ML20140D869
| ML20140D869 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 12/11/1984 |
| From: | ILLINOIS POWER CO. |
| To: | |
| Shared Package | |
| ML20140D867 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, RTR-REGGD-01.097, RTR-REGGD-1.097 NUDOCS 8412190235 | |
| Download: ML20140D869 (29) | |
Text
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ATTACHMENT i
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COMPLIANCE REPORT Regulatory Guide 1.97 (Rev. 3)
(Revision 1)
November, 1983 l-l 8412190235 841211 PDR ADOCM 05000461 l
TABLE OF CONfENTS 1.0 IJTRODUCTION' 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)
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" and also describes how Clinton meets the requirements contained in both 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. Guide 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 supporting justification or alternatives are provided in notes to the table.
1
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 feasible 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 approved quality assurance program, as described in FSAR Chapter 17.0.
This will ensure that accident monitoring instruments comply with the applicable requirements of Title 10CFR50, 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 adversely effect operator judgement under certain conditions.
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3.0
SUMMARY
INFORMATION FOR' COMPLIANCE WITH REGULATORY CUIDE 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 assignment and compliance with design and qualification criteria for the instrumentation proposed for their measurement is summarized in l
this compliance report.
The variables listed in the Table of this compliance report are in l
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 alphanumerically designated.
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r-5tietART INFORMATION FOR (DNFLI ANCR WITU RECUtATORT CtJtDR I.97 RN7!ROWNENTAL SRISMIC QUALITY PARAMTtt W ALtFICAftos QUALIFIC&y!ON ASSURANCE REDUNDANCY RANCE TTFE A A!)
RPT Pressure Will comply with Witt comply with Complies hee channele 0-1500 pois 10CFR50.49 Reg. Cuide 3.100 A2)
RPT Water level Upset Reage We Pressure boundary Complies One chamael 0" to 180" ccepties with Reg. Ceide 1.800 Wide Range Will comply with Witt ceaely with Complies hee channeto
-160* to 60" 10CFR50.49 Seg. Cuide I.100 Feet Zone Bamse Witt comply with Will comply with Complies Two channets
-150" to 50" 10CFR50.49 Reg. Guide 1.100 A3) Suppreselon Pool Buth Witt comply with Witt comply with Complies hee channele 40-250' F Average Temperature 10CFR50.49 Beg. Guide 3.100 A4) suppreesten Pool tavel Witt cogty with Witt tempty with Couplies hee chemoete 720' to 736' 10CFR50.49 seg. Cuide 3.100 AS) Drywell Pressure Witt congly with Will comply with Complies hee chamaele 10-50 pela 50CFR50.49 seg. Cuide 1.100 A6)
Coutoimment end Dryuell Witt comply with Witt comply with Complies hee channelo 0-301 Rydrogen Concentration 10CFR50.49 Reg. Cuide 3.100 TTPR 5
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Neutree Flus He Me No 4 chameets SEN 10' to 10' CPS S channete IRN 10 to 403 RI FUR 4 channele Aran O to 125E 32)
Centret Red Peeltlee N/A N/A N/A One chaemet Rod position B3)
SCS Soluble Borea N/A W/A Cancentretles 5/A Dee chamael 0-1000 Sra 54?
RFF Water Level Upeet Range Be Freesere benadery Complies one chaemet 0" to 180" complies with Beg. Cnide I.100 Wide Range Witt comply with Will comply with' Complies hoe chaemete
-160" to 60*
10CFt50.49 seg. Omide 1.500 Fuel Zone Range Witt comply with Will comply with Couplies hse cheneele
-150* to 50" 10CFR50.49 Beg. Cuide 1.100
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See isote 1 Y,e teel 2 m R.s.ge Both Channels yee see note I IE Recorder and All 5.q :. seams P.28 so3s' Indicator Tee Tee IE See Note 1 L.esage temperature (2) RecerJers Tee 50th Chamaele Tee
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C.mtrol Lad Position Station Power Display b dule Ei)
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$EISMIC QcAllTT P as e*e Tl a,
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AmaIysis of Ptsmary m/A N/A N#A One channel 10 eCa/s to lo Ci/s Coolast C3) 34R Care Temperatore se no No No No C6)
EFW Freenre Compfies with Complies with Complies Two channels 0-1500 peig 10cT350.49 Beg. Cuide 1.100 C5)
Primary Costeicees Area Es tl comply with Wall comply with Complies Two chammels I to 10 t/Ma Balaation I)CI B 50.49 Beg. Ceide 1.100 Cs)
Drywell D eam sump Leeel no No No No 50 CF)
Sqpressimo Put Level Wall ceeply with Will coeply with Complies two channels 720' to 7 M' ICCFR 50.4 6 Reg. CusJe 3.103 CS)
Drywell Pres==ve Will comply with Will comply with Camplies
% chamaele 30-50 p ie 10CTEM.49 tea. Cuide 1.100 top srs Fres==ec Wall caoyty wath Will caerly wa th Complies h channels 0-8%00 psig 30tFa %.49 Beg. Conde I I00 Clan Futeary C.seresumens Wall compt e wit h Wall comptv with f.= plies Two channels 10 psia to M roia Fre esere 300 s%).44 Beg. CwiJe 1.800 Cla)
C..t o. seres e J De s-15 W it cceply with hill c.*rle wette
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Bi ly. gee fewes est rat e.g lad E %0.6e Reg. CusJe 3.500 each ClJ) C ast einocet aaed Dr ew II W:Il cceply with Wall e amply wit h C =plice N thaname**
O-li oo rg es Cear s e t s.ee led e W.49 Reg. Cande I. Ism eeth Cll) C %teamecer telleret Ee.tse-5/A R/A N/A One c hamae l ID' to lo eCe/CC
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F.e chaemel 30 to ID etarcC 341, Geero I
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Man Ee*Mter Flow h/A s/A s, A Two channels 0 to 2 10 Its/hr 22)
C atessere 5tsrege Tash M/A N/A Level ml 4 One channel (0-282*)
Sottom to top I
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Analysis of Primary Station Pcm.er No Tee Yes traes spectral analysia.
Cos t aat ALARA and Dosimetry Record-keeping syntes.
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S u Cere Temper at ore No No Na No
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RPV Frese re IE Recorders Yes Yes See parawter Al Both Chamaele CS)
Fr amary C.= c airmarat Area It
!adicater Yes Yes Ra4 a at ion toth Chamaels C6)
Dt vell Da aen ser level Ma No h
No See Note S CF) 5=prsessian F I Leeel
'It (2) BecorJere Te*
Yre See parameter A4 poth Channels CE)
Drywell Pressure IE Recorders Yes Tee See parameter AS Both C%annels C9)
EFw Press re IE Recorders Yes Yes See persneter Al Both C)annels C10) Primary containment IE (2) Secor?cre Yes Yes See parameter 89 Frees re Bath Channels C11) Cant a iwat amJ Drye ll IE ladieeter Yes Yes See parameter A6 Rydrogen Concentration each cf.sanel C12) Containment and Drywl!
IE ladic at er Yes Tee Osygen Concentrataon each channel Cl3) Containment E f flisent Radio-station Power O(FTR CRT Y es Yes actieity - kble Cao C14) Radiation Exposure Rate No No h
No Donot plan to install.
Deleted from Ree. 3 of Reg. Cuide.
C15) Efft.ent Radioacti sty -
IE CMPTR CRT Tes Yes See Note 8 k ble Canes TYPE D DI) main Feedwater Flow
$tation Power Indicator Yes Yes D2)
C e densate Storage Tank Station Power Indicatar Yes Yes Leeel
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1 gNTI AOINENTAL SEl$NIC QUALITY MaalETBS QUALIFICAftnes ge*ALIFICAtl0N ASSUSANCE RF0tW ANCY RaggCE TTet D (Cent'd)"
D3) Centelement (s ppreselen complies with Complies with Complies Two channele O to 10,000 spe C M er) Spray Flow 10CF350.49 Beg. Cnide 4.500 D4) Drywell pressere Complies with
'Ceeplies with Complies Two cheneele 10-50 poie 10CFE SS.49 Beg. Cuide 1.800
- 95) Seppreselon poet Level Will comply with Will reepty with Caetties Two chenmate 720' to 734' 30CFESO.49,
a.A. Cuide I. loo 06)
Seppreseles poel Delk Will comply with Will comply with Complies Two channele 40-250* r Average Teeperatore 10CF350.49 Reg. CeiJe 8.800
- 37) Drywell Ateeephere Belk Will comply with Will comply with Ceeplies
' Two channele 40 to 350* F Average Temperatere 10CFR50.49 pag. Cuide 3.800 DS)
Brywell Spray Flow No No Me No No D9) IISIV Leebzee Centrol Will comply with Will comply with Complies Two channele 4 to 90" WC Systee pressere 10CFB50.49 Reg. Cuide 1.500 DIO) SAV/ASE Talve posities Will tempty with Will comply with Complies 14 chesnele Cleoed-Net cleoed 10CFt50.49 Beg. Cuide 3.400 ene per valve Dil) feeletten Condeneer Weter Me We We No We Level 312) feeletten Ceedeneer No No Me We Ne Systee Velve reeltion DI)) BCIC Flow Will comply with Will emeply with Complies one chamael 0-800 spe 30 Cf350.49 Reg. Cuide 1.500 Die) NpCS Flow Will comply with Will esoply wish Complies Dee ebennel 0-8000 spe 10CytSO.49 Reg. Cuide 3.800 DI5) Core Spray Systee Flee Will comply with Will comply with Camplies one channel 0-6000 spe (LPCS) 10CFRSO.49 Beg. Ceide I.100 D14) Lycl Systee plow Will eseply with Will comply with Complies 3 channele O to 10,000 spe 10CF350.49 Reg. Ceide 3.100 917) SLCS Flow We No No Me IIe DIS) ECS Storage Tenh Imel N/A N/A N/A 0.e channel O to 5000 sets.
Dit) ame System Flow Will comply with Will comply with Ceeplies 3 skennele O to 30,000 spe IOCFE50.49 Reg. Cuide 3.500 D
TSC Enr Ca B5MAass Di$Pt.AT IJrk:Af toff IJk'Af tfMI 70WER SUFFtf PAAAfETER Indireter Yes Yes it D1) Caetainment seppreselon Each CLeenet See paraenter AS Che) spray Flow secordere Tee Yes It D4) Drywell Pressere Sath Cheeeele See parameter A4 (2) Secordere Yes Tee IE DS) Seppreseles Peel I.evel Seth Chemmele See parameter A1 (2) Secordere Tee Tee SE D4) Seppression Peel tolk math Cheemele Average Temperatore See Note 9 Recordere Yes Tee IE DF) Drywell neseophere Selk a.th Channele Average Teeperatore f*
De met plea to imetall.
Na No Me CPS does met have e dry-We DS) Drywell Srpey Flow well errey system.
See Note lo ledicater Tee Yes 991 30$19 Leekage Central IE Each Channel Systes Pressere Tee fee Indiceter IE Ble) $4V/ ADS Velve Peeltion Each Cheneel De not plea to lestell.
Ne Me Na CPS does not have se Me Dll) lealeties Ceedesser Water instation condeneer.
Level See parameter Dil Ne me Me Me Di2) leeletion Condenser System Talve Position Indicator Yes Tee IE DI)) DCIC Flow ladicator Tee Tee it D14) EPCs Flow InJicater Tee Tee It D15) Core sprey Systen Fles (LPCS)
Indicator Yes Tee IE 316) LPCI System Flow Tech Channel See Note Il No No No No D17) ELCS Plow See Note 12 Dil) SLCS Storage Teak Level Station Power Indicater Tea fee lediceter Tee Tee IE Dit) ENE System flaw tech Chamael w
r EnvitomeENTAL peedsSTEE Stl5NIC
_ quALIFICATlos qu4LITY
_ quai.IFICATION
_ASSUSANCE TVr8 9 (Cent'd)
_ RFOUNDANCY SANCg 320) met RE cettet Temperatore Will esoply with Will comply eith Ceeplies 2 channele 32' to 350' F e
10CFs50.49 Reg. Cuide 1.800 Dill Cee. leg Water Temperatore Witt comply with Will comply with Comptkee to ESF Systee Ceepesente 10CFESS.49 Reg. Guide 8.800 2 cheneels 32' to 200* F 922) Coelies Weter Fler to Unti comply with Will comply with Complies 3 cheneele ESF Systee Ceepeneste 40CFt10.49 Reg. GeiJe 1.800 O to 200 peig D21) uigh Bedienctioiry Liquid h/A 0 to 10000 Cpse Teek Leeet N/A N/A One cheesel Settee to top B24) Emergency 9entilaties per teak Deeper Peefties Will comply with Will comply with Ceeplies one cheeeel Opened and cleoed 10CFt50.49 Seg. Cuide 1.800 925) States of Steedby rever per deeper ned other Seergy Searces leperaset to Sefety
- 4) ADS lastrument Air Reeder Freeeere Will esoply with Will comply with Complies Two channel IOCFt50.49 seg. Guide 3.100 0-350 peig B) ABE Sechop Air Settle needer Fresesse Will eseply with Will comply with Ceeplies Tee cheneel 10Cn 50.49 Reg. Cuide 4.800 0-1000 peig C) DC Teltese Will eempty with Will esoply with Complies Three cheenal 0-52509 10CFESO.49 Reg. Cuide 5.800
- 9) BC Asperee Will comply with Wall comply with Ceeplies Three ehennel 0-600 AMPS 50CFa50.49 seg. Cuide 8.100
- 5) 4.16-69 Bee Teltages Will comply with Will eseply with Cooplies Three cheesel 0-5250v 0-400 An.*S 40CFE50.49 343. Ceide 1.500 F) 4.86-hv Bee leceming Will toeply with bill eseply with Complies Three cheeee!
0-800 A MS Steater Corrent 50CFE 50.49 Reg. Cuide 1.500 C) DC See Weltage 0-600 AMFS Will esoply with Will comply with 10CFt10.49 Complies
' Faer channel 0-150v seg. Ceide 1.800 B) SC See Current Will roeply with Will comply with 40CFB50.49 Ceeglies Thsee cheesel %
seg. Ceide 3.100
-100 to 200 AMPS
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- 9) Chloride Centeet Statice Faser Me Tee Tee
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- S It me Tee Tee tedicated en pees panel 534) accidset Seepting CapeHlity -
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f:
=
' Notes:
1.
Variable A2 - RPV Water Level Issue definition: The measurement of RPV water level is specified as a key variable in monitoring core cooling and maintaining core cooling and mcintaining'. r' actor coolant system integrity. RPV e
water level is classified as a Type A variable, Category I.
The specified range-is 197.6" to 636.5".
Discussion: Clinton Power Station has redundant and qualified level measurement for the range of 360.6" to 580.6" with respect to vessel bottom. Prior to power ascension following the first refueling outage, Clinton Power Station will have redundant and qualifled level measurement for the range of 208.6" to 408.6" with respect to vessel bottom. For the fuel zone range (208.6" to 408.6") the control room displays will include one fully cualified indicator and one unqualified, but properly isolated non-divisional recorder. The recorder instrument loop will be fully qualified, class 1E, up to and including the isolation device. Clinton Fower Station also has level measurement which is seismically qualified sfron the reactor coolant pressure boundary standpoint, but not environmentally qualified, for the range of 529.6" to 700.6" with respect to vessel bottom.
9
==
Conclusion:==
The Clinton RPV water level monitoring system design meets the intent of Reg. Cuide 1.97, Rev. 3.
2.
Variable A5 - Drywell Pressure Issue Definition: lhe neasurement of drywell pressure is specified as a key variable in maintaining containment and reactor coolant system integrity. Drywell pressure is classified as a Type A vaciable, Category I.
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 p
operation without adversely affecting operator judgement. The range provir 2ed exceeds the range proposed within Reg. Guide 1.97.
- e
_ (
3.
Variable B1 - Neutron Flux Issue definition: The measurement of neutron flux is specified as the key variable in monitoring the status of reactivity. Neutron fluxisclasg%to100%fullpower(SRM,APRM).
ified as a Type B variable, Category 1.
The specified n
range is 10" The stated purpose is " function detection;' accomplishment of mitigation".
e
Discussion: The Clinton neutron monitoring detectors are powered
.from a IE power source, but the SRM/IRM drive mechanisms and all neutron monitoring displays are powered from station power.
Continuous recording is provided. The existing 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 Category 1 system that meets all Reg. Guide 1.97, Rev. 3, requirements is an industry developement item.
Clinto will follow industry developmental activities and upgrade or replace the existing system when a fully qualified and proven neutron flux monitoring system becomes available.
.4.
Variable B5 - BWR Core Temperature Issue Definition: The measurment of BWR core temperature is specified to monitor the status of core cooling. BWR core temperatrue is classfied as a Type B variable, Category -
(unstated). The specified range is 200* F to 2300* f.
The stated purpose is "to provide diverse indication of water level".
Discussion: The use of in-core thermocouples has been investigated, and an analysis of the heat transfer in a BWR fuel bundle during a core uncovery event was performed to determine 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 accidents, there is a delay of at least 13 minutes between the start of core uncovery and the time when the thermocouples read 45' F above saturation.
It is also probable that operation of relief valves during a small-break LOCA would interfere with the thermocouples' operatin and could render them useless.
==
Conclusion:==
In-core thermocouples should not be required for diverse. water level monitoring and no longer are being considered
'by the Nuclear Regulatory Commission reference: NRC Generic Letter j
'84-23 dated October 26, 1984.
5.
-Variable B8 - Drywell Sump Level Variable C6 - Drywell Drain Sump Level Issue Definition: Reg. Guide 1.97 requires Category 1 instrumentation 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. The following discussion supports the IP position that drywell sump level and drywell drain sump level should not be implemented as r
Reg. Guide 1.97 parameters, however, in lieu of monitoring sump
levels, IP proposes to monitor the drywell equipment drain sump flow (drywell sump flow) and the drywell floor drain sump flow (drywell drain sump flow) with existing Category 3 instrumentation.
Discussion: The Clinton Power Station drywell has two 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 indication of breach of the reactor coolant system pressure boundary, 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 - Types C & E, Category 1 The Drywell Leak Detection system for the Clinton Power Station includes the monitoring of the drywell floor drain and equipment sumps as described in the CPS FSAR in Sections 5.2.5.4.2, 5.2.5.5, 5.2.5.10, 7.7.1.24.10 and 7.7.2.24.
In general, a detailed description of the drywell equipment sump and the drywell floor drain sump is provided in FSAR Section 7.7.1.24.10.1.1.
The sump leakage detection system is classified as not related to safety and uses non-essential 120-Vac instrument power. The system is in compliance with Reg. Guide 1.45 as described in FSAR SEction 5.2.5.10.
The normal design leakage collected in the flow drain sump includes unidentified leakage from the control rod drives, valve flange leakage, component service water, air cooler drains, and any other leakage not connected to the equipment drain sump. The flow drain sump is provided with a weir box through which all leakage flows.
The level of the water in the weir box is converted to a flow rate signal which is continuously recorded in the main control room. An excessive flow rate will activate an annunciator. The flow rate signal is also input to the plant process computer system. The flow rate is integrated to give a total sump influent volume and displayed on a resettable counter in the main control room.
The flow rate signal is input to a differential flow circuit which will actuate an annunciator in the main control room if the flow rate increases by one gpm in an hour.
In addition of the weir box flow rate monitoring, the sump pumps are equipped with interval timers which monitor the pumping and filling times of the sumps.
If the filling time becomes too short or the pumping time becomes too long due to higher than acceptable leakage, an annunciator is activated in the main control room.
m
4 A level switch, different from the one used for pump-control, is provided in each sump to alarm high sump level. This alarm would indicate that the sump is not being pumped down due to either a high leak rate or sump pump trouble.
The Emergency Procedure Guidelines uses the RPV level and the drywell pressure as entry conditions for the Level Control Guidelines. As such, the drywell sump indications are not the primary symptoms used for operator action in these guidelines. A small line break will cause the drywell pressure 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 above discussion, IP believes that the drywell sump level and drywell drain sump level instrumentation should not be implemented as a Reg. Guide 1.97 parameter. However, drywell sump flow and drywell drain sump flow will be implemented as a Category 3 instrumentation parameter.
6.
Variable B10 - Primary Containment Isolation Valve Position Issue definition: Primary containment valve position is specified as a key variablesto monitor containment integrity. Primary containment isolation valve position is classified as a Type B variable, Category I.
The specified 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.. All pressure relief valves are not capable of being fitted with position switches, but the intent of Regulatory Guide 1.97 is being met. The regulatory guide does not impose position indication requirements on any check valves.
==
Conclusion:==
Based on the above discussion, the Clinton design complies with Regulatory Guide 1.97 requirements.
d NOIES (Cont'd):
7.
Variable C1 - Rad b etivity Concentration or Radiation level in Dirculating Primary Coolant Issue definition: Regulatory Guide 1.97 specifies that the status of the fuel cladding be armitored during and after an accident..
h specified variaale to accouplish this monitoring is Variable C1-
--radioactivity concentration or radiation level in circulating
, primary coolant. h range is given as "% Tech Spec Limit to 100 times Tech Spec Limit, R/hr." In Table 2 of Re,gulatory Guide 1.97, Revision 3,- instrtunentation for measuring Varia)1e C1 is designated as Category 1.
The purpse for monitoring this variable is given as " detection of breach', referring, in tals case, to breach of fuel cladding.
Discussion: The usefulness of the information obtained by monitoring the radioactivity concentration or. radiation level in the circulating primary coolant, in terms of helping the oxrator
-in his efforts to prevent and mitigate accidents, has not been.
substantiated. - The critical actions that nust be taken to prevent and mitigate a gross breach of fuel cladding are (1) shut down the reactor and (2) maintain water level. Monitoring-Variable C1, as directed in the Regulatory Guide 1.97, will have no influence on either of these actions.- h purpose of this monitor falls in the category of "information that the barriers to release of radioactive material are being challenged".and " identification of degraded conditions and their magnitude, so the operator can take actions that are available to mitigate the consequences of fuel barriers being challenged, other than those based ca Type A and B variables, have not been identified.
Regulatory Guide 1.97 specifies measurement of the radioactivity of the ciruelating primary coolant as the key variable.in monTtoring fuel cladding status during isolation of the NSSS. h words
" circulating primary coolant" are interpreted to mean coolant, or a representative saiple of such coolant, that flows past the core.. A basic criterion for a valid measurement of the saecified variable is that the coolant being monitored is coolant tut is in active contact with the fuel, tut is, flowing past the failed fuel.
Monitoring the active coolant (or a sanple thereof) is the dominant consideration. The post-accident sarpling systen (PASS) provides a-representative sanple which can be monitored.
i e
E
Notes (Cont'd):
h subject of concern in the Regulatory Guide 1.97 requirment is assmed to be an isolated NSSS that is shut down. This asstmption is justified as current monitors in the condenser off-gas and main steam lines provide reliable and accurate infonnation 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 cln M Ng status, once the PASS is activated.
In the interim between NSSS isolation and operation of the PASS, monitoring of the primary containment radiation and contairunent hydrogen both Cate 1 variables, will provide infonnation on tw status of the fuel c
==
Conclusion:==
Based on the above considerations, IP believes that 4
the radioactivity concentration or radiation level in circulating primary coolant instruentation should not be inplanented as a Regulatory Guide 1.97 parameter.
8.
Variable C15 - Effluent Radioactivity - Noble Gas Issue definition: The measurement of effluent radioactivity -
noblegasisclassifiegasaTypeC3ariable, Category 2.
The specified range is 10-Ci/cc to 10 Ci/cc. The stated purpose-is " indication of breach".
Discussion: Clinton has procured instruentation to monitor effluent radioactivity 4 qualified to Category 2 requirenents which has a low range of 10 Ci/cc. It is neither feasiale nor practical to inplanent Category 2 qualified lower range instr mentation from the standpoint of functional need. Clinton hasCategory3in9traentationwhichprovidesalowerrange capability of 10-Ci/cc. Providing this lower range coverage by unquagied devices is acceptable since indication below the range of 10 Ci/cc is not applicable to accident scenarios.
==
Conclusion:==
Based on discussion above, the Clinton design meets the intent of Regulatory Guide 1.97 for this parameter.
9.
Variable D7 - Drywell Atmosphere Tenperature Issue definition: The measurement of drywell atmosphere tanperature is classified as a Type D variable, Category 2.
The specified range is 40*F to 440* F.
h stated purpose is "to monitor operation".
c NUIES (Cont'd):
Discussion: %e Clinton existing instrument range is 40* F to 350*
F.
h e impl e ented range exceed the DBA limit of 330* F. To extend the upward bound of this tenperature range would introduce greater departures from linearity.
I
==
Conclusion:==
Based on the above discussion, Clinton meets the intent of Regulatory Guide 1.97 for this parameter.
- 10. Variable D9 - MSIV leakage Control System Pressure Issue definition: %e measurement of MSIV leakage control system pressure is classified as Type D, Category 2.- % e specified ranges j;
are 0" to 15" H 0 and 0 to 5 psid. B e stated purpose is "to
- 3 provide indication of pressure boundary maintenance.
i Discussion: 2 e Clinton design monitors both the inboard and outboard syst e pressures. %e ranges of these instruments are 0"
.to 90" H 0 per system design. System differential pressure can be 9
ascertained from these instr ments. %e existing ranges of these instrments exceed the required ranges of the regulatory guide.
==
Conclusion:==
Based on the above discussion the Clinton design meets i
the intent of Regulatory Guide 1.97.
- 11. Variable D17 - SILS Flow Issue definition: %e measurment of SILS flow is classified as
%e stated purpose is "to nonitor operation.,0 to 110% design flow.
Type D, Category 2.
h e specified range is Discussion: We SILS on Clinton is manually initiated. Flow measuring devices were not provided for this system. %e pmp discharge header pressure, which is indicated in the control rom, will indicate SILS pmp operation. Besides the discharge header pressure observation, the operator can verify the proper functioning of-the SILS by monitoring the following:
1.
he decrease in the level of the SILS storage tank.
2.
% e reactivity change in the reactor as measured by neutron flux and boron concentration (the latter by sapling).
3.
%e SILS pmp motor contactor indicating lights.
4.
Squib valve continuity indicating lights.
A Notes (Cont'd):
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 c q-writs.
For Division 3, Clinton will utilize shutdown service water pmp discharge pressure, in conjunction with the shutdown service water pump 1SK01PC performance curves and proper valve alignment, as i
indication of flow to the Division 3 ESF system c = v w mts.
==
Conclusion:==
Based on discussion above, the Clinton design meets the intent of Regulatory Guide 1.97.
- 14. Variable D25(H) - DC Bus Current Issue definition: The measurement of DC bus current is classified j
as a Type D variable, Category 2.
The stated range is -300 to +700 anps.
i Discussion: Clinton instr m entation for Division 1, 2 and 4 has qualified bus current measurements for the range of -300 to +700 anps in the control room. Division 3 instrmentation for bus current measurement is monitored locally. Alarms are provided in the control room for Division 3 battery charger trouble and 125 VDC system trouble.
i
==
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 Regulatory Guide 1.97.
- 15. Variable E6 - Radiation Exposure Meters Discussion: Revision 3 of Regulatory Guide 1.97 states "it is l
unlikely that a few fixed-station area monitors could provide sufficiently reliable information to be of use in detecting i
releases from unmanitored containment release points... the decision to install such a system is left to the licensee."
Conclusion:
Clinton will not be inplementing this parameter.
5 a
w 1
4 k
Notes (Cont'd):
- 16. Variable E8 - Plant and Environs Radiation (Portable Instnanentation)
Issue definition: h measurement of plant and environs radiation is classifie h specified range is 10-j as a p /hr, photons:Evariable,Catggory34 to 10 R 10- to 10 Rads /HR, beta and low energ The stated purpose is " release assessment; analysis.gphotons.
Discussion: Clinton will utilize instn nentation that will measure the intended ranges.
==
Conclusion:==
Based on discussion above, the Clinton design meets the intent of Regulatory Guide 1.97 for this parameter.
i
.a a
s.-
s e
N a
.--,n--,
~-
,.,,,e n
, - - ~, -..
r NOTES (Cont'd):
The use of these indications is believed to be a valid alternative to SILS flow indication.
==
Conclusion:==
Based on the discussion above no direct indication of SILS flow is needed for Clinton.
- 12. Variable D18 - SILS Storage Tank Imvel Issue definition: The measurement of SILS storage tank level is classified as Type D, Category 2.
Thespecifiedrangeistopto bottom. The stated purpose is "to monitor operation'.
Discussion: The Category 2 requirement for the SLCS storage tank level instrtunentation is not considered appropriate for the following reasons:
1.
h current design basis for the SILS assumes a need for an alternative method of reactivity control without a concurrent loss of coolant accident or high energy line break. h i
environment.in which the SILS instrumentation nust work is,-
therefore, a " mild" enviroment for qualification purposes.
2.
The current design basis for the SILS recognizes that the
-systs has a classification that is less tun the safety related classification of the reactor protection system and the engineered safeguards systems.
Based on a graded approach to safety, this variable is nore appropriately considered a Category 3 variable.-
==
Conclusion:==
Based on the above discussion, the existing instninentation meets Category 3 design and qualification criteria.
[
The SILS design criteria is in coupliance with-the ATWS rule making i
in 100 R50.62.
I
- 13. Variable D22 - Cooling Water Flow to ESF Couponents l
Issue definition: The measurement of cooling water flow to ESF
(
couponents is classified as a Type D variable, Category 2.
The "pecified range is 0 to 110% design flow. The stated purpose is l
s to monitor operation."
i 6
1 1