ML20095J040

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Common Sensor Failure Evaluation Rept
ML20095J040
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 08/31/1984
From:
Public Service Enterprise Group
To:
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ML20095H943 List:
References
NUDOCS 8408290160
Download: ML20095J040 (60)
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Text

l' <C COMMON SENSOR FAILURE EVALUATION REPORT .

AUGUST ~1984 PUBLIC SERVICE ELECTRIC AND GAS COMPANY HOPE CREEK GENERATING STATION e

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t, :a, C0Pfl0N SENSOR FAILURE EVALUATION REPORT PUBLIC SERVICE ELECTRIC AND GAS COMPANY NOPE CREEK GENERATING STATION 1.0 PURPOSE The purpose of this report . is to provide an analysis to confirm the consequences of the Chapter 15 events analyses of the Hope Creek Generating Station (HCGS) Final Safety Analysis Report (FSAR) bound any occurrence that could result from the failure of a single common instrument line. This report . addresses that part of FSAR Ques-

' tion 421.51 that deals with common secsing line failures.

.A. Definition

1. A common instrument line is defined as a line having two or more sensors, each of which belongs to a different system, or a line having one or more sensors, one of which sends signals.to two different control systems. For instance, one sensor could-belong to the Feedwater Control System, another to the Nuclear Boiler Process Instrumentation System. Instrument lines which serve only one control system and did not qualify under this criterion or that which follows were eliminated because their failure effects are bounded by the current FSAR Chapter 15 analysis.
2. A line is also analyzed when it is not directly covered by definition 1.A.1 but still serves as a variable or reference leg for a differential pressure or level transmitter (s), when the other leg is a common instrument line.

2.0 CONCLUSION

S This report, which supplements the existing HCGS FSAR Chapter 15 transient analyses, documents an evaluation of the HCGS for common sensor failures. No new transients have been identified as a result of this study and all the analyzed consequences of common instrument line failures are bounded by the existing HCGS FSAR Chapter 15 analyses.

3.0 ANALYSIS METHODOLOGY

! A comprehensive approach was developed to analyze control systems j that may affect the reactor pressure vessel (RPV) parameters of water

! level, pressure or power. This report is a part of the total effort l to resolve' Question 421.51 and has analyzed the list' of applicable i

control systems listed in Section 3.1 and identified all instrument

! sensing lines and sensors as defined in the definition above.

! The common sensors failure analysis was conducted in the following manner:

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ACTIVITY SECTION

  • Identify Common Sensors 3.1
  • Determine Failure Modes 3.2
  • Tabulate Common Sensor Failures 3.3 & ,

Appendix A,B l

  • Analyze Combined Effects 3.4 & 4.0
  • Compare Results to Chapter 15 3.5 & 4.0 '
  • Evaluate an Additional Single 3.7 Failure in a Mitigating Safety System
  • Modify / Augment Chapter 15, if 3.8 Necessary 3.1 IDENTIFY COMMON SENSORS The elimination criteria (Appendix C) were applied to a complete list of systems as elaborated in Appendix D.

The following systems were then examined to determine whether they contained common sensor lines and sensors:

System Designation System Generator System Generator Excitation System Generator Gas Control System Main Turbine System B21 Jet Pump Instrumentation System B21/M25 Plant Leak Detection System B21/M42 Nuclear Boiler Vessel Instrumentation System B31/M43 Reactor Recirculation System C11 CRD Hydraulic System C11 Reactor Manual Control System C32 Feedwater Control System CSI Neutron Monitoring Systems G33 Reactor Water Cleanup System M1 Main Steam System M2 Extraction Steam System M3/M4 Heater, Vent and Drains System M5 Condensate System M6 Feedwater System M8 Condensate Refueling Water Storage and Transfer System 11-1178 (2)

,s., -O, System Designation. System M9 Circulating Water System M10 Service Water System t M11 Safety Auxiliaries Cooling, Reactor Building M12- Safety Auxiliaries Colling, Auxiliary Building M13 Reactor Auxiliaries Cooling System M14 Auxiliaries Turbine Cooling Systems MIS Compressed Air System M16 Condensate Demineralizer System M19 Lube Oil System M24 Circulation and Service Water Hypochlorination and CW Acid Injection M26 Radiological Monitoring System M28 Generator Gas Control System M29 Turbine Sealing Steam System M31 Reactor Feed Pump Turbine Steam System M57 Containment Atmosphere Control System M59 Primary Containment Instrument Gas System M69/70 Gaseous Radwaste System M71 Liquid Nitrogen for Purge and Containment Inerting M82 Turbine Bldg. Supply and Exhaust Vent System M83/M84 Reactor Bldg. Supply and Exhaust Vent System M86 Drywell Vent Control System M87 Chilled Water System M89 Auxiliary Bldg. - Control Area Vent Control System M90 Auxiliary Bldg - Control Area Chilled Water System 3.2 DETERMINE FAILURE MODES The bounding failures for an instrument line were designated as an instantaneous break (guillotine) or a complete plug in a line during normal, full power operating conditions.

A broken line to a pressure transmitter would result in a sensed low pressure reading (close to atmospheric). A broken reference line to a differential pressure transmitter used as a water level sensor would result in an indicated high water level (reduced differential pres-sure). A broken " variable leg" line would result in an indicated low water level (increased differential pressure).

Plugged lines are conservatively considered to be 100% plugged or pinched, causing sensors to be inaccurate under changing pressure conditions. In the case of differential pressure transmitters used to sense water level changes, a plugged reference or variable line 11-1178 (3)

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would results in\a more complex response than that which would result from al broken line, as described in the following paragraph.

f Pressaire fluctuations of about 9 psi (14.5 psi) have been measured in operating reactors under normal full power operation. These pressure variations are sensed on both the variable and reference sides of the differential-piessure instruments that sense water level, and do not affect the water level reading. In the dvent of a plugged line, the change in pressure is sensed on only one# side of the differential pressure diaphragm. The response of the instrument will depend upon.

when the, line is assumed to.have been plug,'ged in the pressure fluctu-ation . cycle, since the response willtbe different if the plug occurs atthemaximumorminimumpointonefepressurefluctuationcurve. A pressure variation of 9 psi translates into a sensed water level change of about 21 feet. In analyzing po,ssi,ble instrument responses, the plugging of the instrument line was pastplated at the maximum and minimum points on the pressure variation < curve. Assuming the extreme conditions, a plugged reference leg could result in the instrument indicating a low water level and actuating all applicable low water level trips when the level bra in fact' remained constant. A plugged variable leg could result in the instrument indicating a high water level and actuating . all ihigh ; vater level trips when the level has remained coastant.. The instrument responses are listed in Appendix A under the column labeled SECOVDARY EFFECT.

/

The PRIMARY EFFECT is the 'ef fect a broken or plugged line has on the specific sensor being analyacdr the sensed pressure or differential pressure signal goes to a ma'ximum or minimum value or remains at a constant (inaccurate) reading in thecase of a broken line. In the case of plugged lines, a range of responses is possible.

The SECONDARY EFFECT is the.effect of sensing an incorrect pressure or water level on trips,( permissives, in:erlocks and scram signals.

These may be inappropriately ' actuate'd or rendered inoperative /inhi-bited for the particular instrument being evaluated.

The last column of Appendix,A and Appendix B lists the effect of the incorrectly sensed pressure , or water level upon RPV water level, pressure or power.

The combined effect of the ' interaction of all of the sensors on one line if that line were broken or plugged is listed in Section 4.0.

\

3.3 TABULATE COMMON SENSCR FAILURES Common Sensor Failures for given instrument lines are described in Appendix A tables. Described in the tables are: (1) system identi-fication, (2) the common sensors, (3) failure type, (4) the primary effect of either a broken or plugged line upon that sensor, (5) the l secondary effect on systems' instrumentation and logic, and (6) the

! effect on RPV water level, pressure, or power due to an erroneous l signal from an instrument.

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1 3.4 ANALYZE COMBINED EFFECTS l

This' step combined all of the individual effects for each instrument '

on a given line. The interaction of each effect relative to the other was evaluated; the combined effect consequences, if any, were ,

determined. The results are described for each line in Section 4.0, I

" Common Sensor Summary Results and Chapter 15 Comparison."

3.5 COMPARE RESULTS TO CHAPTER 15 The combined effects, as discussed in Section 4.0, were compared to

!- the consequences of existing FSAR Chapter 15 analyses to determine if any new transient was possible with consequences not bounded by those of the existing analyses.

3.6 ANALYZE ADDITIONAL TRANSIENTS l

l No additional transients were identified.

l 3.7 EV_ALUATE AN ADDITIONAL SINGLE FAILURE IN A MITIGATING SAFETY SYSTEM The consequences of the postulated - common instrument line plug or break events, detailed in Section 4, are all bounded by the conse-quences of FSAR Chapter 15 transients. For each bounded instrument i line plug or break event the mitigating safety systems were identi-fied according to the FSAR Chapter 15 event description. One addi-d tional worst case single failure in a mitigating safety system was 4 then postulated for each event taking into consideration the effects l of the instrument line plus or break. No event was identified j wherein an additional single failure in a mitigating safety system would cause the failure of that system to perform its intended safety '

l function.

j As an example of this process, consider a break in instrument line

  1. 1 from Section 4.0.

i

. The Chapter 15 bounding event is the Loss of Feedwater Flow, described in HCGS FSAR 15.2.7. The event scenario includes a vessel

} low water level (L3) scram trip from the Reactor Protection System j (RPS), which performs a mitigating function. The break in instrument

line #1 together with an additional single failure in the RPS was postulated. The RPS would not be prohibited from inserting the i

control rods and thereby mitigating the effects of the transient.

l This process was followed for each mitigating safety system identi-fled for the Loss of Feedwater Flow event. Each mitigating safety system in the Loss of Feedwater Flow event scenario was able to perform its intended safety function, even considering an additional single failure. -

The above process was repeated for each identified bounding FSAR Chapter 15 event.

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3.8 MODIFY / AUGMENT CHAPTFR 15 IF NECESSARY 4 This step was not necessary in the Hope Creek' Generating Station analysis._

4.0 -COMMON SENSCR

SUMMARY

RESULTS AND CHAPTER 15 COMPARISONS ',

INSTRUMENT LINE; LINE FAILURE CONSEQUENCES (Refer to Appendix A) -

  1. 1 A break in 'this line would cause a reduction in fsedwater flow, lowered reactor vessel water
  • . level and possible reactor scram. At worst, this will be 5cunded by the Loss of reedwater Flow .

event, (FSAR 15.2.7).

A plugged line could possiblyt cause a level 2 RRCS Division 2 init.iation, resulting in reactor scram (recire pump trip, initiatica of ARI, actuation of the time delay for SLCS). This c' transient isx accounted for in the reactor duty cycles estimation.

  1. 2 None
  1. 3 A break in this line would cause an. increase in feedwater flow resulting in a high water level in the reactor vessel, resulting in reactor scram.

At worst, this w'.ll be bounded by .a Feedwater

~

Control Failure ' Maximum Demand event (FSAR 15.1.2) .

There would be, no combined ' effects on RPV level, pressure or power due to a plugged lire.

(

  1. 4&5 None '

., <5 A 15reak in this line would cause a level 2 RRCS Division 2 initiation, resulting in reactor scram, (recirc pump trip, initiate ARI, actuate time delay for SLCS). This transient is ac-counted for in the reactor duty cycles estima-tion.

l ]

l There would be no combined effects. on RPV water level, pressure or power due to a plugged line..

  1. 7 -

None l l

  1. 8 Eliminated, since none of the instruments on this line perform any control function.

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s.

  1. 9,10&11 None
  1. 12 A break in this line would cause a reduction in feedwater flow, lowered reactor vessel water level and possible reactor scram. At worst this will be bounded by the Loss of Feedwater Flow event (FSAR 15.2.7). A plugged line could possibly_ cause a Level 2 RRCS Division 1 initia-tion, would result in reactor scram (recirc pump trip, initiate ARI actuation of time delay for SLCS). This transient is accounted. for in the reactor duty cycles estimation.
  1. 13 None

. #14 A break in this line would cause an increase in feedwater flow resulting in a high water level in the reactor vessel, causing a reactor scram. At worst, this will be bounded by the Feedwater Controller Failure Maximum Demand event (FSAR 15.1.2.).

, A plugged line would have no effect on RPV.

  1. 15&l6 None
  1. 17 A break in this line would cause a level 2 RRCS Division 1 initiation, resulting in reactor

, scram, (recire pump trip, ARI, actuation time l delay for SLCS). This transient is accounted for a in the reactor duty cycles estimation.

i A plugged line has no effect upon RPV level, pressure or power.

  1. 18&l9 None
  1. 20 Line 20 was deleted since none of the instruments on it perform a control function. ,
  1. 21,22&23 None
  1. 24,25,26&27 A break or a plug in any one of these lines would i

result in minor fluctuations in the reactor vessel water level. These would be corrected by the feedwater controller, when in automatic control, or by the operator, when in manual control.

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  1. 28,29,30&31 A break in any one of these lines would cause an MSIV closure,-as defined in FSAR 15.2.4.

A plugged line would have no effect on RPV water level, pressure or power.

  1. 32,33 None -
  1. 34 A break in this line would cause turbine and generator trip discussed in Chapters 15.2.2 and 15.2.3 of the FSAR.

A plugged line would have no effect on RPV water level, pressure or power.

  1. 35 None
  1. 36 A plugged or broken line has no effect on RPV water level, pressure or power.
  1. 37 A broken line would cause the rer.ctor feed pumps to be tripped, resulting in a Loss of Feedwater Flow. This event is bounded by the Loss of Feedwater Flow event (FSAR 15.2.7).

A plugged line would have no effect on RPV water level, pressure or power.

  1. 38 None
  1. 39 A broken line would result in a slight increase in reactor water level or pressure.

A plugged line would have no effect on RPV water level, pressure or power.

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APPENDIX A HOPE CREEK COMMON SENSOR FAILURE FAILURE TYPE COMMON TAP (BROKEN OR EFFECT ON RPV WATER IIVEL, SYSTEM ID SENSOR MPL PLUCCED) PRIMARY EFFECT SECONDARY EFFECT PRESSURE OR POWER NUCLEAR BOILER B21-N0908 BROKEN MINIMUM PRESSURE SIGNAL IDW VESSEL PRESSURE PERMISSIVE SIGNAL NONE AND FOR CS (B) PRESSURE INTERIDCK VALVE TO B21-NOSOF OPEN DIVISION 2.

PLUGCED CONSTANT PRESSURE SIGNAL LOW VESSEL PRESSURE PERMISSIVE SIGNAL NONE '

FOR CS (B) PRESSURE INTERIDCK VALVE TO OPEN DIVISION 2 INOPERATIVE.

NUCLEAR BOILER B21-N090K BROKEN MINIMUM PRESSURE SIGNAL IDW VESSEL PRESSURE PERMISSIVE SIGNAL NONE AND FOR CS (B) PRESSURE INTERLOCK VALVE TO B21-N090P OPEN DIVISION 2.

PLUGGED CONSTANT PRESSURE SIGNAL IDW VESSEL PRESSURE PERMISSIVE SIGNAL NONE FOR CS (B) PRESSURE INTERIDCK VALVE TO OPEN DIVISION 2 INOPERATIVE.

NUCLEAR BOILER B21-N403B BROKEN MINIMUM FRESSURE SIGNAL RRCS DIVISION 2 PRESSURE INITIATION NONE AND INOPERATIVE (RECIRC IDIP TRIP, ARI, B21-N403F PLUGGED CONSTANF PRESSURE SIGNAL FEEDWATER RUMBACK, ACTUATE TIME DELAY FOR SLCS, AND RWCS ISOLATION). DIVI-SION 1 AVAIIABLE.

NUCLEAR BOILER B21-N0858 BROKEN MAXIMUM UIFFERENTIAL RECORDER R610 INDICATES HIGH WATER NOME PRESSURE SIGNAL (HIGH LEVEL.

WATER LEVEL)

PLUGGED INACCURATE DIFFERENTIAL RECORDER R610 INDICATES INACCURATE NONE PRESSURE SIGNAL WATER IIVEL.

NUCLEAR BOILER B21-N402B BROKEN MAXIMUM DIFFERENTIAL RRCS DIVISION 2 LEVEL INITIATION NONE AND PRESSURE (HIGH WATER INOPERATIVE (RECIRC PUMP TRIP, ARI, B21-N402F LEVEL) ACTUATE TIME DELAY FOR SLCS, RWCS ISOIATE) . DIVISION ! AVAILABLE.

PLUGGED INACCURATE DIFFERENTIAL POSSIBLE WATER LEVEL 2 RRCS DIVISION 2 REACTOR SCRAM PRESSURE SIGNAL (POSSIBLE INITIATION (RECIRC PUMP TRIP, INITIATE LOW ATER LEVEL SIGNAL) ARI, ACTUATE TIME DELAY FOR SLCS AND RWCS ISOLATION).

INSTRUMENT LINE I PAGE I 0F 3 LINE I (N12, 160*) REFERENCE LINE 12-197524 (A-1)

l APPENDIX A HOPE CREEK ColeION SENSOR FAILURE l

FAILURE TYPE ColeION TAP (BROKEN OR EFFECT ON RPV WATER LEVEL, t

-SYSTEM ID SENSOR MPL PLUGGED) PRIMARY EFFECT SECONDARY EFFECT PRESSINtE OR POWER NUCLEAR BOILER 821-N0808 BROKEN MAXIMUM DIFFERENTIAL WATER LEVEL 3 SCRAM AND ISotATION NONE PRESSURE SIGNAL (HIGH WATER SIGNAL. CHANNEL B INOPERATIVE.

IIVEL)

PLUGGED INACCURATE DIFFERENTIAL POSSIB M WATER LEVEL 3 SCRAM AND NONE l PRESSURE SIGNAL (POSSIBLE ISOLATION SIGNAL CHANNEL B.

IhW WATER LEVEL SIGNAL)

NUCLEAR BOILER B21-N081B BROKEN MAXIMUM DIFFERENTIAL HALF OF WATER IIVEL 1 MSIV ISOLATION NONE PRESSURE SIGNAL (HIGH WATER INOPERATIVE. HALF OF WATER LEVEL 2 LEVEL) ISOLATION SIGNAL INOPERATIVE.

PLUGGED INACCURATE DIFFERENTIAL POSSIBLE WATER LEVEL I MSIV ISOIATION NONE PRESSURE SIGNAL (POSSIBLE AND WATER LEVEL 2 ISOLATION CHANNEL B.

IDW WATER LEVEL SIGNAL)

! NUCLEAR BOILER B21-N091B BROKEN MAXIMUM DIFFERENTIAL RHR B, CS B, AND PARTIAL ADS INITIA- NONE AND PRESSURE SIG.JAL (HIGH WATER TION INOPERATIVE. DIVISION 2 RCIC B21-N091F LEVEL) INITIATION INOPERATIVE. RALF RCIC HIGH WATER LEVEL TURBINE TRIP.

PLUGGED INACCURATE DIFFERENTIAL POSSIBLE RNR B, CS B, AND PARTIAL ADS NONE PRESSURE SIGNAL (POSSIBLE INITIATION. DIVISION 2 RCIC IDW WATER LEVEL SIGNAL) INITIATION. POSSIBLE START OF EMERGENCY DIESEL GENERATORS.

NUCLEAR BOILER B21-N0958 BROKEN MAXIPRBI DIFFERENTIAL PARTIAL

  • ADS WATER LEVEL 3 INITIATION NONE PRESSURE SIGNAL (HIGH WATER SIGNAL DIVISION 2 INOPERATIVE.

LEVEL)

PLUGGED INACCURATE DIFFERENTIAL PARTIAL ADS WATER LEVEL 3 INITIATION NONE PRESSURE SIGNAL (POSSIBLE SIGNAL DIVISION 2.

IDW WATER LEVEL SIGNAL)

OA PARTIAL INITIATION MEANS THAT SOME OF THE INPITTS NEEDED TO ACTUATE A PARTICUIAR SYSTEM ARE PRESENT, BUT FURTHER INPUTS ARE STILL NECESLARY BEFORE THE SYSTEM FUNCTION IS INITIATED. A SYSTEM BEING PARTIALLY INOPERATIVE REFERS TO A CONDITION WHEREIN CERTAIN INPUTS TO A PARTICULAR DIVISION WILL NOT BE AVAILABLE TO INITIATE THAT DIVISION, Btrf ANOTHER FULLY OPERATIONAL DIVISION IS STILL AVAILABLE TO INITIATE THE SYSTEM.

INSTRUMENT LINE I j PAGE 2 OF 3 LINE I (N12, 160') REFERENCE LINE 12-19752 e (A-2) k

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APPENDIX A HOPE CREEK COPMON SENSOR FAILURE FAILURE TYPE COPMOM TAP (BROKEN OR EFFECT ON RPV WATER LEVEL, SYSTEM ID SENSOR MTL PLUCCED) PRIMARY EFFECT SECONDARY EFFECT PRESSERE OR POWER FEEDWATER C32-N004P BROKEN MAXIMUM DIFFERENTIAL C32-R606B WATER LEVEL INDICATOR HIGH CONTINUED CONTROL ON CHANNEL R WOULD CONTROL PRESSURE SIGNAL (HIGH WATER READING. DECREASED FEEDWATER FIDW. RESULT IN IAWERED VESSEL WATER LEVEL, LEVEL) HALF MAIN TURBINE TRIP AND RFPT TRIP POSSIBIZ SCRAM.

ON HIGH WATER LEVEL. ANNUNCIATOR ALARM IN CONTROL ROOM.

PLUGGED INACCURATE DIFFERENTIAL C32-R606B WATER LEVEL RECORDER AT FLUCTUATION IN REACTOR WATER LEVEL.

PRESSURE SIGNAL (WATER INACCURATE READING. ANNUNCIATOR LEVEL) WILL AIARM IN CONTROL ROOM.

NUCLEAR BOILER B21-N0788 BROKEN MINIMUM PRESSUkE SIGNAL HIGH RPV PRESSURE SCRAM SIGNAL ON NONE ONE CHANNEL DISABLED.

PLUGGED CONSTANT PRESSURE SIGNAL HIGH RPV PRESSURE SCRAM SIGNAL ON NONE ONE CHANNEL DISABLED.

1 INSTRUMENT LINE I PAGE 3 0F 3 LINE I (N12, 160*) REFERENCE LINE 12-197528 (A-3)

APPENDIX A HOPE CREEA 3)MMOW SENSOR FAILURE FAILURE TYPE COPMON TAP (BROKEN OR EFFECT ON RPV WATER LEVEL, SYSTEM ID SENSOR MPL PLUGGED) PRIMARY EFFECT Sr.CONDARY EFFECT PRESSURE Or. POWER NUCLEAR BOILER B21-N097D BROKEN MAXIMUM DIFFERENTIAL DIVISION 4 RCIC TURBINE TRIP SIGNAL. NOME AND PRESSURE SIGNAL (HIGH WATER DIVISION 4 RCIC INITIATION INOPERA-B21-N097H LEVEL) TIVE.

PLUGGED INACCURATE DIFFERENTIAL POSSIBLE LEVEL 2 RCIC INITIATION NONE PRESSURE SIGNAL (POSSIBLE DIVISION 4. RCIC TURBINE TRIP IDW WATER LEVEL SIGNAL) INOPERATIVE.

NUCLEAR BOILER B21-N095D BROKEN MAXIMUM DIFFERENTIAL PARTIAL ADS WATER LEVEL 3 INITIATION NOME PRESSURE SIGNAL (HIGH WATER SIGNAL DIVISION 4 INOPERATIVE.

LEVEL)

PLUGGED INACCURATE DIFFERENTIAL POSSIBLE PARTIAL ADS WATER LEVEL 3 NOFE PRESSURE SIGNAL (POSSIBLE INITIATION, DIVISION 4.

LOW WATER LEVEL)

NUCLEAR BOIER B21-N080D BROKEN MAXIMUM DIFFERENTIAL WATER LEVEL 3 SCRAM AND ISOLATION NONE PRESSURE SIGNAL (HIGH SIGNAL CHANNEL D INOPERATIVE.

WATER LEVEL) a PLUGGED INACCURATE DIFFERENTIAL POSSIBLE INITIATION OF WATER LEVEL 3 NONE PRESSURE SIGNAL (POSSIBLE SCRAM AnD ISOLATION SICNAL CHANNEL D.

LOW WATER LEVEL SIGNAL) .

NUCLFAR SOILER B21-N081D BROKEN MAXIMUM DIFFERENTIAL HALF OF WATER LEVEL I MSIV ISOLATION NONE PRESSURE SIGNAL (HIGH INOPERATIVE. HALF OF WATER LEVEL 2 WATER LEVEL) ISOLATION SIGNAL INOPERATIVE.

PLUGGED INACCURATE DIFFERENTIAL POSSIBLE WATER LEVEL I MSIV ISOLATION NOME PRESSURE SIGNAL (POSSIBLE AND WATER LEVEL 2 ISOLATION CHANNEL D.

IDW WATER LEVEL SIGNAL)

NUCLEAR BOILER B21-N078D BROKEN MINIMUM PRESSURE SIGNAL HIGH RPV PRESSURE SCRAM SIGNAL ON ONE NONE CHANNEL DISABLED.

PLUGGED CONSTANT PRESSURE SIGNAL HIGH RPV PRESSURE SCRAM SIGNAL ON ONE NONE CHANNEL DISABLED.

INSTRUMENT LINE 2 PAGE I 0F 2 LINE 2 (N12, IO*) REFERENCE LINE 13-19752 6 (A-4)

APPENDIX A HOPE CREEK C0t990N SENSOR FAILURE

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FAILURE TiPE C01990N TAP (BROKEN OR EFFECT ON RPV WATER LEVEL, SYSTEM ID SENSOR MPL PLUGCED) PRIMARY EFFECT SECONDARY EFFICT PRESSURE OR POWER NUCLEAR BOILER B21-N091D BROKEN MAXIMUM DIFFEREWTIAL RHR D, CS D, AND PARTIAL ADS INITIA- NONE AND PRESSURE SIGNAL (HIGH WATER TION INOPERATIVE.

B21-N091H LEVEL)

PLUGGED INACCURATE DIFFERENTIAL POSSIBLE RHR D, CS D, AND PARTIAL ADS NONE PRESSURE SIGNAL (POSSIBLE INITIATION.

LOW WATER LEVEL SIGNAL)

INSTRUMENT LINE 2 PACE 2 0F 2 LINE 2 (N12, 10') REFERENCE LINE 12-197524 (g.5)

APPENDIX A HOPE CREEK COPB10N SENSOR FAILURE FAILURE TYPE COMMON TAP (BROKEN OR EFFECT ON RPV WATER LEVEL, SYSTEM ID SENSOR MPL PLUGGED) PRIMART EFFECT SECONDARY EFFECT PRESSURE OR POWER NUCLEAR BOILER B21-N0808 BROKEN MINIMUM DIFFERENTIAL WATER LEVEL 3 SCRAM AND ISOLATION NONE PRESSURE SIGNAL (IDW SIGNAL, CHANNEL B.

WATER LEVEL)

PLUGGED INACCURATE DIFFERENTIAL LEVEL 3 SCRAM AND ISOIATION SIGNAL ON '

NONE PRESSURE SIGNAL (POSSIBLE CHANNEL B INOPERATIVE.

HIGH WATER LEVEL SIGNAL)

NUCLEAR BOILER B21-N0958 BROKEN MINIMUM DIFFERENTIAL PARTIAL ADS WATER LEVEL 3 INITIATION, NONE PRESSURE SIGNAL (LOW DIVISION 2.

WATER LEVEL)

PLUCCED INACCURATE DIFFERENTIAL PARTIAL ADS WATER LEVEL 3 INITIATION NONE PRESSURE SIGNAL (POSSIBLE SIGNAL DIVISION 2 INOPERATIVE.

HIGH WATER LEVEL SIGNAL)

FEEDWATER C32-N004B BROKEN MINIMUM DIFFERENTIAL C32-R606B WATER LEVEL INDICATOR FALSE CONTINUED CONTROL ON CHANNEL B WOULD PRESSURE SIGNAL (LOW WATER LOW READING. INCREASED FEEDWATER RESULT IN HIGH WATER LEVEL IN VESSEL LEVEL) FLOW. ANNUNCIATOR ALARM IN CONTROL POSSIBLE TURBINE TRIP.

ROOM.

PLUGGED INACCURATE DIFFERENTIAL C32-R606B WATER LEVEL INDICAlt)R AT NONE PRESSURE SIGNAL (WATER INACCURATE READING. REACTOR FEEDWATER ERROR IN LEVEL) LEVEL FOLLOWING.

l INSTRUMENT LINE 3 PAGE I- 0F 1 LINE 3 (Nil, 160*) VARIABLE LINE 12-197584 (A-6) n _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

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APPENDIX A HOPE CREEK C0t990N SENSOR FAILURE FAILURE TYPE Coretosi TAP (BROKEN OR EFFECT ON RPV WA1ER LEVEL, l

i SYSTEM ID SENSOR MPL PLUGGED) PRIMARY EFFECT SECONDARY EFFECT PRESSURE OR POWER NUCLEAR BOILER B21-N080D BROKEN MINIMUM DIFFERENTIAL WATER LEVEL 3 SCRAM AND ISOLATION NONE PRESSURE SIGNAL (LOW WATER SIGNAL, CHANNEL D.

LEVEL)

PLUCCED INACCURATE DIFFERENTIAL LEVEL 3 SCRAM AND ISOLATION SIGNAL ON NONE PRESSURE SIGNAL (POSSIBLE CHANNEL D INOPERATIVE.

HIGH WATER LEVEL SIGNAL)

NUCLEAR BOILER B21-N095D BROKEN MINIMUM DIFFERENTIAL PARTIAL ADS WATER IIVEL 3 INITIATION, NONE PRESSURE SIGNAL (LOW WATER DIVISION 4.

LEVEL)

PLUGGED INACCURATE DIFFERENTIAL ADS WATER LEVEL 3 INITIATION SIGNAL NONE PRESSURE SIGNAL (POSSIBLE INOPERATIVE, DIVISION 4.

HIGH WATER LEVEL SIGNAL) l l

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W INSTRUMENT LINE 4 PAGE I 0F I LINE 4 (NII, IO*) VARIABLE LINE 12-197524 (4 7)

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APPENDIX A HOPE CREEK C0tef0N SENSOR FAILURE FAILURE TYPE C0teION TAP (BROKEN OR EFFECT ON RPV WATER IIVEL, SYSTEM ID SENSOR MPL PLUGGED) PRIMARY EFFECT SECONDARY EFFECT PRESSURE OR POWER NUCLEAR BOILER B21-N08ID BROKEN MINIMtti DIFFERENTIAL HALF WATER LEVEL I M31V ISOIATION, NONE PRESSURE SIGNAL (thW AND HALF WATER LEVEL 2 ISOLATION WATER LEVEL) SIGNAL.

PLUGGED INACCURATr. DIFFFil.NTIAL HALF WATER LEVEL I hSIV IS01ATION AND NONE PRESSURE SIGNAL (POSSIBLE HALF WATER LEVEL 2 ISOIATION SIGNAL HIGH WATER IIVEL SIGN 4L) INOPERATIVE.

NUCLEAR BOILER B21-N091D BROKEN MINIMUM DIFFERENTIAL RHR D, CS D, AND PARTIAL ADS NONE AND PRESSURE SIGNAL (LOW WATER INITIATION.

B21-N091H LEVEL)

PLUGGED INACCURATE DIFFERENTIAL RHR D, CS D, AND PARTIAL ADS INITIA- NONE PRESSURE SIGNAL (POSSIBLE TION INOPERATIVE.

HIGH WATER LEVEL SIGNAL) 2."JCLEAR BOILER B21-N097D BROKEN MINIMUM DIFFERENTIAL LEVEL 2 RCIC INITIATION DIVISION 4, NONE AND PRESSURE SIGNAL (LOW WATER RCIC TURBINE TRIP INOPERATIVE.

B21-N097H LEVEL)

PLUGGED INACCURATE DIFFERENTIAL POSSIBLE DIVISION 4 RCIC TURBINE TRIP NONE PRESSURE SIGNAL (POSSIBLE SIGNAL, DIVISION 4 RCIC INITIAITON HIGH WATER LEVEL SIGNAL) INOPERATIVE.

4 INSTRUMENT LINE 5 PAGE I 0F I LINE 5 (N16, 10') VARIABLE LINE 13-197524 (A-8)

APPENDIX A HOPE CREEK COMMON SENSOR FAILURE FAILURE TYPE COMMON TAP (BROKEN OR EFFECT ON RPV WATER LEVEL, SYSTEM ID SENSOR MPL PLUGGED) PRIMART EFFECT SECONDARY EFFECT PRESSURE OR POWER NUCLEAR BOILER B21-N402B BROKEN MINIMUM DIFFERENTIAL WATER LEVEL 2 RRCS DIVISION 2 INITIA- REACTOR SCRAM.

AND PRESSURE SIGNAL (IDW WATER TION (RECIRC PLMP TRIP, INITIATE ARI, B21-N402F LEVEL) ACTUATE TIME DELAY FOR SLCS, AND RWCS ISOLATION).

PLUGGED INACCURATE DIFFERENTIAL RRCS DIVISION 2 IIVEL TRIP INOPERATIVE NONE PRESSURE SIGNAL (POSSIBLE (RECIRC PUMP TRIP, ARI, S'.CS, AND RWCS HIGH WATER LEVEL SIGNAL) ISOLATE). DIVISION 1 AVAILABLE.

NUCLEAR BOILER B21-N081B BROKEN MINIMUM DIFFERENTIAL HALF WATER LEVEL I MSIV ISOLATION, NONE PRESSURE SIGNAL (IDW HALF WATER LEVEL 2 ISOLATION SIGNAL.

WATER LEVEL)

PLUGCED INACCURATE DIFFERENTIAL HALF WATFR LEVEL 1 MSIV ISOLATION, NONE PRESSURE SIGNAL (POSSIBLE AND HALF WATER LEVEL 2 ISOLATION HIGH WATER LEVEL SIGNAL) SIGNAL INOPERATIVE.

NUCLEAR BOILER B21-N091B BROKEN MINIMUM DIFFERENTIAL RNR (B) CS/(B) INITIATION, DIVISION 2 NONE AND PRESSURE SIGNAL (LOW RCIC LOW WATER LEVEL INITIATION.

B21-N091F WATER LEVEL) DIVISION 2 RCIC HIGH WATER LEVEL TURBINE TRIP INOPERATIVE. PARTIAL ADS

  • INITIATION.

PLUGGED INACCURATE DIFFERENTIAL RHR (B) CS/(B) HALF RCIC, AND PARTIAL NONE PRESSURE SIGNAL (POSSIBLE ADS INITIATION INOPERATIVE. HALF HIGH WATER LEVEL SIGNAL) RCIC HIGH WATER LEVEL TURBINE TRIP.

INSTRUMENT LINE 6 PAGE I 0F 1 LINE 6 (N16, 160') VARIABLE LINE 12-197524 (3 9)

J

A' APPENDIX A HOPE CREEK C0tet0N SENSOR FAILURE FAILURE TYPE COPMON TAP (BROKEN OR EFFECT ON RPV WATER LEVEL, SYSTEM ID SENSOR MPL PLUGGED) PRIMARY EFFECT SECONDARY EFFECT PRESSURE OR POWER JET PUMP B21-NO348 BROKEN NO EFFECT; USE FOR NONE NONE INSTRUMENTATION INDICATION ONLY PLUGGED NO EFFECT UPON CONTROL NONE NONE SYSTEMS; USE FOR INDICATION ONLY NUCLEAR BOILER B21-N0858 BROKEN MINIMUM DIFFERENTIAL RECORDER R610 INDICATES INACCURATE NONE PRESSURE SIGNAL (LOW WATER WATER LEVEL.

LEVEL)

PLUGGED INACCURATE DIFFERENTIAL RECORDER R610 INDICATES INACCURATE NONE PRESSURE SIGNAL WATER LEVEL.

INSTRUMENT LINE 7 PAGE 1 0F 1 LINE 7 (N8, 105*) VARIABLE LINE 12-197524 (A-10)

APPENDIX A HOPE CREEK Core 10N SENSOR TAILUNE

. FAILURE TYPE .

C0t910N TAP (BROKEN OR EFFECT ON RPV WATER LEVEL, SYSTEM ID SENSOR HPL PLUCCED) PRIMARY EFFECT SECONGARY EFFECT PRESSURE OR POWER REACTOR C71-N050B BROKEN MINIMUM PRESSURE SIGNAL ONE CHANNEL FOR SCRAM ON HIGH DR M LL NONE-PROTECTION PRESSURE INOPERATIVE. HIGH DRYWELL PRESSUk; ISOLATION CIASURE OF BAIANCE OF PIANT ISOIATION VALVES INOPERATIVE.

PLUGGED CONSTANT PRESSURE SIGNAL ONE CHANNEL FOR SCRAM ON MIGH DR M LL NONE PRESSURE INOPERATIVE. HIGH DRYWELL PRESSURE ISOIATION CLOSURE OF BAIANCE OF PLANT ISOLATION VALVES INOPERATIVE.

NUCLEAR BOILER B2I-N0948 BROKEN MINIMUM PRESSURE SIGNAL ' HALF HIGH DRYWELL PRESSURE SIGNAL NONE AND INOPERATIVE. CORE SPRAY PUMP B AUTO B21-N094F INITIATION INOPERATIVE. "B" TRIP TO ADS SAFETY RELIEF VALVES B2I-FOI3A THROUGH -F0I3E INOPERATIVE. CIASURE OF ESI-F062 TURBINE EXHAUST LINE ISOLATION OUTBOARD VALVE ON HIGH DR M LL PRESSURE LOW STEAM LINE PRES-SURE INOPERATIVE. RHR R INITIATION ON HIGH DRYWELL PRESSURE INOPERATIVE.

PLUGGED CONSTANT PRESSURE SIGNAL RHR R INITIATION ON HIGH DRYWELL NOME PRESSURE INOPERATIVE.

INSTRUMENT LINE 9 PAGE 1 0F I LINE 9 (CONTAINMElrf PENETRATION J7A) 13-197524 (A-II)

?

APPENDIX A

  • HOPE CREF'" COMMON SENSOR FAILURE FAILURE TYPE CorMON TAP (BROKEN OR EFFECT ON RPV WATER IIVEL, SYSTEM ID SENSOR HPL PLUGGED) PRIMARY EFFECT SECONDARY EFFECT PRESSt5tE OR POWER NUCLEAR BOILER B21-N094D BROKEN MINIMUM PRESSURE SIGNAL HALF HIGH DRYWELL PRESSURE SIGNAL NOME AND INOPERATIVE. CORE SPRAY PtMP D AtrTO B21-N094H INITIATION INOPERATIVE. "D" TRIP To ADS SAFETY RELIEF VALVES B21-F013A THROUGH -F013E INOPERATIVE. CLOSURE OF E51-F084 TURBINE EXHAUST LINE ISOLATION INBOARD VALVE ON MIGH DRYWELL PRESSURE LDW STEAM LINE PRES-SURE INOPERATIVE. RHR D INITIATION ON HIGH DRYWELL PRESSURE INOPERATIVE.

PLUGGED CONSTANT PRESSURE SIGNAL HALF HIGH DRYWELL PRESSURE SIGNAL NONE-INOPERATIVE. CORE SPRAY PtMP D AUTO INITIATION INOPERATIVE. "D" TRIP TO ADS SAFETY RELIEF VALVES B21-F013A THROUGH -F013E INOPERATIVE. CIDSURE OF E51-F084 TURBINE EXHAUST LINE ISOLATION INBOARD VALVE ON HIGH i DRYWELL PRESSURE IDW STEAM LINE PRES-

! SURE INOPERATIVE. RNR D INITIATION ON HIGH DRYWELL PRESSURE INOPERATIVE.

REACTOR C71-N0508 BROKEN MINIMUM PRESSURE SIGNAL ONE CHANNEL FOR SCRAM ON HIGH DRYWELL NONE PROTECTION PRESSURE INOPERATIVE. HIGH DRYWELL i PRESSURE CIhSURE OF EII-F040 RNR DISH TO RADWASTE OUTBOARD ISOLATION VALVE ,

AND EII-F080A&R RHR SAMPLE LINE ISOIA-TION VALVES INOPERATIVE. HIGH DRYWELL

! PRESSURE CLOSURE TO BALANCE OF plt.NT

, IS01ATION VALVES INOPERATIVE.

PLUGGED CONSTANT PRESSURE SIGNAL ONE CHANNEL FOR SCRAM ON HIGH DRYWELL NONE PRESSURE INOPERATIVE. HIGH DRYWELL PRESSURE CIASURE TO BALANCE OT PLANT ISOLATION VALVES INOPERATIVE.

CONTAINMENT PT-496082 BROKEN MINIMUM PRESSURE SIGNAL NONE, USED FOR INDICATION ONLY. NONE ATMOSPHERE CONTROL

. (M57) PLUGGED CONSTANT PRESSURE SIGNAL NONE, USED FOR INDICATION ONLY. NONE CONTAINMENT PT-496081,B3 BROKEN IDW PRESSURE SIGNAL NONE, USED FOR INDICATION ONLY.e NONE ATMOSPHERE CONTROL (M57) PLUGGED INACCURATE PRESSURE SIGNAL NONE, USED FOR INDICATION ONLY. NONE INSTRUMENT LINE 10 PAGE I 0F 1 LINE 10 (CONTAINMENT PENETRATION J10D) 12-197524 (A-12)

+

APPENDIX A #  :.

HOPE CREEK COMMON SENSOR FAILURE FAILURE TYPE COPMON TAP (BROKEN OR EFFECT ON RPV WATER LEVEL, SYSTEM ID SENSOR MPL PLUCCED) PRIMARY EFFECT SECONDARY EFFECT PRESSURE OR POWER NUCLEAR B21-N027 BROKEN MAXIMtM DIFFERENTIAL R605 SHtrTDOWN WATER IIVEL INDICATOR AT NONE LOILER PRESSURE SIGNAL (HIGH WATER MAXIMUM WATER LEVEL INDICATION.

LEVEL)

PLUGGED INACCURATE DIFFERENTIAL INACCURATE READING. NONE PRESSURE SIGNAL (WATER LEVEL)

FEEDWATER C32-N017 BROKEN MAXIMUM DIFFERENTIAL R608 WIDE RANGE LEVEL RECORDER WILL NONE CONTROL PRESSURE SIGNAL (HIGH WATER INDICATE MAXIMUM WATER LEVEL.

LEVEL)

PLUGGED INACCURATE DIFFERENTIAL INACCURATE READING. NONE PRESSURE SIGNAL (WATER LEVEL)

INSTRUMENT LINE 11 PAGE 1 0F 1 LINE 11 (REFERENCE LINE, CONDENSING CHAMBER D002) 12-197524 (A-13)

APPENDIX A

  • HOPE CREEK COPMON SENSOR FAILURE FAILURE TYPE C0tMON TAP (BROKEN OR EFFECT ON RPV WATER LEVEL, STSTEM ID SENSOR MPL PLUGGED) PRIMARY EFFECT SECONDART EFFECT PRESSURE OR POWER NUCLEAR BOILER B21-N080A BROKEN MAXIffUM DIFFERENTIAL WATER LEVEL 3 SCRAM AND ISOLATION NONE PRESSURE SIGNAL (HICH WATER SIGNAL CHANNEL A INOPERATIVE.

LEVEL)

PLUGCED INACCURATE DIFFERENTIAL POSSIBLE WATER LEVEL 3 SCRAM AND NONE PRESSURL SIGNAL (POSSIBLE ISOLATION SIGNAL CHANNEL A.

LOW WATER LEVEL)

NUCLEAR BOILER B21-N081A BROKEN MAXIMUM DIFFERENTIAL HALF OF WATER LEVEL I MSIV ISOLATION NONE PRESSURE SIGNAL (NIGH WATER INOPERATIVE. HALF OF WATER LEVEL 2 LEVEL) ISOLATION INOPERATIVE.

PLUGGED INACCURATE DIFFERENTIAL POSSIBLE WATER LEVEL 1 MSIV IS01ATION NONE PRESSURE SIGNAL (POSSIBLE AND WATER LEVEL 2 ISOLATION CHANNEL A.

LOW WATER LEVEL SIGNAL)

NUCLEAR BOILER B21-N091A BROKEN MAXIMUM DIFFERENTIAL RHR A, CS A INITIATION INOPERATIVE. NONE AND PRESSURE SIGNAL (POSSIBLE DIVISION 1 HPCI TURBINE TRIP ON HIGN 821-N091E HIGH WATER LEVEL SIGNAL) WATER LEVEL.

PLUGGED INACCURATE DIFFERENTIAL DIVISION I HPCI INITIATION INOPERA- NONE PRESSURE SIGNAL (POSSIBLE TIVE. POSSIBLE RHR A AND CS A IDW WATER LEVEL SIGNAL) INITIATION, DIVISIbN 1 HPCI INITIATION.

INSTRUMENT LINE 12 PAGE I 0F 5 LINE 12 (N12, 190') REFERENCE LINE 12-197584 (A-14)

APPENDIX A i HOPE CREEK C0ttt0N SENSOR FAILURE FAILURE TYPE C0fet0N TAP (BROKEN OR EFFECT ON RPV WATER IIVEL, SYSTEM ID SENSOR MPL PLUGCED) PRIMARY EFFECT SECONDARY EFFECT PRESSURE OR POWER NUCLEAR BOILER B21-N090A BROKEN MINIMUM PRESSURE SIGNAL IDW VESSEL PRESSURE PERMISSIVE SIGNAL NONE AND FOR CS (A) AND RNR (A) INITIATION ON B21-N090E DIVISION 1.

PLUGGED CONSTANT PRESSURE SIGNAL LOW VESSEL PRESSURE PERMISSIVE SIGNAL NONE FOR CS (A) AND RNR (A) INITIATION ON DIVISION I INOPERATIVE.

NUCLEAR BOILER B21-N090J BROKEN MINIMUM PRESSURE SIGNAL LOW VESSEL PRESSURE PERKISSIVE SIGNAL NONE AND FOR CS (A) PRESSURE INTERIDCK VALVE TO B21-N090N OPEN DIVISION 1.

PLUGGED CONSTANT PRESSURE SIGNAL LOW VESSEL PRESSURE PERMISSIVE SIGNAL NONE FOR CS (A) INOPERATIVE. .

INSTRUMENT LINE 12 PAGE 2 OF 5 LINE 12 (NI2, 190*) REFERENCE LINE 12-197524 (A-15)

- ________m

- _ . ~ - . . _ ,

e APPENDIX A HOPE CREEK C0tm0N SENSOR FAILURE FAILURE TYPE COPMON TAP (BROKEN OR EFFECT ON RPV WATER LEVEL,.

SYSTEM ID SENSOR MPL PLUCCED) PRIMARY EFFECT SECONDART EFFECT PitESStRE OR POWER NUCLEAR BOILER B21-N402A BROKEN MAXIMUM DIFFERENTIAL RRCS DIVISION I INOPERATIVE (RECIRC NONE AND PRESSURE SIGNAL (HIGH WATER PUMP TRIP, ARI SLCS, RWCS ISOIATE).

B21-N402E II, VEL) DIVISION 2 AVATIABLE.

PLUGGED INACCURATE DIFFERElfrIAL POSSIBLE WATER LEVEL 2 RRCS DIVISION 1 POSSIBLE REACTOR SCRAM.

PRESSURE SIGNAL (POSSIBLE INITIATION (RECIRC PLMP TRIP, INITIATE LOW WATER LEVEL SIGNAL) ARI, ACTIVATE TIME DELAT FOR SLCS AND

  • RWCS ISOIATION).

NUCLEAR BOILER B21-N403A BROKEN MINIMlM PRESSURE SIGNAL RRCS DIVISION I PRESSURE INITIATION NONE AND TRIP INOPERATIVE (REIRC PUMP TRIP, ARI B21-N403E PLUGCED CONSTANT PRESSURE SIGNAL FEEDWATER RUNBACK SLCS, RWCS ISO-LATE). DIVISION 2 AVAILABLE.

NUCLEAR BOILER B21-N085A BROKEN MAXIMUM DIFFERENTIAL RECORDER R615 INDICATES HIGH WATER NONE PRESSURE SIGNAL (HIGH WATER LEVEL.

LEVEL)

PLUGGED INACCURATE DIFFERENTIAL RECORDER R615 INDICATES INACCURATE NONE PRESSURE SIGNAL WATER LEVEL.

INSTRUMENT l'NE 12 '

PAGE 3 0F 5 LINE 12 (NI2, 190') REFERENCE LINE 13-197524 (A-16)

. _ _ - _ _ _ _ _ _ - _ _ _ _ _ _ - _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ - - _ . _ - . . - - _ . - _ _ - __ ?

o APPENDIX A HOPE CREEK C0tm0N SENSOR FAILURE FAILURE TYPE Carm0N TAP (BROKEN OR EFFECT ON RPV WATER LEVEL, SYSTEM ID SENSOR HPL PLUGGED) PRIMARY EFFECT SECONDARY EFFECT PRESSURE OR POWER FEEDWATER C32-N004A BROKEN MAXIMUM DIFFERENTIAL C32-R606A WATER LEVEL INDICATOR FALSE CONTROL ON CH WNEL A WOULD RESULT IN CONTROL PRESSURE SIGNAL (HIGH WATER HIGH READING. DECREASED FEEDWATER LOWERED VCSSEL WATER LEVEL, POSSIBLE IIVEL) FI4W. HALF MAIN TURBINE AND RFPT TRIP SCRAM.

ON HIGH WATER LEVEL. ANNUNCIATOR ALARM IN CONTROL ROOM. OPERATOR WOULD

-HAVE TO IGNORE ANNUNCIATOR ALARM.

PLUGGED INACCURATE DIFFERENTIAL C32-R606A WATER IIVEL INDICATOR AT CONTINUED CONTROL ON CHANNEL A COULD PRESSURE SIGNAL (WATER INACCURATE READING. REACTOR FEEDWATER RESULT IN RPV WATER LEVEL FLUCTUATION.

LEVEL) ERROR IN LEVEL FOLI4 WING.

NUCLEAR BOILER B21-N078A BROKEN MINIMUM PRESSURE SIGNAL HIGH RPV PRESSURE SCRAM SIGNAL ON ONE NONE CHANNEL DISABLED.

PLUGGED CONSTANT PRESSURE SIGNAL HIGN RPV PRESSURE SCRAM SIGNAL ON ONE NONE CHANNEL DISABLED.

INSTRUMENT LINE 12 PAGE 4 0F 5 LINE 12 (NI2, 190*) REFERENCE LINE 12-19752 e (g.g7)

la APPENDIX A HOPE CREEK Cotm0N SENSOR FAILURE FAILURE TVPE Corm 0N TAP (BROKEN .At EFFECT ON RPV WATER IIVEL.

SYSTEM ID SENSOR MPL PLUGCED) PRIMARY EFFECT SECONDARY EFFECT PRES 3UltE OR poker FEEDWATER C32-NOO8 BROKEN MINIMUM PRESSURE SIGNAL PRESSURE RECORDER R609 WILL INDICATE MONE CONTROL LOW REACTOR PRESSURE.

CONSTANT PRESSURE SIGNAL PRESEURE RECORDER R609 WILL INDICATE .MONE INCORRECT REACTOR VESSEL PRESSURE.

FEEDWATER C32-N005 BROKEN MINIMtM PRESSURE SIGNAL HIGH PRESSIRE ALARM (K636) IN0PERA- NOME CONTROL TIVE, PRESSURE RECORDER (R605) AT HINIMIM PRESSURE. '

PLtMGED CONSTANT PRESSURE SIGNAL HIGH PRESSURE AIJUtM (K636) IN0PERA- NONE TIVE, PRESSURE RECORDER (R605) AT CONSTANT PRESSURE.

l i,

INSTRUMENT LINE 12 PAGE 5 0F 5 LINE 12 (NI2, 190*) REFERENCE LINE 12-197524 (A-18)

t.

APPENDIX A w HOPE CREEK COMMON SENSOR FAILURE FAILURE TYPE COPHOW TAP (BROKEN OR EFFECT ON RPV WATER E VEL, SYSTEM ID SENSOR MPL PLUGGED) PRIMARY EFFECT SECONDARY EFFICT PRESSURE OR POWER NUCLEAR BOILER B21-N081C BROKEN MAXIHLPt DIFFERENTIAL POSSIBLE WATER LEVEL 1 MSIV ISOLATION NONE PRESSURE SIGNAL (HIGH INOPERATIVE, HALF OF WATER LEVEL 2 WATER LEVEL) ISOLATION INOPERATI W..

PLUGGED INACCURATE DIFFERENTIAL POSSIBLE WATER EVEL I MSIV ISOIATION NONE PRESSURE SIGNAL (POSSIBLE AND WATER LEVEL 2 IS01ATION CHANNEL C.

  • IDW WATER LEVEL SIGNAL)

B21-N091C BROKEN MAXIMlff DIFFERNENTIAL RHR C AND CS C INITIATION INOPERATIVE. NONE AND PRESSURE SIGNAL (HICH WATER DIVISION 3 HPCI HIGH WATER LEVEL 821-N091G LEVEL) TURBINE TRIP. DIVISION 3 HPCI INITIATION INOPERATIVE.

PL*JGGED INACCURATE DIFFERENTIAL POSSIBLE RHR C AND CS C INITIATION. NONE PRESSURE SIGNAL (POSSIBLE DIVISION 3 HPCI INITIATION.

LOW WATER EVEL SIGNAL)

FEEDWATER C32-N004C BROKEN MAXIMUM DIFFERENTIAL C32-R606C WATER E VEL INDICATOR FALSE NONr.

CONTROL PRESSURE SIGNAL (HIGH WATER HIGH READING. HALF MAIN TURBINE AND LEVEL) RFFT TRIP ON HIGH WATER LEVEL. ANNUN-CIATOR ALARM IN CONTROL ROOM.

PLUGCED INACCURATE DIFFERENTIAL C33-R606C WATER LEVEL INDICATOR AT WONE PRESSURE SIGNAL (WATER INACCURATE READING.

LEVEL)

NUCLEAR BOILER B21-N080C BROKEN MAXIMitt DIFFERENTIAL WATER LEVEL 3 SCRAM AND ISOLATION NONE PRESSURE SIGNAL (HIGH SIGNAL CHANNEL C INOPERATIVE.

WATER LEVEL)

PLUGGED INACCURATE DIFFERENTIAL POSSIBLE WATER LEVEL 3 SCRAM AND NONE PRESSURE SIGNAL (POSSIBLE ISOLATION SIGNAL CHANNEL C.

LOW WATER LEVEL SIGNAL)

NUCLEAR BOILER B21-N07BC BROKEN MINIMitt PRESSURE SIGNAL HIGH RPV PRESSURE SCRAM SIGNAL ON ONE NONE CHANNEL DISABLED.

PLUGGED CONSTANT PRESSURE SIGNAL HIGH RPV PRESSURE SCRAM SIGNAL ON THE CHANNEL DISABLED.

INSTRUMENT LINE 13 PAGE 1 OF I LINE 13, (N12, 340*) REFERENCE LINE 13-197584 (A-19)

APPENDIX A ,

HOPE CREEK C0tm0N SENSOR FAILURE FAILURE TYPE C0rm0N TAP (BROKEN OR EFFECT ON RPV WATER LEVEL, .

SYSTEM ID SENSOR MPL PLUGGED) PRIMARY EFFECT SECONDARY EFFECT PRESSIRE OR POWER FEEDWATER C32-N017 BROKEN MINIMUM DIFFERENTIAL R608 WIDE RANCE LEVEL RECORDER WILL NONE CONTROL PRESSURE SIGNAL (IDW WATER INDICATE MINIMUM WATER LEVEL.

LEVEL)

PLUGCF.D INACCURATE DIFFERENTIAL R608 WIDE RANGE LEVEL RECORDER WILL NONE PRESSURE SIGNAL (WATER INDICATE INACCURATE WATER LEVEL.

LEVEL)

NUCLEAR BOILER B21-N027 BROKEN MINIHLM DIFFERENTIAL R605 SHUTDOWN WATER LEVEL INDICATOR AT NONE PRESSURE SIGNAL (LOW WATER MINIMUM WATER LEVEL INDICATION.

LEVEL)

PLUGGED INACCURATE DIFFERENTIAL R605 SHITfDOWN WATER LEVEL INDICATOR NONE PRESSURE SIGNAL (POSSIBLE MAT INDICATE HIGH WATER LEVEL.

HIGH WATER LEVEL SJGNAL)

NUCLEAR BOILER B21-N080A BROKEN MINIMiff DIFFERENTIAL WATER LEVEL 3 SCRAM AND IS01ATION NONE PRESSURE SIGNAL (LOW WATER SIGNAL ON CHANNEL A.

LEVEL)

PLUGGED INACCURATE DIFTERENTIAL LEVEL 3 SCRAM AND ISOLATION SIGNAL NONE PRESSURE SIGNAL (POSSIBLE ON CHANNEL A INOPERATIVE.

HIGH WATER LEVEL SIGNAL)

FLEDWATER C32-N004A BROKEN MINIMttl DIFFERENTIAL C32-R606A WATER IIVEL INDICATOR FALSE CONTINUED CONTROL ON CHANNEL A WOULD PRESSURE SIGNAL (IDW WATER LOW READING. INCREASED FiEDWATER RESULT IN HIGH WATER LEVEL IN VESSEL, LEVEL) FLOW. ANNUNCIATOR ALARM IN CONTROL POSSIBLE TURBINE TRIP.

ROOM.

PLUGGED INACCURATE DIFFERE'ITIAL C32-R606A WATER LEVEL INDICATOR AT NONE PRESSURE SIGNAL (WATER INACCURATE READING. REACTOR FEED-LEVEL) WATER ERROR IN LEVEL FOLLOWING.

INSTRtMENT LINE I4 PAGE I OF 1 LINE 14, (NII, 190*) VARIABLE LINE 13-1975 24 (A-20)

APPENDIX A -

HOPE CREEK COMMON SENSOR FAILURE FAILURE TYPE C0t990N TAP (BROKEN OR EFFECT ON RPV WATER IIVEL, SYSTEM ID SENSOR MPL PLUGGED) PRIMART EFFECT SECONDARY EFFECT PRESSURE OR POWER FEEDWATER C32-N004C BROKEN MINIMUM DIFFERENTIAL C32-R606C WATER LEVEI'. INDICATOR FALSE NONE CONTROL PRESSURE SIGNAL (IDW WATER LOW READING. LEVEL SIGNAL FAILURE LEVEL) ANNUNCIATOR ALARM IN CONTROL ROOM.

PLUGCED INACCURATE DIFFERENTIAL C32-R606C WATER LEVEL INDICATOR AT NONE PRESSURE SIGNAL (WATER INACCURATE READING.

LEVEL)

NUCLEAR BOILER B21-N080C BROKEN MINIMUM DIFFERENTIAL WATER LEVEL 3 SCRAM AND ISOIATION NONE PRESSURE SIGNAL (LOW WATER SIGNAL CNANNEL C.

LEVEL)

PLUGGED INACCURATE DIFFERENTIAL LEVEL 3 SCRAM AND ISOLATION SIGNAL ON NONE PRESSURE SIGNAL (POSSIBLE CHANNEL C INOPERATIVE.

HIGH WATER LEVEL SIGNAL)

INSTRUMENT LINE 15 PAGE 1 0F I LINE 15 (Nil, 340') VARIABLE LINE 12-197524 (g.21)

APPENDIX A '.

HOPE CREEK COMMON SENSOR FAILURE FAILURE TYPE Corm 0N TAP (BROKEN OR EFFECT ON RPV WATER LEVEL, ,

SYSTEM ID SENSOR MPL PLUGGED) PRIMARY EFFECT SECONDARY EFFECT PRESSURE OR POWER NUCLEAR BOILER B21-N081C BROKEN MINIMtM DIFFERENTIAL HALF WATER LEVEL I MSIV ISCIATION, NONE PRESSURE SIGNAL (LOW HALF WATER LEVEL 2 ISOLATION SIGNAL.

WATER LEVEL)

PLUGGED INACCURATE DIFFEREKfIAL HALF WATER LEVEL I MSIV ISOLATION AND NONE PRESSURE SIGNAL (POSSIBLE HALF WATER LEVEL 2 ISOIATION SIGNAL -

HIGH WATER LEVEL SIGNAL) INOPERATIVE.

B21-N09IC BROKEN MINIMUM DIFFERENTIAL RHR C AND CS C INITIATION. DIVISION 3 NONE AND PRESSURE SIGNAL (IDW WATER HPCI INITIATION. DIVISION 3 HIGH B21-W091G LEVEL) WATER LEVEL HPCI TURBINE TRIP INOPERATIVE.

PLUGGED INACCURATE DIFFERENTIAL RHR C AND CS C INITIATION INOPERATIVE. NONE

, PRESSURE SIGNAL (POSSIBLE DIVISION 3 HPCI YNITIATION INOPERA-HIGH WATER LEVEL SIGNAL) TIVE. DIVISION 3 HIGH WATER LEVEL HPCI TURBINE TRIP.

I INSTRUMENT LINE 16 PAGE 1 0F 1 LINE 16 (N16, 3408) VARIABLE LINE 13-1975H (A-22)

( '.

APPENDIX A

  • HOPE CREEK Corr 10N SENSOR FAILURE

! FAILURE TYPE COPHON TAP (BROKEN OR EFFECT ON RPV WATER LEVEL, SYSTEM ID SENSOR MPL PLUGGED) PRIMARY EFFECT SECONDARY EFFECT PRESSURE OR POWER NUCLEAR BOILER B21-N402A BROKEN HINIMLM DIFFERENTIAL WATER IIVEL 2 RRCS DIVISION 1 INITIA- REACTOR SCRAM.

AND PRESSURE SIGNAL (LOW WATER TION (RECIRC PLMP TRIP, INITIATE ARI, B21-N402E LEVEL) ACTIVATE TIME DELAT FOR SLCS, AND RWCS-ISOLATION).

PLUGGED INACCURATE DIFFERENTIAL RRCS DIVISION 1 INOPERATIVE (RECIRC NONE PRESSURE SIGNAL (POSSIBLE PUMP TRIP, ARI. SLCS AND RWCS ISO-HIGH WATER LEVEL SIGNAL) IATION). DIVISION 2 AVAILABLE.

NUCLEAR BOILER B21-N081A BROKEN MINIMUM DIFFERENTIAL HALF WATER LEVEL I MSIV ISOLATION, NONE PRESSURE SIGNAL (LOW HALF WATER LEVEL 2 IS0!ATION SIGNAL.

WATER LEVEL)

PLUGGED INACCURATE DIFFERENTIAL HALF WATER LEVEL 1 MSIV ISOIATION, NONE PRESSURE SIGNAL (POSSIBLE AND HALF WATER LEVEL 2 ISOLATION -

HIGH WATER LEVEL SIGNAL) SIGNAL INOPERATIVE.

NUCIIAR BOILER B21-N09tA BROKEN HINIMUM DIFFERENTIAL RHR A AND CS A INITIATION. DIVISION 1 NONE AND PRESSURE SIGNAL (IDW HPCI INITIATION.

821-N091E WATER LEVEL)

PLUGGED INACCURATE DIFFERENTIAL RHR A, CS A INITIATION INOPERATIVE. NONE PRESSURE SIGNAL (POSSIBLE DIVISION I HIGH WATER LEVEL HPCI HIGH WATER LEVEL SIGNAL) TURBINE TRIP.

1 INSTRUMENT LINE 17 PAGE I 0F 1 LINE 17 (N16, 1908) VARIABLE LINE 12-197524 (3 23)

t APPENDIX A HOPE CREEK COffl0N SENSOR FAILURE FAII11tE TYPE CottlON TAP (BROKEN OR EFFECT ON RPV WAIT.R LEVEL, SYSTEM ID SENSOR MPL PLUGGED) PRIMARY EFFECT SECONDARY EFFECT PRESSUPE OR POWER

{

JET PUMP 821-NO33A BROKEN FIDW TRANSMITTER READING NONE. USED FOR JET PIMP CALIBRATION - -NONE e,

INSTRUMENTATION WILL BE INACCURATE ONLY. .y-PLUGGED FIDW TRANSMITTER READISG NONE. USED FOR JET PtMP CAllBRATION ,

, w .

MONR  %

WILL BE INACCURATE ONLY. --

JET PUMP B21-NO34J BROKEN FIDW TNANSHITTER WILL BE NONE. USED FOR JET PUMP CALIBRATION. NtJE INSTRUMENTATION INACCURATE PLUGGED FLOW TRANSMITTER WILL BE NONE. ~USED-FOR JET PUMP' CALIBRATION. NONE _

INACCURATE ~ -

h. ./g h' j ne -

n

~

w

% - W N

.s hw

a. ,

N .

. ,. J:

e 4

f

.m 5

INSTRUMENT LINE 18 PAGE I OF 1 LINE 18 (N8, 285*) VARIABLE LINE 12-197524 (A-24)

b APPENDIX A .

HOPE CREEE C0fm0N SENSOR FAILURE FAILURE TYPE C0fMON TAP (BROKEN OR EFFECT ON RPV WATER LEVEL,

' SYSTEM ID SFNSOR MPL PLUGGED) PRIMARY EFFECT SECONDARY EFFECT PRESStRE OR POWER NUCLEAR BOILER B21-N085A BROKEN MINIMUM DIFFERENTIAL LEVEL RECOPDER B21-R615 INDICATES IDW NONE PRESSURE SIGNAL (IDW WATER WATER LEVEL.

LEVEL)

PLUGGED INACCURATE DIFFERElff!AL LEVEL RECORDER B21-R615 INACCURATE. NONE

. PRESSURE SIGNAL INSTRUMENT LINE 19 3

PAGE I 0F 1 LINE 19 (HIGN PRESSURE CONNECTOR) 13-197524 (4 25)

e

, +2

+ APPENDIX A

} '

% -j' ~

~.V 1 HOPE CREEE Cotm0N SENSOR FA.ILURE

~

x FAILURE TYPE

_ Col 980N TAP , ' { BROKEN OR _ 'EFFECT ON RPV WATER IXVEL,

" SYS W ID SENSOR MPL PLUCCED) PRIMARY 1FTE6_T' ~_ SECONDARY EFFECT PRESSURE OR POWER NUCLEAR BOILER B21-NO32 BROKEN MINIMUtf DIFFERENTIAL DIFFERENTIAL PRESSURE /FIDW RECORDER NCNE PRESSURE SIGNAL. 2613 INDICATES MINIMUM PRESSURE / FLOW.

v. . PLUGCED INACCURATE DIFFERENTIAL DIFFERENTIAL PRESSURE /FIM RECORDER NONE

' %~ PRESSURE SIGNAL R613 INDICATES INACCURATE PRESSURE /

~'- FLOW.

REACTOR WATER ,G33-NO37 BROKIN MINIMUM DIFFERENTIAL INSTRIMENT USED TO MEASURE FIM NONE CLEANUP , PRESSURE SIGNAL THROUGH DRAIN LINE, DRAIN NOT USED DURING NORMAL OPERATION.

- PLucCED INACCUR TE DIFFERENTIAL SEE ABOVE FOR BROKEN LINE. NONE FRESSURE SIGNAL '-

NUCLEAR BOILER B21-R034J BROKEN MINIMUM DIITERDTIAL NOR. USED F02 INDICATION ONLT. NONE PRESSURE SIGNAL- s *

' s PLUCCED INACCURATE DIFFERENTIAL NONE. USED FOR INDICATION ONLT. . liONE PRESSURE SIGNAL .

,- _ ., N s

~

, s u -

w

, ,f

=

s

,i 3 ._

INSTRUMENT LINE 21 PACE I 0F 1 LINE 21 (PRESSURE BEIAW CORE PLATE) 2 12-1975 ' (A-26) i

~ . -- - . - . . .

APPENDIX A ,

I HOPE CREEK Coltt0N SENSOR FAILURE FAILURE TTPE Coltt0K TAP (BROKEN OR ' EFFECT ON RPV WATER IXVEL, j SYSTEM ID SENSOR N'L PLUGGED) PRIMART EFFECT SECONDART EFFECT PRESSURE OR POWER

- REACTOR C71-N050A BROKEN MINIMUM PRESSURE SIGNAL ONE CHANNEL FOR SCRAM 001 NIGN DRTWELL NONE

, PROTE NION PRESSURE INOPERATIVE. NIGH DRTWELL i

PRESSURE ISOLATION CIASURE OF El1-F049 RNR DISH TO RADWASTE INBD ISOL VALVE AND Ell-F079A&B. RNR SAMPLE LINE ISOLATION VALVES INOPERATIVE.

PLUGCED CONSTANT PRESSURE SIGNAL ONE CHANKEL FOR SCRAM ON MIGN DRYWELL NONE PRESSURE INOPERATIVE.

'i NUCLEAR BOILER B21-N094A BROKEN MINIMUM PRESSURE SIGNAL HALF NIGN DRTWELL PRESSURE SIGNAL NONE AND INOPERATIVE. CORE SPRAT PtBIP A AUTO

~

821-N094E INITIATION INOPERATIVE. RNR A INITIA-TION ON HIGN DRYWELL PRESSURE INOPERA-TIVE. NIGN DRYWELL PRESSURE NPCI INITIATION OPERATIVE (CNANNEL A IDST, BUT CHANNEL C AVAILABLE - B21-N094C&G).

Alf!O OPEN Ell-F021A AND Ell-F016A CONTAINMENT SPRAT DUTBOARD AND INBOARD VALVES INOPERATIVE.

PLUGGED CONSTANT PRESSURE SIGNAL AUTO OPEN Ell-F021A AND Ell-F016A NONE CONTAINMENT SPRAT OUTBOARD AND INBOARD

. VALVES INOPERATIVE.

CONTAINMENT PT-4960A1 BROKEN LOW PRESSURE SIGNAL USED FOR INDICATION ONLY; NO EFFECT. NONE ATHOSPNERIC CONTROL (M57) PLUGGED INACCURATE PRESSURE SIGNAL USED FOR INDICATION ONLT; NO EFFECT. NONE

]

PT-4960A2 BROKEN LOW PRESSURE SIGNAL USED FOR INDICATION ONLY; NO EFFECT. NONE PLUGGED INACURRATE PRESSURE SIGNAL USED FOR INDICATION ONLY; NO EFFECT. NONE PT-4960A3 BROKEN NO EFFECT. USED FOR INDICATION ONLT; NO EFFECT. NOIrL PLUGGED NO EFFECT. USED FOR INDICATION ONLT; NO EFFECT. NONE l

4 INSTRUMENT LINE 22

^

PAGE I 0F 1 LINE 22 (CONTAINMENT PENETRATION J6A) 13-197584 (A-27) -]

4

APPENDIX A .

HOPE CREEE C0t910N SENSOR FAILURE FAILURE TYPE C0ftt0W TAP (BROKEN OR EFFECT ON RPV WATER LEVEL, SYSTEM ID SENSOR HPL PLUCCED) PRIMARY EFFECT SECONDARY EFFECT PRESSURE OR POWER NUCLEAR BOILER B21-N094C BROKEN CONSTANT PRESSURE SIGNAL HIGH DR M LL PRESSURE CORE SPRAT NOME AND PttfP C AUTO INITIATION INOPERATIVE.

B21-NO94G RHR C INITIATION ON HIGH DR M LL PRESSURE INOPERATIVE. HIGH DR M LL PRESSURE HPCI INITIATION OPERATIVE (CHANNEL C IDST, BUT CHANNEL A AVAILABLE - P11-N094A&E).

PLUGGED CONSTANT PRESSURE SIGNAL (CHANNEL C IDST, BUT CHANNEL A NONE AVAILABLE - 821-N094A&E).

REACTOR C71-N050C BROKEN MINIMUM PRESSURE SIGNAL ONE CHANNEL FOR SCRAM ON HIGI DRMLL NONE PROTECTION PRESSURE INOPERATIVE. HIGH DR M LL PRESSURE CIDSURE OF BALANCE OF PLANT ISOLATION VALVES INOPERATIVE.

i PLUGGED CONSTANT PRESSURE SIGNAL ONE CHANNEL FOR SCRAM ON HIGH DR M LL NONE PRESSURE INOPERATIVE. HIGH DR M LL PRESSURE CLOSURE OF BALANCE OF PLANT ISOLATION VALVES INOPERATIVE.

l INSTRUMENT LINE 21 PAGE 1 OF 1 LINE 23 (CONTAINMENT PENETRATION J8D) 12-197524 (A-28)

APPENDIX A y

~

HOPE CREEK COMMON SENSOR FAILURE FAILURE TYPE C0tMON TAP (BROKEN OR EFFECT ON RPV WATER MVEL, SYSTEM ID SENSOR MPL PLUCCED) PRIMARY EFFECT SECONDARY EFFECT PRESSURE OR POWER NUCLEAR BOILER B21-N086A BROKEN MINIMUM DIFFERENTIAL MSIV CIASURE CHANNELS A AND B INOPERA- NOME AND PRESSURE SIGNAL (IAW FLOW) TIVE; BACKED UP BY CHANNELS C AND D.

B21-N086B PLUGCED INACCURATE DIFFERENTIAL MSIV CIASURE CHANNELS A AND B IN0PERA- NONE PRESSURE SIGNAL (FLOW) TIVE; BACKED UP BY CH4NNELS C AND D.

FEEDWATER C32-N003A BROKEN MINIMUM DIFFERENTIAL IAW FLOW INDICATION ON ONE STEAM LINE MINOR DECREASE IN WATER H VEL, BUT RPV CONTROL PRESSURE SIGNAL (IAW FLOW) TO FEEDWATER CONTROLER WHICH TOTALS LEVEL SENSORS FEED BACK TO CONTROLLER, FIAW FROM ALL STEAM LINES AND DE- CAUSING INCREASED FEEDWATER FIDW WHICH CREASES FEEDWATER ACCORDINGa.f. READJUSTS RPV WATER LEVEL.

PLUGGED INACCURATE DIFFERENTIAL INACCURATE FLOW INDICATION IN ONE MINOR FLUCTUATIONS IN RPV WATER MVEL PkESSURE SIGNAL (FLOW) STEAMLINE; SUBSEQUENT SMALL FRROR IN FEEDWATER FLOW.

1 1

a INSTRUMENT LINE 24 PAGE I 0F I LINE 24 (CONDENSING CHAMBER D008A ON STEAM LINE "A", HIGH PRESSURE SIDE) 13-197524 (A-29)

APPENDIX A- , ,

HOPE CREEK C0tet0N SENSOR FAILURE FAILURE TYPE Cole 10N TAP (BROKEN OR EFFECT ON RPV WATER IIVEL, STSTEM ID SENSOR MPL PLUGGED) PRIMART EFFCCT SECONDART EFFECT PRESSINtE OR POWER NUCLEAR BOILER B21-N087A BROKEN MINIMUM DIFFERENTIAL MSIV CLOSURE CHANNELS A AND B IN0PERA- M AND PRESSURE SIGNAL (IDW FLOW) TIVE; BACKED UP BT CHANNELS C AND D.

821-N0878 PLUGGED INACCURATE DIFFERI.NTIAL MSIV CIDSURE CHA10 LEIS A AND B IN0PERA- NONE PRESSURE SIGNAL (FIDW) TIVE; BACKED UP BT CHANNELS C AND D.

FEEDWATER C32-N0038 BROKEN MINIMUff DIFFERENTIAL LOW FIDW INDICATION ON ONE STEAM LINE MINOR DECREASE IN WATER LEVEL, BUT RPV CONTROL PRESSURE SIGNAL (LOW FLOW) TO FEEDWATER CONTROLIIR WHICH TOTALS LEVEL SENSORS FEED BACK TO CONTROLLER, FIDW FROM ALL STEAM LINES AND DE- CAUSING INCREASED IEEDWATER FIDW WHICH CREASES FEEDWATER ACCORDINGLY. READJUSTS RPV WATER LEVEL.

j PLUGGED INACCURATE DIFFERENTIAL INACCURATE FIDW INDICATION IN ONE MINOR FLUCTUATIONS IN RPV WATER LEVEL,,

PRESSURE SIGNAL (FLOW) STEAMLINE; SUBSEQUENT SMALL ERROR IN SEE NOTE ABOYE.

FEEDWATER FIDW.

I 1

l 1

l t

I INSTRUMENT LINE 25 PAGE I 0F 1 LINE 25 (CONDENSING CHAMBER D008A ON STEAM LINE "B", HIGH PRESSITAE SIDE) 12-1975" (A-30)

APPENDIX A ,

NOPE CREEK COMMON, SENSOR FAILURE FAILURE TYPE Corm 0N TAP EFFECT ON RPV WATER IIVEL, (BROKEN OR SYSTEM ID SENSOR MPL PLUGCED) PRIMARY EFFECT SECONDART EFFECT PRESSIRE OR POWER NUCLEAR BOILER B21-N088A BROKEN MINIMIM DIFFERENTIAL MSIV CIDSURE CHANNELS A AND B IN0PERA- NONE AND PRESSURE SIGNAL (IDW FIDW) TIVE; BACKED UP BY C'iANNELS C AND D.

821-N0888 PLUGGED INACCURATE DIFFERENTIAL MSIV CIDSURE CHANNELS A AND B IN0PERA- NONE PRESSURE SIGNAL (FLOW) TIVE; BACKED UP BY CHANNELS C AND D.

MINIMUM DIFFERENTIAL LOW FLOW INDICATION ON ONE STEAM LINE MINOR DECREASE IN WATER LEVEL, BUT RPV FEEDWATER C32-N003C BROKEN I2 VEL SENSORS FEED BACK TO CONTROLI2R, i

CONTROL PRESSURE SIGNAL (IDW FLOW) TO FEEDWATER CONTROLLER (WHICH TOTALS FLOW FROM ALL STEAM LINES AND DE- CAUSING INCREASED FEEDWATER FLOW WHICH CREASES FEEDWATER ACCORDINGLT). READJUSTS RPV WATER LEVEL.

PLUGGED INACCURATE DIFFERENTIAL INACCURATE FIDW INDICATION IN ONE MINOR FLUCTUATIONS IN RPV WATER LEVEL, PRESSURE SIGNAL (FLOW) STEAMLINE; SUBSEQUENT SMALL ERROR IN SEE NOTE ABOVE.

FEEDWATER FLOW.

l I

I j

INSTRUMENT LINE 26 PAGE I OF I LINE 26 (CONDENSING CHAMBER D008A ON STEAM LINE "C", "IGH PRESSURE SIDE) 12-1975 " (A-31)

i I

APPENDIX A  ;

HOPE CREEK C0te10N SFNSOR FAILURE FAILURE TYPE Cortt0N TAP (BROKEN OR EFHCT ON RPV WATER LE%EL, SYSTEM ID SENSOR MPL PLUGCED) PRIMARY EFFECT SECONDARY EFFECT PRESSURE OR POWER NUCIIAR BOILER B21-N089A BROKEN HINIMUM DIFFERENTIAL MSIV CIDSURE CHANNELS A AND B INOPERA- NONE AND PRESSURE SIGNAL TIVE; BACKED UP BY CHANNELS C AND D.

B21-N0898 PLUGCED INACCURATE DIFFERENTIAL HSIV CIDSURE CHANNEIS A AND B IMOPERA- NONE PRESSURE SIGNAL (FLOW) TIVE; BACKED UP BY CHANNELS C AND D.

FEEDWATER C32-N003D BROKEN MINIMUM DIFFERENTIAL LOW FIDW INDICATION ON ONE STEAM LINE MINOR DECREASE IN WATER LEVEL. BUT RPV CONTROL PRESSURE SIGNAL (FIDW) To FEEDWATER CONTROLLER WHICH TOTALS LEVEL SENSORS FEED BACK TO CONTROLIER, FIDW FROM ALL STEAM LINES AND DE- CAUSING INCREASED FEEDWATER FLOW WHICH PLUGGED INACCURATE DIFFERENTIAL CREASES FEEDWATER ACCORDINGLY. READJUSTS RPV WATER IIVEL.

PRESSURE SIGNAL (FIDW)

INACCURATE FIDW INDICATION IN ONE MINOR FLUCTUATIONS IN RPV WATER LEVEL, STEAMLINE; SUBSEQUENT SMALL ERROR IN SEE NOTE ABOVE.

FEEDWATER FLOW.

i INSTRUMENT LINE 27 PACE I OF 1 LINE 27 (CONDENSING CHAMBER D008A ON STEAM LINE "D", HIGH PRESSURE SIDE) 13-197524 (A-32)

4 APPENDIX A , ,

HOPE CREEK LOMMON SENSOR FAILURE FAILURE TYPE COtMON TAP (BROKEN OR EFFECT ON RPV WATER LEVEL, STSTEM ID SENSOR MPL PLUGGED) PRIMART EFFECT SECONDARY EFFECT PRESSURE OR POWER NUCLEAR BOILER B21-WO86A BROKEN MAXIMUM DIFFERENTIAL SIGNAL TO ISOLATE MSIVs DUE TO HIGN REACTOR SCRAM.

AND PRESSURE SIGNAL (HIGH FLOW) STEAM FLOW.

B21-N086B PLUGGED INACCURATE DIFFERENTIAL INACCURATE FIDW INDICATION FROM ONE OF NONE PRESSURE SIGNAL (FIDW) THE MAIN STEAM LINES.

FEEDWATER C32-N0034 BROKEN MAXIMUM DIFFERENTIAL HIGH FIDW INDICATION ON ONE STEAM LINE MINOR INCREASE IN WATER LEVEL, BUT RPV CONTROL PRESSURE SIGNAL (HIGH FLOW) TO FEEDWATER CONTROLLER (WHICH TOTALS LEVEL SENSORS FEED BACK TO CONTROLLER, FLOW FROM ALL STEAM LINES AND IN- CAUSING DECREASED FEEDWATER FIDW.

CREASES FEEDWATER ACCORDINGLY).

PLUGGED INACCURATE DIFFERENTIAL INACCURATE FLOW INDICATION FROM ONE MINOR FLUCRIATIONS IN RPV WATER LEVEL, PRESSURE SIGNAL (FLOW) STEAM LINE; SUBSEQUENT SMALL ERROR IN SEE NOTE ABOVE.

FEEDWATER FLOW.

k INSTRtMENT LINE 28 PAGE I OF 1 LIhE 28 (CONDENSING CHAMBER D007A ON STEAM LINE "A", LOW PRESSURE SIDE) 12-197524 (4 33)

APPENDIX A HOPE CREEK Cotet0N SENSOR FAILURE FAILURE TYPE Cotet0N TAP (BROKEN OR SYSTEM ID EFFECT ON RPV WATER IEVEL.

SENSOR MPL PLUGGED) PRIMARY EFFECT SECONDARY EFFECT PRESSURE OR POWER OCLEAR BOILER B21-N087A BROKEN MAXIMikt DIFFERENTIAL SIGNAL TO ISOLATE MSIVs IYK TO RICH REACTOR SCRAM.

AND PRESSURE SIGNAL (HIGH FLOW) STEAM FI M .

B21-N0878 PLUGGED INACCURATE DIFFERENTIAL INACCURATE FIM INDICATION FROM ONE OF NONE PRESSURE SIGNAL (FIDW) THE MAIN STEAM LINES.

FEEDWATER C32-N003B BROKEN MAXIMUM DIFFERENTIAL HIGH FIM INDICATION 'ON ONE STEAM LINE MINOR INCREASE IN WATER LEVEL, BUT RPV CONTROL PRESSU" SIGNAL (HIGH FIDW) TO FEEDWATER CONTROLLER WHICH TOTALS IE AL SENSORS FEED BACK TO CONTROLLER.

FLOW FROM ALL STEAM LINES AND IN- CAUSING DECREASED FEEDWATER FIM.

CREASES FEEDWATER ACCORDINGLT.

PLUGCED INACCURATE DIFFERENTIAL INACCURATE FI M INDICN. ION FROM ONE MINOR FLUCTUATIONS IN RPV WATER LEVEL, PRESSURE SIGNAL (FIM) STEAM LINE; SUBSEQUENT SMALL ERROR IN SEE NOTE ABOVE.

FEEDWATER FI N .

INSTRUMENT LINE 29 PAGE I 0F I LINE 29 (CONDENSING CHAMBER D007A ON STEAM LINE "B", IM PRESSURE SIDE) 12-197524 (4 34)

l APPENDIX A r HOPE CREEE CorHON SENSOR FAILURE

( FAILURE TYPE l COMMON TAP (BROKEN OR EFFECT ON RPV WATER IIVEL, STSTEM ID SENSOR MPL PLUGGED) PRIMART EFFECT SECONDARY EFFECT PRESSURE OR POWER NUCLEAR BOILER B21-N088A BROKEN MAXIPRM DIFFERENTIAL SIGNAL TO. ISOLATE MSIVs DUE TO NIGH REACTOR SCRAM.

AND PRESSURE SIGNAL (HICH FLOW) STEAM FIN.

B21-N0888 PLUGGED INACCURATE DIFFERENTIAL INACCURATE FIM INDICATION FROM ONE OF NONE PRESSURE SIGNAL (FLOW) THE MAIN STEAM LINES.

FEEDWATER C32-N003C BROKEN MAXIMUM DIFFERENTIAL NIGH FIM INDICATION ON ONE STEAP' LINE MINOR INCREASE IN WATER LEVEL, BUT RPV CONTROL PRESSURE SIGNA 8 (HIGH FIN) TO FEEDWATER CONTROLLER WHICH TOTALS LEVEL SENSORS FEED BACE TO CONTROLLER, FI M FROM ALL STEAM LINES AND IN- CAUSING DECREASED FEEDWATER FIM .

CREASES FEEDWATER ACCORDINGLY.

PLUGCED INACCURATE DIFFERENTIAL INACCURATE FI M INDICATION FROM ONE MINOR FLUCTUATIONS IN RPV WATER LEVEL, PRESSURE SIGNAL (FLOW) STEAM LINE; SUBSEQUENT SMALL ERROR IN SEE NOTE ABOVE.

FEEDWATER FI N .

1 I

l l

INSTRUMENT LINE 30 PAGE I 0F I LINE 30 (CONDENSING CHAMBER D007A ON STEAM LINE "C", IM PRESSURE SIDE) 12-197524 (A-35)

APPENDIX A  ;

HOPE CREEE Cottt0N SENSOR FAILURE FAILURE TYPE EFFECT ON RPV WATER LEVEL, Cortg0N TAP (BROKEN OR SECONDARY EFFECT PRESSLEtt OR POWER STSTEM ID SENSOR MPL PLUGGED) PRIMARY EFFECT MAXIMLRf DIFFERENTIAL SIGNAL TO ISOLATE MSIVs DUE TO HIGH REACTOR SCRAM.

NUCLEAR BOILER B21-NG89A BROKEN AND PRESSURE SIGNAL (HIGH FLOW) STEAM FIDW.

B21-N089B PL8Y,GED INACCURATE DIFFERENTIAL INACCURATE FIhW INDICATION FROM ONE OF NONE PRESSURE SIGNAL (FIN) THE MAIN STEAM LINES.

BROKEN MAXIMUM DIFFERENTIAL HIGH FI M INDICATION ON ONE STEAM LINE MINOR INCREASE IN WATER IIVEL, BUT RPV

.FEEDWATER C32-N003D LEVEL SENSORS FEED BACK TO CONTROLLER, CONTROL PRESSURE SIGNAL (HIGH FIN) To FEEDWATER CONTROLLER (WHICH TOTALS FLOW FROM ALL STEAM LINES AND IN- CAUSING DECREASED FEEDWATER FIhW.

CREASES FEEDWATER ACCORDINGLT).

INACCURATE FLOW INDICATION FROM ONE MINOR FLUCTUATIONS IN RPV WATER LEVEL, PLUGGED INACCURATE DIFFERENTIAL PRESSURE SIGNAL (FIN) STEAM LINE; SUBSEQUENT SMALL ERROR IN SEE NOTE ABOVE.

FEEDWATER FLOW.

l l

I l

l INSTRUMENT LINE 31 l PACE I 0F 1 LINE 31 (CONDENSING CHAMBER D007A ON STEAM LINE "D", IM PRESSURE SIDE) l 12-197584 (A-36)

>-6 APPENDIX A NOPE CREEK Colfl0N SENSOR FAILURE FAILURE TYPE C0f910N TAP (BROKEN OR EFFECT ON RPV WATER LEVEL.

SYSTEM ID SENSOR MPL PLUGGED) PRIMARY EFFECs SECONDARY EFFECT PRESSURE OR POWER CONTROL ROD Cll-N054A BROKEN MINIffUN PRESSURE SIGNAL POWER INDICATION BELOW 20% ENFORCED NONE DRIVE ROD PATTERN CONTROL.

PLUGGED INACCURATE PRESSURE SIGNAL NONE NOME REACTOR C71-N052A BROKEN MINI

  • fun PRESSURE SIGNAL NONE PROTECTION AND C71-N0528 PLUGGED INACCURATE PRESSURE SIGNAL NONE NONE l

1 4

1 4

i I

INSTRUPENT LINE 32 PACE I OF I LINE 32 (FIRST STAGE PRESSURE, NP TURBINE) j I2-197524 (A-37)

APPENDIX A ,

NOPE CREEE C0 ret 0N SENSOR FAILINtE FAILURE TYPE COMtDN TAP (BROEEN OR EFFECT ON RPV 1 DATER I2 VEL, SYSTDI ID SENSOR MPL PLUGGED) PRIMARY EFFECT SECONDARY EFFECT PRESSLRE OR POWER CONTROL ROD Cll-N054B BROKEN MINIMLRt PitESSINtE SIGNAL POWER INDICATION PELOW 201 ENFORCED N06 DRIVE ROD PATTERN CONTROL.

PLUGGED INACCURATE PRESSURE C00lTit0L NOME NONE REACTOR C71-N052C BROEEN MINIfftM PRESSINtt SIGNAL POWER INDICATION BEIDW 301 REESTABLISN NONE PROTECTION AND TURRINE STOP VALbZ CIDSURE, CONTit0L C71-N052D VALVE FAST CIDSURE SCRAM BYPASS.

PLUGGED INACCURATE PRESSURE SIGNAL NONE NGA 1

I

+

l INSTRittENT LINE 33 PAGE 1 0F 1 LINE 33 (FIRST STAGE PRESSultE, HP 7tRBINE) 8 12-1975 ' (A-38)

APPENDII B ,

BOPE CREEE Cor000N SENSOR FAILURE FAILIstE TTPE Corn 0N TAP (BROKEN OR EFFECT ON RPV WATER 12 VEL, ST57EM ID SENSOR MPL PLUGGED) PRIMART EFFECT SECONDART EFFECT PRESSWE OR POWER STATOR COOLING PSLL-3589A-C BROEEN SENSOR FAILS IDW 2/3 IDGIC WILL TRIP TURBINE, GENERATOR REACTOR LOAD RUNRACE, SLIGHT INCREASE WATER SYSTEfl IN REACTOR WATER LEVEL, PRESSURE.

(CEN STS)

PLUGGED SENSOR FAILS IDW IDSS OF STATOR COOLING TRIP SIGNAL NONE 3

i INSTRINENT LINE 34 PAGE I OF I LINE 34 VARIABLE LINE 38-0211 (B-1)

-. ._. . _ . - - . _ - . . _ ~ - - - - - _

APPENDIX B ,

NOPE CREEE Colet0N Srm FAILINtE FAILINtt TYPE Coret0N TAP (BROEEN OR EFFECT ON RPV WATER IKVEL, SYSTEM ID SENSOR MPL PLUGGED) PRIMARY EFFECT SECONDARY EFFECT PRESSINtB OR PO W R STEAM SEAL PT-1998, BROEEN AUXILIARY STEAM SUPPLY NOME NOIE SYSTEM (M29) PSL-1997, VALVE OPENS PT-1996, PIC-2038 PLUGGED INACCURATE INDICATION OF NOME NONE SEALING STEAM PRESSURE

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2 1 INSTRUDENT LINE 35 PAGE 1 OF 1 LIllE 35 VARIABLE LINE 38-0211 (B-2) i

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MOPE CREEE CorMON SENSOR FAILURE FAILURE TTPE EFFECT ON RPV WATER LEVEL, f

C0fMON TAP (BROKEN OR STSTEM ID SENSOR MPL PLUGGED) PRIMART EFFECT SECONDART EFTECT PRESStBE OR POWER CONDENSATE PSN-1056A,B,C BROEEN SENSES HIGN PRESSURE TRI?S TURBINE. WILL TRIP THE REACTOR FRED PtMPS.

STSTEM (ft5) PSN-1058A,B,C (ATNOSPMERE)

PSN-1060A,B,C PSN-1664A,B,C PLUGGED INACCURATE PRESSURE SIGNAL DUE TO INCORRECT PRESStBE, MAT IIOT NO EFFECT*AT NORMAL OPERATION.

TRIP THE TURBINE ON MIGH PRESSURE (IAW VACtRM) .

INSintDENT LINE 37 PAGE 1 0F 1 LINE 37 VARIABIZ LINE 38-0211 (B-4)

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APPENDIX R ,'

NOPE CREEE Cortt0N SENSOR FAILIEtE FAILIRE TYPF.

0019 EON TAP (BROKEN OR EFNCT ON RPV WATER M VEL, STSTEM ID SENSOR MPL PLUGGED) PRiteART EFFECT SECONDART EFFECT PRES $tBE OR PO ER LUBE OIL PSL-3118A-C BROKEN SENSOR READS LOW 2/3 IDGIC WILL TRIP TIIE TURBINE / GEN. REACTOR IAAD Bl51 RACE, SLIGNT IFuan STSTEM IN REACTOR WATER M VEL / PRES 8tNLE.

PRESStBE (M19)

  • PLUGGED IDSS OF LUBE OIL PRESSURE NONE NONE TRIP SIGNAL INSTRUPENT LINE 39 PAGE 1 0F 1 LINE 39 VARIABLE LINE 38-0211 (B-6)

APPENDIX C CRITERIA FOR ELIMINATION OF SYSTEMS AND COMPONENTS OF SYSTEMS FROM THE CONTROL SYSTEMS FAILURE ANALYSIS Elimination Criterion

  • Basis N1 Nonelectrical components- (i.e., mechanical and structural components); however, associated functions that are electrically controlled or controlling (including signal inputs to electrical systems) may be relevant to the analysis. N1 examples are piping, tanks, turbines, etc.

N2 Instrumentation with no direct or indirect controlling function or passive input (such as a permissive signal) into control logic. Instrumentation and other dedicated inputs to the process computer, as well as the computer itself, are excluded.

Operator actions as a result of indications are not considered control functions for the control systems failure analysis.

N3 Control systems and controlled components' (i.e. , pumps, valves) that have no direct or indirect interaction with reactor opera-tion / parameters. Examples are communications, most unit heaters and controls, lighting controls, ventilation control systems for exterior building, machine shop equipment, refueling or main-tenance equipment controls, etc.

N4 Control systems and controlled components (i.e., pumps, valves) that do interact or interface with reactor operating systems but ca nnot affect the reactor parameters (water level, pressure or reactivity) either directly or indirectly.

N5 Systems or components that cannot affect reactor parameters within 30 minutes of the loss of any power bus or combination thereof.

N6 Systems that are not used during normal power operation. For example, start-up, shutdown or refueling systems not used during normal operation may be eliminated.

N7 Electrical components involved in distribution, tranformation or interruption of power; however, controls for these components may need to be considered if loss of such control power may lead to failure of other electrical busses.

N8 Safety systeras, except for their response to conditions brought about by control systems failures. Example: A level 3 scram will be assumed for a loss-of-feedwater event.

  • In some cases, more than one of these criteria may apply.

C-1 12-2011

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APPENDIX D HCGS COMMON SENSOR FAILURE ANALYSIS -

SYSTEM ELIMINATION PROCESS l GE I l RELATED l MPL l ELIMINATION l P&ID NO. CRITERION SYSTEM / SUBSYSTEMS I l l I. REACTOR SYSTEMS I I I M42 l B21 l

  • I Nuclear Boiler Vessel Instrumentation i I- l M43 l B31 1
  • I Reactor Recirculation System

'l i I M44/M45 l G33 1

I l l M46/M47 l C11 1

  • l Jet Pump Instrumentation System 1 I I M41 1 B21 I N8 i Nuclear Steam Supply Shutoff System l l l Various l I N8 I Primary Containment Isolation System I l l l C22 l N8 I Redundant Reactivity Control System I I I M72 l l N8/N6 i Main Steam Isolation Valve Scaling System I I I M53/M54 l l N3 I Fuel Pool Cooling & Torus Water Cleanup i l I M57 l l
  • I Containment Atmosphere Control l l l M58 I I N8/N6 l Containment Hydrogen Recombination System i I I M57 I I N1 l Primary Containment Vacuum Relief System i I l l C51 1
  • l Neutron Monitoring System i I I M41 l l N3 l Safety Relief Valve Position Indication i I I l C11 1
  • 1 Reactor Manual Control System i I I
  • To be included in analysis.

D-1 12-2011

c. -

APPENDIX D HCGS COMMON SENSOR FAILURE ANALYSIS -

SYSTEM ELIMINATION PROCESS l GE l l RELATED l MPL l ELIMINATION l P&ID NO. CRITERION SYSTEM / SUBSYSTEMS M59 l l

  • To be included in analysis.

D-2 12-2011

APPENDIX D HCGS COMMON SENSOR FAILURE ANALYSIS -

SYSTEM ELIMINATION PROCESS l GE l l RELATED l MPL l ELIMINATION l P&ID NO. CRITERION SYSTEM / SUBSYSTEMS l l l II. TURBINE / GENERATOR SYSTEM i l 1 M1 1 -l

  • l Turbine Control System l l l M2 l l
  • l Heater Vent & Drain System l l l M5 I l
  • l Condensate System l l l M6 l l
  • l Condenser Air Removal System i I l M8 l l
  • l Condensate & Refueling Water Storage & Transfer l l l M16 l l
  • l Condensate Demineralizer l l l M19 l l
  • I Turbine Sealing Steam l l l M31 l l
  • l Reactor Feed Pump Turbine Steam System

. 1 I l 7 M9 l l

  • l Generator System l I l l l
  • I Generator Excitation System l l l M28 l l
  • I Generator Gas Control System l l l I
  • To be included in analysis.

D-3 12-2011

__ - ~ _ _ _ _ . _ . _ _ _ ~_. _

>. e

.e, . w. .

APPENDIX D HCGS COMMON' SENSOR FAILURE ANALYSIS -

SYSTEM ELIMINATION PROCESS-

'l GE l l RELATED I 'MPL l ELIMINATION l P&ID NO. CRITERION SYSTEM / SUBSYSTEMS l l l III. AUXILIARY SYSTEMS I I i l l N8/N6 l Diesel Generator System l l l M30 l l N8/N6 l Diesel Engine Auxiliary System l l l M20 l l N3/N6 i Auxiliary Boiler Fuel Oil System I I I M21 l -I N3/N6 i Auxiliary Steam System I l l M10 l l

  • l Safety Aux Cooling (SAC), Reactor Building I l l M12 l l
  • l Safety Aux Cooling, Aux Building

-l l l M13 l l

  • l Reactor Auxiliary Cooling (RAC) i I I M14 l l
  • l Turbine Auxiliary Cooling l l 1 M24 l l

l l l CW Acid Injection l I I MIS l l

  • I Compressed Air System i I I M18 l l N4 l Demineralizer Water Makeup Storage & Transfer I I l M22 l l N3 l Fire Protection i i 1 M23 l l N4 l Process Sampling

.I I l M25 i B21 1 ,

  • l Plant Leak Detection System i I l M26 l l
  • I Radiological Monitoring System
1 I I I

M33 l l N3 l Low Volume & Oily Wastewater Treatment

! I I M17 l l N3 l Fresh Water Supply l I I M71 l l

  • l Liquid N2 for Purge & Containment Inerting l l l M94/M97 l l N3 l Building Drainage System

. I l l M99 l l N6 l Building Sewage System I I I M60 l l N3 l Primary Containment Leak Testing l l l l l N3 l Site Environs Radiation Monitoring l l l

'M98 l l N3 l Domestic Water System I i l

  • To be included in analysis.

D-4 12-2011 i

9 w3 APPENDIX D HCGS COMMON SENSOR FAILURE ANALYSIS -

SYSTEM ELIMINATION PROCESS l GE l l RELATED l MPL l ELIMINATION l P&ID NO. CRITERION SYSTEM / SUBSYSTEMS l l l IV. HEATING, VENTILATION, AIR CONDITION AND l l 1 COOLING (HVAC) SYSTEMS I I l M36/M37 l 'l N3 l Guard House HVAC System l l l M73/M74 l l N3 l Admin. Suilding & Warehouse HVAC System l l l M82 l l

  • I Turbine Building Supply & Exhaust Vent System l l l M83/M84 l l
  • l Reactor Building Supply & Exhaust Vent System I I I (FRVS) i I I M86 l l
  • I Drywell Vent Control System l l l M88 l l N3 l Auxiliary Bldg-Diesel Area Vent Control System i 1 l M89 l l
  • I Auxiliary Bldg-Control Area Vent Control System l l l M92 l l N3 -l Auxiliary Bldg - RW Area Vent Control System I I l M93 l l N3 l Aux Bldg-Service Area & TSC Vent Control System I I l M87 l l
  • l Chilled Water System i I I M90 l l
  • l Aux Bldg - Control Area Chilled Water System l l l M95 l l N3 l Misc Structure & Yard Bldgs Vent Control Systems l l l M96 l l N3 l Plant Heating System i I I
  • To be included in analysis.

D-5 12-2011

1 l

1 APPENDIX D HCGS COMMON SENSOR FAILURE ANALYSIS -

SYSTEM ELIMINATION PROCESS I E I I RELATED l MPL l ELIMINATION l P&ID NO. CRITERION SYSTEM / SUBSYSTEMS l 1 l V. RADWASTE SYSTEM l l , 1 M69/M70 l l

  • l Gaseous Radwaste System l l 1 >

M61/M62 l l N3 l Liquid Radwaste System M63/M64 l l l M65 l l l l l l M66/M67 l l N3 l Solid Radwaste System M68 l l l 1 I l 1

e

  • To be included in analysis.

D-6 12-2011 I --

r -

.* .(- l

< y- 1 l

APPENDIX D HCGS COMMON SENSOR FAILURE ANALYSIS - .

l SYSTEM ELIMINATION PROCESS f i

l. GE l l i

RELATED l MPL l ELIMINATION l u P&ID NO. CRITERION 'l SYSTEM / SUBSYSTEMS l l l VI. ELECTRICAL SYSTEMS l l l l l N3 l Communication System 4f l l I l Lighting System l l N3

. l l l s

a

. s.

v 4

'l

..(.

i t

i

  • To be included in analysis.

D-7 12-2011

. -. . . - . . - , . . , . -

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