ML18087A912
| ML18087A912 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 05/09/1983 |
| From: | Liden E Public Service Enterprise Group |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8305170328 | |
| Download: ML18087A912 (16) | |
Text
PS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Nuclear Department May 9, 1983 Director of Nuclear Reactor Regulation U. s. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20014 Attention:
Mr. Steven A. Varga, Chief Operating Reactors Branch 1 Division of Licensing
Dear Mr. Varga:
SAFETY EVALUATION REPORT FOR ENVIRONMENTAL QUALIFICATION OF SAFETY-RELATED ELECTRICAL EQUIPMENT SALEM GENERATING STATION UNITS NO. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 The subject SER's forwarded the Franklin Research Center's (FRC) evaluation of PSE&G's Equipment Qualification Report for Salem Units No. 1 and 2.
The SER's requested within 90 days our plans for qualification or replacement of unqualified equipment and a schedule for corrective actions.
In addition, we were required to resolve qualification deficiencies identified by the FRC's review.
Attachments 1 and 2 address equipment listed in FRC Report Table 4-1, Categories I.B, II.A, II.C and IV for Unit 1 and 2 respectively as follows:
- 1)
Category I.B -
Equipment to be replaced, relocated or redesigned.
Indicates whether equipment has been replaced, relocated or redesigned or gives an installation date.
The type of replacement equipment and qualification status is stated.
- 2)
Category II.A -
Equipment qualification not established based on FRC's review of documentation.
Contains PSE&G's resolution to the deficiencies that were identified by the FRC.
8305170328 830509 PDR ADOCK 05000272 P
PDR The Energy People 95-21 68 (80 M) 11-82
Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 3)
Category II.C -
Equipment satisfies all requirements except qualified life or replacement schedule not justified.
Contains PSE&G's resolution to the qualified life deficiencies that were identified by the FRC.
- 4)
Category IV -
Documentation not made available to the FRC.
Restates PSE&G's previous position that portions of documentation are proprietary and are available for review at PSE&G.
Summary 5/9/83 PSE&G has modified or will modify during the next Unit No. 1 and Unit No. 2 refueling outages those items addressed in Category I.B.
The deficiencies identified by the FRC in Categories II.A, II.C and IV have been addressed except for Limitorque valve operators, Burndy lugs, Samual Moore cable and AIW cable.
These items require additional informat~on prior to resolution of the FRC's questions.
Should you have any questions, please do not hesitate to contact us.
Attachments CC:
Mr. Donald C. Fischer Licensing Project Manager Mr. Leif Norrholm Senior Resident Inspector Very truly yours,
- A. Liden Manager -
Nuclear Licensing and Regulation
. ~*
UNIT I ITEM NO.
1 2
13 14 17 18, 19 CATEGORY IIA IIA IB IB IB IIA 06/9 1 & 2 DESCRIPTION RC Hot/Cold Leg Narrow Range Temperature -
Rosemount Model 176KF RTD RC Hot/Cold Leg Wide Range Temperature -
Rosemount Model 176KS RTD Local Control of MS167 Hydraulic Pump Micro Switch Model 910 PGD533 Local Control of MS167 Hydraulic Pump Cinch Jones Terminal Block Auxiliary Feedwater Flow -
Square Root Extractors Pump Motors located in Auxiliary Building ACTION
-Will be replaced next Unit 1 refueling outage with qualified RTD QUALIFICATION STATUS
-Will be replaced next Unit 1 refueling outage with qualified Conax RTD PSE&G is in the process of reviewing Conax's Environmental Qualification Report and should be finished by 8/1/83.
-Removed from the control. circuitry
-Removed from the Control circuitry
-Will be relocated to a mild environment next Unit 1 refueling outage
-FRC had four questions regarding the qualification of motors:
- 10) Lack of traceability of installed motors to the reference test report.
lA) Our analysis of WCAP 8754 contained in PSE&G E0-16 Report identified an anomaly concerning insulation thickness.
Westing-house answered our question via a letter dated March 24, 1981 contained. in EQ-15 volume 2 Tab 15.05.
Westinghouse has used only thermolastic epoxy insulation in their nuclear motors.
Therefore, these motors do have thermolastic epoxy stator insulation.
- 20) Lack of documented evidence for the qualificati"on of the motor to lead splice 2A) There are actually two splices per phase in the motor.
One between the thermolastic epoxy and the internal cable and a second at the lead box.
The first splic~ was supplied with the motor from Westinghouse.
As stated on page 1-1 of WCAP8754, Environmental Qualification of Class lE Motors for Nuclear Out-of-Containment Use,
".** all large AC motors manufactured. by Westinghouse for nuclear service employ the same insulation system and types of bearings, a generic qualification of these motors is possible." The splice material is actually qualified by WCAP 7829, Fan Cooler Motor unit test, under component testing "for Scotch 70 splice tape summarized in table 22 un page 46.
UNIT l ITEM NO.
CATEGORY 18, 19 (Contin~ed)
IIA 50 IIA DESCRIPTION Fan Cooler Motor loc~ted in containment ACTION The second splice was originally made with Okonite splice kits.
Since FRC did not question the Okonite qualification, we assume that it was acceptable.
PSE&G will verify the splices on all motors.
3Q) The insulation class was not stated.
3A) As stated in 2A, only thermolastic epoxy insulation with thermal endurance as shown in Figure 4.1, page 4-2 of WCAP 8754 is used.
The curve is equal to or greater than the requirement of Class F insulation 4Q) The installed grease (bearing) lubricant was not identified.
4A) The appropriate lubricant is Westinghouse grease S#773A773G05 conforming to WCAP7498-L, Section 17.
Plant records are being checked to assure that the correct lubricant was used.
-FRC had 3 questions regarding the qualification of the motors:
lQ) Lack of traceability of the installed motor to the referenced test report.
lA) Our analysis of WCAP 8754 contained in PSE&G EQ-16 Report identified an anomaly concerning insulation thickness.
Westinghouse answered our question via a letter dated March 24, 1981 contained in EQ-15 volume 2 Tab 15.05.
Westinghouse has used only thermolastic epoxy insulation in their nuclear motors.
Therfore, these motors do have thermolastic epoxy stator insulation.
- 20).It was not stated whether the motor had an integral air-to-water heat exchanger.
2A) The motors have inte9ral air-to-water heat exchanger.
3Q) The motor insulation class and type were not stated.
3A) Our analysis of WCAP 8754 contained in PSE&G EQ-16 Report identified an anomaly concerning insulation thickness.
Westinghouse answered our question via a letter dated March 24, 1981 contained in EQ-15 volume 2 Tab 15.05.
Westinghouse has used only thermolastic epoxy insulation in their nuclear motors.
Therefore, these motors do have thermolastic epoxy stator insulation.
QUALIFICATION STATUS
UNIT 1 ITEM NO.
CATEGORY 90
!IA 91
!IA 94
!IA 44
!IA 06/9 5 & 6 DESCRIPTION Motorized Valve Actuator Limitorque SMB Motors Motorized Valve Actuator Limitorque SMB Motors Rockbestos Electrical Cable -
Firewall SR Boston Insulated Wire Bostrad 7E Insulation Bostrad 7 ESPE Jacket Boston Insulated Wire Bostrad 7E Insulation Bostrad 7 ESPE Jacket
- ' -. ' 1 ~I,'
....'* ',""".~~:,;*,' !"'
ACTION PSE&G is presently reviewing this item.
Results should be available 10/1/83.
PSE&G is presently reviewing this item; Results should be available 10/1/83.
FRC stated that PSE&G did not identify cable with respect to:
wire size, arrangement of conductors, fillers, binders, etc. & rated characteristics.
The cable in the plant is a single conductor number 2 on the pressurizer heater.
It has a thicker insulation than the test sample and the same insulation compound as stated in our Report EQ-07.
IEEE 383 implies that a cable with thicker insulations than the tested cable is also qualified.*
-FRC had several questions concerning the several types of cable:
lQ) PSE&G has not provided information either on the SCEW sheets or in analysis E0-05 to establish that the installed cable constructions are the same as those constructions which successfully passed a test which envelopes the required Salem Parameters.
lA) BIW has retested this product to expand and update their previous testing.
Analysis of that report is contained in EQ-34.
A letter dated May 24, 1982, indicates that all of the nuclear EPR insulation (Bostrad 7E) manufactured by BIW is of the same formulation.
This connection is established by the QAF21 forms attached to all safety related orders.
Therefore, the appropriate
- correlation has been established.
2Q) The report also refers to F-C3859-l for test results.
Report F-C3859-l is a report of testing conducted on various BIW cable constructions in accordance with IEEE 383-74 and IEEE 323-74.
The cables tested and the results of the tests are reproduced on page 5i.
The report indicates that some constructions successfully passed test while other cable constructions did not.
QUALIFICATION STATUS PSE&G E.Q. Report # EQ-07 PSE&G E.Q. Report #34
_____________ ______j
44 CATEGORY (Continued)
IIA 06/9 7 & 8 DESCRIPTION Boston Insulated Wire XLPE Coaxial Cable Boston Insulated Wire BIWF Fluoropolymer ACTION 2A) The questionable cables reported on page 5i:
are for multi-conductor flame retardant XLPE and single conductor
- l6EPR cable.
The BIW part number indicates that the cables were laboratory test samples (LSS number Vs a part number).
The BIW report indicates, and verbal discussions with BIW have confirmed, that the compounds used in the questionable laboratory samples are not used in nuclear products.
lQ) Report B912 (1705) is a test summary which discusses test results on Triaxial cable.
The test profile does not envelope the Salem profile.
The report also discusses test results on a coaxial cable.
The reported test duration exceeds the Salem accident duration but the reported peak temperature is 50°F below the peak temperature described by the Salem required profile.
lA) This is covered by EQ-i7.
That report shows three separate sets of testing.
The first two sets.were to a maximum temperature of 300°F.
The third test was to the IEEE 323 LOCA profile which is to 340°F peak.
The last tests shows that there is not a change in state of the insulation which allows the use of the long term aging data in Figure 2.
That data indicates that our required 1 minute hold at 350° is equivalent to approxima-tely a 15 minute hold at 300°F.
The test peak of 300°F was held for 15 minutes in the first test and 240 minutes in the second test.
Therefore, the tests temperatures meet or exceed the Salem requirements.
lQ) Report B913 is a summary report of information concerning Coaxial and triaxial cable with BIWF Fluoropolymer insulation.
The document refers to tests report in F-C3859-l which are discussed on page 5h and 5i.
lA) The cables in question are not insulated with BIWF Fluoropolymer.
QUALIFICATION STATUS PSE&G E.Q. Report E0-27
t UNIT 1 ITEM NO.
CATEGORY 44 6,22,25 35,61,71, 72,73,74, 75,76,77 78,79,80, 81,83,84, 85 82, 92 35 3,4,5,8,15 32,66,68, 69,89,93 16 65 29 30 D6/9 9 & 10 IIA IB IB IIA IB IB IIA IB Hl DESCRIPTION Boston Insulated Wire All Various Solenoid Valves Various Solenoid Valves Various Solenoid Valves Various Pressure Transmitters Various Pressure Transmitters Various Pressure Transmitters Flow/Pressure Control -
Square Root Extractor Flow Controller ACTION lQ) Descriptions of cable constructions contained in the referenced test reports do not correspond to descriptions provided by the licensee on the SCEW sheets or in Analysis EQ-05.
lA) IBEE 383 and IEEE 323 allow the use of representative samples in performing specific testing.
The use of two conductor and seven conductor cable is considered representative of the cables at Salem according to IEEE 383.
Replaced all with ASCO NP Series Solenoid Valves.
Replaced all with ASCO NP Series Solenoid Valves", save SV0621, SV0624, SV0627, SV0630, which were deleted from the system FRC questioned the status of these valves in a submerged state.
PSE&G has stated that the valves have not been proven in a submerged state, but the electrical circuits are protected by lE breakers.
PSE&G has analyzed the potential loss of power and this analysis has been reviewed and approved by the NRC (Reference in Salem FSAR response to Question 6.28)
-Replaced with Rosemount Model 1153D pressure transmitters
-Replaced all except FA-0218, containment Spray Addition Tank Header, with Rosemount 1153D Pressure transmitters; will replace FA-0218 next outage with a Rosemount 1153 pressure transmitter.
-Will replace PA-0227, PA-7461 and PT-0942 with a Rosemount 1153 pressure transmitter next Unit 1 refueling out~ge.
-Relocated to a mild environment (828 Panel, Switchgear Room, 84' Elevation)
System redesigned; function is now performed by a mechanical device.
QUALIFICATION STATUS Valves have undergone a successful qualification program; PSE&G has test report and will review it by 10/1/83 Valves have undergone a successful qualification program; PSE&G has test report and will review it by 10/1/83 Model has been successfully qualified by manufacturer; the qualification test report is not yet available; PSE&G expects to have report reviewed by 1/1/84 Model has been successfully qualified by manufacturer; the qualification test report is not yet available.
PSE&G expects to have ~
report reviewed by 1/1/84 Model has been successfully qualified by manufacturer; the qualification test report is not yet available.
PSE&G expects to hav~
report reviewed by 1/1/84
UNIT 1
- ~:
- NG.
CATEGORY 31 IB 38 IIA 47 IIA 52 IIC 54 IB 57 IB 62.
IB 67 IB 12,26,27 IB 28,34,36, 63,64,70 86,88 36,87 IIA 36 IIA D6/9 11 & 12 DESCRIPTION Plow/Pressure Control -
E/P Transducer Motorized Valve Actuator located outside containment Limitorque Model SMB, Class B Insulation Rockbestos Electrical Cable Electrical Connections -
Burndy Model HY Lug Containment Sump Level -
Gems Model LS 800 Containment Radiation Detector High Range - Trapelo Model TA 63A Hydrogen-Oxygen Analyzer -
Bacharach Model ND Auxilliary Peedwater Plow -
Square Root Extractor Various Limit Switches Various Limit Switches Various Limit Switches ACTION
-Relocated to a mild environment (830 Panel, Service Water Piping Room)
PSE&G is presently reviewing latest qualifi-cation data.
Results should be available 10/1/83.
-These cables are not used in safety-related circuits, therefore exempt PSE&G is presently reviewing this item.
Results should be available 7/1/83.
-Equipment was qualified by manufacturer.
-Replaced with Victoreen Model, which was qualified by manufacturer.
-Replaced with Exosenser model, which has been qualified.
-Will be relocated to a mild environment next Unit 1 outage
-Replaced all with Namco Model EA-180 Limit Switches
-Replaced all with Namco Model EA-180 Limit Switches, save VC5 & VC6 which used a Namco EA-740 Limit ~witch.
-PRC had three questions regarding the qualification of Namco EA-180 Limit Switch:
Ql) The method used by Salem to seal the Limit Switches.
Al) Conax connectors are used to seal the limit switches from the environment.
Q2) The concentration of chemical spray used in the test as compared to in the plant.
A2) The test chemical spray was composed of boric acid, water sodium thiosulfate &
sodium hydroxide at a pH between 10 & 11 with a coverage of.015 gallons/min./
/ft2.
The test was maintained for 4 days.
Plant "condition called for a pH greater than 8.5 for 22.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.
QUALIPICATION STATUS PSE&G E.Q. Report EQ-8 PSE&G will review manufacturer's E.Q. Report by 10/1/83 PSE&G has Victoreen's Environmental Qualification Report and will review it by.....
10/1/83 PSE&G E.Q. Report Pile #33 Namco Model EA-180 Limit Switches are qualified by manufacturer (Report QTR-105, Rev. 3, dated August 20, 1981).
PSE&G
~~.Q.
Report.
Namco Model EA-180 Limit Switches are qualified by manufacturec (Repoct OTR-105, Rev. 3, dated August 20, 1981).
Namco Model EA-740 Limit Switches ace qualified by manufactucer (Report QTR-111, dated Oct. 2, 1980).
PSE&G E~Q. Report.
UNIT l
~
NO.
36 43 49 51 42 CATEGORY (Continued)
IIA IIC IV IV IIC D6/9 13 DESCRIPTION Samual Moore Electrical Cable, EPR Insulation Motor Control Center located in Electrical Penetration, Auxiliary Building 84' Elevation -
GE Model 7700 Hydrogen Recombiner located in Containment -
Westinghouse Model American Insulated Wire ACTION Q3) The length of the qualified life of the limit switches.
A3) PSE&G is, at present, reviewing the latest submittal from Namco and will institute a maintenance/replacement schedule.
PSE&G is reviewing the data on cable and will present~ qualified life by 10/1/83.
PSE&G considers this equipment to be qualified.
Some documentation has been classified as proprietary but is available for examination at our office.
Documentation has been classified as proprietary but.is available for examination at our office.
PSE&G is awaiting results from Westinghouse on aging specifications.
PSE&G has reaffirmed that plant safety is not affected pending qualification for aging.
PSE&G is presently undergoing a review, which will extend the qualified life.
QUALIFICATION STATUS PSE&G E. Q. File EQ-14
_J
UNIT 2 ITEM NO.
1 2
13 14 17 18' 19 CATEGORY IIA IIA I8 I8 IB
!IA D6/14 1 & 2 DESCRIPTION RC Hot/Cold Leg Narrow Range Temperature -
Rosemount Model 176KF RTD RC Hot/Cold Leg Wide Range Temperature -
Rosemount Model 176KS RTD Local Control of MS167 Hydraulic Pump Micro Switch Model 910 PGD533 Local Control of MS167 Hydraulic Pump Cinch Jones Terminal Block Auxiliary Feedwater.Flow -
Square Root Extractors Pump Motors located in Auxiliary Building ACTION
-Will be replaced next Unit 2 refueling outage with qualified RTD OUALIFICATION STATUS Replaced with qualified Conax RTD PSE&G is in the process of reviewing Conax's Environmental Qualification Report and should be finished by 8/1/83.
-Removed from the control circuitry
-Removed from the Control circuitry Relocated to a mild environment
-FRC had four questions regarding the qualification of motors:
lQ) Lack of traceability of installed motors to the reference test report.
lAf Our analysis of WCAP 8754 contained in PSE&G EQ-16 Report identified an anomaly concerning insulation thickness.
Westing-house answered our question via a letter dated March 24, 1981 contained in E0-15 volume 2 Tab 15.05.
Westinghouse has* used only thermolastic epoxy insulation in their nuclear motors.
Therefore, these motors do have thermolastic epoxy stator insulation.
2Q) Lack of documented evidence for the qualification of the motor to lead splice 2A) There are actually two splices per phase in the motor.
One between the thermolastic epoxy and the internal cable and a second at the lead box.
The first splice was supplied with the motor from Westinghouse.
As stated on page 1-1 of WCAP8754, Environmental Qualification of Class lE Motors for Nuclear Out-of-Containment Use,
"... all large AC motors manufactured by Westinghouse for nuclear service employ the same insulation system and types of bearings, a generic qualification of these motors is possible." The splice m~terial is actually qualified by WCAP 782~, Fan Cooler Motor unit test, under component testing for Scotch 70 splice tape summarized in table 22 on page 46.
UNIT 2
~
~ CATEGORY 18, 19 (Continued)
IIA 50 IIA DESCRIPTION Fan Cooler Motor located in containment ACTION The second splice was originally made with Okonite splice kits.
Since FRC did not question the Okonite qualification, we assume that it was acceptable.
PSE&G will verify the splices on all motors.
- 30) The insulation class was not stated.
3A) As stated in 2A, only thermolastic epoxy insulation with thermal endurance as shown in Figure 4.1, page 4-2 of WCAP 8754 is used.
The curve is equal to or greater than the requirement of Class F insulation 4Q) The installed grease (bearing) lubricant was not identified.
4A) The appropriate lubricant is Westinghouse grease S#773A773G05 conforming to WCAP7498-L, Section 17.
Plant records are being checked to assure that the correct lubricant was used.
-FRC had 3 questions regarding the qualification of the motors:
lQ) Lack of traceability of the installed motor to the referenced test report.
lA) Our analysis of WCAP 8754 contained in PSE&G EQ-16 Report identified an anomaly concerning insulation thickness.
Westinghouse answered our question via a letter dated March 24, 1981 contained in EQ-15 volume 2 Tab 15.05.
has used only thermolastic epoxy insulation in their nuclear motors.
Therfore, these motors do have thermolastic epoxy stator insulation.
2Q) It was not stated whether the motor had an integral air-to-water heat exchanger.
2A) The motors have integral air-to-water heat exchanger.
- 30) The motor insulation class and type were not stated.
3A) Our analysis of WCAP 8754 contained in PSE&G E0-16 Report identified an anomaly concerning insulation thickness.
Westinghouse answered our question via a letter dated March 24, 1981 contained in EQ-15 volume 2 Tab 15.05.
Westinghouse has used only thermolastic epoxy insulation in their nuclear motors.
Therefore, these motors do have thermolastic epoxy stator insulation.
QUALIFICATION STATUS
_J
UNIT 2 ITEM NO.
CATEGORY 90
!IA 91
!IA 97
!IA 44
!IA 06/14 5* & 6 DESCRIPTION Motorized Valve Actuator Limitorque SMB Motors Motorized Valve Actuator Limitorque SMB Motors Rockbestos Electrical Cable -
Firewall SR Boston Insulated Wire Bostrad 7E Insulation Bostrad 7 ESPE Jacket Boston Insulated Wire Bostrad 7E Insulation Bostrad 7 ESPE Jacket PSE&G is presently reviewing this item.
Results should be available 10/1/83.
PSE&G is presently reviewing this item.
Results should be available 10/1/83.
FRC stated that PSE&G did not identify cable with respect to:
wire size, arrangement of conductors, fillers, binders, etc. & rated characteristics.
The cable in the plant is a single conductor number 2 on the pressurizer heater.
It has a thicker insulation than the test sample and the same insulation compound as stated in our Report EQ-07.
IEEE 383 implies that a cable with thicker insulations than the tested cable is also qualified.
-FRC had several questions concerning the several types of cable:
lQ) PSE&G has not provided information either on the SCEW sheets or in analysis E0-05 to establish that the installed cable constructions are the same as those constructions which successfully passed a test which envelopes the required Salem Parameters.
lA) BIW has retested this product to expand and update their previous testing.
Analysis of that report is contained in EQ-34.
A letter dated May 24, 1982, indicates that all of the nuclear EPR insulation (Bostrad 7E) manufactured by BIW is of the same formulation.
This connection is established by the QAF21 forms attached to all safety related orders.
Therefore, the appropriate correlation has been established.
2Q) The report also refers to F-C3859-l for test results.
Report F-C3859-l is a report of testing conducted on various BIW cable constructions in accordance with IEEE 383-74 and IEEE 323-74.
The cables tested and the results of the tests *are reproduced on page Si.
The report indicates that some constructions successfully passed test while other cable constructions did not.
QUALIFICATION STATUS PSE&G E.Q. Report # E0-07 PSE&G E.Q. Report #34
UNIT 2 ITEM NO.
44 CATEGORY (Continued)
IIA D6/14 7 & 8 DESCRIPTION Boston Insulated Wire XLPE Coaxial Cable Boston Insulated Wire BIWF Fluoropolymer ACTION 2A) The questionable cables reported on page Si:
are for multi-conductor flame retardant XLPE and single conductor
- 16EPR cable.
The BIW part number indicates that the cables were laboratory test samples (LSS number Vs a part number).
The BIW report indicates, and verbal discussions with BIW have confirmed, that the compounds used in the questionable laboratory samples are not used in nuclear products.
lQ) Report B912 (170S) is a test summary which discusses test results on Triaxial cable.
The test profile does not envelope the Salem profile.
The report also discusses test results on a coaxial cable.
The reported test duration exceeds the Salem accident duration but the reported peak temperature is S0°F below the peak temperature described by the Salem required profile.
lA) This is covered by EQ-27.
That report shows three separate sets of testing.
The first two sets were to a maximum temperature of 300°F.
The third test was to the IEEE 323 LOCA profile which is to 340°F peak.
The last tests shows that there is not a change in state of the insulation which allows the use of the long term aging data in Figure 2.
That data indicates that our required 1 minute hold at 350° is equivalent to approxima-tely a lS minute hold at 300°F.
The test peak of 300°F was held for 15 minutes in the first test and 240 minutes in the second test.
Therefore, the tests temperatures meet or exceed the Salem requirements.
lQ) Report 8913 is a summary report of information concerning Coaxial and triaxial cable with BIWF Fluoropolymer insulation.
The document refers to tests report in F-C38S9-l which are discussed on page 5h and 5i.
lA) The cables in qu~stion are not insulated with BIWF Fluoropolymer.
QUALIFICATION STATUS PSE&G E.Q. Report EQ-27
CATEGORY 44 3,22,25 35,61,71, 72,73,74, 75,76,77 78,79,80, 81,83,84, 85 82, 92 35 IIA IB IB IIA 5,8,15,32 IB 57,66,68, 69,89,93,94 16 IB 65 IIA 29 IB 30 IB D6/14 9 & 10
~- *----*--------------- -.
DESCRIPTION Boston Insulated Wire All Various Solenoid Valves Various Solenoid Valves Various Solenoid Valves Various Pressure Transmitters Various Pressure Transmitters Various Pressure Transmitters Flow/Pressure Control -
Square Root Extractor Flow Controller ACTION lQ) Descriptions of cable constructions contained in the referenced test reports do not correspond to descriptions provided by the licensee on the SCEW sheets or in Analysis EQ-05.
lA) IEEE 383 and IEEE 323 allow the use of representative samples in performing specific testing.
The use of two conductor and seven conductor cable is considered representative of the cables at Salem according to IEEE 383.
Replaced all with ASCO NP Series Solenoid Valves.
Replaced all with ASCO NP Series Solenoid Valves", save SV0621, SV0624, SV0627, SV0630, which were deleted from the system FRC questioned the status of these valves in a submerged state.
PSE&G has stated that the valves have not been proven in a submerged state, but the electrical circuits are protected by lE breakers.
PSE&G has analyzed the potential loss of power and this analysis has been reviewed and approved by the NRC (Reference in Salem FSAR* response to Question 6.28)
-Replaced with Rosemount Model 1153D pressure transmitters
-Replaced all except FA-0218, containment Spray Addition Tank Header, with Rosemount 1153D Pressure transmitters; will replace FA-0218 next outage with a Rosemount 1153 pressure transmitter.
-Will replace PA-0227, PA-7461 and PT-0942 with a Rosemount 1153 pressure transmitter next Unit 2 refueling ?utage.
-Relocated to a mild e~vironment (828 Panel, Switchgear Room, 84' Elevation)
System redesigned; function is now performed by a mechanical devic.e.
QUALIFICATION STATUS Valves have undergone a successful qualification program; PSE&G has test report and will review it by 10/1/83 Valves have undergone a successful qualification program; PSE&G has test report and will review it by 10/1/83 Model has been successfully qualified by manufacturer; the qualification test report is not yet available; PSE&G expects to have report reviewed by 1/1/84 Model has been successfully qualified by manufacturer; the qualification test report is not yet available.
PSE&G expects to have report reviewed by 1/1/84 Mode~ has been successfully qualified by manufacturer; the qualification test report is not yet available.
PSE&G expects to have report reviewed by 1/1/84
__j
UNI'J'. 2 ITEM NO.
CATEGORY 31 IB 38 IIA 47 IIA 52 IIC 54 IB 95, 96 IB 6f IB 67 IB 4,7,12, IB 26,27,28, 34,36,63,
- 64. 70,86,88
- 36. 87 IB 36 IIA D6/14.11 & 12 DESCRIPTION Flow/Pressure Control -
E/P Transducer Motorized Valve Actuator located outside containment Liniitorque Model SMB, Class B Insulation Rockbestos Electrical Cable Electrical Connections -
Burndy Model HY Lug Containment Sump Level -
Gems Model LS 800 Containment Radiation Detector High Range - Trapelo Model TA 63A Hydrogen-Oxygen Analyzer -
Bacharach Model ND Auxilliary Feedwater Flow - Square Root Extractor Various Limit Switches Various Limit Switches Various Limit Switches ACTION
-Relocated to a mild en~ironment (830 Panel, Service Water Piping Room)
PSE&G is presently reviewing latest qualifi-cation data.
Results should be available 10/1/83.
-These cables are not used in safety-related circuits, therefore exempt PSE&G is presently reviewing this item.
Results should be available 7/1/83.
-Equipment was qualified by manufacturer.
-Replaced with Victoreen Model, which was qualified by manufacturer.
-Replaced with Exosenser model, which has been qualified.
Relocated to a mild environment
-Replaced all with Namco Model EA-180 Limit Switches
-Replaced all with Namco Model EA-180 Limit Switches, save VC5 & VC6 which used a Namco EA-740 Limit Switch.
-FRC had three questions regarding the qualification of Namco EA-180 Limit Switch:
- 01) The method used by Salem to seal the Limit Switches.
Al) Conax connectors are used to seal the limit switches from the environment.
Q2) The concentration of chemical spray used in the test as compared to in the plant.
A2) The test chemical spray was composed of boric acid, water sodium thiosulfate &
sodium hydroxide at a pH between 10 & 11 with a coverage of.015 gallons/min./
ft2.
The test was maintained for 4 days.
Plqnt condition called for a pH greater than 8.5*for 22.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.
QUALIFICATION STATUS f'
PSE&G E.Q. Report EQ-8 PSE&G will review manufacturer's E.O. Report.
by 10/1/83 PSE&G has Victoreen's Environmental Qualification Report and will review it by 10/1/83 PSE&G E.O. Report File #33 Namco Model EA-180 Limit Switches are qualified by manufacturer (Report QTR-105, Rev. 3, dated August 20, 1981).
PSE:&G E.O.
Report.
Namco Model EA-180 Limit Switches are qualified by manufacturer (Report QTR-105, Rev. 3, dated August 20, 1981).
Namco Model EA-740 Limit Switches are qualified by manufacturer (Report OTR-111, dated Oct. 2, 1980).
PSE&G E.Q. Report.
UNIT 2 ITE:f.I~
NO.
CATEGORY 36 (Continued)
IIA 43 IIC 49 IV 51 IV 42 II'C D6/14 13 DESCRIPTION.
ACTION Samual Moore Electrical Cable, EPR Insulation Motor Control Center located in Electrical Penetration, Auxiliary Building 84' Elevation 7 GE Model 7700 Hydrogen Recombiner located in Containment - Westinghouse Model American Insulated Wire
- 03) The length of the qualified life of the limit switches.
A3) PSE&G is, at present, reviewing the latest submittal from Namco and will institute a maintenance/replacement schedule.
PSE&G is reviewing the data on cable and will present a qualified life by 10/1/83 *.
PSE&G considers this equipment to be qualified.
Some documentation has been classified as proprietary but is available for examination at our office.
Documentation has been classified as proprietary but is available for examination at our office.
PSE&G is awaiting results from Westinghouse on aging specifications.
PSE&G has reaffirmed that plant safety is not affected pending qualification for aging.
PSE&G is presently undergoing a review, which will extend the qualified life.
QUALIFICATION STATUS PSE&G E. O. File E0-14