/02-3078 03-305C/02-305C 03-3108/02-3108 03-410C/02-410C 03-410A/02-410A 03-4108/02-4108 03-410D/02-410D NONUM/NONUM 03-341C/02-340E 03-3418/02-340D 02-3078/02-3078 02-305C/02-305C 02-3108/02-3108 02-410C/02-410C 02-410A/02-410A 02-4108/02-4108 02-410D/02-410D NONUM/NONUM 02-341C/02-341C 02-340D/02-3418 02-3078/02-3078 02-305C/02-305C 02-3108/02-3108 02-410C/02-410C 02-410A/02-410A 02-4108/02-4108 02-410D/02-410D NONUM/NONUM 02-341C/02-341C 02-3418/02-3418 TDI COMPONENT NUMBER CROSS REFERENCE COMPONENT DESCRIPTION Pistons Push Rods Rocker Arm Bushings Rocker Arm Capscrews, Drive Studs (Pop Rivets)Starting Air Distributor Assembly Star ting Air Storage Tank Thermocouples Thermostatic Valves Thrust Bearing Ring Turbo/water Piping-Pipe and Fittings COMANCHE PEAK/.SHOREHAM 02-341A/03-341A 02-390C/03-390C 02-390E/03-390E 02-390G/03-390G 00-442A/03-442A 02-835J/10-111 02-630D/03-630D 02-810D/03-515 02-310C/03-310C 02-437/03-437A RANCHO SECO/SAN ONOFRE 03-341A/02-341A 03-390C/D/

02-390C 03-390E/02-390E 03-390G/02-390G 03-442A/02-442A 03-835F/.02-835E 03-630D/02-630D 03-799A/02-515 03-310C/02-310C 03-437A/02-437A PERRY/VOGTLE 02-341A/02-341A 02-390C/02-390C 02-390E/02-390E 02-390G/02-390G 00-442A/02-442A 02-835B/02-835D 02-630D/02-630D 02-810C/02-717W 02-310C/02-310C 02-437/02-437A RIVER BEND/GRAND GULF 03-341A/02-340C 03-390C/02-390C 03-390E/02-390E 03-390G/02-360G 03-442A/02-442A 03-835A/03-630D/02-630D 03-515/02-515 03-310C/02-310C 03-437A/02-437 CATAWBA/BELLEFONTE 02-340C/02-341A 02-390C/02-390C 02-390E/02-390E 02-390G/02-390G 02-442A/00-442A CN-112 02-835A 02-630D 02-630D C136/40/02-810C 02-310C/02-310C 02-437/02-437 WNP-1/SHEARON HARRIS 02-341A/02-341A 02-390C/02-390C 02-,390E/02-390E 02-390G/02-390F 00-442A/02-442A 02-835F/02-835D 02-630D/02-630D 02-810A/02-810 E 02-310C/02-310C 02-437/02-437 II-E-10 TDI COMPONENT NUMBER CROSS REFERENCE COMPONENT DESCRIPTION Turbocharger Turbocharger Lube Oil Fit-tings: Pipe, Tubing, Fittings and Flexible Coupling (Small Bore Scope Only)Turbocharger:

Bracket Bolting and Gaskets Water Discharge Manifold-Jacket Water Discharge.Piping, Couplings and Seals Woodward Governor COMANCHE PEAK/SHOREHAM HP-022/23/

MP-017 02-467A/03-467A 02-475A,C/, 02-475A,D 02-317A8 B/03-317A&B 02-415A/03-415A RANCHO SECO/SAN ONOFRE HP-020/HH-19/20 03-467A/02-467A 03-475A,C/

02-475A,C 03-317A8B/

02-317A8 B=-03-415A/02-415A PERRY/VOGTLE MP-022/3/HP-022/3 02-467A/02-467A 02-475A,C/

02-475A,C 02-317A8 B/02-317A8 B 02-415A/02-415A'RIVER BEND/GRAND GULF HP-017/HP-022/3 03-467A/02-467A 02-475A,C/

02-475A,C 03-317A8 B/02-317A8 B 03-415A/'2-415A CATAWBA/BELLEFONTE HP-022/3/MP-022/3 02-467A/02-467A 02-475A,C/

02-475A,C 02-317A8 B/02-317A8 B 02-415A/02-415 A WNP-1/SHEARON HARRIS HP-022/3/MP-022/3 02-467A/02-467A 02-475A,C/

02-475A,C 02-317A8B/

02-317A8 B 02-415A/02-415A ATTACHMENT 1 SERIAL: NLS-84-522 (978PPC/ccc)

Provide a copy of the procurement specifications to which the standby diesel generators (DG)were ordered.~Res onse The diesel generator equipment was procured by the plant Architect Engineer (Ebasco)utilizing Specification Ebasco CAR-SH-E-11,"Diesel Generator Unit and Control Panel for Nuclear Power Plants." Revision 7 of this specification is applicable to Shearon Harris Unit 1 and a copy is attached.2~Provide the performance specification and inspections performed upon receiving the DGs to show that the p'rocurement specifications were met.~Res onse The performance parameters and requirements are contained within the procurement specification provided in response to question 1.A separate performance specification was not developed.

Receipt inspections were performed by site QC inspectors in accordance with an approved receipt inspection procedure.

These inspections were primarily concerned with shipping damage and verification that the documentation was complete.The diesel generators have not yet been operated to verify performance at the Shearon Harris Nuclear Power Plant.3~Identify the materials used in the design of the DGs at your plant (specifically limiting components such as crankshafts, camshafts, pistons rocker arms, bearing materials, cylinder blocks, cylinder heads, pumps, turbochargers, etc.).Discuss how you assured yourself that design materials used in the manufacture of your DGs were as stated and in accordance with materials described in the TDI proposal, purchase specifications and conformance to industry standards.

~Res onse A TDI Owners'roup was formed in late 1983 due to concerns with TDI supplied equipment.

CPSL is an active member of the TDI Owners'roup.

The TDI Diesel Generator Owners'roup has issued several reports covering the key diesel engine components which have had adverse operating experience and are considered to be important to engine operation.

Each report assesses the adequacy of the component from a design and material standpoint.

These reports also recommend certain inspections and tests be performed on these components to validate assumptions made in the report or to establish the as found condition of the component.

CP6L has conducted inspections of these components in accordance with the Owners'roup recommendations.

The results of these inspections were addressed in CPSL's letter dated December 20, 1984 (NLS-84-490).

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Does TDI have a program where parts/components, etc.', are modified (such that design margins are reduced)in order to improve operability and DG reliability?

Does this apply to any DG parts at your plant?Provide a list of product improvements made by TDI on your model DG and identify and justify which of these were not incorporated on your diesels.~Res onse TDI does have a product improvement program which intends to improve the operability and reliability of their engines.Notification of noteworthy modifications are issued to TDI dies'el engine owners by a Service Information Memo (SIM).The TDI Diesel Generator Owners'roup is not aware of modifications recommended by TDI, which will decrease design margins.CP6L is a member of the TDI Diesel Generator Owners'roup which has produced a report to specifically address the SHNPP diesel generator equipment.

This report is referred to as the Phase II DR/QR Report and was provided to the NRC in a letter dated December 20, 1984.The report addresses the improvements which have been incorporated into the SHNPP diesel generator equipment.

If applicable, provide responses to all NRC open items on standby DGs at your plant.~Res onse The NRC Safety Evaluation Report (NUREG-1038) for SHNPP does not identify a specific open item concerning the diesel generator equipment.

Identify each of your DGs by model number and rating (continuous duty and short time overload)as purchased and discuss all tests (including torsional and other design proof tests)performed on the DGs that were observed (also those not observed)by you at the manufacturer's facilities.

~Res onse The emergency diesel generator model number and ratings are provided in Table 1, along with other engine and generator specifications.

Table 2 lists the vendor tests performed on each of the two emergency diesel generators supplied for SHNPP Unit 1.Testing of SHNPP Emergency Diesel Generator 1A-SA consisted of the standard Diesel Engine Manufacturers Association (DEMA)test.Additional tests were conducted to demonstrate performance requirements specified in the purchase contract.Testing of SHNPP Emergency Diesel Generator 1B-SB consisted only of the standard DEMA since the purchase contract p'erformance requirements had been previously demonstrated by the Emergency Diesel Generator 1AHA tests.Torsional testing of a diesel engine will be conducted per the TDI Owner Group DR/QR program after completing the equipment installation.

(9 78P PC/ccc)

Table 1 Diesel Generator Specifications Model Service Fuel Configuration No.of Cylinders Bore (in.)Stroke (in.)Cycle Mode Total Displacement (cu.in.)BMEP (psi)BHP RPM Crankshaft Rotation Firing Order DSRV-1 6-4 Stationary Nuclear Service No.2 Diesel 45'V" Type 16 17 21 4 76,266 209 9,074 450 CW (from flywheel end)1L-8R-4L-5R-7L-2R-3L-6R-8L<<1R-5L-4R-2L-7R-6L-3R Generator Continuous Rating (kw)Overload Rating (kw)*KVA*Voltage*Amperes Phase Power Factor 6,500 71150 8,125 6,900 679.9 3 (wye connected) 0.8*Continuous Ratings (9 78P PC/ccc)

Table 2 Testing of SHNPP Emergency Diesels TEST(')S ecified(Performed (3)IA-SA IB-SB (3)Witnessed 1A-SA 1B-SB 1)Functional Tests 2)Air Starting System Tests 3)Sequential Loading Tests 4)Load Rejection Tests 5)Margin Test 6)Rated Load Test 7)DEMA Test X ,X X X X X X X X X X X X X (4)(4)(4)(4)(4)(4)X X X X X X X X NOTE: (1)Test nomenclature taken from TDI uglification Testin Procedure.

(2)As required by Purchase Specification CAR-SH-E-11 (Purchase Order NY435079).(3)As witnessed by Ebasco Services, Inc., acting as CPSL's representative.

(4)Test not required to be performed.

O(9 78PPC/ccc) 7.In addition to qualification tests that were performed in accordance with Regulatory Guides 1.9 and 1.108, and IEEE Standard 387, describe all other onsite tests performed on your DGs.~Res onse The emergency diesel generator (EDG)installation at SHNPP is approximately 95 percent complete.Turnover of emergency diesel generator and associated, auxiliary systems from the construction phase to the startup testing phase will commence in early 1985.Testing to be performed is described in the SHNPP FSAR Sections 1.8, 8.3.1, and 14.2.The start-up test phase will be modified as necessary to incorporate recommendations made as a result of the TDI Diesel Owners'roup Design Review and Quality Revalidation program for SHNPP Unit 1 EDG installation.

Test reports will be written and retained in accordance with site procedures.

8.In addition to any deficiency reports already provided to the NRC, summarize and describe problems encountered and resolved during installation and preliminary operation of the DGs.During this period, were any unusual or abnormal operations observed such as excessive vibration noise, etc., and how were these conditions corrected.

Provide a detailed summary of the complete operating histories of your DGs.~Res onse During the installation of the emergency diesel generators the following problems were encountered:

A.The below listed conditions were found prior to installation:

a.Six pole washers on the rotors were found to be cracked or broken.b.One wire hold-down stud on the rotor was damaged.c.Pour stator cover plate studs were broken off.d.One rotor would not register on a megger due to condensation found when crate was opened.The above noted conditions were processed in accordance with site procedures and all repairs have been made.(9 78P PC/ccc)

B.During the preparation and installation process, some clarifications and additional information had to be obtained to supplement the instruction manual.This was not considered a major problem but is mentioned here to ensure completeness of response.Examples are: a.The manual does not state any tolerances on specified torquing values.Tolerances were provided by the vendor and issued per a Field Change Request.b.The vendor manual states that the connecting bolts for the rotor/flywheel/engine flange are to be a press fit.However, the manual also states that mechanical devices are not to be used to install the bolts.The vendor representative stated that a porta~ower jack may be used to push bolts through the flanges.c.Roll pins are installed between the nut crown and through the, connecting bolt for the rotor/engine/flywheel flange connection.

Several instances occurred where once the connecting bolts were torqued to their specified value the holes in the bolts and nut crown did not line up to allow installation of roll pins.The manual states the nuts are then to be tightened until opening comes up.However, no maximum torque or alternate method of alignment are given to install the roll pins.Vendor representative supplied the required maximum torque value and alternate method for installation (i.e., shaving nuts).CPGL's letter dated December 20, 1984 (NLS-84-490) discusses the inspections performed and changes implemented on the diesel generators as a result of the TDI Diesel Generator Owners'roup program.This work will be performed prior to operating the equipment at the site.The SHNPP diesel generators are presently scheduled for initial operation in May 1985.9.Tabulate, compare and discuss differences in present actual DG loading to estimated loads included in the procurement specifications.

Identify the magnitude of the increased load (if any)on the DGs and describe how the increased loading affects the DG capability with regard to reserve margin.~Res ense The procurement specification (provided in response to question 1)contains electrical loading information and tabulates the data in Sketch No.CAR-2166&29, Rev.6 for load blocks 1 through 8.Per this sketch the maximum tabulated load for blocks 1 through 8 is 5322.55 kw.(9 78PPC/ccc)

A recent review of the estimated loading on the diesel generators indicates that the anticipated blocks 1 through 8 loading is about 70 kw less than identified in the procurement specification.

The following tabulates the summation of the 1E loads from the recent review: Blocks 1-8 Block 9 Total~En ine Condition Load, kw Load, kw Load, kw A Safe Shutdown 4821.05 703 552 4.05 LOCA 52 47.55 3 44.5 5592.05 B Safe Shutdown 4823.05 748.5 55 71.55 LOCA 5249.55 348.5 5598.05 The present maximum load of 5598.05 kw is substantially less than the 6500 kw design rating for the diesel generators.

However, these numbers are subject to revision particularly in light of the cancellation of SHNPP Unit 2.If DG loading has increased from that specified in the procurement specifications, has it been necessary to upgrade the standby DGs to meet the new load requirements?

If DG upgrading has been performed, provide a detailed description of the upgrading accomplished on your DGs?What is the revised manufacturer's rating for each upgraded unit for normal continuous duty and short time overload conditions?

Is the DG built-in design margin (after upgrading) still within the recommendations of IEEE Standard 387.What is the reserve load carrying capability (margin)of your upgraded DGs?~Res onse The diesel generator rating has not been increased from that specified in the procurement specification.

In light of the problems that have been identified to date with Delaval diesels, discuss your plans to perform an internal visual inspection of each standby DG with regard to potential crankshaft and/or web cracks as identified at the Shoreham Station and provide a detailed discussion of your plans to perform any nondestructive testing (NDT)such as dye penetrant testing, etc., as deemed appropriate to assure absence of cracks at these locations or at any other locations where cracks may have been observed.Discuss schedules for such testing.~Res onse As a result of the failure of the Shoreham crankshaft, the TDI Diesel Generator Owners'roup identified the crankshaft as a generic component for analysis in Phase I of the program.Failure Analysis Associates (FaAA)completed its analysis of crankshafts for the DSR-48, DSRV-1 6-4, DSRV-12, and DSRV-20 diesel engines.These reports were forwarded to the NRC for review in letters dated April 20, 1984 (Serial No.TDI-17), May 24, 1984 (Serial.No.

OGTP-39), and June 15, 1984 (Serial No.OGTP-76)~(9 78PPC/ccc)

The FaAA reports recommend torsiograph testing of one crankshaft at each plant and NDE inspection of the oil holes in the main journals number 4, 6, and 8 for the DSRV-16-4 crankshafts.

The torsiograph of one crankshaft will be performed at SHNPP during the initial diesel generator testing.The NDE inspection of the SHNPP oil holes in the main journals (journals 2 through 9)has been successfully completed by FaAA NDE personnel on both diesel generators installed at SHNPP.Results of this inspection have been forwarded to the TDI Owners'roup technical staff.This information was also discussed in'CP&L's December 20, 1984 NRC submittal.

Justify that the standby DGs at your plant are sufficiently reliable that there will be reasonable assurance that the facility can operate without undue risk to the health and safety of the public.Your, justification should include, but not be limited to the following:

(1)quality assurance program conducted by you during procurement, manufacturing and receipt of your DGs, (2)your assessment of the TDI manufacturing process, inspection, and quality assurance program conducted during manufacture of your DGs, (3)your assessment of TDI responsiveness to problems that have occurred with your engines during installation and preliminary operation including assessment of TDI performance, (4)comparison of your DGs with all other TDI emergency DG models now in use or to be used in other nuclear generating stations (and other non-nuclear facilities) to show that the conditions and/or failure modes present at Shoreham will not occur at your plant and at other nuclear plants;provide any supporting information that may be obtained from nonnuclear installations, (5)independent revie~of verification of any TDI design calculations for critical components of your DGs, and/or other means used to assure that your DGs are designed to DEMA standards and applicable industry codes and standards, and (6)your overall assessment of the DGs at your plant with regard to TDI system design, operating experience to date, and system dependability, availability, and reliability to warrant operation of your plant.Response Ebasco Services, Inc.was employed by CP&L as the plant's Architect Engineer (A/E)during the design and construction of the SHNPP.As the plant's A/E, Ebasco procured the SHNPP diesel generator equipment.

The specification provided in response to Question 1 shows that the diesel generators were purchased as nuclear safety-related Class 1E and were required to be covered by a vendor quality assurance program.The Quality Assurance Program for procurement, manufacturing and release for shipment was formulated and implemented by Ebasco Services Inc.after review and concurrence by CP&L.(9 78PPC/ccc)

The installation and assembly process up to the present time has been completed with the supervision of Transamerica Delaval representative.

The representative has been helpful and informative in resolving installation problems.The vendor representative was also responsive in providing the needed information to solve problems and answer questions pertaining to QA, electrical systems and piping.The SHNPP diesel generators are TDI Model DSRV-1 6-4.Similar engines are presently in use at other nuclear power plants.CP&L is a member of the TDI Diesel Generator Owners'roup (OG)and provided specific information to the OG on the SHNPP equipment.

The OG program has used the information, provided by CP&L and other utilities, to develop a data base and perform a component by component comparison of the CP&L diesel engine.The comparison used failure history data developed by the Owners'roup for nuclear and non-nuclear diesel engines.The above process is described in the Owners'roup Program Plan as the Component Selection process.The Owners'roup has performed an independent Design Review and/or Quality Revalidation of each component as applicable.

The results of the SHNPP review were forwarded to the NRC in a letter dated December 20, 1984.This letter provided the Owners'roup Phase II DR/QR Report on the SHNPP equipment.

CP&L believes that the overall Owners'roup program has been beneficial.

The Owners'roup program used a two phase approach.The first phase addresses generic problems with the TDI diesel engines and is essentially complete.A detailed review was performed to identify the cause of these 1 6 problems and to recommend corrective action.The results of the review identified the need for increased component inspection, better installation procedures, some component design changes and periodic component maintenance and inspection.

CP&L and the TDI Diesel Generator Owners'roup maintain that the resolution of these 1 6 generic problems has assured that the diesel generator equipment will perform reliably.As a confirmatory effort, Phase II of the program (the DR/QR report)has reviewed a substantially larger number of engine components and identified many improvements for operation and maintenance that will further enhance the equipment's reliability.

Provide a tabulation of the number of times (including each date of occurrence) voltage was lost at the emergency bus(es)requiring operation of the DG(s)including a brief description of each incident.In the above tabulation, also identify the loss of emergency bus voltage due to loss of offsite power.~Res ense The Shearon Harris Nuclear Power Plant is presently under construction and the installation of the SHNPP emergency diesel generators is not yet complete.Shoreham has identified connecting rod bearing materials are not in accordance with design specifications on their engines.This condition may also exist on all other TDI diesels.Provide assurance the correct (9 78PPC/ccc) bearing design and materials have been used in your engines.Should you find that improper bearings have been used in your diesels, state how and when you propose to correct this problem.~Res onse The Failure Analysis Associates report on Connecting Rod Bearing Shells (FaAA-84-3-1) discusses the failure mode of the original 11-inch diameter bearings on the Shoreham engines.The report concludes that the replacement Shoreham 12" diameter bearing shells will not exhibit the same failure mode.The report also analyzed the DSRV-1 6-4 bearing shell design used at SHNPP and.concluded that the design is acceptable.

FaAA was unable to establish that the original bearing shells met design specifications in the area of tensile strength and elongation.

The reason for the discrepancy was attributed to the inability to obtain a large enough test specimen on the finished bearing shell;However, tensile and ductile properties of the material were not identified as the root cause of the failure.The FaAA report recommends radiography of the bearing shells to ensure no casting voids greater than.050 inch are present in the critical areas of the bearing shells.The FaAA report states that this inspection should be done on a sampling basis.All connecting rod bearing shells installed on both SHNPP TDI diesels and spare bearing shells have been radiographically examined to the criteria stated in the SHNPP Phase II Design Review/Quality Revalidation Report.A total of six bearing shells (one on diesel 1A-SA and five on diesel 1B-SB)were rejected for material porosity or material density below specification and will be replaced during engine reassembly.

Examination of spare bearing shells is still in progress.Most of the piston skirts in the Shoreham diesels were cracked.Because of a common cylinder design for all TDI diesels, it is presumed that this condition potentially exists on all other TDI diesels.Discuss your plans, including internal inspection or other means to determine the potential or actual existence of such cracking.In your response, indicate whether the design and materials are identical to those in the Shoreham units;if not identify differences.

Identify any corrective actions you have taken to date or plan to take.The staff understands that the TDI has a piston design modification to correct the above problems.Are you aware of this and has TDI transmitted this service information to you?~Res onse The TDI Diesel Generator Owners'roup has completed an extensive review of the modified type AF piston skirt originally installed in the Shoreham engines.Failure Analysis Associates reports FaAA-84-2-14, May 23, 1984 and FaAA-84-5-8, June 1984 documents this review.-10-(9 78PPC/ccc)

There are several types of pistons in use in nuclear services.The above reports deal with the AF and AE piston type.The TDI Diesel Generator Owners'roup reported on the AH and AN piston type designs in Failure Analysis Associates report FaAA-84-10-30, November 1984.CP&L is aware of the various piston types as a result of the Owners'roup review of this component.

The piston skirts installed in the SHNPP diesels were originally of the AN design.Due to the timeframe of the SHNPP Diesel Quality Revalidation Inspection and that the design review of the AN piston type was not complet'e, SHNPP decided to replace all AN piston skirts originally installed with the latest design AE piston skirts.These new components have been successfully liquid penetrant and magnetic particle inspected.

The Owners'roup has also determined that the AE piston skirts are acceptable.

What maintenance and/or operating practices have you developed to assure optimum reliability of your diesel generators at your plant7~Res ones A review of maintenance practices and recommendations has also been performed by the TDI Diesel Generator Owners'roup.

This resulted in a maintenance matrix being provided in the SHNPP DR/QR report which was transmitted to NRC by CP&L's letter of December 20, 1984 (NLS-84-490).

With a few exceptions as discussed in that transmittal, CP&L commits to following the Owners'roup recommended maintenance recommendations as part of the overall SHNPP maintenance program.What surveillance practices in addition to those required by plant technical specifications have you instituted to assure optimum reliability of your diesel generators at your plantf~Res onse The TDI Diesel Generator Owners'roup program has developed a maintenance matrix for this equipment based upon documentation review.The maintenance matrix is provided in the SHNPP DR/QR Report (Appendix II)and includes surveillance items which should be checked on a daily basis.CP&L's letter of December 20, 1984 (NLS-84-490) transmitted the DR/QR report to NRC and, except as noted in the transmittal, committed to incorporating the Owners'roup recommendations into the overall SHNPP program.-11 (9 78PPC/ccc) 0