|
---|
Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML20216D8721999-07-26026 July 1999 Review of Submittal in Response to USNRC GL 88-20,Suppl 4: 'Ipeees,' Fire Submittal Screening Review Technical Evaluation Rept:Hope Creek Rev 1:980518 ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20216D8451999-04-30030 April 1999 Rev 1, Submittal-Only Screening Review of Hope Creek Unit 1 IPEEE (Seismic Portion). Finalized April 1999 ML20198N4161998-11-12012 November 1998 MSIV Alternate Leakage Treatment Pathway Seismic Evaluation ML18106A6821998-06-24024 June 1998 Revised Charting Our Future. ML18106A6681998-06-17017 June 1998 Charting the Future. ML20248C7381998-05-22022 May 1998 Rev 0 to Safety Evaluation 98-015, Extension of Allowed Out of Service Time for B Emergency Diesel Generator ML18106A2571998-01-19019 January 1998 Nuclear Business Unit Future Objectives. ML20216E5431997-12-31031 December 1997 Rev 1 to GE-NE-523-A164-1294, Hope Creek 1 Generating Station RPV Surveillance Matls Testing & Fracture Toughness Analysis ML20199A6791997-10-31031 October 1997 RF07 Shroud Circumferential Weld Ultrasonic Exams, Final Rept ML20249A8281997-06-0505 June 1997 100 F Sacs Design Temp Limit Evaluation ML20085F1221995-04-30030 April 1995 RPV Surveillance Matls Testing & Fracture Toughness Analysis ML20082V1881994-10-11011 October 1994 Investigation of an Allegation of Inadequate CR Staffing at Hope Creek Generating Station ML20125D9171992-12-11011 December 1992 Simulator 4-Yr Recertification Rept ML18096A5831992-03-31031 March 1992 Rev 1 to Estimated Frequency of Loss of Off-Site Power Due to Extremely Severe Weather & Severe Weather for Salem & Hope Creek Generating Stations. ML20076E2741991-07-0101 July 1991 Rev 0 to Hope Creek Generating Station Bailey 862 Sys Logic Module Failure Data Rept,Second Quarter 1991 ML20077C4961991-04-0808 April 1991 Rev 1 to Hope Creek Generating Station Bailey 862 Sys Logic Module Failure Data Rept,First Quarter 1991 ML20067B3751991-01-0808 January 1991 Bailey 862 Sys Logic Module Failure Data Rept,Fourth Quarter 1990 ML20045G4211990-10-31031 October 1990 Nonproprietary TS Improvement Analysis for ECCS Actuation Instrumentation for Hope Creek Generating Station. ML20058F2441990-10-0101 October 1990 Bailey 862 Sys Logic Module Failure Data Rept,Third Quarter 1990 ML20059E5401990-08-21021 August 1990 Rev 2 to Removal of APRM Downscale Scram Setpoint for Hope Creek ML18094A3551989-04-30030 April 1989 Assessment of Impacts of Salem & Hope Creek Generating Stations on Kemps Ridley (Lepidochelys Kempi) & Loggerhead (Carretta Caretta) Sea Turtles. ML20086U2571989-03-31031 March 1989 Estimated Frequency of Loss of Offsite Power Due to Extremely Severe Weather & Severe Weather for Salem & Hope Creek Generating Stations ML20248D7751989-03-0909 March 1989 Rev 1 to SPDS Final Validation & Verification Rept ML20207P1011988-09-28028 September 1988 Rev 0 to SPDS Verification & Validation Program,Final Rept ML20151V1221988-04-0101 April 1988 1987 Summary Rept for Hope Creek Generating Station Salt Drift Monitoring Program ML20151A5811988-03-31031 March 1988 Reliability Summary Rept for Bailey 862 Solid State Logic Module ML20237L6171987-08-17017 August 1987 Bailey 862 Solid State Logic Module Bi-Monthly Failure Rept ML18093A1791987-06-19019 June 1987 Installation of Trip-A-Unit Protection Scheme Suppl Info Salem & Hope Creek Generating Stations. ML20209H5461987-04-15015 April 1987 Crdr Supplemental Rept III Hope Creek Generating Station ML18092B4971987-04-0303 April 1987 S-C-E500-NSE-0675-R-1, Justification for Operation of All Three Units at Artificial Island at Increased Power During Hope Creek-Keeney Line Outage. ML20204G0861987-02-12012 February 1987 Rev 0 to Hope Creek SPDS Verification & Validation Design Review Rept ML20213F8451986-11-0606 November 1986 Crdr Supplemental Rept Ii,Hope Creek Generating Station ML20215F3881986-10-0303 October 1986 Hot/Cold Loss of Power Observation Rept ML20195D1411986-05-23023 May 1986 Addendum 3 to Rev 4 to Environ Qualification Summary Rept ML20154N2251986-02-28028 February 1986 Rev 1 to Main Steam Tunnel Flooding Analysis ML20205K2001986-02-21021 February 1986 Rev 4 to Environ Qualification Summary Rept for Hope Creek Generating Station ML20151U7081986-01-31031 January 1986 Monitoring of Lng & Liquified Petrolium Gas Shipping & Const Activities on Delaware River ML20138J8351985-12-31031 December 1985 Single-Failure Analysis for Neutron Monitoring & Process Radiation Monitoring Sys ML20136J3471985-12-27027 December 1985 Control Room Design Review Supplemental Rept 1,Hope Creek Generating Station ML20136D7951985-11-30030 November 1985 Preservice Exam Limitations Rept ML20137T6711985-11-0505 November 1985 Rev 3 to Environ Qualification Summary Rept for Hope Creek Generating Station ML20209J0041985-11-0404 November 1985 Safety Evaluation PSE-SE-Z-024, Deletion of Transversing In-Core Probe Uncertainty,Test 16. Related Info Encl ML20136D6581985-10-31031 October 1985 Rev 1 to Confirmatory Reactor Bldg Basemat Analysis for Hope Creek Generating Station Pse&G ML20138G4741985-10-15015 October 1985 Safety Evaluation:Simplification of Test 23A,MSIV Functional Test ML20138N6681985-10-15015 October 1985 Single Failure Analysis for Neutron Monitoring & Process Radiation Monitoring Sys ML20138G5051985-10-15015 October 1985 Safety Evaluation:Simplification of Test 32,Reactor Water Cleanup Sys ML20138G4931985-10-15015 October 1985 Safety Evaluation:Simplification of Test 28E,Recirculation Sys Cavitation ML20138G4871985-10-15015 October 1985 Safety Evaluation:Simplification of Test 24,Relief Valves 1999-09-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217F1501999-10-12012 October 1999 Special Rept:On 990929,south Plant Vent (SPV) Range Ng Monitor Was Inoperable.Monitor Was Inoperable for More than 72 H.Caused by Electronic Noise Generated from Noise Suppression Circuit.Replaced Circuit ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML20217N6531999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Hope Creek Generating Station,Unit 1.With ML20217M0211999-09-20020 September 1999 Part 21 Rept Re Possible Deviation of NLI Dc Power Supply Over Voltage Protection Circuit Actuation.Caused by Electrical Circuit Conditions Unique to Remote Engine Panel. Travelled to Hope Creek to Witness Startup Sequence of DG ML20211N5531999-09-0808 September 1999 Safety Evaluation Supporting Amend 121 to License NPF-57 ML20211B3781999-08-13013 August 1999 Special Rept 99-002:on 990730,NPV Radiation Monitoring Sys Was Declared Inoperable.Caused by Voltage Induced in Detector Output by Power Cable to Low Range Sample Pump. Separated Cables & Secured in Place to Prevent Recurrence ML20210U4721999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Hope Creek Generating Station,Unit 1.With ML20216D8331999-07-26026 July 1999 Safety Evaluation Concluding That Licensee IPEEE Complete Re Info Requested by Suppl 4 to GL 88-20 & That IPEEE Results Reasonable Given HCGS Design,Operation & History ML20216D8721999-07-26026 July 1999 Review of Submittal in Response to USNRC GL 88-20,Suppl 4: 'Ipeees,' Fire Submittal Screening Review Technical Evaluation Rept:Hope Creek Rev 1:980518 ML20210F3331999-07-22022 July 1999 Safety Evaluation Granting Relief Requests RR-B1,RR-C1,RR-D1 & RR-B3.Finds That Proposed Alternative for RR-B3 Provides Acceptable Level of Quality & Safety & Authorizes Alternative Pursuant to 10CFR50.55a(a)(3)(i) ML20210C4731999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Hope Creek Generating Station,Unit 1.With ML20216D8901999-06-30030 June 1999 IPEEEs Technical Evaluation Rept High Winds,Floods & Other External Events ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML18107A3441999-06-0101 June 1999 Interim Part 21 Rept Re Premature Over Voltage Protection Actuation in Circuit Specific Application in Dc Power Supply.Testing & Evaluation Activities Will Be Completed on 990716 ML20196A1511999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Hope Creek Generating Station,Unit 1.With ML20206Q4731999-05-14014 May 1999 SER Accepting Response to GL 97-05, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Plant ML20206U1571999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Hope Creek Generating Station,Unit 1.With ML20216D8451999-04-30030 April 1999 Rev 1, Submittal-Only Screening Review of Hope Creek Unit 1 IPEEE (Seismic Portion). Finalized April 1999 ML20206C8481999-04-22022 April 1999 SER Authorizing Pse&G Proposed Relief Requests Associated with Changes Made to Repair Plan for Core Spray Nozzle Weld N5B Pursuant to 10CFR50.55a(a)(3)(i) LR-N990157, Special Rept 99-001:on 990315, C EDG Valid Failure Occurred During Surveillance Testing.Testing Resulted in Unsuccessful Loading Attempt,Due to Failure EDG Output Breaker to Close.Faulty Card Replaced1999-04-12012 April 1999 Special Rept 99-001:on 990315, C EDG Valid Failure Occurred During Surveillance Testing.Testing Resulted in Unsuccessful Loading Attempt,Due to Failure EDG Output Breaker to Close.Faulty Card Replaced ML20205R5901999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Hope Creek Generating Station,Unit 1.With ML20205G6051999-03-19019 March 1999 SER Accepting Relief Request Re Acme Code Case N-567, Alternate Requirements for Class 1,2 & 3 Replacement Components,Section Xi,Div 1 ML20205F8911999-03-18018 March 1999 Safety Evaluation Authorizing Licensee Requests for Second 10-year Interval for Pumps & Valves IST Program ML20204F7951999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Hope Creek Generating Station,Unit 1.With ML18106B0931999-02-25025 February 1999 Part 21 Rept Re Possible Defect in Swagelok Pipe Fitting Tee,Part Number SS-6-T.Caused by Crack Due to Improper Location of Heated Bar.Only One Part Out of 7396 Pieces in Forging Lot Was Found to Be Cracked.Affected Util,Notified ML18106B0551999-02-0101 February 1999 Part 21 Rept Re Possible Matl Defect in Swagelok Pipe Fitting Tee,Part Number SS-6-T.Defect Is Crack in Center of Forging.Analysis of Part Is Continuing & Further Details Will Be Provided IAW Ncr Timetables.Drawing of Part,Encl ML18106B0441999-01-29029 January 1999 Part 21 Rept Re Possible Defect in Swagelok Pipe Fitting Tee Part Number SS-6-T.Caused by Crack in Center of Forging. Continuing Analysis of Part & Will Provide Details in Acoordance with NRC Timetables ML20202F6861999-01-26026 January 1999 Engine Sys,Inc Part 21 (10CFR21-0078) Rept Re Degradation of Synchrostat Model ESSB-4AT Speed Switches Resulting in Heat Related Damage to Power Supply Card Components.Caused by Incorrect Sized Resistor.Notification Sent to Customers ML18107A1871998-12-31031 December 1998 PSEG Annual Rept for 1998. ML20199E7271998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Hope Creek Generating Station,Unit 1.With ML18107A1881998-12-31031 December 1998 PECO 1998 Annual Rept. LR-N980580, Monthly Operating Rept for Nov 1998 for Hope Creek Generating Station,Unit 1.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Hope Creek Generating Station,Unit 1.With ML20198N4161998-11-12012 November 1998 MSIV Alternate Leakage Treatment Pathway Seismic Evaluation LR-N980544, Monthly Operating Rept for Oct 1998 for Hcgs,Unit 1. with1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Hcgs,Unit 1. with ML20155J9861998-10-31031 October 1998 Non-proprietary TR NEDO-32511, Safety Review for HCGS SRVs Tolerance Analyses LR-N980491, Monthly Operating Rept for Sept 1998 for Hope Creek Generating Station,Unit 1.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Hope Creek Generating Station,Unit 1.With ML17354B0971998-09-0909 September 1998 Part 21 Rept Re Possible Machining Defect in Certain One Inch Stainless Steel Swagelok Front Ferrules,Part Number SS-1613-1.Caused by Tubing Slipping Out of Fitting at Three Times Working Pressure of Tubing.Notified Affected Utils LR-N980439, Monthly Operating Rept for Aug 1998 for Hope Creek Generating Station Unit 1.With1998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Hope Creek Generating Station Unit 1.With LR-N980401, Monthly Operating Rept for July 1998 for Hope Creek Generating Station,Unit 11998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Hope Creek Generating Station,Unit 1 ML20236N6751998-07-0909 July 1998 Part 21 & Deficiency Rept Re Notification of Potential Safety Hazard from Breakage of Cast Iron Suction Heads in Apkd Type Pumps.Caused by Migration of Suction Head Journal Sleeve Along Lower End of Pump Shaft.Will Inspect Pumps LR-N980354, Monthly Operating Rept for June 1998 for Hope Creek Generating Station,Unit 11998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Hope Creek Generating Station,Unit 1 ML20236E9491998-06-30030 June 1998 Rev 0 to non-proprietary Rept 24A5392AB, Lattice Dependent MAPLHGR Rept for Hope Creek Generating Station Reload 7 Cycle 8 ML18106A6821998-06-24024 June 1998 Revised Charting Our Future. ML18106A6681998-06-17017 June 1998 Charting the Future. LR-N980302, Monthly Operating Rept for May 1998 for Hope Creek Generating Station,Unit 11998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Hope Creek Generating Station,Unit 1 ML20248C7381998-05-22022 May 1998 Rev 0 to Safety Evaluation 98-015, Extension of Allowed Out of Service Time for B Emergency Diesel Generator LR-N980247, Monthly Operating Rept for Apr 1998 for Hope Creek Station, Unit 11998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Hope Creek Station, Unit 1 LR-N980196, Monthly Operating Rept for Mar 1998 for Hope Creek Generating Station,Unit 11998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Hope Creek Generating Station,Unit 1 ML20217D5701998-03-20020 March 1998 Part 21 Rept 40 Re Governor Valve Stems Made of Inconel 718 Matl Which Caused Loss of Governor Control.Control Problems Have Been Traced to Valve Stems Mfg by Bw/Ip.Id of Carbon Spacer Should Be Increased to at Least .5005/.5010 ML18106A5851998-03-0303 March 1998 Emergency Response Graded Exercise,S98-03. Nuclear Business Unit Salem,Hope Creek Emergency Preparedness, 980303 1999-09-08
[Table view] |
Text
r --
r .
p . '- (
L:
SINGLE-FAILURE ANALYSIS FOR THE NEUTRON MONITORING AND PROCESS RADIATION MONITORING SYSTEMS HOPE CREEK GENERATING STATION PUBLIC SERVICE ELECTRIC AND GAS COMPANY
! December , 1985-l' 1
n' 8512190072 851216 PDR ADOCK 05000354 A PM L- ..
SU.GLE-FAILURE A'!tiLYSIS FOR THE NEUIR0fiICilTORIfiG
-AND PROCESS RADIATION 12ilTORI!!G SYSTEll5 Some of the safety related portions of the neutron monitoring system (liMS) and tne process radiation conitoring system (PPF.5) for the Hope Creek Generating Station (H:GS) are not designed and built to confom to the literal separation guidelines of Regulatory Guide 1.75. This analysis establishes the acceptabil-ity of these portions of the ti.' 5 and PPJ!5 by demonstrating that tney meet the single-failure criteria of IEEE Standard 279, which requires that the conse-quences of any single, design-basis failure event in a safety related portion of the systems be' tolerated without the loss of any safety function. -
Portions of NM5 and PRMS External to the NMS and PRMS Panels See Figure 7.1-1 of the HCGS FSAR for the separations concept of the reactor' protection system (RPS) and its relationship to the NM5.
Under the reactor vessel, cables from the individual, local power range conitor (LPRM) detectors and from the individual intercediate range conitor (IRM) detectors are grouped to correspond with the RPS trip channel designations.
These cable groupings are run in conduit from the vessel pedestal area to the NM5 and PRMS panels.
The radiation conitors on the main-steam lines are physically separated. The cabling from the individual sensors to the panels is run in separate cetallic conduit.
Cabling from the HMS and PRMS panels to the RPS cabinets is also run in cetal-lic conduit, providing electrical isolation and physical separation of the HMS and PRMS cabling associated with the RPS system.
It 'is concluded that the safety-related portions of the Nu.5 and PRMS external l to the HMS and PRMS panels adequately conform to the separation criteria of Regulatory, Guide 1.75.
1 l
^
_ ,=
Single Failurn in tha NMS rnd'PRMS Panoln Figures-1 and 2 depict schematically the physical arrangement of the equipment in NMS and PRMS panels Hil-P608, Hil-P635, and Hll-P636. The designs of these panels are similar to those of NMS'and PRMS panels used in several BWR plants accepted by the NRC.
The layouts of the panels and the assignments of specific RPS trip logic circuitry provides the designs with the required tolerance to postulated single failures. The worst-case single failure-would be the loss of any combination
~
of trip signals within one bay of any panel. However, the loss of any bay and its associated wiring would not prevent a scram. A valid scram signal would be transmitted via the other bays.because of the redundancy in the panel designs and the interconnections to the RPS (see Figure 7.1-1 of the'HCGS~FSAR).
The.eight IRM channels and the six average power range monitor (APRM) channels are electrically isolated and physically
- separated. Within the IRM and APRM modules, analog outputs are. derived for use with control room meters, recorders, and the process computer. Electrical isolation at the interfaces _would prevent any single failure from influencing the. trip unit output.
Physical Separation in the NMS and PRMS Panels Adequate separation in the NMS and PRMS panels is achieved
! by using the bay design depicted _in Figures 1 and 2, by using_ relay coil-to-contact as sufficient separation / isolation, and by separation between divisions / channels / wiring. Where conformation with Regulatory Guide 1.75 separation criteria cannot be achieved, the best-effort design is used.
. Circuits that provide inputs to-different divisions of the RPS are physically separated by airgaps or by the walls.
between the bays. Within the panels, where the cable and wiring runs to the different RPS divisions do not conform to the Regulatory Guide 1.75 separation criteria, fire-resistant "Sil-Temp" tape is wrapped around the cables and wires.
This eliminates the possibility of fault propagation between the RPS divisions. In accordance with paragraph 5.6.2 of IEEE: Standard 384,_this; tape has been demonstrated to be acceptable.
' All safety related cabling and wires within these panels
. either meet Regulatory Guide 1.75 or are wrapped 'in Sil-Temp tapefwith the. exception of the Redundant Reactivity Control System _(RRCS) inputs which are electrically isolated at
. the RRCS panels.
1
Separated ducts are provided in the panel for the incering circuit wires frcm
_ tne sensors that belong to UPS Bus I cr Bus 2.
As shown in Figure 3, the isolation / separation precludes the propacation fro:
outside the tiMS cabinets of failures that coulo cause the loss of any safety function.
liMS/PRMS Interface to RP5 Althouch the LPPJi sensors are not recuired to ceet Class 1E recuirecents, the design bases of the APFJis specify that the LPPJi signals used for the APFJ!s be so selected, powered, and routed that the APPJis do ceet applicable safety
~
criteria. The LPRM signal conditioners and associated power supplies are isolated and separated into groups.
The logic circuitry for the lim 5 and PFJ45 scra:n trip signals conforcs to the single-failure criteria. The contact configurations and failure consequences associated with IRM A (see Figure 4) and APPJi A (see Figure 5) are typical of
- the other trip channels and are described in what follows.
- With the reactor scram mode switch in the " Shutdown," " Refuel," or "Startup" positions, IRM A upscale or inoperating signals (unless bypassed) or APRM A upscale or inoperative signals (unless bypassed) would produce a channel trip of the output relay.
- With the reactor system code switch in the "Run" position, IRM A upscale '
or inoperative signals (unless bypassed) and an APRM A downstale signal (unless bypassed) or APRM A upscale neutron trip or upscale thermal trip or inoperative signals (unless bypassed) would produce a channel trip of the output relay.
- A trip of the channel output relay for IRM A and APRM A or a trip of the channel output relay for IRM E and APRM E would produce an RPS Al channel trip. In PRMS, the log radiation conitor A would produce an RPS Al channel trip (see Figure 6).
a for Mis, one tripped (urbypassed) channel on the RPS trip system would cause a l
I
,. half scra- If one APPJi bev were to fail in an entripoed condition, the i
remaining bays would be capaele of sending RPS sufficient scra signals to j produce a full scram, even if cne of tnem were bypassed.
As shown in Figures 2 and 7, if one bay of panels H11-P635 or H11-P636 were te fail in an untripped condition, the remaining bays would be capable of sending sufficient RPS signals even if one of the IFR channels were bynassed. The IPJi
- bypass switches can bypass one IRM channel at a tics.
Similarly for PPRS, if one bay were to fail in an untripped condition, the
~
remaining bays would be capable of sending sufficient RPS trip signals to produce a full scrat.
' Common Power Sucoly Justification The fiM5 is supplied with 120-Vac, 60-Hz power from UPS busses 1 & 2. A design change has been authorized for the installation on each bus of redundant
? electrical protection assemblies (EPKs), which will conitor the incoming voltage and frequency.
Any fault in one lim 5 channel could not cause an unsafe failurt in another channel sharing the same low voltage power supply because 10-acp fuses are installed.for wire protection, and the power supplies are designed with i over-voltage and over-current protection circuitry at their output.
The PPRS is supplied with 120-Vac, 60-Hz power from RPS busses A and B. EPAs are already installed on each bus to provide voltage and frequency protection.
Any fault in one PPRS channel could not cause an unsafe failure in another channel sharing the same power supply because 5-a:p fuses are installed for wire protection, and the power supplies are designed with over-voltage and over-current protection circuitry at their output.
l l
l l-
~
Because of'the'fai1-safe HMS/FEMS logic configuration, a loss of one supply would result'in a half scra: signal to RPS. Loss of both supplies would result t
- in'a full scrat.
Common Associated Circuit Interfaces Nonessential (associated) circuits to common information equipment are current limited 'and protected such that their failure cannot jeooardize an adjacent circuit.
Figure 8 provides an example of an associated circuit interface on LPRi card Z11. - At the zera'to-160 mV computer output, the card is protected with q 30-MA ~
fuse. The zero-to-10-V output to the rod block monitor has an additional ^
isolator protection for the card.
~
e
.$ 4
_ m_. .
?
i RPS RPS RPS (AI) (A2) (AI) (A 2) o n o o APRM CH. A APRM CH. C APRM CH.E PANEL
- (lipsBy$j) (Up.SBusj) (Ups BUSi)
Hil-P6c8 -------- ~~~~---- - - - - - - - - ------- - ------
BAYl BAYL BAY 3 BAY 4 BAY 5 APRM CH. F APRM CN.h APRM CH.S .
l (UPSBus1) (ops aus 1) (UPS BUS 1) ' '
j ,
i l' 1 1' 3 (BI) (B2) (B2.) (BI)
RPS RPS RPS FIGURE 1 - APRM Panel Assignment l
A'PS (B1) RPS(A&
a a .-
pp3(g) ppS(Ap) .
4 a I
Lo4. TAD.MCW l.06 TAh koM L OS. RA D. NcM iOGTAD McA1.
PANEL 214yDC BUSB .t24VDC ous A pangc gg4yng gy33 ty4ygg yys A hil-P&35 Hit- PG3G IRM IRM
^
IRM ZRM CN. D CH.H CH.C CH. 4 cH.a cH.F cH. A CH.E'
'. .s l' U U .p .-
R P.s .RPS 3 i ,, ,
si t
' RPS PS 3 (B2) (B2) (A1) 1) RPS RPS RPS RPA
( . .
( g ,) (3 1) (4 (Ap) s '
FIGURE 2 - Radiation Monitoring Panels
~
.; ~ .- .
.J
. . :: . . :~ , .s . ..z-
~- *~%> ~~
- - ?
z *l l...,. ("'.-T.
......~. . _
- .. .s . .
c
,. .~;.'r.
,~
{
j
APRH PENETRATIONS QUAD TR)? CHAyggy gg g- - g _ P608 ~~~~~~~~-l, i qi I l D I .
Dv200 f APRM Iy piy.1
^
y' l CH. F I I
I d! Is I .
I, l
APRM CH.D n B I cw2co i I y DIV. /
FROM LPRM < l
^ * ##' ' - '
' g*tW ll :
SENSCRS l ,
l A
y, APRH CH. B % I sw200 l -
l l APRM CH. A ^ Es l
> b!V I I .. , I I I s
I' AW200 l APRM s c '
i
-s l C#. E "
I y biy 2.
l .
g% l H! I
_______________Is ,
FIGURE 3 - APPJ4/RPS Signal Separation ,
F'i , S
.g ,
.. ). ,
,_ :. ;, r ,' . . - .
% e *
N g ** *,
,. [ . ,- e , * ,
,',-.--,.-,--n ,%
, e e , a i ,
. ,, , ,., -Fr-- %. - - -, -- .-, , - ,- e
4 9 4
I.
ama, em
~
nn IRM C)AE A d , 5__ E_e .
4..K30 I
- 8 s
tinCP3 e.. t el s by- a 8'A55) ::unturset. - 8 4 susPs 54
,I,nlp autgy,sJ,,JJ,,a
"~
FIGURE 4 - IRM Channel A Pape(b
.... w u. a -
- at-, 3a s,- <>
I
) C II 4 5 .
- as . :: co
. msc. ' : , p z
s ,
5 il I . , n e
- st 3 i 6 8' pcp 4 '
. . ....so .
- u 6 w l
~
man T 46 P 4
- en r- vPecum Tm9.
I A
-- ~ '
m
- : mi n ., ,
.-_ . __s, . _y
.s
- -..=-- --.
.'~~#' ' FIGURE 5 - APRM Channel A
. v. . , . .
w, ,. - . - .- -
.. t
.t . .
~s- - ' -
- n. . . ' U.
s jy s'.
. - ~ . . .
.t..',
=
- s. : . .
f y
, \
t 4
..) : .- .
..-f.,,.. .
e ., . .. , ,
4 .1 - .4
,. -.r. ,
,. , , . . ~ . .
.4 .
., . t .
.,p'.~, .
- g. . . *
- ~ ' .".
- 4,,r..-
,y ).,. .
~
~, l cc-1_" IV DC ALIA
- .. 6pt N lOlad
GOR AL M
?. . w -1 ,
3 y , . .
- t e n ,. J . r ,. e, .,.
pcts $ Tadb-Ab y_
.s
.5...
w .,
' 2
.wA.
O .
. i. -
-,3 voet ic, g TE si.CT
.: s (e m W M "'*'
~
i - Ter./t . . ,._~
8"
',3- ,/
.' me-t- Tsi.:s - _ MAdu STEAa4 u uE RADe AT10s4
' f,/
TB&S J TIf1_5 -l . ' Mi-Ung He P TM A gsal,3 P V u A4.
,: .. g3 NM .
8CT3h N3 -
to.w_ _
," , ' " . 4.',
TM ,,., _
4 '., 4. MAILJ d5TEAA4 L IhJ C J '
9(11y.1, 7g.g CC-6 _ H4 RADIATICL) SI
.' s % .uun4.e.usc>. M i.-
g
_ w.
m.; ,,.,-
unsu sTru4 ug
-ll',
3:: L. ,,*'* :* m'4 '*c u= bM?iXetk*e1
. .cy,: fa , , , ,
.,:....,=.
. ..b1
.m
.d :
1* # a +
w9..' . '
$13 .
., in. c 4 Tot.is i.
Il lll
'70
> en oense as
.' ,j gi' . p.
- Tygges AageuAmy sphetT y > ll1 TIESPS (,64JPPL Occ.4) e essa s stT3 v v394 tc4 r im m ino taim nom.oocu (' '
),. -
' .
.: . . . . _ . . _ :_ _ ... . . . _METALt.'f comi __
- ' FIGURE 6 - Log Radiation Monitor Channel A
, S4 4
O e
.# e
. e
+
(
PANM 21HDC PMEA . SUPPLY ### M#'###'
N# 5 BU.S-A :
RPS BUS A HRDC PCMR. SUPPLY PANEL _ f)gy)[ g gy g ypg,y BUS B py_p' ' '-
RPS BUS B -
FIGURE 7 - Radiation Monitoring Panels Power Sources
. t a- e
,,o,-
-- s.. gg ; ; ;
> e y a=
%3 d'
m
=
auto
=
TM u
Wa I i i
am um 'en vwi -- -
rr ' !
an. _. .
w .l .* .
s go, - - - ,
'. e ga 7 _. - __.-
. nn -- ,em g ~%
=
h
, ).. am '
.. w- p .
t >=
_,e -
,s!. -
b e, ~ ~ qu <
n (*? wtE4 e -
H >
s, a,
8
, m . ..
W 8.3 3 to asae
_ 9 %e att Q '
s, *b "w 8 $ I w
.wY n 's%t 9 .
,sa m ,
ra. l 'n =% as Y ' .
' '"** , .. as
. co) = A .m. .
aie
-- .. - u a w.s l'. - e
. ~ . ,
FIGURE 8' - LPRM Circuit Card b
A O
.g O
g e I *
=
=***
,,.{',.L.'.g*,*, -
4 *
, e p,..'
r_ i~ ~ - ,_. , __; - _
L __. _ _ . _. , _ _ . _ , _ _ , _ _