ML20150E286
| ML20150E286 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 12/31/1987 |
| From: | LONG ISLAND LIGHTING CO. |
| To: | |
| Shared Package | |
| ML20150E284 | List: |
| References | |
| NUDOCS 8803300381 | |
| Download: ML20150E286 (20) | |
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ENCLOSURE A 10 CFR 50.59 REPORT Period _from June 8, 1987 through December 31, 1987 Shoreham Nuclear Power Station Docket No. 50-322 March 1988 8803300381 880318 PDR ADOCK 05000267 O DCD
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Description of Change:
Software modifications were made to the Radiation Monitoring System (RMS) computer. Where RMS channels have hard wired annunciators, computer generated redundant main control room annunciations were removed. Also removed were computer generated annunciations, except high radiation alarms for nontechnical specification channels, that do not have hard-wired annunciators.
Computer activated main control room "RMS RM FAIL" (1409) annunciation for technical specification monitors that do not have hard-wire annunciators were provided. Logic in the RMS software to activate the "RMS RM FAIL" (1409) annunciator in the main control room for a "COMLINE STOP" condition was incorporated. The inputs and annunciator panel (1D1-PNLRMA) in the Health Physics Room were removed.
Summary I. No. The RMS computer is not safety related. Additionally, all safety related monitors associated with the computer have separate hard wire annunciation in the main control room.
II. No. All safety related monitors have hard wired alarms which are unchanged by this modification. The only effect ,.
on safety related equipment is to remove redundant alarms.
III. No. All safety related and technical specification required monitors will continue to alarm in the main control room.
A-1
Description of Change:
This modification included wiring changes to the water chiller leak detection transmitters for the Reactor Building Ventilation System, the Control Room, and the Main Water Chiller systems.
This was done to provide for proper operation of the installed Panametrics Hygrometers. Existing Rockbestos cables were replaced with two (2) NFP-44 cables (twisted pair with an overall shield) per channel, in seven (7) of the eight (8) channels. New cables were run from the moisture element junction box to the water chiller leak detection transmitters (1M50-XT099,100, 1M60-XT092, 094) in Hygrometric Instrument Panel (IM50-PNL-110).
Summary:
I. No. This modification involved non-safety related, O.A.
Category II, equipment. This equipment is located in a seismic Category I structure. The modification did not affect and has no interaction with any safety related equipment.
II. No. All cables installed are in existing non-safety related raceways.
III. No. Failure of the leak detection of water chillers will not increase the radiation in the control room.
A-2
SM 85-005 (DOP 83-036) (VC-2005)
Description of Change:
The Reactor Water Cleanup System (RWCU) recirculation pump protection was replaced. Removed the high temperature trip logic between the temperature switch (1G33-TIS-015A&B) and the pump (lG33-P-019A&B). Annunciation in the control room when the seal gland plate temperature exceeds 250 F was provided. A jumper was added in panel (lHil*PNL602) to eliminate the high temperature interlock, and alarm number 1054 on that panel was changed to read "RWCU SYS PUMP SEAL GLAND PLATE TEMP HIGH". Also, station procedures were modified to protcct these pumps.
Summary:
I. No. This modification functionally affects only non-safety related equipment. There is a wiring change in a QA Category I panel, 1Hil*PNL602 (sparing a cable and adding a jumper), the viring change itself is confined to the non-safety related section of the panel and has no effect on any safety related equipment.
II. No. This modification has no interaction with any safety-related equipment.
III. No. There is no impact on the Technical Specifications.
Description of Change:
Accessibility for calibration of the Average Power Range Monitoring (APRM) and Rod Block Monitoring (RBM) channels 15 volt regulator circuit boards has been modified. The four flow units (AR 53, AR 13, AR 43 and AR 2 3) located in the control room power range monitoring panel (lHil*PNL608) have two 3/16 inch holes added in the bottom of the unit, in-line with the 15 volt regulator adjustment resistors R4 and R12. This change will provide a means of calibrating the flow units without causing a half-scram or rod block.
Summary:
I. No. This modification af fects non-safety related equipment.
The equipment is located in a seismic, Category I structure.
These changes will not adversely compromise the reliabilit" or safety function of this equipment.
II. No. This modification has improved the design and wil.1 not alter the safe operation of the power range monitoring system.
l III. No. There is no impact on the Technical Specifications.
A-3
Description of Change:
A modification to the Control Rod Drive (CRD) cooling water orifice was performed to minimize the potential for plugging.
The modification includes the addition of a new orifice and two holes drilled through the set screws at 90 degrees to the main bore, providing a total of five inlet holes. The hydraulic characteristics are essentially the same as the originel orifice configuration. Teflon seats in the hydraulic control unit (HCU) inlet scram valves were also replaced with a less brittle form of teflon (Tefzel). Modification of both the CRD mechanism and the hydraulic control unit was designated QA Category I. The replacement cooling water orifice and Tefzel insert scram valve seat ring was designated QA Category II.
Summary:
I. No. The replacement of the original orifice with the new multi-inlet design orifice will not affect the function of the CRD mechanism cooling water supply since the new orifices have essentially the same hydraulic characteristics as those which have been replaced. The replacement of the insert scram valve seat with a less brittle seat of the same shape will not affect the function of the valve but will enhance the long term performance 7.nd reliability of the valve, and CRD mechanism cooling water flowpath.
II. No. Equipment has not been added, deleted, or functionally altered by this modification.
III. No. The functional capabilities of the system have not been eltered by this modification.
A- 4
Description of Change:
The security provisions were modified for the EMD diesel generator area, the RSS transformer area, and the 69 KV switchyard /20 Mw gas turbine generator area. These enhancements ,%
included additions to area fencinc; vehicle barriers at approach routes; visual obstructions for vital equipment; manned ouard booths; access control posts; and lighting equipment meeting increased requirements.
Summary:
I. No. Safety related equipment was not involved. The equipment affected by this change has no interaction with any safety related equipment.
II. No. The modification did not change safety related equipment or alter the basis of any accident analyses.
III. No. Safety related equipment was not changed.
Description of Change:
This modification replacce the pressure gauges in the Peactor Building Primary Containment Atmospheric Control ('T46) system. 4 Tne originally supplied and installed pressure gaugen (lT48*PI823A and B, and IT48*PI824A and B) located in panels (lT48*PNLO68A ar.d B, and IT48*PNLO69A and B), respectively, had a scale range of -30" Hg to 60 psig. The vendor for these panels no longer supplies QA Category I gauges in that original scale range. The vendor has supplied QA Category I gauges with scale ranges of -30" Hg to 100 psig as replacemar.ts for ti.e originally supplied gauges.
Summary:
I. No. The replacement of the original gauges with equally qualified substitutes does not alter the operation of the systems in which the gauges are installed.
II. No. Equipment has not been added, deleted or functionally altered by this modification. The replacement gauges have the same physical parameters (size, weight, mounting configuration) as the original gauges, but provide the means for monitoring higher pressures than the original.
III. No. The functional capabilities of the system have not been reduced.
A- 5
1
Description of Change:
This modification changed the logic for the fire water storage tank level control valve. The original logic prevented the filling of the fire water storage tanks (1M43-TK-074 A and B) i whenever the domestic water system hydropneumatic tank (1M42-TR-082) required filling by closing the well water pump discharge isolation valve, to the fire protection water storage tanks. This change modified the fire water storage tank level control valve (1M42-LCV-010) logic from air to "OPEN" to air to "CLOSE". A spare normally closed contact from the fire water storage tank low level relay has been wired in series with the normally open contact from the domestic water hydropneumatic tank low level relay. These changes will allow the well water pump discharge isolation valve to remain open, thereby permitting the fire water storage tanks to be filled if the operator chooses.
Summary:
I. No. There is no safety related equipment involved in this change.
II. No. There is no interaction with any safety related equipment.
III. No. This modification gives priority to filling the fire water storage tanks instead of the domestic water hydropneumatic tank thus ensuring that the minimum contained water volume of 300,000 gallons in each tank, committed to in Technical Specification 3/4.7.7, is met.
SM 85-109 (DOP 85-202) (VC-2003)
] Description of Change:
Copes Vulcan has supplied new valve internals for the main condensate valves (1N21-PCV-027A and B) which have had excessive cavitation in operation. The vendor has provided "HUSH II" trim i
which will eliminate the cavitation. The trim design will control flow and velocity of the liquid through many orifice openings and stages of pressure drop. This modification has rotated the valve 180 so that flow direction enters from under the main seat.
Summary:
I. No. This design modification did not involve any safety related equipment.
II. No. This modification protects the flow control valve and the condensate piping from mechanical failure due to cavitation.
III. No. Safety related equipment is not involved in this design change.
A-6
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SM 85-117 (COP 85-238) (VC-2006)
Description of Change:
This modification relocated the four guide ears on the radwaste solids handling system transfer carts (lP63-VH-001A, B, C, and D) for positioning the waste shipping containers, and modified the supports for the radiation monitors (lDil-RE-074 A, B, C and D) to eliminate interference from the modified transfer carts. This allowed the new, larger, high integrity containers to be transferred into the cubicles. Setpoints for the radiation monitors were recalculated to reflect the new detector geometry.
Summary:
I. No. The solid waste handling system is not safety related and is not involved in any accident analysis in the USAR.
II. No. The solid waste handling system does not affect any safety related system.
III. No. This modification did not eliminate any previously installed equipment.
Description of Change:
Temperature monitoring alarms were installed in the yard pipe trench to alert the operator of impending freezing conditicas within the trench. Ccpper Constantan thermecouples (1RB1-T/C-318 and 1RB1-T/C-7 0'/) were inste.lled at the two trench locations considered most susceptible to freezing. Monitoring and alarming was accomplished using existing Sigma Series 9231 indicating controllers, located in the radwaste building cample room at electrical panels (1R81-PNL-ll5 and 1R81-PNL-115A).
Summary,:
I. No. This change does not involve safety related equipment.
II. No. This modification does not have any interaction with safety related equipment.
III. No. Safety related equipment is not included in this change.
A- 7
Description of Change:
This modification included additions to the Process Computer digital input data bus circuits. In order to decrease the length of data pulses (i.e., to improve the signal pulse trailing edges and shrink the pulse width) resistore have been soldered to contact fingers on the bottom of each stick in each of the 1C91-P608 and 1C91-P622 digital input cabinets. Out of the 32 contact fingers per stick, only the 24 data lines had to be connected to ground through resistors. This addition of 50K ohm resistors should have decreased the length of the data pulses to 20 msec. The reduction in pulse width reduced erroneous data transmission to the Process Computer and improved system reliability.
Summary:
I. No. This design modification did not involve any safety related equipment.
II. No. The addition of resistors to data lines improved system functionally and did not alter the safety classification of the Process Computer.
III. No. There was no reduction in the margin of safety in the basis of any Technical Specification.
Description of Change:
This modification established a data transfer capability from the Radiation Monitoring System (RMS) computer to the DEC computer and the IBM computer. A magnetic tape drive has been installed on the RMS and DEC computers to establish data transfer. The magtape solution is more versatile than modifying the floppy disk system. This modification increased the flexibility and the reliability of both computers by establishing the data transfer capability.
Summary:
I. The RMS computer system is not safety related. The USAR describes the RMS computer only in general terms and does not state details of data transfer.
II. No. Safety related equipment is not involved in the change.
III. No. There is no impact on the Technical Specifications.
A-8
Description of Change:
This modification installed run time meters on the 4 KV cubicles for the circulating water and the Turbinn Building F.ervice Water cystem pumps. To comply with the State Pollution Discharge Elimination System, reports to New York State must indicc.te the total gallons of water discharged per day from the main outfall pipe, which consists of contributions from the Main Circulating W..ter and the Service Water (Turbine anu Reactor) systems. The run time meters indicate the total number of hours that each pump is running from which the quantity of water pumped can be calculated.
Summary:
I. No. This modification was involved with non-safety related equipment.
II. No. This modification will not affect and has no interaction with any safety related equipment.
III. No. Safety related equipment was not involved and there was no impact on the Technical Specifications.
Description of Change:
Manual shutoff valves (IN71-06V-0025A-D) in the Main Circulating Water System for isolation of screenwash spray to traveling water screens (1N71-TCS-001 A-D) have been replaced. 'ine original Crane 6-inch bronze gate valves are no longer manufactured. The replacement valves are Williams 6-inch brorze gate valves. In addition, manual operated valves (IN71-006V-0026 A-D) have been
, removed. These valves funtioned as redundant shatoff valves to tne high pressure spray nozzles, and they were not essential since shutoff of screenwash water is sti.'1 accomplished by the remaining valves (IN71-06V-0025 A-D).
Summary:
I. No. Safety related equipment was not involved in this modification.
II. No. This modification does not interface with safety related systems.
III. No. There was no reduction in any Technical Specifica*lon margin of safety.
A-9 ;
l
Description of Change:
This modification changed the watt hour meter registers for the Normal. Service Station Transformer (NSST) and Reserve Service Station Transformer (RSST) meters (WH-lR62N02 and WH-lR62N05).
The current transformer ratio for the NSST metering circuits was changed from 300/5 (60/1) to 200/5 (40/1). These changes gave both meters a multiplier of 1000 and produced 1000 watts secondary for 48 watts primary on both the NSST and the RSST metering circuits.
Summary:
I. No. This modification involved non-safety related equipment.
II. No. This modification will not affect and has no interaction with any safety related equipment.
III. No. There is no impact on the margin of safety for any technical specification.
Description of Change:
The Security Closed Circuit Television system has been modified with enhancements to assure a proper level of station protection as required by the NRC and to reduce compensatory measures as a result of various camera limits. This modification involved both the fixed (or perimeter) cameras and the PTZ (Pan / Tilt / Zoom) cameras. Each fixed camera was modified to meet or exceed its original characteristics, after a camera by camera assessment.
Several lensing changes were installed, the remaining cameras were provided local field-of-view adjustments. Several test installations on selected cameras were installed In to reduce blooming effects and to improve video signals. addition, all sources of bright objects such as local control boxes were repainted to a non-reflective color, thereby reducing the glare.
Summary:
I. No. Safety related equipment was not involved in this design change.
II. No. This modification involved non-safety related equipment and had no interaction with any safety related equipment.
III. No. There is no impact on any Technical Specification margin of safety.
A- 10
Description of Change:
An access platform and additional lighting has been installed to eliminate personnel safety hazards within the screenwell sound enclosure area. A catwalk type platform has been installed that runs above the service water piping complete with vertical ladders providing safe access up and over the piping. Additional lighting has been installed to provide adequate illumination at the pump gauge panels and to brighten the dark shadow areas for safe walking conditions.
Summary:
I. No. Safety related equipment was not involved in this design change.
II. No. This modification had no interaction with any safety related equipment.
III. No. There was no reduction in the margin of safety for any Technical Specifications.
SM 86-063 (DOF 86-047)
Description of Change:
The Perimeter Intrusion Detection System has been modified by removal of the E-field equipment at the screenwell (Zone #4).
This has been replaced by a microwave perimater intrusion detection system. Platforms have been constructed at each end of the screenwell to mount the microwave transmitter and receiver equipment. Gates have been added to allow maintenance access to these platforms. In addition, the adjacent E-field zones (Zones
- 3 and Zone #5) have been extended onto the screenwell deck to improve detection coverage.
Summary:
I. No. This design change did not include any safety related equipment.
II. No. This modification does not involve any interaction with safety related equipment.
III. No. There was no impact on the Technical Specifications.
A- 11
Description of Change:
This modification has installed a ground in the Emergency Response Facilities (ERP) instruments (1Z97* MUX 001, 004, 005, 008). Validyne, the instrument manufacturer had indicated that for proper operation of the amplifiers, a signal ground reference was required for each instrument. Installation of the ground wire has eliminated the intermittent calibration drift problem previously experienced with these instruments.
Summary:
I. No. The installation of the ground wires eliminates the intermittent calibration drift problems and permits operation of the ERF system as designed.
II. No. Ground wires have improved the operation of the ERF system and their installation does not alter the failure mode of the system.
III. No. The functional capabilities of the ERF system have actually been improved by this modification. The margin of safety as defined in any technical specifications is not affected.
Description of Change:
This modification relocated the sprinkler heads on the fire suppression system in the area of the turbine control valves.
The sprinkler heads, in their original positions, could discharge water directly onto the control valves and this could result in excessive thermal stress which could cause severe damage to the control valves. This modification has relocated sprinkler heads on line number 814, on line number 815; and on line number 817.
All sprinkler heads on these three lines have been dropped in elevation, thus eliminating the possibility of water discharging directly on to the turbine control valves.
Summary:
I. No. Safety related equipment was not involved in this design change.
II. No. This modification did not affect any safety related equipment.
III. No. This modification has increased the fire extinguishing capability of the existing sprinkler system zone.
A- 12
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Description of Change:
This modification has replaced the strip chart recorder (lN62-H2R-500) in the radwaste off-gas systen with a replacement recorder that meets the same operational requirements as the original recorder. The recorder measures hydrogen concentration and moisture levels in the radwaste off-gas procersing system.
Summary:
I. No. Safety related equipment was not involved in this change.
II. No. This modification did not interface with any safety related equipment.
III. No. There was no reduction in the margin of safety in the basis of any Technical Specification.
_SM 87-011 (DOP-N/A)
Description of Change:
This modification has provided a permanent power feed to the Maintenance Services Department (MSD) Shop and the laundry trailer at Shoreham. The modification has installed a new 3-phase, 480 VAC feed from 1R23-SWG-12B, cabinet 7D to the distribution panel in the MSD Shop. The laundry trailer has been fed from the MSD Shop via a 150 KVA, 480-208 volt transformer with disconnects.
Summary:
I. No. This modification involved non-safety related equipment.
II. No. This modifi.ation had no interaction with any safety related equipment.
III. No. There was no reduction in the margin of safety in the basis of any Technical Specification.
A- 13
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Description of Change:
This modification provided electrical interlocks on the suppression pool suction valves of the RHR system to prevent opening if the shutdown cooling valves are open. Electrical interlocks were installed on Residual Heat Removal (RHR) System valves (IEll*MOV31A, B, C and D) to prevent those valves from opening if the shutdown cooling valves (IEll*MOV32A, B, C, and D) are not closed, respectively. Limit switch (LS#6 of lEll*MOV32A, B, C, and D) has been serially interconnected to the (IEll*MOV031A, B, C, and D) opening coil 42Z0, respectively.
This modification was performed in compliance with General Electric Field Deviation Disposition Request (FDDR) KSI-2353, Rev. O, dated October 4, 1985.
Summary:
I. No. This modification will interconnect the safety related valve controls. If any shutdown cooling valve fails to close, its interlock on the corresponding suppression pool suction valve would cause loss of an RHR pump in a Low Pressure Coolant Injection (LPCI) System injection event.
This scenario is within the envelope of design basis single failure evaluation which includes failure of one RHR loop consisting of two RHR pumps (USAR 6.3, Table 6.3.3-4).
There would be no adverse impact on the design basis safety-related function of the system.
II. No. This modification installs an electrical interlock which was designed to improve system reliability. This modification physically prevents RHR system valve misalignment and thus prevents a potential operational error which was originally only prevented administratively by a caution statement in a station procedure.
III. No. This modification has not reduced the margin of safety in the basis of any Technical Specification.
A- 14
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SM 87-017 (DOP 87-019) (VC-2008)
Description of Change:
The reactor water cleanup (RWCU) system hold pump (lG33-P073B) has been replaced by this modification. The replacement pump has been purchased from General Electric (FDDR KSI-1267) and, although not identical in pump characteristics, has been approved by GE for the hold pump application. This modification has been classified QA Category I. The RWCU system has no active safety related function, although the RWCU piping has been designated ASMC Class 3.
Summary:
I. No. This modification will not introduce any new failure modes and the input parameters of the USAR Chapter 15 analysis remain unchanged. The RWCU system has no safety function other than pressure boundary. The design pressure of the replacement pump is 1420 psi. The existing piping stress analysis has been reviewed and was unaffected by implementation of this modification.
II. No. This modification did not delete or otherwise change any required safety system operating parameters.
III. No. This modification did not affect any safety functions from any Technical Specifications. This change does not present a source of radiological exposure to the offsite general public.
SM 87-021 (DOP-N/A)
Description of Change:
This modification installed high temperature indicating lights for 480 volt Inductrol voltage regulators (lR23-IND llA, B, C, D, and 12 A, B, C and D) which provided local indication of high temperature. Two local indicating lamps were wired for each voltage regulator; a red light to go "ON" upon stator winding high temperature, and a white light to go "ON" to indicate that alarm power is available. (See Engineering and Design Change Request, E&DCR L-00169B).
Summary:
I. No. Safety related equipment was not involved in this design modification.
II. No. This modification did not affect any safety related system or component.
III. No. This modification only provided local alarm indication for the operation of non-safety related equipment.
A- 15
Description of Change:
The modification is in response to the NRC fire protection inspection report item No. 84-46-17. The LILCO solution was accepted by the NRC, as documented in their letter dated February 25, 1987 including Supplemental Safety Evaluation Report (SSER).
This modification required that the following motor operated valves (MOV) be deenergized in the closed position when the plant was at power operation:
lEll*MOV081A and B - Residual Heat Removal (RHR) System injection check valve bypass (E11-F122A and B),
lE21*MOV081A and B - Core Spray injection valve bypass (E21-F047A and B),
lEll*MOV052 - RHR line to radwaste system (Ell-F040),
1B21*MOV083 - reactor vessel head drain valve (B21-F001),
1G33-MOV037 - Reactor Water Cleanup (RWCU) system line to condenser and RWCU waste collector (G33-F031) tanks.
These MOVs were deenergized by removing the overload heaters from their respective 480 VAC motor control centers. This rendered the respective valve electrically inoperable (therefore, impervious to spurious electrical control signals) while preserving the position indication in the control room.
Summary:
I. No. The de-energization of the motor operators of the subject valves eliminated the potential for high/ low pressure system interface LOCAs, if the valves inadvertently open by fire induced spurious signals. This modification did not change the design basis or the specified safety function of the valves or other safety related equipment as previously evaluated in the USAR. These valves are not used during normal plant operation.
II. No. This modification has not introduced any new equipment and has not caused equipment or systems to function differently from the design basis previously evaluated in the USAR.
III. No. This modificaticn did not change the basis for any Technical Specification and, therefore, the margin of safety was not reduced.
I i
A- 16
Description of Change:
This modification installed an air conditioning unit (Liebert Mini-Mate Plus) in the telephone room of the O&S Building. This unit has been sized to maintain the required operating temperature conditions for the new telephone equipment. The electrical power for this unit has been provided from an existing 240/120V AC distribution panel (lR35-PNL-N14).
Summary:
I. No. This modification involved non-safety related equipment.
II. No. These changes did not affect and had no interaction with any safety related equipment.
III. No. This modification had no impact on the Technical Specifications. This modification had no effect on radiological impacts to the offsite general public.
A - 17
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SPCN 87-0657 Description of Change:
This change revised procedure, "RPS-Monthly Trip Unit Calculation and Functional Test," SP44.611.10. This revision adds the use of four new slave units (1B21*LS-155A, B, C and D), associated with modified main steam isolation valve closure setpoints, to the procedure. The new slave units were installed under SM 87-006, which was previously reported in SNRC-1397, dated December 4, 1987. SM 87-006 was a result of a commitment made to the NRC and it was addressed by the Boiling Water Reactor Owners' Group (BWROG) in the evaluation of NUREG-0737, item II.K.3.16. The NRC was notified by SNRC-816 of LILCO's intent to implement SM 87-006 and that it would not impact the safe operation of the plant.
The NRC acknowledged this modification in the SNPS SER (NUREG-0420), Supplement 4, with no unresolved outstanding issues.
Summary:
I. No. This revised procedure only implemented the use of the equipment installed under SM 87-006, which reduced the probability of accidents due to challenges to the safety relief valves. Analyses demonstrated that the consequences of this modification of loss of feedwater transient and large and small break LOCAs were not significant.
II. No. This revised procedure implemented that modification and the ef fects of the change were encompassed by existing accident analyses.
III. No. The procedure revision and that modification did not involve a significant reduction in any margin of safety because the analyses demonstrated that the design parameters affected were not significantly reduced, i
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A - 18
SPCN 87-1792 Description of Change:
This change created a new temporary procedure, 24.311.01, "lR24*MG-ll3B Voltage Regulation Test." This procedure describes the testing requirements for the voltage regulation test to be performed on LPCI motor-generator set (1R24*MG-113B) to demonstrate that the motor-generator set meets the requirements of specification SHI-439. This procedure was performed to demonstrate that the motor generator set meets the requirements of the specification after replacing the motor-generator exciter current transformers.
Summary:
I. No. Section 8.3 of the USAR makes specific reference to LPCI motor-generator set operation. This procedure merely tests voltage regulation of the motor-generator set, after replacement of the current transformers was completed, to verify that its operation is within the specified requirements. The loads'on lR24*MG-ll3B are composed of IB31*MOV032B, lEll*MOV036B, 1 Ell *MOV045B, and lEll*MOV037B.
The procedure provides e. means to monitor the output voltage with the motor-generator set operated around no-load and then loaded up with normal loading.
II. No. This procedure verifies that the motor generator set meets the specified requirements. Thus, an accident or a malfunction of a different type is not a concern.
III. No. This test procedure did not reduce the margin of safety in the bases of any Technical Specification.
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l A - 19 l