ML20077N428
| ML20077N428 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 09/09/1983 |
| From: | Nelson R ILLINOIS POWER CO. |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, RTR-REGGD-01.097, RTR-REGGD-1.097 0982-L, 982-L, L30-83(09-09)-L, L30-83(9-9)-L, U-0633, U-633, NUDOCS 8309130090 | |
| Download: ML20077N428 (40) | |
Text
r U 0633 0982-L Illinois Power Company L30-83 ( 09- 0 9)-L 500 SOUTH 27TH STREET, P. O. BOX 511, DECATUR, ILLI.SOIS 62525-1805 Docket No. 50-461 September 9, 1983 Director of Nuclear Reactor Regulation Attention: Mr. A. Schwencer, Chief Licensing Branch No. 2 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
Clinton Power Station Unit 1-Compliance Report - Regulatory Guide 1.97
Dear Mr. Schwencer:
Reference:
IPletterdatedJuly5,1[83(U-0647),G.E.Wuller to A. Schwencer, NRC, subj ect : Emergency' Response Capability - Implementation Schedule.
The referenced letter provided schedules for the submittals of information on the Clinton Emergency Response Capability to fulfill the requirements of Supplement 1 to NUREG-0737.
Enclosed is our Compliance Report on Regulatory Guide 1.97.
Sincerely, R. H. Nelson Director-Nuclear Licensing and Configuration Management Nuclear Station Engineering GEW/lt attachment cc: H. Abelson, NRC Clinton Licensing Project Manager D. M. Rohrer, NRC EPLB W. A. Paulson, NRC Operating Reactors Branch #5 R. A. Kendall, NRC ICSB H. H. Livermore, NRC Senior Resident Inspector Illinois Department of Nuclear Safety 00 3 8309130090 830909
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, COMPLIANCE REPORT Regulatory-Guide 1.97 (Rev. 3) 1 h
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TABLE OF CONTENTS r.0 INTRODUCTION 2.0 IP POSITION ON REGULATORY GUIDE 1.97 (REV. 3)
FOR CLINTON POWER STATION 3.0
SUMMARY
INFORMATION FOR COMPLIANCE WITH REGULATORY GUIDE 1.97 (REV. 3) 4.0 JUSTIFICATIONS i
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1 ~. 0 INTRODUCTION
' This report presents the Clinton Power Station position on NRC Regulatory Guide 1.97, Revision 3 " Instrumentation
- for.' Light-Water Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident" 1 and also describes how Clinton meets the requirements con-tained inlboth the Reg. Guide 1.97 and Section 6.0 (Reg.
. Guide 1.97 - Application to Emergency Response Facilities)
. of NUREG 0737, supplement 1.
Clinton instrumentation that will be used to monitor Types A, B, C, D and E variables listed on Table 2 of Reg. Guide 1.97, Rev. 3, have been reviewed for compliance with Reg.
Gui+1e Requirements. The results of the review are summarized in'Section 3.0 of this report. Deviations from the guidance
. in-Reg. Guide 1.97, Rev. 3, are explicitly shown and support-ing justification or alternatives are provided in Section 4.0.
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2.0 IP POSITION ON REG. GUIDE 1.97 (REV. 3) FOR CLINTON POWER STATION IP concurs with the intent of Reg. Guide 1.97 (Rev. 3).
The intent of the Reg. Guide is to ensure that necessary and sufficient instrumentation exists at each nuclear power station for assessing plant and environmental conditions during and following an accident, as required by 10CFR Part 50, Appendix A and General Design Criteria 13, 19 and 64.
Reg. Guide 1.97 requirements will be implemented where fea-sible and practical, except in those instances in which deviations from the letter of the guide are technically justified. IP has followed the criteria used by the NRC for establishing category 1, 2 and 3 instruments. IP will comply with the quality assurance requirements using an ap-proved quality assurance program, as described in FSAR Chapter 17.0. This will ensure that accident monitoring instruments comply with the applicable requirements of Title IOCFR50, Appendix B.
In assessing Reg. Guide 1.97, IP has drawn upon information contained in several applicable documents, such as BWROG Position on NRC Reg. Guide 1.97, ANS.4.5, NUREG/CR-2100, NUREG 0737, Supplement 1, and BWROG Emergency Procedures Guidelines. IP believes that literal compliance with the provisions of Reg. Guide 1.97 would require excessive ranges or inappropriate categories. Other requirements could ad-versely effect operator judgement under certain conditions, s
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l 3.0
SUMMARY
INFORMATION FOR COMPLIANCE WITH REGULATORY GUIDE I 1.97 (REV. 3) !
IP positions on the implementation of the variables listed in Table 2 of Reg. Guide 1.97, Revision 3, and on the assign-ment and compliance with design and qualification criteria for the instrumentation proposed for their measurement is summarized in Table 3 of this compliance report.
The-variables are listed in Table 3 of this_ compliance report 1 in the same sequence used in Table 2 of Reg. Guide 1.97, Revision 3; however, for convenience in cross-referencing entries and supporting data, the variables are alphanumeri-cally designated.
9 I
TABLF 3 PAGE 1 of 16
SUMMARY
INFORMATION FOR COMPLIANCE WITH REG. GUIDE 1.97 ENVIRONMENTAL SEISMIC QUALITY PARAMETER QUALIFICATION QUALIFICATION ASSURANCE RE00hDANCY RAN3E TYPE A g 41) RPV PRESSURE WILL COMPLY WITH WILL COMPLY WITH COMPLIES - TWO CHANNELS 0-1500 PSIG 10CFR50.49 REG. GUIDE 1.100 A2) RPV WATER LEVEL WILL COMPLY WITH WILL COMPLY WITH COMPLIES TWO CHANNELS W!bI -160* TO 60*
10CFR50.49 REG. GUIDE 1.100 HARROW 0* TO 60*
FUEL -150* TO 50*
A3) SUPPRESSION POOL BULK WILL COMPLY WITH WILL COMPLY WITH COMPLIES TWO CHANNELS 40-2500F AVERAGE TEMPERATURE 10CFR50.49 - REG. GUIDE 1.100 A4) SUPPRESSION POOL LEVEL WILL COMPLY WITH WILL COMPLY WITH COMPLIES TWO CHANNELS 720' TO 736' 10CFR50.49 REG. GUIDE 1.100 A5) MYWELL PRESSURE WILL COMPLY WITH WILL COMPLY WITH COMPLIES TWO CHANNELS 10-50 PSIA 10CFR50.49 REG. GUIDE 1.100 A6) CONTAINMENT ANO DRYWELL WILL COMPLY WITH WILL COMPLY WITH COMPLIES' TWO CHANNELS 0-305 HYOR0 GEN CONCENTRATION 10CFR50.49 REG. GUIDE 1.100 TYPE B 6 g,$
B1) NEUTRON FLUX NO NO NO YES 4 CHANNELS 8 CHANNELS SRM10*fTO10 IFM 10- TO 401 RX PWR 4 CHANNELS APRM 0 TO 125%
B2) CONTROL ROD POSITION N/A N/A N/A ONE CHANNEL R00 POSITION B3) RCS SOLUBLE BORON N/A N/A N/A ONE CHANNEL 0-1000 PPM CONCENTRATION
10 CFR 50.49 REG. GU!OE 1.100 NARROW 0* TO 60*
FUEL -150" TO 50*
B5) 8.'R CORE TEMPERATURE NO NO NO NO NO BS) RPV PRESSURE WILL COMPLY WITH WILL COMPLY WITH COMPLIES TWO CMANNELS 0-1500 PS!G 100FR50.49 REG. GUIDE 1.100 E7) ORYWELL PRESSURE WILL COMPLY WITH WILL COMPLY WITH COMPLIES TWO CHANNELS 10-50 PSIA -
10CFR50.49 REG. GUIDE 1.100
-n-. , _ - ..
SUMMARY
INFORMATION FOR COMPLIANCE WITH RES. GUIDE 1.97 (CONT'D.) PAGE 2 of 16 ,
CR TSC EOF PARAMETER POWER SUPPLY DISPLAY LOCAYION . LOCATION SCHEDULE COMMENTS TYPi A A1) RPV PRESSURE 1E RECORDERS YES YES 10-09-84 BOTH CHANNELS
\
A2) RPY WATER LEVEL 1E RECORDERS YES YES 10-09-84 SEE 4.1
. BOTH CHANNELS A3) SUPPRESSION POOL BULK IE RECORDERS YES YES 10-01-85 AVERAGE TEMPERATURE BOTH CHANNELS A4) SUPPRESSION P0UL LEVEL 1E (2) RECORDERS YES YES 10-08-84 CENTER OF ECCS BOTH CHANNELS SUCTION AS) DRYWELL PRESSURE 1E RECORDER YES YES 10-01-85 SEE 4.2 B0TH CHANNELS A6) CONTAINMENT AND ORYWELL IE INDICATORS YES YES 03-25-85 HYDROGEN CONCENTRATION BOTH CHANNELS TYPE 8 B1) NEUTRON FLUX STATION POWER 2 RECORDERS YES YES 07-15-85 SEE 4.3 4 RECORDERS 4 RECOROERS B2) CONTR0s. ROD POSITION STATION POWER DISPLAY MODULE YES YES 07-15-85 B3) RCS SOLUBLE BORON STATION POWER NO YES YES 03-25-85 GRAB SAMPLE CONCENTRATION
- 84) RPV WATER LEVEL 1E RECORDER YES YES 10-09-B4 SEE A2 BOTH CHANNELS B5) 8iR CORE TEMPERATURE NO NO NO NO DO NOT PLAN SEE 4.4 TO INSTALL B6) RPV PRESSURE IE RECORDERS VES YES 10-09-84 SEE Al BOTH CHANNELS B7) DRYWELL PRESSURE 1E RECORDERS YES YES 10-01-85 SEE AS BOTH CHAhhELS
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SumARY INFORMATION FOR COMPLIANCE WITH REG. GUIDE 1.97 Page 3 of 16 ENVIRONMENTAL SE!SMIC QUALITY PARAMETER QUALIFIEATION QUALIFICATION ASSURANCE REDUNDANCY RANSE TYPE 8 (CONT'D.)
- 88) DRYWELL SUMP LEVEL NO NO NO NO NO
- 89) PRIMARY CONTAINMENT WILL COMPLY WITH WILL COMPLY WITH
\ COMPLIES TWO CHANNELS -5 PS!G TO 60 PSIA PRE 550RE 10CFR50.49 REG. GUIDE 1.100 BIO) PRIMARY CONTAINMENT COMPLIES WITH WILL COMPLY WITH COMPLIES ONE INDICATOR CLOSED AND NOT ISOLATION VALVE POSITION 10CFR50.a9 REG. GUIDE 1.100 PER VALVE CLOSED TYPE C C1) RAD. CONC. OR RAD, LEVEL NO NO NO NO NO IN CIRCULATING PRIMARY COOLANT C2) ANALYSIS OF PRIMARY N/A N/A N/A COOLANT ONE CHANNEL 10 pC1/ GM TO 10 C1/GM C3) BWR CORE TEMPERATURE NO NO NO NO NO C4) RPV PRESSURE COMPLIES WITH COMPLIES WITH COMPLIES TWO CHANNELS 0-1500 PSIG IOCFR50.49 REG. GUIDE 1.100 C5) PRIMARY CONTAINMENT AREA WILL COMPLY WITH WILL COMPLY WITH COMPLIES 7 RADIATION WITH 10CFR50.49 TWO CHANNELS 1 TO 10 R/HR REG. GUIDE 1.100 C6) DRYWELL DRAIN SUMP LEVEL NO NO NO NO NO C7) SUPPRESSION POOL LEVEL WILL COMPLY WITH WILL COMPLY WITH COMPLIES WITH 100FR50.49 TWO CHANNELS 720' TO 736' REG. GUIDE 1.100 C8) DRYWELL PRESSURE WILL COMPLY WITH WILL COMPLY WITH COMPLIES TWO CHANNELS 10-50 PSIA 10CFR50.49 REG. GUIDE 1.100 C9) RPV PRESSURE WILL COMPLY WITH WILL COMPLY WITH COMPLIES 100FR50.49 TWO CHANNELS 0-1500 PSIG REG. GUIDE 1.100
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S;.PP.ARY INFORMATION FOR COMPLIANCE WITH REG. GUIDE 1.97 PAGE 5 of 16 ENVIRONMENTAu SEISMIC QUALITY -
PAE Af*ETER QUA.!FICATIO% OUALIFICATION ASSURANCE RE'v0NDANCY - RANGE -
TYPE C (CONT'D.)
C10) PRIMARY CONTAINMENT , WILL CUMPLY WITH- WILL COMPLY WITH COMPLIES PRESSURE TW CHANNELS -5 PSIG TO 60 PS!A 10CFR50.49 REG. GUIDE 1.100
\
Cll) CONTAINMENT AND DRYWELL WILL COMPLY WITH WILL COMPLY WITH COMPLIES TWO CHANNELS 0-305 HYOROGEN CONCENTRATION 100FR50.49 RIG. GUIDE 1.100 EACH C12) CONTAINMENT AND ORYWELL WILL COMPLY WITH WILL COMPLY WITH COMPLIES TWO CHANNELS 0-305 :
OXYGEh CONCEhTRATION 10CFR50.49 REG. GUIDE 1.100 EACH C13) CONTAINMENT EFFLUENT RADIO- N/A N/A N/A . ONE CHANNEL 10*# TO ACTIVITY - NOBLE GAS 5 EACH VDT/ STACK 10 WC1/CC C14) RADIATION EXPOSURE RATE NO NC NO NO NO CIS) EFFLUENT RADI0 ACTIVITY - WILL COMPLY WITH WILL COMPLY WITH COMPLIE! ONE CHANNEL 10-4 TO NOBLE GASES 10CFR50.49 REG. GUIDE 1.100 EACH VENT / STACK 105 pCi/CC TYPE D
- 01) MAIN FEEDWATER FLOW N/A N/A 7 N/A TWO CHANNELS - 0 TO 210 L85/HR D2) CONDENSATE STORAGE TANK N/A N/A N/A LEVEL ONE CHANNEL (0-252')
SOTTOM TO TOS C3) CONTAINMENT (SUPPRES$10N COMPLIES WITH COMPLI'ES WITH COMPLIES TWO CHANNELS 0 TO 10,000 GPM CHAM 3ER) SPRAY FLOW 10CFR50.49 RES GUIDE 1.100 D4) ORYWELL PRESSURE COMPLIES WITH COMPLIES WITH CONDLIES TW') CHAN4ELS 10-50 PSIA 100FR50.49 REG. GUIDE 1.100 D5) SUPPRESSION POOL LEVEL WILL COMPLY WITH WILL COMPLY WITH COMPLIES TWO CHANNELS 720' TO 736' 10CFR50.49 REG. GUIDE 1.100
- 06) SUPPRESSION POOL BULK . WILL COMPLY WITH WILL COMPLY WITH COMPLIES TWO CHANNELS 40-2500F AVERAGE TEMPERATURE 100FR50.49 REG. GU10E 1.100 s ....--~=es.~ _ _
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SM%RY INFOR% TION FOR ODMPLIANCE WITH REG. GUIDE 1.97 PAGE 7 of 16 ;
ENVIRONMENTAL SE!SMIC OuALITY PARAMETER QUAI!FICATION OUALIFICATION ASSURANCE REDUNDANCY RANGE TYPE D (CONT'D.)
- 07) DRYWELL ATMOSPHERE BULK WILL C0F tY WITH WILL COMPLY WITH COMPLIES
- TWO CHANNELS 40 TO 350*F g AVERAGE TEMPERATURE 10CFR50 49 - REG. GUIDE 1.100 DS) DRYWELL SPRAY FLCW NO NO ' NO NO ' NO D9) MSIV LEAKAGE CONTROL WILL COMPLY WITH WILL COMPLY'w!TH COMFLIES TWO CHANNELS 0 TO 90* WC SYSTEM PRES $URE 10CFR50.49 REG. GUIDE 1.100 C10) SRV/ ADS VALVE POSITION WILL COMPLY WITH WILL COMPLY WITH COMPLIES 16 CHANNELS- CLOSED-NOT CLOSED 10CTR50.49 REG. GUIDE 1.100 ONE PER VALVE Dil) ISOLATION CONDENSER WATER NO NO NO NO NO LEVCL D12) ISOLATION CONDENSER NO NO NO NO NO SYSTEM VALVE POSITION 013) RCIC FLOW WILL COMPLY WITH WILL COMPLY WITH C9tPLIES ONE CHANNEL 0-800 GPM 10CFR50.49 REG. GUIDE 1.100 014) HPCS FLOW WILL COMPLY WITH WILL COMPLY WITH COMPLIES ONE CHA%NEL 0-8000 GPM 10CFR50.49 REG. GUIDE 1.100 D15) CORE SPRAY SYSTEM FLOW WILL COMPLY WITH WILL COMPLY WITH COMPLIES ONE CHANNEL 0-8000 GPM (LPCS) 10CFR50.49 REG. GUIDE 1.100 D16) LPCI SYSTEM FLOW WILL COMPLY WITH WILL COMPLY WITH COMPLIES 3 CHANNELS 0 TO 10.000 GPM 10CFR50.49 REG. Gul0E 1.100 D17) SLCS FLOW NO NO NO NO NO DIS) SLCS STORATE TANK LEVEL N/A N/A N/A ONE CHANNEL 0 TO 5000 GALS.
M9) P.HR SYSTEM FLOW WILL COMPT? WITH WILL COMPLY WITH COMPLIES 3 CHANNELS 0 TO 10,000 GPM 100FR50.49 REG. Gu!DE 1.100
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r SumARY INFORMATION FOR COM*LIANCE WITH REG. GUIDE 1.97 PAGE'S of 16' ENVIR09 TENT Ac SEISMIC
'PAAAMETER - QUALITY OUALIFICATION 00A;1rICAYIDs ' ASSURANCE REDuNaaNCY RANGE TYPE D (CONT *D.)
C20) R$ HX OUTLET TEMPERATURE WILL COMPiY WITH 10CFR50.49 WILL COMPLY' WITH REG. GUIDE 1.100 COMPi!ES 2 CHANNELS 320 TO 350'r D21) COOLING WATER TEMPERATURE. WILL CngPLY WITH TO E5F SYSTEM COMDONENTS 10CFR50.49 WILL COMPLY WITH COMPLIES _2 CHANNELS . 32' TO 200 0F REG. GUIDE 1.100 D22) COOLING WATER FLO. TO WILL COMPLY.WITH WILL CCMPLY WITH' COMPLIES 3 CHANNELS 0 TO 200 PSIG ESF SYSTEM COMPONENTS 10CFR$0.49 REG. GUIDE 1.100 0 TO 10000 GPM D23) HIGN RADI0 ACTIVITY LIQUID R/A N/A h/A TANK LEVEL- .ONE CHANNEL BOTTOM TO TOP PER TANK C24) EMERGENCY VENTILATION WILL COMPLY WITH WILL COMPLY h1TH COMPLIES ONE CHANNEL. OPENED AND CLOSED DAMPER POSITION 10CFR50.49 REG. GUIDE 1.100 PER DAMPER D25) STATUS OF STANDBY POWER AND OTHER ENERGt SOURCES IMPORTANT TO SAFETY A) ADS INSTRUMENT AIR NEADER WILL COMPLY WITH WILL COMPLY WITH COMPLIES TWO CHANNEL 0-250 PSIG PRESSURE 10CFR50.89 REG. GUIDE 1.100 B) ADS BACKUP AIR BOTTLE WILL COMPLY WITH WILL COMPLf WITH COMPLIES TWO CHAMEL 0-3000 PSIG HEADER PRESSURE 10CFR50.49 REG. GUIDE 1.100 C) DG V0.TAGE WILL COMPLY WITH WILL COMPLY WITH COMPi!ES THREE CHANNEL 0-525]v 10CFR50.49 REG. GUIDE 1.100
- 0) DG AMPERES WILL COMP.Y WITH WILL COM3LY WITH COMPLIES THREE CHANNEL 0-800 AMPS 10CFR50.49 REG. GUIDE 1.100 0-600 AMPS f) 4.16(v BUS VOLTAGES WILL COMPL Y WITH WILL COMPLY WITH L IES COMP THREE CHANNEL 0-5250V-10CFR50.49 REG. GJIDE 1.100 F) 4.16 KV BUS INCOMING WILL COMPLY WITH WILL COMPLY WITH COMPILES THREE CHANNEL 0 800 AMPS BREAKER CURRENT 10CFR50.49 REG. GUIDE 1.100 0-600 AMPS G) DC BUS VOLTAGE WILL COMPLY WITH WILL COMPLY WITH COMPi!ES FOUR CHANNEL 0-150V 10CFR50.49 REG. GUIDE 1.100 H) DC BUS CURRENT' WILL COMPLY WITH WILL COMPLY WITH COMPLIES THREE CHANNEL 300 TO 700 AM*S 10CFR50.49 REG. GUIDE 1.10;
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S w.A41 Ih:DR ETIch FOR COMPLIANCE WITH REG. GU!OE 1.97 P4&E 13 of 16-ENVIRON" ENTAL SEISMIC OuALITY PAPA"! tea ' OUAIFICAT10mi OUALIFICATION ASSURANCE NEDUNDANCY RACE .
' TYPE E (CONT'D.)
E7) AIRBORNE RADIO *6ALOGENS N/A N/A h/A ONE CHANNEL - 10'I TO 10'3 pct /CC
'ANO PARTICULATL5
- (PORTABLE SAMPLING WITH g ON-5ITE ANALY115 CAPABILITY)
- 8 ES) PLAhT AN3 ENVIRONS N/A N/A N/A ONE CHANNEL 10* R/HR PHOT 045 RCIATION (PORT 7BLE 10~lTO10 4 T0 > 10 RC 5/W BETA INSTR'MENTATIONJ E9) PLANT AND ENVIRONS N/A %/A N/A ONE CHANNEL ISOTOPIC ANA'Y515 .
RCIATION (PORTABLE j INSTRUMENTATION) 3 l E10] WIN 3 DIRECTION N/A N/A N/A TWO CHANNEL $' 0' TO 36C' STARTI G 5'EED 0.75 MPH. 4 FT
,' DISTANCE CONSTANT, CAMPI C RATIO BET =EEN 0.5 AND 6.0 Ell) WINO SPEED N/A N/A N/A TWO CHANelELS 0 TO 100 9PH, THRE$4)LD
', AT 0.75 MPH 4
E12) ESTIMATION OF ATMO5PHERIC N/A N/A N/A ONE CHANNEL -5.4'F TO 12.6*F STABILITY (DIFFERENTIAL TEMPERATURE)
E13) ACCIDENT SAMPLI C CAPABILITY - PRIMARY
, C00 JNT AND SUMP I A) GROSS ACTIVITY h/A N/A N/A DNE C MNNEL 1 pC1/". TO 10 C1/ML
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t i D) CHLORIDE CONTENT N/A N/A N/A ONE CHANNEL 0 TO 20 PPM 1
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SUWJV INFOR".ATION FOR C0ci1ANCE WITH REG. GUIDE 1.97 (CONT *D.) -- PAGE 14 ef 16 .
CR T5C E3F 2-PARAMETEE PO'e TR SifDP'. V . DISPLAY, LOCATION LOCATION SCHEDULE C0seENT5 TYPE E (C0hT'D.)
E7) AIRBORNE RCI0 HALOGENS STATIO4 POWER NO YES YES 03-25-85 U$ES GELI SYSTEM AND PARTICULATE 5 4
g~ . (PORTABLE SAM i7 l4G WITH Dh-5ITE AhALYSIS CAPA!ILITY)
E8) PLANT Aho Ehi!RONS SATTr 40 YES YE5 10-01-85 RG-7 5'JRVEY METERS RADIAT!0h (PORTAELE IkSTRUMENTAT!ch)
E9) PLAh7 AND thV!RON5 STATION POQR' NO YES YES '03-25-85 U5ES GELI 3YSTEM RADIATIOh (PORTABLE Ih5TiiUMENTATIGN)
EIO) WIN 3 DIRECTION STATIOM POWEA RECORDER YES YES 02-27-85 EACH CHANNEL Ell) WIN 3 SPEED STATION POWER RECORDER YES YE5 02-27-85 EACH CHANNEL E12) ESTIMATIOh 0F ATMOSPHERIC STATION POWER ONE RECORDER YES YES 02-27-85 STABILITY (DIFFEREhTIAL TEMPERATURE)
E13) ACCIDENT SAMPLING CM ABILITY - PRIMARY
-; COOLANT AC SM A) GROSS ACT!WITY STATI0h POWER NO YES YES 03-25-85 USES GELI SYSTEM B) G49tA SPECTRUM STATION POWER NO YES YES 03-25-85 USES GELI SYSTEM C) BORO % CONTENT STATIOh POWER NO YE5 YES 03-25-85 LAB ANALY!!5 i
D) CHLORIDE CONTENT STATIOh POWER NO YES YES 03-25-85 LAB ANALYS!$
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SUMMARY
INFOR% TION FOR COMPLIAN~E WITH REG. GUIDE 1.97 (CONT'O.)' PAGE 16 of 16 .
CR TSC . EOF PARAMETER POWER SUPPLY DISPLAY LOCATION LOCATION SCHEDULE COMMEhT5
, TYPE E (CONT *D.)
, E) 0!S50LVED H 2OR TOTAL GAS; .IE- No YES YES . 03-25 RECORDED ON
, PASS PENEL G) PH 1E . No Yr5 YES 03-25-85 INDICATED ON PASS PANEL 2
E14) ACCIDENT SAMPLING CAPA.
BlitTY - C0%TAIN4ENT AIR A) H CONTENT --- ---- --- ---- ---- SEE A6 2
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I 4.0 JUSTIFICATIONS Justifications-presented in the following sections, support the positions and deviations identified in Section 3.0 and/or Table 3 of this compliance report.
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4.1 VARIABLE A2 - RPV WATER LEVEL s
Issue definition: The measurement of RPV water level is specified as.a key variable in monitoring core cooling and
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maintaining reactor coolant system integrity. RPV water level is classified as a Type A variable, Category 1. The specified range-is 197.6" to 636.5".
Discussion: Clinton has redundant and qualified level measure-ment for the range of 360.6" to 580.6" with respect to vessel bottom. Clinton also has redundant level measurement which is seismically qualified, but not environmentally qualified, with the ranges of 208.6" to 408.6" and 529.6" to 700.6" with respect to vessel bottom.
Conclusion:
The Clinton RPV water level monitoring system design meets the intent of Reg. Guide 1.97, Rev. 3, however, the resolution of the issue of inadequate core cooling may dictate design changes in the present Clinton water level monitoring system.
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f 4.2 VARIABLE A5 - DRYWELL PRESSURE Issue definition: The measurement of drywell pressure is specified as a key variable in maintaining containment and reactor coolant system integrity. Drywell pressure.is classi-fled as a Type A variable, Category 1. The specified ranges are -4 psig to 3 psig and 0 to 110% design pressure.
Discussion: Clinton has redundant and qualified pressure measurement for the range of 10 to 50 psia.
Conclusion:
The Clinton pressure measurement system provides the control room operator with appropriate information to monitor plant operation without adversely affecting operator judgement. The range provided exceeds the range proposed within Reg. Guide 1.97.
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4.3 VARIABLE B1 - NEUTRON FLUX Issue definition: The measurement of neutron flux is speci-fled as the key variable in monitoring the status of reactiv-ity.
1.
Neutron flux is classifigd as a Type B variable, Category
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The specified range is 10 % to 100% full power (S RM ,
APRM). The stated purpose is " function detection; accomplish-ment of mitigation".
Discussion: The Clinton neutron monitoring detectors are
. powered f rom'a lE power source, but the SRM/IRM drive mecha-nisms and all neutron monitoring displays are powered from station power. Continuous recording.is provided. The exist-ing monitoring system _is capable of providing the intended function of this variable until the industry developmental activities are completed.
Conclusion:
The Clinton neutron flux monitoring system is of a similar design as those used in most BWRs. A Cate-gory 1 system that meets all Reg. Guide 1.97, Rev. 3, require-ments is an industry developmental item.
Clinton will follow industry developmental activities and upgrade or replace the existing system when a fully qualified and proven neutron flux monitoring system becomes available.
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4.4 VARIABLE B5 - BWR CORE TEMPERATURE Issue definition: The measurement'of BWR core temperature is specified to monitor the status of core cooling. BWR core temperature is classified as a Type B variable, Cate- ,
gory - (unstated). The specified range is 200*F to 2300*F j The stated purpose is "to provide diverse indication i of water level".
Discussion: The use of in-core thermocouples has been investi-gated, and an analysis of the heat transfer in a BWR fuel bundle during a core uncovery event was performed to deter-mine the nature of the response of thermocouples to core heatup. The thermocouples were assumed to be located in !
the in-core guide tubes and heated primarily by radiation from the fuel channels. Results of this analysis show that, for conditions' typical of small break, loss-of-coolant acci-dents, there is a delay of at least 13 minutes between the start of core uncovery and the time when the thermoccuples reads 45*F above saturation. It is also probable that opera-tion of relief valves during a small-break LOCA would inter-fere with the thermocouples' operation and could render them useless.
Conclusion:
In-core thermocouples should not be required for diverse water level monitoring; however, other means are being investigated. In-core thermocouples are also no longer being considered a viable means for monitoring inadequate core cooling.
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4.5 VARIABLE B6 - DRYWELL SUMP LEVEL VARIABLE C6 - DRYWELL DRAIN SUMP LEVEL Issue definition: Reg. Guide 1.97 requires Category 1 instru-mentation to monitor drywell sump level (Variable B8) and drywell drain sump level (Variable C6). These designations refer to the drywell equipment and floor drain sump levels.
Category 1 instrumentation indicates that the variable being monitored is a key variable. In Reg. Guide 1.97, a key variable is defined as "...that single variable (or minimum number of variables) that most directly indicates the accom-plishment of a safety function...". The following discussion supports the IP position that drywell sump level and drywell drain sump level should not be implemented as a Reg. Guide 1.97 parameter.
Discussion: The Clinton drywell has two drain sumps. One sump is the equipment drain sump, which collects identified leakage; the other is the floor drain sump, which collects unidentified leakage.
Although the level of the drain sumps can be a direct indica-tion of breach of the reactor coolant system prescure boun-dary, the indication is not unambiguous, because there is water in those sumps during normal operation. There is other instrumentation required by Reg. Guide 1.97 that would indicate leakage in the drywell:
- 1. Drywell pressure--Type A, Category 1
- 2. Drywell temperature--Type D, Category 2
- 3. Primary containment area radiation--Type C & E, Category 1 The drywell sump level signal neither automatically initiates safety-related systems nor alerts the operator to the need to take safety-related actions. Both sumps have level detec-tors that provide only the following nonsafety indications:
- 1. Flow indication / recording
- 2. Totalized flow indication
- 3. High-level alarm (starts first sump pump)
- 4. High-high level alarm (starts second sump pump)
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In addition, timers are used to indicate the duration of sump pump operation and thereby permit the amount of leakage to be estimated.
Reg. Guide 1.97 requires instrumentation to function during and after an accident. The drywell sump systems are deliber-ately isolated at the. primary containment and drywell pene-trations upon receipt of an accident signal to establish containment and drywell integrity. This fact renders the drywell sump level signal irrelevant. Therefore by design, drywell level instrumentation serves no useful accident monitoring function.
The Emergency Procedure Guidelines use the RPV level and the drywell pressure as entry conditions for the Level Control Guidelines. A small line break will cause the drywell pres-sure to increase before a noticeable increase in the sump level. Therefore, the drywell sump will provide a " lagging" versus "early" indication of a leak.
Conclusion:
Based on the discussion above, IP believes that the drywell sump level and drywell drain sump level instrumentation should not be implemented as a Reg. Guide 1.97 parameter.
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4.6 VARIABLE B10 PRIMARY CONTAINMENT ISOLATION VALVE POSITION Issue definition: Primary containment isolation valve posi-tion is specified as a key variable to monitor containment integrity. Primary containment isolation valve position is classified as a Type B variable, Category 1. The speci-fled range is closed-not closed. The stated purpose is
" accomplishment of isolation".
Discussion: With the exception of some check, pressure relief and test valves, all containment isolation valves have position indication in the main control room. The test valves will be under administrative control and the pressure relief valves are not capable of being fitted with position switches. The Reg. Guide does not impose position indication requirements on any check valves.
Conclusion:
Eased on the above discussion, the Clinton design complies with Reg. Guide 1.97 requirements.
4.7 VARIABLE C1 - RADIOACTIVITY CONCENTRATION OR RADIATION LEVEL IN CIRCULATING PRIMARY COOLANT Issue definition: Reg. Guide 1.97 specifies'that the status of the fuel cladding be monitored during and after an acci-
, dent. The'specified variable to accomplish this monitoring is Variable Cl--radioactivity concentration or radiation level in circulating primary coolant. The range.is given as "% Tech Spec Limit to 100 times Tech Spec Limit, R/hr."
.In Table 2 of Reg. Guide 1.97, Revision 3, instrumentation for measuring Variable C1 is designated as Category 1.
i The purpose for monitoring this variable is given as "detec-tion of breach", referring, in this case, to breach of fuel cladding.
j Discussion: The usefulness of the.information obtained i
by monitoring the radioactivity concentration or radiation level in the circulating primary coolant,.in terms of helping the operator in his efforts to prevent and mitigate accidents, has not been substantiated. The critical actions that must be taken to prevent and mitigate a gross breach of fuel clad-ding are (1) shut down the reactor and (2) maintain water level. Monitoring Variable Cl, as directed in Reg. Guide 1.97, will have no influence on either of these actions.
The purpose of this monitor falls in the category of "infor-mation that the barriers to release of radioactive material are being challenged" and " identification of degraded condi-tions and their magnitude, so the operator can take actions that are available to mitigate the consequences". Additional operator actions to mitigate the consequences of fuel bar-riers being challenged, other than those based on Type A and B variables, have not been identified.
1 Reg. Guide 1.97 specifies measurement of the radioactivity of the circulating primary coolant as the key variable in i
monitoring fuel cladding status during isolation of the i NSSS. The words " circulating primary coclant" are inter-preted to mean coolant, or a representative sample of such coolant, that flows past the core. A basic criterion for a valid measurement of the specified variable is that the
, coolant being monitored is coolant that is in active contact with the fuel, that is, flowing past the failed fuel. Moni-l toring the active coolant (or a sample thereof) is the domi-l nant consideration. The post-accident sampling system (PASS) l provides a representative sample which can be monitored.
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4.7 (Cont'd)'
The subject of concern in'the Reg. Guide 1.97 requirement i is assumed to be an isolated NSSS that is shutdown. This
- assumption-is justified as current monitors in the condenser off-gas.and. main steam lines provide reliable and accurate information on the status of fuel cladding when the plant is not isolated. Further, the PASS will provide an accurate status of coolant radioactivity, and hence cladding status, once the PASS is activated. In the interim between NSSS isolation and operation of the PASS, monitoring of the pri-mary containment radiation and containment hydrogen both -
Category 1 variables, will provide information on the status I of.the fuel cladding.
Conclusion:
. Based.on the above considerations, IP believes that the radioactivity concentration.or radiation _ level in circulating primary coolant instrumentation should not be implemented as'a Reg. Guide 1.97 parameter.
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4.8 VARIABLE CIS - EFFLUENT RADIOACTIVITY - NOBLE GAS Issue definition: The measurement of effluent radioactivity -
noble gas is classified as a Type C varigble, Category 2.
The specified range is 10 ~6 pCi/cc to 10 pCi/cc. The stated purpose is " indication of breach".
Discussion Clinton has procured instrumentation to monitor effluentradioactivityquali{iedtoCategory2 which has a low range of 10
~ requirements pCi/cc. It is neither feasible nor practical to implement Category 2 qualified lower range instrumentation from the standpoint of functional need.
Clinton has Category 3 instruyentation which provides a lower range capability of 10 pCi/cc. Providing this lower rangecoveragebyunqualifieddevfcesisacceptablesince indication below the range of 10 pC1/cc is not applicable to accident scenarios.
Conclusion:
Based on discussion above the Clinton design meets the intent of Reg. Guide 1.97 for this parameter.
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4.9 VARIABLE D7 - DRYWELL ATMOSPHERE TEMPERATURE
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Issue definition: The measurement of drywell atmosphere temperature is classified as a Type D variable, Category 2.
'The specified range is 40* to 440*F. The stated purpose is "to monitor operation".
Discussion: The Clinton existing instrument range is 40*
to 350*F. The implemented range exceeds the DBA limit of 330*F. To extend the upward bound of this temperature range would introduce greater departures from linearity.
Conclusion:
Based on the above discussion, Clinton meets the-intent of Reg. Guide 1.97 for this parameter.
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4.10 VARIAGLE D9 - MSIV LEAKAGE CONTROL SYSTEM PRESSURE Issue Definition: The measurement of MSIV leakage control system pressure is classified as a Type D, Category 2.
The specified ranges are 0" to 15" H 90 and 0 to 5 paid.
The stated purpose is "to provide in51 cation of pressure boundary maintenance".
Discussion: The Clinton design monitors both the inboard and outboard system pressures. The ranges of these instru-ments are 0" to 90" H 2O per the system design. System differential pressure can be ascertained from these instru-ments. The existing ranges of these instruments exceed the required ranges of the Reg. Guide.
Conclusion:
Based on the above discussion, the Clinton design meets the intent of Reg. Guide 1.97.
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4.11 VARIABLE D17 - SLCS FLOW Issue definition: The measurement of SLCS flow is classified as Type D, Category 2. The specified range is 0 to 110%
design flow. The stated purpose is "to monitor operation".
Discussion: The SLCS on Clinton is manually initiated.
Flow measuring devices were not provided for this system.
The pump discharge header pressure, which is indicated in the control room, will indicate SLCS pump operation. Besides the discharge header pressure observation, the operator can verify the proper functioning of the SLCS by monitoring the following:
- 1. The decrease in the level of the SLCS storage tank.
- 2. The reactivity change in the reactor as measured by neutron flux and boron concentration (the latter by samp-ling).
- 3. The motor contactor indicating lights.
- 4. Squib valve continuity indicating lights.
The use of these indications is~ believed to be a valid alter-native to SLCS flow indication.
Conclusion:
Based on the disscussion above no direct indica-tion of SLCS flow is provided for Clinton.
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4.12 VARIABLE D18 - SLCS STORAGE TANK LEVEL Issue definition: The measurement of SLCS storage tank. ,
level is classified as Type.D, Category 2. 'The specified range is top to bottom. The stated purpose is "to monitor operation"..
Discussion: The Category 2 requirement for the SLCS storage
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tank leve1~ instrumentation is not considered appropriate for;the following reasons:
-1. The current design basis for the SLCS assumes.a need for an alternative method of' reactivity control without a' concurrent loss of coolant accident or high energy
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' line break. The environment in which the SLCS instrumen-tation must work is,.therefore, a " mild" environment for. qualification purposes.
- 2. The current design basis for the SLCS recognizes that j the system has a classification that is less than the i
' safety related classification of the reactor protection system and the engineered safeguards systems.
Based on a graded approach to safety, this variable is more appropriately considered'a Category 3 variable.
Conclusion:
Based on the above discussion, the existing instrumentation meets Category 3 design and qualification criteria.
, It is reali7ad that the resolution of the ATWS issue may include substantial changes to the SLCS design criteria.
'At that time, the SLCS instrumentation will be re-evaluated to ensure adequacy.-
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4.13 VARIABLE D22 - COOLING WATER FLOW TO ESF COMPONENTS Issue definition: The measurement of cooling water flow to ESF components is classified as a Type D variable, Cate-gory 2. The specified range is 0 to 110% design flow.
-The stated purpose is "to monitor operation".
Discussion:- For Division 1 and Division 2 cooling water, Clinton will utilize the flow transmitters on the shutdown service water supply to the Division 1 and Division 2 RHR heat exchangers, in conjunction with proper valve alignment, as indication of flow to the Division 1 and Division 2 ESF system components. For Division 3, Clinton will utilize shutdown service water pump discharge pressure, in conjunc-tion.with-the shutdown service. water pump 1SX0lPC performance curves and proper valve alignment, as indication of flow to the Division 3 ESF system components.
Conclusion:
' Based on discussion above, the Clinton design meets the intent of Reg. Guide 1.97.
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4.14 VARIABLE D25 (II) - DC BUS CURRENT Issue ' definition: The measurement of DC bus current is classified as a Type D variable, Category 2. The stated range is -300 to +700 amps.
. Discussion: Clinton instrumentation for Division 1, 2 and 4 has qualified bus current measurements for the range of
-300 to +700_ amps in the control room. Division 3 instrumen-tation for bus current measurement is monitored locally.
Alarms are provided in the control room for Division 3 bat-tery charger trouble and 125 VDC system trouble.
Conclusion:
Based on the above discussion and the NRC acceptance of General Electric NEDO 10905-2 dated April 1976, IP believes the Clinton design meets the intent of Reg. Guide 1.97.
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4.15 VARIABLE E6 - RADIATION EXPOSURE METERS Discussion: Revision 3 of Reg. Guide 1.97 states "it is unlikely that a few fixed-station area monitors could provide sufficiently reliable information to be of use in detecting releases from unmonitored containment release points...the decision to install such a system is left to the licensee".
Conclusion:
Clinton will not be implementing this parameter.
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