Text

Review of Auxiliary Feedwater Sys for Reliability Improvements
	ML20137H598
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	11/30/1985
From:	; BECHTEL GROUP, INC.
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ML20137H542	List: ML20137H537; ML20137H598;
References
	TAC-60783, NUDOCS 8512020430
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i l Trojan Nuclear Plant l

Roview of the Auxiliary Feedwater System i fer Rellability Improvements Partland General Electric Company

( GE

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t @Bechtel Power Corporation

[ November 1985

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[ g p=SnuBiaaja4 L .

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[ TROJAN NUCLEAR PLANT

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REVIEW 0F THE

{ AUXILIARY FEEDWATER SYSTEM FOR RELIABILITY IMPROVEMENTS

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l Prepared for

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PORTLAND GENERAL ELECTRIC COMPANY

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BECHTEL POWER CORPORATION San Francisco, California

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E November, 1985 b

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TABLE OF CONTENTS E

PAGE EXECUTIVE

SUMMARY

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1. INTRODUCTION 1

( 2. GENERAL SYSTEM DESCRIPTION 2

3. DESIGN REVIEW, CRITIQUE AND RECOMMENDATIONS 9 3.1 Suction Piping 9 3.2 Discharge Piping 13 3.3 Pump Drivers and Controls 15

[ 3.4 Flow Control Valves 29 3.5 Service Water System 30 3.6 Other Recommendations 32 3.7 Summary of Recommendations 34 F

q FIGURES REFERENCES SUPPLIER CONTACTS Appendix Reliability and Maintenance Data Review L -

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( EXECUTIVE

SUMMARY

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A component by component review was performed of the Trojan Auxiliary Feedwater ( AFW) System to identify improvements to enhance system reliability. Design information, operational procedures and history, supplier input, and a physical walkdown all contributed to the review, b Major recommendations for reliability improvement include:

( o Upgrade the AFW pump suction piping and trip instrumentation.

o Bypass thermal overload relays in various motor starter

{ circuits.

o Provide detailed calibration procedures for turbine and diesel driver governor control systems.

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1. INTRODUCTION L

[ On August 2, 1985, PGE requested Bechtel to perform a review of the auxiliary feedwater ( AFW) system at the Trojan Nuclear Plant for r potential reliability improvements. The request was in response to recent operational anomalies at Trojan and a serious loss of feedwater r event at Davis Besse Plant in June 1985. The philosophy of the review L was to identify reif abfiity improvements witnin the frame, work of tne existing system. This report documents the findings of the review.

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The effort included a component by component review of the AFV system through examination of plant drawings, maintenance data, operating

{ procedures and Licensee Event Reports (LER's). A plant walkdown was conducted to cneck physical aspects of the system and observe the test startup of both the diesel driven and turbine driven pu:pt. The pump and driver suppliers were contacted and a comparison review was made of AFW systems from several other nuclear plants. As directed by PGE, the review did not include quantitative reliability nor probabilistic risk analyses, since several such studies had been performed previously. The results of these analyses were considered in the review.

l Section 2 of the report presents a general overview of the AFW system design. Section 3 is the detailed review of the system with I

recommendations for improvement. A list of references and collection of the writeups of telephone conversations with suppliers complete the report, L

r The Appendix to the report describes a review of component reliability data and presents a breakdown of maintenance activities and Licensee Event Reports.

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2. GENERAL SYSTEM DESCRIPTION

[ The Auxiliary Feedwater (AFW) system for Trojan consists of two safety-grade full capacity pumps (880 gpm) with diverse drivers (1 b turbine driven and 1 diesel driven) and a third non-safety grade full capacity electric motor driven pump for startup and shutdown

( (See Figure 1). The two safety-grade AFW pumps P-102A (turbine) and P-1028 (diesel) take normal suction from the 450,000 gallon capacity Condensate Storage Tank (CST) through a common suction header which

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is non-seismic up to the check valves at each pump suction. The check valves serve as the seismic boundary. An alternate seismic Category I supply of water from the Service Water System (SWS) connects to the piping between the check valves and the pumps.

[ Normally closed motor operated valves that can be operated from the control room isolate the service water supply from the pump suction.

The non-safety grade electric motor driven AFW pump P-182 takes suction from the CST but through a separate 6" line which connects to an 8" CST nozzle. This nozzle also serves as the supply / dump line to the condenser and supply to the condensate demineralizer backwash system.

Each safety grade AFW pump feeds all four steam generators through a 6" discharge line which branches into four lines. Each pump discharge line is provided with a check valve and an isolation valve to permit maintenance of the pump and the check valve. The discharge line then branches into four lines to supply the four steam generators. Each of the eight branch lines is provided with a motor-operated flow control valve, a check valve downstream, and manually-operated isolation valves upstream and downstream of the control valve.

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Each of four auxiliary feedwater lines from one pump joins with a corresponding line from the second pump into a single line in which a flow indicator is provided for remote and local indication. Also, flow restrictors are located upstream of each motor-operated control valve. In the event of a pipe break downstream of the MOV, a high-flow signal from a flow element at one of these restrictors aill automatically close the motor-operated flow control valve

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associated with the orifice. Downstream of the flow indicator, the single auxiliary feed line then joins with the steam generator main feedwater line in the Seismic Category I section between the feedwater line isolation check valve and the containment.

The electric motor driven AFW pump discharge is provided with a check valve, a flow indicator, an air operated control valve, and a manual isolation valve to permit maintenance of the pump, control valve and check valve. The piping then branches so that the electric motor driven pump can discharge to either the diesel-driven or turbine driven pump discharge lines downstream of their check L valves and isolation valves. Each of these branch lines is provided eith a Seismic Category I normally closed motor operated valve. A check valve is also provided in each line to prevent cross flow between the diesel-driven and turbine driven discharge piping.

Each pump has a continuous minimum flow recirculation line with a 7

pressure reducing orifice, a locked open valve and check valve. All three recirculation lines join together before connecting to the CST.

L The turbine driven AFW pump receives steam from all four steam generators. A connection is provided from each of the Seismic

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Category I sections of the four main steam lines upstream of the MSIVs (see Figure 2). Each connection is provided with an air-operated supply valve, a manually operated isolation valve L upstream, and a nonreturn valve downstream. The air-operated valves b

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L L remain closed during normal operations and are equipped with Seismic Category I air accumulators. Each valve has a 3/4" bypass L line with a flow restricting orifice for supplying warming steam.

The four steam lines join into a single line which supplies steam to the steam turbine through a-c motor-operated stop valve and a

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combined trip and throttle valve. The turbine exhausts steam to the 7

atmosphere. Lube oil cooling water for the turbine driver is taken from the pump casing through a pressure reducing orifice, a locked

, open isolation valve, and flow element, and is then returned to the L pump suction. A backup cooling water supply is available from the service water line to the AFW pump.

Diesel oil is supplied to the diesel driven AFW pump from a 500 gallon day tank through a gravity feed line (see Figure 3). The engine is provided with a closed jacket water cooling system and a pressurized lubrication system complete with pumps, filters, and lube oil coolers. An oil priming pump maintains engine oil circulating during engine shutdown periods. Two 4000-W heaters maintain engine jacket water temperature between 100*F and 120*F while shut down. Cooling water required for the oil coolers for the pumps and their drivers and for the engine jacket water heat exchanger is supplied from the SWS. A connection is taken from the SB line to the diesel auxiliary feedwater pump and is provided with L

a motor-operated valve which opens automatically whenever the diesel auxiliary feedwater pump is started. The SW outlet from the oil coolers and jacket water heat exchangers is drained to the dilution structure.

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The electric motor for the motor-driven pump is a three-phase, 7 60-cycle,1250-hp, 4000-V motor which is powered from the 4.16-kV, A5 bus (see Figure 4). The motor is sel f-lubricating and sel f-cooling. Space heaters are used to prevent condensation of moisture within the motor enclosure during the shutdown periods.

J The motor has thermal, overcurrent and undervoltage trips. Normal operating speed is 3579 rpm. Both the motor and pump are Seismic Category II.

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L The AFWS is provided with the necessary controls for local or remote, and automatic or manual operation of the system for the safety-related pumps. The local controls are mounted on panel C160 near the safety-related auxiliary feedwater pumps and the remote controls are in the main control room. All the controls and control signals for the steam turbine-driven pump and the diesel

[ engine-driven pump are channelized. Physical separation between the safety-related pump controls is maintained in local control panel C160 also. The electric motor-driven pump is controlled from the

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main control room. The breaker for the electric pump can also be controlled at the breaker cubicle in the electric auxiliary room.

The AFW system is designed to automatically start both safety-grade AFW pumps upon receipt of initiating signals. All actuated valves in the system flowpaths from the diesel driven and turbine driven pumps are normally open and fail as-is. The steam turbine driven pump is auto / manual started by opening air operated isolation valves from the steam lines of all four steam generators and by opening the turbine trip and throttle valve in the common header downstream of the four inlet valves.

The diesel driven pump has its own starting battery which automatically starts the diesel. The initiating signals also start a reduction gear lube oil priming pump, and open an MOV to supply service water for jacket cooling and lube oil cooling. The diesel has a day tank with a 500 gallon capacity good for 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months of diesel operation. Automatic transfer of fuel to the day tank from the emergency diesel fuel oil transfer system is controlled by day tank level.

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Both the diesel and turbine driven pumps use governors that control the speed to automatically maintain a set pressure differential

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between the pump discharge and the steam generators. This pressure differential can be selected by the control room operator tt h el p

[ control steam generator level.

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s A walkdown of the AFW line from the safety-grade pumps P102A & B to steam generator will encounter the instrumentation described below.

At the AFW pump suctions, pump suction pressures are measured by PT3044A

[ & B. PT3044A & B have no control functions. They merely transmit suction pressure signals to PI3044A & B in local panel C160.

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On the pump discharges, pressure gauges PI3064A & 8 provide local indications of discharge pressures. Pressure transmitters PT3083A & B provide signals for the following functions:

b a) Discharge pressure indication on control room panel Cl4.

b) One of two inputs to differential pressure indicator PDI3083A & B in

[ panel C160 and to the turbine or diesel speed control systems.

PT3046A&B located on the pump discharges, have no control functions.

Thoy merely transmit discharge pressure signals to PI3046A&B in panel C160.

Position switches ZS3022A & B. ZS3004A3-D3, ZS3004A4-D4, ZS3004AS-D5 and ZS3004A6-D6 indicate positions of manual discharge valves on local panel l C160 and control roon panel C19. Closure of any of these valves in any of the eight discharge lines will illuminate an annunciator window on l

panel C160.

Flow control valves CV3004Al-01 and CY3004A2-D2 are maintained at a prescribed throttle setting in order to pass the required flow upon l automatic startup. All changes of valve position are done remote-manually by the operator at local panel C160 or control room panel

{ C05 -- except for automatic closure when high flow occurs. Flow indicating switches FIS3004Al-D1 and FIS3004A2-D2 upstream of each of the eight control valves will automatically trip if some abnormality occurs downstream which allows a flow of 500 GPM or more to any of the four steam generators. This trip simultaneously closes its associated control

[ valve only and disables (locks out) the high flow trip closure of the

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remaining 3 control valves in the same AFW train so that they remain

( open to pass flow to their respective steam generators. Flow L

transmitters FT3043A-D sense total AFW flow to their respective steam generators and provide signals for the following functions:

a) Flow indications on panels C160 and C05;

[ b) One of two inputs into FY3078A to control shutdown hydrazine pump P-157A chemical injecti7n into the steam generator feedwater inlet header.

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7 Flow transmitters FT3043E-H provide signals to the Technical Support L Center and to flow indicators at control room panel Cip.

The instrumentation is described below for the suction piping starting from the safety-grade pumps P-102A&B to the CST.

[ Pressure gauges PI3063A and PI30638 provide local indication of

( static head when the pumps are down and indications of suction pressure when the pumps are running.

Pressure transmitters PT3072A and PT3072B provide signals for the following functions:

L a) Trips of AFW pump driver (s) on low suction pressure.

b) Suctica pressure indications on control room panel C15.

c) Low suction pressure alarms on control room panel C15.

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L If any or all of valves FWil2, FWill and/or M0050 in the suction path to either AFW pumps are incorrectly positioned (closed),

( position switches ZS3061A, ZS3061B and/or ZS5262 will activate an alarm, annunciate on local panel C160, and indicate position by means of indicating lamps on panels C160 and C19.

- Level transmitter LT5201 provides indications of CST level and low L

(60%) or high (95%) CST level annunciations at panels C160 and C17.

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Level transmitter LT5265 provides indications of CST level and low-low (about 19%) level annunciations on panels C160 and C17. This low-low signal alerts the operator to enter the procedure for changing the AFW suction source from the CST to the service water system.

The function of level controller LC5214 and valve CV5214 is to provide

[ makeup condensate to the CST. Makeup is provided from the demineralized cater storage tank T-131 either directly or indirectly through the condenser. Normally, the makeup is from the condenser which supplies

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deaerated condensate through the makeup / dump line to the condenser.

The secondary or alternate source of water to the AFW pumps is the safety-grade service water system. Yalves M03045A&B are remote-manually operated from control room panel C14, with valve position indications.

{ The electric motor driven pump P-182 is manually controlled from either a local panel or the control room. It is powered from the non-safety related 4.16kV bus AS. On the suction piping, pressure switch PS-2955 provides a signal to trip the electric motor pump on low suction pressure. On the discharge, PI-2953 and FI-2957 provide local indication of pump discharge pressure and flow. Control Valve CV-2967 is used to maintain the pressure of the auxiliary feedwater downstream of the valve at 100 psi above the main steam line pressure. The valve is a pneumatic actuated drag type valve.

The pressure transmitter, PT-2967 downstream of the control valve provides one of the two inputs to the differential pressure control L system and also provides discharge pressure indication on panel Cl4 in the control room. Valve CV-2967 can be operated in auto or remote

( manual from the control room panel Cl4.

{ Valves M0-2947A&B are normally closed, and remote manually operated from control room panel C05 with the valve position indication. By opening either or both of these valves, the output of the electric motor driven AFW pump can be directed to the steam generators via the safety-grade AFW header piping.

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3. DESIGN REVIEW / CRITIQUE AND RECOMMENDATIONS The design of the Trojan Auxiliary Feedwater System (AFW) was reviewed to identify components or system configuration changes that would improve )

[ AFW system reliability. As an aid, the reliability assessment contained l in NUREG-0611, Generic Evaluation of Feedwater Transients and Small Break Loss-of-Coolant Accidents in Westinghouse-Designed Operating Plants, was

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used as a guide. Also, Trojan's AFW system was compared with AFW systems of other plants to see if any system configuration differences could be corelated with higher reliability. Plants examined included Diablo Canyon, Farley, Arkansas, Rancho Seco, Palisades, South Texas and Palo Verde.

The review of AFW systems was broken into segments consisting of 3.1 j Suction piping from the CST to the pumps, 3.2 Discharge piping from the pumps to the steam generators, 3.3 Drivers and controls, 3.4 Flow control

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valves, 3.5 Service water supply, and 3.6 Support systems. Each of these segments are discussed below. A summary of recommended improvements is

[ included in Section 3.7.

3.1 Suction Piping The two safety-grade AFW pumps are normally supplied condensate from the non-seismic condensate storage tank through a common 8" line that reduces to 6" as it splits to the suction of the two AFW pumps. This suction piping is buried just a few feet from the CST nozzle until it emerges as 6" piping in each of the AFW pump rooms. Low suction pressure trips were I installed on both the diesel and turbine driven AFW pumps to satisfy the l NRC's Long-Term Generic Recommendations GL-2 and GL-4 dealing with !

( protection against multiple pump damage from single valve closure in the AFW system flow path or due to loss of suction resulting from natural phenomena. The setpoint of the low suction pressure trips was set at

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+0.5 psig to provide protection from a complete loss of the CST or suction line which would result in atmospheric pressure at the pump suction, with no source of water. The minimum NPSH requirement for two pumps at rated flow is lower (on the order of -3.0 psig). Upon startup

[ of both pumps, suction pressure drops below the setpoint on a transient basis and then rises back above the setpoint. This trip has been a cause

[ of unreliability to the system due to its limited range (see next page) and its artificially high setpoint (set for loss of suction line as opposed to inadequate NPSH). In order to preclude spurious trips of the

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pumps, a time delay was installed bypassing the trip until the startup transient was complete. In addition, the flow through the common suction line was limited to 1460 gpm to avoid low suction pressure conditions at low CST level s.

As an alternate means of satisfying GL-4, upgrading of the suction line and CST was investigated. A review of the seismic capability of the

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common suction piping from the CST indicates that the buried piping should be able to survive a seismic event. The CST, although classified as Seismic Category II, will also be reviewed for seismic capability.

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L With respect to tornado missiles, the CST is fairly well protected by

' surrounding structures on three sides. The turbine building is located on the west side of the CST, the Main Steam Support Structure and Containment on the north side, and three large water tanks on the east side. Only the south side of the tank is not protected. However, of the 41 f t tank height, only the lower portion containing the minimum

( volume for cooldown and NPSH would need protection.

[ The small target area combined with the already low probability of a tornado at the Trojan site indicate a high availability of the CST.

With the service water as the backup source, any additional tornado protection for the CST would result in little improvement in AFW system reliability.

L The non-safety grade electric motor driven AFW pump P-182 was installed

( as a plant betterment after initial startup and commercial operation.

Its primary function is to relieve the safety-grade AFW pumps from normal startup and shutdown duties. The P-182 suction piping connects to the CST at a nozzle, separate from the safety-related pumps, which serves as the supply / dump from the condenser and supply to the I

% condensate demineralizer backwash system.

F L While reviewing suction instrumentation, the following observations were made:

The instruments for the AFW pump suction transmitters PT3072A, e PT3072B and pressure gages PI3063A, PI30638 are not capable of L

reading pressures below 0 psig. Pressure switches PS3072A, and PS3072B, in the PT3072A and PT3072B loops, are used to trip the AFW L pumps P-102A and P-102B when suction pressures drop to about 0.5 psig. Recent testing shows that the P-102B suction pressure does drop below 0 psig when both pumps are started simultaneously. Also the test data showed that the suction piping undergoes dynamic and

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unpredictable pressure oscillations during the early stages of the start transient. These oscillations have been severe enough to have most probably been the primary contributor to the failure of L some suction pressure instruments.

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F The CST level transmitters LT5201 and LT5265 were previously

- reviewed for compliance with Reg. Guide 1.97, Rev. 3 variables A-9 L and D-21. Power supplies to these transmitters are not Class lE.

[ Position switches ZS3061 A & B and ZS5262 were installed on the manual valves in the AFW suction piping in response to TMI and short and long-term Generic Recommendations. The power supplies to these

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position indications are not Class lE.

Suction pressure gages received frequent corrective maintenance attention.

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Recommendation I

Consider upgrades to suction piping and instrumentation which would

[L improve the reliability of the AFW System while maintaining low suction pressure protection for the AFW pumps. The following are recommendations for consideration:

Eliminate the common suction piping as a concern by:

a. Upgrading the line to Seismic Category I

b. Deleting the common suction line isolation valve

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7 Upgrade the low suction pressure protection by:

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c. Installation of a seismic, safety grade CST level detection system L d. Modifying the pump trip circuit to put a low CST level trip in series with the low suction pressure trips ("and" circuits). The

{ time delay for low suction pressure trip should be removed.

e. Replace the low suction pressure transmitter with one which is r capable of the full pressure range expected during pump transients L

and steady state, and lower the setpoint to a more realistic value.

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f. Alarm both low suction pressure and low CST level in the main control room.

One additional suction piping recommendation came from the review of

( system maintenance records:

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g. Evaluate suitability of suction and discharge pressure gages and their periodic preventive maintenance requirements.

[ Bith the suction piping upgrades, loss of CST inventory is the mechanism for pump damage due to low suction pressure. By using the proposed "and" circuit of low suction pressure and low CST level, spurious trips of either instrument will not prevent the pumps from starting.

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In developing this recommendation consideration was given to regulatory requirements, safety and improvement in operational flexibility, as well

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as reliability. Several configuration changes were investigated. They included deleting the low suction pressure trip, automatic switchover to service water on low suction pressure, seismic upgrade of the CST, modifications to suction pressure instruments, circuit, and logic,

( modifications to the suction piping, and alternate water sources.

Factors such as cost, maintenance, spurious operation, recovery from

{ spurious operations, constructability and the use of existing plant features were also considered. The above recommendation should provide improvement in AFW system reliability while meeting the intent of the Long-Term Generic Recommendations GL-2 and GL-4.

( 3.2 Discharge Piping

( The piping arrangements of the discharge piping of the AFW pumps are for the most part independent of each other. Common or connecting piping exists at the non-seismic portion of the recirculation piping to the CST,

{ the connection from the electric motor driven pump P-182 and the connection to the main feedwater line to each steam generator. The recirculation line from each pump has a flow restriction which limits

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flow to 80 gpm for the diesel and turbine driven pumps and 120 gpm for the electric motor driven pumps and a check valve which prevents backflow from the other pumps. The common recirculation piping from the diesel and turbine pumps is buried from the CST to just before the pump rooms.

The recirculation line from P-182 is routed separately and connects to the common piping near the CST tank nozzle.

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Closure of a single valve MD150 located near the CST could interrupt recirculation flow from both safety-grade AFW pumps. However, the valve

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is normally locked open, is located behind a security barrier and does not require any repositioning for routine testing or maintenance.

The discharge of the electric motor driven AFW pump ties into each

( safety-grade train with a remote-manual motor operated isolation valve (MO-2947A&B) and a check valve. The check valve prevents cross connecting the two trains of AFW in the event that both isolation valves

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are left open. Both the motor operated valves and check valve are Seismic Category 1 for pressure boundary integrity. The controls and power for MO-2947A & B are not safety-grade.

The branch lines from each AFW train combine just prior to connecting to the main feedwater line to each steam generator. A flow element with two flow transmitters and a check valve is in each of the four lines. The check valves prevent backflow from the main feedwater system to the auxiliary feedwater system during normal operation.

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The discharge pressure gages received frequent corrective maintenance attention.

( Recommendation

{ Evaluate suitability of discharge pressure gages and their preventive maintenance to lower the frequency of corrective maintenance, r

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3.3 PUMPS, DRIVERS & CONTROLS This section reviews the pumps, the turbine driver, the diesel driver, r the electric motor driver, and the differential pressure control L circuits.

[ a) Pumps The safety-grade AFW pumps P-102A & B are Bingham, Type MSD, 6 stage,

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4560 RPM, horizontal pumps with a shaf t driven lubrication pump. The turbine driven pump P-102A uses water from the pump casing as coolant L for the oil coolers while the diesel driven pump P-102B uses service water for cooling the lube oil, diesel jacket, and air intercooler.

The pump manufacturer was contacted to see what modifications could be made to improve the NPSH characteristics and increase pump life

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when operated dry. The manufacturer indicated that the impellers supplied have the optimum NPSH requirements and that no further

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modifications could be made. With regard to operating the pump dry, the manufacturer indicated that the wear rings between the impellers and the casing could be changed to rings with graphite inserts. This should substantially increase the capability of the pump to run under

( dry conditions. However, this does not improve operating times when cavitation occurs. Because of the vibration caused by cavitation, the manuf acturer estimates that permanent damage to the pump will

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occur if cavitation exists for longer than 30 seconds.

The electric motor driven AFW pump P-182 is also a Bingham, Type MSO pump but is an 8 stage, 3560 RPM pump. The flow characteristics are

( similar to those of P-102A & B but the NPSH requirements are lower (see Figures 5 & 6). P-182 also has an auxiliary lube oil pump driven by an electric motor which starts first to circulate lube oil

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prior to start of the pump motor. Cooling water for the lube oil cooler is taken from the pump casing and returned to the pump suction.

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Although P-182 is non-seismic, its similarity in size and design to the safety-grade AFW pumps would indicate similar seismic capability.

[ b) Turbine Driver & Controls Turbine Driver K-107A is a Terry, Type GS-2,1045 BHP, 4560 RPM steam

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turbine with Woodward governor models EG-R and EG-M with ramp generators. The turbine is supplied with a motor driven trip &

throttle (T&T) valve M0-3071. Steam is supplied to the turbine from each of the four steam generators through valves CV-1451 to CV-1454.

b (See Figure 2).

[ A '4-way pilot solenoid valve switches air to the actuator to open or close each steam supply valve. Air is supplied from the normal instrument air supply, or from a seismic class I accumulator should

{ the normal air supply fail. The electrical signal to operate the solenoid valves comes from the channel A AFW pump auto start logic.

The solenoids are energized to close (120 volts AC, breaker Ylll4).

Position switches indicate valve positions on local panel C160 and

( control room panel C05.

{ The normally open 3/4 inch branch line that bypasses each steam inlet valve allows 500 pounds per hour of steam through to keep the line hot all the way down to T&T valve M03071.

Steam stop valve M03170 is normally open and is remote-manually I operated either from panel C160 or panel C05. Position switch ZS3170 provides signals to position indicating lights in panels C160 and C05.

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If the trips on T&T valve M03071 are in their reset positions and suction pressure is greater than 0.5 psig (bypassed for 25 seconds on auto start), then M03071 can be opened by an electrical signal from channel A AFW pump autostart logic. Position switch ZS3071 indicates M03071 position on panels C160 and C05.

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Low suction pressure (0.5 psig setpoint) will actua.te-pressure switch

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PS3072C, which in turn energizes a relay and motor starter which

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powers the valve motor to close T&T valve M03071 (valve closure upon I low suction pressure trip is slower than for electrical or mechanical turbine overspeed trips). As a part of the suction piping

( recommendations in Section 3.1, this trip would be modifled.

There are two turbine overspeed trips that close T&T valve M03071 to

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shut off steam: one is electrical and the other is mechanical.

[ The electrical trip signal is derived from a magnetic pickup which monitors the speed of a toothed wheel en the shaf t between turbine l and pump. When the high speed setpoint' (5400 rpm) is reached, relays trip to energize a valve-mounted solenoid which moves the T&T valve

{ trip hook which releases a ;ompressed spring. The valve is slammed shut by this spring and steam pressure on the valve plug.

[ The mechanical overspeed trip is actuated by a spring restrained lever on the periphery of a shaf t-mounted disc. At high turbine speed (5,700 rpm) this lever extends radially due to centrifugal force and strikes a tappet which moves to release a spring-loaded

[ connecting rod. The connecting rod pulls the valve M03071 trip hook so that the valve slams shut. Coincident with this closure a switch is actuated to interrupt power to the T&T valve motor.

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The electrical overspeed trip automatically resets at 4,000 rpm

[ allowing for re-opening of the T&T valve. However, the mechanical overspeed trip must be reset manually at the turbine by

( simultaneously pulling the emergency connecting rod towards the T&T valve and lif ting the trip lever in order to release the trip hook.

( Then M03071 can be remote manually operated to open.

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L When T&T valve M03071 is open, steam flows through the governor valve into turbine K107A. The governor valve is the final element in a

( Woodward control system which regulates governor valve opening, and hence turbine speed. The input to the Woodward control system is a 20-4 na signal from differential pressure controller PDC 3083A which

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in turn receives signals from P102A discharge pressure transmitter PT3083A and main steam pressure transmitter PT514.

The Woodward turbine speed control system includes an adjustable I electronic ramp generator, an electrohydraulic converter and a hydraulic servo piston which actuates the govgrnor valve. The system

[ monitors turbine (and pump) speed by means of a separate magnetic pickup looking at the toothed wheel on the main shaft.

[ Both Terry and Woodward represantatives were contacted to see if any improvements to the design of the turbine controls had been made for the type supplied to Trojan. They both indicated that no specific modifications were recommended and that the model used is still the

( recommended model for the applications. However, the Terry representative did indicate that both GE and Terry had performed separate qualification of components to Class lE requirements. The

{

GE qualification work was done seven years ago. In 1984, Terry-Woodward completed a generic component-by-component Class lE qualification with the intent of being in position to generate documentation for equipment installed prior to their qualification

[ tests and reports.

[ In addition, GE in San Jose was contacted to see if GE had performed any reliability studies on the Terry turbines. The GE representative indicated that there was no such reliability study. However, GE periodically issues Service Information Letters (SIL) to it's clients which cover equipment maintenance, repair, modification, inspection,

( and procedure changes. SIL's that have been issued for the Terry Turbine drivers for pumps in the Reactor Core Isolation Coolant

( (RCIC) system and the High Pressure Core Injection (HPCI) system were reviewed for applicability. SIL No. 351 was found to have information

[

18

(

1 L

regarding calibration of the Woodward governor controls that may be

[ useful for both the turbine and diesel controls. However, a detailed review is necessary to ensure that the calibration parameters are applicable to the controls being used at Trojan.

c) Diesel Driver & Controls Diesel oil is supplied to the diesel driven AFW pump from a 500 gallon day tank through a gravity feed line (see Figure 3). The engine is provided with a closed cooling water system and a pressurized lubrication system complete with pumps, filters, and oil

{ coolers. An oil priming pump maintains engine oil circulating during engine shutdown periods. Two 4000-W heaters maintain engine jacket

[ water temperature between 100*F and 120*F while shut down. Cooling water required for the oil coolers, for the pumps and their drivers and for the engine jacket water heat exchanger is supplied from the SWS. A connection is taken from the service water line to the diesel auxiliary feedwater pump which is provided with a motor-operated

{

valve receives a start signal that opens automatically whenever the diesel auxiliary feedwater pump is started. The service water outlet from the oil cooler and jacket water heat exchangers is drained to

_ the dilution structure.

Upon receiving a start signal, lube oil pump P-168, driven by a 24

[ volt D.C. 1 Hp motor, provides lubrication to the diesel speed increaser. The start signal for the speed increaser lube oil pump comes from the auto-start circuit of the AFW diesel engine. After 3

{ seconds or when lube oil pressure reaches 5 psig, the AFW pump diesel engine driver is cranked by two 24 volt D.C. starting motors (SM1 and SM2). Both P-168 and the starter motors are powered from a dedicated 24 volt nickel-cadmium battery. Battery energy level is

( automatically maintained by a charger. As soon as lube oil pressure in the speed increaser can be maintained at 5 psig by the shaft driven lube cil pump, P-168 is shut off by pressure switch PS3073X.

{

The positive lead to motor PM-168 includes a thermal overload relay 72-QMP168/0L which protects the motor circuit on high current.

19 ma

I L

Diesel engine speed, when running on automatic, is a function of the difference between main steam pressure and pump P1028 discharge

{ An analog signal proportional to this difference is fed pressure.

7 through a differential pressure controller to the Woodward governor L speed control circuits, and then to the Woodward electromechanical operator which actuates the diesel engine throttle rod. Thus, except

( for the actuator, the engine speed control system is the same as that used for speed control of the AFW pump turbine.

[

The automatic trips on the AFW diesel engine were reviewed to determine whether or not some of these trips should be temporarily

{ bypassed on diesel auto start or diesel manual start.

The AFW diesel engine automatic trips are as follows and are discussed in more detail below:

[

1. Overspeed, 1350 + 50 rpm

2. Low lube oil pressure, 15 psig

{ 3. High jacket water temperature, 205'F

4. Low suction pressure 0.5 psig

5. Starter overcrank of 112 seconds

[ All of the above trips actuate relays to energize the diesel engine fuel rack solenoid to shut down the engine. Relay TOS in this shutdown logic keeps the fuel rack solenoid energized for 20 seconds

[

af ter the actuation logic is energized.

1. The overspeed trip protects the engine from potential damage that may result from an overspeed condition and therefore should b not be bypassed at anytime.

2. Relays in the diesel starting circuit are energized 3 seconds after the auto start signal energizes relay TD3. At 3 seconds low oil pressure (LOP) time delay relay T6 is energized and

+

holds for 25 seconds, effectively bypassing the LOP trip until the engine has run long enough to bring the lube oil pressure up

- above the 15 psig setpoint.

20 se

%,,,u,-,..

F

3. Diesel engine water jacket temperature at auto start is

- 100-120*F, a bypass of the high water jacket water temperature L trip at auto start wouid preciude an instrument fatiure from spuriously tripping the pump.

Additionally, when AFW pump diesel engine driver K1078 receives a start signal, valve M03060B automatically opens to supply service water for air intercooler, engine jacket cooling, engine oil cooling, and speed increaser lube oil cooling. The motor starter circuit for this valve contains three thermal overload relays which if actuated could restrict cooling water flow

[

~

causing insufficient cooling water to the diesel.

4. The diesel engine will crank, and may start, with suction

{

pressure below the 0.5 psig setpoint upon receipt of an auto start signal. Immediately thereaf ter, however, the low suction pressure (LSP) trip energizes the coil of time delay relay 62P1028 which, 25 seconds later, interrupts the automatic start b signal, opens the engine start circuit and energizes relay TD5 which trips to energize the fuel rack solenoid to shut down the

( engine.

An LSP trip block is available which, af ter checking valve

{

alignment and CST level, would allow the operator to restart the diesel.

(As part of the suction piping recommendations in Section 3.1, this trip would be modified by Item d).

5. At 3 seconds af ter receipt of an auto start signal, the two

{

diesel engine starter motors SM1 and SM2 begin cranking. If the engine does not fire up, the starter motors crank for 15

[ seconds, stop and rest for 15 seconds and repeat this sequence for a total of 112 seconds. Then at auto start plus 112 seconds

( the starter overcrank trip energizes the coil of relay TD5 and the fuel rack solenoid is energized to the shutdown position.

21

?

The starting motor circuits contain thermal overload relays r SMB-1 and SMB-2. The relays can actuate on high current to open 1

L the starting motor circuits rendering one or both starting motor i unable to crank the diesel.

Each automatic trip on the AFW diesel engine was also reviewed to see how the control system responds when the engine is operating at speed.

When any of the above trips occur at operating speed, the trip signal activates the shutdown logic (which includes relay TDS) to energize b the diesel engine fuel rack solenoid to shutdown the engine.

1. The overspeed trip can occur when the engine speed governor controls are out of adjustment, or are defective.

2. The low lube oil pressure trip can occur when lube oil is low, when pressure switch PS/TS3076X is out of calibration or defective, or when the lube oil pumps are defective.

( 3. The high engine jacket water temperature trip would occur if service water were to be interrupted while the engine is running. This could occur with the present setup if the thermal

{

overload relays in the valve M03060B motor control circuit trip or if service water supply failed.

4. When the AFW diesel engine is at speed, the low suction pressure (LSP) trip energizes the coil of time delay relay 62P102B which, 25 seconds later, interrupts the auto start signal,

[ opens the engine start circuit and activates the logic to energize the fuel rack solenoid to shutdown the engine. As part of the suction piping recommendation in Section 3.1, this trip

{ would be modified.

S 22

u

5. The starter overcrank trip cannot occur when the engine is running.

It was noted in the review that the diesel AFWP starting battery and charger do not have a surveillance requirement, whereas the diesel fire pump does.

, d) Electric Motor Driver & Controls for P-182

[

The electric motor driven pump is powered from non-class 1E, 4.16kV Bus No. AS as shown on Figure 4. The associated auxiliary lube oil pump is powered from the non-class IE, 480V MCC Bus B30 which is connected opposite 4.16K Bus No. A6. P-182 is controlled manually either from the local panel at the pump or remotely from the control room. A low suction pressure trip is provided from PS2955 set at 12 psia. On starting P-182, the auxiliary lube oil pressure reaches 6 psig. At 6 psig, a pressure switch supplied with the pump provides the permissive

{

for starting the main driver motor. This same pressure switch will trip the main driver motor at 3 psi. The auxiliary lube oil pump continues to run until a second pressure switch shuts it down at 15 psig and will restart it upon decreasing pressure at 5 psig. A third pressure switch provides a low lube oil alarm at 3 psig with reset at 6 psig.

The following trips will stop the electric motor driven AFW pump:

1. Low suction pressure, 12 psia, PS-2955.

2. Pump motor overcurrent, phase or ground.

3. Bus undervoltage, 60% 4.16kV, 127-5X.

4. Pump oil pressure low, _3 psig, PS 2949B The motor and all controls are non safety-related.

r 23

t E

L By following procedure ONI-55, the electric motor driven AFW pump can be supplied power from either Emergency Diesel

[

Generator (EDG) by manipulation of a series of breakers and stripping the diesel of all loads prior to starting the pump.

Supporting load studies have verified the EDG load capability but have not determined if any loads beside the AFW pump could

( be left on the EDG or could be added after pump start.

e)

( Differential Pressure Control Pressure transmitters are provided in the discharge line of the auxiliary feedwater pumps and in the main steam lines from the

. steam generators. Discharge and main steam pressure signals enter a summer which transmits a 4-20 ma signal proportional to the pressure difference to a DP controller, which in turn transmits a 20-4 ma signal to the safety-related AFW pump speed control system to maintain a preset differential between the pump discharge and the steam generator. A similar pressure

{ difference signal is used to modulate control valve CV2967 in the non-safety related system.

This control scheme was reviewed with the objective of trying to reduce or stabilize the oscillatory response of the system to startup transients and minimum recirculation testing transients. Interviews were conducted with plant personnel, test results were reviewed and operational verification tests of both the turbine and diesel driven pumps were witnessed. With primary interest in the safety-grade AFW pumps, other schemes

- for controlling the pumps were examined. These included flow

- control, direct reading differential pressure instruments, and two or three element steam generator level control. Although

[ the alternate schemes could in theory improve system stability, or reduce circuit complexity, improvements in reliability were not clearly indicated. Potentials for increasing overspeed trips, inability to test using the recirculation line, available location of sensing points, and increased electronics complexity seem to overshadow any gains offered by the alternative schemes.

24

s L

Simplification and modernization of components of the existing l

( I control scheme appear to offer the improvements in reliability and/or stability with least compromise or penalty in other areas.

Recommendations Arcas where reliability improvements in the pump and drivers, except for the electric motor driven AFW pump, were not as clea'rly identifiable as

( for the suction piping. Possible bypassing or elimination of interlocks

, and automatic protective trips seem to be where some gain in reliability could be made. The interlocks and automatic protective trips were -

reviewed against the need for the pumps to perform their emergency functions, protect the pumps from incapacitating damage and minimizing spurious trips.

The recommendations listed below are aimed at reliability without sacrificing equipment safety, original design intgnt, or operational fl e xi bil i ty.

{

Pumps (All) a) At next scheduled teardown of the pumps, replace wear rings with graphite inserts.

o Under normal circumstances this change will not affect pump reliability, but it will reduce the chance of pump damage if it is inadvertently started with a dry suction.

Turbine Driver (K-107A) a) In *.he rear of panel C160 are thermal overload relays OLI and OL2

( which are in the motor circuit of TAT valve M03071 (reference scheme E-333). If either of these relays actuate, at some random valve position, steam flow to turbine K107A may be severely limited.

{

[

2s r

h Consider removal of, or bypass for emergency starts, of the thermal overload relays OL1 and OL2 in the motor control circuit of valve M03071 as allowed by Reg. Guide 1.106.

o This change will ensure that the TAT valve will perform its safety function during emergency starts, but may allow destructive heating of the motor operator.

{

b) Develop a detailed calibration procedure similar to the procedures given in G.E.'s SIL #351 for HPCI and RCIC turbine governor control system.

o The G.E. procedure consolidates various calibration and trouble shooting procedures throughout the instruction manuals provided by Terry. More detail and a step-by-step sequence required for proper control system calibration reduce confusion and bring out

{

the need for iterative or repetitive steps. Al though the same type of Woodward components are used (EGM Control Box with Ramp Generator Signal Converter Module, and an EGR actuator) the differences in models will require some differences in calibration parameters, most notably polarity of the output and frequency inputs to simulate speed. Therefore, the G.E.

procedures cannot be directly applied to Trojan without detailed review and modification, c) Delete the electrical overspeed trip.

o The mechanical overspeed trip provides required protection.

( d) Seal transmitters PT3072A and PT3083A, and box ATB701 in the pump room from the high moisture environment.

[ e) Provide various revisions to the operating instructions as follows:

01-8-2,Section II.B.4 has voltages on busses Al and A2 stated as 4160ky, rather than 4.160ky, or 4160V.Section III.C.2.f. concerning 26

H L

AFW system realignment for autostart standby, does not provide instruction to the operator for setting the AFW flow control valves CY3004 at the prescribed throttle points. See, for instance, POT-5-1 section 7.3.14.

Section III.D.4.c should also instruct the operator to (upon realignment for autostart standby): place AFW lockout switch in C17

{ to NORMAL, place low suction pressure block switch in NORMAL and place maintenance lockout switch in C160 to NORMAL.

[

0

[

27

5

{

Diesel Driver (K1078) a) Bypass the engine jacket water high temperature trip during aut", start to preclude an instrument failure from spuriously tripping the diesel.

b) Remove or continuously bypass (except during maintenance or testing) the thermal overload relays in the motor starter circuit of M03060B (service water supply valve for diesel cooling) as allowed by Reg.

( Guide 1.106.

O This change will ensure that the service water supply valve will perform it's safety function during emergency starts, but may allow destructive heating of the motor operator.

c) Develop a detailed calibration procedure for the Diesel governor control System. (Reference item (b) for the turbine driver recommendations above). Similar Woodward electronics are used for

( the diesel and turbine control systems.

d) Provide a surveillance requirement for the starting battery similar to the diesel driven fire pump.

Electric Motor Driver & Controls (P-182) i a) Power the auxiliary lube oil pump P-183 from the same power supply as the electric motor driven pump P-182.

o This change will reduce the complexity of the procedure ONI-55 for powering the electric motor driven pump from the EDG's.

b) Add critical position indication on manual valves to the locked valve

( list.

0

( By this addition, flowpath status would be periodically checked.

28

b

[ c) Set low lube oil alarm above low lube oil pump trip.

o This change would provide operator advance warning of possible pump trip, d) Add indication for pump suction pressure and provide local manual override capability for low suction pressure trip.

o This additional indication would provide operator information and local capability to override spurious trips.

Differential Pressure Control a) Replace AFW pump discharge pressure transmitters with more durable, small displacement instrume'nts.

o Increasing the instrument's resistance to pressure spikes observed in the system during operation should prolong instrument life.

b) Change to use multiple inputs from the main steam lines, together with auctioneering of pressures, for control during/following a main steam line break event.

[ .

29 e

% 3.4 Flow Control Valves

~

Flow control valves CV-3004Al through CV-3004D1 are in branch lines to the steam generators from the turbine driven AFW oump P-102A. CV-3004A2 through CV-3004D2 are in the branch lines to the steam generators from the diesel driven AFW pump P-1028. There are manual isolation valves with a position indication upstream and downstream, a check valve and a L flow element with each of the control valves. The control valves are caintained in a normally throttled position to limit the flow through each branch to 162.5 gpm upon automatic initiation of AFW. Each valve is re:ote-manual operated from the local panel C160 or control room panel r C05. Automatic closure of the valve will occur when a high flow of 500 gp3 is sensed by the associated flow indicating switch. Actuation of one flow switch will also lock out the high flow trips of the remaining 3 control valves in the same AFW train.

The Limitorque operators and controllers originally supplied on the flow control valves were recently replaced with new qualified Limitorque motor

( operators without controllers.

Recommendations Tho passive role of the flow control valves for AFW automatic initiation, the multi-path configuration, and redundant AFW systems provide for an extremely reliable flow path arrangement to the steam generators. No changes are recommended. However, proper setting of the torque switches in the Limitorque operators should be checked.

L r

L d

L

" 30 ,

s F

y -

?

" 3.5 Service Water Supply r

In the event that the normal source of water to the safety-grade AFW pucps is not kvailable, service water (SW) can be supplied to the pumps.

Valve MO-3045A can be opened to supply A train SW to the turbine driven AFW pump, and M0-3045B can be opened to supply B train SW to the diesel driven AFW pump. Both valves are remote manually controlled from control

{ room panel C14.

Recommendations None were noted.

1

[

l

[

31

{

(

i . . . . .

c 3.6 OTHER RECOMMENDATIONS a) Pump Room HVAC

( ,

L The two safety grade AFW pumps are contained in separate rooms.

Each room has supply and exhaust fans which supply outside air and

( exhaust room air to the Turbine Building. The turbine pump room supply fan VC-166 and exhaust fan VC-168 circulate 1500 cfm through the room and are powered from the train A safety-related bus. For

{ the diesel pump room, fan VC-165 supplies 24,270 cfm of outside air and fan VC-167 exhausts 21,000 cfm air. The difference is accounted

[ for as combustion air consumed by the diesel engine. VC-165 &

VC-167 are powered from a train 8 safety-related bus. All the fans are started automatically by the same signals that automatically start the AFW pumps, or remote-manually from panel C17 in the control room.

During the plant walkdown, it was observed that the turbine driven pump room was much more humid than the adjacent rooms. This was attributed to tha open equipment drains with hot condensate being constantly drained to the floor drains near the turbine driver.

l b) Electrical device ratings of relays, timers, control switches, and fuses were reviewed for the voltage and current ratings. The review was limited to the comparison of manufacturer's published ratings against the nominal rating of the distribution fuses. The only potential problems identified were timers 62-P102B in the low suction pressure trip circuit of the diesel pump, TD3 in the diesel start circuit and TD5 in the diesel trip circuit. These timers are rated at 24 volt + 10% de, while the circuit may see a voltage of 28 to 30 volts during battery charging.

c)' During system operation, discharge pressure oscillations were observed. System testing could be conducted to identify source and '

impact of the oscillations during post modification system checkout.

[

32

Recommendations r

l a) Modify equipment drains to route hot condensate directly to the drain

~ system.

L Advantage:

o This modification would reduce equipment exposure to prolonged f

L high humidity environment.

b) Replace timers 62-P1028, TD3, and TDS with components with increased vol tage capability.

c) Conduct testing of system to identify source of pressure oscillations when system check out is conducted af ter modifications.

r l

L M

i 33 e

l -

L 3.7 Summary of Recommendations L

Listed below are the recommended changes described in Section 3.1 through 3.6 for the Trojan AFW system.

Suction Piping (a) Upgrade suction piping to Seismic Category I (b) Delete the common suction line isolation valve (c) Install a safety grade CST level detection system (d) Modify the pump trip circuit to place CST low level in series with low suction pressure to affect a trip (e) Replace the low suction pressure instrument with one of increased range and lower the setpoint (f) Provide MCR alarms of both low suction pressure and low CST level (g) Evaluate suitability of suction pressure gages-components and preventive maintenance.

[ Discharge Piping

( Evaluate the suitability of pressure gages and their required preventive caintenance.

Pucps Replace wear rings with graphite inserts.

Turbine Driver a) Bypass thermal overload relays OLI and OL2 in the motor control circuit of the trip and throttle valve M0-3071.

b) Develop a detailed calibration procedure for the turbine governor control system.

34

F L

c) Delete the electrical overspeed trip, d) Seal two transmitters and a junction box from moisture.

[ e) Revise operating instructions. .

)

Diesel Driver a) Bypass the engine jacket water high temperature trip on autostart b) Bypass thermal overload relays on service water supply valve M0-30608 for cooling water.

c) Develop a detailed calibration procedure for the Diesel governor control system.

d) Add surveillance requirement for the starting battery.

Electric Motor Driver l a) Power the auxiliary lube oil pump P-183 from the same power l supply as the electric motor driven pump P-182.

b) Add critical valves to locked valve list.

c) Set low lube oil alarm setpoint above low lube oil pump trip, d) Add indication for pump suction pressure and provide local manual override capability for low suction pressure trip.

Differential Pressure and Control

[ a) Replace the AFW pump discharge pressure transmitters with more durable, small displacement instruments.

[

35

L b) Utilize multiple input pressure signals from main steam lines y together with an auctioneering circuit.

L Flcw Control Valves No recommended changes.

[,

Service Water Supply No recommended changes.

( Other Recommendations a) Modify equipment drains to route hot condensate directly to the drain system.

b) Replace 3 timers with models of increased voltage capability.

c) Perform system testing to identify source of discharge pressure oscillations.

[

( 36

L E

[

FIGURES c

[

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Figure 4 SIMPLIFIED ELECTRICAL SINGLE LINE FOR ELECTRIC MOTOR DRIVER AFW PUMP P -182 i MAIN TRANSFORMERS

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[

REFERENCES

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F L

REFERENCES

[

SECTION 2. GENERAL SYSTEM DESCRIPTION

{

l. Trojan Nuclear Plant Updated Final Safety Analysis Report, July 1982.

2. Trojan Nuclear Plant Technical Specifications.

( 3. Trojan Nuclear Plant Training Manual: Section 12, Auxiliary Feedwater Systems.

( 4. Trojan Nuclear Plant Operating Manual:

General Operating Procedures:

[ GOI-1, Rev.' 24, 7/23/85. Plant Startup From Cold Shutdown to Hot Standby.

GOI-2, Rev. 22, 7/23/85. Plant Startup From Hot Shutdown to

( Power Operation.

Operating Instructions: l OI-8-2, Rev. 19, 6/29/85. Auxiliary Feedwater.

Off-Normal Instructions:

[

ONI-50, Rev. 1, 12/28/84. Plant Operations After A Loss of Off-Site Power.

ONI-55, Rev. O, 7/26/82. Operation of Electric AFP Supplied by

[. EDG.

Emergency Instructions:

EI-4, Rev. 10, 5/17/84. Loss of All AC Power.

5. Trojan Nuclear Plant Periodic Operating Tests:

{

POT-5-1, Rev. 21, 11/4/83. Auxiliary Feedwater System, Pump and Valve Inservice Test.

[- POT-5-2, Rev. 10, 6/10/83. Auxiliary Feedwater System, Valve Lineups and Inservice Testing.

POT-5-3, Rev. 9, 8/6/85. Auxiliary Feedwater System, System

( Performance and Valve Inservice Test.

6. TPT-125, Rev. O, 4/30/85. Temporary Plant Test, Auxiliary Feedwater Pump Suction Transmitters

[ Data Acquisition.

7. TPT-143, Rev. 1, 8/6/85. Temporary Plant Test, AFW Pump

( Auton; tart Test.

r L

8. Design Review of Turbine-Driven Auxiliary Feedwater Pump Suction Pressure Transmitter, Trojan Nuclear Plant, Portland General Electric

[ Company, Nuclear Plant Engineering Department, 6/17/85. .

9. Report No. D06320, Human Engineering Discrepancies, 12/27/84.

l'

[ 10. Trojan Nuclear Plant Civil Drawings:

C-103, Rev. 8. Typical Details, Concrete, Sheet 3.

[ C-907, Rev. 12. Miscellaneous Structures., Foundations for Tanks., Plans & Sections.

( 11. Trojan Nuclear Plant Electrical Drawings:

E-1, Rev. 10. Plant Single Line Diagram.

E-26, Rev. 12. Electrical Device Index.

{ E-1266, Rev. 2 H&V Fans, Auxiliary Feedwater Pump Room (Logic).

( 12. Trojan Nuclear Plant "M" Drawings:

M-1, Rev. 3. Plant General Arrangement Plan - Ground Floor & Below.

{ M-60, Rev. 30. Piping & Mechanical Area 5 - Reactor Containment, Misc. Sect. & Dets.

M-66, Rev. 26. Piping & Mechanical Area'7 - Turbine &

[ Auxiliary Building, Plan at El. 45 -7".

M-80, Rev. 27. Piping & Mechanical Area 10 - Turbine Building Plan, El. 45'-0".

M-88, Rev. 23. Piping & Mechanical Area 11 - Turbine

( Building Plan, El. 45'-0".

M-148, Rev. 20. Piping & Mechanical Area 19 - Process Yard Piping.

[ M-245, Rev. 12. Air Flow Diagram, Turbine & Containment Bldg. Ventilating & Cooling Systems.

M-290, Rev. 12. HVAC, Turbine' Building' Area 7, Plan &

( Section, El. 45 -0" & El. 93 -0".

13. Trojan Nuclear Plant Instrument Index:

Rev. 23, Numeric Sort.

14. USNRC Regulatory Documents:

NUREG-0578: Generic Evaluation of Feedwater Transients and Small Break Loss-of-Coolant Accidents in Westinghouse -

Designed Operating Plants. July 1979.

{

NUREG-0611: General Evaluation of Feedwater Transients and Small

( Break Loss-of-Coolant Accidents in Westinghouse -

L Designed Operating Plants.

NUREG-0737: Classification of TMI-2 Action Plan Requirements, November 1980.

.t_

r s '

r w

NUREG-1032: Evaluation of Station Blackout Accidents at Nuclear p Power Plants, Technical Findings Related to Unresolved L Safety Issue A-44. May 1985.

NUREG-ll54: Loss of Main and Auxiliary Feedwater Event at the

[ Davis-Besse Plant on June 9, 1985.

Regulatory Guide 1.106, Rev. 1, March 1977. Thermal Overload

[ Protection for Electric Motors on Motor-Operated Valves, h IE Information Notice No. 85-50: Complete Loss of Main and Auxiliary Feedwater Event at a PWR Designed by Babcock & Wilcox,

{ July 8, 1985.

p 15. Trojan Nuclear Plant Environmental Qualification Program Manual, L PGE-1025, July 1985.

16. Trojan Nuclear Plant Regulatory Guide Policy Manual, PGE-1028, July 1985.

{

17. Trojan Nuclear Plant Licensee Event Reports, 1979-1985.

s Report Numbers: 76-02, 76-04,76-04A, 76-04B, 76-05, 76-12, 76-14, 76-15, 76-17, 76-19, 76-24, 76-56, 76-57, 76-60 and 76-65; 7"-06, 77-43, 77-45 and 77-46;

[ 30-15, 80-18 and 50-24., 83-02, 83-12 and 83-22.,84-016

18. Various Correspondence: NRC to PGE/PGE to NRC, 1979-1985.

19. Trojan-Specific Probability Risk Analyses:

[ Reliability Assessment of the Trojan Auxiliary Feedwater System.

Inter-mountain Technologies, Inc. , December 28, 1979, f Technical Evaluation Report: Auxiliary Feedwater System Automatic L Initiation and Flow Indication, Portland General Electric Co., Trojan Nuclear Plant. Franklin Research Center, March 3, 1982.

i

( INPO Memorandum dated 10/19/84: Lawson to Paleologos & Beard.

Subject:

Trojan Special Assist Visit. Review of Events Leading to Plant Trips of September 20 and September 26, 1984.

INPO Special Assistance Visit Report', December 1984.

Sequence Risk Analysis for Loss of Main Feedwater ,and Loss of

_ Off-Site Power Events at Trojan. Institute of Nuclear Power Operations, March 1985.

[

E L

20. Probability and Reliability Analyses for Other Plants.

Probability Analysis of Diablo Canyon Auxiliary Feedwater System.

Document PLG-0140. Pickard, Lowe and Garrick, Inc., July 8, 1980.

Status Report, Rancho Seco Auxiliary Feedwater System Upgrade Review, March-April 1983.

- Palo Verde Nuclear Generating Station Auxiliary Feedwater System Reliability Analysis.

[ Reliability Analysis of the SNUPPS Auxiliary Feedwater System, May 1984.

South Texas Project Auxiliary Feedwater System Reliability Evaluation, May 1985.

4

[

r

[ .

[

L

/

SECTION 3.1 SUCTION PIPING 7 1. Trojan Nuclear Plant Civil Drawings C-907, Rev. 12. Miscellaneous Structures., Foundations for Tanks., Plans & Sections.

2. Trojan Nuclear Plant Electrical Drawings E-213, Rev. 7. Typical 480V Motor Control Center, Full Voltage

[ Reversing Motor Controllers.

E-332, Rev. 18. Auxiliary Feedwater Pump Diesel Controls.

E-333, Rev. 15. Auxiliary Feedwater Pump Turbine Control Valve,

{ E-381, Rev. 4.

Sh. 1.

Condensate System MOV's.

E-1133A, Rev. O. Auxiliary Feedwater Pump West, P-102A, Channel

'A'.

E-ll34A, Rev. 3. Auxiliary Feedwater Pump East, P-102B, Channel

'B'.

E-1545, Rev. 16. Annunciators:, Radwaste, Diesel Oil, H&V, Aux.

F.W., Sh. 2.

E-1559, Rev. 14. Auxiliary Feedwater Control Panel Annunciator, Sh. 1.

E-1624, Rev. 2. Digital Computer Inputs, Miscellaneous, Sh. 4.

E-1705, Rev. 4. CST Instrumentation Loops.

E-2072A, Rev. 6 Startup Auxiliary Feedwater Pump, Sh. 2.

E-2170, Rev. 3. Auxiliary Feedwater Control Panel Annunciator, Sh. 2.

E-2171, Rev. 8. Auxiliary Feedwater Control Panel Annunciator, Sh. 3.

E-2172, Rev. 5.

[ Auxiliary Feedwater Control Panel Annunciator, Sh. 4.

E-2300, Rev. 4. Startup Auxiliary Feedwater Pump P-182.

b 3. Trojan Nuclear Plant, Instrument Data Sheets:

M-513, Sh. 1, Rev. 5. Pressure Transmitters.

M-516, Sh. 2, Rev. 6.

{ M-534, Sh. 1, Rev. 6.

Pressure Gauges.

M-534, Sh. 12, Rev. 2.

Differential Pressure Transmitters.

[ 4. Trojan Nuclear Plant, Level Setting Diagram:

M-537, Sh. 10, Rev. 3. Condensate Storage Tank T-105.

1

[

1

[

r 5. Trojan Nuclear Plant "M" Drawings:

L M-56, Rev. 28. Piping & Mechanical Area 5 Reactor

- Containment Plan of El. 45'-6".

" M-142, Rev. 15. Piping & Mechanical Area 7 & 8 Turbine Aux.

Building Plan Below El. 45'-0".

M-149, Rev. 22. Piping and Mechanical - Process Yard Piping r Sections.

L

6. Trojan Nuclear Plant Piping and Instrumentation Diagrams:

[ M-213, Sh. 1, Rev. 26. Condensate and Feedwater System.

M-218, Rev. 30. Service Water System.

M-228, Rev. 28. Make-up Water Treatment System.

M-236, Rev. 10. Condensate and Feedwater Chemical Injection

[ System.

7. Vendor Documents:

6478-Cl4-53-10 6478-C14-101-6 6478-C14-102-3 6478-C14-103-3 6478-C14-105-4

8. Contractor Drawing:

HUICO Dw9. No. HBD-43-1, Rev. 15. Auxiliary Feedwater 8" & 6"

[ HBD-43.

9. Comments on the Trojan Nuclear Plant Regulatory Guide 1.97 Qualification Review. Bechtel Power Corporation, Operating Plant

[ Services, July 1984.

10. Seismic Design of Liquid Storage Tanks, by Haroun and Housner.

' Published in the Journal of Technical Councils of ASCE, Proceedings of the American Society of Civil Engineers, Vol. 107, No. TCI, April 1981.

I

+

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N f

y SECTION 3.2 DISCHARGE PIPING

l. Trojan Nuclear Plant Electrical Drawings:

L E-213, Rev. 7. Typ' cal 480V Motor Control Center Full Voltage Reversing Motor Controllers.

E-556, Rev. 8. Turbine & FW Valve Lights.

c' E-556A, Rev. O. Turbine & FW Valve Lights.

L E-559, Rev. 10. Turbine & FW Valve Lights.

E-559A, Rev. O. Turbine & FW Valve Lights..

E-637A, Rev. 2. Aux. Feedwater Flow Valves Control &

" Lock-Out Circuit.

E-637B, Rev. 1. Aux. Feedwater Flow Valves Control &

Lock-Out Circuit. t E-694, Rev. 14, Indicator Instrument Loop, Sheet 4. j

[ E-763, Rev. 3. Instrumentation - Main Steam Gen. Pressure I Control.

p E-1133, Rev. 7. Auxiliary Feedwater Pump West, P-102A,

[ E-ll34, Rev. 7.

Channel 'A'.

Auxiliary Feedwater Pump East, P-102B, )

Channel 'B'.

E-1285, Rev. 3. Auxiliary Feedwater Pump Valves.

E-1559, Rev. 14. Auxiliary Feedwater Control Panel Annunciator, Sh. 1.

E-1575, Rev. 16. Annunciators - Miscellaneous.

E-1722, Rev. 13. Pressure Loop for Aux. F.W. Pump Speed Control.

E-1727, Rev. 13. Miscellaneous Instrumentation.

E-1852, Rev. 5. Auxiliary F.W. Valve Lock-Out Circuit.

[ E-2171, Rev. 8. Auxiliary Feedwater Control Panel Annunciator, Sh. 3.

E-2178, Rev. 2. Auxiliary Feedwater Flow Indication, Sh. 2.

[ E-2181, REv. 3. Startup Auxiliary Feedwater Pump P-182 Discharge Valves M02947A&B.

E-2316, Rev. 1. Startup Auxiliary Feedwater Pump P-182 ,

Discharge Valves. {

{ l

2. Trojan Nuclear Plant Instrument Data Sheets:

L M-513, Sh. 13, Rev. 3. Pressure Transmitters. '

M-516, Sh. 2, Rev. 6. Pressure Gauges, j M-523, Sh. 16, Rev. 5. Differential Pressure Transmitters. '

M-525, Sh. 4, Rev. 2. Orifice Plates.

M-526, Sh. 6, Rev. 1. Differential Pressure.

M-541, Sh. 11, Rev. 3. Control Valves.

M-581, Sh. 1, Rev. 4. Receivers & Controllers.

3. Trojan Nuclear Plant "M" Drawings: '

M-99, Rev. 22. Piping .& Mechanical Area 5 Reactor Containment - Misc. Details.

F 5

s

i

4. Trojan Nuclear Plant Piping and Instrumentation Diagrams:

[ M-213, Sh. 1, Rev. 26. Condensate & Feedwater System.

M-213, Sh. 2, Rev. 5. Condensate & Feedwater System.

[ 5. Vendor Documents:

6478-M-12-22. Pressure Readout System Schematics.

6478-N12816-2-1. Operation and Maintenance Instructions,

[ Self-Drag Velocity Control Element (for tag number CV2967).

( 6. Comments on the Trojan Nuclear Plant Regulatory Guide 1.97 Qualification Review. Bechtel Power Corporation, Operating Plant Services, July 1984.

[

SECTION 3.3 PUMP DRIVERS AND CONTROLS

[ 1. Trojan Nuclear Plant Electric Drawings:

E-326, Rev. 9. Auxiliary Feedwater Pump Turbine Control Valve, Sh. 2.

[ E-331, Rev. 4. 4160V Non-Engineered Safeguard Bus Lockout &

Undervoltage Relays.

/ E-332, Rev. 18. Auxiliary Feedwater Pump Diesel Controls.

L E-332A, Rev. 5. Diesel Auxiliary Feedwater Pump Controls.

E-332B, Rev. O. Auxiliary Feedwater Pump Diesel Controls.

E-333, Rev. 16. Auxiliary Feedwater Pump "urbine Control

[ E-333A, Rev. 2.

valve Sh. 1.

Auxiliary Feedwater Pump Turbine Control valve.

E-372, Rev. 14. Auxiliary Feedwater Pump Turbine Steam Inlet

[ valves.

E-373, Rev. 15. Auxiliary Feedwater Pump Auto Start & S.G.

Blowdown Isolation - Sh. 1.

( E-374, Rev. 12. Auxiliary Feedwater Pump Auto Start & S.G.

Blowdown Isolation - Sh. 2.

E-418, Rev. 11. Service Water to Aux. FW PP Cooler Valve (M030608).

[ E-763, Rev. 3. Instrumentation - Main Steam Gen. Pressure Control.

E-1133, Rev. 7. Auxiliary Feedwater Pump West P-102A, Channel 'A'.

E-1133A, Rev. O. Auxiliary. Feedwater Pump West P-102A, Channel 'A'.

[

E-1134, Rev. 7. Auxiliary Feedwater Pump East P-102B, Channel 'B'.

E-ll34A, Rev. 3. Auxiliary Feedwater Pump East P-102B, Channel 'B'.

[

E-1559, Rev. 14. Auxiliary Feedwater Control Panel F

Annunciator, Sh. 1.

E-1575, Rev. 16. Annunciators Miscellaneout.

E-1728, Rev. 1. Auxiliary F.W. Turbine Instrumentation.

s E-1762, Rev. 1. Multipoint Temperature Recorder - Panel i C160.

E-1858, Rev. 3. Auxiliary F.W. Pump Diesel Speed Increaser

, Aux. L.O. Pump i E-1881, Rev. 5. Auxiliary F.W. Pump Diesel Controls.

E-2072, Rev. 6. Startup Auxiliary Feedwater Pump, Sh. 1.

E-2072A, Rev. 6. Startup Auxiliary Feedwater Pump, Sh. 2.

E-2072B, Rev. 2. Startup Auxiliary Feedwater Pump, Sh. 3.

s E-2170, Rev. 3. Auxiliary Feedwater Control Panel Annunciator, Sh. 2.

E-2171, Rev. 8. Auxiliary Feedwater Control Panel Annunciator, Sh. 3.

E-2172, Rev. 5. Auxiliary Feedwater Control Panel Annunciator, Sh. 4.

E-2300, Rev. 4. Startup Auxiliary Feedwater Pump P-182.

E-5051, Rev. 4. Startup AFW Pump Aux. Lube Oil Pump Scheme No. NB3045.

2. Trojan Nuclear Plant Connection Diagram:

E-1466, Rev. 16. Auxiliary F.W. Pump Terminal Boxes ATB701, ATB702 and BTB701.

3. Trojan Nuclear Plant Piping and Instrumentation Diagrams:

( M-208, M-213, Rev. 23.

Sh. 1, Rev. 26.

Main Steam System.

Condensate & Feedwater System.

M-214, Rev. 31. Auxiliary Steam System.

M-218, Rev. 30. Service Water System.

[ M-226, Rev. 16. Diesel Fuel Oil System.

p 4. Vendor Documents:

L 6478-M12-36. Auxiliary Feedwater Pump Diesel Control.

6478-M12-53. Engine Connection Diagram.

" 6478-M12-54. Auxiliary Feedwater Pumps Tech. Manual.

6478-M12-55. Diesel Engine Driver Tech. Manual.

6478-M12-56. Jacket Water Piping & Electrical Waukesha p Motor Co. Dwg. SKD-4192-A.

L 6478-M12-61. Auxiliary Feedwater Pump Tech. Manual.

6478-N14440-10. Installation, Operation, Maintenance. MSD, MSD-D, MSE Bingham-Willamette Multi-Stage L Horizontal Pumps 6478-N17258-2. Anchor / Darling Dwg. 8714-01. 3'-6006 Gate, Air Operator Conversion Kit.

5. Auxiliary Feedwater Pump Steam Turbine Driver. Report MOO 1496, prepared for Mitsubishi Heavy Industries, Ltd. by Bechtel Power g Corp., November 1982.

( ,

I i

L SECTION 3.4 FLOW CONTROL VALVES

1. RDC 84-104: Replace Motor Operators for AFW Control Valves.

2. RDC 84-105: Replace AFW Flow Indicating Switches.

3. Trojan Nuclear Plant Electrical Drawings:

{

E-637A, Rev. 2. Aux. Feedwater Flow Valves Control & Lock-Out Circuit.

( E-637B, Rev. 1. Aux. Feedwater Flow Valves Control & Lock-Out Circuit.

E-1285, Rev. 3. Auxiliary Feedwater Pump Valves.

E-1852, Rev. 5. Auxiliary FW Valve Lockout Circuit.

{

4. Trojan Nuclear Plant Instrument Data Sheets.

M-525, Sh. 10, Rev. 1. Orifice Plates.

M-526, Sh. 6, Rev. 1. Differential Press. Switches.

M-541, Sh. 11, Rev. 3. Control Valves.

5. Trojan Nuclear Plant Piping and Instrumentation Diagram:

M-213, Sheet 2, Rev. 5. Condensate & Feedwater System.

6. Vendor Document:

6478-M204A-130-5: Limitorque Wiring Diagram.

{

Limitorque Dwg. No. 15-480-0055-3 (includes turbine and diesel valve settings).

[ SECTION 3.5 SERVICE WATER SYSTEM

l. Trojan Nuclear Plant Electrical Drawings:

E-381, Rev. 4. Condensate System MOV's.

E-418, Rev. 11. Service Water to Aux. FW PP Cooler Valves.

1

2. Trojan Nuclear Plant Piping and Instrumentation Diagram: 1 1

1 M-213, Sheet 1, Rev. 26. Condensate & Feedwater System.

[ M-213, Sheet 2, Rev. 5. Condensate & Feedwater System.

l l

M-218, Rev. 30. Service Water System. '

[

[ l

L l

[

SUPPLIER CONTACTS

[

m l

[

m

[

O

- .i

R. W. Fosse , ,

"- "* o <>

. TELEPHONE g W. Sherwood

{

, 3 nc # Tn9947n F i t.E DATE

" Jim Rayner Bingham Pumps 750 8/29/85 JO8 NO. TIME To B.C. Acosta/M. Nakao Bechtel 11760-124 3:30 p.m.

( ACTION REO'D. (INCLUDE NAMES & OATES)

BTEMS OF DISCUSSION

SUBJECT:

Aux. FW Pumps Arked Jim how long can the AFW Bingham pumps bo operated on very low suction pressure

[ bsfore any damage to the pumps occurs. Jim 1

said that PGE previously asked the same question. He said that damage occurs in about 30 seconds. The first item to go would be the saals and later the bearings because of excessive vibration.

Masa explained to Jim the nature of the work being done in relation to the operation of the aux. FW pumps at Trojan.

[

[ !

_. . m s.

[

c R. W. Fosse , ,

c TELEPHONE e " "=* o . >

[ lB. Acosta , ,

. S en d , ,

DC #T022536 F H.E AFW Revie'up^rE

( "

" Bien Acosta/ Bill Sherwood ' Bechtel 124 9/9/85 JOB No. TIME Bob Roberts / Ken Wheeler Terry Turbine Div.ll760-124 1035 hours0.012 days 0.288 hours 0.00171 weeks 3.938175e-4 months

~~iEus i or ossCussioN ACTION REQ'D. UNCLUDE NAMES & DATES)

Ra: Governor on Trojan AFWP turbine driver

[ The Woodward Model R8250-033 has been in place -

since 1976.

Roberts said same governor was sold to TVA (Sequoyah 1 & 2), Florida Power & Light (St. Lucie), Arkansas Power and Light (Arkansas Nuclear One), Alabama Power .

(Farley).

There has been no update on the control electronics. That is, no modifications have been made on governor and governor electronics

.since 1976.

Roberts doesn't know whether later type governors can be applied to existing turbine installation.

Ken Wheeler said the GE and Woodward separatel v, have both analified Woodward governors for

[ clnac 1F appl i cations (Wheeler is in Terrv.

nuclear dept.)

0046 t2-756

[

a

TELEPHONE e s BEE PAGE 1 s

d page 2 of 2

- CALLS DC #T022536 8 <>

i '

F ' 'E DATE p

)

1 OLL FAUL 1 JOS NO. TIME ITEM 8 OF DISCUSSION ACTION REQ'D. IINCLUDE NAMES es DATES)

GE did their qualification work 7-8 years ago. Terry / Woodward finished qualification h work last year. Terry / Woodward did a generic ,

component by component Class lE qualification with the intent of being in position to generate documentation for equipment installe i prior to their qualification tests and report s.

If any questions regarding availability of this documentation, call Russ Hebert at -

L above number.

u a

s s

0046(2-75) i i

)

W R. Fosse , ,

TELEPHONE < l o

W. Sherwood ' '

CALLS DC #T022553 <>

FILE DATE

' " " Gerry Clodius/ Jim Kelso

" GE 750 9/10/85 aos No. riue

- 'O B. C. Acosta " Bechtel 11770-124 1:30 p.m.

ITEMS OF DISCUSSION ACTION REQ'D.(INCLUDE NAMES & DATES)

L

SUBJECT:

TERRY TURBINES Asked Clodius if they have made any reliabilit y ctudy of Terry turbines. Kelso said that GE does not have any reliability study on Terry trubines to date.

L e

L L

L W

~

0046 (2 75)

n. Fossa r TELEPHONE : - "*e Sherwood ll

( o W.

CALLS DC #T022590 t 8 FILE DATE

" " Jim Reynar " Bingham 750 9/16/85 JOS NO. TIME B. C. Acosta Bechtel 11760-124 33 gg ,,g_

ITEMS OF DISCUSSION ACTION REQ'D. (INCLUDE NAMES & DATES)

SUBJECT:

Diesel & Turbine Driven AFW Pumps

[ (Earlier Bingham was asked what would be the needed modifications to the AFW pumps if the pumps are allowed to run dry without damaging the pumps. The initial response given to me was to replace the wear rings with carbon inserts to the wearing parts.)

Jim asked if Bingham should pursue this modification to the Trojan AFW pumps.

Told Jim that we need the information in orde r to make a recommendation to PGE for AFW pump

[ reliability improvement.

Jim also gave me the following critical speeds of the AFW pumps:

At 4560 rpm - critical speed is 8100 rpm, wet 3000 rpm - critical speed is 6600 rpm, wet.

[

004642 75)

[

N Ik. W . Fosse ,

. TELEPHONE e = a akao - , ,

l W. Sherwood , ,

- DC #T022587 ( 8 F LE DATE rno" Dan Hoffman " Waukesha 750 9/16/85 JO8 NO. TIME To B. C. Acosta ' Bechtel 11760-124 9 no n.m.

ITEMS OF DISCUSSION ACTION REQ *D.11NCLUDE N AMES & DATES)

SUBJECT:

TROJAN AFW PUMP DIESEL DRIVER (Earlier, Dan Hoffman of Waukesha was asked I

if there is an improved type of Woodward governor for the Waukesha engine driven AFW pump at Trojan. The serial no. for the engine isEf'21035 2 & Model No. L5790-DSlU).

Dan told me that the Woodward governor supplie41 _

cith the diesel driver for the Trojan AFW

(

pump is the best available and no modification

[ has been made so far. Since there was a governor overspeed problem, Dan suggested u to contact their Portland representative, y Their distributor - representative is KEM Equipment at (503) 692-5012.

V W

N GM6 t245a

I W

4 f

L r

I L APPENDIX c

u P

u

[

c l

I W

W W

Y W

~

in . . .

L r APPENDIX L

RELIABILITY AND MAINTENANCE DATA REVIEW I

1.0 INTRODUCTION

P This Appendix presents results of a limited review of generic component L failure rates and failure-upon-demand probabilities for equipments of the types used in the Trojan Huclear-Plant Auxiliary Feedwater (AFW) System c (section 2). Also included, as section 3, are tabulations of AFW System L Maintenance Requests (MR's) by year and equipment category, and a tabulation of Licensee Event Reports (LER's) by year and equipment category.

2.0 COMPONENT RELIABILITY INVESTIGATIONS The Nuclear Plant Reliability Data System (NPRDS) provides the total number of components reported in use, the number of reported failures of these components, dates operated and failed, and narratives for some of the reported failures. The reported failures are not normalized to operating hours or the number of demands. However, this information is specific to component

{- vendor, model number and ranges of operating parameters.

The NPRDS summary report (reference 2) provided failure data on similar

[ component types used in the Trojan AFW system. This data is exhibited in Table ,1.

NUREG-0020 (reference 3) was scanned but did not provide enough information

[ to be useful.

The failure upon demand probabilities, numbers of failures of sub-system

[ components and other data displayed in INP0 85-036 (reference 1) provide relevant general insights into AFW component and system average performance ,

from all U.S. nuclear plants. The supplementary letter, INP0 to PGE 9/27/85, i

( makes a specific comparison of Trojan AFW system performance to the above averaged performances.

I

[ WASH-1400 was reviewed for generic failure upon demand probabilities and L operating failure rates of nuclear plant components. WASH-1400 was also used for definitions of basic terms and to gain a better understanding of y fundamental concepts.

L IEEE-Std. 500-1984 was also reviewed for failure data on generic components.

Data in IEEE 500 is given in terms of failures /million hours or failures /

I million cycles, the latter being equivalent to f ailures/ demand in WASH-1400.

L The data here are intended for:

e 1. Determination of system adequacy L 2. Evaluation of system design alternatives

3. Evaluation of, or contribution to, system test intervals, maintenance -

programs or operating procedures, or both.

4. Contribute to probabilistic risk assessment studies.

_y v A-1 r

L W

e

r L

2.1 Results

( Table 1 shows industry failure data for selected Trojan AFW component types. The data in Table 1 are not restricted to AFW systems. Any single reported component in Table 1 (or NPRDS) can have more than one reported failure.

{

Where only a small number of components has been reported, no solid conclu-stons can be drawn from the failure data. The Waukesha engine failures

[ could have been due to its governor or any of its auxiliary support and control systems. The turbine failures coulo have been caused by the governor, the trip and throttle valve, overspeed trip, or any of the auxiliary support and control systems. The majority of Woodward governor " failures" were

{' caused by incorrect adjustments. ITT-Barton flow switches usually failed by i drifting out of tolerance, apparently due to long intervals between maintenance and calibration activities. Limitorque geared operators failed because of

[ .

infrequent maintenance and improper torque switch adjustment.

2.2 Conclusions of Reliability Data Review

{

These investigations did not uncover any new information about the AFW systems component failures.

The findings in INP0-85-036 are more meaningful than data obtained from NPRDS alone because INP0 85-036 results are derived from NPRDS and other sources;

( and because INP0 has calculated demand probabilities from this combined data.

[

c L

A-2 L

r

L W

1 3.0 MAINTENANCE DATA REVIEW I

3.1 INTRODUCTION

SUMMARY

e There were 525 Maintenance Requests (MR) and 39 Licensee Event Reports L (LER) reviewed. Except for the governor /overspeed problem on both turbine and diesel drivers, the occurrence and subject of the MRs and LERs appear r unrelated. Pump suction and discharge (turbine pump only) pressure and flow l

instrumentation caused a significant number of MRs. The instrumentation (indicators and transmitters) should be evaluated for replacement with a ,

more suitable model and/or determine the adequacy of the routine mainte-nance procedures and frequency of preventative maintenance.

{

A description of each reviewed item follows and covers 1) Summary of LERs;

2) Summary of MRs, and 3) Correlation between MRs and LERs. Attached are

[ 1) a list of LERs reviewed (Table 2); 2) a table showing the category and year of occurrence of LERs (Table 3); 3) a list of MRs reviewed (Table 4);

4) a table showing the category and year of occurrence of MRs (Table 5);

5) graph showing the MR results (Figs. I and 2); and 6) a graph showing

[ the LER results (Fig. 3).

3.2

SUMMARY

OF LICENSEE EVENT REPORTS

[

Diesel Pump Pump overspeed trips make up a large part of the LERs. Problems include

[ improper overspeed trip setpoints, lack of oil supply during cold start, and loss of governor signal. However, the overspeed LERs ( 6 of 7) are in the startup phase of the plant 1975-77. Since that time, only one overspeed

[ related LER (1983) has been issued. Operator and maintenance errors (7 items) have contributed greatly to pump start failure.

Diesel Driver

(

Five failures occurred with different components. The only repeat was a r crack in the fuel line fitting. Personnel error contributed to the remaining u four items. The last LER was written in 1979.

, Turbine Pump Again, pump overspeed trips make up a large part of the documented events.

These trips are due to failures of the governor, lack of oil supply during cold start, faulty limit switches and operator error. 5 of 6 LERs are in the startup phase, 1975-77. Since then only one (in 1983 - operator error) trip event occurred. Pump failure to start was caused by the torque switch

- not being set properly, grease buildup on the torque switch and 3 problems with the trip and throttle valve.

Turbine Driver The turbine-related LERs include a broken lube oil pump shaft, and seismic restraints not installed. These LERs have not repeated.

A-3 s

/

s r

Control Valves 7 These LERs concern violation of 10CFR50 due to 1) no functional testing L performed on CVs following seismic excitation and 2) water damage to the valve operator through a leaking gasket.

[ 3.3

SUMMARY

OF MAINTENANCE REQUESTS Turbine Pump A large number of turbine pump related MRs (about half) involve the pump discharge and suction pressure gauge and transmitters. Instruments were i r either replaced or recalibrated. At the present rate of occurrence, these i

[ items will continue to be major system maintenance items. These instruments should be evaluated for replacement by more reliable models, and the routine maintenance procedures should be reviewed and modified as deemed necessary.

Turbine Driver Nearly half of the MRs occurred during the startup phase of 1975-77. A

( major contributor was the governor. 16 of the 18 items occurred in 1975-76 and none have occurred since 1980. Periodic preventive maintenance for the driver is not reflected in the MRs.

Diesel Pump Pump suction, discharge and controller pressure instrumentation and the

( oil system are the major maintenance items. The failures of the pressure instruments were not identified as causing system trips when the fault was detected. The pressure instrument items include erroneous readings requiring recalibration and replacement of faulty gauges. The pump

[ controller pressure and pump discharge pressure problems appear to be resolved since there are no occurrences since 1977 and 1981, respectively.

The pump suction pressure problem is still occurring and the suction pressure

[ instruments should be evaluated for replacement.by more reliable models.

Additionally, the adequacy of the routine maintenance procedures and frequency should be reviewed. Pump lube oil system leaks continue frequently

{ and there are more occurrences in the latter years.

Diesel Driver j

( Again, the majority of the MR activities on this equipment occurred in 1976-77, shortly after plant startup. Problem areas included the lube oil system, the fuel oil system and the governor (overspeed). Lube oil MRs show

[ leaking oil, changing oil and addition of temporary oil cooler and pump.

Fuel oil MRs were also mainly for leaks. Governor MRs showed errors in RPM setpoints and ranges, problems with calibration and modification of the r speed increaser, and trips due to overspeed. Instrument and control MRs L were not available for review. The jacket water system also provided a large number of MRs. The problems included temperature switch failures, tank low level instrument failures, work on the heaters and leaks. Other

( MRs describe work on other engine mechanical and electrical components.

[

A-4 f

L r

L Flow Instrunients

[ Work on the flow indicators and flow transmitters provides a major part of total system maintenance in recent years (1963-85). Activities include resetting and recalibrating, damaged indicators, incorrect readings, pegged meters, and erratic signals. It is not clear whether these MRs

{ are associated with routine maintenance or due to failure of the instruments.

The instruments should be evaluated for replacement by more reliable models, and the maintenance procedures and frequencies should be reviewed for adequacy.

[

Diesel Recorder & Turbine Recorder

' The types of problems are scattered and appear to point to general mainte-nance of the recorders.

Miscellaneous

[

A number of miscellaneous (do not fit in above categories) maintenance activities were conducted. The largest contributors are the regulating controllers which no longer exist in the system.

{

[ 3.4 CORRELATION BETWEEN MAINTENANCE REPORTS AND LICENSEE EVENT REPORTS Turbine Pump and Driver -

(

The turbine pump and driver LERs and MRs show that the majority of governor /

overspeed problems occurred in 1975-77. Thereafter, satisfactory performance

[ is maintained.

A large number (38 total) of maintenance activities was carried out on the

( pump suction and discharge pressure instruments. However, there were only two recent low suction pressure LERs (1984 and 1985).

[ The rest of the LERs involve personnel error and component failure whereas L the MRs largely involve component failure and component modifications.

Except for the governor /overspeed items, the occurrence and subject of the MRs and.LERs appear unrelated.

Diesel Pump and Driver fL The LERs and MRs for the diesel pump and driver also show that the governor /

overspeed problem frequently occurred in 1975-77. However, since then, the problem has been minimal.

[ Throughout the 1975-85 period, the oil system, the cooling water system and the fuel oil system received frequent maintenance. However, the LER occurrences could not always be correlated with the MRs reviewed. (Probably due to incomplete documentation available or produced).

{

(

A-5

I l

Recorders Both turbine and diesel driver bearing temperature recorders had numerous I h MRs. However, there was only one LER related to this equipment (for the diesel driver) and it can not be correlated to any of the reviewed MRs.

Flow Instruments

{

There are many MRs on flow instruments but none relate to an LER.

Control Valves :

There are seven MRs and two LERs related to control valves. Again, there

[ appears to be no relationship between the MRs and LERs.

[

l

[

A-6

[

t L REFERENCES

[ 1. INP0 85-036. The Operational Performance of Auxiliary Feedwater Systems in U.S. PWRS 1980-84, September 1985.

2. INP0 85-024. Nuclear Reliability Data System Q04 Report. Sumary of

( Component Failures In Nuclear Power Plants Discovered Between January 1,1985 and June 30, 1985. July 1985.

[

3. NUREG-0020, Vol. 9, No. 1. Licensed Operating Reactors, Status Summary Report, Data as of 12/31/84. January 1985.

4. IEEE Std. 500-1984. IEEE Guide to the Collection and Presentation of

( Electrical, Electronic, Sensing Component, and Mechanical Equipment Reliability Data for Nuclear Power Generating Stations.

[

5. WASH-1400(NUREG-75/014). Reactor Safety Study. An Assessment of Accident Risks in U.S. Commercial Nuclear Power Plants, October 1975.

6. Oraft Procedure for Auxiliary Feedwater System Reliability Analysis,

( Bechtel Power Corporation,1980.

[

1 1

[

(

[

A-7

,-r v rm v n r, r- .r- - e em rm r rm r-

. O O EE $$ EE E COMPONENT FAILURES FROM INP0 85-024 se ae se 4m REMARKS NPRDS MFG QUANTITY OF QUANTITY OF (1) QUANTITIES ONLY AS DEVICE MANUFACTURER I.D. NO. FAILURES (l) COMPONENTS (1) REPORTED IN NPRDS i Engine, Diesel Waukesha WO70 N/L 6 N/L 1 1000-5000 HP Governor Woodward W290 N/L 86 N/L 214 Lumped Three Categories Operator, Valve Air Anchor / Darling A391 9 44 500 500 Gate, shut-off isolation stop, 2 to 3.99 in. complete assembly -- valve

+ operator Operator, Valve, Motor Limitorque L200 52 190 71 7 717 D.C. Motor, geared.

Relay Amerace/ Electric A348/E098 23 35 633 719 Gen. Purpose Cntl., solid state Stop Nut (Agastat T.D. , N.D. , 100-199V Relay Amerace/ Electric A348/E098 N/L 4 N/L 140 Gen. Purpose Cntl., solid state Stop Nut (Agastat) T.D., N.D. & N.E., less than 50V.

Relay General Electric G080 42 164 8961 8961 Gen. Purpose Cntl., solid state i T.D., N.D. & N.E., 100-199V P

Relay Potter & Brumfield P297 2 2 233 233 Cntl., T.D., N.E., less than 50V.

Relay Potter & Brumfield P297 N/L 1 N/L 33 Gen. Purpose Cntl., N.D., less than 50V Relay Potter & Brumfield P297 N/L 1 N/L 1 04 Gen. Purpose Cntl., N.D., 100-199V Switch, Flow ITT-Barton 1204 166 434 1417 1417 Switch, Limit NAMCO N007 3 9 141 141 l l

Transmitter Fischer & Porter F120 29 190 1022 1022 Transmitter Rosemount R369 125 204 3413 3413 Turbine Terry T147 9 30 2 22 1000-5000 HP, Non-Condensing, Single ;

Stage '

Valve, Globe Fisher F130 5 9 196 196 Shut-off isolation stop, 2 to 3.9 in.

Valve, Solenoid ASCO A610 N/L 1 N/L 1 3-Way Selector, plug, under 1/2"

i COMMENTS ON TABLE 1

[ All data in Table 1 is from NPRD Q04 Report, INP0 85-024, Summary of Cooponent Failures in Nuclear Power Plants, Second Quarter 1985.

" Failure" in NPRDS is any reported deficiency that perturbs, inhibits or

[ prevents normal function. Some causes of " failure" are: burned, loose, open, cracked, bent, stuck, worn, dirty, corroded, aged, damaged, not lubricated, over-ranged, out-of-adjustment, mis-applied, defective, and drifted components.

{

ihe data in Table 1 is not restricted to Auxiliary Feedwater Systems.

Failure reports have only been filed in NPRDS for a relative few of the b failures enumerated.

( Numbers of failures are not normalized to operating times. Failure rates are not available from NPRDS.

Any single reported component can have more than one reported failure.

NPRDS formatted engineering reports for each failure -- 252 reports per 3 x 5 film - - are available on microfiche.

[

A-9

L TABLE 2 AUXILIARY FEE 0 WATER LER'S REVIEWED Diesel Driver Turbine Pump 76-01 76-06 76-12 76-14 76-13 76-15

( 76-56 76-16 76-17 77-06 76-60

(- 76-65 78-028 77-46 79-06

( 80-15 80-02 81 -32 83-02

[- 83-22 Diesel Pump 84-05

( 76-04 84-016 76-05 85-09 76-06

( 76-17 76-19 Turbine Driver 76-24 76-57 76-02 77-45 78-16 i 80-18 80-12 80-20 81-01 80-24 83-02 Control Valves 83-12 77-43 84-05 84-016 85-01

[ 85-09 l

[

A-10 l

v m m - m e- _, r

- v v c- v 1- r ,. r-----

TABLE 3 (Sh. 1 of 2)

TROJAN AUXILIARY FEEDWATER SYSTEM LICENSEE EVENT REPORTS

SUMMARY

OF FAILURES CATEGORY / YEAR 1975 1976 1977 1978 1979 1980 1981 1 982 1983 1984 1985 TOTAL DIESEL PLMP Overspeed 2 2 Inadequate Procedure 1 1 Component Failure 2 2 Maintenance Error 1 1 2 SUB 7 Maintenance Error 1 1 2 Operator Error 1 1 1 3 Component Failure 1 2 3

y Low Suction Pressure 1 1

=.

Totals 1 6 1 - -

3 - - 2 2 1 16 DIESEL DRIVER V l

Component Failure 1 1 1 1 1 5 Design / Personnel Error 1 1 2 Maintenance Error 1 1 1 Inadequate Procedures 1 1 l

l Totals 1 3 1 1 1 1 1 9 l

1

v v r, v m i- v <- r- r, . r- .

ca i TABLE 3 (Sht. 2 of 2)

TROJAN AUXILIARY FEEDWATER SYSTEM LICENSEE EVENT REPORTS SIM4ARY OF FAILURES

-CATEGORY / YEAR 1975 1976 1977 1978 1979 1980 1981 1982 1983 1984 1985 TOTAL TUR8INE PLSIP Overspeed 2 1 3 !

Component Failure 2 1 3 SUB 6 i Component Failure 1 1 2 Inadequate Procedure 1 1 l I

Low S;ction Pressure 1 1 2 l Operator Error 1 1 2

L Totals _

5 1 .- -

1 - -

1 3 1 12 TURBINE D3IVER Component Failure 1 1 2 Construction Error 1 1 2 Totals 1 - -

1 -

2 - - - - -

4 CONTROL VALVES l Inadequate Specification 1 1 i

Component Failure 1 1 Totals - -

1 - - - - - -

1 -

2 l

TABLE 4 (Sht. I of 8)

AUXILIARY FEE 0 WATER MAINTENANCE REQUESTS REVIEWED FOR TURBINE ORIVER (K-107A)

MR-75-1859 MR-79-1062 MR-75-1878 Nt-79-1260

(-

MR-75-0320 MR-79-2325 MR-75-2322 MR-79-2365 MR-75-2337 MR-79-2555

( MR-76-2660 MR-79-2888 MR-76-2667 MR-80-2502

( MR-76-2786 MR-80-2565

( MR-76-2861 MR-80-2715 MR-76-3145 MR-80-3134 MR-76-3164 MR-80-3470

( MR-76-3303 MR-76-3327 MR-80-4026 MR-80-4257 MR-76-3331

( MR-76-3463 MR-81 -0163 L MR-76-3560 MR-81 -1060 MR-76-3780 MR-81 -1629 MR-76-3820 MR-81-3167

( MR-76-3894 MR-76-3993 MR-81-3464 MR-81-4141 MR-76-4112 MR-81 -5110 MR-76-4155 MR-76-4988 MR-82-0010 MR-76-6395 MR-82-0834 MR-76-6549 MR-82-1328

( MR-76-6860 MR-76-6865 MR-82-1980 MR-82-2287 MR-76-6908 MR-82-3272 MR-76-6957 MR-82-3282 MR-76-7033 MR-82-4410 M2-76-7070 MR-83-1015 MR-77-0191 MR-83-ll36 MR-77-0588 MR-83-4300 MR-77-3602 MR-83-4917

( MR-77-4377 MR-84-0641 MR-78-il87 MR-84-3032 MR-84-3293

[ MR-78-1909 MR-78-2425 MR-85-0046 MR-78-2759 MR-85-0053 MR-78-3444 MR-85-0096 MR-78-3945 MR-85-0663 MR-85-0664 MR-85-2899 MR-85-2900 MR-85-2901 MR-85-3159 A-13

l 4

TABLE 4 (Sht. 2 of 8)

AUXILIARY FEEDWATER MAINTENANCE REQUESTS REVIEWED FOR DIESEL PUMP

( MR-75-1203 MR-81-0831 L MR-75-1721 MR-81 -1662 MR-75-1756 MR-81 2694 MR-75-1942 MR-81 -2852

( MR-75-2050 MR-75-2575 MR-81-3308 MR-75-2581

( MR-82-3038 L MR-76-2689 MR-82-3462 MR-76-4082 MR-82-5282 MR-76-4365 j MR-76-6168 MR-83-0129 MR-76-6185 MR-83-1603 MR-76-6483 MR-83-2356 MR-83-2502 MR-77-0040 MR-83-2971 MR-77-0370 MR-83-4478 MR-77-1655 MR-83-4757

( MR-77-3256 MR-77-4240 MR-84-0041 MR-84-0435 MR-78-0214 MR-84-0574 MR-78-1217 MR-84-2320 MR-78-2203 MR-84-2447 MR-78-2252 MR-84-2798 i

(- MR-78-2768 MR-84-3089 l MR-78-4851 MR-84-3383 MR-78-4890

( MR-79-0347 MR-85-0047 MR-85-0166 MR-79-2753 MR-85-0167 MR-79-3725 MR-85-0405

( '

MR-85-0449 -

MR-85-0660 MR-80-0982 MR-85-1259

( MR-80-1042 MR-80-1582 MR-85-2045 MR-80-1692 MR-80-2165

(- MR-83-2166 MR-80-2167 MR-80-2168

( MR-80-2556 MR-80-2596 MR-80-2784 MR-80-2787

{ MR-80-3145 MR-80-3831

(

A-14

TABLE 4 (Sht. 3 of 8)

AUXILIARY FEEDWATER MAINTENANCE REQUESTS REVIEWED FOR DIESEL DRIVER (K-107B)

MR-75-2125 MR-77-0102 MR-80-0322 MR-84-1400

( MR-75-2143 MR-77-0143 te-80-0561 MR-84-1474 MR-75-2164 MR-77-0280 MR-80-0624 MR-84-3304 MR-75-2221 MR-77-0339 MR-80-0688 MR-84-3318

[ MR-75-2321 MR-77-0342 MR-80-0/22 MR-84-3621 MR-75-2402 MR-77-0414 MR-80-1917 MR-84-4041 MR-75-2462 MR-77-0538 MR-80-1984 MR-75-2490 MR-77-0584 MR-80-1986 MR-85-0286 MR-75-2577 MR-77-0588 MR-80-3473 MR-85-0327 MR-75-2622 MR-77-1019 MR-80-3578 MR-85-1405

( MR-77-ll79 MR-80-3695 MR-85-1840

( MR-76-2646 MR-77-1389 MR-80-3952 MR-76-2781 MR-77-2528 MR-80-4318 MR-76 2889 MR-77-3231' MR-80-4326 MR-76-2890 MR-77 3886 MR-80-4571 MR-76-2892 MR-77-3988 MR-76-2956 MR-77-4105 MR-81-1507 MR-76-3167 MR-77-4373 MR-81 -2607 MR-76-3724 MR-77-4492 MR-81-2785 MR-76-3870 MR-77-4513 MR-81 -2904 MR-76-3909 MR-77-4516 MR-81-2906

( MR-76-3916 MR-76-3943 MR-77-8117 MR-77-8166 MR-81 -3492 MR-81-4580 MR-76-3974 MR-81 -4688 MR-76-3989 MR-78-0431

( MR-76-3997 MR-78-1439 MR-82-0019 MR-76-4037 MR-78-1563 MR-82-0899 MR-76-4091 MR-78-1670 MR-82-1297

( MR-76-4112 MR-78-2644 MR-82-2679 MR-76-4148 MR-78-2705 MR-82-2726 MR-76-4277 MR-78-2892 MR-82-3150 MR-76-4278 MR-78-3974

( MR-76-4627 MR-78-4052 MR-82-3199 MR-82-3204 MR-76-4822 MR-78-4688 MR-82-3207 I MR-76-4877 MR-82-4754

( MR-76-4897 MR-79-0013 MR-76-5078 MR-79-0286 MR-83-0295 MR-76-5105 MR-79-0290 MR-83-0569

( MR-76-5288 MR-76-5327 MR-79-0346 MR-79-0907 MR-83-2092 MR-83-2183 MR-76-5359 MR-79-il68 MR-83-2501 MR-76-5518 MR-79-1531 MR-83-2971

( MR-76-5532 MR-79-1656 MR-83-2949 MR-76-5677 MR-79-2253 MR-83-3139 MR-76-5687 MR-79-2851 MR-83-3316

( MR-76-6287 MR-76-6730 MR-79-3199 MR-79-3479 MR-83-3410 MR-83-3448 MR-76-6884 MR-79-3653 MR-83-4579

( MR-76-6987 L MR-76-6989 MR-76-7412 MR-76-7743 A-15

{ -- - - - -

L p TABLE 4 (Sht. 4 of 8)

L AUXILIARY FEEDWATER MAINTENANCE REQUESTS REVIEWED I FOR FLOW INSTRUMENTS M*-75-1748 MR-82-0101 MR-75-1971 MR-82-2857 MR-75-2377 MR-82-2949 MR-82-3224 I MR-76-3017 MR-82-3603 MR-76-3867 MR-82-3606 MR-76-3918 MR-82-3843 MR-76-3969 MR-76-4066 MR-83-0988 MR-76-4257 MR-83-1676 MR-76-4540 PR-83-2455 MR-83-2626

( MR-77-0612 MR-83-2680 MR-77-0684 MR-83-2891

( MR-77-2367 MR-83-3580

( MR-77-3025 MR-83-4090 MR-77-40ll MR-77-4012 MR-84-1786

( MR-77-8287 MR-84-2115 MR-84-3133 MR-78-ll52 MR-84-3204 MR-78-2503 MR-84-4469 MR-79-2984 MR-85-2369 MR-79-4465 MR-85-2514 MR-80-1241 MR-80-2877 MR-80-3721

( MR-80-3738 MR-80-3868 MR-80-4254 MR-81-0361 MR-81-0455 MR-81 -1760

( MR-81-2175 MR-81-2217 MR-81-2857

( MR-81-2858 MR-81-3021

(

A-16

TABLE 4 (Sht. 5 of 8)

{

AUXILIARY FEEDWATER MAINTENANCE REQUESTS REVIEWED FOR DIESEL RECORDER TJR-30696 MR-77-7957 MR-19-3033

( MR 79-4174 K;-80-0010 AR-80-3539 MR-80-4059 MR-80-4304 MR-80-4354 MR-81-0070 MR-81-ll23 MR-81 -1695

(

MR-82-5166 MR-83-3778 MR-85-0133

( MR-85-0439 MR-85-1548 MR-85-1913

(

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[ l

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A-17

s

( TABLE 4 (Sht. 6 of 8) r AUXILIARY FEEDWATER MAINTENANCE REQUESTS REVIEWED L FOR TURBINE RECORDER TJR-3069A

( MR-76-6746 MR-77-3653 MR-79-1226 MR-79-2431

( MR-79-3349 MR-81-il23 MR-82-0350 MR-82-0830 MR-82-1054 MR-83-0582 MR-83-3043 MR-83-4832

(

[

(

A-18

r TABLE 4 (Sht. 7 of 8)

AUXILIARY FEEDWATER MAINTENANCE REQUESTS REVIEWED MISCELLANE0US f

( '

MR-75-1716 MR-81 -1518 g MR-75-1746 MR-81 -1716

[ MR-75-2358 MR-81-2860 MR-75-2406 MR-81 -3285

[ MR-76-3230 MR-82-0730 5 MR-76-3578 MR-82-1449 MR-76-3910 MR-82-2155

( MR-76-3912 MR-82-2210

[ MR-76-4112 MR-82-2503 MR-76-4130 MR-82-3602 MR-76-5269 MR-82-4483 MR-76-6343

(- MR-76-7659 MR-83-2208 MR-83-2226 r MR-83-2554

( MR-77-0129 MR-83-3511 MR-77-0296 MR-77-3614 MR-84-1029 MR-77-8227 MR-84-2572

(

MR-85-0614 MR-78-2613 MR-85-1428 MR-79-0243 MR-79-1453 MR-79-1629

[ MR-79-2646 MR-79-3737 MR-80-1088 MR-80-1368 MR-80-1636

( MR-80-1802 MR-80-2089 HR-80 2252

( MR-80 2314 L MR-80-2806 MR-80-2924 MR-80-3588

( MR-80-3719 MR-80-3734 MR-80-3987 MR-80-3994

( MR-80-4258 MR-80-4414 MR-80-4454 MR-80-4511

(

A-19

(

TABLE 4 (Sht. 8 of 8)

( AUXILIARY FEEDWATER MAINTENANCE REQUESTS REVIEWED FOR TURBINE PUMP MR-75-2338 MR-81 -1578

(. MR-75-2474 MR-75-2575 MR-81 -3147 MR-81-3729 MR-75-2576 I

[ MR-75-2578 MR-82-0637 L MR-82-4872 MR-76-3687

< MR-76-3699 MR-83-0859

[ MR-76-4441 MR-83-1035 MR-76-6145 MR-83-2032 MR-76-6286

[ MR-76-6514 MR-84-0090 L MR-76-6913 MR-84-0671 MR-76-7067 MR-84-2209 r MR-84-2253

( MR-77-0472 MR-84-2511 MR-77-3256 MR-84-2836 MR-77-3257 MR-84-2998 MR-77-3558 MR-84-3156

( MR-77-4241 MR-84-3173 MR-77-7817 MR-84-3281

( MR-77-8156 MR-84-3314 i MR-84-3334 MR-78-0214 MR-84-3383 MR-78-0291 MR-84-3443 MR-78-0816 MR-84-3516 l MR-78-2203 l

l MR-78-2298 MR-85-0166

[ MR-78-2763 MR-85-0167 L PR-85-0405 MR-79-0192 MR-85-ll63 MR-79-1672 MR-85-1351 MR-79-2538

( MR-79-3725 MR-85-1672 MR-85-2045 MR-85-2133 MR-80-0493 MR-80-1503 MR-80-1692 MR-80-2596

( MR-80-2822 MR-80-3145 MR-80-3736 MR-80-4025

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v t e Letter Sequence Other
TAC:60783, (Approved, Closed)
Initiation Acceptance... Administration Questions Answers Results Approval, Approval Other: ML20132B333, ML20134D439, ML20137H537, ML20137H598, ML20137Y186, ML20137Y198, ML20203L324, ML20203N845, ML20214N970
MONTHYEAR1985-08-12 [Table View]

ML20137H598

Text

SUMMARY

SUMMARY

Subject:

SUBJECT:

SUBJECT:

SUBJECT:

SUBJECT:

1.0 INTRODUCTION

3.1 INTRODUCTION

SUMMARY

SUMMARY

SUMMARY

SUMMARY

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