ML17266A088
| ML17266A088 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 07/02/1979 |
| From: | Robert E. Uhrig FLORIDA POWER & LIGHT CO. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| NUDOCS 7908090141 | |
| Download: ML17266A088 (81) | |
Text
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P. O. BOX 013100, MIAMI, FL 33101 FLORIDAPOWER & LIGHT COMPANY July 2, 1979 L-79-181 Mr. James P. O'Reilly, Director, Region II Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303
Dear Mr. O'Reilly:
Re:'II JPO 50-335 IE Bulletin 79-01 The attached information is submitted in response to the subject Bulletin.
A detailed test documentation package will be available at the St. Lucie plant site by early August, 1979.
As discussed in the Attachment, the following equipment will be replaced:
(a)
ASCO solenoid valves and NAMCO limit switches, including sealant material, on CVCS Letdown Isolation Valves and Containment Radiation Sampling System Isolation Valves, and (b)
AVCO solenoid valves and NAMCO limit switches, including sealant material, on Containment Purge Supply and Exhaust Isolation Valves.
The AttachIIent also discusses the justification for continued operation until these items can be replaced.
Very y yours, Robert E. Uhrig Vice President Advanced Systems 5 Technology REU/MAS/cph Attachmen t cc:
Harold F. Reis, Esquire 7tggy g Docket@~
Controt@Pg~g o
t</
Date.
of acument.
IKGQ1ILTGRY GCKHF04~
FLORIDA POWER AND LIG1IT CO.
.RESPONSE TO 16E BULLETIN 79-01 FOR ST.LUCIE UNIT NO.
1 ENVIRONHENTAL UALIFICATION OF CLASS IE E UIPMENT June 29, 1979
TABLE OF CONTENTS Section TITLE PAGE 20 30 2.1 2 2 3.1 3.2 3-3 Introduction Post-Accident Environment Post-LOCA Environmental Conditions Main Steam Line Break Environmental Conditions Qualification of Electrical Equipment Introducticn Post-Accident Equipment Qualification Summary Remarks and Justification for Continued Operation l-l 2-1 2-1 3-1 3-1 3-2 3-8 Conclusions Qualification Data Sheets 4-1 5-0
1-1 1.
Introduction This report responds to I&K Bulletin 79-01 which contains.-the NRC's request for written evidence of the qualification of electrical equip-ment required to function under post accident conditions.
The report includes a description of the post-accident environmental conditions involved, the actual qualification data available and our conclusions.
The equipment discussed and environmental conditions described have been selected following a review of the St. Lucie Unit 1 licensing docket.
Documents contained therein which were utilized to establish qualification parameters include the
This search was undertaken to ensure the report contained a complete and updated compilation of electrical equipment required post-LOCA inside contain-ment, plus the limiting environmental conditions.
St. Lucie Unit 1 discussed the environmental qualification of electrical equipment in Section 3.11 of the FSAR.
This section not only established the criteria to be met by the equipment determined to be required, but also included in an appendix, the discussion of the tests and analyses performed to qualify the majority of these devices.
The documentation search for St. Lucie took the form of either ensuring the written evidence was readily accessible at our general offices or plant files and con-tacting the vendor for the necessary documents.
Qualification documentation problems generic to the nuclear industry, such as ASCO Solenoids and NAMCO limit switches were found to apply to St. Lucie 1 also.
The application of each of these devices were reviewed (see Section
- 3) and following an engineering evaluation of application it was determined that continued safe operation with the existing devices could be assured.
These devices were reordered ho~ever, with the require qua q alification to ensure safety margin and operability.
The remainder of ments of the documentation was substantially complete and met the commitments o
the FSAR.
2-1 Post-Accident Environment 2.1 Post-LOCA Environmental Conditions The plant environmental service conditions within the containment are classified in the following environmental design categories described in FSAR section 3.11.1:
I-A Long term containment environment following LOCA or steam line break accident I-B Short term containment environment following LOCA or steam line break accident The environmental conditions of temperature,
- pressure, humidity, and radiation for each of these two categories are presented in Table 3.11-1 of the FSAR and are repeated in Tables 2-1 and 2-2 herein.
The category I-A and I-B environmental conditions completely envelope the worst case loss of coolant accident considered in the FSAR.
This worst case LOCA is a double ended slot rupture at the suction of the reactor coolant pump in the cold leg (9.82 ft2 break area).
This results in the highest peak contain-ment pressure (38.4 psig) and coincident temperature (259'F).
The postulated accident pressure and temperature time history curves are presented in Figures 6.2-1A and 6.2-1C of the FSAR
'nd are included in Figures 2-1 and 2-2 of this section respectively.
The containment radiation environment is based on a LOCA fission product release source consisting of 50 percent of the core halogen inventory, 100 percent of core inventory and 1 percent core solid fission product inventory.
In addition to the temperature,
- pressure, humidity, ano radiation environments described in the above categories, the electrical equipment within the containment will be exposed to a chemical environment.
The pH of the containment spray is maintained be-tween 8.5 and ll during both injection and recirculation by the injection of sodium hydroxide.
This chemical spray environment will exist for only a limited period following which the the equipment in question will begin to dry.
2.2 Main Steam Line Break Environmental Conditions The containment atmospheric temperature exceeds that of categories I-h and I-B (see tables 2-1 and 2-2) for the worst case main steam line break accident for approximately 40 seconds.
The worst case MSLB accident occurs at 105X power with a 5.355 ft2 break area.
The postulated accident prcssure and temperature time history curves are presented in Figures 6.2-14 and 6.2-12 of the FSAR and are in-cluded in Figure 2-3 and 2-4 of this section respectively.
2-2 2.2 (Continued)
This temperature (290'F) has not been used as a basis for environmental qualification of electrical equipment due to the extremely short time of the transient as discussed in the FSAR.
2-3 TABLE 2-1 ENVIRONMENTAL REQUIRElKNTS ST. LUCIE UNIT 1 LICENSING CON IIT!KilTS Category I-A Time Temperature Pressure Humidity (X
Radiation R/hr 0-2hr 270 44 100 2x10 2-24 hr 240 27 100 1 x 106 1-31 day 150 100 3 x103 31 day-1 yr 130 100 10 NOTES:
(1)
Integrated Accident Dose (R):
40 years of Normal Operation (R):
Total Integrated Dose (R) 2.8 x 107 3.5 x 105 2.8 x 107 (2)
For Hain Steam Break Qualification see Section 2.2
2-4 TABLE 2-2 ENVIRONMENTAL REQUIREMENTS ST. LUCIE UNIT 1 LICENSINC COMMIZiENTS
~Cete o
I-B Time min.
Temperature Pressure Humidity X)
Radiation R
15 270 44 100 7.6 x 105 Integrated Accident Dose (R):
40 years of Normal Operation (R):
Total Integrated Dose (R) 7.6 x 10 3.5 x 105 1.1 x 106
tV I
100 Iol I00 TIME {SECT 10S I04 l0$
Re<.
32 9/f/74 FLORIVA PWER N LR;I 5IEAQ I.IHK bNEAK FIGURE
- 6. 2-14
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32 9/6/74 FLORIDA POwER L LICHT COffPAHY ST. LVCIK PLAHT VHIT I O 0 N 'I AINVfV 1 A I VOi >Ilf Rt AVO I IQVIP TfVafOATURK5 Y5. TIVt fOR A 105%
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3-1 3.
uglification of Electrical E ui ment 3.1 Introduction The purpose of this section is to present a summary of the qualification data for electrical equipment located inside the containment which is required to function under accident conditions (see Section 2 for description of the post-accident conditions).
The selection of the summarized equipment corresponds to those required for the safe shutdown of the plant following a Design Bases Accident as stated in the various licensing documents for the docket (FSAR, SER, letters to the NRC, etc.).
The investigation for data was done on a "loop" basis, that is the emphasis was placed on obtaining qualification data for the electrical loop from the penetration to the device.
For example, the manufacturer and model number was obtained for the penetration,
- cable, splices, position indication and operator for all containment isolation valves, and qualification data was pursued for each component in the loop.
This approach was utilized to avoid a piecemeal component
- search, assure completeness and assure post-accident operability.
The summary sheets in Subsection 3.2 contains the results of the search for qualification data for these electrical devices.
The actual documentation and a summary of the report results is referenced to the appropriate page in Section 5.
In those cases where further analytical work was required or where )ustification for continued unit operation has been given prior to replacement or requalifying equipment, a reference has been provided to the appropriate page in Subsection 3.3.
Qualification test records and analyses will be available on site.
Safety related equipment is required by the FSAR to function for either fifteen minutes, twenty-four hours, or one year.
The time period of fifteen minutes is tied to environmental requirements of C t I-B described in Table 2-2.
The time period of twenty-four a egory e
f Table 2-1 hours refers to environmental requirement of category l-A of a
e f
th first twenty-four hours while the time period of one year or e
refers to Category 1-A requirement for the entire duration o t e
accident.
3-2 SECTION 3.2 POST ACCIDENT EQUIPMENT QUALIFICATION
SUMMARY
ST.
LUCIE POST-ACCIDENT E UIPMENT 1
FICA ION
SUMMARY
MANUFACTURER
& MODEL POST-ACCIDENT FUNCTION TIME REQUIRED AVAILABLE QUALIFICATION DATA QUALIFICATION METHOD(S) cher
& Porter pany "1071BCXA-NS Special Modificatio Containment Pressure Signal Input to ESFAS Logic (SIAS,
- CSAS, CIS) s 15 Min.
Page 5-1 By Test cher
& Porter pany P1041BCXA-NS Pressurizer Pressure Signal 15 Min.
(high range)
Page 5-2 By Test Steam Generator Pressure Signal Input to ESFAS Logic (MSIS)
Pressurizer Pressure (low range)
Indication to Operator Required for Initiation of Hot Leg In]ection via SDC Suction Line 15 Min.
24 Hrs.
Page 5-2 Page 5"2 By Test By Test and FPL Analysis See section 3.3-1 cher
& Porter yany i2496QBBABDB-NS Pressurizer Level to Provide Operator arith Indication of Course of Accident and of its Severity 24 Hrs.
Page 5-3 By Test and FPL Analysis See section 3.3-2 cher
& Porter rpany i249 5KB-NS Steam Generator Level to Provide Operator with Indication of Course of Accident and its Severity 24 Hrs.
Page 5-4 By Test and FPL Analysis See section 3.3-3
ST. LUCI POST-ACCIDENT F. UIPMENT 1
FICATION
SUMMARY
MANUFhCTURER
& MODEL POST-ACCIDENT FUNCTION TIME REQUIRED AVAILABLE QUALIFICATION DATA QUALIFICATION METHOD(S)
~oro Corporation Pressurizer Pressure (3.ov range)
Indication to Operator Required for Initiation of Hot Leg Injection via SDC Suction Line 24 Hrs.
Page 5-5 By Test emount Incorporated Direct Indication of Containment Temperature for Initial Stage of ESFAS Logic {CIS) 15 Mins.
Page 5-6 By Test and Analysis by Manufacturer toreen Instrument tpany 857-3 Containment Radiation Signal Input to ESFAS Logic (CIS) 15 Mins.
None Manufacturers Instruction Manual See section 3.3<
itinghouse Electric
~pany
'rogen Recombiners Post-LOCA Hydrogen Removal from Containment Atmosphere 1 Yr.
Page 5-7 By Test and Analysis by Manufacturer tinghouse Electric beany ttainment Fan ilers Post-LOCA Containment Heat Removal and Prevention of at atmospheric stratification 1 Yr.
Page 5-8 By Test and Analysis by Manufacturer See section 3.3+
.cor Engineering beany
'600-515 H
Sampling Solenoid Isolation Vtlves to be Opened as Required to Allov the Operation of the Hydrogen Sampling System for the Purpose of Determining Amount of 1 Yr.
Page 5-9 By Test and Analysis by Manufacturer
ST.
LUCIH 1
FICATION
SUMMARY
MANUFACTURER
& MODEL POST-ACCIDENT FUNCTION TIME REQUIRED AVAILABLE QUALIFICATION DATA QUALIFICATION METHOD(S) ico 00X Position Indication of Containmen Isolation Valves Containment Purge Supply and Exhaust Isolation Valves 15 Mins.
None
'ee section 3.3-6 Chemical and Volume Control System Letdown Isolation Valves 15 Mins.
None See section 3.3-6
~1302 Position Indication of Containmen Isolation Valves Containment Radiation Sampling System Isolation Valves 15 Mins.
None See section 3.3-6
- omatic Svltch q any (ASCO)
>2C27R1
-HT-8300B61 Containment Isolation Valve Solenoid Operator Chemical and Volume Control System Letdovn Isolation Valves Containment Radiation Sampling System Valves 15 Mins.
15 Mins.
None None See section 3.3-7 See section 3.3-7 I..get Rock Company
+004 Operator for Containment Isolation Valve Reactor Coolant Pump Bleedoff Isolation Valve 15 Mins.
Page 5-10 By Test See section 3.3-8
ST.
LUCI T 1 POST-ACCIDENT E UIPMFN CATION
SUMMARY
MANUFACTURER 6
MODEL POST-ACCIDENT FUNCTION TIME REQUIRED AVAILABLE QUALIFICATION
.DATA QUALIFICATION METHOD(S)
~tomatic Valve iimpany 439 Containment Isolation Valve Solenoid Containment Purge Supply Exhaust Isolation Valve 15 Min.
None See section 3.3-9
.mitorque Corporatio Valve Motor Operator for Shutdown Cooling System Isolation Valves 1 Yr.
Page 5-11 By Test and FPL Analysis See section 3.3-10 Valve Motor Operator for Safety In)ection Tank Isolation Valves 15 Min.
Page 5-11 By Test
<<rro Mire and Cable erpany
,.rewall III Containment Electric Cable for Safety Related Devices 1 Yr.
(maximum)
Page 5-12 By Test and FPL Analysis See section 3.3-11'ychem Corporation
)amtrol Containment Electric Cable for Safety Related Devices 1 Yr.
(maximum)
Page 5-13 Page 5-1S By Test and Analysis See section 3.3-12 r
e Okonite Company onite/Okoprene Containment Electric Cable for Safety Related Devices 1 Yr.
(maximum)
Page 5-14 By Test and Analysis See section 3.3-13 eton Insulated Mire mpany Containment Electric Cable for Safety Related Devices 15 Min.
Page 5-15 By Test
/C Composite Cable
ST.
LU IT 1 POST-ACCIDENT E UIPMEN LIFICATION
SUMMARY
MANUPhCTURER 6 MODEL POST-ACCII)ENT FUNCTION TIME REQUIRED AVAILABLE QUALIFICATION DATA QUALIFICATION METHOD(S)
Q.f Ceneral htomic incorporated Containment Electrical Penetratio 1 Yr.
(Maximum)
Page 5-16 By Test and Analysis by Manufacturer See section 3.3-14 OHAZ Corporation Containment Electrical Penetration 1 Yr.
(Maximum)
Page 5-17 By Test and Analysis by Manufacturer See section 3.3 15 aychea Corporation chem MCSF Heat Shrink Splices 1 Yr.
(Maximum)
Page 5-18 By Test and FPL Analysis See section 3.3-16
3-8 3.3 Remarks and Justification For Continued Operation
- 3. 3-1 Fischer
& Porter Company Pressure Transmitter Model:
50EP1041BCXA-NS Pressurizer Pressure Transmitter (low range)
Tag No: PT~1103 Post-LOCA operation of the low range pressurizer pressure transmitter is required for a period of twenty-four hours.
The indication of this instrument informs the operator that the reactor coolant system pressure has dropped below 250 psig so that hot, leg injection via the shutdown cooling suction line can be initiated.
The available qualification docu-ments summarized on page 5-2 demonstrate that this transmitter has been tested to conditions in excess of those expected following a LOCA for the first seven hours.
In addition, the transmitter was monitored for an additional seventeen hours and remained functional.
While no written evidence of testing these devices for a chemical sprav environment is avail-
- able, documentation is available that states that they are coated with Amercoat 66, a coating tested successfully for three hours at post-LOCA conditions including a pH of 10.5.
Therefore,'he devices should be ade-quately protected to perform for the time required.
The above test results and an FPL engineering extrapolation of thermal effects demonstrates that the transmitt'er can operate for the required period.
Based on the above, the transmitter has an adequate margin to ensure proper post-LOCA operation.
3 ~ 3 2 Fischer
& Porter Company Level Transmitter Model:
13D2496QBBABDB-NS Pressurizer Level Transmitters Tag No:
LT-lllOX, - lllOY Post-LOCA operation of the pressurizer level transmitter is required for a period of twenty-four hours.
The indication of this instrument will provide the operator with information concerning the cause of the accident and its severity.
The available qualification documents summarized on page 5-3 dem-onstrate that this transmitter has been tested to conditions in excess of those expected following a LOCA for the first seven hours.
While no written evidence of testing these devices for a chemical spray environment is available, documentation is available that states that they are coated with Amercoat 66, a coating tested successfully for three hours at post-LOCA conditions including a
pH of 10.5.
Therefore, the devices should bc adequately protected to perform for the time required.
The above test results and an FPL engineering extrapolation of thermal effects demonstrates that the transmitter can operate for the required period.
Based on the above, the transmitter has an adequate margin to ensure proper post-LOCA operation.
3-9 3 ~ 3 3 Fischer 6 Porter Company Level Transmitter Model:
13D2495KB-NS Steam Generator Level Transmitters LT-9013A, B, C,
D LT-9023A, B, C, D
P t-a cident operation of the stea~ generator level transmitter is required ide for a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Indication from these instruments will prov e
th operator with information necessary to control the flow of auxiliary feedwater post-accident.
The available qualification documents summarize e o d
on page 5-'4 demonstrate that this transmitter has been tested to conditions in excess of those expected following a LOCA for the first 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />.
The transmitter was monitored for an additional 17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br /> and remained functional.
While no written evidence of testing these devices for a chemical spray environment is available, documentation is available that states that they are coated with Amercoat 66, a coating tested successfully for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> at post-LOCA conditions including a pH of 10.5.
Therefore, the devices should be adequately protected to perform for the time required.
The above test results and an FPL engineering extrapolation of thermal effects demonstrate that the transmitter can operate for the required period.
Based on the above, the transmitter has an adequate margin to ensure proper post-LOCA operation.
3.3-4 Victoreen Instrument Company Model:
857-3 Containment Radiation Sensors Tag Nos:
RE-26-3, 4, 5, 6
The Victoreen Instruction Manual delivered with the device states that the detector is designed to withstand pressures up to 44 psig, temperature between 30'F and 264'F and withstand 0.974 boric acid spray.
No testing for this device was committed to in Section 3.11 of the FSAk.
In view of the nominal environment the devices operate in and the fact that readout from these monitors is continuously availab)e in the control room to monitor status during normal operation, it can be reasonably assumed that thc device will perform its design function.
The purpose of this device is to provide a Containment Isolation Signal upon high radiation inside the containment.
In the event of conditions such as those in Category I-B, CIS would also be initiated by either High Containment Pressure or Safety In)ection Signal actuation and therefore operation of the radiation monitor is not required during these conditions.
Operation is however, necessary during fuel movement, when normal operating conditions prevail.
3-10 3.3-5 Containment Fan Cooler Push Button Station Tag No:
HVS - lA, B, C,
D The St. Lucie containment fan coolers have push button stations mounted nearby the equipment inside the containment.
These stations consist of two momentary push buttons one off and one on.
The switches are GE type CR2940 mounted in a standard watertinht NEMA IV box.
This assembly is then mounted inside a field fabricated box.
The outer field fabricated box is designed for outdoor application.
It contains a
gasketed full length hinged door, rain shield with drip gutter on top, Neilson stainless steel latches and screened vent hole in the bottom.
This design is comparable to a standard rainproof NEMA III design.
Conduit entry into the outer box is by watertight connections.
The cable entry to the control stations is by watertight terminators Grouse-Hinds CGB or OZ model GRE.
These push button stations are not required to operate post-LOCA.
However, should a short circuit occur across the stop push button the fan cooler would stop.
Such could only happen if the box filled with water.
In view of the above design of a NEMA IV water tight box contained within another box similar to NEMA III construction it is unlikely that a significant amount of water could enter the inner NEMA IV box and interfere with the fan cooler operation.
In order to insure proper post-LOCA operation these stations have been disconnected.
- 3. 3-6 NAMCO Limit Switches The NAMCO limit switches used on valves located inside the containment serve to provide valve position indication during normal operation and a verification of valve position following containment isolation.
They are not used for any associated control function.
Following containm nt isolation there are backup position indication methods available to the control room operator to verify that the containment boundary is maintained and isolation completed should the switches fail under post-accident conditions.
These methods are discussed in detail on the following pages in this subsection for the particular valves suppli.ed with these switches.
It is our opinion that these discussions provide justification for continued operation as continued service in a post-LOCA environment is not required for the safe shutdown of the unit.
However, in order to provide additional safety margin and to ensure valve position indication, replacement limit switches are being ordered.
These replacement switches are qualified for the post-LOCA environment as evidenced by the attached data sheet (written documentation to support the data will be delivered with the switches).
The switches will bc installed at the first available opportunity following the receipt of the switches and the necessary sealant material.
3-11 3.3-6a Table 7.5-4 of the Unit 1 FSAR (Accident and Incident Instrumentation) requires that position indication be provided on isolation valves functioning to verify automatic isolation valve closure.
This function requires only short term life of the device and since position indication is a separate circuit from the control circuit the, operation of these devices in no way compromises..or affects the ability of the subject isolation valves to operate as required.
Administrative controls insure that manually closed valves are kept in the locked close position.
Therefore, this discussion will be limited to those applications where position indication may be necessary to ascertain the proper operation of active isolation valves.
1)
CVCS Letdown Isolation (V-2515, 2516)
These are two fail closed pneumatic isolation valves in series upstream of the regenerative heat exchanger inside containment.
These are Safety Class 2,
seismic Class I valves which close on CIAS and SIAS, one valve receiving power and closure signals from Safety Train A and the other Train B.
Therefore it can be assumed that despite the potential for lack of indication, the valves are closed.
However, verification of containment integrity and isolation of the letdown line can be performed by the operator by checking the position indication of valve LCV-2110P, a seismic Class I, Safety Class 2 located outside containment designed to the same pressure and temperature conditions as those inside containment.
A visual check of various flow indications throughout the CVCS letdown line will allow the verification of closure of V2515 and V2516.
In addition the operator will manually actuate the control room local control switches for these valves upon indication of CIS.
- 2) Containment Purge Exhaust
& Supply Isolation (I-FCV-25-3, -4):
These valves are located within the containment on the containment purge supply and containment purge exhaust lines respectively.
Each valve is one of a set of three identical isolation valves in series, of which the other two valves of each set are located outside of the containment in the shield building annulus (I-FCV-25-3,2) and in the RAB (I-FCV-25-1,6) respectively.
The valves are fail closed seismic Class I, Safety Class 2,
and close on CIS.
It should be noted that a failure of the indication does not affect the ability of the va]ve to close.
Despite a potential for lack of position indication of the valves within the containment following a CIS, the remaining two valves in each line which are not located in hostile environments and their position indicators will show actual position.
Therefore, it is not necessary to know the, position of the isolation valve within thc containment since the position of the other two valves will be known and containment isolation will be verified.
In addition the operator will manually actuate the local control room controls for these valves upon indication of CIS.
3-l2
- 3) Containment Radiation Monitor Isolation Valves (I-FCU-26, -1, <<3, -5)
These valves are located within the containment on the particulate
- sample, iodine sample, and common return lines of the containment radiation monitoring system.
Each valve is one of a pair of identical isolation valves whose mate is located outside the containment.
The valves are failed close, Safety Class 2, seismic Class I pneumatic isolation valves which close on CIS, the valves within containment receiving power and closure signals rom S f t T ai 4 and the others from Safety Train B.
Therefore it can be aey r n.
tial for assumed for the valves within containment that despite the potent a
or lack of indication, the valves have closed.
The three valves located outside of containment (I-FCU-26,-2,4,6) do not see the extreme environmental conditions and their position indication can be considered correct.
Additional verification of isolation of the particulate sample and iodine sample lines can be made by manual closure of a one inch globe valve located outside of the containment air monitoring cabinet (outside of containment) on each line.
The piping on which these valves are located is designed for the same temperature and pressure as the containment isolation valves.
Indication of closure of the common return line isolation valves can be further verified by flow indication on the containment air monitoring cabinet.
In addition the operator will manually actuate the local control switches for these valves.
ST. LUCIE UNIT 1 Pape ~13 EQUIPHENT TAG NUiKFRS Re lacement Limit Switches for Air operated valves; V-2515 2516 I-FCV-25-3 4-I-FCV-26-1 3,
5 HAllUFACTURER NAMCO MODEL EA18011302 QUALIFICATION DOCUMENTATION Per telecon between FPL and NAMCO the replacement limit switches are qualified to the IEEE-323 LOCA profile.
A copy of the test report will be furnished with the switch purchase.
QUALIFICATION ElAfIRONlKNT psig REL.
HUl' to 5 Min 0to 62 0to 300 5 Min to 3 Hr 40 300 3 Hr to 5 Hr 40to 0
300 to 4
5 Hr to Hr 5M' to 40 140to 5 Hr to 6 Hr 40 300to 0
6 Hr to 10 Hr 25 250 F
10 Hr to 4 Day 25 4 Day to 30 Day 167 F
steam autoclave CllEil HAD First 24 hrs spray with H BO and Na S 0
. Buffered to pH of 10.5 w/NaOH 2xl0 R
8 QUALIFICATION h'K HODS Testin vas done in accordance with IEEE 323 -
curve iven above)
This vill re uire sealin thc limit switch conduit entrv oint with a ualified sealant material.
Such material is currently being investigated.
Mote:
The above results are a summary provided for reviewer convenience.
3-14 3 ~ 3 7
Automatic Switch Company (ASCO)
Solenoid Valves The ASCO solenoid valves are used on valve operators inside the containment
,to control the associated valve operator during normal operation and automatically close the valve following receipt of a containment isolation i
1 The are not used for any long-term post-LOCA function.
These valves have been analyzed in a generic Westinghouse letter (N-S-CE-755 response to comm en to commitment, for WCAP-7410-L) which demonstrated that all failure modes of the valve will result in safe operation.
Potential mo es o
failure identified for solenoid valves in this letter were loss of air supply, electrical failure in the solenoid, environmentally-caused degradation of materia s o 1
of construction, and plunger binding due to thermal expansion of the plunger to the core.
NRC has accepted this evaluation n
dated January 31, 1979.
The application of these solenoids are discussed in detail on the following pages in this subsection for the particular valve operator.
It is concluded that these discussions provide justification for continued operation as.long term service in a post-LOCA environment is not required for the sai'e shutdown of the unit.
However, in order to provide additional safety margin and to ensure required so eno v
1 id valve operation, we have ordered replacement solenoid valves.
o t-LOCA These replacement solenoid valves are qualified for the pos-environment as evidenced by the attached data sheet (written documentation to support the data will be delivered with the solenoid valves).
The valves will be installed at the first available opportunity following receipt of the valves and the necessary sealant material.
3+3-7a ASCO Solenoid Valve {8302C27Rl)
Thi d
1 f ASCO solenoid valve regulates the air supply to the Chemical s
mo e
o (V-2515
-2516).
an o
ume ontro y
d V 1 C
1 S stem letdown Ii>>e containment iso] atinn valves (-
d b ei'her Th f '1 losed valves that are to be automaticall>
close e t e'er cse are ai c
a CIS or SIAS (FSAR Table 6.2-16) in order to assure containment ntegr y.
The only safety related function that these valves must perform is closure upon receipt of CIS during very short post LOCA conditions.
A generic M
i l
1 tter described in thc previous section demonstrates that est ng iouse e
h 1
oid valves which regulate air supply to containment so a
on air operators, will close (its safe position) in a postulate acc cn environment for all postulated modes of failure.
Therefore it can reasonably be concluded that if the valve should fail it vill fail closed and isolate the containment as designed.
3-15
- 3. 3-7b DISCO Solenoid Valve (MP-HT-8300 B61)
This model of ASCO solenoid valve regulates the air supply to the containment ir onitoring system isolation valves (I-FCV-26-1, -3, -5).
These are a
m 6
fail closed valves that are automatically closed by a CIS (FSAR Table 6.2-)
)
in order to assure containment integrity.
A generic t4estinghouse letter described in a previous section demonstrates that the solenoid valves, which regulate air supply to containment isolation air operators, will close (its safe position) in all postulated modes of failure.
Therefore, it is concluded that even if the valve fails, it will isolate the containment as designed.
It should be noted that redundant isolation valves (I-FCV-26-2, 4,
- 6) are provided outside of the containment and will close upon receiving CIS.
Post-LOCA radiation sampling of the containment air is normally obtained by the containment air monitoring system.
If the operator solenoids of the isolation valves within the containment fail, they will fail in the closed position and this system will not be available for post-LOCA sampling.
The hydrogen sampling system is a backup system that has the capability to take grab samples of containment air that can be analyzed for radioactivity.
The hydrogen sampling system and its associates containment isolation valves
{see page 5-9) are long term post-LOCA qualified.
ST. LUCIE UNIT 1 Pape 3-16 EQUIPMENT TAG NUIKEBS Replacement Solenoid Valves for Air Onerated Valves U-2515'516, I-FCV-26-1, 3, 5
MMlUFACTUHER Automatic Switch Company (ASCO)
MODEL QUAL FICATION DOCUMENTATION 1)
ASCO Test Report AQS-21678/TR Q
Aging LOCA S
mu at on TIlE PRISMS psig 12 Days 12 Min.
0
'to 110 Hr 110 110to 0
Min.
0to 110 Hr 110 Hr 75 4
30 Days Days 15 10 TEN!'F REL.
HUl 268 140 to 346 346 346 to 140 140 to 346 346 320 250 200 100 100 100 100 100 100 100 100 CHE 3000 ppm Boron as Boric Acid in solution with 0.064 molar sodium thiosulfate buffered with NaOH to a pH of 10 at room temp.
(starting at 288 F on first transient continued for entire e
8 2xl0 R
QUALIFlCATION lM'llODS Thermal a in then radiation then wear a in then seismic.
then accident radtattcc then s ner tsttc test fnr rcsscrc tern rature, humidit, chemical s ra - all on same valves.
Note:
This test valid fox'ealed entrance to solenoid housing to prevent entry o umph ty or c enustry.
Sealant material is currently being investigated.
>>vd results are s summary provided for reviewer convenience
3-17
- 3. 3-8 Target Rock Company Model:
74/-004 Motor Operator for Reactor Coolant Pump Bleedoff Isolation Valve Tag No:
I-SE-Ol-l Post-LOCA operation of this containment isolation valve is required for a period of 15 minutes.
With the exception of explicit chemical environmen't test data, the qualification test documents summarized on page 5-10 completely envelope the category I-B environment.
The pH at the containment spray nozzles is designed to be between 8.5 and ll.
This pH serves to minimize caustic corrosion and in the short time required for I-B equipment to function, provides reasonable assurance that this valve will perform as designed.
Based on the above, the valve has an adequate margin to ensure proper post-LOCA operation.
3.3-9 Automatic Valve Corporation
{AVCO)
Model:
C-5439 Solenoid Valves The AVCO solenoid valves are used on valve operators inside the containment to control the associated valve operation during normal operation and automatically close the valve following receipt of a containment isolation signal.
They are not used for any long-tenn post-LOCA function.
An engineering evaluation of the components of these solenoid valves was performed by FPL which indicates these valves will perform their function.
This model of AVCO solenoid valve regulates the air supply to the containment purge supply and containment purge exhaust isolation valves.
Each valve within the containment (1-FCV-25-3, -4) is one of a set of three identical isolation valves in series which are fail closed Seismic Category I, Safety Class 2,
and automatically close upon receipt of a CIS.
The other two valves of each set are located in the shield building annulus (I-FCV-25-3,2) and outside of the containment (I-FCV-25-1, -6) respectively.
The only safety related function is that these valves must perform is closure upon receipt of CIS during very short term post-LOCA conditions.
An engineering evaluation was performed by FPL on the AVCO valves supplied for St. Lucie Unit 1.
This evaluation and analysis indicates that despite the lack of actual test data the construction of the valve and materia s
utilized therein are capable of meeting the category I-B requirements.
Items investigated include pressure and humidity resistance of the solenoid
- housing, temperature rating of the solenoid, and radiation resistance of the insulating material, seals, and coil.
However, in order to provide additional safety and margin and to ensure long term solenoid valve operation we will order replacement solenoid valves with equivalent qualification data as the ASCO valves described in section 3.3-7.
These valves will be installed at the first available opportunity following receipt of the valves and the necessary sealant material.
3.3-10 Limitorque Corporation Model:
SMB-1 Shutdown Cooling System Isolation Valves Tag No:
V-3651,
- 3652, 3680, 3681 Post-LOCA operation of these valves is required for a period of 1 year.
The valves are required to be opened following a LOCA to allow for hot-leg in)ection via the shutdown cooling suction line.
The available qualification documents summarized on page 5-11 demonstrate that these valves have been tested to conditions in excess of that expected following a LOCA for the first 30 days.
The above test results and an FPL engineering extrapolation of thermal effects demonstrates that the valves can operate for the required period.
Based on the above, the valve has an adequate margin to ensure proper post-LOCA operation.
3.3-11 Cerro Wire and Cable Company Containment Electric Cable, Firewall III Post-LOCA operation of this cable is required for a period of 1 year.
The available qualification documents summarized on page 5-12 demonstrate that this cable has been tested to conditions in excess of that expected following a LOCA for the first 30 days.
The above test results and an FPL engineering extrapolation of thermal effects demonstrates that the cable can operate for the required period.
Based on the above, the cable has an adequate margin to ensure proper post-LOCA operation.
3-19 3 ~ 3 12 Raychem Corporation Containment Electrical Cable, Flamtrol Post-LOCA operation of this cable is required for a period of 1 year.
The available qualification documents summarized on page 5-13 describe two tests designed to simulate the post-LOCA environment.
In addition to these tests, the qualification document summarized on page 5-18 for qualification of Raychem Corporation heat shrink splices is also applicable to Raychem Corporation cable.
Mhen the heat shrink splices were tested, Ray hem Flamtrol cable as well as other cable was a part of the test.
The cable therefore was subjected to the same environment as the heat sh ink c
rin splices and remained functional in conditions in excess of those expected during a LOCA for 30 days.
The above test results and an FPL engineering extrapolation of thermal effects demonstrates that this cable can operate for the required period.
Based on the above, the cable has an adequate margin to ensure proper post-LOCA operation.
3.3-13 The Okonite Company Okonite/Okoprene Cable Containment Electrical Cable Post-LOCA operation of this cable is required'or a period of 1 year.
The available qualification document summarized on page 5-14 demonstrates that the cable has been tested to conditions exceeding that expected following a LOCA for 100 days.
The above test results and an FPL engineering extrapolation of thermal effects demonstrates that the cable can operate for the required period.
Based on the above, the cable has an adequate margin to ensure proper post-LOCA operation.
3.3-14 Gulf General Atomic Incorporated Containment Flectrical Penetration Assemblies Post-LOCA operation of the containment electrical assemblies are require r
uired riod of 1
ear.
Mith the exception of explicit chemical environmental 5-16 demonstrate test data, the qualification test documents summarized on page 5-the penetrations can operate for the required period.
3-20 The St. Lucie penetrations were specified to withstand a post-LOCA environmental spray of 1660 pram Boric acid.
A Certificate of Comnliance from the manufacturer certifies that the penetrations were designed to withstand the cumulative environmental conuxtions as detined in Architect/Engineer's specification FL0-8770-307, Rev 7, paragraph 6.
Correspondance between the architect engineer and the manufacturer on January 24, 1972 and August 8, 1974 confirm that the penetrations will maintain their electrical and mechanical integrity when exposed to the boric acid spray.
The three materials of the penetrations that are exposed to the containment interior are 304 stainless
- steel, ceramic, and epoxy and are not generally susceptible to damage from the specified chemical spray.
In addi.tion, the penetrations are protected from direct impingement of the chemical spray by the wireways which connect the penetrations to the junction boxes inside containmcnt.
Therefore, it is concluded that the chemical spray inside containment will not adversely affect the penetrations mechanically or electronically.
Based on the above, the penetrations have an adequate margin to ensure proper post-LOCA operation.
3.3-15 Conax Corporation Containment Electrical Penetration Assemblies Post-LOCA operation of the containment electrical assemblies are required for a period of 1 year.
With the exception of explicit chemical environmental test data concerning pH levels, the qualification test documents summarized on page 5-17 demonstrate the penetrations can operate for the required period.
The materials of the penetrations that are exposed to the containment interior are 304 stainless
- steel, ceramic, and epoxy and are not generally susceptible to damage from the specified chemical spray.
In addition, the penetrations are protected from direct impingement of the chemical spray by the wireways which connect the penetrations to the junction boxes within the containment.
Therefore, it is concluded that the chemical spray within the containment will not adversely affect the penetrations mechanically or electronically.
Based on the above, the penetrations have an adequate margin to ensure proper post-LOCA operation.
3-21 3.3-16 Raychem Corporation Type:
Raychem MCSF Heat Shrink Splices Post-LOCA operation of the heat shrink splices is required for a period f 1 ear The available qualification document summarized on page 5-18 i
demonstrates that the splices have been tested to conditions exceed ng that expected following a LOCA for 30 days.
The above test results and an FPL engineering extrapolation of thermal effects demonstrates that the splices can operate for the required period.
Based on the above, the heat shrink splices have adequate margin to ensure porper post-LOCA operation.
3-22 4 ~
Conclusions The review of the written evidence of the qualification of electrical equipment required to function under accident conditions has been completed with the majority of documentation successfully located.
Generic problems with the qualification of NAMCO limit switches
{as developed from I&E Circular 78-08) and qualification for extended post-LOCA operation of ASCO solenoid valves (raised in I&E Bulletin 79-01A) have been identified.
An engineering evaluation was performed on each application of these devices to determine whether replacement or requalification was necessary, and whether the safe operation of the unit could be assured with the existing equipment.
The results of this val ation are contained in the appropriate subsection of Section 3 and d.
indicate that continued operation of St. Lucie Unit 1 is justifie In those places where the replacement option was chosen, it was done so in an effort to increase the margin of safety, and provide the ability for extended post-LOCA operation.
Therefore, it is our opinion that the proper documentation does exist for the majority electrical equipment used in St. Lucie Unit 1 to assure its proper functioning under post-LOCA conditions.
In the minor cases where the documentation has not been found, it was determined that the device would be replaced and that interim operation until replacement could be continued safely and without danger to the health and safety of the public.
5-0 SECTION 5
/VALIFICATION DATA TABLES
ST. LUCIE UNIT 1 Pare 5-1 EQUIPiKNT TAG NUI%ERS Containment Pressure Transmitters PT-07-2A, 2B, 2C, 2D HAHUFACTURER NiODEL Fischer
& Porter Co.
50EN1071BCXA-NS w/
Special Modifications"
{Sealed unit containing OSC/AMP 8805B241UOl)
QUAL FICATION DOCUNEHTATION 1
Fischer
& Porter Co. Test Re ort 2204-51-B-006
- 2) Fischer
& Porter Co. Engineering Report DPP2224-1, RPT 8004
- 3) Westinghouse WCAP 7410-L (containing FIRL report F-C2639)
- 4) Westinghouse letter NS-CE-1586 to NRC dated Oct. 28, 1977
- 5) Fischer
& Porter Co. letter to FPL dated May 29, 1979
Ameron letter to F&P dated Nov. 20, 1972 QUALIFIGATI0>
EIlVIRO s,'9' eT ua I
oc ~
i ual. Doc.
3 3
es s
0-1 Min 1 Mi to 1 Hr 1-3 Hr 3-6-1 2
Hr 6- -7 1
2 Hr 2 Hours PRMS psig TB%'F 0to 75 AMB to 320 75 45 5
227 320 293 35 281 60 (Rise in 5 sec.)
290 (82-293 in 5 sec.)
REL.
HUJ' 100 100 100 100 100 100X CHER Qual.
Doc.
7 Transmitter coating tested for 3 hrs.
under
.1X NaOH, 1X Sodium Thiosulfate by wt, 15,000ppm Boric Acid at pH 10.5 1.2 x10 R
8
( ual.
- Doc, 82) 2.16 x 10 R
8 (Qual.
Doc.
d3)
+Temperature from stcam tables based on saturated stcam at respective pressures.
QUALIFI<ATIO.1 >>>HOD< This is.an estimate of the test conditions and was no< part o,'he test report
- 1) Synergistic Test on Press, Temp, Humidity dia on est if r n s rumen t a S ner istic Test on Press Tem Humidit followed bv Seismic, then radiation - on same instrument.
This test was on Fischcr Porter transmitters using identical electronics.
(R f. Q~l. Doc. t5)
The above results are a auuunary provided for reviewer convenience.
~
~ ~
~
~
~ ~
I II ~
~
~
~
~
t
~
~
~
~
~
~
~
I ~
~
~
~
~
~
~
~
~
~
I ~
~ I I
~
II II II II
~
~
I I I
~
~
I
~ ~
o I
~
~
I I ~
I ~
~ I
~
~
\\
~
~
~
I
~
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II
~
~
~
~
~
~
I I ~
j
~
c
~ ~ III
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~
ST. LUCIE UNIT 1 Pape 5-3 B)VIPHEiVL'ressurizer Level Transmit ters TAG NVHBFRS LT-1110 X, Y YiODEL gglUFACTUHER Fischer
& Por ter Company 13D2496QBBABDB-NS w/"Special Modifications" Sealed unit containing OSC AMPlI805B241U01)
QUALIFICATIO>> DOCUiiENTATIOlf
- 1) Fischer
& Porter Co.
Test Report 2204-51-B-006
- 2) Fischer
& Porter Co. Engineering Report DPt?2224-1, RPTv'004
- 4) Westinghouse letter NS-CE-1586 to NRC dated Oct. 28, 1977 Fischcr
& Porter Co.
r o FP da Mnv 97 6)
FPL Telecon Memorandum by L.R. Casella dated June 27, 1979 7
Ameron letter to F&P dated Nov.
20 1972
E? JVIRO?! <iFNT Qua
~ Doc.
1 ua
~ Doc.
tests PRMS psig 0-1 Min 0to 75 1 Min to 1 Hr 1-3 45 3-62 Hr 6- -7 2
Hr 35 2 Hours 60 (Rise in 5 sec. )
TEl iJ'F REL.
HVl' AMB to 320 100 320 100 293 100 227 281 100 100 290 (82-293 in 5 sec. )
100X CHF.i.
Qual.
Doc. P7 Transmitter coating tested for 3 hrs.
under
. 1X NaOH, 1X Sodium Thiosulfate by wt.', 15,000 ppm Boric Acid at pH 10.5 1.2 x 10 R
8 (Qual.
Doc.
d2) 2 ~ 16 x 10 R
8 (Qual.
Doc.
P3)
- Temperature from steam tables based on saturated stcam at respective pressures.
This is an estimate of the test conditions and was not part of the test report.
- 1) Synergistic Test on Press, Temp, Humidity
- 2) Radiation Test on different instrument than 1)
- 3) Synergistic Test on Press, Temp, Humidity, followed by Seismic, then radiation - on same instrument.
This test was on Fischcr Porter transmitters usin identical electronics.
(R r.Qual ~
D c. f5) nrnv4 Rod for reviewer convenience.
ST. LUCIE UNIT 1 Pope 5-4 EQUIPMENT TAG NUMBERS HAIAJFACTUi<ER MODEL Steam Generator Level Transmitters LT-9013A, B, C, D; LT-9023A, B, C,
D Fischer
& Porter Company 13D2495KB-NS w/"Special Modifications" (Sealed unit containing OSC/AMP //805B241U01)
QUALIFICA'nON DOCU:mNTATION
- 1) Fischer
& Porter Co. Test Re ort 2204-51-B-6 QUALIFIC
- 2) Fischer
& Porter Co.
En ineerin Re ort DP82224-1 R t.
il 04
- 4) Westinghouse WCAP 7410-L (containing PIRL Report F-C2639) 5 Westinghouse Letter NS-CE-l586 to NRC dated Oct. 28, 1977
- 6) Fischer
& Porter Co. letter to FPL dated May 29, 1979
~I
..incr.r
- 8) Ameron le er to F&P dated Nov. 20 I
72 ual.
Doc 0- 1 Min 1 Min IQ HR 3-6 2 HR
~l 2
HR 2 Hours PRISMS psig TEiQ' R}:L. HUlL 0to 75 AMB to 320 75 45 5
320 293 227 35 281 60 psig (Rise in 5 sec.)
290'F (82-292'F in 5 sec.)
100 100 100 100 100 100X OH' Qual.
Doc.
8 Transmitter coating tested for 3 hrs.
under.IX NaOH, 1X Sodium Thiosulfate by wt, 15,000 ppm Boric Acid at pH 10.5 1.2 x 10 R
8 (Qual.
Doc. 2) 2.16 x 10 R
8 (Qual. Doc. 4)
- Saturation temperature from steam tables based on chamber pressure.
This QUpi IiI( ATIOH 7+7HODS is an est imate of test condit ions and was not part of test result.
I S ner istic 3)
S nergistic test on press.,
temp., humidit
- followed b
'eismic nn F&P 50EP 50E and 1082496 transmitters The 1082496 whicli uses electronics identical to the l3D2495 (Ref. Qual.
Doc. t6) was then radiation tested.
'Q~ ~ ~ ~
~o above results are s summary provided for reviewer conveniences
ST. LUCIE UNIT 1 Pap~e +
EQUIPHENT Pressurizer Pressure Transmitter Low Ran e
TAG NUHBFRS PT-1104 MANUFACTURER Foxboro Corporation YiODEL Ell-GM QUAL FICATIOll DOCUMENTATION 1
Foxboro Test Re ort No. T3-1013 2
Foxboro Test Re ort No. T3-1068
- 3) Combustion En ineerin, letter F-CE-6789 to FPL dated June 12, 1979 QUALIFICATION EWfIRO>>'!PNT ual.
Doc.
0'1 FIRL F-C 63 TI11E PRISMS psig TEi8'F REL.
HN'-35 Sec.
0to 60 75to 300 100 35-45 Sec.
60to 40 300to 260 100 45-88 Sec.
40to 60 260to 290 100 88 sec to 2 Hrs 60 300 100 2 Hrs 1 to 2 Y Hrs 60to 20 300 100 22 Hrs to 24 Hrs 20 244 100 CllBl 1.5X by weight Boric Acid, pH ad)usted to 10.0 for first 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, pH of 9.2 for remaining time 7.6 x 10 R (Qual.
Doc.
d2) 7 See page 5-5a for supplementary report QUALIFICATIK: HETllODS
- 1) Synergistic test for temp, humidity, press, chem spray and another synergistic test for press, temp, humidity (2 different
- 2) Radiation test on transmitter previously sub)ected to test in Qual.
Doc. tl Note:
The above results are a auaanary provided for revieMer convenience.
ST.
LUCXE UNIT 1 Pape 5-5a EI)VIPi4ENT TAG NUI%ERS HAIIUFACTUHER Pressurizer Pressure Transmitter (Low Range)
PT-1 104 Foxboro Corporation N)DEL Ell-GM QUALIFICATION DOCUMENTATION QUALIFICATION EIIVIRONIIEhT Qual.
Doc. Pl u
emen ar e or TIIPE PZESS psig TB~Q
'F REL.
HUl'-15 Min 0to 58 75
~ to 308 100 15 Min to 2 Hrs 58 308 100 2 1 2
Hrs 58to 21 308to 266 100 4- - 23 1
2 Hr 21 266 100 23-86 0
'47 5 Not Recorded CIIF'I
- 1. 5X by weight Boric Acid, pH ad5 usted to 10. 0 for first 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, pH of 9.2 for remaining time 7 ~ 6 x 10 R (Qual.
Doc.
- 1) Synergistic test for temp, humidity, press, chem s rav and another synergistic test for press, temp, humidity (2 different ins trumen ts)
- 2) Radiation test on transmit ter reviousl sub ected tn test fn Qual.
Doc .
t 1
ST. LUCIE UNIT 1 Pape 5-6 EQUIPi4EHT TAG NUHBFRS l4AlfUFACTURER YiODEL Containment Temperature Elements TE-07-3A, B
Rosemount, Inc.
88-52-17 and 88-120-18 QUAL FICATIOH DOC(MEHTATIOH 1)
Rosemount Report
- 2767, Rev.
B 2)
Rosemount Similarity Report 67912A QUALIFICATIOH El@IROV!1FNT Qu>>
Doc 1
HUJ 1.
0 to 7 min.
Ambient to 125 Ambient
~ to 340'F 7 min.
to 17 min.
125 340 17 min.
to 8 hrs.
70 303 8 hrs.
to 50 hrs.
20 228 50 hrs.
to 51 hrs.
Ambient Ambient Steam Chamber CHE.'1 No Boric Acid 15,000
- ppm, NaOH 0.1X by vt pH 11 8 77'F 2 x 10 Rad 8
QVALTFICATIOH METHODS Qual.
Doc.
- 1) Radiation test then seismic then s ne s
Qual.
Doc. 2) Similarit re ort com grin 88-51-50 to 88-52-18 and 88-120-17 and stating applicability of re ort Note:
The above results are s summary provided for reviever convenience.
ST.
LUCXF. VHXT 1 d dd(a ~
Ei/UX)'i)""'T TACi )lU:iPsRltS gydrogen Recombiner H dr en Recombiners lA-1B Hhi¹ACTU))!R Westinghouse Electric Com an NODL'1 QUALIFJGATI0!) DOCU: s),"!lTATIOi) 6 and 7.
+2 NRC memorandum f dated Jan.
31, 1979 QUAL IFICATIO'.! E)PfIPO!!!').";ts'T Qual. Doc.
1 Supplements 2,
3 and 4
upp
~
3 0 to 4 hr.
4 hr. to 24 hr.
1 to 22 Days Supp.
f3 Supp'3 Supp.
II3 8}:!.. )IU:;
85 psia note 1
35 psia note 1
Steam Chamber 20 psia 155oF Suppf2' Supp.
42 C)j'
)UiD ¹2 69 psia 4 hr.
Spray 2500 pram boric acid and NaOH pH of 10.
then 35 psia for 20 hr. Also a 10 day Sodium Tetraborate spray
~t du lament l>4 2 x 10 Rads
+ 6 LOCA cycles note 1:
Atmospheric temperatures are not explicitlv given in the test results but T
Appfed.,/hatkptsMere run at temperatures much in excess of the maximum temperature predicted for post-LOCA.
i)
Various tests were rf redoimneuludin radiation to spray tests.
2)
NRC has accepted this report for seismic and environmental qual ifica tions.
Note:
Vhc above results arc a summary provided for rcvieMcr convcnicncc.
For complctc details, ecc thc above rcfcrcnccd repnrt document(s)
~
ST. LUCIE UNIT l Pare 5-8 B)VIPlKll'1'ontainment Fan Coolers TAG NUIHFRS HVS-l A s
> s C ~
D
~pUFACTURER Westinghouse Electric Company NODEL QUAL FICATION DOCUMENTATION l
MCAP-7829 si nificant a
e atta d
2 NRC Acce tance:
I&E re ort 50-335 76-10 3)
MCAP 9003 QUALIFICATIO:lZtNIROll!KIT (See following page for sample test)
TIIE Uarious tests vere run.
PRMS See attached sheet for a general summary.
Mestinghouse TBG'onclusion states that assembly is good for long term LOCA vith heat exchangers.
Rk:L.
HU.'L St. Lucie Unit l has heat exchangers.
CHE." t QUALIFICATION! lM'HODS Tests and anal sis.
ual.
Doc. 2:
IE Re ort 0-3 5
7 -1 contains NRC acce tancc of the WCAP for PSL-l.
Sote:
The above results are a summary provided for reviewer convenience.
ST. LUCIE UNIT 1 Pope 5-Sa EQUIPi&IIT Containment Fan Coolers TAC NUI&FRS HSV l-A,B, C, D
HAQlFACTURER Mestinghouse Electric Company YODEL QUALIFICATION DOCUhKNTATIOIJ tWALIFICrTION VIVXROV~Zr,T u
Test No.
3 Doc.
3 Te t No 7
TIIE 1
HR 30 12 ll 1
2 HR HR 45 MIN 1
1 4
HRS 3
15 HR MIN 2
2 4
1 1
2 2
HRS HRS HRS 10 HRS 10 HRS PRISMS psig 0
to 60 60 to 80 80 80 0
to 80 80 60 Peak to 80 5
<5 TEJ IPoF'6to 266 266to 310 310 320 77to 302 Peak 311 290 to 302 302 230 to 230 to 230 185 185
'to 230 221 REL.
HU)I.
X 100 100 100 100 100 100 100 100 100 100 100 100 100 CHE See note bel oM Start spray 2HR45mi into test,co>>tinue to end (acid)
Start spray 15 min into test, continue to end (alkaline)
QJAL11'ICATIO)I HETIIODS 9 test Mere erformed.
Tes No.
and w
cr r
i ion as formal verification runs.
Fan cnn ere M r c n cd re resent 7
ears service before s
er istic test for
- ressurc, temperature, humidit and chemical s ra Note: Chemistry not specified other than acid or alkaline.
The above results are a summary provided for reviewer convenience.
TASLK 1 COMPARISON OF PR'EVIOUS TESTS AND GUIOK REOUIRKMENTS MET IN PRKStNT TESTS 1988 Tests ysCrsP 9003 IKEE Golds 334 Requirements PRKPARATION 197071 Tests tyCAP 782~9 Aged 38 hove at t70'C Applied iiirorrrial mteiiaiiieal stress Vvd sure or e issx Tested stsrvr vivftr wsf+f
'2300vott The msrastic 'Epoxy 15 VPM sl rss 5885 I t~
5 r 1 t w'nd'+9 motor Laiarrinfh b Sriiig Seal Heat treat&. ant fi:ct on bearings frcrrton:~I HX orsfes Ride mounted HX)
Cvsfonr made chtctr vobt Ltad sptKes I55 C i>svration in sttsm 19 starts in steam Kvccstd fo 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> sl 80 osiy Exposed for 150 rxxrrs st 80 to 5 psry Used 320'F maximum ambient Aoohed ac d and afaariw sprays Chvcatd vibration snd looseness Into<<:ttd v'tvsrfv Apot'td normal vortsgt onty Simulate 40 year d!rFsdstion tdethanKSI Slretl aging requirtrf Simulate effects expected to accrvo In use USn nvitnal manvlOCIVrin ioteSSeS TYPE TKST h'IOTOR FEATURES Ovalify to IEEE 27S Same efectiical sfiess Fv>> site r ofor pitlerrtd Incn ooiste essential comooner ts lnenrpqiate elfenlial COmpunenta Inc'rrpoiste essential compo"tnls Incniporafe essential components IrKOrpprsfe efrenfisl eomoontnta Incfvde auxiliory equlpmtnt Oemonsfrste eqv'omenl oerlinent to application Otmonsti ~ te tqvipmtnt ctrtinent to application ENVIRONhlKNTALKXPOSUR'E 105 prig svgg. sled
~ approximate 10 second rist time
'slvialtd sltsm (324'F al 80 osig)
Use mixed spray. pH ~ 8.8 POST EXPOSURE EXAMINATION Assess ability to continue to operate Assess abilily to continue to ootratt Apply 2/3 12x rating a 1000 vOfls)
COhIPONENT TKS15 Ay.d insulation 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> at 200'C Vibroterf I hour st l.5 y Irrsdioltd ail yitsse 2 x 10 rsds TeSltd Stater under water Ssmt 2300voft. qvahfied rnsufstron used No change in stress 58'8 5 Rome f500 hp litt)
Twp winding rnqlqr Ssmt btsr >9 stol on all motors No change in bea ings Ve>>ical HX pfafes )HX undtr motor)
COmn erC al Cheefr valve VSed Plant cables and splices used 200 C fnsvfsf:o<< in sfeanr 8 chemistry Over 100 stsM in stet'll Five 4 hr transients )~ 10 seconds to contsinmtnt design pressure)
+7 days 0.2P 324'F msx., no HX test st 80 osig.
Used mixed sorsy. pH 9.5
~ 'IO.
Chtcted vibration, loosentn, and coastdovm time Comofeted visual Inspection Applied 1300 volts - destructive tests planned later Co ducted no str orated bearing tests
+sdt no stpsrslt lnsvra'lion ftsfs Tesltd no rr sft<<sfs separately lncfv&h no sr ramie tests Oemonstrsfs undtr design basis conditions Test modtls In va'ious SequtnCta and con'binolions tif radiation and tnv'iionmenl Msteiiafs tc be evaluated SKISh'lfC QUALIFICATION Ovslity per IEtE.344 Completed 20 month btsriny ltst with steam and chem'stm usiny rrradisftd g'esse Compfetrd txtensive tests lo meet lht Guide renuiir'enfs Exposed sir materials to radiation snd steam Ovalllied by tests snd ans'lysis lo lEEK 344
ST. LUCD>> UHJ.T 1
~ ~
)-'ql)IPj'!f llT TAG ))U 'I,!:.}(5
~SSamyling Solenoid laolation velvet I FSE 27 lr 2d 3
4d 5r 6r 7
))AIAIFACTV!<I:R V>>cor Engineering Corporation
)!OD} L V52600-515 qVALl)'JCATJ 0:I DOCU:'!r;::"A'Zro;')
Valcor re rt " ualification Test Re rt for IEEE Class IE Solenoid Valve P/N V52600-515 'alve T
e I" QUAl 1F'1 CAT) 0."! ):!.'VJRA'i!!! LPP ln cc1 ent 1mu at1on 172 hrs.
0 to 3 hrs. 3hr.to 5 br. to 6 hr.to 5 hr.
6 hr.
9 hr.
9 hr.
12 hr.
12 hr.
16 hr.
J6hr.
4 Days 4 Days 31 Days
) l'L;AS 113 PS1g J13psi Atmos.
113 to Atcfas 113 psig psig 95 PSig 69 P81g 28 PS1g 13 PS1g
))):Iaa
)IU.
31BOF 3464F 464F t 10OF to 3464F 1004F 3464F 3354F 315 F 272 F
245 F Steam A'osphere IiAB 1720-2200 PPN Boric Acid and 0.064 molar Na2S20, adjust.
ith NaOH to roduce a
I 2.x 10 rads
~ ~
QUA).I)'J CA')'JO:1
!i!;.'HO:".'TYPE TEST" Valve thermally aged to equfvalcnt 40 yr. life, then life c cled 7500 tfme~efrrcdiatcd, seismically tested and then 31 day LOCA Test.
Valcor calculations in the'eport state that the valve should last 6 '
years post LOCA due to the maigin in thc tested tcmperaturc over the required Category 1A LOCA environment.
Note:
Thc above results ore o summary provided for rcvic,vcr convenience.
>or complete details, sec the above rc.fcrcnccd rcport document.(s).
ST. LUCIE UNIT 1 Pape 5 10 EQUIPilEilT TAG NUMJ3ERS RCP Bleed Off Isolation Valve I-SE-Ol-l HhllUFACTUHER Tar et Rock Com any YiODEL
'4Q-004 QUALIFICATION DOCUNEhTATION 1
Telex from Tar et Rock to Ebasco Services Referencing Telecon of 5/24/79
- 2) Tar et Rock Co.
Re ort No.
1500 (containing Isomedix letter of Irradiation Certification dated May 20, 1974 and East-Vest Technology Corp. Test Report 798-4.)
QUALIFICATION EfiVIRON!lENT ln ccrc ent emu at on PP~S 240 Hr
~10 se 0
70 psig 3 Hrs 70 psi 2 Hrs
'410 se Reduc d 0 to psi
&S 3 Hrs 70 ps 4
Hrs 30 Days ps!a TEJ9'50
+
+300'F 10' 340'F Reduce to ANB
+300'F 340 F 250'F
+200'F REL.
HU CllE!l 55 + 5 100%
No 100%
Not Avail.
100%
No 100%
100%
Not Avail.
5 x 10 RAD/Hr for total integrated dose of 3.3 x 10 RAD (Qual'oc.
3)
QUALIFICATION HtrHODS Radiation test (Qual.
Doc.
2)
~ then aging and synergistic accident simulation (Press
~ Temp, Humidity)
All tests on same valve (Model 72V Type, 1") Mhich is similar to 74Q-004 and test is applicable (Ref. Qual.
Doc. fl) nrn&Anh fnr revit&'r conveniences
ST. LUCIE UNIT 1 I'af,e 5-11 EQUIPHEdlT TAG NJi&FBS HA1AJFACTUBER Valve Motor 0 erators V 3651 52 V3614 24 34 44; V3480 81 Limitorque Cor oration N4ODEL SMB-1 QUALIFICAT1 ON DOCU4&HTA'I'ION 1)
Franklin Institute Re ort F-C3441 2)
Limitor ue letter to Combustion En ineerin dated Mav 1, 1974 33 Nestinghousc letter NS-CR 692 to NRC discussing tests on Lame,torque operators 4)
Limitor ue Test Re ort 600198 QUALIFIGATIOll EPf IRON!4E!lT Q<<l ~
0 to 3
hr.
3 hr. t 6 hr.
6 hr to 9 hr.
9hr to 12 hr.
12 hr to 13 hrs t 13 hrs.
4 days 4 days to 30 days PRVMS 05 psig Rise in 19 sec.)
105 psi to 0si.
1)5 77 psig 77 psig 15 psig 10 psig 19 psip REL.
HU4'40'F (Rise in
<3 min.
340'F to 162'F 340'F Rise in
< 4 min Steam 100%
320'F 320'F to 252'F 251'F 200'F 1.5% by weight boric acid in water prepared by dissolving 7 lbs t grade boric acid in 55 gal (460 lbs) demineralized water
.NaOH used to titrate to H of 7.67.
2 x 10 Rads 8
chnical QUALIFICATIOdl NEFHODS Qual.
Doc. Pl Simultaneous Pressure tern eraturc and Steam Test done on Qual.
Doc.
03 A lies chemical s ra of Limitor uc Test Rc ort 600198 to FIRL F-C 3441.
Qual.
Doc. f4 Simultaneous test for pressure, temperature, humidity, chemical spray.
Franklin Institute Research Laboratories Final Report F-C2232-01 The above results are a summary provided for reviewer convenience.
STs LUCIE UNIT 1 E<)UIPi II iI'i'ontainment Electric Cable V/30 IIUt~l)I'.BS IWIUF/ic'I'UII!'.II Cerro Wire and Cable Co.
V40DEL Firewall III QUAL FTCJ'T) 0:l DOCUllE,"il'I'I<'"10N TEST 1
~1Franklin lnstitct Research Laboratories Final Re ort F C3-798 2)
Cerro letter to Ebasco dated Ju~~
1973 FIRL Report'-C-3402 qUALIF1CA " 'i". ""'~
A in 7 Days l'3
~ s
~
J n
.asa3 Oto 3
hr.
Doc.
1 3 hr. to 5hr. to 5 hr.
8 hr.
8 br. to llhr.
llhr. to 15hr. to 15 hr.
4 Days 4 Days to 30 Days psia 127 Note:
127 Note:1 ill Note:1 83 Note:1 39 Note:1 14.7 Note:
1 1210C 346 F rise i 2 mine.
3460F to 0
346'F.
risq i 3 mins.
335'F 3150F 2660F 2120F RI;is. IIU" Steam Autoclave Roric Acid 3000 ppm Boron PH 9-11 at 77 F 2 x 10 Rads Note 1:
The pressures arc not provided in the test report.
The valves given have QUA! 3!'1 CA~'j(3,"..'.I;; l:.0')!been takeR' rom steam tables for saturated condi t ions and arc a
approximation of what the cable experienced in the steam autoclave.
Cable thermal 1 a e~d~xo~d~o~a~d'~a~~~g~~~~e 4
IOCR environment.
Ccscri tion oE FC3402 ~~n~i~36a Note:
Thc above results arc a summary provided for rcv'ic Mar convenience.
For complc te. details, scc thc above referenced rcport document(s).
ST. LUCIE Ul<IT 1
~I ~4 elk F<)UIPi II'IIT Containment Elec trical Cable TAG IIVIIII!'.IIS HAiR1F/iCTUIIIll Cerro Mire & Cable Co.
ViOD1:L Firewall III QUAFF'ICAT)0!I DDCUNEiITliTIO'l QUALIP)CAT) O'.I EIIV3'"nO!I!IF::".'7 Qual.
Doc ~
2 0 to 1 min.
1 min. to 5 hr.
5 hr. to 6 hr.
6 hr. to 48 hr.
48 hr. to 49 hr.
49 hr. to 336 hr.
Pil!~~'5 psig TR!
11'F 0
104 340 104 to 58 340 to 305 58 to 20 305 to 260 20 260 20 to 2 ~ 5 260 to 220 2 '
220 BI'.I.. IIV.
Steam Atmosphere CIII '4 2000 ppm boric acid ph 9-10 HAI) 1 x 10
. Rads QUAI.YV1 CATI0! !.I1','~iIODS Radiation exposure - Then cable was sub'ected to steam
- rcssurc, temperature, and chemical environment simultancousl Note:
Vhc above results arc n aummary provided for rcvicvcr convcnicncc.
tie above refit'canc eel rwnnrt Ant sidiint (e%
ST. LUCIE UNIT 1 Pais(
5-13 E<)UZPilEilT TAG NUi63ERS MAlAJFAGTURER YiODEL Containment Electrical Cable Raychem Corporation Flamtrol QUALIFICATION DOCUHEHTATZOil 1)
Raychem Test Report EM /l517A 2)
Raychem Test Report EM 81010 QUALZFZCATI0!l EllVIROii!K!'T ua oc.
TZ>.n'4 hr.
ua oc.
- 89. 3 hr 4 hr.
20 hr.
376 hr.
200 hr 168 hr PRMS TE!0'EL.
HUl'.
68 75 psig Note:
1 360'F Note:
1 Steam Auto Clave 25'C
~170'C
~ 129'C
~85 C
w 85'50'C HAD Boric Acid P-H 7-8 Pre-aged 7 Day at 121 C 10 Rod
.56 MR/
.25 MR/
.25 MR/
.25 MR/
2 x 10 Rad QUALZFICATIOil1M'llODS 1)
Simultaneous Pressure
. temperature, humidity, chemi cal spray done on Pre-aged and irradiated samples.
2)
Temperature and radiation done simultaneously Note 1
Pressure and Temperature Values Taken from Sequence of Table 4, Ranging from 150 Min. to 24 Hrs., in Raychem Test Report Em f5
'rh~ above results are a summary provided for revicver convenience.
ST.
LUCRE UNIT 1 Pape 5-13 Ei)UXPJ 1ENT TAG NUMBERS WiIAJF/sCTU HER MODEL Containment Electrical Cable Raychem Corporation Flamtrol QUAL FIGATION DOCUMENTATION 1)
Raychem Test Report EM /l517A 2)
Raychem Test Report EM 81010 QUALIFICATI0" L'PfIRON'~'lT
~ua oc.
ua oc.
24 hr.
89 ~ 3 hr 4 hr.
20 hr.
376 hr.
200 hr. 168 hr PR MS 68 - 75 psig Note:
1 REL.
HUl'HF
'1
'4 360'F Note:
1 Steam Auto Clave Boric Acid P-H 7-8 25'C
~170'C
'4 129'C 85'C
~ 85'50'C hAD Pre-aged 7 Day at 121'C 10 Rad
~ 56 MR/
~ 25 MR/
~ 25 MR/
HR MR/.25 MR HR HR Total osl' None QUALIFICATI0)1 JM')lODS 2 x 10 Rad I)
Simultaneous
- Pressure, temperature, humidity, chemical spray done on Pre-aged and irradiated samples.
2)
Temperature and radiation done simultaneously Note 1
Pressure and Temperature Values Taken from Sequence of Table 4, Ranging from 150 Min. to 24 Hrs., in Raychcm Test Rcport Em f51 u4AoA fat rovieMer convenience
e
~
~
~
~. a
~
ST. LUCIE UNIT 1 Pape. 5-14 F)UIPHENT TAG NUMBERS Containment Electtical Cables NltAJFACTURER The Okoni te Company Y>ODEL Okonite/Okoprene QUAL FICATION DOCUMEliTATION The Okonite Co.
QUALIFICATION Eln IRON~1ENT 168 Hrs 10 3 Hr 40 Sec 20m Min Da s N/A 35 Hours 100 Days PRESS psig 0
to 80 80 80 to 16 16 2 Transients to 104 1 ea. trans-ient. to 75,15,25 0 with 1-10 hr transient to 20 TEiP 4F REL. HUl'50 AMB 324 to 324 to 324 252 100 100 100 252 100 2 transients to
)45~1 ea ag-100 212 with 1-10 hr transient to 258 100 CHB) 10,000 ppm Boric Acid Buffered with NaOH to a-pH of 10. 5 2 x 10 R
(3 x 10 MR/Hr) 8 5
QUALIFICATIOllh1ETHODS Heat aging, followed by radiation, then s ergistic test for pressure, temperature, humidity and chemical spray.
Cables carried full rated voltage and current during testing.
Note:
The above results are a summary provided for reviewer convenience.
oo~ >1~ abOYo reforonr oh ronnry g~oe~
ST. LUCIE UNIT 1 e EJ)pV Q ] I)
EQUIP))E )T TAG ))U '))3EBS Containment Electrical Cable pp))UFACTU)))'H Boston Insulated Wire Company
)'tODLL 13/C Composi te Cable QUAL'ICh'VIOLS) DOCUl)E)JTATIOil 1)
BIW Test 9298 2)
BIW Test 9299 3
BIW En ineeiin Comments 33388-EP QUALIFIChTI 0:! E) 1'1i: 0!i!'!!'.".lT Qual.
Doc.
81 and II2 0 to 5 hr.
5 to 11 hr.
11 to 24 hr.
24 to 36 hr.
105 psig 75 psig 25 psig 25 psig Tii)) '
~
RR)ee
)IU 340'F 315'F (Test929 325'F (Test 929
)265oF
)
265 F Steam Autoclave C)I)';)
HAD None AS x 10 Rad.
Chemical Spray 2000 ppm Boric Acid PH 9-10 with NaOH starting at hr ll QUh).IYIChYI0': h); i'i)ODfe
- Pressure, tern eratu~re ~m~~~hc)aic~p~a'gm~ta~t~
after radiation exposure.
Test 9298 was on silicone insulated cables.
Test 9299 was on XLPE insulated cables.
Ref. 3, above,
~ete noble eonstruetlnn nnd n
lfenbflft of tests.
Mote:
The above results are a summary provided for reviewer conven5cncc
~
tete 1
~fs A
f ~%le ac o thc above'eferenced ronort document <s)
~
ST. I.UCIE UIJIT 1 lap'c a Lo B)IJIPi II'.iJT TAG I)UHi)!'.HS Containment Electrical Penetration Assembl A lg B l~
B O' 5~
B 8t B
9~
B 10' 1'
4~
C 5g C 7~
C10 D4~ D7~ DS'Elp E3 E7~ E10 tRISFACTUIIEB Gulf General Atomic Incor orated RODE)a Low voltage, power, contol, and instrumentation penetrations and high voltage penetrations.
QUALlF'JCAT10:,'OCU:'!Ei)TA) 1'OH
-115-8 d
- 81 2
Intelcom Rad. Tech.
7 15 74 renort and Gul Atomic letter 6/28/74 transmitting Gulf 6/26/74 test.
3)
General Atomic August 1974 "Design Report Environnental Conditioi for St. Lucie 1 Secondary Electric Penetration Assemblies" QUALlF'AT1O'I
)'.!
)VITRO"')")IT Test 1
ual. Doc.
1 Qual Doc.
2 0 to 15 min.
15 min. to 24 hr.
Step 1
0 to 2 hr.
2 hr. to 26 hr.
psig 70 50
~310~F 290 F 264OF 2400F R)'lL. )IU!';
Steam Autoclave Cll);'I None
)IAD None Irradiated to 5 x 10 Rads.
QUA).I)'1( AT10i) I',.':I'jj(li)
Tests and Analysis Qual.
Doc.
1 Tests vere performed on onc of each type penetration tLV, pcarcr, control, instrument, HV Pover).Qual Doc. 2 Test Gulf.~
certifies all materials used can vithstand LOCA environment.
Qual.
Doc.
3 Provides a detailed analysis in addition to the above test of each of the components and materials used in thc Penetration.
Thc results of this analysis indicate that (contknuccO IIotc:
11>c above results nrc. n summary yroviancl ror rcvikvcr cnnvcnicncc.
For corn)'lute details, scc thc above rc.fcrcnccd rcport document(s).
I (Q
~
~
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~
~
~
~ ~
~
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~
~
~
~
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~ ~
~ ~
~I ~
~
~ ~
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~ ~
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~
~
~
~
~ ~
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~
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~
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~ ~
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~ I
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~
PSL-1 Page 5-16a Qualification Methods (continued) all assemblies will maintain their pressure seal capability for at least 1 year of post-LOCA operation.
According to the analysis, the high voltage penetrations will also function electrically for at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> post-LOCA and the 600 v power, and instrument penetrations will function electrically for at least 1 year post-LOCA.
ST. LVCIF. UNIT 1 Ei)VIP)1":llT TAG l!Ulhl3?'.RS
.Heat Shrink Splices HAilUFAC')'URL:R Raychem Corporation YiODEL Thermofit VCSF QVALIFJCATIOil DJCU."ZHTATIOi(
Franklin Institute Research Laboratores Final Re rt F-C4033-3 QUALIFICA')')0'.! )'.HV3RO:!!i!'.!l7 Aging Tlt?E Acci ent Simulation
) JUida TP! il'
~
7 Days Not easured 302oF 0-5 min.
0 to 70 psig (in C.
140-280 F
(in 25 sec) to 357 F 5 min. to 10 hr.
> 70 psig 357'F 10-12 hr.
7M31 ~ig (in 1 hr.)
357-275o F 12 hr. to 4Das 31 psig 275'F-4 Days to 30 Da
'4 10 psig 2120F R)'.L.
)lUi5.
Not Measured 100%
100%
100%
100%
100'L Clii"i Clienu.cal Spray Solution:
3000 ppm Boron as Boric Acid, 0.064 Molar Sodium Thiosulfate ad)usted M/NaOH to H of 10.5 ar room temreratore llA))
Sx 10 Rad
~ ~
- 1. 5 x 10 Rads.
(For a tntal dose o f 2xlOR)
QUAJrT)'ICATIOfl i?!)'?iODS Synergistic - All t'nreameters.
Note:
The above results arc a summary provided for rcvicMcz convcniencc.
For comnlcte dntnils Non the ahnvn ~n<n~n~--~