ML20055A180
| ML20055A180 | |
| Person / Time | |
|---|---|
| Site: | Clinch River |
| Issue date: | 07/07/1982 |
| From: | Longenecker J ENERGY, DEPT. OF, CLINCH RIVER BREEDER REACTOR PLANT |
| To: | Check P Office of Nuclear Reactor Regulation |
| References | |
| HQ:S:82:065, HQ:S:82:65, NUDOCS 8207150554 | |
| Download: ML20055A180 (109) | |
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t am Department of Energy Washington, D.C. 20545 Docket No. 50-537 HQ:S:82:065 JUL 07 N Mr. Paul S. Check, Director CRBR Program Office Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Check:
RESPONSES TO REQUEST FOR ADDITIONAL INFORMATION
Reference:
Letter, P. S. Check to J. R. Longenecker, "CRBRP Request for Additional Information," dated April 30, 1982 This letter formally responds to your request for additional information contained in the reference letter.
l Enclosed are responses to Questions CS760.6, 35, 49, 50,113,116, and 131; which will also be incorporated into the PSAR Amendment 69; scheduled for submittal later in July.
Sincerely, h
. CN M A%
J hn R. Longena,cher c
Acting Director, Office of the Clinch River Breeder Reactor Plant Project Office of Nuclear Energy Enclosures p[
cc: Service List l
Standard Distribution Licensing Distribution B207150554 820707 PDR ADOCK 05000537 A
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l puestion CS760.6 "With respect to Reg. Guide 1.97, ' Instrumentation f or Light Water Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident' needed by the operator to monitor and respond to ar.cidents or postulated ocurrences, identify the system or event most closely related to each Instrument; the section of the PSAR In which use of the Instrument is describod; the significance of the information provided by the instrument; and the basis f or required accuracy, redundancy, range, and q ual i f i cati on. "
Resoonse The CRBRP Project has committed to provide Accident Monitoring Instruments in accordance with Reg. Guide 1.97, Revision 2 as applied to CRBRP. This commitment is in Appendix H to the PSAR.
Functional requirements and top level hardware design requirements have been established and are included in ammended Section 7.5.11 of the PSAR.
Further preliminary Inf ormation describing the current specifics of the Accident Monitoring design is included in this response in Table CS760.6-1. A description of the final Accident Monitoring Instrumentation will be provided in the FSAR.
t l
l QCS760.06-1 Amend. 69 July 1982 82-0361
RESPONSE TO NRC QUESTION CS760.6 CRBRP ACClDENT MONITORING VARIABLES TABLE CS760.6-1 This table contains the following preliminary Information describing the CRBRP Accident Monitoring design.
DEFINITION OF VARI ABLE TYPES A, B, C, D, AND E VARI ABLES ASSOCl ATED WlTH EACH VARI ABLE TYPE A, B, C, D, AND E DESCRIPTIVE PURPOSE OF EACH VARI ABLE RANGE AND RANGE RATIONAI.E FOR EACH VARI ABLE INSTRUENT LOOP ACCURACY AND RATIONAL FOR EACH VARI ABLE PSAR LOCATION WHERE EACH VARI ABLE IS DISCUSSED QCS760.06-2
^ M*
TYPE A MANUAL ACT10NS FOR INITIAT10N OF SAFETY SYSTEMS Those variables to be monitored that provide the primary inf ormation required to permit the control room operator to take specific manually controlled actions f or which no automatic control is provided and that are required f or saf ety systems to accomplish their saf ety f unctions f or Design Basis Accident events. Primary information is Information that is essential for the direct accomplishment of the specified safety functions; it does not include those variables that are associated with contingency actions that may also be Identified in written procedures. All Type A variables f or CRBRP are Indicated by design and qualification as Category 1.
A.1 TITLE:
Instrumentation Leadina to Actuation of DHRS A.1. A PHTS Hot Leo Temoerature CATEGORY 1 PURPOSE: THE PHTS Hot Leg Temperature, together with the PHTS IHX Outlet Temperature (i.e. Cold Leg) provides the operator with Information relating to shutdown heat rejection f rom the PHTS to the IHTS.
If this temperature exceeds a predetermined value, in conjunction with a collapse of the IHX primary sided 1T, the operator will take the appropriate manual action of initiating the direct heat renoval service (DHRS).
RANGE: 3000F - 12000F RATIONALE FOR RANGE: This range was chosen to cover the normal temperature range plus a minimum of 10% margin.
INSTRUMENT LOOP ACCURACY: f).1%
RATIONALE FOR INSTRUMENT LOOP ACCURACY: This is based on the best accuracy commercially available with reliable Instrumentation, and is adequate f or this accident monitoring f unction.
LOCATION IN PSAR: SECTION 7.5.2.1.1, 7.5.3.1.2, Tabl e 7.5-1 A.1.8 IHX Outlet Temoerature CATEGORY 1 PURPOSE: The IHX Outlet Temperature (i.e. Cold Leg), together with the PHTS Hot Leg Temperature provides the operator with Information relating to Shutdown heat rejection from the PHTS to the lHTS.
Ifthis temperature exceeds a predetermined value, in conjunction with a col lapse of the IHX primary side sit, the operator wil l take the appropriate manual action of initiating the direct heat removal service (DHRS).
RANGE: 3000F - 12000F QCS760.06-3
RATIONALE FOR RANGE: The range was chosen to cover the normal temperature range plus a minimum of 10% margin.
INSTRUMENT LOOP ACCURACY: 13.1%
RATIONALE FOR INSTRUMENT LOOP ACCURACY: This is based on the best accuracy commercially available with reliable Instrumentation, and is adequate f or this accident monitoring f unction.
LOCATION IN PSAR: S ection 7.5.2.1.1, 7.5.3.1.2, 7.5.11, Tabl e 7.5-1 TYPE B: VERIFICATION THAT SAFETY FUNCTIONS ARE BEING ACCOMPLISHED Those variables that provide inf ormation necessary to Indicate whether plant saf ety f unctions are being accomplished. The variables are listed with designated ranges and category for design and qualification.
B.1 TITLE: Reactor Shutdown B. I. A Neutron Flux CATEGORY 1 PURPOSE: The neutron flux Indication provides the f astest response to reactor power level change and the most direct indication of control of reactivity in the core.
RANGE:
10-6% to 100% f ul l power RATIONALE FOR RANGE: The instrument range is Intended to encompass all neutron f lux l evels f rom reactor f ull power down to shutdown power level and to prov!de indication of any significant deviation from shutdown power l evel.
INSTRUMENT LOOP ACCURACY: The loop is compossed of two overlapping range f rom 10-gges wherein the worst case minimum accuracy over the logarithmic ra % to 100% reactor power is 13.2% of linear equivalent f ul l scale accuracy.
RATIONALE FOR INSTRUMENT LOOP ACCURACY: The stated loop accuracy provides Indication to the operator of reactor power level to better than 130% of point over the ten decade range from reactor full power to shutdown power. This accuracy is verification adequate to f ulfill the purpose of monitoring the variable, that is, Indication of accomplishment of control of reactivity.
LOCATION IN PSAR: Section 7.5.1 QCS760.06-4
B.I.B Primarv Control Rod Position CATEGORY 3 PURPOSE: The Primary Rod " Bottom" Light which is located on the Main Control Panel illuminates when the primary rod position as measured by the Absolute Rod Position Indication (ARPI) System is less than 1.5 inches withdrawn.
The illumination of all 9 " Bottom" lights signifies that all 9 primary control rods are f ully inserted and shutdown has been accomplished.
RANGE: Full in or Not Full in RATIONALE FOR RANGE: This is positive Indication of rod position (Rod Bottom)
INSTRUMENT LOOP ACCURACY: The accuracy of the transducer and signal l
conditioning electronics is 1,0.2 inches. The accuracy of the rod bottom bistable which illuminates the indicating light is 1.0.1 inches.
RATIONALE FOR INSTRUMENT LOOP ACCURACY: Accuracy requirements have been established consistent with the capabilities of this type of measuring system. The levels will be verified to be achievable during the component tests. The maximum error of 0.3 inches is consistent with the purpose of this Instrument f or verification that shutdown has been accomplished.
LOCATION IN PSAR: SECTION 7.7.1.3.2 t
B.I.C Secondarv Control Rod Position CATEGORY 3 PURPOSE: A latched Indication on the Main Control Panel Indicates that the secondary rod is coupled to the secondary control rod driveline.
Confirmation of rod insertion f ollowing unlatching is accomplished by the operator driving the carriage downward while it contacts the top of the control assembly. Carriage position thus provides Indication of rod Insertion and accomplishment of the shutdown f unction.
RANGE: Latched or Unlatched RATIONALE FOR RANGE: NA
!NSTRUMENT LOOP ACCURACY: NA RATIONALE FOR INSTRUMENT LOOP ACCURACY: NA LOCATION IN PSAR: SECTION Paragraph 4.2.3.5.2.3, Scram Latch Indication System QCS760.06-5
8.2 TITLE
Core Coolina B.2.A PHTS Hot Isa Tamnerature CATEGORY I PURPOSE: The PHTS Hot Lag Temperature provides the operator with direct Indication of reactor heat removal and core cooling. During reactor operation, and following reactor shutdown, this parameter, combined with the IHX outlet temperature, provides thesiT across the IHX, which is a verification of PHTS heat rejection.
RANGE: 300oF to 12000F RATIONALE FOR RANGE: This range was chosen to cover the nr.aal temperature range plus a minimum of 10% margin.
INSTRUMENT LOOP ACCURACY: 9.1%
RATIONALE FOR INSTRUMENT LOOP ACCURACY-This is based on the best accuracy commercial ly avail abl e with reliabl e insircr.cr.tetlcn, end is adoquate for this accident monitoring f unction.
LOCATION IN PSAR: SECTION 7.5.2.1.1, 7.5.3. l.2, Tabl e 7.5-l B.2.B IHX Outlet Temoerature CATEGORY 1 i
PURPOSE: The IHX Outlet Temperature provides the operator with direct Indication of reactor heat renoval and core cooling.
During reactor operation, and following reactor shutdown, this parameter, combined with the PHTS Hot Leg Temperature, provides theg1T across the IHX, which is verification of PHTS heat rejection.
RANGE: 3000F - 12000F RATIONALE FOR RANGE: This range was chosen to cover the normal temperature range plus a minimum of 10% margin.
INSTRUMENT LOOP ACCURACY: D.1%
RATIONALE FOR INSTRUMENT LOOP ACCURACY: This is based on the best accuracy commercially available with reliable instrumer.tation, and is adequate f or this accident monitoring f unction.
LOCATION IN PSAR: SECTION 7.5.2.1.1, 7.5.3.1.2, Tabl e 7.5-1 B.2.0 PHTS Flow CATEGORY 3 PURPOSE: The PHTS Flow provides a direct verification of the capability to cool the reactor.
QCS760.06-6 l
RANGE: -1500 to +6000 GPM RATIONALE FOR RANGE: This range was chosen to cover the flow rate while operating on pony motors or on natural circulation. The reverse flow measurement covers the case of two pony motors operating and the th i rd pony motor i dl e.
INSTRUMENT LOOP ACCURACY: 46.1%
RATIONALE FOR INSTRUMENT LOOP ACCURACY: Thi s i s based on the state-of-the-art accuracy available f or this type of Instrumentation, and is adequate f or this accident monitoring f unction.
LOCATION IN PSAR: SECTION 7.2.1.2, 7.5.2.1.1 B.2,D Qqrg,fgit Temoerature CATEGORY 3 PURPOSE: The temperature of the sodium as it exits the reactor core is measured by 338 thermocouples distributed uniformly above the f uel and blanket assemblies.
By the use of these thermocouples information regarding the condition of Individual core assemblies may be obtained.
This measurement is used f or diagnosis of fuel cladding condition and in flow distribution through the core by monitoring change.
RANGE: 3000F to 17000F RATIONALE FOR RANGE: The instrument range, 3000F to 17000F, includes the minimum sodium temperature which is expected during cold shutdown and the maximum temperature which is expected to occur f or any accident condition.
Above 17000F the Indication would not be Indicative of the core or clad condition.
INSTRUMENT LOOP ACCURACY: 1110F RATIONALE FOR INSTRUMENT LOOP ACCURACY: Accuracy level s have been estabilshed consistent with the capabilities of this type of measuring system which are adequate f or Accident Monitoring.
LOCATION IN PSAR: SECTION 7.5.3.1.2 B.2.E Coolant Level in Reactor CATEGORY 3 PURPOSE: This instrument verifies continuing core cooling capability.
The Inf ormation is used to verify that the sodium level is above the level of the outlet nozzle, and that the core is covered.
RANGE: These wide range Reactor vessel level Instruments measure from 6" above the operating level to 6" below the top of the outlet nozzle.
QCS760.06-7
RATIONALE FOR RANGE: The level range includes the maximum sodium level which is expected f or any event and the lowest level at which primary loop f low can be maintai ned. There is minimum margin however.
Loop flow is the back up indication f or level for this f unction.
INSTRUMENT LOOP ACCURACY: The accuracy of the Instrument channel is i3% of range or 19.5 inches. The Indicator accuracy is 1.1% of range i.1.9 inches.
RATIONALE FOR INSTRUMENT LOOP ACCURACY: Accuracy levels have been established consistent with the capabilities of this type of measuring system which are adequate for accident monitoring.
Loop f low is the back up f or the level.
LOCATION IN PSAR: SECTION 7.5.3.1.1 B.3 TITLE: Maintainina Reactor Coolant System Intearltv (Coolant Inventorv)
B.3.A Coolant Level In Reactor Vessel CATEGORY I PURPOSE: This instrument directly measures Reactor sodium inventory and is used to verify cooling system integrity. The inf ormation is used to verify that the core is covered, that the sodium level is above the level of the outlet nozzle and that the Integrity of the primary heat transport loops is maintained.
c RANGE: These wide range Reactor vessel Instruments measure f rom 6" above the operation level to 6" below the top of the outlet nozzle RATIONALE FOR RANGE: The level range includes the maximum sodium level I
which is expected f or any event and the lowest level at which primary loop flow can be maintained. There is minimum margin however.
INSTRUMENT LOOP ACCURACYr The accuracy of the Instrument channel is l
i3% of range or 19.5 inches. The Indicator accuracy is 11% or range 1.1.9 inches.
RATIONALE FOR INSTRUMENT LOOP ACCURACY: Accuracy levels have been established consistent with the capabilities of this type of measuring system, and are adequate for accident monitoring.
LOCATION IN PSAR: SECTION 7.5.3.1.1 t
QCS760.06-8
1 i
B.3.B Sodium Leaks B.3.B.1.
Sodium Aerosols CATEGORY 3 PURPOSE: These paraneters verify that the saf ety function of the primary sodi um-to-gas pressure boundary Integrity Is maintained.
Absence of sodium aerosols In cells containing primary sodium components provides this verification.
RANGE: Greater than 100 grans/ hour sodium leak RATIONALE FOR RANGE: The lower end of leak detection range is established in PSAR Section 1.6 Reference 2.
Requirements f or leak detection to assure sodium inventory to support core cooling capability and to detect a breach of the boundary to radio-nuclide release are bounded by the 100 gram /hr threshold of detectability. The capability to detect a 100 gran/ hour sodium leak is related to the amount of aerosols the leak generates, dependent on temperature, oxygen, and water concentration, etc. and the concentration in a particular cell, depending on cell size, gas recirculation rate, etc.
INSTRUMENT LOOP ACCURACY: The sensitivity of these instruments is such that they will detect aerosol concentrations greater than 5 x 10-11 grams /cc.
RATIONALE FOR INSTRUMENT LOOP ACCURACY:
Instrument loop accuracy is not applicable to this f unction.
Capability to detect sodium leaks has been demonstrated by experimental data taken f rom small sodium leak tests in an integrated test cell.
Leak detection is provided by an alarm from one or both of two types of aerosol leak detection.
LOCATION IN PSAR: SECTION 7.5.5.11 B. 3. B. 2 Sodlum Particulate Radioactivltv CATEGORY 3 PURPOSE: Particulate radiation monitors are used to detect radioactive sodium aerosol in the atmosphere of inerted cells containing PHTS piping in order to detect a PHTS breach.
RANGER Greater than 100 grans/hr sodium leak RATIONALE FOR RANGE:
Range has been selected so as to detect a concentration of 10-16 grans/cc of Na24 INSTRUMENT LOOP ACCURACYr Accuracy wilI be within a f actor of 2 over the entire range.
RATIONALE FOR INSTRUMENT LOOP ACCURACYr Instrumentation is similar to that used on LWR, accuracy is consistent with Reg. Guide 1.97.
LOCATION IN PSAR:
SECTION 11.4.2.2.6 QCS760.06-9
B.4 TITLE: Maintaining containment / Confinement Integrity B.4.A Containment isolation Automatic Valves Position CATEGORY 2*
Indication PURPOSE: Tnese Indications provide the operator Indication that the containment automatic isolation valves have closed and that the containment isolation f unction is accomplished.
RANGE: Closed /Not Closed RATIONALE FOR RANGE: Not applicable INSTRUMENT LOOP ACCURACY: Not applicablo RATIONALE FOR INSTRUMENT LOOP ACCURACY: Not applicable LOCATION IN PSAR: SECTIONS 9.5.5.1, and 7.3 "The containment Isolation Indication will be Class 1E.
B.4.8 Annulus Pressure CATEGORY 2 PURPOSE: To monitor the containment confinement Integrity, the annulus pressure which is kept sub-atmospheric is being monitored by these i nstruments.
RANGE: 1 15" W. G.
RATIONALE FOR RANGE: The range of these dif ferential pressure Instruments is selected based on the maximum pressure which can be created by annulus cooling f ans (positive), annulus filter and pressure maintenance f ans (negative).
INSTRUMENT LOOP ACCURACY: Within 2.5%
RATIONALE FOR INSTRUMENT LOOP ACCURACY: The accuracy of the instrument Loop is based on the accuracy of its Individual components. Pressure dif ferential transnitters have accuracy within 10.5% and the indicators i 2.0%.
So the overall accuracy of the Instrument loop comes within i 2.5%.
LOCATION IN PSAR: SECTION 7.6 l
QCS760.06-10
TYPE C: Containment of Fission Products Those variables that provide information to indicate the potential for, and/or the actual breach of barriers to fission product releases. The barriers are (1) fuel cladding, (2) primary coolant pressure boundary, and (3) containment.
C.1 IITLE: Fuel and/or Fission Gas-----------to be determined C.2 TITLE: Reactor Coolant Pressure Boundarv (Coolant Inventorv)
C.2.A Coolant Level in Reactor Vessel CATEGORY 1 PURPOSE: This Instrument veriflos cooling system integrity. The information is used to verify that the integrity of the primary heat transport loops is maintained and that the sodium level is above the level of the reactor vessel outlet nozzle.
RANGE: These wide range reactor vessel level instruments measure from 6" above the operating level to 6" below the top of outlet nozzle RATIONALE FOR RANGE: The level range includes the maximum sodium level which is expected for any event and the lowest level at which primary loop flow can be maintained.
There is minimum margin however.
Loop flow is the back up indication for level.
INSTRUMENT LOOP ACCURACY: The accuracy of the Instrument channel is 35 of range or 19.5 inches. The Indicator accuracy is 11% of range or 11.9 inches.
RATIONALE FOR INSTRUMENT LOOP ACCURACY: Accuracy requirements have been established consistent with the capabilities of this type of measuring system.
Loop flow is the back up for the level.
LOCATION IN PSAR: SECTION 7.5.3.1.1 QCS760.06-11
C.2.B Reactor Cover Gas CATEGORY 1 PURPOSE:
The operator uses these data channels to follow the cause of an incident which results in abnormally high cover gas pressure (i.e.
greater than 1/2 psig). The operator monitors these channels to confirm the results of actions taken to limit the rise and reduce the level of the pressure.
Should this pressure increase to more than 7 psig the operator uses this data to confirm that the pressure relief val ves have actuated.
Af ter the incident has been brought under control, these channals provide data throughout the past-incident surveillance period.
RANGE: 0-15 psig RATIONALE FOR RANGE: The range selected covers the f ull design pressure of the Reactor Vessel and provides over 100% margin beyond the value at which the pressure relief valves are set to actuate. Thi s assures that data are available in the very unlikely event that the relief valves actuate at pressures higher than that f or which they are set.
INSTRUMENT LOOP ACCURACY:
10% of Full Scale or i 1.5 psi RATIONALE FOR INSTRUMENT LOOP ACCURACY: These channels are designed primarily to provide Indications of trends rather than to allow precise control of reactor cover gas pressure. The specified accuracy is suf ficient to indicate to the operator that the relief valves have actuated prior to the reactor vessel pressure limit being approached.
LOCATION IN PSAR: To Be Provided later.
l C.2.C Sodium Leaks CATEGORY 3 C.2.C.1 Sodium Aerosols PURPOSE: These parameters verify that the safety function of the primary sodi um-to-gas pressure boundary Integrity is mai ntai ned.
Absence of sodium aerosols in cells containing primary sodium components provides this verification.
I RANGE: Greater than 100 grams / hour sodlum leak RATIONALE FOR RANGE: The lower end of leak detection range is established in PSAR Section 1.6 Ref erence 2.
Requirements f or leak detection to assure sodium Inventory to support core cooling capability and to detect a breach of the boundary to radionuclide release are bounded by the 100 grams / hour threshold of detectability. The capability to detect a 100 grams / hour sodium leak is related to the snount of aerosols the leak generates, dependent on tanperature, QCS760.06-12
oxygen, and water concentration, etc. and the concentration in a particular cell, depending on cell size, gas recirculation rate, etc.
INSTRUMENT LOOP ACCURACY: The sensitivity of these instruments is such that they wil1 detect aerosol concentrations greater than 5 x 10-11 gres/cc.
RATIONALE FOR INSTRUMENT LOOP ACCURACY:
Instrument loop accuracy is not applicable to this f unction. Capability to detect sodium leaks has been demonstrated by experimental data taken f rom smalI sodium leak tests in an Integrated test cell.
Leak detection is provided by an alarm from one or both of two types of aerosol leak detection.
LOCATION IN PSAR: SECTION 7.5.5.11 C.2.C.2 Sodlum Particulate Radioactivity CATEGORY 3 PURPOSE: Particulate radiation monitors are used to detect radioactive sodium aerosol in the atmosphere of inerted celis containing PHTS piping in order to detect a PHTS breach.
RANGE: Greater than 100 gres/ hour sodium leak RATIONALE FOR RANGE: Range has been selected so as to detect a concentration of 10-16 gres/cc of Na24 INSTRUMENT LOOP ACCURACY: Accuracy will be within a f actor of 2 over the entire range.
RATIONALE FOR INSTRUMENT LOOP ACCURACY:
Instrumentation is similar to that used on LWR, accuracy is consistent with Reg. Guide 1.97.
LOCATION IN PSAR: SECTION 11.4.2.2.6 C.2.D Overflow vessel Level CATEGORY 3 l
PURPOSE: This parmeter verifles that the saf ety f unction of the primary sodium boundary integrity Is malntalned. The overfIow vessei i
serves as an expansion tank for the primary sodium system. A loss of I
sodium anywhere in the reactor vessel or PHTS loop would be reflected by low sodium level in this overflow vessel.
RANGE:
0.5 - 17 feet RATIONALE FOR RANGE: The range of this instrument is based on the depth of the overflow vessel.
INSTRUMENT LOOP ACCURACY: +/-5% f ull range with a repeatability of
+/-2.5% fulI range.
QCS760.06-13
RATIONALE FOR INSTRUMENT LOOP ACCURACY: The state-of-the-art capability of hardware has been employed, and these accuracles are satisf actory to allow the operator to detect a signi ficant loss of sodium Inventory.
LOCATION IN PSAR: SECTION 7.6.3.1 l
C.3 TITLE: Containments C.3. A Containment Pressure CATEGORY I j
l PURPOSE: This parmeter provides indication in the Control Room of the pressure Inside the containment above the operating floor and is used to indicate potential for a breach of containment integrity.
RANGE: To 40 psig RATIONALE FOR RANGE: Consistent with RG 1.97 the Instrument range was chosdn to include significant margin over design pressure (15 psig) of the contai nment.
INSTRUMENT LOOP ACCURACX: 12 psig RATIONALE FOR INSTRUMENT LOOP ACCURACY: The instrument loop accuracy supports determination of potential or breach of containment integrity.
LOCATION IN PSAR: SECTION 7.5.9 C.3.B Containment Temoerature (Bulk Atmosobere)
CATEGORY 1 PURPOSE: This permeter provides indication in the Control Room of the atmospheric temperature inside the containment building and is used to indicate challenges to containment integrity.
RANGE: 0 - 3000F RATIONALE FOR RANGE: The Instrument range was chosen to cover maximum containment design temperature plus margin.
INSTRUMENT LOOP ACCURACY: 1500F RATIONALE FOR INSTRUMENT LOOP ACCURACY: The instrument loop accuracy adequately meets accident monitoring requirements allowing the operator to determine challenges to containment integrity.
LOCATION IN PSAR: SECTION 7.5.10 QCS760.06-14
C.3.C Containment Effluent Radioactivity - Noble CATEGORY 2 Gases from Identified Release Points (f.e.
discharge to atmosohere from the containment cleanuo and annulus filtration system)
PURPOSE: Monitoring of the containment ef fluent will verify that the containment cleanup and annulus f ilter systems are perf orming their requred f unctions.
RANGE:
10-6 p. CI/cc to 10-2/4CI/cc RATIONALE FOR RANGE: The lower range approaches the lowest sensitivities commercial ly avail able.
Upper range is 4 decades above l ower.
INSTRUMENT LOOP ACCURACY: Accuracy wil l be within a f actor of 2 over 1he entire range.
RATIONALE FOR INSTRUMENT LOOP ACCURACY:
Instrumentation is similar to that used on LWR, accuracy is consistent with Reg. Guide 1.97.
LOCATION IN PSAR: SECTION 11.3 C.3.D Radiation Exoosure Rate (Inside buildinas CATEGORY 2 or areas. e.g. auxillarv buildinas. annulus, SGB which are in direct contact with orfmarv containment where oenetrations and hatches are located)
PURPOSE: Monitoring of penetrations and hatches will detect a breach of containment at the penetration or hatch.
RANGE:
10-1 R/hr to 104 R/hr RATIONALE FOR RANGE:
1.
Since source term for CRBR is similar to LWR, range is similar to LWR f or similar instruments and is consistent with Reg. Guide 1.97.
2.
Standard commercial ly avail able range.
INSTRUMENT LOOP ACCURACY: Accuracy will be within a f actor of 2 over the entire range.
RATIONALE FOR INSTRUMENT LOOP ACCURACY:
Instrumentation is similar to that used on LWR, accuracy is consistent with Reg. Guide 1.97.
LOCATION IN PSAR: SECTION 12.1 QCS760.06 15
C.3.E Efffuent RadIcact!vity - Noble Gases (from CATEGORY 2 buildings as Indicated In C.3.D above)
PURPOSE:
Indication of breach of containment at the penetration by detecting noble gases in building in direct contact with containment.
RANGE:
10-6pCI/cc to 10-3pCI/cc RATIONALE FOR RANGE: Since source term for CRBR is similar to LWR, range is similar to LWR for similar instruments and consistent with Reg. Gui de 1.97.
INSTRUMENT LOOP ACCURACY: Accuracy wilI be within a factor of 2 over the enti re range.
RATIONALE FOR INSTRUMENT LOOP ACCURACY:
Instrumentation is sim!!ar to that used on LWR, accuracy is consistent with Reg. Guide 1.97.
LOCATION IN PSAR: SECTION 11.3.3.3 TYPE D: Verification of Saf ety System Operation Those variables that provide Information to Indicate the operation of Individual saf ety systems and other systems important to saf ety. These variables are to help the operator make appropriate decisions in using the Individual systems important to safety in mitigating the consequences of an accident.
D.1 TITLE: Decav Heat Removal D.1.A SGHRS D.1.A.1 EWST Level CATEGORY 1 PURPOSE: The PWST level Instrumentation provides the operator with a reading of water Inventory in the PWST. Alarms are provided to alert the operator to low level conditions and allow him to take corrective actions. Minimun level will be required for plant operation to provide adequate emergency supply. The PWST is the primary source of auxiliary feedwater to the SGAHRS. The set point f or minimum PWST inventory corresponds to the PWST water inventory required to complete the 30 day decay heat removal mission.
If the water inventory were allowed to f all below the minimum allowable level during normal plant operation, suf ficient water inventory for the f ull 30 day decay heat removal mission may not be avalIable.
RANGE:
0-162.5" QCS760.06-16
RATIONALE FOR RANGE: This covers all possible water levels in the tank corresponding to the internal disneter of the PWST and envelopes the low level setpoint of signi f icance to plant saf ety.
l_NSTRUMENT LOOP ACCURACY: 11.6 Inches (i1%)
RATIONALE FOR INSTRUMENT LOOP ACCURACY: This accuracy is consistent with commerical ly avail able l evel instrumentation, and exceeds that required f or the operator to determine if the plant has adequate auxiliary feed water Inventory.
LOCATION IN PSAR: To be provided later.
D.I.A.2.A AFW Flow (Turbine Driven Pumo)
CATEGORY 2 PURPOSE: This parsneter provides Indication that the auxiliary f eodwater f l ow is being controlled to permit the SGAHRS to complete its heat removal mission.
PANGE:
0-300,000 ibm /hr RATIONALE FCR RANGE: The instrument range was chosen to cover the f ull range of flow conditions with a 25,000 lbm/ hour margin.
lNSTRUMENT LOOP ACCURACY:
2.8 x 103 lbm/ hour (11%)
RATIONALE FOR INSTRUMENT LOOP ACCURACY: This instrument loop accuracy is more than adequate f or monitoring system perf ormance.
LOCATION IN PSAR: To be provided later.
D.1.A.2.B AFW Flow (Motor Driven Pumos)
CATEGORY 2 PURPOSE: This parameter provides indication that the auxiliary feedwater flow is being controlled to permit the SGAHRS to complete its heat removal mission.
RANGE:
0-300,000 ibm /hr RATIONALE FOR RANGE: This Instrument range was chose to cover the f ull range of flow conditions with a 25,000 lbm/ hour margin.
INSTRUMENT LOOP ACCURACY:
2.8 x 103 lbm/ hour (11%)
RATIONALE FOR INSTRUMENT LOOP ACCURACY: This instrument loop accuracy is more than adequate f or monitoring system perf ormance.
LOCATION IN PSAR: To be provided later.
QCS760.06-17
D.1. A.3 Steam Drum Level CATEGORY 2 PURPOSE: This water level position Indication will allow the operator to verify the proper controlled operation of the auxiliary feedwater supply subsystan.
RANGE: -21 to +16" RATIONALE FOR RANGE: This range covers all trip levels and control setpoints with at least 3 inches margin.
INSTRUMENT LOOP ACCURACY:
01.5 Inches (11.35%)
RATIONALE FOR INSTRUMENT LOOP ACCURACY: This accuracy is sufficient f or the steam drum level control for PPS f unctions and is more than adequate f or monitoring purposes.
LOCATION IN PSAR: SECTION 7.5.2.1.3, Tabl e 7.5-1 D.1. A 4 Steam Drum Pressure CATEGORY 2 PURPOSE: The steam drum pressure is monitored to Indicate proper operation of the Protected Air Cooled Condenser (PACC) and the vent val ves, during decay heat removal operation.
Control of saturated drum pressure determines the heat sink temperature of the IHTS.
RANGE: 0-2500 psig RATIONALE FOR RANGE: This range was chosen to cover the maximum design pressure plus a 10% margin.
.lNSTRUMENT LOOP ACCUR? ICY: 120 psig (1,0.8%)
RATIONALE FOR INSTRUMENT LOOP ACCURACY: This instrument loop accuracy is consistent with the capability of commercially available equipment and was established to provide suf ficient accuracy for PACC and venting control.
It is more than adequate f or monitoring purposes.
LOCATION IN PSAR: SECTION 7.5.11, Tabl e 7.5-1 D.I.A.5 Pumo Discharge Pressure CATEGORY 3 PURPOSE: The AFW pump discharge pressure, along with the pump Inlet pressure, provides the operator with an Indication of pump perf ormance.
RANGE:
0-2200 psig RATIONALE FOR RANGE: This range covers the f ull range of expected pump outlet pressures plus a 160 psi margin.
QCS760.06-18
INSTRUMENT LOOP ACCURACY: 122 psig (11%)
RATIONALE FOR INSTRUMENT LOOP ACCURACY: The instrument accuracy is required for system performance and Is more than adequate for the monitoring funct!on.
LOCATION IN PSAR: To be provided later.
D.I.A.6 Vent valves. Steam Drum Suoerheater CATEGORY 3 PURPOSE: The actual position of the vent valves wili Indicate proper operation of these valves to control steam drum pressure soon af ter shutdown.
Later when the heat load has decreased, PACCS wilI control steam drum pressure and the valves are required to close. The Indication then Indicates that the valves are closed.
RANGE: Open/cl osed RATIONALE FOR RANGE: Not applicable INSTRUMENT LOOP ACCURACY: Not applIcabie RATIONALE FOR INSTRUMENT LOOP ACCURACY: Not applicable LOCATION IN PSAR: To be provided later.
D.1.A.7 Safetv valves.
CATEGORY 3 (Steam Drum. Suoerheater. Evaoorator)
PURPOSE: This valve position Indication will allow the operator to verify the relay valves are closed (in normal operation and following the initial stage of SGAHRS operation) to prevent loss of water inventory.
i RANGE: Open/Cl osed RATIONALE FOR RANGE: Not applicable l
INSTRUMENT LOOP ACCURACY: Not applicable RATIONALE FOR INSTRUMENT LOOP ACCURACY: Not applicable LOCATION IN PSAR: To be provided later.
D.1.A.8 Suoerheater Steam Outlet Isolation Valve CATEGORY 3 PURPOSE: This direct valve posttion indication wIII alIow the operator to verify this valve is open or closed as required for each particular mode of plant operation.
QCS760.06-19
RANGE: Open/ Closed RATIONALE FOR RANGE: Not applicable 4
_I_NSTRUMENT LOOP ACCURACY: Not applicable RATIONALE FOR INSTRUMENT LOOP ACCURACYr Not applicable
_ LOCATION IN PSAR: SECTION 7.5, Figure 7.5-6 D.I.A.9 Feedwater Isolation valves CATEGORY 3 PURPOSE: This yalve position Indication wIlI alIow the operator to verify that these valves are closed or open as required by the plant operati ng mode.
RANGE: Open/ Closed RATIONALE FOR RANGE: Not applicable INSTRUMENT LOOP ACCURACY: Not applicable RATIONALE FOR INSTRUMENT LOOP ACCURACY: Not applicable LOCATION IN PSAR: SECTION 7.5, Figure 7.5-6 l
D.1. A.10 PACC Outlet Water Flow CATEGORY 3 PURPOSE: The PACC outlet flowmeters are used in conjunction with temperature and pressure measurements to provide Indication of PACC performance.
RANGE:
0-100,000 lb/ hour RATIONALE FOR RANGEL This range was established to cover all possible flows with a margin of 10,500 lbm/ hour above the expected flow levels.
l INSTRUMENT LOOP ACCURACY: 11500 lbm/ hour (11.5%)
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RATIONALE FOR INSTRUMENT LOOP ACCURACY: This accuracy is adequate for j
PACC control and is more than adequate for monitoring PACC perf ormance.
LOCATION IN PSAR: To be provided later.
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QCS760.06-20
D.I.A.11 PACC Non-Condensible Vent Valve Position CATEGORY 3 PURPOSE: The direct position Indication of the vent valves will allow the operator to verify that valves are open or closed as required by the speci fic mode of plant operation.
RANGE: Open/ Closed RATIONALE FOR RANGE: Not applicable INSTRUMENT LOOP ACCURACY: Not applicable RATIONALE FOR INSTRUMENT LOOP ACCURACY: Not applicable LOCATION IN PSAR: To be provided later.
D.1. A.12 Evan. (West) Inlet Iso. Valve CATEGORY 3 PURPOSE This valve position Indication provides Information to allow the operator to verify the valve is open or closed as required by the specific plant operating mode.
RANGE: Open/ Closed RAT 10NALE FOR RANGE: Not applIcable INSTRUMENT LOOP ACCURACY: Not applicable RATIONALE FOR INSTRUMENT LOOP ACCURACY: Not applicable LOCATION IN PSAR: To be provided later.
D.1.A.13 Evan. (East) Inlet Iso. Valve CATEGORY 3 PURPOSE: This valve position Indication provides Infortiation to allow the operator to verify that the valve is open or closed as required f or the specific operating mode of the plant.
RANGE: Open/ Closed RATIONALE FOR RANGE: Not applicable INSTRUMENT LOOP ACCURACY: Not applicable RATIONALE FOR INSTRUMENT LOOP ACCURACY: Not applicable LOCATION IN PSAR: To be provided later.
QCS760.06-21
/
D.I.A.14 Recirculation Pumo isolation Valve CATEGORY 3 PURPOSE: This valve position Indicator will allow the operator to verify this valve is either open or closed as required by the specific system operating mode.
RANGE: Open/ Closed RATIONALE FOR RANGER Not applicable INSTRUMENT LOOP ACCURACYr Not applicable RATIONALE FOR INSTRUMENT LOOP ACCURACY: Not applicable LOCATION IN PSAR: SECTION 7.5.2.1.3 D.I.A.15 Rectrc. Pumo Discharge Pressur.g CATEGORY 3 PURPOSE: This pump pressure Indication will allow the operator to verify the performance of the recirculation pump to ensure the ability of the steam generator system to remove heat.
RANGER 0-2700 psig RATIONAL FOR RANGER This range covers the f ull range of operating pressures as welI as a 10% margin above design pressure.
INSTRUMENT LOOP ACCURACYr +27 psig (11%)
EATIONALE FOR INSTRUMENT LOOP ACCURACY: The accuracy is within capabilities of commercially available Instrumentation and exceeds that required to allow the operator to determine recirculation pump performance.
LOCATf0N IN PSAR: To be provided later.
D. I. A.16 Steam Drum Drafn Valve Position CATEGORY 3 PURPOSE: This valve position Indication will allow the operator to verify these valves are open or closed as required by the specific plant operating condition.
RANGE: Open/ Closed RATIONALE FOR RANGE: Not applicable
_lfl1TRUMENT LOOP ACCURACY: Not applIcabIe RATIONALE FOR INSTRUMENT LOOP ACCURACY: Not applicable
_ LOCATION IN PSAR: SECTION 7.5.2.1.3 and Fig. 7.5.6 QCS760.06-22
D. I. A.17 Rectre. Pumo Bvoass Valves Position CATEGr';Y 3 PURPOSE: This valve position Indication will allow the operator to verify these valves are either closed or open as required by the specific system operating mode.
RANGE: Open/ Closed RATIONALE FOR RANGE: Not applicable INSTRUMENT LOOP ACCURACY: Not applicable RATIONALE FOR INSTRUMENT tOOP ACCURACY: Not applicable LOCATION IN PSAR: SECTION 7.5, Figure 7.5-6 0.1.A.18 Suoerheater Bvoass Valves CATEGORY 3 PURPOSE: This valve position Indication will allow the operator to verify this valve is closed or open as required for the specific system operation mode.
RANGE: Open/ Closed RATIONALE FOR RANGE: Not applicable INSTRUMENT LOOP ACCURACY: Not applicable RATIONALE FOR INSTRUMENT LOOP ACCURACY: Not applicable LOCATION IN PSAR: To be provided later.
D.1.A.19 Suoerheater inlet isolation Valve CATEGORY 3 PURPOSE: This valve position Indication will allow the operator to verify this valve is open or closed as required f or the specific system operati ng mode.
RANGE: Open/Cl osed RATIONALE FOR RANGE: Not applicable INSTRUMENT LOOP ACCURACYr Not applicable RATIONALE FOR INSTRUMENT LOOP ACCURACY: Not applicable LOCATION IN PSAR: SECTION 7.5.6.1.2, Figure 7.5-6 QCS760.06-23
D.I.B HTS Loops D.I.B.1 Pony Motor Soeed PHTS CATEGORY 3 PURPOSE: This parameter verifles that a portion of the heat removal train is operating. The PHTS Pony Motor is used to maintain forced convection in the PHTS during the shutdown heat removal mission.
RANGE: 0-120 rpm RATIONALE FOR RANGE: The pony motor operates in one of six discrete speeds on a " selection" basis, the highest of which is 115 rpm.
INSTRUMENT LOOP ACCURACY: 14 rpm (13% of the 120 rpm span)
RATIONALE FOR INSTRUMENT LOOP ACCURACY: The selection of this accuracy is based on the state-of-the-art capability for the equipment and is adequate for monitoring pump operation.
LOCATION IN PSAR: SECT ION 7.5.2.1.2, Tabl e 7.5-1 D.I.B.2 Pony Motor Soeed lHTS CATEGORY 3 PURPOSE: This parameter verifles that a portion of the heat removal train is operating.
The IHTS Pony Motor is used to maintain forced convection in the IHTS during the shutdown heat removal mission.
BANGE: 0-120 rpm RATIONALE FOR RANGE: The pony motor operates in one of six discrete speeds on a " selection" basis, the highest of which is 115 rpm.
INSTRUMENT LOOP ACCURACY: 14 rpm (13% of the 120 rpm span)
RATIONALE FOR INSTRUMENT LOOP ACCURACY: The selection of this accuracy is based on the state-of-the-art capability for the equipment and is adequate for monitoring pump operation.
LOCATION IN PSAR: SECTION 7.5.2.1.2, Tabl e 7.5-1 D.I.B.3 lHTS IHX Na Outlet Temnerature CATEGORY 3 PURPOSE: The IHX outlet temperature provides the operator with direct Indication of reactor heat removal and verifles core cooling.
During reactor operation and following reactor shutdown this parameter, combined with the PHTS hot leg temperature, provides the T across the IHX, this AT is an Indication of PHTS heat rejection.
R3272@,@@-24
RANGE: 300o - 1100oF RATIONALE FOR RANGE: This range was selected to provide capability to monitor all anticipated normal and of f-normal conditions with margin.
INSTRUMENT LOOP ACCURACY: i 3.1%
RATIONALE FOR INSTRUMENT LOOP ACCURACY: This is based on the highest accuracy commercially available with reliable instrumentation and is adequate f or accident monitoring.
LOCATION IN PSAR: SECTION 7.5.2.1.1, 7.5.3.1.2, Tabl e 7.5-1 D.I.B.4 Evanorator Na Outlet Temoerature CATEGORY 3 PURPOSE: This temperature Indication verifles to the operator heat rejection through the steam generator system.
RANGE: 3000 - 8000F RATIONALE FOR RANGE: This range was chosen to monitor the f ull range of anticipated temperatures.
INSTRUMENT LOOP ACCURACY: 1100F (25 of span)
RATIONALE FOR INSTRUMENT LOOP ACCURACY: This accuracy was chosen to meet the needs of the Plant Protection System and is adequate for accident monitoring.
LOCATION IN PSAR: SECTION 7.5.2.1.1, Tabl e 7.5-1 0.1.B.5 PHTS Flow CATEGORY 3 PURPOSE: The PHTS flow provides a direct verification of the capability to cool the reactor, t
RANGE: -1500 TO +6000 GPM RATIONALE FOR RANGER This range was chosen to cover the flow rate while operating on pony motors or natural circulation. The reverse flow measurement covers the use of 2 pony motors operating and the 3rd pump I dl e.
INSTRUMENT LOOP ACCURACY:.16.1%
RATION /.LE FOR INSTRUMENT LOOP ACCURACY: This is based on the state-of-tie-art accuracy available f or this type of Instrumentation, and is adequate f or this accident monitoring f unction.
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LOCATION IN PSAR: SECTION 7.2.1.2, 7.5.2.1.1 i
QcS760.06-25
D.1.B.6 IHTS Flow CATEGORY 3 PURPOSEr This inf ormation provides verification of IHTS operation and accordingly capability to cool the reactor.
RANGE:
0 to +6000 gpm RATIONALE FOR RANGE: This range was chosen to cover the flow rates while operating on pony motors or on natural circulation.
INSTRUMENT LOOP ACCURACY: 1 7% of span RATIONALE FOR INSTRUMENT LOOP ACCURACY: This accuracy is based on the state-of-the-art accuracy available f or this type of instrument and is adequate for monitoring lHTS fIow.
LOCATION IN PSAR: SECTION 7.5.2.1.1 and Tabl e 7.5.1 D.2 TITLE: Direct Heat Removal Service (DHRS)/EVST Coolina D.2.A OHX Sodlum Outlet Temnerature CATEGORY 3 PURPOSE: This parameter verifles that the direct heat removal service (DHRS) is f unctioning properly, i.e. that the sodium returning to the reactor has been cooled.
RANGE: 32-12000F RATIONALE FOR RANGE: This range is based on the maximum temperature expected plus a minimum of 10% margin.
_lNSTRUMENT LOOP ACCURACY: 11% of fuli range RATIONALE FOR INSTRUMENT LOOP ACCURACY: This accuracy is based on that of commerical grade instrumentation and is satisf actory for accident monitoring purposes.
LOCATION IN PSAR: SECTION 7.6.3.1 D.2.8 Overflow Vessel Level CATEGORY 3 PURPOSE: This parameter verifles suf ficiency sodium Inventory which is necessary for the continuing availabilliy of DHRS.
RANGE:
0.5-17 f t QCS760.06-26
RATIONALE FOR RANGE: The range of this Instrument is based on the depth of the overflow vessel.
.lNSTRUMENT LOOP ACCURACY: 15% fulI range RATIONALE FOR INSTRUMENT LOOP ACCURACY: This is the best accuracy attainable with state-of-the-art instrumentation and is adequate for accident monitoring.
_ LOCATION IN PSAR: SECTION 7.6.3.1 D.2.C Reactor Overflow Temnerature CATEGORY 3 PUPPOSE: This parameter verifles that the direct heat removal service (DHRS) is f unctioning properly, i.e. that heat energy is being removed f rom the reactor.
RANGE: 32-15000F RATIONALE FOR RANGE: The range of thIs instrument Is based on the maximum temperature expected plus a minimum of 10% margin.
INSTRUMENT LOOP ACCURACY: 11% of fulI range.
RATIONALE FOR INSTRUMENT LOOP ACCURACY: This accuracy Is based on that of commerical grade instrumentation and is satisf actory for accident monitoring purposes.
LOCATION IN PSAR: SECTION 7.6.3.1 D.2.D Primarv Makeuo Flow CATEGORY 3 PURPOSE: Verify that the direct heat removal service (DHRS) is f unctioning properly, i.e. that the sodium makeup pumps are providing the requi red f Iow.
RANGE:
0-500 gpm RATIONALE FOR RANGE: This range is based on the maximum flow expected plus a minimum of 10% margin.
INSTRUMENT LOOP ACCURACY: 13% of fulI range.
RATIONALE FOR INSTRUMENT LOOP ACCURACY: Ths accuracy is based on that of commerical grade instrumentation and is satisf actory for accident monitoring purposes.
LOCATION IN PSAR: SECTION 7.6.3.1 QCS760.06-27
0.2.E OHX NaK Outlet Temnerature CATEGORY 3 PURPOSE: This parameter verifles that the direct heat romoval service (DHRS) is f unctioning properly, i.e. that NaK returning f rom the ABHX has been cooled.
RANGE: 32-12000F RATIONALE FOR RANGE: This range is based on the maximum temperatures expected plus a minimum of 10% margin.
INSTRUMENT LOOP ACCURACY: 11% of fulI range.
RATIONALE FOR INSTRUMENT LOOP ACCURACY: This accuracy is based on that of commerical grade instrumentation and is satisf actory for accident monitoring purposes.
LOCATION IN PSAR: SECT ION 7.6.3.1 D.2.F OHX NaK inlet Temnerature CATEGORY 3 PURPOSE: This paraneter verifles that the direct heat renovel service (DHRS) is f unctioning properly, i.e. that NaK returning from the OHX is transf erring heat f rom the primary sodium makeup loop.
RANGE: 32-12000F RATIONALE FOR RANGE: This range is based on the maximum temperature expected plus a minimum of 10% margin.
INSTRUMENT LOOP ACCURACY: i1% of fulI range.
RATIONALE FOR INSTRUMENT LOOP ACCURACY: This accuracy is based on that of commerical grade Instrumentation and is satisf actory for accident monitoring purposes.
LOCATION IN PSAR: SECTION 7.6.3.1 D.2.G OHX NaK Flew CATEGORY 3 PURPOSE: This instrumentation verifles that the direct heat removal service (DHRS) is f unctioning properly, i.e. that the EVST NaK pumps are providing the required flow.
RANGE:
0-500 gpm QCS760.06-28
RATIONALE FOR RANGE: This range is based on the maximum flow expected plus a minimum of 10% margin.
INSTRUMENT LOOP ACCURACY: 13% of fulI range.
RATIONALE FOR INSTRUMENT LOOP ACCURACY: This accuracy is based on that of commerical grade Instrumentation and is satisf actory for accident monitoring purposes.
LOCATION IN PSAR: SECTION 7.6.3.1 D.2.H EVST Outlet Temocrature CATEGORY 2 PURPOSE: This paraneter verifles that the EYST direct heat removal service is f unctioning properly, i.e. that EVST design temperatures are not exceeded and to record the samo.
RANGE: 32-12000F RATIONALE FOR RANGE: This range is based on the maximum temperature expected plus a minimum of 10% margin.
_lNSTRUMENT LOOP ACCURACY: 11% of full range.
RATIONALE FOR INSTRUMENT LOOP ACCURACY: This accuracy is based on that of commerical grade Instrumentation and is satisf actory for accident monitoring purposes.
LOCATION IN PSAR: SECTION 7.6.3.1 D.2.1 EVST Level CATEGORY 3 PURPOSE: This parameter verifles thai the sodium is at a safe level (fuel is covered and sodium nozzles are covered enabling f orced or natural convection in the EVST cooling system to remove decay heat).
RANGE:
25-37 f t RATIONALE FOR RANGE: The rationale is based on the need to measure f rom the l owest sodi um l evel in the EVST (corresponding to EYST leak into guard vessel) to the highest safe level plus a minimum of 10%
nergin.
INSTRUMENT LOOP ACCURACY: 15% of full range RATIONALE FOR INSTRUMENT LOOP ACCURACY: This accuracy is based on state-of-the-art instrumentation and is satisf actory for accident monitoring purposes.
LOCATION IN PSAR: SECTION 7.6.3.1 QCS760.06-29
D.2.J EVST Na Flow CATEGORY 2 PURPOSE: This parameter verifles that the EVST direct heat removal service is f unctioning properly, i.e. that the EYST Na pumps are providing the required flow to the Na/NaK cooler.
RANGE:
0-500 GPM RATIONALE FOR RANGE: This range is based on the maximum flow expected plus a minimum of 10% margin.
INSTRUMENT LOOP ACCURACY: 13% of full range.
RATIONALE FOR INSTRUMENT LOOP ACCURACY: This accuracy is based on that of commercial grade instrumentation and is satisf actory for accident monitoring purposes.
LOCATION IN PSAR: SECTION 7.6.3.1 D.2.K Reactor Vessel Level CATEGORY 3 PURPOSE: This Instrument verifles sodium inventory in the reactor vessel which is necessary for continuing availabilI+ of DHRS.
RANGE: These wide range reactor vessel Instruments measure f rom 6" above operating level to 6" below the top of the outlet nozzle.
RATIONALE FOR RANGE: The level range includes the maximum sodium level which is expected f or any event and the lowest level at which primary loop flow can be maintained.
INSTRUMENT LOOP ACCURACY: The accuracy of the instrument channel is 15% of range or 19.5 Inches.
The indicator accuracy is 1,1% of range or 1.1.9 inches.
RATIONALE FOR INSTRUMENT LOOP ACCURACY: Accuracy requirements have been established consistent with the capabilities of this type of measuring system.
Loop f low is the back up f or the level.
LOCATION IN PSAR: SECTION 7.5.3.1.1 (to be revised to address the above).
QCS760.06-30
D.2.L Sodium Side Valve Indication D.2.L.1 Cold Tran isol ation (81-PP-HV-109)
CATEGORY 3 PURPOSE: This Indication provides Inf ormation with respect to this valve being open or closed, its purpose is to verify that the direct heat removal service (DHRS) system is f unctioning properly, i.e. that this valve is aligned as required to enable the proper coolant flow.
RANGE: Open/ Closed RATIONALE FOR RANGE: Not applIcabie INSTRUMENT LOOP ACCURACY: Not applicable RATIONALE FOR INSTRUMENT LOOP ACCURACY: Not applicable LOCATION IN PSAR: SECTION 7.6.3.1 0.2.L.2 OHX Bvoass (82-PP-HV-102)
CATEGORY 3 PURPOSE: This inf ormation provides indication with respect to the valve being open or closed, its purpose is to verify that the direct heat renoval service (DHRS) system is f unctioning properly, i.e. that this valve is aligned as required to enable the proper coolant flow.
RANGE: Open/Cl osed RATIONALE FOR RANGE: Not applicable INSTRUMENT LOOP ACCURACY: Not applicable RATIONALE FOR INSTRUMENT LOOP ACCURACY: Not applicable LOCATION IN PSAR: SECTION 7.6.3.1 D.2.L.3 OHX Inlet Valve (81-PP-HV-103)
CATEGORY 3 PURPOSE: This Inf ormation provides indication with respect to the valve being open or closed.
Its purpose is to verify that the direct heat removal service (DHRS) system is f unctioning properly, i.e. that this valve is aligned as required to enable the proper coolant flow.
RANGE: Open/ Closed RATIONALE FOR RANGE: Not appiicabie INSTRUMENT LOOP ACCURACY: Not applicable RATIONALE FOR INSTRUMENT LOOP ACCURACY: Not applicable LOCATION IN PSAR: SECTION 7.6.3.1 QCS760.06-31
D.2.M NaK Side Valve Indication D.2.M.1 EVST/DHRS Crossover Valve (82-EPHV-415)
CATEGORY 3 F' RPOSE: This provides indication of the valve being open or closed.
J its purpose is to verify that the direct heat renoval service (DHRS) system is able to f unction properly, i.e. that this valve is aligned as required to enable the proper coolant flow.
RANGE: Open/ Closed RATIONALE FOR RANGE: Not applicable INSTRUMENT LOOP ACCURACY: Not applicable RATIONALE FOR INSTRUMENT LOOP ACCURACY: Not applicable LOCATION IN PSAR: SECTION 7.6.3.1 D.2.M.2 EVST/DHRS Crossover Valve (81-EPHV-416)
CATEGORY 3 PURPOSE: This provides indication of the valve being open or closed.
its purpose is to verify that the direct heat renoval service (DHRS) system is able to f unction properly, i.e. that this valve is aligned as required to enable the proper coolant flow.
RANGE: Open/ Closed RATIONALE FOR RANGE: Not applicable INSTRUMENT LOOP ACCURACY: Not applicable RATIONALE FOR INSTRUMEN7 LOOP ACCURACY: Not applicable LOCATION IN PjiAB: SECTION 7.6.3.1 D.2.M.3 EVST/DHRS Crossover Valve (81-EPHV-357)
CATEGORY 3 PURPOSE: This provides Indication of the valve being open or closed.
its purpose is to verify that the direct heat removal service (DHRS) system is able to f unction properly, i.e. that this valve is aligned as required to enable the proper coolant flow.
RANGE: Open/ Closed RATIONALE FOR RANGE: Not applicable QCS760.06-32
INSTRUMENT LOOP ACCURACY: Not applIcabIe RATIONALE FOR INSTRUMENT LOOP ACCURACY: Not applicable LOCATION IN PSAR: SECTION 7.6.3.1 D.2.M.4 EVST/DHRS Crossover Valve (81-EPHV-358)
CATEGORY 3 PURPOSE: This provides Indication of the valve being open or closed.
Its purpose is to verify that the direct heat removal service (DHRS) system is able to f unction properly, i.e. that this valve is aligned as required to enable the proper coolant flow.
RANGE: Open/Cl osed RATlONALE FOR RANGE: Not applicable
_lNSTRUMENT LOOP ACCURACY: Not applIcabl e RATIONALE FOR INSTRUMENT LOOP ACCURACY: Not applicable LOCATION IN PSAR: SECTION 7.6.3.1 D.2.M.5 EVST/DHRS Crossover Valve (81-EPHV-359)
CATEGORY 3 PURPOSE: This provides Indication of the valve being open or closed, its purpose is to verify that the direct heat renovel service (DHRS) system is able to f unction properly, i.e. that this valve is aligned as required to enable the proper coolant flow.
RANGE: Open/ Closed RATIONALE FOR RANGE: Not applicable INSTRUMENT LOOP ACCURACY: Not applIcabie RATIONALE FOR INSTRUMENT LOOP ACCURACY: Not applicable LOCATION IN PSAR: SECTION 7.6.3.1 D.2.M.6 EVST/DHRS Crossover Valve (81-EPHV-420)
CATEGORY 3 PURPOSE: This provides Indication of the valve being open or closed.
Its purpose is to verify that the direct heat removal service (DHRS) system is able to f unction properly, i.e. that this valve is aligned as required to enable the proper coolant flow.
QCS760.06-33
RANGE: Open/ Closed RATIONALE FOR RANGE: Not applicable INSTRUMENT LOOP ACCURACY: N3 applicabl e RATIONALE FOR INSTRUMENT LOOF ACCURACY: Not applicable LOCATION IN PSAR: SECTION 7.6.3.1 D.3 TITLE: CooIIng Water System D.3.A Emergenev ChiIled Water Temeerature CATEGORY 2 PURPOSE:
Indication of the Emerg. Chilled Water Chiller inlet & outlet temps. Is necessary for evaluation of ECW chillers performance, ef ficiency & ability to f ulfill plant heat removal requirements; Low ef fIciency of ECW Chi lIers wIII impalr the operation of Emerg. Recirc.
Gas Cooling system, Fuel Handling System, Emerg. HVAC System & certain Radiation Monitoring equipment.
RANGE: 300F to 800F RATIONALE FOR RANGE: The instrument range of 300-800F is provided on the basis of normal (420F) and high (650F) operating conditions and 25%
downscale and upscale margin.
INSTRUMENT LOOP ACCURACY: Accuracy of the loop is within 16% of the 500F span.
RATIONALE FOR INSTRUMENT LOOP ACCURACY: The accuracy of the loop is based on the accuracy of its individual market available components.
The loop consists of thermocoupie (a =t).5% for 50 F span) temperature t
transmitter (a =10.5%) and panel electronic temperature Indicator 2
(a =12%).
3 LOCATION IN PSAR: SECTION 9.7.2 - Emergency Chil led Water System (being rewritten)
D.3.B Emergency Chilled Water Pressure CATEGORY 2 PURPOSE:
Indication of the Emerg. Chilled Water Chiller discharge pressure is necessary for evaluation of ECW ci rc. pumps' perf ormance, system piping tightness & pressure operating conditions. The low discharge pressure will Indicate ECW pump or piping f ailure, & will Impair the ability of Emerg. Chilled Water System for plant heat removal.
QCS760.06-34
RANGE:
0-220 psig RATIONALE FOR RANGE: The Instrument range of 0-220 psig is provided on the basis of ECW chiller discharge pressure normal (110 psig) and high (180 psig) operating conditions, and 20% upscale margin.
INSTRUMENT LOOP ACCURACY: The accuracy of the loop is within 12.5% of 220 psig span.
PATIONALE FOR INSTRUMENT LOOP ACCURACY: The accuracy of the loop is based on the accuracy of its market available components. The loop consists of electronic pressure transmitter (a.g,o,5%) and panel j
electronic pressure indicator (a =2%).
2 LOCATION IN PSAR: SECTION 9.7.2 - Emergency Chilled Water System D.3.C Emergency Chi lIed Water FIow CATEGORY 2 PURPOSE:
Indication of Emerg. Chilled Water flow thru chillers is necessary for the evaluation of ECW Circ. Pumps' performance and systern fIow operating conditions. The Iow fIow of Emerg. Chi lIed Water wIII trip Emerg. Chiller & disable the ECW System which is required f or plant heat removal operation.
RANGE: 0-2000 gpm RATIONALE FOR RANGE: The instrument range of 0-2000 gpm is provided on the basis of normal (1250 gpm) and high (1600) flow operating conditions and approximately 20% upscale margin.
INSTRUMENT LOOP ACCURACY: Accuracy of the loop is within i3.5% of the 2000 gpm span.
PATIONALE FOR INSTRUMENT LOOP ACCURACY: The accuracy of the loop is based on the accuracy of its individual market available components.
The Ioop consists of orifice wIth fIange taps (a 0.5%) eiectrontc j.
flow transmitter (a =0.5%) and panel electronic flow Indicator 2
(a.fyg).
j 3
I LOCATION IN PSAR: SECTION 9.7.2 - Emergency Chil led Water System (bei ng rewritten).
D.3.D Emeroencv ChlIled Water Recir. Pumo Status CATEGORY 3
(
PURPOSE: Emergency Chilled Water System pump status is used for assessing operation of Emergency Recirculation Gas Cooling Systems, Fuel Handling Systems, Emergency HVAC Systems, end certain Radiation Monitoring equipment.
QCS760.06-35 l
RANGE: Run/Not Run RATIONALE FOR RANGE: N/A INSTRUMENT LOOP ACCURACY: N/A RATIONALE FOR INSTRUMENT LOOP ACCURACY: N/A LOCATION IN PSAR: To be provided later.
D.3. E Emergency Chiller Status CATEGORY 3 PURPOSE: Emergency Chilled Water System chiller status indicates operation of Emergency Recirculation Gas Cooling Systems, Fuel Handling Systems, Emergency HVAC Systems, and certain Radiation Monitoring eq ui pment.
RANGE: Run/Not Run RATIONALE FOR RANGE: N/A INSTRUMENT LOOP ACCURACY: N/A RATIONALE FOR INSTRUMENT LOOP ACCURACY: N/A LOCATION IN PSAR: To be provided later.
D. 3. F Emergency Chilled Water Exo. Tank Level CATEGORY 3 PURPOSE:
Indication of Emergency Chilled Water Expansion Tank level allows proper evaluation of systems operating and leakage conditions.
ECW Expansion Tank Low-Low Level signal trips ECW Recirculation Pump and disables Emergency Chilled Water System impairing plant heat removal operation.
RANGE: 0-100 inches.
RATIONALE FOR RANGE: The Instrument range 0-100" is provided on the basis of ECW Expansion Tank height.
INSTRUMENT LOOP ACCURACY: The accuracy of the loop is within i2.5% of the span.
RATIONALE FOR INSTRUMENT LOOP ACCURACY: The accuracy of the loop is based on the accuracy of its individual market available components.
The 1oop consists of the electronic Ievel transmitter (a =i,0.5%) and j
panel electronic level Indicator (a2 = 12%).
LOCATION IN PSAR: SECTION 9.7.2 - Emergency Chilled Water System (being rewritten)
QCS760.06-36
D.3.G Exoansion Tank Isolation Valve Positica CATEGORY 3 PURPOSE: Emergency Chilled Water System expansion status indicates operation of Emergency Recirculation Gas Cooling Systems, Fuel Handling Systems, Emergency HVAC Systems, and certain Radiation Monitoring equipment.
RANGE: Open/Not Open RATIONALE FOR RANGE: N/A INSTRUMENT LOOP ACCURACY: N/A RATIONALE FOR INSTRUMENT LOOP ACCURACY: N/A LOCATION IN PSAR: To be provided later.
D. 3. H Emergency Plant Service Water Suoolv Temoerature CATEGORY 2 PURPOSE:
Indication of Emergency Plant Service Water supply header temperature is used f or evaluation of Emergency Water Cooling System heat removal capabilities.
RANGE: 30-1300F RATIONALE FOR RANGE: The Instrument range of 30-1300F is provided on the basis of normal (900F), low (450F) high (1100F), operating conditions and 20% upscale and downscale margin.
INSTRUMENT LOOP ACCURACY: The accuracy of the loop is within 1.4.3% of 1000F span.
RATIONALE FOR INSTRUMENT LOOP ACCURACY: The accuracy of the loop is based on the accuracy of its Individual market available components.
The loop consists of thermocouple (a
,1.8% of 100%F span), electronic j
temperature transmitter (a =.0.5%) and panel electronic Indicator 2
(i2%).
LOCATION IN PSAR: SECTION 9.9.2 - Emergency Plant Service Water System D.3.1 Emergency Plant Service Water Flow CATEGORY 2 PURPOSE:
Indication of Emergency Plant Service Water flow through the chillers is used f or evaluation of Emergency Chilled Water Systems operation capabilities.
RANGE:
0-2500 gpm QCS760.06-37
RATIONALE FOR RANGE: The instrument range of 0-2500 gpm is provided on the basis of normal (2000 gpm) and high (2100 gpm) operating conditions, and 20% upscale margin.
INSTRUMENT LOOP ACCURACY: The accracy of the loop is within i3 5% of 2500 gpm span.
RATIONALE FOR INSTRUMENT LOOP ACCURACY: The accuracy of the loop is based on the accuracy of its individual market available components.
The loop consists of orifice with flange tops (a =10.5%), electronic t
flow transmitter (a =0.5%) and panel electronic flow Indicator 2
(83=12%).
LOCATION IN PSAR: SECTION 9.9.2 - Emergency Plant Service Water System D. 3. J Emergency Plant Service Water Basin Level CATEGORY 2 PURPOSE:
Indication of Emergency Cooling Tower Water Storage Basin l evel is used f or evaluation of EPSW reserve storage capacity and Cooling Water System operation capabilities.
RANGE: 0-100%
RATIONALE FOR RANGE: The Instrument range El. 771'-816' is based on the storage basin bottom (El. 771') and top (816') elevation.
INSTRUMENT LOOP ACCURACY: The accuracy of the loop is within 13% of 45 foot span.
RATIONALE FOR INSTRUMENT LOOP ACCURACY: The accuracy of loop is based on the accuracy of its individual market available components. The loop consists of the electronic level transmitter (a =t1%) and panel t
electronic level indicator (a *i2%).
2 LOCATION IN PSAR: SECTICt. 9.9.2 - Emergency Plant Service Water System D.3.K Emergency Plant Service Water Pit Level CATEGORY 2 PURPO*":
Indication of Emergency Plant Service Water pump pit level allows f or evaluation of EPSW pump operation conditions and Cooling Water System operation capabilities.
RANGE:
0-100%
RATIONALE FOR RANGE: The Instrument range El. 810' - 821 ' f t. Is based on pump pit bottom (el. 810') and top (821') elevation.
QCS760.06-38
INSTRUMENT LOOP ACCURACY: The accuracy of the 1oop is wIthin 13% of 11 foot span.
RATIONALE FOR INSTRUMENT LOOP ACCURACY: The accuracy of the loop is based on the accuracy of its individual market available components.
The loop consists of the electronic level transmitter (aAl%) and panel electronic level indicator (a d I)-
2 LOCATION IN PSAR: SECTION 9.9.2 - Emergency Plant Service Water System D. 3. L Emergency Plant Service Water Pumo Status CATEGORY 3 PUPPOSE: Emergency Plant Service Water flow status indicates proper operation of Emergency Chilled Water System, and cooling of the Diesel Generator Systans.
PANGE: N/A RATIONALE FOR RANGE: N/A INSTRUMENT LOOP ACCURACY: N/A RATIONALE FOR INSTRUMENT LOOP ACCURACY: N/A LOCATION IN PSAR: To be provided later.
D.3.M Emeraency Cooling Water Status CATEGORY 3 PURPOSE:
Indication of Emergency Cooling Fan Status is used for evaluation of Emergency Water Cooling System heat removal capabilities.
RANGE: Run/Not Run RATIONALE FOR RANGE: N/A INSTRUMENT LOOP ACCURACY: N/A l
RATIONALE FOR INSTRUMENT LOOP ACCURACY: N/A LOCATION IN PSAR: To be provided later.
l l
QCS760.06-39
D.4 TITLE: Power Sunolles D.4. A.1 fjar+rical Voltage (1 E Inst.)
CATEGORY 2 PURPOSE:
Indication system status by indicating the voltage levels at 4.16KV switchgear and the diesel generators and undervoltage conditions at 480V switchgear, 125/250V DC switchgear and 120/208V uninterruptible power supplies. This inf ormation is necessary to indicate whether system voltage is adequate f or the operation of plant electrical loads.
RANGE: As discussed below RATIONALE FOR RANGE:
Instrument range is selected to provide readings f rom zero to nominal vol tage rati ng (e.g., 4.16KY, range i s 0-5000 volts) using commercially available scales.
INSTRUMENT LOOP ACCURACY: Accuracy within 1.8% for 4.16KY, diesel generators, 0.3% f or 480V switchgear, 0.0% for DC and UPS RATIONALE FOR INSTRUMENT LOOP ACCURACY: The accuracy of the loop is based on the accuracy of its individual components, instruments f or medium voltage switchgear consist of a potential transformer (0.3%), a transducer (0.5%) and a vol tmeter (1.0%) for a combined accuracy of w i th i n 11.8%.
Low voltage switchgear (480V) utilize a potential transf ormer (0.3%), an undervoltage relay (fleid adjusted to correct setpoint) and an annunciator to inoicate undervoltage conditions.
DC and UPS systems use an undervoltage relay and an annunciator.
LOCATION IN PSAR: SECTIONS 8.3.1.1.2, 8.3.1.1.5 and 8.3.2.1.1.1 and Figures 8.3-2, 8.3-3 and 8.3-5.
D.4. A.2 Electrical Voltage (Non IEl CATEGORY 3 PURPOSE:
Indicate a system status by indicating the voltage levels at 13.8KV switchgear and 4.16KV switchgear and undervoltage conditions at 480V switchgear, 125/250V DC switchgear and 120/208V uninterruptible power supplies. This Information is necessary to indicate whether system voltage is adequate f or the operation of plant electrical loads.
RANGE: As discussed below.
RATIONALE FOR RANGE:
Instrument range is selected to provide readings f rom zero to the nominal voltage rating (e.g., 4.16KV, range is 0-5000 volts) using commercially available scales.
INSTRUMENT LOOP ACCURACY: Accuracy within 1.8% for 13.8KY 0.3% for 480V switchgear 0.0% for DC and UPS RATIONALE FOR INSTRUMENT LOOP ACCURACY: The accuracy of the loop is based on the accuracy of its individual components.
Instruments f or QCS760.06-40
medium voltage switchgear (13.8KV, 4.16KV) consist of a potential transformer (0.3%), a transducer (0.5%) and a voltmeter (1.0%) f or a omnbined accuracy of within 1.1.8%.
Low voltage switchgear (480V) utilize a potential transf ormer (0.3%), and undervoltage relay (fleid adjusted to correct setpoint) and an annunciator to Indicate undervoltage conditions.
DC and UPS systems use an undervoltage relay and an annunciator.
LOCATION IN PSAR: SECTION 8.3.2.1.2 and Figure 8.3-2 and 8.3-4.
D.4.B.1 Electrical Current (1E Inst.)
CATEGORY 2 PURPOSE:
Indicate system status by indicating the ampere load of medium voltage switchgear, medium voltage loads, 480V unit substations and DC batteries and battery chargers.
RANGE: As discussed below RATIONALE FOR RANGE:
Instrument range is selected to provide adequate ampere readings f rom zero to normal fuel load current using commercially available scales.
Ammeter scales f or batteries are selected to Indicate load and charging current (e.g., 800 800)
INSTRUMENT LOOP ACCURACY:
Accuracy within 1.8 - 2.1% for medium voltage switchgear 1.8 - 2.7% for 480V unit substations 1.0% for DC batteries & battery chargers RATIONALE FOR INSTRUMENT LOOP ACCURACY: The accuracy of the loop is based on the accuracy of its individual components.
Instruments f or medium and low voltage switchgear consist of a current transformer (CT)
(0.3 to 1.2%), a transducer (0.5%) and an anmeter (1.0%) for a canbined accuracy of 1.8% to 2.7% depending on CT ratio.
The accuracy of DC Instruments is based on the anmeter itsel f.
LOCAT!ON IN PSAR: Figures 8.3-2, 8.3-3, 8.3-5 i
l l
D.4.B.2 Electrical Current (Non 1E Inst.)
CATEGORY 3 t
l PURPOSE:
Indicate system status by Indicating the ampere load of medium voltage switchgear, medium voltage loads, 480V unit substations and DC batteries and battery chargers.
I RANGE: As discussed below.
RATIONALE FOR RANGE:
Instrument range is selected to provide adequate ampere readings f rom zero to normal full load current using commercially available scales.
Ammeter scales f or batteries are l
selected to Indicate load and charging current (e.g., 800 800) l QCs760.06-41
INSTRUMENT LOOP ACCURACY:
Accuracy within 1.8 - 2.1% for medium voltage switchgear 1.8 - 2.7% for 480V unit substations 1.0% for DC batteries & battery chargers RATIONALE FOR INSTRUMENT LOOP ACCURACY: The accuracy of the loop is based on the accuracy of its Individual components, instruments f or medium and low voltage switchgear consist of a current transf ormer (CT)
(0.3) to 1.2%), a transducer (0.5%) and an anmeter (1.0%) f or a combined accuracy of 1.8% to 2.7% depending on CT ratio. The accuracy of DC Instruments is based on the anmeter itsel f.
LOCATION IN PSAR: Figures 8.3-2 and 8.3-4 D.4.0 Nitrogen CATEGORY 3 PURPOSE: This instrument Indicates to the operator that there is an adequate supply of nitrogen gas available f or use within the RCB 1d RSB.
RANGE:
0-200 psig RATIONALE FOR RANGE: The normal pressure seen by this Instrument is 175 1,5 psig.
The range of the Instrument (0 to 200 psig) was selected to cover this normal pressure and provide a 10% range margin f or contingency.
INSTRUMENT LOOP ACCURACY: 12% of full scale (14 psi).
l RATIONALE FOR INSTRUMENT LOOP ACCURACY: The accuracy is based on the j
need to ensure that a minimum nitrogen pressure of 160 psig is l
available in the RCB and RSB.
Since a low pressure alarm is actuated at 168 psig, the required accuracy provides insurance that the operator is warned bef ore pressure drops below this value.
LOCATION IN PSAR: SECTION 9.5.5.1 l
D.4.D instrument Air CATEGORY 3 PURPOSE:
Indication of the Instrument Air Header pressure is used for the evaluation of continued supply of instrument Air.
RANGE:
0-250 psig RATIONALE FOR RANGE: The Instrument range of 0-250 psig is provided on the basis of normal (165 psig) and maximum (210 psig) operating conditions and 20% upscale margin.
QCS760.06-42
INSTRUMENT LOOP ACCURACY: Accuracy of the loop is within 12.5% of the 250 psig span.
BATIONALE FOR INSTRUMENT LOOP ACCURACY: The accuracy of the loop is based on the accuracy of its Individual market available components.
The loop consists of pressure transmitter (a =1,.5%) and panel j 0 electronic pressure Indicator (a = 2%).
2 LOCATION IN PSAR: SECTION 9.10.1 - Service Air and Instrument Air Syst ans.
D.5 TITLE: Ventilation Systems D.5.A Svstem 28 Ventilation. Subsystems. EA. EB. MA. MB CATEGORY 3 PURPOSE: To indicate system status f or saf ety related subsystems EA, EB, MA & MB which includes status of subsystem f ans and Isolation valves & supply & return gas temperature alarms.
(To monitor the environmental status of decay heat removal components).
RANGE: See Below RATIONALE FOR RANGE:
Instrument range is not applicable for status of f ans and Isolation valves.
Range f or the temperature is 20 F to 2400F 0
which envelops the f unctional operating range of Systems EA, EB, MA and MB and the setpoint of 1500F.
INSTRUMENT LOOP ACCURACY: For status of f ans & Isolation valves, Instrument loop accuracy is not applicable.
For temperature alarm l oops, instrument loop accuracy is i.7% of span, l
RATIONALE FOR INSTRUMENT LOOP ACCURACY:
Instrument loop accuracy is based on addition of accuracles of each Instrument in the loop.
Resistance temperature detector: 10.2%; Tenperature switch: 15%,
Total: 10.7% of span.
LOCATION IN PSAR:
7.6 (being rewritten) 7.6.6 - Recirculating Gas Cooling Instrumentation l
l and Control System D.5.B Cell Atmosohere Temoeratures 28PA. 28PB. 28PC, CATEGORY 3 l
PURPOSE: To indicate system status by providing temperature Indications in control room for PHTS & Reactor Cavity Cell atmospheres.
0 RANGE: 32 F - 600 F QCS760.06-43
RATIONALE FOR RANGE:
Instrument range of thermocouples, 32 F - 6000F, 0
based on lInear range of type "E" thermocouples.
INSTRUMENT LOOP ACCURACY: Temperature Indication loops i 3.0% of span.
PATIONALE FOR INSTRUMENT LOOP ACCURACY:
Instrument loop accuracy is based on addition of accuracy of each Instrument in the loop.
Resistance temperature detector: 10.2%; temperature transmitter:
10.75%; temperature Indicator; 12.0%, Total: 13.0%
LOCATION IN PSAR: SECTION 7.6 (being rewritten), 7.6.6 - Recirculating Gas Cooling Instrumentation and Control System D. 5.C Nuclear Island HVAC Status CATEGORY 3 PURPOSE: To monitor system status of Nuclear Island HVAC components which includes A/C units, filter units, f ans, dampers, air handling units, and discharge air temperature Indication and alarm to verify proper system alignment.
RANGE: Not Applicable f or f an, damper status.
For temperature the range is 320F to 6000F 0
RATIONALE FOR RANGE: Fcr Instrument range of thermoucouples, 32 F -
6000F is derived based on linear range of Type E thermoucouples.
INSTRUMENT LOOP ACCURACY: For status of fans and dampers Instrument loop accuracy is not applicable.
For temperatures alarm loop accuracy is within 11.0% and for temperature Indication loop accuracy is within 13.0%.
RATIONALE FOR INSTRUMENT LOOP ACCURACY: The accuracy of the Instrument Loop is based on the accuracy of its individual components.
Thermoucouples have accuracy within 10.5% alarm switches 10.5%,
temperature transmitter 10.5% and the Indicators 12.0%. So the overall accuracy of the alarm and Indicator loop comes within 11.0% and i3.0%,
respectively.
LOCATION IN PSAR: SECTION 7.6 - Nuclear Island HVAC Instrumentation and Control System is being rewritten D.6 TITLE: Confinements D.6.A Confinement Pressure CATEGORY 2 PURPOSE: To monitor the RSB confinement dif ferential pressure to insure that RSB confinement is monitored by verifying sub-atmospheric pressure.
QCS760.06-44
RANGE: TBD RATIONALE FOR RANGE: The range of these differential pressure transmitters are selected based on the maximum pressure which can be created by the RCB supply f ans (positive) and RSB filter fans (negative).
INSTRUMENT LOOP ACCURACY: Within 0.5%.
RATIONALE FOR INSTRUMENT LOOP ACCURACY: Since output of the pressure transmitter is directly going to the computer and the computer has a very high accuracy, the instrument loop accuracy is the same as the Instrument accuracy.
LOCATION IN PSAR: SECTION 7.6 - Nuclear Island HVAC Instrumentation and Control System is being rewritten.
D.6.B Annulus Pressure CATEGORY 2 PURPOSE: Monitoring of Annulus Pressure will verify that the Annulus space is being maintained at negative pressure with respect to atmosphere.
RANGE: TBD RATIONALE FOR RANGE: TBD INSTRUMENT LOOP ACCURACY: TBD RATIONALE FOR INSTRUMENT LOOP ACCURACY: TBD LOCATION IN PSAR: To be supplied later D.6 TITLE: RSB confinement I
D.6.C.
Radiation Monitorina CATEGORY 2 PURPOSE: Monitoring of the RSB HVAC ef fluent will assist in determining if RSB Cleanup System is f unctioning properly.
RANGE:
10-6 to 10-2p CI/cc RATIONALE FOR RANGE: Lower range is selected on basis of RSB oonfinement Initiation setpoint and commercially available range.
Upper range selected as standard 4 decade range of monitors.
INSTRUMENT LOOP ACCURACY: Accuracy will be within a f actor of 2 over the enti re range.
QCS760.06-45 l
RATIONALE FOR INSTRUMENT LOOP ACCURALY:
Instrumentation is similar to that used on LWR, accuracy is consistent with Reg. Guide 1.97.
LOCATION IN PSAR: SECTION 11.4 D.7 TITLE: CAPS Boundarv Integrity D.7.A
. CAP D essure. Surge vessel CATEGORY 3 PURPOSE: This instrument provides indication to the operator that the radioactive Inventory of this vessel is contained and That the pressure has not reached a value that will threaten the containment f unction of the surge vessel.
RANGE:
0-200 Psig RATIONALE FOR RANGE: The Instrument range has been selected to provide information during normal operation (40 i 10 psig); under pressure-limiting condition (compressor shutof f at 135 psig); and up to the setting of the pressure relief valve (175 psig). The margin above the relief setting ensures that, despite the uncertainty of the instrument loop accuracy and the pressure relief setting, the operator can confirm that relief has occurred prior to any threat to the pressure boundary function.
INSTRUMENT LOOP ACCURACY: 14 psig (i25 of f ul I scal e).
RATIONALE FOR INSTRUMENT LOOP ACCURACY: The accuracy of 1.4 psi was selected so that, when added to th uncertainty of the relief valve setting, the operator has an assured margin bef ore the confinement boundary is threatened which is adequate f or monitoring.
LOCATION IN PSAR: SECT ION 9.5.5.4 D.7.B CAPS Pressure. Cold Box CATEGORY 3 PURPOSE: This Instrument provides information to the operat'or that the radioactivity in the CAPS cold box is contained and that the pressure boundary (CAPS cold box wall) is not threatened.
RANGE:
0-50 psig l
RATIONALE FOR RANGE: The Instrument range is selected to provide l
Inf ormation f or normal operation of the cold box (0-35 psig) and to l
alarm the operator if this pressure exceeds the upper limit.
This will l
alert the operator bef ore there is any threat to the vessel boundary.
l l
QCS760.06-46
INSTRUMENT LOOP ACCURACY: 11 psi (i2% of fulI scale)
RATIONALE FOR INSTRUMENT LOOP ACCURACY: For accident monitoring an accuracy of 14 ps! Is adequate to assure that operator action can be taken prior to a threat to the pressure boundary.
LOCATION IN PSAR: SECTION 9.5.5.1 D.8 TITLE: RAPS Boundarv Intearity D.8. A RAPS Pressure. Surge Vessel CATEGORY 3 PURPOSE: This instrument provides Indication to the operator that the radioactive inventory in the RAPS surge vessel is contained and that the pressure boundary (vessel wall) is not threatened.
RANGE:
0-200 psIg RATIONALE FOR RANGE: The Instrument range is selected to include the normal operating conditions within the vessel (95 to 105 psig) and the setting of the vessel pressure relief valve (175 psig). The margin ensures that, with a 14 psig uncertainty band of the relief valve, the operator can confinn that pressure relief has occurred prior to any threat to the boundary.
INSTRUMENT LOOP ACCURACY: 14 psi (12% of fuil scale)
RATIONALE FOR INSTRUMENT LOOP ACCURACY: The accuracy of 14 psi was selected so that, when added to the uncertainty in the relief valve actuation level (14 psig), the operator has an assured margin before the pressure boundary is threatened.
LOCATION IN PSAR: SECTION 9.5.5.4 i
i D.8.B RAPS Pressure Noble Gas Storage Vessel CATEGORY 3 l
PURPOSE: This instrument provides Information to the operator that the radioactive inventory of the Noble Gas Storage Vessel is contained and that the pressure boundary (vessel wal1) is not threatened.
l l
RANGE:
-10 to +200 psIg RATIONALE FOR RANGE: The instrument range (-10 to 200 psig) is selected to cover not only normal operating conditions within the l
vessel (-7 to 75 psig) but also the pressure relief valve setting (175 psig). The margin ensures that with the 14 psig uncertainty band of the rellef valve the operator can ascertain that rellef has occurred before the boundary is threatened.
t QCS760.06-47
INSTRUMENT LOOP ACCURACY: 14 psi (12% of full scale)
RATIONALE FOR INSTRUMENT LOOP ACCURACY: The accuracy of 14 psi was selected so that, when added to the uncertainty in the relief valve actuation level (14 psig), the operator has an assured margin bef ore the pressure boundary is threatened.
LOCATION IN PSAR: SECTION 9.5.5.1 D.8.C RAPS Pressure. Cold Box Discharae CATEG0Fl. 3 PURPOSE: This Instrument provides Information to the operator that the radioactive inventory of the vessel is contained and that the pressure boundary (vessel wal l) is not threatened. This pressure, which is sensed on the discharge line of the cold box (cryostill), is also the pressure within the vessel.
RANGE: 0-200 psig RATIONALE FOR RANGE: The range is selected to cover not only the normal value of the parerneter but also the level at which the relief valve will actuate (175 psig) to protect the vessel. The 25 psi margin ensures that with the er. certainty band (14 psig) the operator can ascertain that relief has occurred bef ore the boundary is threatened.
INSTRUMENT LOOP ACCURACY: 14 psi (12% of full scale)
RATIONALE FOR INSTRUMENT LOOP ACCURACY: The accuracy of 14 ps! was selected so that when added to the uncertainty in the relief valve actuation level (14 ps!), the operator has an assured margin before the pressure boundary is threatened.
LOCATION IN PSAR: SECTION 9.5.5.1 i
TYPE E Monitoring of Radlatton Reieases Those variables to be monitored as required f or use in determining the magnitude of release of radioactive materials, and continually assessing such rel eases.
QCS760.06-48
4 1
E.1 TITLE: Containment Radiation i
E.1.A Containment Area Radiation Hlah Ranae CATEGORY 1 PURPOSE: Monitors are Iocated In annulus space and monitor radiation '
levels emitted f rom containment. Monitors wilI provide long terg surveillance (8000 hrs.) of activity in containment.
RANGE:
1 R/hr to 107 R/hr i
RATIONALE FOR RANGE: Since source term for CRBR is simil ar to ' LWR, range is similar to LWR for similar instruments and consistent with Reg. Gulde 1.97.
INSTRUMENT LOOP ACCURACY.: Accuracy will be within a f actor of 2 over the entire range.
RATIONALE FOR INSTRUMENT LOOP ACCURACY:
Instrumentation'is simif er to that used on LWR, accuracy is consistent with Reg. Guide 1.97.
LOCATION IN PSAR: SECTION 12.1 E. 2 TITLE: Area Radiation E.2.A Radiation Exoosure Rate (Inside buildina where CATEGORY 2 access Is reaufred to service eautomont imoortant to safetv)
PURPOSE: Detection of significant releases and long term surveII jar, tis' in areas where access may be required to service _ safety equipmert RANGE:
10-1 R/hr to 104 R/hr level is <10 pssumed that if the radietior, NOTE:
It Is R/hr, lower radiation level l
Indication is not necessary.
Standard Health r
f Physics requirements will be in ef fect RATIONALE FOR RANGE:
1.
Since source terms f or CRBR and LWR are similar, range is similar to LWR f or simil ar instruments and consistent with Reg. Guide 1.97.
2.
Standard commercially avalIable range.
INSTRUMENT LOOP ACCURACY: Acci. acy will be.within a f actor of 2 over '
the entire range.
RATIONALE FOR INSTRUMENT LOOP ACCURACY:
instrumentation is similar to that used on LWR, accuracy is consistent with Reg. Gu,lde 1.97.
i LOCATION IN PSAR: SECTION 12.1
/
/
,)
QCS760.06-49 j
i )
r 1
E.3 Ti1LE: Airborne Radioactive Materials Released From Plant E.3. A Noble Gas and Vent Flow Rate E.3. A.1 Contalrment or Purae Ef f luent CATEGORY 2 PURPOSE: Detection of significant releases and long term surveillance of all identified plant release points.
RANGE:
10-6 5
/4 Cl/cc to 10 /4CI/cc 0 to 110% vent design flow (not needed if ef fluent discharges are through common pl ent vent).
RATIONALE FOR RANGE: Since source term for CRBR is similar to LWR, range is similar to LWR f or simil ar Instruments and is consistent with Reg. Gui de 1.97.
INSTRUMENT LOOP ACCURACY: Accuracy will be within a f actor of 2 over the entire range.
EAT 10NALE FOR INSTRUMENT LOOP ACCURACY:
Instrumentation is similar to that used on LWR, accuracy is consistent with Reg. Guide 1.97.
LOCATION IN PSAR: SECTION 12.1 E.4 TITLE: Annulus Filtration System (Noble Gas)
CATEGORY 2 EUEEDSE: Detection of significant releases and long term surveillance of all Identified plant release points.
RANGE:
10-6 5
/tCl/cc to 10 /aCl/cc 0 to 110% vent design flow (not needed if ef fluent discharges are through common plant vent).
l RATIONALE EOR RANGE: Since source term for CRBR is similar to LWR, range is similar to LWR f or similar instruments and is consistent with l
Reg. Gui de 1.97.
l INSTRUMENT LOOP ACCURACY: Accuracy will be within a f actor of 2 over f
this enti re range.
l' t'
RATIONALE FOR LNSTRUMENT LOOP ACCURACY:
Instrumentation is similar to that used on LWR, accuracy is consistent with Reg. Guide 1.97.
LOCATION IN PSAR: SECTION 12.1
\\
z' g
QCS760.06-50 I
E.5 TITLE: Steam Generator Bullding. Reactor Service CATEGORY 2 Buildina (Noble Gas)
PURPOSE: Detect!on of signifIcant reieases and Iong term surveliIance of alI identifled plent release points.
3 RANGE:
10-6pCl/cc to 10 pCl/cc 0 to 110% vent design fIow (not needed If effIuent discharges are through common vent)
RATIONALE FOR RANGE: Since source term for CRBR is similar to LWR, range is similar to LWR for similar Instruments and is consistent with Reg. Gulde 1.97.
INSTRUMENT LOOP ACCURACY: Accuracy will be within a f actor of 2 over the entire page.
RATIONALE FOR INSTRUMENT LOOP ACCURACX:
Instrumentation is similar to that used on LWR, accuracy is consistant with Reg. Guide 1.97.
LOCATION IN PSAR: SECTION 12.1 E. 6 TITLE: Particulates and Halocens E.6.A All Identified Plant Release Points (excent CATEGORY 3 steam generator safety relief valves or atmoseheric steam dumo valves and condenser air removal system exhaust)
PURPOSE: Detection of significant releases and long term surveillance of all Identifled plant reiease points.
RANGE:
10-3 2
pCI/cc to 10 /tCl/cc 0 - 110% vent design flow RATIONALE FOR RANGE: Since source term for CRBR is similar to LWR, range is similar to LWR for similar instruments and is consistent with Reg. Guide 1.97.
INSTRUMENT LOOP ACCURACY: Accuracy will be within a f actor of 2 over the enti re range.
RATIONALE FOR INSTRUMENT LOOP ACCURACY:
Instrumentation is similar to that used on LWR, accuracy is consistent with Reg. Guide 1.97.
LOCATION IN PSAR: SECTION 12.1 QCS760.06-51
l E. 7 TITLE: Environs Radiation and Radioactivity E.7.A Radiation Exoosure Meters (Continuous Indication CATEGORY 3 at fixed locations)
PURPOSE: To verify significant releases and local magnitudes.
RANGE: S ee bel ow RATIONALE FOR RANGE: Range, location, and qualification criteria to be developed to satisfy NUREG-0654, Section ll.H.5b and 6b requirements f or emergency radiological monitors.
INSTRUMENT LOOP ACCURACY: TBD RATIONALE FOR INSTRUMENT LOOP ACCURACY:
Instrumentation is similar to that used on LWR, accuracy is consistant with Reg. Guide 1.97.
LOCATION IN PSAR: SECTION 12.1 E.7.8 Airborne Radiohaloaens and Particulates CATEGORY 3 (nortable samolina with onsite analvsis caoebilltv).
PURPOSE: This instrumentation enables the operator to assess magnitudes of any releases.
RANGE:
10-9pCI/cc to 10-3.Cl/cc ja RATIONALE FOR RANGE: The range conf orms to the guidance provided in Reg. Gui de 1.97.
INSTRUMENT LOOP ACCURACY: TBD RATIONALE FOR INSTRUMENT LOOP ACCURACY: Conventional standards f or accuracy for this type equipment will be applied.
LOCATION IN PSAR: To be provided.
i i
E.7.C Plant and Environs Radiation (Portable CATEGORY 3 Instrumentation)
PURPOSE: This Instrumentation enables the operator to access the magnitudes of releases.
RANGE:
10-3 R/hr to 104 R/hr, photons 10-3 rads /hr to 104 rads /hr, beta radiations and low-energy l
photons QCS760.06-52
RATIONALE FOR RANGE: The range conf orms to the guidance of Reg. Guide 1.97.
Radiation instruments capable of monitoring over the necessary range will be available.
INSTRUMENT LOOP ACCURACY:
RATIONALE FOR INSTRUMENT LOOP ACCURACY: The accuracles will be typical of this type of counting Instruments with energy discrimination capability for the appropriate radiation type and will employ industry accepted techniques.
LOCATION IN PSAR: SECTION 11.4 and 12.1 E.7.D Plant and Environs Radioactivltv (oortable CATEGORY 3 Instrumentation)
PURPOSE: This Instrumentation enables the operator to assess the magnitude of any release.
RANGE: Multichannel gamma-ray spectrometer RATIONALE FOR RANGE: The range will be within conventional standards f or this type equipment.
INSTRUMENT LOOP ACCURACY: Variable dependent on the make of the detector.
To be determined upon final selection of equipment.
RATIONALE FOR INSTRUMENT LOOP ACCURACY: The typical accuracles f or this type of equipment will be accepted.
LOCATION IN PSAR: To be provided.
E.8 TITLE: Meteroloav E.8. A Wind Direction CATEGORY 3 PURPOSE: Will allow operator to assess direction of any plant releases carried by the wind.
0 0
RANGE: 0 to 360 F (fj5 accuracy with a deflection of 150).
Starti ng speed 0.45 mps (1.0 mph).
l Damping ratio between 0.4 and 0.6, distance constant 52 meters RATIONALE FOR RANGE: Conforms to the guidance provided in the Reg.
Gui de 1.97.
INSTRUMENT LOOP ACCURACY: Conventional standards f or the accuracy of this type of equipment will be applied.
QCS760.06-53
RATIONALE FOR INSTRUMENT LOOP ACCURACY: Conventional standards f or the accuracy of this type of equipment will be applied.
LOCATION IN PSAR: To be provided.
E.9 TITLE: Gran Samole f rom Containment CATEGORY 3 PURPOSE: This information provides operator with data to make an assessment of any releases in containment and perf orm radioisotopic ana l y si s.
RANGE: NA RATIONALE FOR RANGE: The counting equipment will be selected at a later date, however, the necessary detector type and energy discrimination capability will be provided to support this radioisotopic analysis.
INSTRUMENT LOOP ACCURACY: Achievable accuracles will be consistent with this type of equipment in accordance with accepted industry standards.
RATIONALE FOR INSTRUMENT LOOP ACCURACY: The accuracy is based on standard Industry practice.
LOCATION IN PSAR: To be provided.
QCS760.06-54
Pcge 1 (82-0446) [8,07] #30 7.5 INSTRUMENTATION AND MONITORING SYSTEM The instrumentation and monitoring systems included in this Section are the Flux Monitoring System, the Heat Transport Instrumentation System, the Reactor and Vessel Instrumentation System, the Fuel Failure Monitoring System, the Leak Detection Instrumentation System, and the Sodium-Water Reactor Pressure Rel ief System. Table 7.5-1 lists the measured paraneters and instrumentation provided by these systems, The Instrumentation which is safety related as defined in Section 3.2.1 is identified with an asterisk in column 2 of Table 7.5-1.
Instrumentation and monitoring for TLTM parameters not included in the design basis are also discussed. These include containment hydrogen monitoring and containment vessel temperature and pressure monitoring.
7.5.1 Flux Monitorina Svstem The objective of the Flux Monitoring System (FMS) is to provide Indications and electrical signals proportional to reactor power for reactor plant control and protection. The FMS meets its objective by means of neutron measuring Instrumentation comprised of sensors and signal conditioning equipment which provide Indications and signals f or conditions of reactor shutdown, startup and f ul l power operation.
Neutron sensors located around the periphery of the reactor guard vessel sense thermalIzed reactor leakage flux which is proportional to the reactor flux and thus to reactor power.
Signals f rcrn the sensors are conditioned and then used to do the following:
o Determine the flux status of the reactor from shutdown through startup and al l power level s.
o Provide signals to the Plant Protection System (PPS) to initiate reactor protective trips.
o Provide signals to the Plant Control System (PCS) for reactor and plant control.
o Provide neutron flux Information f or display, annunciation and recording.
A block diagram of the FM System is provided in Figure 7.5-1.
7.5.1.1 Deslan Descriotion The Neutron Flux Monitoring System provides three ranges of Instrumentation:
Source Range, Wide Range and Power Range.
Each range of Instrumentation is provided in three identical channels comprised of a detector, preamplifier (source and wide ranges), junction box (power range) and signal conditioning equipment. The Flux Monitoring System measures neutron flux proportional to reactor power over a span or more than ten decades f rom shutdown to above f ull power and provides Indications and electrical outputs for plant protection, plant control, accident monitoring, data handling and display, recording, and annunciation.
7.5-1 Amend. 69 July 1982
P;ge 2 (82-0446) [8,07] #30 7.5.1.1.2 Wide Range Each of the three channels of Wide Range instrumentation will use a U235 fission chamber to sense neutron flux from low power to above f ull power by providing, within each channel, overlapping ranges of counting, mean square voltage (MSV) and direct current Instrumentation. The counting and MSV Instrumentation provides precent power indications on logarithmic scaled meters and rate of change of level on a lInear scale from -1 to O to +3 decades per minute. These two overlapping ranges of instrumentation are designated as Category 1, Type B, Accident Monitoring equipment as defined in PSAR Section 7.5.11.
The d-c instrumentation Indicates percent power on a lInear scale.
The signal conditioning equipment produces electrical signals which are indicative of the power levels and rate of change of power levels.
These signals are used for plant protection, data handling and annunciation. The MSV and linear circuits outputs will be linear to at least 140 percent power and will have a significant positive response to as high a power level as required by the worst case power overshoot for which protection must be provided.
Built-in test circuits and controls will be provided to permit testing and aligning the equipment during plant operation and during plant shutdown.
7.5.1.1.3 Power Range Each of the three channels of power Range Instrumentation will use B10 compensated Ionization chambers to sense the neutron flux in a span of from less than one percent power to more than f ull power. The d-c current output 7.5-3b Amend. 69 July 1982 rstuve
Pcge 3 (82-0446) L8,07J #30 Output of the detector will be processed in the signal conditioning equipment to provide linear indication of percent power and linear output signals f or plant protection, plant control, data logging and annunciators.
This instrumentat!on operates over the same flux span as the direct current circuitry of the wide range Instrumentation to add redundancy and diversity to the wide range power measurements.
The output of this Instrument will be linear to at least 140 percent power and will have no foldover to as high a power level as required by the worst case power overshoot for which protection must be provided.
Built-in test circuits and controls will be provided to pennit testing and aligning the equipment during plant operation and plant shutdown.
7.5.1.2 Deslan Analysis The Flux Monitoring System will be a f unctional subsystem of the Plant Protection System and wil l meet the saf ety related channel perf ormance and reliability requirements of the CRBRP General Design Criteria, RDT Standard C16-lT, Dec. 1969, IEEE Standard 279-1971, applicable Regulatory Guides,
criteria of Section 7.5.11 and other appropriate criteria and standards by complying with the applicable design requirements delineated in Section 7.1.2.
The FMS meets CRDRP General Design Criterion 21, which is applicab;e to instrumentation f or normal and accident conditions, as f ollows:
o The shutdown flux level will be monitored at all times while f uel is in the core so as to provide saf e operational control of the reactor during low power, normal shutdown, ref ueling and shutdown maintenance operations.
o The reactor flux will be continuously monitored during operation from shutdown to f ull power operation (i.e., overlap wil l exist between cascaded channels so that all power levels can be monitored without a gap in range).
o Reactor power operations will be continuously monitored with linear response to power up to at least 140% full power.
Significant positive response will be provided to as high a power level as i
required by the worst case power overshoot for which protection must be provided. This positive response will be provided for as long as i
is required to seal in the scram trip.
l o
The FMS Instrument respor:se time delays wil l meet the response requirements of the Reactor Shutdown and Plant Control Systems, o
Indication of reactor power level and rate of change of power level will be provided to the operator. One set of meters and a selector l
switch will be provided for each range of instrumentailon permitting the operator to select one channel at a time to be displayed on the l
7.5-4 Amend. 69 July 1982
~~----
1 P:ge 4 (82-0446) [8,07] #30 i
related meters.
Seven power level meters, five selector switches and three rate of change of power meters will be provided for the operator.
o The source range level will be indicated in logarithmic counts per second and rate of change of level in decades per minute.
Linear count rate will be provided at shutdown at the ref ueling console and at the FMS system panels in the control room.
Audible count rate Indication will be provided in the control room and in containment at the ref uel ing console.
o The wide ranges will be Indicated as follows:
Counting channels - Logarithmic percent power level and decades per minute rate of change.
MSV channels - Logarithmic percent power level and decades per minute rate of change.
DC channels - Linear percent power level, o
The power range will be Indicated in linear percent power level.
Preliminary Failure Mode and Ef fect Analysis results applicable to the FMS have been determined in an analysis of possible f ailure modes and their ef fects on the Reactor Shutdown System performance and are presented in Tables C.S. 1-4 and C.S. 1-5.
7.5.2 Heat Transoort instrumentation System 7.5.2.1 Descriotion The Heat Transport Instrumentation System provides sensors, associated signal conditioning equ!pment and controls other than Plant Control, for the Primary Heat Transport, the intermediate Heat Transport and the Steam Generator. The signals f rom the sensors are conditioned and then supplied to the Reactor Shutdown System logic, the Plant Control System, the Plant Data Handling and Display System, and the Plant Annunciator System as appropriate. The location of the Heat Transport instrumentation is provided in Figures 5.1-2 and 5.1-4 l
(PalD's).
7.5.2.1.1 Primarv and Intermediate Sodium Locos Reactor Inlet Pressure The measurement is made by pressure elements Installed in the cold leg of the primary loop piping just bef ore it enters the reactor vessel.
NaK filled capillaries f rom the pressure elanents ars connected to pressure transducers which develop electrical signals proportional to the pressure. These pressure transducers provide a secondary boundary if the bellows in the pressure elanents should f all.
l l
1 7.5-5 Amend. 69 July 1982
P:ge 1 ( 82-0447) [8,07] #31 7.5.3 Reactor and Vessel Instrumentation 7.5.3.1 Descriotion The Reactor and Vessel Instrumentation System includes all in-vessel temperature, sodium level and vibration sensors for instrumenting the reactor parameters required for the Reactor Shutuown System, PCS, surveillance and design verif ication.
It also !r.ciudes signal conditioning equipment needed to make the sensor signal usable in the systems receiving the signal.
Tabl e 7.5-2 shows the In-vessel Instruments provided, their location, their quantity and purpose.
7.5.3.1.1 Sodlum Level A total of six sodium level sensors are provided.
All of these sensors are l
mounted in wells to provide the physical barrier maintaining the Integrity of the primary loop closed system. The sensors are induction type probes continuously sensitive over their entire length.
Four of the units, located approximately equally spaced on the top of the reactor, are short with a sensing range of from 6 inches above the operating level to 24 inches below.
Three of these provide the level signals to the three Reactor shutdown system logic and are thus isolated from each other and from non-PPS equipment. The fourth is an Installed spare unit providing a means of maintaining the three operating channels without a shutdown in the event of f ailure of one of them.
The remaining two level sensors are located close to one of the short units but provides a measuring range f rom 6 inches above the operating level to six Inches below the top of the outlet nozzle.
It has approximately sixteen feet of sensing length. The two signals is are supplied to two indicators located on the main control panel and are monitored at all times, including refueling.
These two wide range sodium level channels are Category 1, Accident Monitoring i nstr uments.
7.5.3.1.2 Temoerature All in-vessel temperatures are sensed by 1/8 inch, chromel alumel, ungrounded, stainless steel sheathed thermocouples. Thirty wel ls are provided f or thermocouples located in the sodium at the exit f rom the core. These thermocouples provide signals to the PCS and the PDH&DS.
Additional wells are provided at the core exit (308), core periphery 7 2), and on parts of the upper Internal structure (6) for thermocouples providing signals to the PDH&DS for surveillance and design verification.
The 338 thermocouples provided at the core exit are Category 3, Accident Monitoring Instruments.
7.5.3.1.3 Non-reolaceable Instruments Within the reactor vessel, four blaxial accelerometers are mounted on the upper Internal structure so that they cannot be replaced. These sensors are not required to f unction beyond the f irst six months of operation although they are required to physically withstand the sodium environment for the life of the reactor.
The signals provided by these sensors provide design 7.5-13 Amend. 69 July 1982
7.5.10 Containment Atmosohere Tamnerature l
The objective of the Containment Atmosphere Temperature Monitoring System is to provide Indication in the Control Room of the atmosphere temperature inside the contai nment building.
7.5.10.1 Deslan Descriotion The temperature Instrumentation consists of two f ully redundant and independent channels.
Each channel consists of two thermocouples mounted on the RW dome, with each thermocouple providing a signal to conditioning instrumentation in the SGB. The l
Instrumentation sends a signal to the Control Room where Individual rendout is provided. This instrument is also required to perf orm functions f or events which lie beyond the design basis f or the plant.
This instrument is f urther discussed in this capacity in Section 2.1 and 2.2 of Ref erence 10b of PSAR Section 1.6.
7.5.11 Accident Monitorina Instrumentation The Accident Monitoring Instrumentation is an integrated set of instruments made available to assess plant and environs conditions during and following accidents.
7.5.11.1 Descriotion Accident Monitoring parameters are monitored to perf orm the fol lowing f unctions:
o Provide primary inf ormation to permit manual Variable Type A actuation of saf ety systems.
Type A variables monitor the primary inf ormation required to permit the control room operator to take specific manually controlled actions f or which no automatic control is provided and that are required for saf ety systems to accomplish thelr saf ety functions f or Design Basis Accident events.
Primary information is that which is essential for the direct accomplishment of the specified saf ety functions; it does not include those variables that are associated with contingency actions that may also be identified in written procedures.
l o Indicate that saf ety functions are being accom-Variable Type B plished (i.e., reactor shutdown, core cooling, containment integrity).
Type B variables provide Inf ormation necessary to indicate whether plant saf ety functions are being accompl i shed.
7.5-33c Amend. 69 July 1982
o Indicate potential for or breach of barriers to Variable Type C fission products release (i.e., fuel, cladding, primary boundary, containment).
Type C variables provide information to Indicate the potential for, and/or the actual breach of barriers' to fission product releases. The barriers are (1) fuel cladding, (2) primary coolant pressure boundary, and (3) containment.
o Indicate operation of saf ety systems or other Variable Type D systems important to saf ety.
Type D variables provide information to indicate the operation of Individual safety systems and other system important to saf ety. These variables are to help the operator make appropriate decisions in using the Individual system important to saf ety in mitigating the consequences of an accident.
o Indicate magnitude of release of radioactive Variable Type E materials and continuously access such release.
Type E variables provide Information required for use in determining the magnitude of release of radioactive materials, and continually assessing such releases.
7.5.11.2 Instrumentation Design and Oualification A graded approach to Instrument requirements has been incorporated which emphasizes the importance to safety of a particular measured variable.
Different' categories for instrumentation have been Identified as follows:
Category 1: Class IE Instrumentation which requires seismic and environmental qualification, single failure criteria, and Class 1E power source.
Category 2: Instrumentation which is environmentally qualified and powered from a reliable power source.
Category 3: Instrumentation of a high quality commercial grade.
7.5.11.2.1 Categorv 1 Each Category 1 parameter is monitored by at least o
two instruments. These Instruments are referred to as:
7.5-33d Amend. 69
o Pri ncipal Instruments, and o Redundant Backup Instruments All Category 1 Principal Instruments are classified as 1 E.
Category 1 Redundant Backup Instruments are classified as IE up to the isolation device from the sensor.
A third verification Instrument is provided if a f ailure of the principal or redundant instrument will result in Information ambiguity (that is the redundant displays disagree) that could lead operators to def eat or f all to accomplish a required saf ety function. This third Instrument is called a verification instrument.
o The Principal Instrument Indication will be located in the viewing area of the operator in the Control Room. The Redundant Backup Instrument Indicator will be in the proximity of the Principal Instrument Indicator to permit the operator to make comparisons.
If a Verification Instrument is requi red, its indication will be accessible but not necessarily in the Control Room.
(The plant computer may provide the Verification Instrument i nf ormati on).
o A minimum of one Instrumentation channel for each Category 1 variable will be recorded unless it can be shown that reccrdir.9 ihot particular parameter will not provide benefit in analyzing the overall l
accident. The plant computer (non-1E) is the pref erred method of recording.
Special attention
[
will be given to the logging f requency of each of these Category 1 parameters so that an adequate presentation of the parameter response during an event will be available.
A recorded pre-event history for these parameters is required f or a minimum of one hour, and continuous recording of these instruments is required following an accident until such time as continuous recording of such inf ormation is no longer deemed necessary.
(
i o The single f ailure criteria for Category 1 l
Instruments is applied to the combination of the Principal Instrument and the Redundant Backup Instrument. The Verification Instrument is not taken into consideration when considering single f ail ure criteria. No single f ailure within the Principal Instrument chain, and the Redundant Backup instrument chain, their auxiliary supporting 7.5-33 e Amend. 69 July 1982
features, or their power sources, concurrent with the f ailures that are a condition of, or a result of a specific accident, wil l prevent the operator f rom being presented the required inf ormation.
o The Principal instruments f rom sensor to Indicator, and the Redundant Backup instruments f rom sensor through the Indication device will be quellfled in accordance with PS AR Section 1.6 Ref erence 13,
" Requirements f or Environmental Qualification of Class IE Equipment." They are qualified to provide the Inf ormation needed by the operator to assess plant and environs conditions during and foliowing design basis events.
o Instrumentation will continue to read within the required accuracy following, but not necessarily during, a Saf e Shutdown Earthquake (SSE).
o The Principal instrument (from sensor to Indicator) and Redundant Backup Instrument (from sensor through the isolation devices) will be energized f rom Class
- IE power and be supplied with battery backing where momentary Interruption of the Indication is not tol erabl e.
7.5.11.2.1 Categorv 2 o Each Category 2 Instrument signal, will be, as a minimum, processed f or display on demand.
o The Category 2 Instrument indicators will be located to ef fectively support normal and emergency plant operati ons, o The Category 2 instruments f rom sensor to Indicator will as a minimum be quellfled in accordance with Reference 13, PSAR Section 1.6, " Requirements f or Environmental Qualification of Class 1E Equipment" except f or sei smic. They will be qualified to provide the information needed by the operator to assess plant and environs conditions during and following design basis events, o The instrumentation will be energized from a highly reliable power source (not necessarily a Class IE power supply). Where Interruption of the power supply is acceptable station AC power may be used.
Where momentary Interruption is not tolerable, the non-1E UPS is used.
i 7.5-33f Amend. 69 July 1982
7.5.11.2.3 Cateaorv 3 o Each Category 3 Instrument signal, wil l be, as a minimum, processed f or display on demand.
o The location of the Category 3 Instrument Indication will be chosen to support normal and of f-normal operati ons, o The Category 3 Instrumentation will be a high quality commercial grade.
7.5.11.2.4 General Ryouirements to Catecorv 1. 2. and 3 o Servicing, testing, and calibration prograns will be specified to maintain the capability of the monitoring instrumentation.
For those Instruments where the required Interval between testing shall be less than the normal time Interval between generating station shutdowns, a capability for testing during power operation shall be provided.
o Whenever means f or removing channels f rom service are included in the plant design, the plant design will facilitate administrative control of the access to such renoval means.
o The plant design will facilitate adninistrative control of the access to all setpoint adjustments, module calibration adjustments, and test points, o The monitoring instrumentation design will minimize the development of conditions that would cause meters, annunciators, recorders, al arms, etc., to give anomalous indications potentially conf using to the operator.
o The instrumentation will be designed to f acilitate the recogni tion, location, replacement, repair, or adjustment of mal functioning components or modules.
o To the extent practicable, monitoring Instrumente-tion inputs will be f rom sensors that directly measure the desired variables.
An Indirect measurement will be made only when it can be shown by analysis to provide unambiguous information.
7.5-33g Amend. 69 July 1982
9 7.5.11.3 Instrument identification All Category 2 Instruments that are Types A, 8, or C, and all Category 1 Principal and Redundant Backup Instruments, will be specifically identified on their respective control panels so the operator can easily discern that they are for use under accident conditi ons. The above instruments will be yellow color coded (Federal Standard 595a, Chip Number 33793).
f l
7.5-33h Amend. 69 July 1982 E
. _. ~.
T ELE 7.5-1 INSTRUENTATION SYSTEM FUNCTIONS AND
SUMMARY
Measured System Paraneters Instrument Measurenent Location Purpose Flux Source Range BF3 Thimbles on periphery of guard Determines or Provides:
Monitoring vessel
- 1. Flux status at shutdown, Wide Range' Fission Chambers Thimbles on periphery of guard startt:p and power levels vessel
- 2. Signals to PPS logic Power Range' B-10, Cepensated Thimbles on periphery of guard (except source range) lon Chamber vessel
- 3. Signals for reactor and plant control (D.C. linear power ranges)
- 4. Signals for display, accident monitoring, annunciation and recording Heat Transport Reactor Inlet Pressure Element Cold leg primary loop PPS and display Primary /
Pressure
- PHTS performances Intermediate Loops Primary and Inter-PM Flowmeter Cold leg of primary and Inter-PPS, Plant Control and Display, mediate Flows mediate loops (hot leg In Inter-PHTS performance mediate loop 2)
IHX Primary Outlet Thermocouple Cold leg piping nearest to lHX Plant Control System (PCS), PPS, Temperature
- primary outlet and Display Primary and Inter-Resistance Primary and Intermediate hot and Surveillance, display and use to mediate Hot and Temperature cold leg calorimetrically calibrate PM Cold Log Tempera-(RTD) fIowneters fure Primary and Inter-Pressure Elements Dralnline from discharge piping of Surveillance, display and mediate Pump the loop's sodlum planp monitor dif ferential pressure Discharge Pressure between primary & Intermediate loops PHTS performance Intermediate Pressure Elanents intermediate between lHX &
Surveillance, display & monIter IHX Outlet Superheater dif forential pressure between Pressure Intermediate loops 7.5-34 Amend. 69 July 1982 82-0444
TELE 7.5-1 (Continued)
Meesured System Par meters Instrument Measured Location Purpose Reactor and Core Sodlum Exit Thermocoupl es Selected f uel and blanket Display, control and accident Vessel Temperature assemblies.
monitoring - core outlet Instr u-temperature mentation Core Peripheral Thermocouples Core periphery - 2 locations Display - Design verification Temperature Upper Internals Thermocouples Parts of upper Internal structure Display - design verification, Temperature 6 locations predict stress on variour components Sodlum Level above Level Probe Reector vessel plenum PPS Display and Accident Core
- Monitoring Upper Internals Vibration Element 4 Blaxlal on parts of Display - measure vibrations Movement appropriate structure Induced by sodium flow Fuel Fallure Cover Gas Gama G ama Spectrometer SepIIng in RSB Detect each Instance of fuel Monitoring Activity clad f ailure and characterize f ail ure Delayed Neutron BF Counter Shielded moderator assembly adjacent Detect f uel In PHTS 3
Monitoring to each of the PHTS hot leg pipes Tag Gas Isotopic Mass Spectrometer Gas tag sampling traps In RSB Locate f ailed f uel Camposition Leak Liquid Metal Contact detectors In various locations in sodium Identify location of IIquid Detection to Gas Leeks cable detectors circults metal to gas leaks for aerosol monitors continuous surveillance of IIquid metal systems boundaries 7.5-37 Amend. 69 July 1982 82-0444
Pcg2 1 (82-0445) L8,07J #29 TABLE 7.5-2 REACTOR AND VESSEL INSTRUfENTATION Measured Instrument Parameter Location Puroose Thermocoupie Core Exlt Sodium One at each of 30 Control,surveliIance Tenperature selected f uel and and accident monitoring blanket _ assemblies Core outlet temp.
308 additional Surve!IIance, locations at Diagnostic and selected fuel and accident monitoring blanket assemblies
- Distribution of temperature across the core Thermocoupi e Core Peripheral Two spaced Ioca-Design Verification -
Tanperature tions on the core Distribution temp.
periphery around the core Upper Internals Six on parts Design Verification -
Tenperature of the upper Distribution of temp.
Internal structure to predict stress on various components Sodium Level Sodium Level Four short units Protection and Con-Detector above the core distributed trol - Measures the equally around operating level of periphery the sodium in the reactor Two long units Survell lance and I
near one of the accident monitoring l
four short ones
- Measure the sodium i
level from operating level down to below
(
the top of the outlet l
nozzle Vibration Upper Internals Four blaxlal on Design Verification -
Detector Vibration parts of appro-Measure vibrations priate structure Induced by sodium flow 7.5-39 Amend. 69 July 1982
Pcg3 2 (82-0396) [8,22] #105 Question CS760.35 The natural circulation transient is analyzed for 500 seconds; after this time the transient is said to be "well-behaved".
However, in order to conserve protected water, the air-cooled condensers must remove the entire decay heat load.
Experiments with steam-generators in the steam condenser mode have shown dif ficulty in predicting behavior.
The results show pressure fluctuations and apparent bistable modes of operation.
What evidence can you give to show that the PACCs will operate as expected and what would be the consequences of pressure fluctuations and/or lower than expected heat rejection capability?
Resoonse Design analysis and testing is being done to provide assurance that the PACC design will perf orm within design requirements.
Considerations to be included in the analysis of the PACC thermal design and hydraulic stability are discussed in updated PSAR Sections:
5.6.1.3.2.2
" Thermal Analysis of PACC" 5.6.1.3.2.3
" Thermal Hydraulic Stability" PACC f unctional tests will be conducted periodically and heat rejection rates will be calculated from test data. These tests will identify lower than expected heat rejection capability if it occurred. The plant is relatively insensitive to PACC heat rejection capability.
If lower than PACC design heat rejection occurred, the SGAHRS steam vent duration would be extended slightly, if higher than PACC, design heat rejection occurred, the SGAHRS steam vent duration would be slightly reduced.
The PACC thermal design conservatively accounts for heat transfer uncertain-ties and allows for 10% tube plugging as noted in Section 5.6.1.3.2.2.
1 I
QCS760.35-1 Amend. 69 July 1982
uc v**.
Pcge 3 (82-0441) [8,05] #52 Each PACC air side will have f orced circulation capability to remove 15 MWt of heat. The cooler inlet air (max.1000F) will be drawn in at the cell base and rise through the 6000F condenser and exit out the cell roof through a stack.
5.6.1.3.2.2 Thermal Analvsis of PACC A thermal hydraulic analysis of the PACC has been perf ormed. The steam side calculations represent a coiled, finned condenser tube f rom steam inlet to condensate outlet.
The appropriate water / steam side heat transfer coef ficient for each segment is determined for the flow regime f or each segment based on water / steam properties and f ilm temperature drop.
For a ratio of steam-to-water density 10.125, the Boyko-Kruzhilin correlation (Ref. 5.6-2) is used.
For a ratio of steam-to-water density < 0.125, the heat transfer coef ficient is selected based on Baker's flow regime transition data.
(Ref. 5.6-3)
When the flow regime in a tube segment is stratified, the modified Sollman, Schuster and Berenson correlation (Ref. 5.6-4) is used.
When the flow regime is dispersed or slug, the Chato correlation (Ref. 5.6-5) is used.
The pressure drop and vold fraction correlations used in determining the flow rate in the heat exchariger tubes are:
Revnold's Void Frictional Number Fraction Pressure Droo Re < 2000 Lockhart-Martinel li (ref 5.6-6)
Lockhart-Martinel li (ref -5.6-6)
Re > 2000 Borocry (ref 5.6-7)
Borocry (ref 5.6-8) 2 The analysis considers a fouling resistance of 0.0005 (Hr-Ft -oF)/ Btu on the steam side af ter 30 years of service. This value is consistent with thermal standards of the Tubular Exchanger Manuf acturers Association (TEMA).
For the air-side, the convective heat transfer coef ficient is computed using l
the method outlined in the ESCOA Fintube Engineerina Manual (Ref. 5.6-1) as a f unction of the gas-side mass flow and the tube, fin and coil geometry.
Ssveral air-side heat transfer coef ficients were examined. The correlation in the ESCOA manual most resembles the conditions in the PACC design.
The ESCO.'. air-side heat transfer coef ficient is based on the total overall heat transfer area between the steam and air.
However, for PACC en Individual l
air-side heat transfer coef ficient is used for each increment of the model.
Local air-side thermal and physical properties are used based on the local air and steam temperatures. Furthermore, row dependent air side heat transf er coef ficients are calculated separately for each of the four turns by snploying an averaging method since each turn of the coil has a dif ferent air flow area.
All these are taken into account to derive the appropriate local air-side heat transf er coef ficient f or each increment.
An air-side fouling resistance of 0.001 (Hr-f t2-oF)/ Btu is applied in the PACC thermal analysis. This value is consistent with recommendations of the ESC 0A Fin Tube Engineerina Manual (Ref. 5.6-1).
5.6-11b Amend. 69 July 1982
Page 4 (82-0441) [8,05] #52 Using the above described correlations and assuming 10% plugged tubes, the ncminal PACC capacity has been determined to be 29.07 x 106 Btu /hr/ tube bundle or 8.53 W (17.06 MW/PACC).
The approach to conservatively determine PACC thermal performance included a sensitivity study where reasonable uncertainties were assumed in turn for each critical parmeter.
The parmeters and uncertainty ranges evaluated and their of fect on heat transfer are given in Table 5.6-14.
The most critical source of uncertainty, the air side heat transfer coef fIcient, was conservatively assumed to have a 25% uncertainty. This was based on ESCDA data (Ref. 5.6-1) which Indicates a maximum uncertainty of 20%.
This uncertainty in air side heat transfer coef ficient could result in a 12.7%
reduction in PACC capacity. Combining alI the uncertainties given in Table 5.6-14 using the method described by Kline and McClintock (Ref. 5.6-9) results in a minimum PACC heat rejection rate of 15 W.
5.6.1.3.2.3 Thermal Hydraulic Stabilltv Thermal hydraulic stability in the PACC condensate return line and in the PACC heat exchanger bundle will be investigated analytically and experimentally (during component test) to assure there wilI be no signif-Icant impact on the PACC performance. The large condensate return lines will be designed to assure stability of the two phase gravity flow.
Flow instablilty is sometimes associated with parallel condensing tube bundles.
Features to ensure steam / water flow stability have been successf ully applied to eliminate flow Instabilities in gravity drains of moisture separator reheater tube bundles in steam turbine cycles of LWR plants. This will be addressed in the analysis, in the PACC unit, shell-side air or tube-side steam maldistribution would cause similar of fects.
Analytical and experimental development progres are currently underway to develop circumferential and axial flow distribution features (e.g., bundle air-side inlet and outlet perforated plate distribution screens) to provide suf ficiently uniform air flow distribution to assure that the outlet conditions of all tubes remain uniformly subcooled.
A three-dimensional flow analysis will be used to define the design of the required air flow distributing features. The design of these air flow distribution features will be refined and verified by tests using a one-fif th scale isothermal ai r f l ow model.
Final confirmation of acceptable air flow distribution and resulting uniformity of condensate subcooling will be obtained during the PACC lead unit test.
This will preclude unstable flow or cyclical cooling modes which have been observed under variable heat load conditions in similar heat exchangers.
Inlet orifices with four size variations to overcome the ef fect of manifold pressure variation are provided to preclude tube side flow maldistribution.
Individual tube oscIIlations may occur, even in the absence of system oscillations, since this is a f unction of the nature of Individual tube flow.
For PACC, oscil latory flow, corresponding to slug or plug flow, wil l be predicted over part of the condensation path. These flow regimes are expected 5.6-11c Amend. 69 i
Ju0s NK4
UL* UMM E Pzge 5 ( 82-0441) [8,05] #52 to impart some Individual tube oscillations. The design bases of the PACC tube to outlet header connection include a conservatively postulated cyclical subcooling f or which ASME code f atigue requirements will be met.
It is expected that the PACC air flow design and tube orificing capability will obviate system instability across the heat exchanger bundle.
Experience with reheater tube bundles suggests the Individual tube oscillations will be acceptabl e.
Specifically, this will be less severe than conservatively assumed cycling to be used in PACC f atigue design analysis.
A f ull-scale PACC test conducted prior to FSAR submittal with low pressure (165-250 psla) steam provides a means f or simulating PACC operation at CRBRP ref uel ing conditions. This condition is included as part of the PACC duty cycle which occurs during plant startup f rom and plant shutdown to ref ueling temperature of 4000F. This f ull scale PACC test, to be performed on the lead unit, wil l address thermal perf ormance and stabil ity.
5.6.1.3.3 Pumn Characteristics The f eed pump head and torque as a f unction of feed pump flow rate will be determined as the design progresses.
5.6.1.3.4 Valve Characteristics The flow coef ficients of all valves and the closing times of all isolation valves will be determined as the design progresses.
5.6.1.3.5 Ploe Leaks Pipe leaks can be categorized under Identified leakage and unidentified leakage.
Identified leakage is leakage into closed systems, such as from pump seals or valve packing leaks where the leakage is captured and directed to a sump or col lection tank. These leaks occur in system components where it is not practical to make the components 100% leaktight. The existence of Identified leakage is known in advance and is provided for in the system design.
5.6-11d Amend. 69 July 1982
Ref erences to Section 5.6 5.6-1 ES00A Fintube Engineering Manual,1979.
5.6-2 Boyko, L. D. and Kruzhll in, G. N., 94 sat transf er and hydraul ic resistance during condensation of steam in a horizontal tube and in a bundl e of tubes", Int. J. Heat Mass Transf er,10, pp. 361-373 (1967).
5.6 3
- Baker, 0., " Simultaneous flow of oil and gas", O!! and Gas Journal 2
11, p. 185 ( 1954 ).
5.6-4 Sol iman, M., Schuster, J. R. and Berenson, P. J., "A general heat transf er correlation f or annular flow condensation", J. Heat Transfer 90, p. 267 (1968).
5.6-5 Chato, J.
C., " Laminar condensation inside horizontal and inclined tubes", ASHRAE Journal, Vol. 4, No. 2, p. 52, February 1962.
5.6-6 Lockhart, R. W. and Martinel l i, R. C., " Proposed correl ation of data f or I sothermal twcrphase, twcr-component f Iow in pi pes", Chern. Eng.
Progress A1, p. 39 (1949).
5. 6-7 Baroczy, C.
J., " Correl ation of liqui d f raction in two-phase f low with application to liquid metals", NAA-SR-8171 ( April 1963), Atomics International, Canoga Park, Cal if ornia.
5.6-8 Baroczy, C. J., "A systemati c correl ation f or two-phase pressure drop", Chem. Eng. Prog. Symp. Ser. 52, No. 64, p. 232 (1966).
5.6-9 Kline, S.J., and ticClinlock, F.A., " Describing Uncertainties in Single-Sample Experiments", Mechanical {ngineering, January 1953.
-~
r
2I TABLE 5.6-14 PACC HEAT TRANSFER UNCERTAINTIES Heat Transfer Parameter Uncertainty Reduction. i Air-side heat transf er coef f icient i 25%
12.68 Water-slde heat transf er coef f Icient i 20%
.95
+
2
- 33 Al r-si de f oul Ing f actor hr-f t -F/ Btu 2
Water-slde f oulIng f acter i.0005 hr-ft -F/8tu 1.45 2
Contact thermal resistance between i.001 hr-ft -F/ Btu 2.26 the tube's and f Ins 2.72
[0.66
, Staggered In-l ne ficw ratio
/
i Ci rcumf erenti al ficw variation 30%
.67 Axlal fIow maldIstributIon i 10%
1.05 o
Air-side system pressure drops transition i f 0%
.18 Inlet louvres
[2
.90
+ 6
- 30 diffuser 0
casing i 10%
.04 screen (perf orated plate) i 20%
.27 coil assembly i 30%
.72 colI center i 15%
.76 expansion i 15%
.09
[2 1.26 outlet louvres 5.6 - 35!
82-0347
Pzgs 1 W82-0320 [8,223 59
~
Ouestion CS760.49 included in the continuing analysis submitted by the applicant in response to concerns voiced in Question Q001.581, reference is made to an Evaluation Basis Leak (EBL). This EBL is def ;ned as that sodium leak rate equal to the design sodium flow rate in the piping and is maintained until the maximum available system Inventory is discharged through the break for the primary HTS piping analysis. The applicant has translated this to specify a constant spill rate of 33,500 gallons per minute for 36 seconds. The basis for this assumption is not specifically defined.
For example, when a break occurs, the pumps will immediately respond by over-speeding due to the sudden depressurization.
Thus, it is unclear as to the constant spill rate assumption.
Furthermore, the arbitrary sudden termination at 36 seconds is not substantiated.
Provide in detall the basis for this EBL.
Substantiate for the assumed leak size that it provides a conservative leak rate.
Resoonse As stated in the response to Question Q001.581, the Evaluation Basis Leak (EBL) flow rate was selected to approximate the maximum flow from the PHTS piping into the Reactor Cavity, the PHTS ells, and the Overflow and Primary Sodium Storage Tank Cell.
The 36 second spill duration is obtained by dividing the maximum spill volume (20,000 gal.) by the flow rate (33,500 gal /m).
The break size assumed in the EBL is considerably beyond the design base. The piping Design Basis Leak (DBL) is defined and discussed in Section 3.6.1.1 of the PSAR. This DBL provides a conservative leak rate for system evaluation.
The analyses and test results are presented in WARD-D-0185, " Clinch River Breeder Reactor Plant Integrity of Primary and intermediate Heat Transport System Piping in Containment", September 1977, and show that no leak rate greater than 8 gpm can be deterministically derived.
in the hypothetical event that a leak as large as an EBL did occur, the Plant Protection System (PPS) would trip the sodlum pumps within seconds on either flow mismatch or speed mismatch.
Pump over-speed, would be prevented by the pump drive system controls.
Erroneous information to the pump flow controllers could not result in pump over-speed conditions beyond five percent because of the synchronous nature of the pump drive system.
Furthermore, there is no driving pressure in the PHTS to cause pump overspeed.
Since no reasonable conditions or physical mechanisms have been identified which would result in a leak rate of the magnitude identifled in the EBL It seems inappropriate to further analyze this event.
QCS760.49-1 Amend. 69 July 1982
@3-@S3@
P ge 2 W82-0320 [8,22] 59 Ouestion CS760.50 The applicant admits that the EBL sp!ll rate is not as high as might be postulated f or a double-ended rupture of the primary HTS piping. Thus, the potential for larger spil ls exists.
The applicant is requested to provide analyses addressing the consequences of sodium spills f rom the primary hot leg which a) include pipe break sizes up to a double-ended break; b) conservatively include the extent of cell liner failure, if any, initially assumed and c) If there is liner failure, utilize the sodium / water reaction data resulting from the Sandia experiments.
Resoonse As Indicated in Question Response CS760.49 further analysis of the EBL in the PHTS piping is inappropriate.
For similar reasons, analysis of a double-ended rupture is also inappropriate.
However, sensitivity analyses f or important input parameters to the SPRAY code f or sodium leaks from the hot leg of the Primary Heat Transport System (PHTS) piping into the PHTS cells have been perf ormed and are discussed in Question Response Q001.700. This sensitivity analysis encompasses the conditions associated with a double-ended rupture of the PHTS.
Analysis of a leak rate of 150 percent f ull flow (50,250 gpm) Indicated that cell pressurization greater than that from a hypothetical EBL would not occur.
(Figure Q001.700-3).
In all cases studied in the sensitivity analysis, the PHTS cell design pressure of 30 psig was not approached. Failure of the engineered safety feature cell liner would not occur as a result of a double-ended rupture of the PHTS piping.
QCS760.50-1 Amend. 69 July 1982
Pcge - 1 (8,22) #104 l'
/
\\'..-
5 i
Question CS760.113
['
~
j What are the SGAHRS system setpoints? At what drum level is. th's eyxil iary feed f ull and f ull of f ? How is the PACC controlled?
Response
The SGAHRS setpol.-ts are shown in the attached PSAR Table 7.4-2.
Following a SGhiRS primary inf riattor. (high main steam to main f eedwater flow ratio) the motor driven pumps will begin to f eed the steam drum when the drum level drops to 4 inches below Normal Water Level (NKL) and control the water level in each drum at 4 inches below MWL. With a secondary SGAHRS Initiation (low steam drum level) the motor driven pumps will begin to f eed each steam drum when the drum level drops to 8 Inches beluw NWL and con ^rol the level in each drum at 4 inches below NWL. The turbine-driven pump wlVilstart delivering water to each drum when the drum level drops to 18 inchep below NWL and f,
maintain steam drum at that level. The AFW flowr, to esca individual steam 7
drum are controlled automatically by control valve' cortfol lers.
,p PACC control is described in revised PSAR section 7.4.1.1.2.
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3 QCS760.113-1 Amend. 69 July 1982
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Materlsl Soecifications i
'I ' ' ' A IIst of material speci f ications f or the SGAHRS vessels, piping, pumps, and
/, ve(ves is given in Table 5.6-3.
Corresponding weld materials specifications
' are listed i n Tabl e 5.6-4.
5.6.1.1.5 Leak Detection Reautrements Leak detection requirements for the SGAHRS are as f ollows:
e 1
a.
Excessive leakage of high pressure and temperature water f rom the
/
/
steam gener'ator system into the SGAHRS will be detectable i
b.
Excessive leakage of low pressure water will be detectable T$c methods used for leak detection are described in Section 5.6.1.2.5.
5.6.1.1.G Instrumentation Reaufrements 1
'l l
Functional requirements of the SGAHRS Instrumentation are to monitor the i
following paraneters and to wcrn the plant operator of any abnormal or dangerous conditions in the folicwing parameters:
- 1. Protected water storage tank level, pressure, and temperature
- 2. Auxiliary feedwater pump Inlet pressure and temperature
- 3. Auxiliary feodwater. pump discharge temperature and pressure
- 4. Auxiliary f eedd$ter flow and temperature
- 5. Position of all Isolation and control valves
- 6. Drive turbino steam supply and discharge pressure
- 7. Operating status of protected air cooled condenser
- 8. Operating status of all motors
- 9. Startup of air-cooled condenser
- 10. Startup of auxillary feedwater pumps.
The plant protection system Instrumentation and control equipment associot d with the active components which must operate to insure that SGAHRS performs i.
Its saf ety f unction are described in Section 7.4.
The SGAHRS control set points are included in Table 7.4-2 "SGAHRS Nominal Set Points."
i r a 3 /*
i 1
3-
.p j
5.6-3 c.
Amend. 69
f, !
July 1982 4
P ge - 1 (8,07) #26 7.4 INSTRUMENTATION AND CONTROL SYSTEMS REQUIRED FOR SAFE SHUTDOWN The instrumentation and Control Systems necessary for saf e shutdown are those associated with monitoring of core criticality, decay heat removal (SGMRS portion), outlet steam isolation, and control room habitability.
Monitoring of core criticality is ef fected by the Flux Monitoring System (Section 7.5.1).
The control room habitability is covered in Chapter 6.
Thus, 'this section treats the control and instrumentation needs f or decay heat removal by the Steam Generator Auxillary Heat Removal System (SGAHRS) and outlet steam isolation by the Outlet Steam isolation System (OSIS); control and Instrumentation f or Direct Heat Removal Service (DHRS) is discussed In Section 7.6.
7.4.1 Steam Generator Auxfilarv Heat Removal Instrumentation and Control Svstem 7.4.1.1 DesIon DeserIotIon 7.4.1.1.1 Function The SGMRS,(fluid system and mechanical components as described in Section 5.6.1, and electrical components as described below) provides the heat removal path and heat sink for the nuclear steam supply system following upset, emergency, or f aulted events which render the normal heat sink unavailable.
The SGAHRS Instrumentation and Control System in conjunction with the PPS detects the need f or, initiates, and controls the alternate heat removal path when the normal heat sink is unavailablo. The SGAHRS nominal control setpoints shown in Table 7.4-2 are discussed in the following subsections.
7.4.1.1.2 Eauloment DesIon The mechanical system for which the SGAHRS l&C is provided is briefly described below.
When actuated, the SGAHRS draws water from a Protected Water Storage Tank and pumps it to each steam drum. Two supply lines are provided for each steam l
drum. One line is supplied by two half-sized, motor-driven feedwater pumps while the other is supplied by a f ull-sized, turbine-driven pump.
Each supply line provides a flow control valve and an isolation valve at the inlet to each l
steam drum. The isolation valves are provided to isolate the auxillary feedwater system from the steam generator system during power operation and to j
provide leak isolation during SGAHRS operation.
In addition, a Protected Air Cooled Condenser (PACC) supplied with each steam 1
drum is placed into operation.
This system rejects heat to the atmosphere via l
convection.
Saturated steam is supplied to the condenser from the steam drum l
l 7.4-1 Amend. 69 July 1982
o.
o,v, Pcge - 2 (8,07) #26 and saturated water is returned.
This steam and water loop is driven by natural circulation.
Each PACC unit consists of two tube bundles, two sets of louvers and two f ans.
Regulation of heat rejectiors is accomplished by controlling the air flow across the condensing tubes through adjustment of inlet louver and f an blade pitch positions. The air side flow is driven by either forced or natural convection.
The arrangement of SGAHRS equipment is shown in Figure 5.1-5 (SGAHRS P&lD).
Instrumentation and controls are provided for the components described below:
o Auxillarv Feedwater Pumo Control - Upon receipt of the SGAHRS Initiation signal, (see Section 7.4.1.1.3), the two motor driven pumps are started, resulting in both pumps coming on line and operating at constant speed.
in addition, the Isolation valves in the steam supply lines f rom the steam drums to the turbine driven pump are opened.
At the turbine inlet a pressure regulating valve reduces the steam supply pressure to the 1000 psig required by the turb!ne drive.
The turbine drive mechanism is equipped with a governor to provide speed regulation.
Each auxillary feedwater pump can also be actuated manually at the operator's discretion.
Each pump control incl udes a " Normal Long Term Cool down (LTC)" mode se l ector.
In " normal" mode, the pumps start on SGAHRS Initiation.
in the "LTC" mode, the operator may shutdown any or all AFW pumps provided the steam drum water level is above the trip point setting.
When in the "LTC" mode, the pumps come on line automatically when the steam drum water level drops to a low level trip point.
o Auxf ilarv Feedwater Flow Control - The Auxiliary Feedwater isolation Valves are opened upon receipt of the SGAHRS Initiation signal.
During SGAHRS operation, these valves close automatically upon Indication of a sodium / water reaction, a high steam drum level, a steam drum pressure less than 200 psig, or AFW flow greater than 150%
of f ul l fl ow f or 5 sec.
This automatic closure occurs only In the af f ected loop.
If the valves are closed by a high drum level signal they will reopen automatically when the drum level f alls to the low drum level trip point. The flow to the steam drum is controlled with a control valve that is positioned by a single controller.
Manual control of the Auxillary Feedwater Flow Control valves is provided at the main control panel and at the local SGAHRS panel.
7.4-2 Amend. 69 July 1982
64 o,v, Pcge - 3 (8,07) #26 o
Protected Air Cooled Condenser Control - The Protected Air Cooled Condenser louvers are opened and the f ans started upon receipt of either a SCRAM or the SGAHRS Initiation signal. The PACCs control l
the steam drum pressure to a variable setpoint with a nominal setting 8
of 1400 psig by regulating heat rejection.
Regulation of heat rejection is accomplished by controlling the air flow across the condensing tubes thru adjustment of inlet louver & f an blade pitch positions.
During the airside f orced convection mode of PACC operations, the air flow is varied by changing f an blade pitch with inlet louvers maintained at f ull open position.
In the natural circulation mode of PACC operation, the air flow is vorled by changing the position of the inlet louvers. The fan blades and inlet louvers are positioned by automatic controllers.
Manual control of the inlet louver position and f an blade pitch is provided. Manual controls are also provided f or the blower motors. The outlet louver is Interlocked with the inlet louver.
It opens automatically when the inlet louver actuator is energized.
if a high concentration of sodium aerosol in each PACC cell is detected, redundant trip logic generates trip signals to shutdown the ef fected PACC system for approximately 1 1/2 hours.
o Pressure Controlled Bvoass Valve - To prevent overheating of the Auxiliary Feedwater Pumps at reduced flow, each pump is provided with a bypass line f rom the discharge back to the Protected Water Storage Tank. The valve in the bypass line is normally open upon initiation during pump startup.
Af ter startup, the valve closes and then opens when pump discharge pressure rises to 1970 psig and closes when the pressure drops below 1820 psig.
o Auxillarv Feedsater Isolation Valves and Pumo Inlet isolation Valves - The isolation valves in each of the supply lines to the steam drums (AFW lsolation valves) are provided to insure an uninterrupted supply of auxillary feedwater to unaf fected loops following f ailures in a loop which would otherwise limit the ef fectiveness of the auxillary feedwater system. The isolation valves at the pump Inlets are provided to prevent loss of water from the Protected Water Storage Tank (PWST) in the event of a failure between these valves and the AFW isolation valves and to allow switching suction from the PWST to the condensate storage tank.
o Suoerheater and Steam Drum Vent Control Valves - These valves are opened upon SGAHRS Initiation and depressurize the steam drums to the valves respective setpoint levels. The superheater vent control valve setpoint is 1475 psig and the steam drum vent control valve setpoint is 1550 psig.
The valves f unction to provide steam release during the venting period until the PACC units can renove the heat load in a closed loop manner.
7.4-2a Amend. 69 July 1982
w o,w, Pcge - 4 (8,07) #26 o
PACC Noncondensible Vent Valve Control These valves are provided to vent noncondensibles from the PACC tube bundles during normal plant and PACC operation, and for PACC heatup following maintenance.
Control of PACC noncondensible vent valves is by differential temperature control. The temperature dif ferential between a concentration of non-condensible gases in a collection pipe and saturated stean temperature, measured in the PACC outlet header, opens the vent valve.
Venting is stopped when saturated steam enters the collection pipe and the temperature dif ferential drops below the set point. The valves are also capable of actuation by remote manual operation.
7.4-2b Amend. 69 July 1982
P:ge - 5 (8,07) #26 TABLE 7.4-2 SGAHRS NOMINAL SET POINTS Set Point SGAHR$ Primary Initiation Signal:
High Main Steam to Main Feedwater Flow Ratio 1.3 SGAHRS Secondary Initiation Signal:
Low Steam Drum level (Inches from Normal Water Level)
-8 Turbine-Driven AFW Pump operating Speed (RPM) 4000 AFW Pump Recirculation Valve (52AFV-108) (Note 1)
Pump Pressure - Open Valve 1970 (ps!g)
Pump Pressure - Close Valve 1820 (psig)
AFW Control Valve (52AFV-104 (Note 1):
Steam Drum Level Control:
Motor-Driven Pumps (In.
from normal water level (note 6)
-4 Turbine-Driven Pumps (In.
from normal water level (note 6)
-18 Flow Limiter ( lbm/hr) 264,500 Drive Turbine Pressure Control Valve (52AFV-121)(psig)(Note 1) 1000 Controls steam pressure to Drive Turbine at:
7.4-10a Amend. 69 July 1982
o,.,
Prge - 6 (8,07) #26 TABLE 7.4-2 I
SGAHRS NOMINAL SET POINTS (cont'd)
Set Point AFW lsolation Valve (52AFV-103 (Note.1):
Valve Closes on:
High AFW Flow for 5 sec.
(1bm/hr) 378,000 Low Steam Drum Pressure (psig) 200 High Drum Level (in, from
+8, +12 normal water level (Note 2 and 6)
Sodium / Water Reaction Indication AFW Pump Test Loop Isolation Valves:
SGAHRS Valves Close on the SGAHRS Initiation signal initiation Steam Drum VU t Valves (52AFV-117) (psig) (Note 1) control 1550 Steam Drum Pressure att Superheater Vent Valves (52AFV-116) (psig) (Note 1) control 1475 Steam Drum Pressure at:
Steam Drum Level at which AFW pumps automatically restart in i
Iong term cooldown mode (inches f rom normal water level):
Motor-Driven Pump (52AFP002A)
-8 Motor-Driven Pump (52AFP0028)
(Note 3 and 6)
-8 Turbine-Driyen Pump (52AFP001)
(Note 4 and 6)
-18 l
i Protected Air Cooled Condenser (PACC)
(psig) controls steam drum pressure at:
1400 During ref ueling and oiher long term cooldown operations: PACC nominal setpoint is 250 (psig)
PACC Vent Valves (52ACV-129 (Note 1) Control by:
Note 5 l
7.4-10b Amend. 69 July 1982
w.
w,v, P:ge - 7 (8,07) #26 l
l TABLE 7.4-2 NOMINAL SET POINTS (Cont'd)
NOTES 1.
The capability for the operator to assume manual control of the Indicated f unctions f rom either the control room or the local panel is provided.
2.
Valves will reopen should steam drum level f all to the low level trip (-8 in from normal water level).
Valves in the motor-driven AFW pump loops close at +8 In. from normal water level while the valves in the turbine-driven AFW pump loops close at +12 In. from normal water level.
3.
In the long term cooldown mode, the second motor driven pump automatically restarts af ter a 1-minute delay if steam drum level remains at -7 in. or l ower.
4.
Steam drum pressure must be above 1000 psig to initiate turbine operation.
5.
PACC vent control valves are controlled by the temperature dif ferential between the noncondensible gas collection pipe and the steam saturation temperature measured in the PACC outlet header.
6.
Normal steam drum water level is 1 inch above drus centerline.
7.4-10c Amend. 69 July 1982
P;ge - 3 (8,22) #104 QuanthGS760.116 The presentation describing the protected air cooled condensers (PACC) needs cl ari f ication. Details are needed with respect to tube size and number, tube Inner and outer disneter, air volume constraints, estimated natural draf t air speed, f an speeds, and so f orth.
Natural circulation is easily demonstratable i f the heat transf er is known.
It is essential that the heat removal capability be established f or the PACCs under the varying operating conditions.
Resoonse A description of the PACC heat exchanger tubes is provided in revised PSAR Section 5.6.1.2.3.1, " Protected Air Cooled Condensers (PACC)."
The forced draf t air flow for each tube bundle is provided by an axial flow fan which operates at 1200 rpm.
At thermal hydraulic design conditions, the air flow is 77600 SCFM with a corresponding f an design power requirement of 53 bhp.
The PACC design will provide air flow control from 10 to 100 percent of rated f l ow.
The PACC design wil l have natural draf t capability.
Under natural draf t operdtion an estimated heat renovel capability of 32 percent per PACC is available and lead unit tests will be perf ormed at reduced water / steam side pressure to confirm the natural draf t heat rejection capability.
l I
i l
l l
QCS760.116-1 Amend. 69 July 1982
P ge 1 (82-0434) [8,05] #50 5.6.1.2.3.1 Protected Air Cooled Condensers (PACC) nnenonent Descriotion The PACC is a tube-type steam condenser constructed of carbon steel. Heat is rejected to the atmosphere by condensing the saturated steam from the steam drums by forced circulation of air over the tube bundles.
Each unit is sized to reject 15 MWt under conditions of f orced convection on the air side and natural circulation flow on the steam / water side. Each PACC has two hal f-size tube bundles, two variable blade pitch f ans and two sets of variable position louvers to control airflow and, therefore, heat rejection.
The electrical power supplies and Instrument and control circuits f or the PACCs are Class IE.
Refer to PSAR Section 7.4 for inf ormation on the power sources and l&C.
The arrangement of PACC is illustrated in Figures 5.6-8 and 5.6-9.
Air is del ivered f rom axial f ans (one f or each tube bundle) into the Insulated plenum surrounding each tube bundle.
Air flows circumferentially around the tube bundle, then radially inward through the fin tube bundle into a central core.
Air then flows upward through the central core and exhausts through louvers to an exhaust stack.
Each tube bundle consists of 50 finned tubes connected in parallel between vertical pipe headers.
Each tube is approximately 100 f t. long and, of the 100 ft, length, 95 f t. Is f inned. The Individual finned tubes are formed in a conical spiral of approximately four concentric turns with a slope toward the center. The tubes are connected in parallel between vertical pipe headers.
The inlet header is on the outside and outlet header is in the center of spiraled coils. The finned tubes are made of 2 inch 0.D. tubes with 0.156 inch minimum wall as shown on Figure 5.6-10.
The 0.D. of the f in is 3.28 inches. The fins are serrated into 0.156 inch segments f rom continuous strip 0.050 inch thick x 0.75 inch wide. The strip is f irst f ormed into the shape of an "L".
The strip is then wound around the tube 0.D. to complete the footed fin attachment to the tube. There are two separate tube bundles in each PACC.
Design Data Design Conditions:
Pressure 2200 psig Temperature 650oF Thermal Hydraulic Perf ormance:
Heat Removal 15 MWt (7.5 MWt per tube bundle)
Steam Pressure 1450 psig Steam Temperature 592oF Moisture 0%
Condensate Tanperature 5920F Air Temperature 1000F Air Pressure 14.3 psia 5.6-6 Amend. 69 July 1982
Paga 2 ( 82-0434) [8,05] #50 4
Design Criteria The power supplies to the PACC f ans, Instrumentation and contro'Is are Class IE.
The instrumentation and Control System is a safety related system and as such will meet the requirements of the regulatory guides and standards as listed in Tables 7.1-2 and 7.1-3 of the PSAR.
The means of compliance are described in Section 7.1.2.
l Three'PACC units are provided, one f or each heat transport loop, each capable of removing the total decay heat approximately 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> af ter shutdown.
Each unit is single active f ailure proof in that no single active f ailure will l
result in the loss of more than 50% of heat renovel capability. This is provided by utilizing two tube bundles, two f ans, etc., such that at least hal f capacity is retained following the f ailure.
The PACC unit is a Seismic Category I design, hardened against tornado missiles and designed to withstand the pressure loads f rom tornados. The PACC tube bundle design is based upon standard techniques f or steam-to-air heat exchangers.
Ooeration and Control The airflow is regulated by the use of variable position inlet louvers and f ans with variable blade pitch. There are separate controls f or the air side of each PACC f or each of the two f ans and f or each of the two sets of louvers. '
The Inlet louvers and f an blade pitch are positioned by controllers which compare steam drum pressure to the setpoint and generate position demand signals to the louvers and f an blade pitch drives as required to maintain pressure at the setpoint value.
In order for the PACC to ef fect heat rejection control over the range of operation there are two modes of air side operation:
(1) Forced convectlon with the louvers open and airflow varied by changing the fan blade pitch.
(2)
Natural circulation with airflow varied by changing the position of the Inlet louvers.
The range of automatic operation is from 15% to 100% heat rejection.
From 100% down to approximately 30% (4.5 MWt) the unit is operating in the first mode, and f rom 30% to 15% in the second mode.
Control is accomplished by sensing and maintaining the steam pressure at the desired set point.
W 5.6-6a Amend. 69 July 1982
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figure 5.6-10 flominal PACC Tube and Fin Geometry S.6-45 Amend 69 July 1982
Page 1 (W82-0421) #115 Ouestion CS760.131 Transient Effects (5.7.5)
In general, the design transients are not sufficiently described to understand the conditions or the analytical results.
The transients are said to be more fully described in Chapter 15 but clarification is needed.
In particular, the analysis for the OBE in Chapter 5 quotes a 5 minute manual plant trip whereas the respondence between Chapter 5 and 15 analyses for the loss of steam generator load is not sel f-contradictory, but needs to be addressed due to the difference in time scales, a.
What are the difference between the results presented in 5.7 and those analyzed in Chapter 15.
Provide justification for differences, b.
For the loss of load transient (Section 5.7.3d) provide the steam generator temperature and pressure response and the core temperatures to 2000 seconds.
Response
No inconsistency between Chapters 5.7 and 15 has been identified.
It should be noted that the apparent difference in the discussion of the Operating Basis Earthquake (OBE) in these two chapters is due to the dif ferences in application of the OBE to the HTS (Chapter 5.7) and to the Reactor (Chapter 15.2 Reactivity insertion Design Events).
Paragraph 5.7.3.c has been amended to clearly describe the application of the OBE to HTS component analyses.
The steam generator temperature and pressure response and core temperature response is provided in Figures 5.7-6a-k.
These data are based on the plant thermal hydraulic design conditions with the hot and cold leg sodium l
arbitrarily increased 20 F.
It should be noted that inadvertant actuation of the water / steam side of the Sodium / water Reaction Pressure System results in dumping of water / steam sides of both evaporators and the superheater.
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QCS760.131-1 Amend. 69 July 1982
Prga - 2 (8,05) #49 Uncontrolled rod withdrawal during startup also results in an up temperature transient at the reactor vessel outlet although the transient occurs at a lower temperature than when the rod withdrawal starts from 100% power.
Figure 5.7-5 depicts the transient Initiated during startup.
Ooerating Basis Earthauake (OBE)
The operating basis earthquake results in reactive forces acting c.
on fue plant components as described in the Seismic Criteria Document.
Five OBEs, each with 10 maximum peak response cycles, are assumed to occur over the design life of the plant.
Four of these OBE's are assumed to occur during the most adverse Normal Operating Conditions determined on a component and design limit basis. The other one OBE is assumed to occur during the most adverse upset event determined on a component and design Iimit basis, and at the most adverse time in the upset event.
Thus, the plant components are simultaneously exposed to the thermal ef fects of the thermal transients as welI as the stresses of the OBE.
Loss of Steam Generator Load d.
Isolation and dumping of the water / steam sides of both evaporators and the superheater removes the load from that loop. This results in up temperature transients on the steam generator module::,, the Intermediate cold leg, the IHX Intermediate inlet, the IHX primary outlet, and the reactor vessel inlet. The ensuing reactor trip then causes down temperature transients on these components. The 0
intermediatecoldlegtemperatureincreasesagproximately350 Fin 400 seconds; then decreases app'roximately 220 F in 300 seconds.
This transient is then transported to the IHX primary outlet and reactor vessel inlet.
Figures 5.7-6 a-k presents the resulting transient at the Intermeldate sodium pump, core & steam generators, Inadvertent Ooening of Suoerheater Outlet Power or Safety e.
ReIIef Valve This event results in a large increase in load without an accompanying increase in reactor power or sodium flows.
It occurs when a super-heater relief valve inadvertently opens to increase steam flow from 40% to 100%. The event results in a reactor trip but overcooling occurs due to the open relief valve. The steam generators, inter-mediate cold leg, lHX Intermediate inlet, primary cold leg and reactor vessel inlet drop in temperature about 150 F in 100 seconds.
The reactor vessel outlet, primary hot leg, and lHX primary inlet drop in temperature about 200 F in 75 seconds.
Figure 5.7-7 depicts the transient at the intermediate pump.
.i 5.2-4 i
Amend. 69 July 1982
page 1 W82-0433 (8 5) 48 0
TABLE 5.7-1 (continued)
PRELIMINARY SUP44ARY OF HEAT TRANSPORT SYSTEM DESIGN TRANSIENTS Frequency (Lifetime)
Primary DUTY CYCLE Event Reactor Primary Inter. Check Super-EVENT NUP0ER, Title Vessel IHX Pump Pump Valve Evap.
heater U-11b Water side Isolation & blowdown of 7
7 evaporator module U-11b Adjacent evaporator during water side 9
9 Isolation and blowdown of evaporator U-21e Adjacent evaporator outlet relief 3
3 valves open E-9a Superheater isolation & blowdown-outlet Note 4 Note 4 valve open E-1g Inadvertent dump of Intermediate sodlum Note 4 Note 4 l
OBE Operating basis earthquake 5
5 5
5 5
5 5
E-16 Three loop natural circulation Note 4 U-21b inadvertent opening of superheater 42 19 24 14 26 13 13 outlet power or safety relief valve U-23 Inadvertent opening of evaporator 33 37 Inlet dump valve 5
5 U-8 Primary pump pony motor failure
- 15 5
Note 4 E-1 Primary pump mechanical failure Note 4 Note 4 E-5 Loss of one primary pump pony motor with Note 4 Note 4 Note 4 Note 4 Note 4 failure of check valve In that loop to shut Note 4 -
Note 4 Note 4 E-6 Design basis steam generator sodlum/
Note 4 water reaction Note 4 Note 4 E-7 One loop natural circulation (from Note 4 Note 4 Initial two loop operation) 2 2
2 2
E-15 DHRS Activation 24 Hours After Scram 2
2 E-16 Three loop natural circulation Note 4 Note 4 Note 4 Note 4 Note 4 Notes:
4.
Each component, or part of a component, must accommodate 5 occurrences of the most severe emergency transient for that component or part of a component (one every 6 years) and two consecutive occurrences of the most severe event (or of unlike events if consecutive occurrences of unlike events provide a more severe offect than two occurrences of the most severe event).
5.
See Paragraph 5.7.3(c) 5.7-8 Amend. 69 July 1982 o,.e n,
Figure 5.7-6a Average Channel Sodium Exit Temperature Top of Active Core vs.
Time for loss of Steam Generator Load (Dumping of Water / Steam Sides of Both Evaporators and the Superheater) 1200 1100 1000 C
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600 500 0
1000 2000 TIME (SECONDS) 5.7-14a Amend 69 July 1982
e w~~e page 2 W82-0440 [8,22] 119 Figure 5.7-6b Maximum Channel Sodium Exit Temperature, Top of Active Core for Loss of Steam Generator Load (Dumping of Water / Steam Sides of Both Evaporators and the Superheater).
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pago 3 W82-0440 [8,22] 119 Figure 4.7-60 Blankot Hot Channel Sodium Outlet Tcanperature f or Loss of Steam Generator Load (Dumping of Wator/ Steam Sides of Both Evaporators and the Suporheator).
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pag [4 W32-0440 [8,22] 119 Figure 5.7-6D Reactor Vessel Exit Tcrnperature f or Loss of Steam Generator Load (Dumping of Water / Steam Sides of Both Evaporators and the Superheater).
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page 5 Wa2-0440 [8,22] 179 Figure 5.7-6E Af f ected Loop Superheater Sodium inlet Tunperature for Loss of Steam Generator Load (Dumping of Water / Steam Sides of Both Evaporators and the Superheater).
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w uwe page 6 W82-0440 [8,22] 119 Figure 5.7-6F Af fected Loop Evaporator Sodium inlet Temperature f or Loss of Steam Generator Load (Dumping of Water / Steam Sides of Both Evaporators and the Superheater).
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TIME (SECONDS) 5.7-14F Amend. 69 l
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un,a page 7 M82-0440 [8,22] 119 F igure 5.7-6G Af f ected Loop Evaporator Sodium Exit Tcrnperature for Loss of Steam Generator Load (Dumping of Water / Steam Sides of Both Evaporators and the Superheater).
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vs,a pags 8 W82-0440 [8,22] 119 Figure 5.7-6H Intermediate Pump Sodium Temperature Vs. Time f or Loss of Steam Generator Load (Dumping of Water / Steam Sides of Both Evaporators and the Superheater).
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July 1982.--- --- -
page 9 W82-0440 [8,22] 119 Figure 5.7-61 Affected Loop Drum Steam Tanperature for Loss of Steam Generator Load (Dumping of Water / Steam Sides of Both Evaporators and the Superheater).
800 700 600 C
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1000 2000 TIME (SECONDS) l 5.7-141 l
Amend. 69 July 1982
hgI[b W82-0440 [8,22] 119 Figure 5.7-6J Af f ected Loop Evaporator inlet Water Tcrnperature f or loss of Steam Generator Load (Dumping of Water / Steam Sides of Both Evaporators and the Superheater).
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Figure 15.3.1.7 IC Temperature of Hot Spot as a Function of Time After inadsertant Actuation of tiie Water / Steam Side of the i
Sodium hater Reactor Pressure Relief Sprem 720.118 4
15.3-28b Amend 69 July 1982 l
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Figure 15.3.1.7-1B. Temperature of Core inlet as a Function of Time After inadvertant Actuation of the Water / Steam Side of the Sodium / Water Reactor Pressure Relief System 7203-17 15.3-28a Amend 69 July 1982 y
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Figure 1. 3.1.71 A. Temperatures of Affected Loop as a Function of Time After inadsertent Actuation of the Water: Steam Side of the Sodium. Water Re a c t i o n Pressure Relie f Sys tem 7203-16 Amend 69 15.3-28 July 1982
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