NSD-NRC-96-4896, Responds to Comments on AP600 Emergency Response Guidelines
| ML20133G345 | |
| Person / Time | |
|---|---|
| Site: | 05200003 |
| Issue date: | 01/09/1997 |
| From: | Mcintyre B WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | Quay T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NSD-NRC-96-4896, NUDOCS 9701150313 | |
| Download: ML20133G345 (11) | |
Text
Westinghouse Energy Systems ll1j3{5 Electric Corporation u gh Pennsylvan:a 15230 0355 NSD-NRC-96-48%
DCP/NRC0669 Docket No.: STN-52-003 January 9,1997 Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION:
T. R. QUAY
SUBJECT:
WESTINGHOUSE RESPONSE TO COMMEN'13 ON AP600 EMERGENCY RESPONSE GUIDELINES (ERGS)
REFERENCE:
NRC LEITER FROM W. C. IIUFFMAN TO N. J. LIPARULO DATED AUGUST 19,1996, " COMMENTS ON AP600 EMERGENCY RESPONSE GUIDELINES" Dear Mr. Quay-
'Ihe referenced letter provided NRC comments to Revision 1 of the AP600 Emergency Response Guidelines. We have reviewed the NRC comments and defined a resolution path. As indicated in the attachment to this letter, we have provided additional information on the ERG contents or made a commitment to update the ERGS, the AP600 Background Doce. ment, or both as appropriate. Several changes to Table 7.5-1, " Post Accident Monitoring System" in Chapter 7 of the SSAR are also proposed.
I f
Brian A. McIntyre, Manager i
Advanced Plant Safety and Licensing I
Attachment cc: Nicholas J. Lipamlo - Westinghouse (w/o attachment) b William C. Iluffman - NRC (w/ attachment)
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9701150313 970109 DR ADOCK 05200003 PDR lE!4L' e pf
Attaclunent A to NSD-NRC-%48%
i Westinghouse Response to NRC Comments on AI%00 Rev.1 ERGS January 9,1997 1
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Westinghouse Response to NRC Comments on AP600 Rev.1 ERGS AFA)
REACf0R TRIP OR SAFETY INJECTION Step 1 - Verify Reactor Trip Comment: There is no " bypass breaker" in the AP600 design. The statement "to verify bypass breaker open" is not correct.
Westinghome Respmse: The AP600 ERGS will be revised to eliminate referewe to " bypass breakers".
Step 3 - Check If Safety Injection Is Actuated Comment: The guidance for "Instmmentation to determine if safety injection is required" should be more specific. Identify the parameters that will be used to satisfy this action.
IVestinghouse Response: Dw AP600 Background Docunwnt will be revised to include the parameters taed to check ifsafety injection is actuated 7hese prameters inchide PAS mlve position indicatiom, PRHRflow rate Accumulator and CMTlevel, CMTtemperature. These imtruments are in SS4R Table 7.5-1.
Step 11 - Verify Passive Containment Cooling (PCS) not Required Comment: The guidance for "PCS indication" should be more specific. Identify the parameters of the PCS that will be used to implement this guidance.
Westinghome Respome: The AP600 ERG Backgrowullheuments will be revised to include the parameters med to verify PCS actuation such as PCS mlve position indication. These prameters are in SS4R Table 7.5-1.
Step 13 - Verify Power To Emergency Cooling System AC Busses Comment: The instruments for " Voltage indication for emergency cooling ac busses" should be specified in Table 7.5-1.
Westinghome Res;x>me: The terminology in the ERG Background will be revised The ECS AC Busses (m called out in Step 13) are referred to in the background doewnent as " Emergency AC Bmses." The correct terminology is " Main AC Pouer System diesel-backed bases."
SS4R Table 7.5-1 has been revised to incorporate the jnrameter "Voltagefi>r the diesel-backed busses".
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i Step 14 - To Block the Low-3 RCS T-cold to Restart SRV Pumps Comment: 'Ihe instruments fbr " Low-3 RCS T-cold block status indication" should be specified in Table 7.5-1. The controls for " Blocking Imw-3 RCS T-cold" should be specified in the control logic 4
j diagram.
ll'estinghome Respume: Statm indication ofPAS actuation, reset, or block signals are twt provided in S%1R 1able 7.5-1. This Table provides the residts ofan analysis conducted to idernify tlw appropriate design bases and quahfication criteriaf>r imtrwnentation ernployed to monitor corulitiom in the RCS, sec<nulary heat removal system, the containment, and the systems medfor attaining safe shutdcnnt The selection ofimtrumentation is based on the guidance provided in Reg. Guide 1.97.
7he PASstatus indications are compiner generatedsignals arulnot associated uithfield-mow 1ted instrimients. They do twt meet the criteriaprovided in Reg. Guide 1.97 and are therefore twt inchuled in S%1R Table 7.5-1.
This statm infornxnion is disemsed in SW1R subsectiom 7.1.4.2.13 and 7.1.4.2.20.
The controlsfor blocking the Lo e RCS T-cold isolation ofstartupfeeduater are shoun onfigure 7.2-1, sheet 9.
Step 23 - Check If SG Tubes Are Intact Comment: The instruments for indication of " Condenser air ejector mdiation" should be specified in j
Table 7.5-1.
1 II'estinghome Respome: The ilP600 ERGS and backgromuldocument uill be revised to reflect the proper terminology. The term " condenser air ejector radiation" uill be revised to " turbine island vent discharge radiation" uhich performs the samefimetion and is inchuled in S%fR Table 7.5-1.
Step 28 - Deaerator Storage Tank Level Decrease Comment: The instruments for "Deaerator storage tank level indication" should be specified in Table 7.5-1.
Il'estinghome Respome: Subsequent to the issuance ofthe 11P600 ERGS, the ilP600 design uas nu>dified such that the startupfeedmuer pwnps no longer take suctionfrorn the deaerator. The<1P600 ERGS and backgrowid document uilt be revised to reflect this design nxxhficatiort This uill residt in the references to "deaerator storage tank level" being removedfrom the ERGS.
Step 29 - Check Secondary Radiation Comment: The instruments to " Indicate secondary radiation level" should be specified in Table 7.5-1.
II'estinghome Response: 1he 11P600 ERG Ikickgrowxt docwnent uill be revised to indicate tixit the SGS main steamline radiation imtrumentation uill be used to check secondary radiatiort 7his pirameter is inchuledin S%tR Table 7.5-1.
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Step 30 - Check If ADS Should Be Actuated Comment: The instruments for " Normal residual heat removal system pumps status' should be specified in Table 7.5-1.
l Westinghaine Respome: he parameter "RNSpunp statm" uill be added to S%1R Table 7.5-1 Step 31: - Check Building Radiation Comment: The instruments to achieve the " Auxiliary Building radiation nunitor" should be specified in Table 7.5-1.
ll'estinghaine Respame: The imtrwnents to detect radiation in the aiailiary or antwx building are in SUR Table 7.5-1 and uill be added to the ERG Background document. This parameter is de " Plant Ttm Radiation lael".
Step 33 - Reset Containment Isolation Comment: The instruments for " Containment isolation indication" should be specified in Table 7.5-1.
Westinghouse Resp >nse: Status indicatian of PAS actuation or nlock signals is not provided in S%IR Table 7.5-1 as discussed in the respome to Step 14 above.
Step 35 - Check If Diesel Generators Should Be Stopped Comment: The instruments for indication of "OfTsite power rtatus, diesel generator load, emergency cooling system ac busses power, diesel generator openuug" should be specified in Table 7.5-1.
Westinghome Respome: The purposepr Step 35 uill be revised in the ERG Backgrowxt document.
In most Westinghaiae plants, the diesel generators start on an scfeguards actuation signal, regarcRess of the statm ofoffsite pouer. This can result in the diesel generators running w1loadedfbr a period oftime. In the AP600, the diesels only start on low voltage to the diesel-backed bmses ofthe Main AC l'mer System (ECS). Therefore, the condition where the diesel generators are running unloaded shoidd twt existfor the AP600. The purp>se of this step is to assess the status of the diesel generators 8
and offsite puer, to determine of the diesels should be stopped and to determine if additional loads shoidd be added The terminology in the ERG backgrowuldocumentfor the imtrumentation necessary to accomplish this task uill be revised asfollows: " Emergency cooling system ac biases pmer" will be revised to "wltagefor the diesel-backed biases"; " Diesel generator operating imtrum Wion" uill be revised to
" diesel gerwrator statm."
Parametersfor " diesel generator load", " diesel-backed busses voltage", and "Pouer Supply to diesel-backed busses" uill be added n S%1R Table 7.5-1. The status indicationfor the compments that are automatically loaded onto dw Jesel are provided in SSAR Table 7.5-1.
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J AE-1 LOSS OF REACTOR OR SECONDARY COOIANT 1
Step 2 - SFW Pump Suction Transfer to the CST Comment: %e instruments for "Deacrator storage tank level indicetion" should be speciDed in Table 7.5-1.
i IVestinghome Respome: See the respome to Step 28 ofAE-0.
i Step 3 - Check Secondary Radiation Comment: %e instruments to " Indicate secondary radiation level" should be specified in Table 7.5-1.
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IVestinghame Respome: See the respnue to Step 29 ofAE-0 i
Step 8 - Check Passive Containment Cooling i
Comment: De instrument for " Passive containment cooling reset status" should be specified in Table 7.5-1.
IVestinghouse Response: See the respome to Step 14 ofAE.h Step 11 - Initiate Evaluation of Plant Status Comment: De instruments for indication of " Auxiliary building radiation and Evaluating plant equipment" should be specified in Table 7.5-1.
IVestinghouse Respome: The imtnenents to detect radiation in the aiailiary and annev buildings is in the SS4R Table 7.5-1, arul will be added to the ERG Backgrowxt docwnent. Thisparameter is the
' plant vent radiation level".
Step 15 - Check If St Accumulator Should Be Isolated C.unment: Le " Accumulator isolation valve and vent valve position indicators and valve power supplies" indication should be specified in Table 7.5-1.
IVestinghatae Respome: As a result of the ongoing review of the ERGS, Step 15 is being deletedfrom AE-1.
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Step 16 - Check If Intact SG Should lle Ikpressurized To RCS Pressure Comment: The instruments for indication of "SG radiation" should be specified in Table 7.5-1.
Westinghatae Resjxnue: The AP600 ERG Backgroied document uill be revised to indicate that the SGS main steamline radiation instntmentation uill be taed to check secondary radiation. This parameter is inchdedin SS4R Table The term "cordemer ofgas radiatiint" uill be revised to
" turbine island vent discharge radiatio,. uhich is inchided in SS4R Table 7.5-1.
Step 17 - IJetermine If Reactor Vessel Ilead Should I3e Vented Comment: 1he instruments used "To determine if reactor,ressel head should be vented" should be specified in Table 7.5-1.
Westinghotwe Res7xnne: 1his imtnanentation is a collecti0n ofRCSparameters that are inchded in Table 7.5-1.
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$4 AES-1.1 PASSIVE SAFETY SYSTEMS TERMINATION Step 8 - Check If Passive Containment Cooling Should Be Styp:d Comment: The instruments for indication of " Containment cooling reset status" should be specified m Table 7.5-1.
I Westinghome Respome: See the respome to Step 14 ofAE-0.
Step 10 - Check RCS Makeup Control System Comment: The instruments for indication of "RCS makeup boron concentration and automatic RCS nukeup control setting" should be specified in Table 7.5-1.
Westinghouse Response: The indicationsfor "RCS makeup boron concentration" and " automatic RCS makeup control setting" referenced in the ERG Background document are tot imtrwnentation but rather are control devices that are pre-set by the operator. They do twt meet the criteria prwided in Reg. Guik 1.97for inchision in PAAS and are not included in SS4R Table 7.5-1.
Step 11 - Transfer Condenser Steam Dump To Pressure Control Mode Comment: The instmments for " Indicating condenser available" should be specified in Table 7.5-1.
Westinghouse Response: The statmfor the availability of the condemer is provided by the parameters
" circulating unter pumps breakers statm" and "condemer backpressure". These parameters will be addedto S%fR Table 7.5-1.
Step 12 - Check RCS Ilot Ixg Temperature Comment: The instruments for indication of " Steam dump status and steam dump to condenser valve position" should be specified in Table 7.5-1.
i Westinghouse Respome: The statusfor the availability ofsteam dump is provided to the operator by computer-generatedlogic via the Plant Control System Similar to the reasoningprovided in the respome to AE-0 Step 14, this statm indication is not included in PAAS or in S%fR Table 7.5-1.
The condemer steam dump valve position indication is provided in S%IR Table 7.5-1.
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Step 13 - Control Pressurizer Pressure Comment: De instruments for indication of " Letdown Status" should be specified in Table 7.5-1.
II'estinghome Reywnse: Die AlW)0 ERG Backgrourxldocument uill be revised to imtniet the operator to me letdtmn valve position indication and letdounflow rate as the parameters to be used to check letd<mn statm. These parameters are inchuled in SS4R Table 7.5-1.
t Step 15 - Check RCP Cooling Comment: De instruments for indication of "RCP temperature" should be specified in Table 7.5-1.
It'estinghouse Re.spame: SS4R Table 7.5-1 uill be uplated to inchule RCS bearing uuter temperature.
Step 16 - Verify All ECS AC Busses i'
Comment: Le instmments for indication of "AC busses power, OfTsite power status, available diesel capacity" should be specified in Table 7.5-1.
Il'estinghome Respome:
See the respome to AE-0 Step 13.
Step 17 - Check RCP Status Comment: The instruments for indication of "RCP support conditions status and condenser steam dump valve position" should be specified in Table 7.5-1.
l ll'estinghome Respame: The AP600 ERG Backj 'und document uill be revised to include de follouingparameters med to determine the statm ofRCP support systerm: CCSflow, CCS vahv position indication, CCS temperature, RCpressure. These parameters are inchuled in SS4R Table 7.5-1.
The condenser steam dump valve p>sition indication is provided in SS4R Table 7.5-1.
Step 20 - Shutdown Unnecessary Plant Equipment Comment: ne instruments for indication of " Equipment to be shutdown" should be specified in Table 7.5-1.
II'estinghouse Respome: The ERG background document has been revised to delete the reference to these imtruments. These parameters do not meet the criteria outlined in Reg. Guide 1.97 arul uill rwt be inchidedin SS4R Table 7.5-1.
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Al%1.2 POST IDCA COOLDOWN AND DEPRESSURIZATION Step 1 - Verify All ECS AC Busses - Energized by OfTsite Power Comment: He instruments for indication of "AC power busses power, Offsite power status, Status of equipment to be loaded on ac busses, and available diesel capacity" should be specified in Table 7.5-1.
Il'estinghome Respome: See the respame to AE-0 Step 13.
Step 4 - SFW Pump Suction Transfer to tie CST Comment: Be instmments for indication of "Deaerator storage tank level" should be specified in Table 7.5-1 II'estinghome Resp <ntse: See the respome to AE-0 Step 28 i
Step 5 - Initiate RCS Cooldown To Cold Shutdown Comment: he instmments for indication of " Condenser status, steam dump valve position, and normal RHR pump status and valve position" should be specified in Table 7.5-1.
Il'estinghome Respome: See the re.spame to AE%1.1 Step 12. Theparameter "RNSpunp status" i
uill be added to SS4R Table 7.5-1.
Step 6 - Tum All Pressurizer IIcaters Off Comment: De instruments for indication of " Backup heaters status and variable heaters status" should be specified in table 7.5-1.
II'estinghome Respome: The parameter Presari:er heater poner is inchuled in St4R Table 7.5-1 (Sheet 4 of12).
Step 8 - Check If ADS Should Be Actuated Comment: he instruments for indication of" Normal RHR pump status" should be specified in Table 7.5-1.
It'estinghome Respame: The parameter "Rh5 pump statm" uill be added to SS4R Table 7.5-1.
Step 11 - Check RCP Cooling Comment: %e instruments for indication of"RCP CCS flow and RCP temperature" should be specified in Table 7.5-1.
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c Westinghome Respnue: See the respome to AES 1.1 Step 15.
Step 13 - Depressurize RCS To Minimize RCS Subcooling Comment: The instruments for indication of " Normal spray valve position" should be specified in Table 7.5-1.
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Westinghouse Resp >me: The position indicationfor the nornudpressuri:er sprmo valves are inchuled i
m S%1R Table 7.5-1 (Sheet 8 of12).
Step 14 - Verify Adequate Shutdown Margin Comment: The instruments for indication of" Sampling valve position and CVS makeup pump suction three way control valve position" should be specified in Table 7.5-1.
Westinghouse Response: The primary system sanpling vah'e that must operate to accomplish post-accident sampling is a containment isolation valve, and as such, position indication is provided as specified in SUR Table 7.5-1 (as " Remotely Operatcd Containment Isolation Valve Status"). The three-um' blending valve position indication is provided in S%fR Table 7.5-1 ("Makeuppwnp suction header udve status").
Eteu 15 - ChecE If SI Accumulator Should Be Isolated I
Comment: 'lhe instruments for indication of" Accumulator isolation valve position, Accumulator isolation valve operator power supply and Accumulator vent valve position" should be specified in Table 7.5-1.
Westinghome Respome: Accunndator isolation vahe paition indication is provided in S%1R Table 7.5-1 ("Accunndator to reactor vessel valve status"). Acewnulator isolation valve operatorponer supply indication is not required to acconplish thisfunction and uill be deletedfrom the ERG backgrowxt docwnent. Accunndator vent mlve position indication uill be inchtded in S%1R Table 7.5-1. The name " Accumulator isolation vahe status" will replace "Accunndator to reactor vessel vah e statm".
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