ML20198B335
| ML20198B335 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 06/30/1997 |
| From: | PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20198B317 | List: |
| References | |
| NUDOCS 9801060271 | |
| Download: ML20198B335 (23) | |
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, .~ f ,j PECO ENERGY COMPANY LIMERICK GENERATING STATION UNITS 1 AND 2 DOCKET NOS. 50-352 AND 50-353 ANNUAL 10CFR50.59 AND COMMITMENT REVISION REPORT JULY 1,1996 TilROUGII JUNE 30,1997 LIMERICK GENERATING STATION a
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PECO ENERGY COMPANY LIMERICK GENERATING STATION UNITS 1 AND 2 DOCKET NOS. 50 352 AND 50-353 ANNUAL 10CFR50.59 AND COMMITMENT REVISION REPORT JULY 1,1996 TilROUG1I JUNE 30,1997 Tids regnt provides a brief description of changes to the facility and procedures as described in the Safety Analysis Report, tests, and experiments that were implemented between July 1,19% and June 30,1997. A summary of the safety evaluation for eac:1 item concluded that an unreviewed safety question, as defined in 10CFR50.59(a)(2), was not involved.
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i l'ECO ENERGY COMI'ANY LIMERICK GENERATING STATION UNITS 1 AND 2 DOCKFT NOS. 50-352 AND 50-353 ANNUAL 16CFR50.59 AND COMMITMENT HF"ISION REPORT JULY 1,1996 TilitOUGli JUNE 30,1997 TAllLE OF CONTENTS 4
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PECO ENERGY COMPANY LIMERICK GENERATING STATION UNITS 1 AND 2 DOCKET NOS. 50-352 AND 50-353 ANNUAL 10CFR50.59 REPORT TABLE OF CONTENTS Modificati0m DEC ECR 9540078 1 ECR 95-05?69 1 ECR 9640719 1 ECR 9640720 2 ECR 96-00721 2 ECR 96-01192 2 ECR 9641594 and ECR 9641598 2 ECR 96-01597 and ECR 9642001 3 ECR 96-02288, ECR 96-02289, ECR 96-02290, and ECR 9642291 3 ECR 9642784 3 ECR %42838 4
< ECR 9643220 4 1 % 100 4 P00140 4 IW166, l@l67, and P00lG8 5 IW227 5 P00290 5 IW291 5 P00565 6 l @ 573 6 P00 tot 6 P00649 6 1 % 674 7 N_Onten(emumge Rerxnts NCR 92-00327 7 NCR 94-00313 7 NCR 9544049 7 NCR 9640733 7 NCR 9642564 8 NCR 96-02901 8 NCR 96-030f4 8 NCR 97 00212 8 NCR 97-00242 9 NCR 97 01026 9 g
TABLE OF CONTENTS Temporary Plant Alterations Pat .
ECR 46 02816 9 ECR c6-03716 9 Procedures. Tests. or Experirnents S10.7.A & S53.7.A 10 S77.1. A 10 SP-176 2 10 ST-2 072-106-1&2, ST-2-0721071&2 10 TCF 97-0!E0 11 llFSAR Changes ECR 9411346 11 ECR 95-05039 11 ECR 96 01283 12 ECR 9641775 12 ECR E02318 12 ECR 96-02319 12 ECR 96 02386 12 ECR 96-02473 13 ECR 96-02488 13 ECR 96-02636 13 ECR 96-02705 13 ECR 96-02738 13 ECR 96-02780 13 ECR 96-02909 14 ECR %42949 14 ECR 96 03791 14 ECR 9641063 14 ECR 9644088 14 ECR 9641205 15 ECR %41208 15 ECR 9641311 15 ECR 9644425 15 ECR %41516 16 ECR 9644524 16 ECR 97 00258 16 .
ECR 97-01088 16 DJhtI ECR 97-01067 16 Combustible Imding Analysis 17 Technical Requirements Manual, Rev. 3 17
4 PECO ENERGY COMPANY LIMERICK GENERATING STATION UNITS 1 AND 2 DOCKET NOS. 50-352 AND 50-353 l
r ANNUAL 10CFR50.59 AND COMMITMENT REVISION REPORT JULY 1,1996 TIIROUGIl JUNE 3t 1997 SAFETY EVALUATION SUMMARIES
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LIMERICK GENERATING STATION UNITS 1 AND 2 DOCKET NOS. 50-352 AND 50-353 LICENSE NOS. NPF-39 AND NPF-85
- MOD ECR 95-00078 . Unit 1 Unit 2. Common x This modification changed the Refuei Floor crane. There were three parts to the improvement project: 1) the load sensing system was modified to provide more consistent load readings during travel; 2) the existing crane positioning system wat.. Ganged from optical-mechanical system to a programmable limit switch with resolvers; 3) the pendant controls were replaced with radio controls. The load sensing improvement resolved inaccuracies associated with load movement. The new positioning system provides more accurate positions information with lower
{ maintenance. The radio controls only change the method of interface with the control system.
Thi; change affected a section of the UFSAR and is an overall enhancement to maintenance and operations.
MOD ECR 95-05269 Unit 1 x Unit 2 x Common.
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) Revision 0 of ECR LG 95-05269 reduced the size of the jungr cables fcr the battery cart for J Batteries 1(2)CD101 and 1(2)DD101 since the jumpers were originally sized to be useable on the Division I and 11 Batteries which are considerably larger than the 1(2)CD101 and 1(2)DD101 batteries. Revision 1 of ECR LG 95-05269 allows the use of the battery carts to exit a Limiting Condition for Operations (LCO) action statement due to permanent plant battery cell problems and provides time for replacing or repairing defective cell (s) while maintaining the battery m a x Technical Specification (TS) operable status. By using the carts to maintain or return the battery to operable status, the possibility of exceeding the eight (8) hour allowable outage time (AOT),
i, which requires plant shutdown, is avoided. The maximum duration for use of the battery cart (s) for this activity is limited to seven (7) days. A maximum duration of seven days has been selected to: limit the duration of the compensatory measures for fire protection; limit ingress / egress ~
restrictions in the battery rooms; eliminate the need for additional equipment surveillance not contained in existing engineering analyses; and because this time period is sufficient to return the permanent plant battery to its normal condition. Tnis change affected a section of the UFSAR and is an overall enhancement to maintenance and operations.
MOD ECR 96-00719 _Un't 1_ Unit 2 3 Common .
This modification drilled a small hole in the high pressure side of the wedge on High Pressure Coolant Injection (HPCI) Pump Discharge injection valve HV-055-2F006, to loop 'B' Core Spray, to eliminate the potential for pressure locking of the valve disc. Numerous industry and regulatory documents identify the problem of flexible wedge gate valves which have failed to open from " pressure locking." This hole provides a continuous vent path from the valve bonnet area to $.: upnream side of the valve disc. This continuous venting prevents pressure build-up inside of the valve bonnet area resulting in the mitigation of the pressure locking phenomena.
This change has no adverse impact on the safety related functions of this valve. This change affected a section of the UFSAR and is an overall enhancement te operations.
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LIMERICK GENERATING STATION UNIT'i 1 AND 2 DOCKET NOS,50-352 AND 50-353 LICENSE NOS. NPF-39 AND NPF-85 hiQD ECR 96-00720 Unit 1 Unit 2 5 Conznon.
This modificetion drilled a small hole in the high pressure side of the wedge on IIPCI pump discharge valve HV-055-2F105 to eliminate the potential for Thermally Induced Pressure Imcking (TIPL) of the valve disc. Numerous industry and regulatory documents identify the problem of flexible wedge gate valves which have failed to open from " pressure locking." This hole provides a continuous vent path from the valve bonnet area to the downstream side of the valve disc. This continuous venting prevents pressure build-up inside of the valve bonnet area resulting in the mitigation of the pressure locking phenomena. This change has no adverse impact on the safety related functions of this valve. This change affected a section of the UFSAR and i3 an overall enhancement to operations.
MOD ECR 96-00721 Unit 1 Unit 2 5 c'ommon.
This modificsion was a corrective action incorporated during 2R04 to reduce the potential for liquid entrapment induced pressure locking and thermal bindmg of Reactor Core Isolation Cooling (RCIC) injection valve HV-049 2F013. The valve manufacturer, Velan, provided a more tiexible wedge for the valve which significantly reduces the probability of a thermal binding event. The wedge was also provided with a small pressure relief hole to eliminate the susceptibility to liquid entrapment induced pressure locking. This change affected a section of the UFSAR and is an overall enhancement to operations.
MOD ECR 96-01192 Unit 1_ Unit 2 s Common .
This modification drilled a small hole in the upstream (suppression pool) side of the wedge on HPCI Pump Suction valve HV-055-2F042 to eliminate the potential for TIPL of the valve disc.
Numerous industry and regulatc y documents identify the prvblem of flexible wedge gate valves which have failed to open from " pressure locking " This liole provides a continucus vent path from the valve bonnet nrea to the upstream side of the valve disc. This continmts venting prevents pressure build-up inside of the valve bonnet area resulting in the mitigation ' the TIPL phenomena. This change has no adverse impact on the safety related functions of u :.s valve.
This change affected a section of the UFSAR and is an overall enhancement to operatLos.
MOD ECR 96-01594 and ECR 96-01598 Unit 1 Unit 2 s Common.
This madification drilled a small hole in the upstream (suppression pool) side of the wedge on RCIC Pump Suction valve HV-049-2F031 and in the downstream (RCIC Pump) cide of RCIC Pump Suction valve HV-049-2F029 to eliminate the potential for TIPL of the valve disc.
Numerous industry and regulatory documents identify the problem of flexible wed :e ge valves which have fat.ed to open from " pressure locking " This hole provides a continuous vent path from the valve bonnet area to the upstream / downstream side of the valve disc. This continuous venting prevents pressure build-up mside of the valve bonnet area resulting in the mitigation of the TIPL phenomenr.. This change has no adverse impact on the safety related functions of these valves. This change affected a sectim of the UFSAR and is an overal! enhancement to operations.
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LIMERICK GENERATING STATION UNITS 1 AND 2 DOCKET NOS. 50-352 AND 50-353 LICENSE NOS. NPF-39 AND NPF-85 hiQD ECR 96-QL5f.2_gnd ECR 96-02001 Unit 1. Unit 2 3 Common .
This modification drilled a small hole in the upstream (Residual Heat Removal Pump) side of the wedge on the Drywell Spray inlet valves MV-051-2F016A/B to eliminate the potential for pressure locking of the valve diec. Numerous industry and regulatory documents identify the problem of flexible wedge ghte valves which have failed to open from " pressure locking." This hole provi6s a continuous vent path from the valve bonnet area to the upstream side piping.
This continuous venting prevents pressure build-up inside of the valve bonnet area resulting in the mitigation of the pressure locking phenomena. This change has no adverse impact on the safety related functions of these valves. This change affected a section of the UFSAR and is an overall enhancement to operations.
MOD ECR 96-02288. ECR 96-02289. Unit 1. Unit 2 x Common .
ECR 0642290. and ECR 96-02291 This modification removed the external bypass line between the bonnet and Reactor Pressure Vessel (RPV) test / drain connection from Low Pressure Coolant hijection (LPCI) valves HV-051-2F017A/B/C/D originally installed to eliminate pressure locking. A disc with a small pressure relief bole ir the high pressure side of the disc face, to allow venting of the bonnet back to the downstream (vessel) side piping, was installed in place of the external bypass line. Numerous industry and regulatory documents identify the problem of flexible wedge gate valves which have failed to open from ' pressure locking." In addition, the manual valves HV-051-2186A/B/C/D installed to facilitate between the seat Local Leak Rate Test (LLRT) testing were removed and replaced with piping. This change affected a section of the UFSAR and is an overall enhancement to operations.
MOD ECR 9642784 Unit 1. Unit 2 I Common .
This modification installed an alternate replacement item for the Electrohydraulic Control (EHC) system backup over speed tri, (BOST) card. The previous card, known as a Megacycler, was no longer available. The vendor recommended replacement is known as an Auxthary Frequency to Voltage Converter (AFVC). The BOST card receives an input pulse signal, which is proportional to turbine speca, and provides a voltage output proportional to turbine speed for use in the electrical BOST circuitry. This activity did not mclude any changes to any trip or actuation seToints or surveillance intervals. The EHC system and the BOST circuitry will continue to operate consistent with the current design and licensing requirements. This change affected a section of the UFSAR and is an overall enhancement to operations.
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LIMERICK GENERATING STATION UNITS 1 AND 2 DOCKET NOS. 50-352 AND 50-353 LICENSE NOS. NPF-39 AND NPF-85 MOD ECR 9642638 Unit 1 x Unit 2. Common.
This modincation drilled a small hole in the upstream (P.esidual Heat Removal Service Water -
Pump) tide of the wedge on the Residual Heat Removal (RHR) Heat Rchanger Residual Heat Removal Service Water (RHRF Inlet vahe HV-051-1F014B to eliminate the potential for pressure locking of the valve disc. Numerous industry and regulato.y documents identify the problem of flexil,1c wedge gate valves which have failed to open from " pressure locking." This hole provides a continuous vent path from the valve bonnet area to the upstream side of the valve disc. This continuous venting prevents pressure build-up inside of the valve bonnet area resulting in the mitigation of the pre;sure locking phenomena. This change has no adverse impact on the safety related functions of this valve. This change affected a section of the UFSAR and is an overall enhancement to operations.
MOD ECR 96-03220 Unit 1 x Unit 2. Common.
This modification added a 1/2" bypass line around the Core Spray (CS) "A" pump discharge check valve 052-1F003A. This line provides a means to bleed a small, quantity of flow past the chcck valve to the suppression pocl to prevent CS injection piping hne pressurization in the event of inleakage past the CS injection valve. i.% bypass line is designec to existing pipe and instrument tubing requirements and its addition does not result in an Unreviewed Safety Question. This chang (. affected a section of the UFSAR and - an overall enhancement to maintenance and operations.
MOD P00100 Unit 1 x Unit 2. Common .
This modification retired the Plant Process Computer (PPC) and the Emergency Response Facility Disalay System JiRFDS) as a result of the installation of the new Plant Monitoring System (PMS) for Unit 1. This change affected a section of the UFSAR and is an overall enhancement to operations.
MOD P00140 Unit 1 x Unit 2 x Conunon .
This modification involved upgrades to the Unit I and Unit 2 Main Steam Isolation Valves (MSIVs). Primarily this inodification replaced the standard pop rt with a nose-guided popret.
This design has been used in the nuclear industry to improve t:e seating characteristics of the valve and improve its leak rate reliability. This change affected a section of the UFSAR and is an overall enhancement to operations.
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LIMEIUCK GENERATING STATION UNITS 1 AND 2 DOCKET NOS. 50-352 AND 50-353 LICENSE NOS. NPF-39 AND NPF-85 MOD P00166. P00167. and P00168 Unit I s Unit 2. Common .
These modifications installed piping and valves in the common Emergency Service Water (ESW) and RHRSW systems. P00166 added piping and valves to unitize the ESW system. Unitization allows work on one unit to be performed without affecting the other unit. P00167 crosstied the ESW and RIntSW supply headers at the Spray Pond Pumphouse (SPPH) yard and then again in the pipe tunnel. The crosstie.; allow one supply header to support operation of both systems.
while the other supply header is out of service. P00168 crosstied the RHRSW return headers in the pipe tunnel, again allowing one header to be removed from service while the remaining header supports operation of both loops. There are different limitations associated with the sarious configurations provided by these mods. The ESW unitization mod is a permanent canfiguration change while both crossties (P-167 and P-168) will only be used during emergency / maintenance situations. These modifications affected a section of the UFSAR and are an overall enhancement to maintenance and operations.
MOD P00227 Unit 1 Unit 2 3 Common.
This modification eliminated the RHR Steam Condensing Mode. The function of the RHR steam e condensing mode was to condense all of the steam generated after a scram. The steam condensing mode was never used at Limerick. A portion of the components which made up this mode were abandoned in place prior to this modification, which rendered the moc'e inoperable.
g However, routine preventive maintenance and testing was required on various components which made up the steam condensing mode and these activities were time consuming and :osuy. This modification affected a sectic,n of the UFSAR and is an overall enhancement to maintenance.
MOD P00290 Unit 1. Unit 2 s Common s This modification replsced several existing Main Control Room (MCR) recorders with new (Westronics 2l00 Series) recorders, Existing recorders were replaced because they are no longer manufactured and a reliable supply of spare parts is not available. This modification affected a section of the UFSAR and is an overall enhanceraent to maintuance and operations.
MOD P00291 Unit 1_ Unit 2 x Common .
This modification replaced fourteen large case multipoint recorders in the MCR with one Data Acquisition Sy.< tem (DAS). These recorders monitored nonsafety-related plant parameters such as temperature, conductivity, vibration, eccentricity, and metal expansion. They provided no cornol or trip functions. None of the recorders were safety-related, or were required for TS compliance. One of the recorders inte3ced with a safety-related system, HPCI, but it was not being utilized as indication for any safe./ related parameters. This modification affected a section of the UFSAR and is an overall enhancement to maintenance and operations.
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LIMERICK GENERATING STATION UNITS 1 AND 2 DOCKET NOS,50-352 AND 50-353 LICENSE NOS. NPF-39 AND NPF-85 MOD P00565 Unit 1. Unit 2 x Common .
This modification added permanent 480vac and 120vac power in the drywell. The power feed is .
from an offsite supply, via the Site Support Building 480vac lead Center and will only be energized during an outtge Added in the drywell were 480vac welding receptacles and 120vac GF1 duplex receptacles. This installation supports outage activities in the drywell by precluding the future necessity of pulling temporary power cables into the drywell and setting up power packs in the dtywell. This installation will result it. a significant time, cost and radiation exposure savings. This change affected a section of the UFSAR and is an overall enhancement to maintenance.
MOD P00573 Unit 1. Unit 2 x Common .
This modification replaced Reactor Water Clean:.p Dump Flow Control valve HV-C-0441F033 due to seat takage when in the closed position. This leakage was attributed to cavitation damage that has occurred as a result of throttling this valve during the operational hydrostatic testing.
This modification replaced the installed Hanunel-Dahl valve ,vith a valve more suitable for the hydrostatic test service conditions (i.e., valves with anti-cavits: ion trim). HV-C-044-1F033 is non-nuclear safety-related but is instailed in a seismic category IIA system. The affected valve and piping are ASME II, Class 3. This change affected a section of the UFSAR and is an overall enhancement maintenance and operations.
MOD P00604 Unit 1_ Unit 2 x Common .
Thic modification replaced all the 1/4 and 1/2 KIP Pacific Scientific (PSA) mechanical snubbera that were part of the TS inspection program with Lisega hydraulic snubbers. A review of both Limerick and industa experience by Limerick Component Engineering showed that the reliability of these snubbers in t.' smaller range (1/4 and 1/2 KIP) is less than desirable. The Lisega snubbers are a functiona. replacement in fit, form, and function for the corresponding PSA snubbers. This modification affected a section of the UFSAR and is an overall enhancement to maintenance and operations.
MOD P00649 Unit 1. Unit 2 Common 3 This modification made alterations to the MCR peripheral rooms' Heating, Ventilating, and Air Conditioning (HVAC) system due to the change in the use, occupancy, and configuration of these rooms. The cooling load and airflow requaements .ar the peripheral rooms were recalculated based on their current usage and utilization of a new maximum room temperature of 78*F. The airflows were rebalanced utilizing the newly calculated values to maintain tne peripheral rooms under design conditions between 65 F and 78 F and under normal operating conditions between 68'F and 72*F under the control of TV-C-090-43A/B. A new return air duct was installed to assure a proper air balance can be maintained for room 535A. This review also support ~1 the approval of SP-170 procedure for the MCR HVAC Air Flow Rebalance which was used during the instelation of this modification. This modification affected a section of the UFSAR and is an overall enhancement to operations.
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LIMERICK GENERATING STATION UNITS 1 AND 2 DOCKET NOS. 50-352 AND 50-353 LICENSE NOS. NPF-39 AND NPF-85
. MOD P00674 Unit 1. Unit 2 x Common .
This modification replaced the 2A-P202-DR RHR pump motor with a newly purchased RHR pump motor. The old motor had a small oil leak in the upper bearing that was drawing oil into the motor by normal cooling air flow when the motor was operated. The replacement motor is a Q-listed, safety related,1250 hp,6 pole,4 kV, 3 phane,60 Hz, vertical form, wound induction motor. General Electric desigrul this replacement motor to bc interchangeable with their existing RHR pump motors. This modification affected a section of the UFSAR and is an overall enhancement to maintenance and operations.
NCR 92-00327 Unit 13 Unit 2 3 Common.
This NCR addressed several discrepancies and amoiguities regarding the H2 02 analyzers as described in the UFSAR and TS. This disposition revised the UFSAR and TS to reflect actual plant configuration and practices. This NCR affected a section of the UFSAR and is an overall enhancement to maintenance and operations.
NCR 94-00313 _ Unit 15 dnit 2_ Common .
This NCR abandoned the Steam Flooding Dampers BPD-076-201-68A/B and control circuits which were blanked off prior to Unit 1 cornmercial operation. They were abandoned by completely isolating the controls electrically. The affected drawings were revised ta show scheduled cables as " Spare" and to show internal vendor wiring as removed or relocated, as required. The dampers were revised to show as " Abandoned" on the affected drawings. This NCR did not impact the physical configuration of the HVAC duct work. There are no equivalent Unit 2 dampers or ductwork, but this NCR deleted Unit 2 electrical components that existed in the Component Record List (CRL). This NCE affected a section of the UFSAR and is an overall enhancement to maintenance and operations.
NCR 95-04N9 Unit 1. Unit 2 x Common .
This NCR had a final repair disposition and an interim use-as-is dispositirn which justified continued operation with av approximately 5/8" hole in the mesh screen in CS suction strainer 2D1F214. The final disposition repaired the hole in the mesh screen by installing a 1/4" toggle bolt, a fender washer, and lock washer through the 5/8" hole in the strainer body and tightening the togp bolt to block the hole. A nut was staked on the toggle bolt to prevent the.
toggle from disengaging from the bolt. All the material were constructed of stainless steel.
This NCR affected a section of the UFSAR and is an overall enhancement to operations.
NCR 96-00733 Urut 1. Unit 2 3 Common _
This NCR addressed the stopping of the leak on Alternate Rod Insertion (ARI) solenoid valve SV-M7-2F162A by temporarily plugging the discharge vent line. The ARI system controls
. eight valves that work together to remove air from all 185 scram valves and activate the scram ascharge volume valves. Plugging the discharge port to the SV-2F162A valve does not negatively affect the ability of the ARI system as described in the SAR and an unreviewed
, safety question _ is not involved. This NCR affected a section of the UFSAR and is an overall enhancement to operations.
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l LIMERICK GENERATING STAT 9 4 UNITS 1 ANb 2 DOCKET NOS. 50-352 AND 50-353 LICENSE NOS. NPF-39 AND NPF-85 NCR 96-02564 Unit 1 x Unit 2 x Common .
This NCR addressed a final use-as-is disposition for not draining the emergency diesel generator air start line coalescent filter bowls in conjunction with receiver blowdown. The filter bowl blowdown is not part of the manufacturer's recommendations contained in the vendor manual. The designed provisions (i.e., non-corroding materials / coatings) that preclude the system from the adverse affects of moisture, coupled with the prescribed air receiver blowdown procedure which minimizes resident system water, make filter bowl draining not necessary. The only recommended action for the filters is met by the five year ext.mination and maintenance procedure M-020-025 which directly satisfies the manufacturer's recommendation of inspecurenlace" on a 41/2 - 5 year frequency. This NCR affected a section of the Ur%R and is an overall enhancement to maintenance and operations.
NCR 96 02901 Unit 1 x Unit 2 x Common.
This NCR justified the existing installation of the Emergency Diesel Generators (EDG) control panel and relay boxes without previously described dust covers, based on the past reliability of the EDGs. The existing UFSAR statements were made in response to FSAR requested information regarding the degree of compliance with the recommendations of an EDG reliability enhancement study that were not mdicative of initial design, and changes were not performed to bring the plant into agreement with the statements. This NCR affected a section of the UFSAR and is an overall enhancement to operations.
NCR 96-03064 Unit 1. Unit 2 x Common .
This NCR, revision 1, provided the engineering and documentation recuirements necessary to support replacement of the 2D (Division IV) Battery as recommenced by the Revision 0 Interim Disposition. Resision 0 identified that the 2D Battery had experienced six cell failures identified by low voltage of the cell. This was apparently caused by positive to negative plate bridging due to sediment bui!d-up. The Interim Disposition established a plan of action to maintain the h tery in operaue status until it could be replaced with a new battery. The plan of action included frequency of cell voltage monitoring, visual inspection and replacement of weak cells to preempt celi failure. In addition, during the performance of the Fire Protection Review Checklist (FPRC) for this NCR, a discrepancy was found in the combustible loading of the battery material which is common to all Division III and IV battery rooms. Revision I to this NCR corrected this condition. This NCR affected a section of the UFSAR and is an overall enhancement to maintenance and operations.
NCR 97-00212 Unit 1 x Unit 2 x Common .
This NCR provided the bases for placing the test switch that simulates the Loss of Coolant Accident (LOCA) signal during circuitry testing in the " Test" position until the LOCA contact was verified as functional. During the review of the logic associated with the detection of a degraded voltage condition per the requirements of Generic Letter 96-01, it was determined that one contact in the logic was not verified during surveillance testing. This particubr relay contact causes the degraded voltage logic to actuate at nine seconds under a LOCA condition vice the normal actuation at 60 seconds. Placing the switch in *he test positica has the effect of preempting the normal,60 second actuation with the operation of the nine second circuit. Th's NCR affected a section of the UFSAR and is an overall enhancement to maintenance and operations.
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LIMERICK GENERATING STATION UNITS 1 AND 2 DOCKET NOS. 50-352 AND 50-353 LICENSE NOS. NPF-39 AND NPF-85
. NCR 9740242 Unit 13 Unit 2 5 Common.
This NCR provided the basis for operating the unit using offsite sources with untested relay contacts, found during the Generic letter 9641 review, until such time as the contacts were tested. These relay contacts are associated with the loads which may not disconnect from the 4ky buses during a LOCA. Both offsite source voltage repilation / loading issues and Regulatory Guide 1.75 concerns were addressed. The final hCR disposition was " rework" since field work was required (testing of the referenced contacts) and the hardware was returned to its original condition. This NCR affected a section of the UFSAR and is an overall enhancement to maintenance and operations.
NCR 97-01026 Unit 13 Unit 2_ Common .
This NCR addressed justification of the use of nineteen original equipment control blades, with their average B-10 depletion greater than 34% but less than 42% for the duration of Cycle 7 of Unit 1. Fuel and Services Division had performed analyses to confirm that adequate cold shutdown margin exists if the worth of the three blades is completely lost. Additionally, General Electric has performed analyses to support operation through the remairder of Cycle 7 with twenty-one blades e)ceec'ing their end of life criteria. This NCR affectui a section of the UFSAR and is an overall enhancement to operations.
TPA 96-02816 Unit 1 a Unit 2 3 Common.
This temporary change involved the temporary removal of the bird screens from the outlet of the EDG exhaust stacks. The bird screens were installed on the exhaust stacks to preclude debris from entering the stacks and accumulating at the base cf the stacks such that exhaust back -
pressure is increased. Excessive back pressure could adversely affect EDG perfonnance. The .
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removal of the bird screens precluded accumulated material (mainly rust from the imide of the cast iron stacks) from being trapped against the inside of the screens, and causing increased back pressure in the FDG exhaust lines. This scenario was r ostulated as a potential contributing factor __-
m recent EDG crankcase overpressurization events. R~emoval of the tird screem provides a freer path for expulsion of any accumulatcd stack debris. This change affected a section of the _
UFSAR and is an overall enhancement to maintenan:e and operations.
l TPA 96-03716 _ Unit 1_ Unit 2 & Common. .
This temporary chaage involved the Drywell Air Cooler Condensate Orain Flow Monitormg System. This change teinpor arily removed the malfm.tior.ing air cooler drain flow tramminer FT-87-220D from se.vice This temporary c'unge was installed to adjust and maintain the output signal of Ft'-OS?-22GD to summer FY-087-220B as 'l Vo?ts Direct Current (VDC). This change y
does not affect any other flow transmitters. This change affected a section of the UFSAR and is an cvemil enharcement to maintenance and operations. _-
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LIh1ERICK GENERATING STATION UNITS 1 AND 2 DOCKET NOS. 50-352 AND 50-353 LICENSE NOS. NPF-39 AND NPF-85 PROCEDURE S10.7.A and S53.7. A Unit 1 x Unit 2 x Common .
These procedures; S10.7.A, " Abnormal Service Water System Operation" and S53.7.A, -
" Alignment of Fuel Pool Cooling System for Natural Circulation," were revised to allow service water to be supplied from the operating unit service water system to support tutural circulation of the refuel unit if the refuel unit service water system is unavailable. During a refuel outage in the natural circulation mode, alternate methods of cooling are desirable if the primary system is lost.
These revisions allow an additional barrier to support the defense-indepth strategy. This change
{ affected a section of the UFSAR and is an overall enhancement to operations.
PROCEDURE S77.1. A Unit 1. Unit 2 x Common .
i This procedure, S77.1.A "Startup of Drywell Recirculation System," was changed to extend the i life of air cooler condensate drain flow element FE-087-22nC. This change involved the L shutdown of the 2EV212 ("E") drywell unit cooler. This action reduced the condensate flow s.en by the flow element and should reduce flow element degradation. This action also iesulted in reductions in local area drywell cooling airflow that must be thoroughly evaluated. This change affected a rection of the UFSAR and is an overall enhancement to maintenance and operations.
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[ PROCEDURE SP-176-2 1, inh 1 Unit 2 x Common.
1 This change inrjlemented Special Procedure SP-176-2 to p:rform Main Generator voltage regult'or (Alterrex Excitation System) stability testing while tne generator is connect to the Main i Power Grid for the Limerick Unit 2 refueling outage,2RN During the course of this test, a voltage difference of appioximately 1% of generator terminal voltage is established between the
, " Auto and " Manual" settings on the regulator. When the regulator is switched from manual to automatic, a 50-60 Mvar swing in the output of the generator remks. As the regulator
[ establishes stability, various regulator performance data is meerded, if the generator terminal voltage becomes unstable, ?he operator is insuucted to immediately place the reguhtor back in manual. A cautien is placed w. thin the procedure to warn of this possible outcome. This was a i
a test not previously described in the SAR.
F PROCEDURE ___SI-2-072-106-l&2 and ST-2-072-107-l&2 Unit 1 x Unit ^2 3 Common .
These tests, Reactor Enclosure Balance of Plant (BOP) Isolation Logic System Functional (LSF)/ Simulated Automatic Actuation (SAA) and Reactor Enclosure Recirculation Systems (RERS), Standby Gas Treatment System (SGTS), were revised to allow the performance of the testing durit.g power operation. In the HVAC LSF, both the A and B Channel HVAC reset switches are placed into the ' reset' position simultaneously. The reset switches bypass the low Differential Pressure (dP) isolation signal for the Reactor Enclosure (rte) secondry containment.
TS Amendments 112 (Unit 1) and 74 (Unit 2) were issued to no longer require the low dP isola: ion for Reactor Enclosure Secondary Contaimnent. Placement of the reset switches in
' reset' no longer requires entry into a TS action. Since the TS requirement no longer exists, the esting may be perfortned during power operatiott This change affected a section of the UFSAR and is an overull enhancement to operations.
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LIMERICK GENERATING STATION UNITS 1 AND 2 DOCKET NOS. 50-352 AND 50-353 LICENSE NOS. NPF-39 AND NPF-85
. TEST TCF 97-0480 Unit 1. Unit 2 x Common _
e This change involves a Troubleshooting Control Form (TCF) to apply a temporary station ground to the neutral bus through a IK oLrn resistor. This activity supports efforts to locate an mtermittent ground on the Unit 2 Non-Safeguard 125/250V DC system. It allows Instrumentation and Controls (I&C) personnel to calibrate the trigger level of the recorder use:d to record grounding events on the DC gstem. The recorder trac, indicates which part of the DC system the ground is on (i.e., posiave, negative or neutral leg of the DC system). With this information, the investigation can be focused on the specific , art of the DC system where h the ground is occurring. The Unit 2 Non-Safeguard 125/200V bC system is independent of the Unit 1 Non-Safeguard 125/250V DC system and the Class IE 125/250V DC system, ed a single ground fault does not cause immediate loss of the faulted nystem. A ground detection and alarm system is provided for each system. This was a test not previously described in the SAR.
UFSAR CIIANGE ECR 94-11346 Unit 15 Unit 2 3 Common .
f- 1his UFSAR change revised Chapter 13 to more accurately reflect our commitment to l ANSI /ANS 3.1-1978, " Standard for Selection and Training of Personnel for Nuclear Power j Plants," as required by TS Section 6.3.1. Chapter 13 of the Limerick UFSAR was revised to include a description of only the essential managerial positions (e.g., Plant Manager, Manager -
Radiation Protection, Manager - Chemistry, etc.) along with the comparable ANSI!ANS 3.1-1 1978 position, and removed references to ANS1/ANS qualification requirements associated with 3
varicus organizational positions throughout Chapter 13. This information is now controlled by Administrative Procedure A-C-31. This change does not involve any reduction in commitment to ANSI /ANS 3.1-1978 as required by TS Section 6.3.1. Lum..ick plant personnel are still required to satisfy the applicable portions of ANS1/ANS 3.1-1978 regarding position qualifications.
UFSAR CHANGS ECR 45-05039 Unit 1_ Unit 2_ Ccmmon a This UFSAR change revised Sections 8.1.6.1.12 and 8.3.1.1.2.11 which describes the primary
_ contai. uncut penetration conductor overet:rrent protection. Thes: revisions included changing 3 test requirements from a rotating 10% sample every 24 months to all breakers every 60 months
, with approximately 40% tested each cycle, incorporating additional detailed information from previous PORC position statements and rewording of text to clarify intent and improve L readability, relocating information from Section 8.1.6.1.12 (RG 1.63 co.npliance) to Section 8.3.1.1.2.11 (electrical cf ruit protection systems), and typing corrections.
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LIMERICK GENERATING STATION UMTS 1 AND 2 DOCKET NOS. 50-352 AND 50-3S3 LICENSE NOS. NPF-39 AND NPF-85 UFSAR CllANGE FfR 96-01283 Unit 1 x Unit 2 x Common .
This UFSAR change incorporated the results of a thermal bydraulic analysis for the spent fuel pools performed by a qualified consultant. This analysis evaluated reducia the in-core decay time prior to moving fuel from the reactor vessel to the spent fuel pool witn the RHR system supplementing the Fuel Pool Cooling and Cleant;p (FPCC) sys'em. The analyzed in core decay time was reduced from 125 hours0.00145 days <br />0.0347 hours <br />2.066799e-4 weeks <br />4.75625e-5 months <br /> to 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />. The anMyzed move rate was also changed from 8 assemblies per hour to 10 assemblies per hour. The reduction in the in-core decay time and the increase in the move rate resulted in an increase in the mr.ximum anticipated decay head load for a full core offload from 37.6 MBtu/hr. to 46.76 MBtu/hr. The increase in the maximum anticipated heat load is within the capacity of the RllR system to maintain the bulk spent fuel pool temperature less than 140'F.
UFSAR CH ANGE ECR 96-01775 Unit 1 x Unit 2 x Common .
This UFSAR change revised Section 3.9.6 deleting Table 3.9-8 and Table 3.9-51 which list specific components in the Inservice Testing (IST) program. The tables were replaced by a note referencing Specification ML-008 which defines the scope of the program. This was done to climinate redundant information in the Specification and the UFSAR.
UFSAR CHANGE ECR 96-02318 Unit 15 Unit 2 3 Common .
This UFSAR change revised the discussion in Section 3.6.1 regarding operator actions to shutdown the reactor following a Reactor Water Cleanup (RWCU), HPCI or RCIC system isolation resulting from a high energy line break in one of those systems. These changes clarified that operator actions following such an isolation are dependent on approved operation and emergency procedures based on plark conditions and tha! these actions do not necessarily include a reactor shutdown. This change makes the UFSAR consistent with the TS and approved cperating procedures.
UFSAR CHANGE ECR 96-02319 Unit 1 x Unit 2 5 Common .
Tlus UFSAR change corrected errors found in Section 3.6.1, Postulated Pipin;; Failures in Fluid Systems, concerning the routing of the auxiliary and heating steam systems in the RE. These errers weie discovered during the UFSAR verification effort.
UFSAR CH ANGE ECR 96-02386 Unit 15 Unit 2 x Common.
This UFSAR change revbd ambiguous and incorrect statements in Sections 2.3.3, 11.5.6.2, .
and 11.5.6.3 found during the UFSAR verification effort. The majority of the incorrect statements in these sections dealt with new computer systems installed on site. For instance, meteorological and radiation data is reviewed at the Emergency Operations Facility (EOF) through the Emergency Preparedness Data System (EPDS). The Radiological Meteorological Monitoring System (RMMS) no longer directly communicates with the EOF, instead it interfaces with the EPDS computer. Another section required revision due to the use of Plant Information Management System (PIMS) for documenting maintenance history.
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LIMERTCF GENERATING STATION UNITS 1 AND 2 DOCKET NOS. 50-352 AND 50-353 LICENSE NOS. NPF-39 AND NPF-85 LIESAR CHANGE ECR 9602473 Unit 1 x Unit 2 x Common.
This UFSAR change revised and clarined Section 6.2.5 due to items discovered during the UFSAR verification effort. One change was strictly editorial and had no impact on the operation of the plant. Another change clarined the type of fuel used in the hydrogen generation calculations, this new fuel type has no significant impact on the hydrogen generation rate during accidents. Another change described how the Pcst LOCA Recombiner system is operated daring-accidents and confirmed that this mode of operation results in plant conditions that are the same as or more conservative than was previously described in the UFSAR.
UF3AR CHANGE ECR 96-02488 Unit 1 x Unit 2 x Common .
This UFSAR change revised Section 15.7.4 which describes the fuel handling sccident. These changes involved rewording the description of the operator actions. The UFSAR previously stated that the operator will initiate evacuation of the refuel floor area and initiate locking < the refueling area doors. The operator actions were changed to initiate evacuation of the refueling area. The UFSAR also previously stated that the supervisor in charge of fuel handling should 4
instruct his employees to go immediately to the radiation protection personnel decontamination area. This s*atement was changed to notify health physics.
IlESAR CHANGE ECR 96-02636 Unit 1 x U - x Commor, .
This UFSAR change revised Sections 12.5.2 and 12.5.3, Health Physics Program, to clarify ambiguous statements and to correct typographical errors and incorrect statements. These items were identified as part of the UFSAR verification effort.
UFSAR CHANGE ECR 96-02705 Unit 1 x Unit 2 s Common .
This UFSAR change revised Sections 3.1, 3.4, 5.4 7, 6.3, 7.3, 7.4, and 7.6 associated with the RHR system. Thesc items were identified as part of the UFSAR verification effort. These changes involved incorrect statements, ambiguous statemeats, and typographical errors.
UFSAR CH3NGE ECR 96-02738 Unit 1 x Unit 2 3 Commor. .
This UFSAR change revised Sections 6.3.2.2.1 and 7.3.1.1.1 1 associated with HPCI. These items were identified as part of the UFSAR verification effort. .,e changes involved incorrect statements, ambiguous statements, and typographical error l!ESAR CHANGE ECR 9002780 Unit 1 x Unit 2 A Connnon _
This UFSAR change revised Sections 11.5.5 and 1.13 associated with the Post Accident Sampling System (PASS). These items were identified as part of the UFSAR verification effort. These changes involved typographical errors, clarification of ambiguous statements, enhancements to the UFSAR content, tna the correction of text, table, or figure to agree with the plant.
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LIMERICK GENERATING STATION
- UNITS 1 AND 2 DOCKET NOS. 50-352 AND 50-353 LICENSE NOS. NPF-39 AND NPF-85 r UFSAR CHANGE ECR 96-02909 Unit 1 v Unit 2 x Common .
This UFSAR change revised Sections 6.3.2.2.2 and 7.3.1.1.1.2, " Automatic Depressurization .
System," and Sections 15.2.4.1.2.2 and 15.2.4.3.3.2. The first two items were identified as r part of the UFSAR verification effort and the second two items were reviewed in response to a
' request from the Independent Safety Engineering Group (ISEG). These changes involved y correcting incorrect statements and clarifymg ambiguous statements.
i . MFSAR CHANQS ECR 9M049 Unit 1 x Unit 2 x Common .
b This UFSAR change revised Section 8.3.1.1.2, " Class ID AC Power System." These items H were identified as part of the UFSAR verification effort. These changes involved resolving F ambiguous or inconsistent statements in Section 8.3.1.1.2 and reference Section 8.3.4.
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J !)FSAR CHANGE ECR_.96-03791 Unit 1_ Unit 2. Common x This UFSAR change revised Sections 9.2.4.2 and 9.2.5.2 to more clearly state how the E equipment for the clarified water and makeup demineralized water systems is operated in
[ accordance with the app' roved system procedures. The rewording resulted in a more accurate statement of the systems design features. This change provided a raore accurate description of s operational latitude afforded in design of clarified water and demineralized water systems.
L System operating ?rocedures exist which provide controls / steps to operate the systems in the
= inanner described by this revision.
I EFSAR CHANGE ECR 96-04063 Unit 1. Unit 2. Common a This UFSAR change allows plant operations personnel to place Area Radiation Monitors (ARMS) in the zero position for reasons such as defective equipment, known evolutions which would cause an ARM alarm, or for determining whether another ARM in a particular operational area is alarming. Plant personnel are able to place an ARM in the zero position 1 once compensatory actions are implemented. Guidance on appropriate compensatory actions is contained in S27.10.A. This ensures that the appropriate radiological controls are established to protect plant personnel.
! e deleted the existence of the Limerick Modification Branch, which was This part ofUFSAR chankupport Department. As a result of the changing business environment, t the Station need for ::ite unique modification branches is no longer required. This is mainly due to a significant reduction in the number of required / planned plant modifications. Plant h- . modifications are now performed by Limerick Site Design Engineering. The Design .
- ; Engineering section has the required personnel and expertise to perform th. modifications which are expected to be required. This change does not make any physical changes to any ple.r.1 componeat, system, or structure.
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1 LIMERICK GENERATING STATION UNI'IS 1 AND 2 DOCKET NOS. 50-352 AND 50-353 LICENSE NOS. NPF-39 AND NPF-85
. UFSAR CllANGE ECR 96-04205 Unit 13 Unit 2 x Common.
This UFSAR change addressed a one time cycle extension from a normal 24 months for Unit 1 cycle 7 and Unit 2 cycle 5. The UFSA.R assumes a 730 day operating time for fission product buildup when detennining total fission product decay power. The methodology used in determining this value is from UFSAR reference 6.2-13, USNRC Starxlard Review Plan (SRP) 6.2.5, Combustible Gas Control in Containment. ANS .5.1-1994 was used to perform a computatiors cf the percent chan in decay ? eat power between a 24 and 27 month operating cycle. The results showed a ne gible increr:e iri decay heat power by running for 27 months.
The changes ranged from 0.0 at 400 seconds to 3.57% at 462 days (4x10E7 secs.) after shutdown. These values are well within the stated 20% over prediction of the Standard t Review Plan (SRP) method.
UFSAR CHANGE ECR 9644208 . Unit 1 x Unit 2 3 Common .
This UFSAR change revised Section 9.1.3, " Fuel Pool Cooling and Cleanup, System." This change involved a one time cycle extension from a normal 24 mcnths for umt I cycle 7 and unit 2 cycle 5. This revision does not invuidate the design bases. The design basis for maximum anticipated heat load is based on one full core off loaded from the reactor approximately nme days after shutdown to fill the pool, plus the previous normal refueling loads from 24 month refuelings. PECON calculations for this one time cycle extension conclude that the impact on the design basis is not significant.
UFSAR CJIAN_GE ECR 9644311 U nit 1 3 Unit 2 3 Common .
This UFSAR change involved changes to the PECON organization stmeture. These revisions reflect changes to the PECON executive management structure, the administrative changes in the Station Su) port Department (SSD) organization, and a change in the title of the Electrical and Controls besign Branch within Site lingineering to Instrumentation and Controls Design Branch. These organizational changes do not have any direct or adverse effect on plant c operations or safety.
UFSAR CHANGE ECR 9644425 Unit 13 Unit 2 3 Common x This UFSAR change revised the lead calcium batteries' requirement for equalization to only 15 days (4%) per year on average, during their operating life. Analysis shows that the impact on connected components is an agmg issue and that the change in exxcted life of these components due to battery equalization is considered negligible. The yearly duration of battery equalization is conservatively defined in accordance with previous Limerick experience and anticipated DC system operation.
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LIMERICK GENERATING STATION UNITS 1 AND 2 DOCKET NOS. 50-352 AND 50-353 LICENSE NOS. NPF-39 AND NPF-85 UFSAR CHANGE ECR 96-G4516 Unit 1 x Unit 2 x Common .
This UFSAR change modified a previous commitment to the NRC to replace all Main Steam .
Relief Valves (MSRV) each refueling cutage. The previous commitment required replacement of all MSRVs each refueling outage within a 30 month interval with surveillance grace. This commitment was motivated by the extension of the 18 month operations cycle to 24 mon'hs, and the lack of MSRV operating experience over a potential two cycle period. This revision changed the reference refueling outage to 24 month surveillance cycle (plus six month grace) replacement of MSRVs. This change allows ccedit to be taken for MSRVs which are replaced before a refueling outage for meeting the commitment, as long as the 30 month replacement interval is met.
UFSAR CHANGE ECR 96-04524 Unit 1 x Unit 2 x Common &
This UFSAR change revised Sections 1.8 and 6.1 to be consistent with a Quality Assurance Plan Document (QAPD) change regarding commitment to Regulatory Guide' 1.54/ ANSI N101.4 during operation with conformance to ASTM D3843-93. These documents provide Quality Assurance (QA) standards which must be adhered to when applying safety-related coatings in service level 1 areas. Responsibility for updating the QA standard was transferred to ASTM which issued its replacement standard practice D3843-93. This standard is more cancise and easier to use. An analysis concluded that there is no downgrade of QA standards in changing to the newer standard for QA of protective coatings rpplied to nuclear facilities.
UFSAR CHANGE ECR 97-00258 Unit 1 x Unit 2 3 Common .
This UFSAR change increased the allowable lift height of steam separator from five feet to seven feet above the floor of the steam dryer and separator storage pool when the reactor is disassembled and assembled during outages. In order to move the separator and dryer from the reactor well to the storage pool, the loads must travel over the top of a concrete wall which is live feet above the storage pool floor, thereby making the separator already above the five foot limit above the pool floor. The load drop calculations were revised to evaluate a load drop of the steam eparator from a height of seven feet. The conclusion of the calculation remains unchanged that the postulated load drops are acceptable.
UFS AR CHANGE ECR 97-01088 Unit 1 x Unit 2. Common .
This UFSAR change revised when the accumulated water needs to be removed from the diesel fuel oil storage tanks. The requirement for removing accumulated wat:r is contained in the TS for the diesel generators. The UFSAR was revised to state that die accumulated water will be removed when required in accordance with the TS.
IS_. Bases ECR 97-01067 Unit 1 x Unit 2. Common .
This change revised the section of the TS Bases that required accumulated water be rcmoved from the $DG fuel oil storage tanks at least o' ice per 31 days. Water has harmful effects in the EDG storage tank, and it was only being removed when it reached a level of reasonable detection. The TS Bases were revised to remove water from the EDG storage tanks whenever it is found at the minimum detectable level, which is 0.25 inches. This change affected a section of the UFSAR and is an overall enhancement to maintenance and operations.
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LIMERICK GENERATING STATION UNITS 1 AND 2 DOCKET NOS. 50-352 AND 50-353 LICENSE NOS NPF-39 AND NPF-85
. Combustible Loadine Analysis Unit 1 x Unit 2 x Common .
This change revised the Limerick Combustible Loading Analysis methodology including a
, revision of how fire zone combustible loadings are evaluated and tabulated in the Limerick Generating Station Fire Protection Evaluaticti Report (FPER), Section 9A.4, and Tables 9A-1 and 9A-2. This revision was made to provide documentcd heat of combustible values of the combustibles listed in Table 9A-2 of the FPER and to revise Table 9A-1 of the FPER from a quantitative to a qualitative fonnat. Fire hazards are conservatively classified as " low",
" moderate", and high" as referenced in the National Fire Protection Association's Fire i Protection Handbook,17* edition. This change to the FPER allows minor changes in combustible loading within a fire area / zone without the need for an UFSAR change.
Technical Reouirements Manual. Rev. 3 Unit 1. Unit 2. Common &
This revision changed the mimmum number of Traversing incore Probes (TIPS) required to be k operable (movable) from five to four for performing a Local Power Range Monitor (LPRM) y calibration or update of TIP data. This is to allow these activities to be performed when one TIP l mr. hine is out of service. The normal practice is to use all five TIP machines when they are available. This revision also changed the Bases for the TIP systera to cisrify the methods used to demonstrate TIP system operability. The previous core monitoring pro'; ram did not incorporate c first principles simulator models to calculate the neutron and power dis'Jibution, but relied totally on the TIP and LPRM readings to infer the core axial and bundle power distrfoulions. As such, all five TIP machines were required to provide the necessary information to determine fuel L
performance and operating limit margins. The 3D-MONICORE system, while using incore data to improve the core simulation, can produce accurate results, even if the data from a large number of TIP locations or LPRMs are not available.
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