ML18087A912: Difference between revisions

From kanterella
Jump to navigation Jump to search
← Older edit
VisualWikitext
Created page by program invented by StriderTol
StriderTol Bot change
 
Line 16: Line 16:


=Text=
=Text=
{{#Wiki_filter:PS~G
{{#Wiki_filter:*
* 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
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:==
==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.
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.
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:
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.
: 1)
Indicates whether equipment has been replaced, relocated or redesigned or gives an installation date.                       The type of replacement equipment and qualification status is stated.
Category I.B -
: 2)   Category II.A - Equipment qualification not established based on FRC's review of documentation.
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.
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
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                   5/9/83
Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 3)
: 3) Category II.C - Equipment satisfies all requirements except qualified life or replacement schedule not justified.
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.
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.
: 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.
Restates PSE&G's previous position that portions of documentation are proprietary and are available for review at PSE&G.
Summary 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.
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.
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.
Should you have any questions, please do not hesitate to contact us.
Very truly yours,
Attachments CC:
* A. Liden Manager - Nuclear Licensing and Regulation Attachments CC: Mr. Donald C. Fischer Licensing Project Manager Mr. Leif Norrholm Senior Resident Inspector
Mr. Donald C. Fischer Licensing Project Manager Mr. Leif Norrholm Senior Resident Inspector Very truly yours,
* A. Liden Manager -
Nuclear Licensing and Regulation


Attachment 1
. ~*
  . ~*
UNIT I ITEM NO.
UNIT I ITEM NO. CATEGORY       DESCRIPTION                                           ACTION                                    QUALIFICATION STATUS 1      IIA  RC Hot/Cold Leg Narrow Range         -Will be replaced next Unit 1 refueling outage Temperature - Rosemount Model           with qualified RTD 176KF RTD 2      IIA  RC Hot/Cold Leg Wide Range           -Will be replaced next Unit 1 refueling               PSE&G is in the process of reviewing Conax's Temperature - Rosemount Model 176KS    outage with qualified Conax RTD                    Environmental Qualification Report and should RTD                                                                                        be finished by 8/1/83.
1 2
13        IB  Local Control of MS167 Hydraulic Pump -Removed from the control. circuitry
13 14 17 18, 19 CATEGORY IIA IIA IB IB IB IIA 06/9 1 & 2 DESCRIPTION RC Hot/Cold Leg Narrow Range Temperature -
                  - Micro Switch Model 910 PGD533 14        IB  Local Control of MS167 Hydraulic Pump -Removed from the Control circuitry
Rosemount Model 176KF RTD RC Hot/Cold Leg Wide Range Temperature -
                  - Cinch Jones Terminal Block 17        IB  Auxiliary Feedwater Flow - Square    -Will be relocated to a mild environment next Root Extractors                        Unit 1 refueling outage 18, 19      IIA  Pump Motors located in Auxiliary      -FRC had four questions regarding the Building                                qualification of motors:
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.
: 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.
lA) Our analysis of WCAP 8754 contained in PSE&G E0-16 Report identified an anomaly concerning insulation thickness.
: 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.
Westing-house answered our question via a {{letter dated|date=March 24, 1981|text=letter dated March 24, 1981}} contained. in EQ-15 volume 2 Tab 15.05.
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,
Westinghouse has used only thermolastic epoxy insulation in their nuclear motors.
                                                              " .** 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 06/9 1 & 2                                                  splice tape summarized in table 22 un page 46.
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                                                                 ACTION                    QUALIFICATION STATUS NO. CATEGORY             DESCRIPTION The second splice was originally made 18, 19 (Contin~ed) with Okonite splice kits. Since FRC did IIA not question the Okonite qualification, we assume that it was acceptable.
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.
PSE&G will verify the splices on all motors.
3Q) The insulation class was not stated.
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.
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.
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.
The curve is equal to or greater than the requirement of Class F insulation 4Q) The installed grease (bearing) lubricant was not identified.
50        IIA  Fan Cooler Motor loc~ted in -FRC had 3 questions regarding the containment                    qualification of the motors:
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.
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.
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.
Westinghouse answered our question via a {{letter dated|date=March 24, 1981|text=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.
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.
: 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.
2A) The motors have inte9ral air-to-water heat exchanger.
3Q) The motor insulation class and type were not stated.
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.
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.
Westinghouse answered our question via a {{letter dated|date=March 24, 1981|text=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.
Therefore, these motors do have thermolastic epoxy stator insulation.
QUALIFICATION STATUS


UNIT 1 ITEM                                                                                                                                       QUALIFICATION STATUS CATEGORY                DESCRIPTION                                                          ACTION NO.
UNIT 1 ITEM NO.
90         !IA   Motorized Valve Actuator                                     PSE&G is presently reviewing this item.
CATEGORY 90  
Limitorque SMB Motors                                        Results should be available 10/1/83.
!IA 91
91        !IA  Motorized Valve Actuator                                    PSE&G is presently reviewing this item; Limitorque SMB Motors                                        Results should be available 10/1/83.
!IA 94
Rockbestos Electrical Cable -                                FRC stated that PSE&G did not identify cable     PSE&G E.Q. Report # EQ-07 94        !IA Firewall SR                                                  with respect to: wire size, arrangement of conductors, fillers, binders, etc. & rated characteristics.
!IA 44
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.*
!IA 06/9 5 & 6 DESCRIPTION Motorized Valve Actuator Limitorque SMB Motors Motorized Valve Actuator Limitorque SMB Motors Rockbestos Electrical Cable -
                                                                              -FRC had several questions concerning the       PSE&G E.Q. Report #34 several types of cable:
Firewall SR Boston Insulated Wire Bostrad 7E Insulation Bostrad 7 ESPE Jacket Boston Insulated Wire Bostrad 7E Insulation Bostrad 7 ESPE Jacket
44        !IA  Boston Insulated Wire                                        lQ) PSE&G has not provided information either Bostrad 7E Insulation                                            on the SCEW sheets or in analysis E0-05 Bostrad 7 ESPE Jacket                                              to establish that the installed cable constructions are the same as those constructions which successfully passed a test which envelopes the required Salem Parameters.
*' -. ' 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.
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
Analysis of that report is contained in EQ-34.
                                                                                    *correlation has been established.
A {{letter dated|date=May 24, 1982|text=letter dated May 24, 1982}}, indicates that all of the nuclear EPR insulation (Bostrad 7E) manufactured by BIW is of the same formulation.
Boston Insulated Wire                                        2Q) The report also refers to F-C3859-l for Bostrad 7E Insulation                                              test results. Report F-C3859-l is a Bostrad 7 ESPE Jacket                                              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.
This connection is established by the QAF21 forms attached to all safety related orders.
06/9 5 & 6
Therefore, the appropriate  
                              *  * ' -. ' 1 ~I,' ... .'* ',"''"".~~:,;*,' !"'
*correlation has been established.
_ _ _ _ _ _ _ _ _ _ _ _ _ ______j
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


CATEGORY DESCRIPTION                                ACTION                  QUALIFICATION STATUS 44    (Continued)                       2A) The questionable cables reported on page IIA                              5i: are for multi-conductor flame retardant XLPE and single conductor
44 CATEGORY (Continued)
                                              #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.
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:
Boston Insulated Wire lQ) Report B912 (1705) is a test summary       PSE&G E.Q. Report E0-27 XLPE Coaxial Cable        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.
are for multi-conductor flame retardant XLPE and single conductor  
lA) This is covered by EQ-i7. That report shows three separate sets of testing.
#l6EPR cable.
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.
The BIW part number indicates that the cables were laboratory test samples (LSS number Vs a part number).
Boston Insulated Wire  lQ) Report B913 is a summary report of BIWF Fluoropolymer        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.
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.
lA) The cables in question are not insulated with BIWF Fluoropolymer.
06/9 7 & 8
QUALIFICATION STATUS PSE&G E.Q. Report E0-27


t UNIT 1 ITEM NO. CATEGORY               DESCRIPTION                          ACTION                                  QUALIFICATION STATUS 44           IIA   Boston Insulated Wire         lQ) Descriptions of cable constructions All                                contained in the referenced test reports do not correspond to descriptions provided by the licensee on the SCEW sheets or in Analysis EQ-05.
t UNIT 1 ITEM NO.
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.
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 -
6,22,25        IB            Various            Replaced all with ASCO NP Series Solenoid       Valves have undergone a successful 35,61,71,                      Solenoid            Valves.                                         qualification program; PSE&G has test report 72,73,74,                      Valves                                                              and will review it by 10/1/83 75,76,77 78,79,80, 81,83,84, 85 82, 92          IB            Various            Replaced all with ASCO NP Series Solenoid       Valves have undergone a successful Solenoid            Valves", save SV0621, SV0624, SV0627, SV0630,   qualification program; PSE&G has test report Valves              which were deleted from the system             and will review it by 10/1/83 35          IIA            Various            FRC questioned the status of these valves in Solenoid            a submerged state. PSE&G has stated that the Valves              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) 3,4,5,8,15      IB Various Pressure Transmitters -Replaced with Rosemount Model 1153D pressure   Model has been successfully qualified by 32,66,68,                                          transmitters                                 manufacturer; the qualification test report 69,89,93                                                                                          is not yet available; PSE&G expects to have report reviewed by 1/1/84 16            IB  Various Pressure Transmitters -Replaced all except FA-0218, containment       Model has been successfully qualified by Spray Addition Tank Header, with Rosemount   manufacturer; the qualification test report 1153D Pressure transmitters; will replace     is not yet available. PSE&G expects to have ~
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.
FA-0218 next outage with a Rosemount 1153     report reviewed by 1/1/84                      ..,
lA) IBEE 383 and IEEE 323 allow the use of representative samples in performing specific testing.
pressure transmitter.
The use of two conductor and seven conductor cable is considered representative of the cables at Salem according to IEEE 383.
65          IIA  Various Pressure Transmitters  -Will replace PA-0227, PA-7461 and PT-0942     Model has been successfully qualified by with a Rosemount 1153 pressure transmitter   manufacturer; the qualification test report next Unit 1 refueling out~ge.                 is not yet available. PSE&G expects to hav~
Replaced all with ASCO NP Series Solenoid Valves.
report reviewed by 1/1/84 29            IB  Flow/Pressure Control -        -Relocated to a mild environment (828 Panel, Square Root Extractor          Switchgear Room, 84' Elevation) 30            Hl  Flow Controller                System redesigned; function is now performed by a mechanical device.
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.
D6/9 9 & 10
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
UNIT 1  
*~:
*~:
* NG.     CATEGORY   DESCRIPTION ACTION QUALIPICATION STATUS 31             IB   Plow/Pressure Control -
* NG.
E/P Transducer                                   -Relocated to a mild environment (830 Panel, Service Water Piping Room) 38          IIA    Motorized Valve Actuator located outside containment                                PSE&G is presently reviewing latest qualifi-Limitorque Model SMB, Class B                      cation data. Results should be available 10/1/83.
CATEGORY 31 IB 38 IIA 47 IIA 52 IIC 54 IB 57 IB 62.
Insulation 47          IIA    Rockbestos Electrical Cable
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 -
                                                                          -These cables are not used in safety-related circuits, therefore exempt                   PSE&G E.Q. Report EQ-8 52          IIC    Electrical Connections -
E/P Transducer Motorized Valve Actuator located outside containment Limitorque Model SMB, Class B Insulation Rockbestos Electrical Cable Electrical Connections -
Burndy Model HY Lug                                PSE&G is presently reviewing this item.
Burndy Model HY Lug Containment Sump Level -
Results should be available 7/1/83.
Gems Model LS 800 Containment Radiation Detector High Range - Trapelo Model TA 63A Hydrogen-Oxygen Analyzer -
54              IB  Containment Sump Level - Gems Model LS 800                                            -Equipment was qualified by manufacturer.
Bacharach Model ND Auxilliary Peedwater Plow -
PSE&G will review manufacturer's E.Q. Report by 10/1/83 57            IB  Containment Radiation Detector High Range - Trapelo Model TA 63A                      -Replaced with Victoreen Model, which was qualified by manufacturer.                  PSE&G has Victoreen's Environmental Qualification Report and will review it by.....
Square Root Extractor Various Limit Switches Various Limit Switches Various Limit Switches ACTION
62 .          IB 10/1/83                                    ..
-Relocated to a mild environment (830 Panel, Service Water Piping Room)
Hydrogen-Oxygen Analyzer - Bacharach Model ND                                          -Replaced with Exosenser model, which has been qualified.                             PSE&G E.Q. Report Pile #33 67            IB  Auxilliary Peedwater Plow - Square Root Extractor                                    -Will be relocated to a mild environment next Unit 1 outage 12,26,27      IB    Various Limit Switches 28,34,36,                                                            -Replaced all with Namco Model EA-180 Limit 63,64,70                                                                  Switches                                    Namco Model EA-180 Limit Switches are 86,88                                                                                                                qualified by manufacturer (Report QTR-105, Rev. 3, dated August 20, 1981). PSE&G ~~.Q.
PSE&G is presently reviewing latest qualifi-cation data.
Report.
Results should be available 10/1/83.  
* 36 ,87      IIA    Various Limit Switches
-These cables are not used in safety-related circuits, therefore exempt PSE&G is presently reviewing this item.
                                                                        -Replaced all with Namco Model EA-180 Limit Switches, save VC5 & VC6 which used a Namco   Namco Model EA-180 Limit Switches are EA-740 Limit ~witch.                           qualified by manufacturec (Repoct OTR-105, 36          IIA                                                                                                      Rev. 3, dated August 20, 1981). Namco Model Various Limit Switches                                                                          EA-740 Limit Switches ace qualified by
Results should be available 7/1/83.  
                                                                          -PRC had three questions regarding the qualification of Namco EA-180 Limit Switch:   manufactucer (Report QTR-111, dated Oct. 2, 1980). PSE&G E~Q. Report.
-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.
Ql) The method used by Salem to seal the Limit Switches.
Al) Conax connectors are used to seal the limit switches from the environment.
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.
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 &
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./
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 hours.
/ft2.
D6/9 11 & 12
The test was maintained for 4 days.
Plant "condition called for a pH greater than 8.5 for 22.5 hours.
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
UNIT l  
~
~
NO.       CATEGORY             DESCRIPTION                                ACTION                                QUALIFICATION STATUS 36    (Continued)                                     Q3) The length of the qualified life of the IIA                                          limit switches.
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.
A3) PSE&G is, at present, reviewing the latest submittal from Namco and will institute a maintenance/replacement schedule.
43          IIC    Samual Moore Electrical Cable, EPR PSE&G is reviewing the data on cable and will Insulation                        present~ qualified life by 10/1/83.
PSE&G is reviewing the data on cable and will present~ qualified life by 10/1/83.
49          IV    Motor Control Center located in    PSE&G considers this equipment to be         PSE&G E. Q. File EQ-14 Electrical Penetration, Auxiliary  qualified. Some documentation has been Building 84' Elevation - GE Model  classified as proprietary but is available 7700                              for examination at our office.
PSE&G considers this equipment to be qualified.
51          IV    Hydrogen Recombiner located in    Documentation has been classified as Containment - Westinghouse Model  proprietary but.is available for examination at our office. PSE&G is awaiting results from Westinghouse on aging specifications.
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 has reaffirmed that plant safety is not affected pending qualification for aging.
42          IIC    American Insulated Wire            PSE&G is presently undergoing a review, which will extend the qualified life.
PSE&G is presently undergoing a review, which will extend the qualified life.
D6/9 13
QUALIFICATION STATUS PSE&G E. Q. File EQ-14
_J
_J  


UNIT 2                                                                                                                        Attachment 2 ITEM CATEGORY              DESCRIPTION                                      ACTION                                    OUALIFICATION STATUS NO.
UNIT 2 ITEM NO.
1         IIA RC Hot/Cold Leg Narrow Range         -Will be replaced next Unit 2 refueling outage Temperature - Rosemount Model           with qualified RTD 176KF RTD IIA  RC Hot/Cold Leg Wide Range           Replaced with qualified Conax RTD                     PSE&G is in the process of reviewing Conax's 2
1 2
Temperature - Rosemount Model 176KS                                                          Environmental Qualification Report and should RTD                                                                                          be finished by 8/1/83.
13 14 17 18' 19 CATEGORY IIA IIA I8 I8 IB
13          I8  Local Control of MS167 Hydraulic Pump -Removed from the control circuitry
!IA D6/14 1 & 2 DESCRIPTION RC Hot/Cold Leg Narrow Range Temperature -
                  - Micro Switch Model 910 PGD533 14          I8  Local Control of MS167 Hydraulic Pump -Removed from the Control circuitry
Rosemount Model 176KF RTD RC Hot/Cold Leg Wide Range Temperature -
                  - Cinch Jones Terminal Block 17          IB Auxiliary Feedwater .Flow - Square    Relocated to a mild environment Root Extractors 18' 19      !IA  Pump Motors located in Auxiliary      -FRC had four questions regarding the Building                                qualification of motors:
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.
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.
lAf Our analysis of WCAP 8754 contained in PSE&G EQ-16 Report identified an anomaly concerning insulation thickness.
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.
Westing-house answered our question via a {{letter dated|date=March 24, 1981|text=letter dated March 24, 1981}} contained in E0-15 volume 2 Tab 15.05.
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,
Westinghouse has* used only thermolastic epoxy insulation in their nuclear motors.
                                                              " ... 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.
Therefore, these motors do have thermolastic epoxy stator insulation.
D6/14 1 & 2
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
UNIT 2  
~                                                                     ACTION                    QUALIFICATION STATUS CATEGORY              DESCRIPTION
~  
~
~ CATEGORY 18, 19 (Continued)
The second splice was originally made 18, 19 (Continued)                                  with Okonite splice kits. Since FRC did IIA                                    not question the Okonite qualification, we assume that it was acceptable.
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.
PSE&G will verify the splices on all motors.
: 30) The insulation class was not stated.
: 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.
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.
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.
The curve is equal to or greater than the requirement of Class F insulation 4Q) The installed grease (bearing) lubricant was not identified.
Fan Cooler Motor located in -FRC had 3 questions regarding the 50        IIA containment                    qualification of the motors:
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.
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.
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 /
Westinghouse answered our question via a {{letter dated|date=March 24, 1981|text=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.
has used only thermolastic epoxy insulation in their nuclear motors.
Therfore, these motors do have thermolastic epoxy stator insulation.
Therfore, these motors do have thermolastic epoxy stator insulation.
Line 170: Line 279:
: 30) The motor insulation class and type were not stated.
: 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.
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.
Westinghouse answered our question via a {{letter dated|date=March 24, 1981|text=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.
Therefore, these motors do have thermolastic epoxy stator insulation.
QUALIFICATION STATUS
_J
_J


UNIT 2 ITEM NO. CATEGORY               DESCRIPTION QUALIFICATION STATUS 90           !IA   Motorized Valve Actuator       PSE&G is presently reviewing this item.
UNIT 2 ITEM NO.
Limitorque SMB Motors          Results should be available 10/1/83.
CATEGORY 90  
91          !IA    Motorized Valve Actuator      PSE&G is presently reviewing this item.
!IA 91
Limitorque SMB Motors          Results should be available 10/1/83.
!IA 97
97          !IA    Rockbestos Electrical Cable -  FRC stated that PSE&G did not identify cable     PSE&G E.Q. Report # E0-07 Firewall SR                    with respect to:     wire size, arrangement of conductors, fillers, binders, etc. & rated characteristics.
!IA 44
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.
!IA 06/14 5* & 6 DESCRIPTION Motorized Valve Actuator Limitorque SMB Motors Motorized Valve Actuator Limitorque SMB Motors Rockbestos Electrical Cable -
                                                  -FRC had several questions concerning the         PSE&G E.Q. Report #34 several types of 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.
44          !IA  Boston Insulated Wire          lQ) PSE&G has not provided information either Bostrad 7E Insulation                on the SCEW sheets or in analysis E0-05 Bostrad 7 ESPE Jacket                to establish that the installed cable constructions are the same as those constructions which successfully passed a test which envelopes the required Salem Parameters.
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.
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.
Analysis of that report is contained in EQ-34.
Boston Insulated Wire          2Q) The report also refers to F-C3859-l for Bostrad 7E Insulation                test results. Report F-C3859-l is a Bostrad 7 ESPE Jacket                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 06/14 5* & 6                                            successfully passed test while other cable constructions did not.
A {{letter dated|date=May 24, 1982|text=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                                                             ACTION                    QUALIFICATION STATUS NO.     CATEGORY DESCRIPTION 2A) The questionable cables reported on page 44  (Continued)
UNIT 2 ITEM NO.
Si: are for multi-conductor flame IIA retardant XLPE and single conductor
44 CATEGORY (Continued)
                                              #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.
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:
lQ) Report B912 (170S) is a test summary           PSE&G E.Q. Report EQ-27 Boston Insulated Wire XLPE Coaxial Cable          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.
are for multi-conductor flame retardant XLPE and single conductor  
lA) This is covered by EQ-27. That report shows three separate sets of testing.
#16EPR cable.
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.
The BIW part number indicates that the cables were laboratory test samples (LSS number Vs a part number).
Boston Insulated Wire  lQ) Report 8913 is a summary report of BIWF Fluoropolymer            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.
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.
lA) The cables in qu~stion are not insulated with BIWF Fluoropolymer.
D6/14 7 & 8
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
CATEGORY              DESCRIPTION                                             ACTION                                  QUALIFICATION STATUS 44          IIA  Boston Insulated Wire                           lQ) Descriptions of cable constructions All                                                  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.
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 -
3,22,25        IB            Various                              Replaced all with ASCO NP Series Solenoid       Valves have undergone a successful 35,61,71,                    Solenoid                              Valves.                                         qualification program;    PSE&G has test report 72,73,74,                    Valves                                                                                and will review it by 10/1/83 75,76,77 78,79,80, 81,83,84, 85 82, 92        IB            Various                              Replaced all with ASCO NP Series Solenoid       Valves have undergone a successful Solenoid                              Valves", save SV0621, SV0624, SV0627, SV0630,   qualification program;    PSE&G has test report Valves                                which were deleted from the system             and will review it by 10/1/83 35          IIA            Various                              FRC questioned the status of these valves in Solenoid                              a submerged state. PSE&G has stated that the Valves                                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) 5,8,15,32      IB  Various Pressure Transmitters                  -Replaced with Rosemount Model 1153D pressure   Model has been successfully qualified by 57,66,68,                                                          transmitters                                   manufacturer; the qualification test report 69,89,93,94                                                                                                        is not yet available; PSE&G expects to have report reviewed by 1/1/84 16          IB  Various Pressure Transmitters                  -Replaced all except FA-0218, containment       Model has been successfully qualified by Spray Addition Tank Header, with Rosemount     manufacturer; the qualification test report 1153D Pressure transmitters; will replace     is not yet available. PSE&G expects to have FA-0218 next outage with a Rosemount 1153     report reviewed by 1/1/84 pressure transmitter.
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.
65          IIA  Various Pressure Transmitters                  -Will replace PA-0227, PA-7461 and PT-0942     Mode~ has been successfully qualified by with a Rosemount 1153 pressure transmitter     manufacturer; the qualification test report next Unit 2 refueling ?utage.                 is not yet available. PSE&G expects to have report reviewed by 1/1/84 29          IB  Flow/Pressure Control -                        -Relocated to a mild e~vironment (828 Panel, Square Root Extractor                            Switchgear Room, 84' Elevation) 30            IB  Flow Controller                                System redesigned; function is now performed by a mechanical devic.e.
lA) IEEE 383 and IEEE 323 allow the use of representative samples in performing specific testing.
D6/14 9 & 10
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 DESCRIPTION                                              ACTION                  QUALIFICATION STATUS 31             IB Flow/Pressure Control -             -Relocated to a mild en~ironment (830 Panel, E/P Transducer                        Service Water Piping Room)                                                               f' 38            IIA  Motorized Valve Actuator located    PSE&G is presently reviewing latest qualifi-outside containment                  cation data. Results should be available Liniitorque Model SMB, Class B      10/1/83.
UNI'J'. 2 ITEM NO.
Insulation 47            IIA  Rockbestos Electrical Cable          -These cables are not used in safety-related PSE&G E.Q. Report EQ-8 circuits, therefore exempt 52            IIC  Electrical Connections -            PSE&G is presently reviewing this item.
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,
Burndy Model HY Lug                  Results should be available 7/1/83.
: 64. 70,86,88
54              IB  Containment Sump Level - Gems Model  -Equipment was qualified by manufacturer. PSE&G will review manufacturer's E.O. Report.
: 36. 87 IB 36 IIA D6/14.11 & 12 DESCRIPTION Flow/Pressure Control -
LS 800                                                                            by 10/1/83 95, 96          IB  Containment Radiation Detector High  -Replaced with Victoreen Model, which was     PSE&G has Victoreen's Environmental Range - Trapelo Model TA 63A          qualified by manufacturer.                   Qualification Report and will review it by 10/1/83 6f              IB  Hydrogen-Oxygen Analyzer - Bacharach -Replaced with Exosenser model, which has     PSE&G E.O. Report File #33 Model ND                              been qualified.
E/P Transducer Motorized Valve Actuator located outside containment Liniitorque Model SMB, Class B Insulation Rockbestos Electrical Cable Electrical Connections -
67            IB  Auxilliary Feedwater Flow - Square  Relocated to a mild environment Root Extractor 4,7,12,          IB  Various Limit Switches              -Replaced all with Namco Model EA-180 Limit   Namco Model EA-180 Limit Switches are 26,27,28,                                                  Switches                                     qualified by manufacturer (Report QTR-105, 34,36,63,                                                                                              Rev. 3, dated August 20, 1981). PSE:&G E.O.
Burndy Model HY Lug Containment Sump Level -
: 64. 70 ,86 ,88                                                                                          Report.
Gems Model LS 800 Containment Radiation Detector High Range - Trapelo Model TA 63A Hydrogen-Oxygen Analyzer -
: 36. 87          IB  Various Limit Switches              -Replaced all with Namco Model EA-180 Limit   Namco Model EA-180 Limit Switches are Switches, save VC5 & VC6 which used a Namco   qualified by manufacturer (Report QTR-105, EA-740 Limit Switch.                         Rev. 3, dated August 20, 1981). Namco Model EA-740 Limit Switches are qualified by 36            IIA  Various Limit Switches              -FRC had three questions regarding the       manufacturer (Report OTR-111, dated Oct. 2, qualification of Namco EA-180 Limit Switch: 1980). PSE&G E.Q. Report.
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.
: 01) The method used by Salem to seal the Limit Switches.
Al) Conax connectors are used to seal the limit switches from the environment.
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.
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 &
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./
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 D6/14 .11 & 12                                                greater than 8.5*for 22.5 hours.
ft2.
The test was maintained for 4 days.
Plqnt condition called for a pH greater than 8.5*for 22.5 hours.
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~
UNIT 2 ITE:f.I~
NO.       CATEGORY             DESCRIPTION .                              ACTION                                QUALIFICATION STATUS 36     (Continued)                                   03) The length of the qualified life of the IIA                                          limit switches.
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.
A3) PSE&G is, at present, reviewing the latest submittal from Namco and will institute a maintenance/replacement schedule.
43          IIC    Samual Moore Electrical Cable, EPR PSE&G is reviewing the data on cable and will Insulation                        present a qualified life by 10/1/83 *.
PSE&G is reviewing the data on cable and will present a qualified life by 10/1/83 *.
49          IV    Motor Control Center located in    PSE&G considers this equipment to be         PSE&G E. O. File E0-14 Electrical Penetration, Auxiliary  qualified. Some documentation has been Building 84' Elevation 7 GE Model  classified as proprietary but is available 7700                              for examination at our office.
PSE&G considers this equipment to be qualified.
51          IV    Hydrogen Recombiner located in    Documentation has been classified as Containment - Westinghouse Model  proprietary but is available for examination at our office. PSE&G is awaiting results from Westinghouse on aging specifications.
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 has reaffirmed that plant safety is not affected pending qualification for aging.
42          II'C  American Insulated Wire            PSE&G is presently undergoing a review, which will extend the qualified life.
PSE&G is presently undergoing a review, which will extend the qualified life.
D6/14 13}}
QUALIFICATION STATUS PSE&G E. O. File E0-14}}

Latest revision as of 04:43, 6 January 2025

Forwards Schedule for Qualification or Replacement of Unqualified Equipment for Categories I.B,Ii.A,Ii.C & IV Identified in SER on Environ Qualification of safety-related Electrical Equipment
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)
v • d • e


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

  1. 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.

Westinghouse /

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

  1. 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

Retrieved from "https://kanterella.com/w/index.php?title=ML18087A912&oldid=5009855"