ML20214K748
| ML20214K748 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, Catawba, McGuire, 05000000 |
| Issue date: | 11/24/1986 |
| From: | Tucker H DUKE POWER CO. |
| To: | Harold Denton, Youngblood B Office of Nuclear Reactor Regulation |
| References | |
| TAC-49653, TAC-53290, TAC-65099, NUDOCS 8612020445 | |
| Download: ML20214K748 (19) | |
Text
,_._
e DUKE POWER GOMPANY P.O. HO_1C 33180 CHAMLOTTE, N.C. 28242 HAL!!. TUCKER Trsrenown vum reemorwr (704) 073-4a3 nuasse rumverum November 24, 1986 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission j
Washington, D.C.
20555 ATTENTION:
B.J. Youngblood, Director PWR Project Directorate #4
Subject:
McGuire Nuclear Station Catawba Nuclear Station l
Docket Nos. 50-369, -370, -413, -414 i
Reactor Coolant Pump Trip
Dear Mr. Denton:
In response to your letter dated September 25, 1986, Duke has reviewed the i
" Request for Additional Information and Record of Telephone Conversation regarding Reactor Coolant Pump Trip".
Our comments are provided in the attached.
I.
If there are any questions regarding this, please handle through the normal Licensing channels.
Very truly yours,
/
B/s Hal B. Tucker RLG/129/jgm Attachments xc:
Dr. J. Nelson Grace Darl Hood Regional Administrator Office of Nuclear Regulation U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Region II Washington, D.C.
20555 101' Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 8612020445 861124 PDR ADOCK 05000369 O{
Dr. K.N. Jabbour S
PDR O
Office of Nuclear Regulation U.S. Nuclear Regulatory Commission
)
Washington, D.C.
20555
DUKE POWER COMPANY McGUIRE NUCLEAR STATION CATAWBA NUCLEAR STATION Response to NRC Letter Dated September 25, 1986 Requesting Additional Information and Record of Telephone Conversation Regarding Reactor Coolant Pump Trip.
Page 8, Line 18 - Response ~to Staff Comment -
The selection of loss of subcooling as the RCP trip criterion for McGuire and Catawba was based on an evaluation of pros and cons associated with each criterion, with emphasis on the overall intent of the trip criteria and human factors aspects..The foremost concern was the direct applicability of the selected criterion to the phenomenon that the pump trip is intended to protect against. Clearly, a loss of subcooling is the only direct indication of when RCS inventory loss following a SBLOCA has increased to where two-phase conditions exist. Two-phase conditions must be present before the inventory depletion has evolved to where a delayed or inadvertent pump trip could lead to the core.uncovery concern.
It should be noted that the loss of subcooling criterion was.also identified by the B&WOG as the optimum pump trip criterion. Another strong point associated with the loss of subcooling criterion is its applicability during any plant operating mode. Although the worst case SBLOCA initiates from full power, SBLOCAs occurring in other
. operating modes must also be mitigated. Prompt tripping of the RCPs is not as critical, but it should still be performed to limit inventory loss and potential pump damage.
The low RCS pressure pump trip criterion is clearly the best in terms of simplicity. However, low pressure is lacking in terms of being more vul-nerable to spurious pump trips, in particular following overcooling tran-sients, and also lacks applicability in some operating modes. The primary-to-secondary. pressure difference criterion is least desirable in terms of direct applicability. Its best advantage is that it provides a means to distinguish between SBLOCAs and overcooling transients. The primary-to-secondary pressure difference criterion is also, in our opinion, the most complex. It is somewhat subject to spurious trips associated with pressure transients and instrument failures.
Based on the above arguments, the loss of subcooling criterion is the most direct, the optimum in terms of phenomenological basis, and the most widely applicable under all plant operating modes.
It was therefore selected for all Duke nuclear stations.
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Page 2 Page 8, Line 26 - Duke Comment -
The plant computer is no longer the " primary" indicator of the need to trip RCP's.
Since the initial Duke response to NRC Generic Letter 85-12, an Inadequate Core Cooling Monitor (ICCM) has been installed at both McGuire and Catawba.
The ICCM is a Class IE microprocessor-based system which monitors several primary system parameters in order to determine the presence of abnormal core cooling conditions. The ICCM is a two-train system, with each train separate-ly monitoring one RVLIS train, two hot leg vide-range temperatureJ, twenty of the forty Class IE core exit thermocouples, and wide range RCS pressure. The ICCM includes a core cooling display consisting of a dynamic RCS pressure /-
temperature plot and a display of the indications available to monitor core cooling status. The information displayed enables the operators to determine the available margin of subcooling. Should a discrepancy in subcooled margin occur between the subcooled margin programs on the Operator Aid Computer (OAC) and the ICCM, the ICCM indication is utilized since it is a safety-grade cystem. Should one of the two independent channels of RCS wide range pressure be inoperable, the ICCM will remain the primary indication for determining loss of subcooling.
Page 9, Line 19 - Duke Comment -
l This sentence is incorrect as all instrumentation is not Category 1 with full redundancy. The RCS wide range pressures, wide range-hot leg temperatures, and core exit thermocouples, are Category 1 (see attached pages from McGuire response to NUREG-0737, Supplement 1, RG 1.97, Rev. 2).
However, the RCS low range pressure transmitters are not functionally safety related and there is only one loop per unit. Although the McGuire low range transmitters are
. qualified to IEEE 32371 standards, the Catawba transmitters are not quali-fled.
The McGuire RCS wide range pressure indicators will be upgraded during the 1988 refueling outages.
Page 9,'Line 24 - Duke Comment -
The current as-built condition of McGuire and Catawba has the RCS low range pressure transmitters located in the annulus (a potentially harsh environment due to a LOCA or MSLB) and the wide range pressure transmitters (safety related-redundant) located in penetration rooms (a mild environment).
Page 3 Page 9, Line 31 - Duke Comment -
Use " wide range" rather than high range.
Page 10 Line 10 - Response to Staff request -
Analyses of the subcooled margin monitor errors were performed to evaluate the uncertainties associated with the subcooling monitors at the McGuire and Catawba Nuclear Stations. The analyses determined the sensor / instrumentation string errors associated with wide range RCS pressure, low range RCS pres-sure, wide range hot leg temperature, and incore thermocouple temperatures.
Instrumentation string errors were calculated using the SIGMA Monte-Carlo simulation code. The analyses also combined string errors to determine the uncertainties of indicated parameters and to determine correction factors for the saturation curve. The combination of string errors for wide range RCS pressure, wide range hot leg temperature, and incore thermocouples for both McGuire and Catawba was performed by the SIGMA code. The combination of string errors for low range RCS pressure for McGuire and Catawba was per-formed by the SIGMA code and square root of the sum of the squares (SRSS) methodology, respectively. The change in methodology for calculating the combination of string errors was made after a compariscn of results showed the simpler SRSS gave results very.similar to the SIGMA Monte-Carlo simu-lation code. The correction factors for the saturation curve are the sum of i.
the calculated saturated temperature margin and a margin of 5 degrees-F to account for environmental factors and calculational uncertainties.
The analyses were performed for both normal and degraded containment conditions.
j A sample of the calculated values for normal containment conditions follows:
l RCS Saturation O'F Subcooling Subcooled Pressure Temperature Temperature Margin (psia)
(*F)
(*F)
(*F) 300 417.35 385.55 31.80 900 531.95 514.13 17.82 i
1700 613.13 601.73 11.40 l
2500 668.11 658.13 9.98 l
l l
l l
l
Page'4 i
i Page 10, Line 16 - Response ~to Staff Request -
Since the McGuire and Catawba RCS low range pressure transmitters are not functionally. safety related and the RCS wide range pressure transmitters are located in a mild environment, none of the transmitter applications are required to be documented in NUREG 0588.
(The McGuire wide range applica-tions are, however, documented in NUREG 0588 based on their previous locations in the Annulus. These applications will be deleted from the McGuire response to NUREG-0588 based on their current location in the Penetration Rooms. These application sheets are attached for your information.) RCS wide range temperature RTD application sheets are also attached. Additionally, based on the McGuire response to the Generic Letter mentioning pressurizer pressure transmitters as a potential source / indication of RCS pressure, the associated NUREG-0588 application sheets are also attached for your information.
1 1
Page 10, Line 21 - Response to Staff Request -
The pressure inputs available to the subcooled margin program on the plant operator aid computer (OAC) at McGuire are one channel of RCS low range pressure and one channel of RCS wide range pressure.
The pressure input is selected from the RCS. low range pressure, if valid, since this instrument had j
the smaller uncertainty. Otherwise, the RCS wide range pressure is used.
If 4
this indication is unavailable, pressurizer pressure is used as a substitute.
Ths-errors associated with pressurizer pressure are bounded by the RCS wide range pressure errors. Consideration is being made to possibly add a second wide range pressure channel to the McGuire OAC in order to make the subcooled margin programs at McGuire and Catawba identical.
4 The pressure inputs available to the subcooled margin program on the OAC at.
Catawba are one channel of RCS low range pressure and two channels of RCS wide range pressure. The pressure input is selected from the RCS low range pressure, if valid, since this instrument has the smaller uncertainty.
j Otherwise, an average of PCS wide range pressure is used.
If one of the RCS wide range pressure channels is unavailable, the secor.d channel is used alone.
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i Page 5 Page 13, Line 23 - Response to Staff Request -
The uncertainties pertaining to the WOG generic analyses of plant behavior under non-LOCA conditions were determined by taking the results for a group of nuclear plants and determining the variation on the calculated results due to plant specific differences. The WOG analyses determined the number of loops, type of safety injection system, steam generator tube diameter, and no-load temperature to be the significant plant characteristics influencing plant transient behavior during a SGTR. The minimum RCS pressure for the model best representing McGuire/ Catawba in the SGTR transient was 1698 psia.
This pressure is considerably higher than the UHI actuation setpoint.
The plants in the WOG study are grouped for the non-LOCA analyses according to the number of loops and type of safety injection system.
The minimum RCS pressure occurring during the McGuire/ Catawba representative steam line break analyses was 1774 psia. The presence of UHI makes no difference in the plant response to SGTR and SLB accidents as determined by the WOG analyses since neither transient results in a depressurization of the primary system below the UHI actuation setpoint. The uncertainty value of + 10'F which includes the effect of uncertainty in break flow and safety injection flow is appli-cable to both McGuire and Catawba.
(
McGUIRE NUCLEAR STATION REGULATORY GUIDE 1.97, REV. 2 REVIEW A-1, Variable:
RCS Pressure B-7, 8-11, Range:
0 to 3000 psig C-4, C-9 Category:
1 Existing Design:
McGuire has two redundant, QA Condition 1 channels of Wide Range RCS pressure instrumentation.
Each transmitter feeds a different channel of the PCS and is powered by that channel's associated Class 1E buss.
The control board indicators share PCS output isolation devices with other non-safety equipment as described in Paragraph 5.5.1.3.1.a.
The indicated range is 0 to 3000 psig.
Redundant /
diverse indication is provided by control grade RCS pressure instrumentation provided for the standby shutdown facility, as well as the QA Condition 1 pressurizer pressure instrumentation.
Environmental qualification is described in the McGuire Nuclear
(
Station FSAR, Section 3.11 and the NUREG 0588 submittal.
Seismic qualification is described in the McGuire FSAR, Section 3.10 and Paragraph 5.5.1.3.la of this submittal.
l Compliance:
This instrumentation is not in full compliance with l
the recommendations of RG 1.97, Rev. 2 as the control indicators are interconnected with non-seismically qualified equipment.
j Display:
Two Control Room indicators One channel on the computer i
One channel recorded Position:
The indicator circuits for this variable will be upgraded as described in Paragraph 5.5.1.3.la.
Implementation Schedule:
These modifications will be ccmpleted by the e~nd of the first refueling outage following January, / j>SS
.1986 for each unit, contingent upon equipment l
availability.
i i
i 5-19 Revision 3 L
(
McGUIRE NUCLEAR STATION REGULATORY GUIDE 1.97, REV. 2 REVIEW A-2, Variable:
Core Exit Temperature B-8, C-1 Range:
200*F to 2300*F Category:
1 Existing Design:
The QA Condition 1 Core-Exit Thermocouple System for accident monitoring will consist of at least 20 thermocouples.
The primary display will be the plant computer, with a Class 1E backup display device.
Inputs to the plant computer will be through qualified Class 1E isolation devices.
Power for the Class 1E portion of the system will be from Class 1E busses, and power for the non-safety portion will be a highly reliable battery backed control buss.
Redundancy / diversity is provided by the Hot and Cold Leg RCS temperature instrumentation.
Environmental qualification for the Class 1E portion will be per the McGuire
(
Nuclear Station FSAR, Section 3.11 and the NUREG-0588 submittal.
Seisr.ic qualification will be described in the McGuire F.iAR, Section 3.10. The existing incore thermocouples will be assumed to be environmentally and seismically qualified as allowed by NUREG 0737 II.F.2 Attachment 1.
The plant computer and backup display are installed in a mild environment.
Range of the system is 200*F to 2300*F.
Compliance:
This instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev. 2 as clarified in Section 5.5.
Display:
Primary display will be the plant computer CRTs in the Control Room.
Backup display will be a Class 1E indicator in the Control Room.
Position:
The upgraded instrumentation will be' adequate for the intended monitoring function.
Implementation Schedule:
The qualified, in containment portion of the ccre exit thermocouple system will be installed prior to startup following the first refueling outate for each Unit.
The Class 1E backup display will.be added by the end of the first refueling outage following January, ASSfr for each unit, contingent upon equipment availability.
IM 5-20 Revision 3
McGUIRE NUCLEAR STATION
)
REGULATORY GUIDE 1.97, REV. 2 REVIEW A-3, Variable:
RCS Hot Leg Water Temperature l
B-5 Range:
50*F to 750*F I
Category:
1 Existing Design:
Each of the four reactor coolant loops employ a QA i
Condition 1 Hot Leg Water Temperature measurement (Ts).
Two of the T instruments feed into one RVLIS chMnnel and are p red from the associated Class 1E buss. The other two T instruments feed into a h
redundant PCS channel and are powered by that channel's Class 1E buss.
The control board display devices (recorders)' share output isolation devices with other non-safety equipment as described in Paragraph 5.5.1.3.la.
The indicated range is O'F to 700'F. The environmental qualification of this instrumentation is described in the McGuire Nuclear Station FSAR, Section 3.11 and the NUREG 0588 submittal.
The seismic qualification is described in the McGuire FSAR, Section 3.10 and Paragraph 5.5.1.3.la of this submittal.
Redundancy / diversity is provided by monitoring Th n all four loops l {
along with monitoring of on all four loops and monitoring of incore the couples.
The existing design does not fully comply with the Compliance:
recommendation of RG 1.97, Rev. 2 because the range does not conform-to RG 1.97, Rev. 2 range of 50*F to 750*F.
Also, the control board display devices (recorders) are not seismically qualified and are interconnected to other non-seismically qualified equipment.
Display:
Four channels recorded Four channels on the computer Position:
The range of the installed instrumentation is adequate for the intended monitoring function.
No range change is required as the installed range is adequate for a Westinghouse NSSS System.
Also note, the present range meets the recommendation of RG 1.97, Rev. 3.
The recorders for this variable will be replaced with seismically qualified units and will be provided with isolated output signals which are not shared with non-seismically qualified equipment.
Implementation Schedule:
These modifications will be completed by the end of the first refueling outage following January, (9$8
,3986' Tor each unit, contingent upon equipment availability.
5-21 Revision 3
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McGUIRE NUCLEAR STATION REGULATORY GUIDE 1.97, REV. 2 REVIEW A-6, Variable:
Degrees of Subcooling B-10 Range:
200*F Subcooling to 35'F Superheat Category:
2 Existing Design:
This variable is a computer calculated value,using various inputs from the Primary System.
A graphic display over the required range gives the operator a representation of primary system conditions compcred to various curves of importance (saturation, NOT,etc.).
The computer is powered by highly reliable battery backed control power.
The computer processing and CRT display are located in a mild environment.
Primary inputs to this graphic display are provided from QA Condition 1 instruments which have been isolated for input to the computer.
Additional inputs of lesser qualification are used, when available and within valid ranges, to provide
(
additional accuracy.
A procedure to manually calculate subcooling margin, using QA Condition 1 instruments for information, exists as a backup to the graphiq display.
Compliance:
This instrumentation is in compliance with Duke's interpretation of RG 1.97, Rev. 2 as clarified in Section 5.5.
Display:
Control Room - Computer graphic on deraand.
Position:
Due to the mild environment maintained in the Computer Room, the projected high availability of the computer and the backup procedure to calculate this variable, Duke Power considers that the installed instrumentation is adequate for the intended monitoring function.
Implementation Schedule:
Not Applicable.
t 5-24 Revision 3
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f g 13 W McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 1 l
ppOV@N uCW UMMARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED INSIDE CONTAINMENT EQUIPMENT ID:
Transmitter - Pressurizer MANUFACTURER:
Barton MODEL #:
763 (Lot 2)
(1)
Pressure (Lower Containment)
(NSSS)
(Unit 1)
ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIR0flMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (2)
QUALIFIED ACCIDENT
(% OF SPAN)
(% OF SPAN)
ENVIRONMENT (3)
Temp:
327 F Temp:
380 F SI Initiation 5 minutes
+10%
Max. Error 7.7%
Press:
14.8 psig Press:
75 psig
(<5 min.)
post DBE (5 min.)
RH:
100%
RH:
100%
Rad:
2.5X10GR Rad:
5X107R Chem Spray: N/A Chem Spray:. Boric acid and sodium hydroxide soln.
2750 ppm Boron, 8.5 pH QUALIFICATION REPORT:
WCAP 9885 (MCM-1399.03-439)
METHOD:
Test ECSE
Q-r\\
McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 5
SUMMARY
OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 1 LOCATED INSIDE CONTAINMENT EQUIPMENT ID:
Transmitter - Pressurizer MANUFACTURER:
Barton MODEL #:
763 (Lot 4, Lot 5)
(1)
Pressure (Lower Containment)
(NSSS)
(Unit 2)
ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (2)
QUALIFIED ACCIDENT
(% OF SPAN)
(% OF SPAN)
ENVIRONMENT (3)
Temp:
327 F Temp:
420 F SI Initiation 5 minutes
+10%
+10%-
Press:
14.8 psig Press:
57 psig
(<5 min.)
post DBE RH:
100%
RH:
100%
Rad:
2.5X10GR Rad:
SX107R Chem Spray: N/A Chem Spray:
Boric acid and sodium hydroxide soln.
2500 ppm Boron, 10.7 pH QUALIFICATION REPORT:
WCAP 8587 Supp. 1, EQDP-ESE-1 and WCAP 8687 Supp. 2, E01A (MCM-1399.03-0472)
METHOD:
Test HPIC 1
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O' McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 10 SUt41ARY OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E. EQUIPMENT Rev. 2 LOCATED INSIDE CONTAINMENT EQUIPMENT ID:
MANUFACTURER:
Rosemount MODEL #:
176 KS (1)
(Lower Containment)
(NSSS) l ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY.
ACCURACY ACCURACY I
ENVIROUMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (2)
QUALIFIED ACCIDENT
(% OF SPAN)
(% OF SPAN)
ENVIRONMENT (3)
Temp:
327 F Temp:
332 F 2 weeks 2 weeks 10.2%
10.2%
Press:
14.8 psig Press:
100%
RH:
100%
Rad:
1X108R Rad:
1X108R Chem Spray: Boric Chem Spray: Boric acid and sodium acid and sodium tetraborate soln.
hydroxide soln.
1.46 wt. % Boric acid 8.5 pH QUALIFICATION REPORT: WCAP 9157 and Supplemental Documentation dated July 20, 1983 and Duke letter Parker to Denton dated December 19, 1979 (MCM-1399.03-0438)
METHOD:
Comparison to Model 176 KF, Test / Analysis ECSE
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-p a b ) cr h r M ' d <*I' #,
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McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Page 2 l
SUMMARY
OF ENVIRONMENTAL QUALIFICATION,0F CLASS 1E EQUIPMENT Rev. 1 LOCATED IN THE ANNU S EQUIPMENT ID:
Transmitter-RCS Pressure (WR)
MANUFACTURER:
osemount MODEL #:
1153GA9 (Unit 1)
ACCIDENT ENVIRONMENT OPERABILITY OPEPABILITY ACCURACY ACCURACY l
ENVIRONMENT TO WHICH REQUIREDJ DEMONSTRATED REQUIRED DEMONSTRATED l
(1)
QUALIFIED ACCIDENT (2)
(% OF SPAN)
(% OF SPAN)
ENVIRONMENT
/
1
/
Tertp:
142 F Temp:
350 F months 1 year i 10%
+6.95%
RH:
100%
RH:
100%
1.0x10CR Rad:
4X107R QUALIFICATION REPORT:
Rosemont Test Report 3788, Rev. A (i1CM-1210.04-0173)
METHOD:
Type Test Similarity MPIC
O~
ofMe*3 4-McGUIRE NUCLEAR STATION - UNITS 1 D2 Page 2A
SUMMARY
OF ENVIRONMENTAL QUALIFICATION OF SS 1E EQUIPMENT Rev. O LOCATED IN THE ANNULUS EQUIPMENT ID:
Transmitter-RCS Pressure (WR)
MANUFACTURER:
Ro mount MODEL #:
1153GD9 (Unit 2)
ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (1)
QUALIFIED ACCIDENT (2)
(% OF SPAN)
(% OF SPAN)
ENVIRONMENT Temp:
142 F Temp:
350 F 4 month 1 year i 10%
-5.5%
RH:
100%
RH:
100%
2x10GR Rad:
4X107R QUALIFICATION REPORT:
Wyle Test Report 45592-1 (MCM-1210.04-0178) j MET 1100:
Type Test i
MPIC
u v-y C
O N
O" 9
- )
93-Q'r{
1
~
trU (t
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McGUIRE NUCLEAR STATION - UNITS 1 AND 2 Pa0e 3
SUMMARY
OF ENVIRONMENTAL QUALIFICATION F CLASS 1E EQUIPMENT Rev. 1 LOCATED IN TiiE ANNUL 1
EQUIPMENT ID:
Transmitter-RCS Pressure (WR)
MANUFACTURER:
arton MODEL #:
763 (Lot 2) l (Unit 1)
ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN..
DEMONSTRATED REQUIRED DEMONSTRATED (1)
QUALIFIED ACCIDENT,
(2)
(% OF SPAN)
(% OF SPAN)
ENVIRONME
/
Temp:
142 F Temp:
380 F 2 weeks 1 year i 10%
1 7.7%
RH:
100%
RH:
100%
1.2X10 R Rad:
SX107R 7
7
/
QUALIFICATION REPORT:
WCAP 9885 (MCM-1399.03-0439)
METil00:
Test ECSE
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McGUIRE NUCLEAF. STATION - NITS 1 AND 2 Page 4
SUMMARY
OF ENVIRONMENTAL QUALIFICA ON OF CLASS 1E EQUIPMENT Rev. 1 LOCATED IN THE'A UlisS EQUIPMENT ID:
Transmitter - RCS Pressure (WR)
MANUFACTURE.
Barton MODEL #:
763 (Lot 5)
(Unit 2)
ACCIDENT ENVIRONMENT OPERABIL OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WHICH REQUIRED IN DEMONSTRATED REQUIREL DEM0NSTRATED (1)
QUALIFIED ACCIDENT (2)
(% OF SPAN)
(% OF SPAN)
ENVIRONMENT
/
Temp:
142 F Temp:
42,'F eeks 1 year i 10%
10%
100%
RH:
100%
p Rad:
1.2X107R Rad:
5X107R
/
QUALIFICATION REPORT:
4 CAP 8587 Supp. 1, EQDP-ESE-1 and WCAP 8687 Supp. 2, E01A (MCM-1399.03-0472)
METHOD:
Test ECSE
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O CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 5
SUMMARY
OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 3 LOCATED INSIDE CONTAINMENT EQUIPMENT ID:
RID -
MANUFACTURER:
RdF Corp.
MODEL #:
21205 (1)
(NSSS)
(lowerContainment)
ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT 10 WilICll REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (2)
QUALIFIED ACCIDENT
(% OF SPAN)
(% OF SPAN)
ENVIRONMENT Temp:
327 F Temp:
420 F 2 weeks 4 months 1 0.2%
i 0.0%
Press:
14.4 psig Press: 72 psig post DBE post DBE Ril:
100%
Ril:
100%
7 Rad:
6.6X10 R Rad:
2.47X10bR for Tip 8
1.22X10 R for Cable Chem Spray: Boric acid and sodium Chem Spray:
Boric tetraborate soln.
acid and sodium hydroxide soln.
2750 ppm Boron 0.9% Na0ll 10.7 pH SUBMERGENCE:
Yes (Note 4)
QUALIFICATION REPORT: WCAP 8687, Sup. 2, E06A (CNM-1399.03-328)
MEll100:
Test REPLACEMENT INTERVAL:
10 years ECSE
O s
CATAWBA NUCLEAR STATION - UNITS 1 AND 2 Page 1
SUMMARY
OF ENVIRONMENTAL QUALIFICATION OF CLASS 1E EQUIPMENT Rev. 3 LOCATED INSIDE CONTAINMENT EQUIPMENT ID:
Transmitter -
MANUFACTURER: Barton MODEL #:
763 (1)
Pressurizer Pressure (NSSS)
(Lot 2)
(Lower Containment)
ACCIDENT ENVIRONMENT OPERABILITY OPERABILITY ACCURACY ACCURACY ENVIRONMENT TO WilICil REQUIRED IN DEMONSTRATED REQUIRED DEMONSTRATED (2)
QUALIFIED ACCIDENT
(% OF SPAN)
(% OF SPAN)
ENVIRONMENT Temp:
327 F Temp:
380 F SI Initiation
>5 minutes
+ 10%
Max. error 7.7%
Press:
14.4 psig Press:
90 psig
(<5 minutes) post DBE (5 minutes)
Ril:
100%
Ril:
100%
7 Rad:
5.0E6R Rad:
SX10 R Chem Spray: Boric Chem Spray: Boric acid and sodium acid and sodium tetraborate soln.
hydroxide soln.
2750 ppm Boron 8.5 pil SUBMERGENCE:
Yes (Note 3)
QUALIFICATION REPORT: WCAP 9885 (CNM-1399.03-318)
MEll10D:
Test ECSE REPLACEMElli INTERVAL:
10 years
.