ML20154B532
| ML20154B532 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 09/09/1988 |
| From: | Woodward N PUBLIC SERVICE CO. OF NEW HAMPSHIRE, TENERA, L.P. (FORMERLY TENERA CORP.) |
| To: | |
| Shared Package | |
| ML20154B444 | List: |
| References | |
| OL-1, NUDOCS 8809140041 | |
| Download: ML20154B532 (243) | |
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UNITED STATES OF AMERICA '68 EP 12 P157 UNITED STATES NUCLEAR REGULATORY COMMISSION before the m' '^
ATOMIC SAFETY AND LICENSING BOARD !
)
In the Matter of ) i
)
PUBLIC SERVICE COMPANY ) Docket Nos. 50-443 OL-1 NEW HAMPSHIRE, et al. ) 50-444 OL-1 ;
)
(Seabrcok Station, Units 1 ) (On-site Emergency ,
and 2) ) Planning and Safety !
) Issues) .
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AFFIDAVIT OF NEWELL K. WOODWARD I, NEWELL K. WOODWARD, being on oath, depose and say as follows i
- 1. I am an independent consultant retcined by the Applicants to advise them with respect to issues related to :
the environmental qualification of Seabrook Station ;
electrical equipment. I am currently employed by TENERA i L
Engineering Services as a Senior Project Manager. I have j previously testified in this proceeding. An updated f statement of my qualifications and background is attached l
[
hereto and marked "A". I was the Project Engineer responsible for the final content, quality and conclusions of the Environmental Qualification (EQ) Files for Seabrook [
t Station while employed at Impell Corporation, including EQ !
[
Filed No. 113-19-01, Revision 1, which is also NECNP i Exhibit 4 of this proceeding.
8809140041B$$o43 PDR ADOCK O ppg I
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- 2. This affidavit describes the environmental qvalification test program for RG-58 Coaxial Instrument Cable completed by the Applicants on July 22, 1988. I assisted in the planning of this RG-58 cable test, personally monitored each phase of the test, and evaluated the test data and results.
- 3. The RC-58 coaxial instrument cable tested was manufactured by ITT Surprenant and is the same cable supplied to Seabrook Station under Purchase Order No. 9763-006-113-19 (NECNP Exh. 4, Reference 7). The cable test apacimens were cut from a reel of cable stored in the station warehouse.
They were colored black with a red trace and imprinted with a Cable Code of TA6Y. This is the same RG-58 cable addressed in EQ File No. 113-19-01, Revision 1 (NECNP Exh. 4).
- 4. The purpose or the test was to expose the RG-58 cable to the same or more severe environmental conditions that similar cables had been exposed to in previous testing (NECNF Exh. 4, Reference 2). The performance specification for the tested cable (coded TA6Y and colored black with a red trace) is the same as had been previously defined in EQ File No. 113-19-01 (NECNP Exh. 4, Reference 6 and Environmental Qualification Assessment Report (Checklist) Item 21 nnd Note 7). Briefly restated, cable that is colored black with a red trace must only remain intact (i.e., not short to ground) and not fail in a manner detrimental to plant safety when exposed to postulated plant environmental conditions. The cable electrical characteristics which define what constitutes remaining intact are its ability to carry current and load during environmental exposure with no insulation failure resulting in a short to ground. The test measurements that demonstrate cable "intactness" are the continuous application of voltage and current during the LOCA simulation such that the leaking / charging current does not exceed one (1) ampere as monitored by a one (1) ampere breaker in the tent circuit, and the ability of the test specimens to withstand a high-potential voltage withstand test at a rate of 80 VAC/ mil of primary insulation thickness af ter all other sequential (i.e., thermal and radiation aging and LOCA) testing was complete.
- 5. During the LOCA simulation test, if the cable insulation degrades to the point of failure (does not remain intact),
the current will increase above one (1) ampere as it flows !
I through the insulation and shorts to ground, and the breaker I
will open. This insulation degradation is permanent and irreversible,
- 6. The high-potential voltage withstand test is not performed under accident environmental conditions. This test ,
provides a basis to assess the overall performance of the cable once all environmental exposure is complete. This is a potentially destructive test where the cables are charged with 3,200 volts while immersed in water. Test results of no i
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. i cable failure (i.e., short to ground) demonstrate that no insulation failure occurred during the environmental testing, '
and this is further proof that the cable will remain intact when exposed to the Applicant's environmental conditions.
- 7. The cable was tested at NTS/Acton Laboratories in Acton, Massachusetts and at Isomedix, Inc. Whippany, New Jersey.
The procedure is NTS/Acton Procedure No. 24843-89N, Revision 1, June 22, 1988 and the final Test Report is NTS/Acton Report No. 24843-89N-2, July 22, 1988 (References 10 and 2, respectively, of EQ File 113-19-02, attached hereto and marked "B"). A summary of the test program preparation, completion and an evaluation of the results is set forth below.
- 8. The test program was based on the environmental testing of similar cables in EQ File 113-19-01 (NECNP Exh. 4, Reference 2), and the conclusions and analyses in that EQ File that support the qualification of this cable for use in Seabrook Station. The environmental parameters to which the RG-58 cable was tested were the same or more severe than those applied in the previous test (NECNP Exh. 4, Reference 2). A summary comparison of the two test programs is as follows:
4 NECNP Exh. 4 NTS/Acton Report Reference 2 No. 24843-89N-2
- a. Thermal Acinct Temperature (*F/'C) 302/150 320/150 Duration (hours) 168 168
- b. Radiation Acina Total Integrated Dose (rads) 2.2 x 108 2.2 x 108
- c. LOCA Simulatient l
i Feak Temperature (*F) 390 420 i Peak Pressure (PSIG) 113 115
- 9. As the Applicants' independent consultant, I monitored l and managed all phases of the RG-58 cable test program, witnessed the recording of data at critical points, and evaluated the final results. I also prepared Revision o of EQ File No. 113-19-02, attached hereto and marked "B",
wherein the environmental qualification of the RG-58 cable is now evaluated and satisfactorily documented for use in seabrook Station. The following is a summary of the evaluation results regarding the test program and the bases for concluding that this testing is acceptable documentation in support of the environmental qualification of the RG-58 coaxial instrument cable for Seabrook Station.
- a. The cable tested is the identical cable installed in the plant. The results of this test verified O
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the statements of similarity used as the basis for l
qualification of this same cable in EQ File l No. 113-19-01 (NECNP Exh. 4). ;
l b. A baseline measurement of insulation resistance [
(IR) was made prior to the start of any testing. A !
comparison of the baseline data to the data l L
i recorded after the thermal and radiation aging !
l tests shows only minute changes in the IR rtadings.
l l Therefore, very littic degradation occurre/..
l L
- c. Once problems associated with the test circuitry i were resolved, the test specimens remained f
energized with voltage, and leaking / charging current did not exceed one (1) aspere throughout ;
the LOCA test. During the margin transient (first .
transient) portion of the test, problems with the test circuitry were observed. The in-line one (1) ampere fuse blev and when replaced, continued to blow whenever power to the cables was reapplied.
However, insulation resistance (IR) and continuity readings taken for all samples showed that the cable insulation had not degraded; therefore, problem resolution centered on the test circuitry.
At this time, it was observed that the ambient
's .
temperature of the test circuitry (i.e. , wire, conns 1tions, fuses and resistors), the monitoring equipment, and IR bridge was approximately 125'F, as the outside air was about 100'r and the equipment was next to the LOCA autoclave. It was concluded that the internal heating of the entire test circuit and its components was the cause of the problem. All of the test circuitry and i monitoring equipment was moved into an air <
conditioned space prior to the LOCA (second) transient. once moved, the fuse never blew for the remainder of the test, the specimens remained energized with specified voltage and current, and l all IR measurements stabilized. Because the test specimens did not remain energized for the entire duration of the margin transient, the margin I transient was not used as a basis for LOCA qualification. The second, or LOCA test transient by itself was more than adequate to demonstrate cable qualification for specific plant conditions. !
- d. Insulation resistance (IR) varied during the initial high temperature phases of the LoCA test (second transient) but recovered to values within the same order of magnitude (i.e., 109 ohms) as !
9 were recorded prior to the LOCA transient. This variation in IR with temperature is typical of many cable tests and was in fact observed in the EQ File No. 113-19-01 test (NECNP Exh. 4, Reference 2). At no time did any shorts to ground occur. After the LOCA test, a visual inspection of the cable showed that a slight darkening of the outer jacket had occurred and that the samples had stiffened; however, no cracking or insulation failure was evident. It was concluded that no insulation failure occurred, no short to ground resulted, the cable carried continuous voltage and the leaking / charging current did not exceed one
, (1) ampere. Therefore, the cable will remain intact in Seabrook Station and not fail in a manner detrimental to plant safety when exposed to postulated worst casa environmental conditions.
- e. In accordance with IEEE Std. 383-1974, a high-potential voltage withstand test was administered to the cable specimens subsequent to the completion of all sequential environmental testing (i.e.,
forty (40) years of simulated thermal and radiation aging, one (1) year of simulated accident radiation exposure, and the equivalent of one (1) year of i
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9 LOCA and high humidity simulation). Voltage was applied to the specimens at a rate of 80 VAC/ mil of insulation thickness while there were immersed in water, and all specimens withstood the test potential. Therefore, no insulation failure occurred during the environmental testing and this is further proof that the performance specification "remain intact" was met.
- 10. In conclusion, the exact RG-58 coaxial instrument cable supplied to Seabrook Station and qualified by similarity to RG-59 and RG-11 coaxial cable in EQ File No. 113-19-01 (NECNP Exh. 4) was tested to the same or more severe environmental conditions than those to which the RG-59 and RG-11 cable were tested (NECNP Exh. 4, Reference 2). The test program was conducted in accordance with the guidelines of IEEE Std. 323-1974 and 383-1974. The results show that when the RG-58 cable was exposed to test conditions designed to emulate the conditions to which similar cables were tested, the cable performed in a similar fashion, and therefore, the basis for the original similarity argument in EQ File No. 113-19-01 has been conclusively established. The RG-58 cable passed all tests, met established performance specifications, and will perform its function as required and not fail in a manner detrimental to plant safety when exposed to the harsh i
environmental conditions occurring subsequent to design basis events.
Of Y , f.) c84 Newell K. Woodward Datedt September 9, 1988 Then personally appeared Newell K. Woodward, before and personally known to me, who, being first duly sworn, made oath that the foregoing statements are true to the best of his knowledge, information, and belief.
YJif u 'f II sl!kt,th Notary Public fi My Commission Expires: UfO'/[?
i WOODWARD AFFIDAVIT ATTACHMENT A NEWELL K. WOODWARD Senior Project Manager Education B.S. Charter Oak College Mechanical Engineering Major, University of Hartford Nuclear Engineering, U.S. Naval Nuclear Power School Summarv of Excerience Mr. Woodward has been associated with the commercial and naval nuclear power industry for over eighteen years. He has extensive experience in nuclear power plant design, licensing, construction, operation, maintenance, refueling and emergancy preparedness. He has supervised the design, procurement, installation, test, operation, maintenance and repair of nuclear power plant mechanical and electrical equipment. He has managed and performed technical work on various multidisciplinary issues including reactor vessel low temperature overpressure protection, equipment qualification and system interaction. Mr. Woodward has prepared testimony and been an expert witness in Atomic Safety and Licensing Board Hearings for PWR and BWR plants. He has also prepared plant operating and maintenance procedures, technical specifications, offsite emergency preparedness plans and procedures and prepared and given training courses and seminars on nuclear plant systems and equipment and regulatory and technical issues.
1986 - Senior Project Manager, TENERA Operating Company, L.P.
present (formerly TERA Corporation). Responsible for the management and technical performance of engineering projects in the areas of Equipment Qualification and Corrective and Preventive Maintenance, Fire Protection and Mechanical, Electrical, and Nuclear Engineering.
1980-86 Technical Manager, Systems Engineering, Impell Corporation. Responsible for the technical development and management of programs and services with respect to equipment qualification and systems engineering.
Supervising Engineer, Systems Engineering, Impell Corporation. Responsible for the management and technical performance of electrical and mechanical equipment qualification programs for PWR and BWR plants. Efforts associated with these programs included master equipment list preparation and reviewt system, equipment, and subcomponent part failure modes and effects analyses; in-plant field verification
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valkdowns; postulated environmental parameter ,
definitions qualification analyses and auditable t documentation file preparation; emergency operating ;
procedure review, licensing submittal preparation; preparation of justifications for continued plant l operation; NRC audit support and ASLB expert witness
! testimony; specification and evaluation of preventive I maintenance requirements; maintenance and surveillance .
program and procedure review and revision; independent [
prgram and documentation file reviews; and impact ;
I reviews of NRC I&E notices and bulletins. Other associated efforts included the completion of a polymer material degradation study with respect to radiation i
i and temperature in support of ASLB hearings for a BWR plant, and the preparation and presentation of equipment qualification training programs to utility ,
i
! management, engineering and technical personnel, i
Lead Senior Engineer, Systems Engineering and Licensing, Impell Corporation. Prepared Pre-Construction Safety Analysis Reports for auxiliary and component cooling water systems based on event and I fault free analyses for a British PWR plant.
Senior Engineer, Management Services, Impell Corporation. Prepared offsite emergency plans and procedures for Rockland and Orange Counties surrounding Indian Point. During the course of this assignment, Mr. Woodward interfaced with state and county officials as well as utility representatives in the development of offsite emergency plans and procedures.
1976-80 NSSS Design Engineer, Combustion Engineering, Incorporated. Responsible for the engineering analysis and technical support of special projects relating to the design and licensing of the Nuclear Steam Supply System (NSSS), secondary feedwater and steam supply systems, and auxiliary systems' interfaces. Specific efforts included the analysis, design, installation, operation and licensing of system backfits related to the reactor vessel low temperature overpressure protection issue, ATWS analyses, NSSS and auxiliary feedwater system design reviews, and technical specification preparation. Other efforts included participation in EPRI sponsored component failure and root cause analysis programs, the training of nuclear plant operators in the low temperature overpressure protection issue and an assignment to the Technical 2-l r
l Advisory Group at Three Mile Island subsequent to the ,
March, 1979 event.
1974-76 Senior Quality Control Inspector, Morrison-Knudsen company. During the overhaul, modification and refueling of several Naval Prototype PWR plants, Mr.
Woodward was responsible for monitoring and certifying !
reactor plant servicing procedures; nuclear and non-nuclear welding and brasings system and component testing, and pressure vessel and fuel lifting and handling equipment.
Shift Refueling Engineer, Morrison-Knudsen Company.
Responsible for the preparation of reactor plant servicing procedures and for supervising the l performance of various reactor plant modifications and ,
refueling cycles.
Purchasing Agent, Morrison-Knudsen Company. Specified, i procured, and expedited nuclear and non-nuclear t
n materials, parts, and equipment.
1968-74 Machinist Mate First Class, US avy. Mr. Woodward was qualified as an Engineering Watch Supervisor and was i the Machinery Division Leading Petty Of ficer on a .,
nuclear powered submarine.
Professional Affiliations Pi Tau Sigma, Mechanical Engineering Honorary American Nuclear Society +
American Nuclear Society Standards Committee ANS 56.3 Technical Presentations l A Short Course on Advances in Equipment Qualification for Nuclear !
Tacilities, Paris, Trance, March 1983. (
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NEWELL K. WOODWARD !
Summary of Environmental Qualification Excerience l
Plant (s) Ernerience summary Shoreham Nuclear Project Engineer for NSSS equipment Power Station Environmental Qualification Program (Long Island (RUREG-0588 Cat. I & II). !
Lighting Co.)
. E.Q. File preparation for electrical and ,
mechanical equipment. j
. Preparation of mechanical equipment Master List.
. Verification of electrical equipment Master List.
. Field Verification Walkdown for NSSS and BOP equipment.
. Review of Emergency Operating Procedures. ;
. Specification of qualified replacement equipment.
. Audit of vendor maintained qualification r documentation. !
. Preparation and review of Justifications i for Continued Operation. l
. Impact review of I&E Notices and Bulletins.
. NRC audit and regulatory support.
. Atomic Safety and Licensing Board (ASLB) f expert witness testimony. j i
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Plant (s) Ernerience Summary Seabrook Station Project Engineer for NSSS and (Public Service BOP equipment Environmental Company of New Qualification Program Hampshire / Yankee (NUREG-0588 Cat. I)
Atomic Electric company)
. E.Q. File preparation for electrical and mechanical equipment.
. Preparation of mechanical iquipment Master List.
. Verification of electrical equipment Master List.
. Field Verification Walkdown of all equipment.
. Review of I&E Notices and Bulletins.
. Specification of qualified replacement equipment.
. Preparation of Environmental Qualif$ cation Report (Program Description for NRC submittal)
. Audit of vendor maintained qualification documentation.
. NRC audit and regulatory support.
. ASLB expcrt witness testimony.
Three Mile Island Project Engineer / Technical Advisor Unit 1 and oyster for NSSS and BOP equipment Creek Nuclear Environmental Qualification Program Generating Station (NUPEG-0588 Cat. I and DOR Guidelines.)
(GPU Huclear Corp-oration)
. E.Q. File preparation for electrical equipment.
6 L
l Plantfa) Ernerience summarv i
. Verification of electrical equipment i 1
Master List.
(
. Field Verification Walkdown (OCNGU ,
only.)
]
. s;picification of quali:21ed replacement I equipment.
I
. Audit of vendor maintained qualification documentation. !
. Review of I&E Notices and Bulletins. '
. NRC audit and regulatory support.
Susquehanna Steam Project Engineer for E.Q. File I
& Electric Station, Independent Review Program (NUREG-0588 Cat.I& i Unit Nos. 1 and 2 II.)
(Pennsylvania Power )
& Light Company) i
. Written review of electrical equipment 1 E.Q. Files. i I
. NRC audie and regulatory support. !
Technical reviewer for correction of E.Q. !
File deficiencies, j Auditor for Quality Assurance ;
l Comanche Peak Steam i and Electric Station ,
I (TU Electric) . Performed a technical audit of the E.Q. l I
Program, including master list and environmental parameter design bases, !
E.Q. files, and plant implementation.
l Beaver Valley Power Project Engineer for E.Q. File Station, Unit No. 1 Independent Review Program j (Duquesne Light Co.) (DOR Guidelines.) [
l Written review of electrical equipment j E.Q. Files.
Beaver Valley Power Project Engineer to: NSSS and BOP Station, Unit No. 2 mechanical equipment (Duquesne Light Co.) Environmental Qualification Program I
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. E.Q. File preparation for mechanical equipment.
. Preparation of mechanical equipment Master List.
Perry Nuclear Power Project Engineer for Polymer Degradation Plant (Cleveland Study prepared in response to ASLB Intervenor Electric Illuminating questions regarding the degradation of company) polymer materials in elevated temperature and low level radiation environments. Work scope included the preparation of ASLB testimony.
Project Manager / Technical Advisor for a class I-E cable test program. Including preparation of test plan and final report.
Donald C. Cook Project Engineer for Thermal Aging and Nuclear Plant Surveillance / Maintenance Evaluation Program Unit Nos. 1&2 (DOR Guidelines)
(Indiana & Michigan Electric Company /
American Electric Power Service Corp.
. Thermal aging life determination for NSSS and BOP electrical equipment
. Written review /ovaluation of plant programs and procedures with respect to the implementation of E.Q. related maintenance and an "on-going" qualification program.
. Preparation of Plant Manager Instruction for Environmental Qualification of Safety-related Electrical Equipment.
. Indian Poi,:- Station, Project Engineer for an E.Q.
Unit No. 2 Training Program for management, (Consolidetad Edison engineering, and plant technical personnel.
Company of N.Y.)
Auditor for Quality Assurance. Performed an audit evaluation for completeness and technical accuracy of E.Q. Files. Effort included reviewing implementation of E.Q.
into plant maintenance and procurement procedures.
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t James A. Fitzpatrick Project Manager / Technical Advisor Nuclear Plant for the preparation of an E.Q.
(New York Power File for the HPCI Turbine Assembly (DOR Authority) Guidelines.)
Davis-Besse. Unit Project Engineer for NSSS and BOP No. 1 (Toledo equipment Environmental Qualification Program Edison Company) (NUREG-0588 Cat. 1 and DOR Guidelines.) (9 month interim period only)
Addressed technical issues relating to the revision of E.Q. Files to resolve open items.
. Revision of E.Q. Files r
e WOODWARD AFFIDAVIT ATTACRMENT B ELECTRICAL EQUIPMENT QUALIFICATION FILE NO. 113-19-02 CONTENTS
- 1. Equipment List
- 2. Equipment Summary Evaluation
- 3. Qualification , Evaluation Worksheet
- 4. Environmental Qualification Assessment Report (Checklist)
- 5. EQ File Attachments 1 through 10 i
k' ,
( 3 Public Service Company of New Hampshire SEABROOK STATION ENVIRONMENTAL QUALIFICATION OF ELECTRICAL EQUIPMENT Electrical Equipment Qualification File No.: 113-19-02 Revision 0 Purchase Order No.: 9763-006-113-19 Manufacturer: ITT Surprenant Model Number: RG-58 Coaxial Equipment Type: Instrument Cable
/ / i t'I Prepared By h
b)(Yt't<Muh $ $h date
\fL ~5 Checked By Q c}l$fSti Date Nnl suu 9 Y-18 Approved Byd ' 6 ate
% l & e lf? if .f Man,/ger of Engine / ring Approval Date L J l
Electrical Equipment Qualification File No. 113-19-02 Revision 0 -
Record of Revisions Revision _ Description 0:te 0 Original Issue 09/06/88 t
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0005L Page 2 of 3 :
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Electrical Equipment Qualification File No. 113-19-02 Revision 0 TABLE OF CONTENTS Title Equipment List Equipment Sumary Evaluation Qualification Evaluation Worksheet Environmental Qualification Assessment Report (Checklist)
LIST OF ATTAf.HMENTS Reference Title
- 1. UE&CSpecifibationNo. 9763-006-113-19 Specification for Specialty Cable, 9/20/82 (Excerpts).
- 2. NTS/Acton Report No. 24843-89N-2. Environmental Qualification Testing of Coaxial Instrument Cables (RG-58)forNHYD/PSNH,7/22/88.
- 3. VU-30454. ITT to UE&C, 8/23/82.
- 4. New Hampshire Yankee Engineering Evaluation No.88-026.
- 5. FSAR, Seabrook Station. Amendment 61. November, 1986 (Excerpts).
- 6. Record of Conversation between Chuck Greiman (UE&C) and N. K. Woodward (Impell), 10/8/85.
- 7. UE&C Purchase Order No. SNH-744, 9763.006-113-19, 10/7/82 (Excerpts).
- 8. SB-92605, UE&C to Impell, 2/13/85.
- 9. Impe11 Letter No. 0570-032-NY-156, Sumary of Class 1E Equipment Submerged as a Result of Design Basis Events.
2/?/86.
- 10. NTS/Acton Procedure No. 24843-89N, Test Procedure for Environmectal Qualification Testing of Coaxial Instrument Cables (RG-58) for NHYD/PSNH, Rev. 1, 6/22/88.
0005L Page 3 of 3
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Electrical Equipment Qualification File No. 113-19-02 Revision 0 EQUIPMENT SUPNARY EVALUATION 1.0 Description The equipr e e under evaluation is RG-58 coaxial instrument cable manufactu.ed by ITT Surprenant Division. This cable may be located in all areas of the plant, both inside and outside containment, and is evaluated for the composite worst case postulated environmental conditions in the plant. The RG-58 cable specified (Reference 1 Appendix A) and provided to the plant under Purchase Order No.
9763.006-113-19 (Reference 7) is marked with the cable code TA6Y and is black in color with a red trace. The RG-58 cable sequentially tested in Reftrence 2 was taken from the Seabrook site and is the same cable supplied to the plant and installed therein.
2.0 Conclusion This equipment is qualified by sequential test for the postulated accident temperature, pressure, humidity, chemical spray and radiation dose time. and Thisby test supplemented equipment by analysis has a qualified for years life of 40 the required operating).
at 1670F(7500 Therefore, this equipment is qualified to the requirements of NUREG-0588, Category I.
3.0 Limitations None.
4.0 Discussion The RG-58 instrument cable that is installed in the plant is coded TA6Y, colored black with a red trace, and used in Train A Associated circuits -
(Reference 1, p. A1, Reference 7, and Reference 5). Its function when exposed to normal and accident environmental conditions is to only remain intact (i.e., not short to ground), and not fail in a manner detrimental to plant safety or accident mitigation (References 5 and 6).
The RG-58 cable specimens tested in Reference 2 were taken from the lot of cable supplied by ITT Surprenant to the plant. Therefore, the tested cable is the same cable installed in the plant. The coaxial cable construction consists of irradiation cross-linked polyethylene insulation, a braided metal shield, and an overall jacket of Exane, which 1:; irradiation cross-linked polyolefin (Reference 1. Appendix B).
0005L Page 1 of 2
Electrical Equipment Qualification File No. 113-19-02 Revision 0
-Continued-Although the RG-58 cable is instrument cable and will carry very low current loads in the plant, the 40 year qualified life has been conservatively evaluated at the design maximum continuous conductor temperature of 7500 (1670F) (Reference 1, p. B1; Reference 3. Item 3 and Reference 2, p. 6-1). i Submergence qualification is not required because these cables are not located in any areas of the plant where they would be submerged subsequent to design basis events (Reference 9).
During LOCA testing, the cable specimens were continuously energized and the 1.0 ampere specified current was not exceeded. The specimens aise withstood a high potential voltage withstand test subsequent to all environmental testing, where the applied potential was 80 VAC/ mil of insulation thickness for five minutes in water. Testing was perforred in accordance with IEEE Std. 383-1974.
A ve'tical tray flame test has been conducted in accordance with Section 2.5 tv IEEE std. 383-1974 (Reference 3. Item 5).
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OUALIFICATION EVALUATION WORK SHEET -
New Hampshire Yankee PrparedBy:['r/
f MY/M" ) Data:
Seabrook St-tf on .
Dochet: 50-443 EQUIPNENT QUALIFICATION FILE NO. 113-19-02 Checked By: OX* M Data: S/0 66
\
Postulated Envirorment Qualtffed Environment QualIfica tion Outstanding favfoment Descrfotton Parameter Talue .I Reference Yalgae Refrerence Nethod Items Furchase Urder No.:
9763-006-113-19 Operating 1 Test and Time 1 Year p. I 1 Year 5 Analysis None Equipment ID No(s).:
EDE-CBL-f4 Peak 1 2 T ature 375 p. I 420 p. 10-9 7est None Peak 1 2 Equipment Type: Pressure 60 p. I 115 p. 10-9 Test None I;strisent Cable (Ps1g)
Manufacturer: Relat1we 1 2 ITT Suprenant Humfdity 100 p. I 100 p. 10-9 Test None (1)
Nodel Nunter:
RG-58 Coaxfal Cheetcal Boric Acid 1 Boric Acid 2 Spray (pH) 1.21 by wt. p. I 1.71 by wt. p. 10-5 Test None pH = 7.5 to 10.5 pH = 10.5 6 Accuracy: Spec: N/A Demon: N/A 40 Year Normal 1 Radta11on Dose 2.0 x 108 p. 3 2 (Rads) Note 1 2.2 x 108 p. 8-2 Test None 1 Year Accident I tfatting Environment: Radiation Dose p. 3 Locction: Contafnment (All Zones) Aging 167/40 3 167/40 2 Test and Rad Zone: Primary Aux. (OF/ Years) (750C ) p. 2 (750C) p. 6-1 Analysis None B1dg. (PS-ISA. PB-18) 4 3 Note 1 p. 2 Lowest Elevation: Note 2 8 Flood Level: Note 2 Submergence N/A Note 2 N/A N/A N/A Mone Above Ficod Level: Note 2 Doc w tatfon
References:
Notes:
- 1. UEE Drawing NO. 9763-F-300219 Revision 19. Service Environment Chart. 9/25/86. 1. The limiting zones for radf ation are P8-15A and
- 2. NTS/Acton Report No. 24843-89N-2. Environmental Qualification Testing of Coaxial PB-18. Iones PB-4 and PB-19 are excluded I striment Cables (RG-58) for NHYD/PSNH. 7/22/88. because no electrical equipment is installed in
- 3. VU-30454. ITT to UEE. 8/23/82. these areas (Reference 7).
4 UEE Spec 1ff cat 1on No. 9763-006-113-19. 9/20/82. 2. Submergence qual 1ffcation 1s not required
- 5. NHY Engineering Evaluation No.88-026 because this equipment is not located in any
- 6. Seabrook E.O. File No. 113-19-02 Assessment Checklist. Note 6. plant area where it would be submerged during
- 7. 580-92605 DESC to Impell. 2/13/85. design basis events. (Reference 9).
- 8. 580-96263 UE K Letter. F1t.eding Study Matriz, 10/25/85.
- 9. Impell Letter No. 0570-032-NY-156. Susanary of Class 1E Equipment Submerged as a Result of Design Basis Events. 2/2/86 Revision 0 0006L Page I of 1
Public Service Company of New Hampshire E0Q0 Assessment Report Seabrook Station E.Q. File No. 113-19-02 ENVIRONMENTAL QUALIFICATION ASSESSMENT REPORT Manufacturer: ITT Surprenant Division Model Number: RG-58 Coaxial Component: Instrument Cable Revig er's Conclusion lXl
-~
Acceptable (i.e., this equipment meets the requirements of NUREG-0588, Category I) l l Acceptable, providing the following special conditions are addressed Special Conditions:
None.
Coments:
None i
Prepared By: / /&([! * "' ch* .
Signature / 06te Checked By: k~ft:. Q. ,2- 9/e/S$
Signature Date Approved By: ~
M/ Signatureo' _.a[ ~
7/S/66
/ Date l
Revision 0 l 0002L Page 1 of 13 1
1 L
Public Service Company of New Hampshire E.Q. Assessment Report Seabrook Station E.Q. File No. 113-19-02 TABLE OF CONTENTS Title g Maintenance Required to Maintain Qualified Life 3 Documents Reviewed for This Report 3 NUREG-0588, Category I Qualification Report Review Checklist 4 Notes 9 LIST OF FIGURES Figure Title Paje 1 Temperature Profile Comparison 13 j
l Revision 0 0002L Page 2 of 13 l
Public Service Company of Ne:s Hampshire E.Q. Assessment Report Seabrook Station E.Q. File No. 113-19-02 MAINTENANCE REQUIRED TO MAINTAIN QUALIFIED LIFE None DOCUMENTS REVIEWED FOR THIS REPORT
- 1. UEAC Specification No. 9763-006-113-19 Specification for Specialty Cable, 9/20/82.
- 2. NTS/Acton Report No 24843-89N-2. Environmental Qualification Testing of Coaxial Instrument Cables (RG-58) for NHYD/PSNH, 7/22/88.
- 3. VU-30454, ITT to UE8C, 8/23/82.
- 4. New Hampshire Yankee Engineering Evaluation No.88-026.
- 5. FSAR, Seabrook Station. Amendment 61, November 1986.
l 6. Record of Conversation between Chuck Greiman (UE80) and N. K.
Woodward (Impe11), 10/8/85.
- 7. UE&C Purchase Order No. SNH-744, 9763.006-113-19, 10/7/82.
- 8. SBU-92605, UE8C to Impe11, 2/13/85.
l 9. Impe11 Letter No. 0570-032-NY-156 Sunnary of Class 1E Equipment Submerged as a Result of Design Basis Events, 2/2/86.
- 10. NTS/Acton Procedure No. 24843-89N, Test Procedure for
[ Environmental Cables (RG-58) forQualification Testing NHYO/PSNH, Rev. of Coaxial Instrument 1, 6/22/88.
- 11. UE&C Drawing No. 9763-F-300219. Rev. 19, Service Environment Chart. 9/25/86.
- 12. UE&C Drawing No. 9763-F.6,01.00.00, Calculation Matrix.
- 13. SBU-96263. UEAC letter Flooding Study Matrix, 10/25/85.
Indicates a generic reference and is not contained in this file.
Revision 0 0002L Page 3 of 13
I Public Service Company of New Hampshire E.Q. Assessment Report Seabrook Station E.Q. File No. 113-19-02 NUREG-0588, CATEGORY ! QUALIFICATION REPORT REVIEW CHECKLIST lYES NO NA REFERENCE l l
- 1. SIMILARITY l 1
- 1. Have all Equipment ID's on X LQEWs the Master List associated l Note 1 with this EQ File number I been addressed in the l l documentation? l l l
- 2. Is the documentation trace- X Reference 2, able to the plant equipment? p. 3-1 Note 1 II. SIMULATED SERVICE CONDITIONS AND TEST DURATION
- 3. Do the temperature / pressure / X See Figure 1 humidity test parameters '
and QEWs meet or exceed the postu- ! Note 2 lated accident environmental I conditions? Make a copy of '
I the test temperature enve- I lope and superimpose it on the required accident envi- ,
ronmental envelope. Assure I l .
I that deviations between the I i two are justified in the l l documentation. l l i i l
- 4. Do the margins of the test X l lSee Figure 1 l -
profiles over the plant I land QEWs specific profiles conform to l Note 2 those suggested by IEEE l 323-1974 and any applicable i daughter standard for this l equipment? I
- 5. Does the test operating time X Reference 4 under the harsh environment i equal or exceed the equip-ment's required operating time? l l l l l l l l 1
l Revision 0 0002L Page 4 of 13
Public Service Company of New Hampshire E.Q. Assessment Report Seabrook Station E.Q. File No. 113-19-02 NUREG-0588, CATEGORY I QUALIFICATION REPORT REVIEW CHECKLIST (continued) lYES NO NA REFERENCE l l l III. RADIATION l l l l
- 6. Does the radiation dose, IX Reference 2 i.e., integrated dose, for p. 8-2 nonnal operations and acci- Note 3 dent dose for the plant, fall within the envelope used in qualification? I l
- 7. Does the total integrated IX '
1 Reference 3. I dose include Beta radiation? '
- p. 2, item 6 (Is Beta radiation ad- .
Note 4 dressed?) J IV. AGING
- 8. Are the thermal aging para- X l Reference 2 meters chosen and used in the' p. 6-1; test supported by adequate l Reference 3 documentation or references? p. 2. Item 3 1
- 9. Was mechanical and/or elec- l X trical cycling addressed? I l
- 10. Is the qualified life (QL) l X l Reference 2, explicitly stated? : p. 6-1; Ref. 3.
- p. 2, Item 3 ,
- 11. Does the qualified life take X Note 5 into account the normal operating state of the equipment (i.e., energized)?
l V. CHEMICAL SPRAY l l
- 12. Does the DBE qualification X IReference 2, testing include chemical p. 10-5 spray?
I l l
- 13. Does the spray concentration l X 1 Reference 2, and pH used in tests meet or I p. 10-5 exceed those to be used for l Note 6 the plant?
l Revision 0 0002L Page 5 of 13
Public Service Company of New Hampshire E.Q. Assessment Report Seabrook Station E.Q. File No. 113-19-02 NUREG-0588, CATEGORY I QUALIFICATION REPORT REVIEW CHECKLIST (continued)
L YES NO NA REFERENCE
- 14. Was the spray testing done X Reference 2, while under the extremes of . pgs. 10-5, 10-7 pressure and temperature?
VI. SUBMERGENCE
- 15. Does the test program include X INote 7 submeraence tests?
VII. SE!SMIC
- 16. Was the seismic' testing / X ' Note 8 analysis done on aged component or equipment?
- 17. Did the seismic testing / X analysis address effects on '
I I age? I ! I l
VI!!. FUNCTIONAL REQUIREMENTS
- 18. Does the test plan / report X Reference 2,
- p. 1-2 specify an acceptance criteria for equipment Note 9 performance?
- 19. Was an initial base line X Reference 2, test done to establish p. 5-1 reference performance char-acteristics?
- 20. Is the accuracy demonstrated X during testing equal to or better than that specified?
- 21. Has the test / analysis esta- X Note 10 blished that this equipment l
can meet plant application l l specific perfonnance re- l quirements? (e.g. accuracy, l response time) l Revision 0 Page 6 of 13
Public Service Company of Nea Hampshire E.Q. Assessment Report Seabrook Station E.Q. File No. 113 19-02 NUREG-0588, CATEGORY I QUALIFICATION REPORT REVIEW CHECKLIST (continued)
- YES NO NA ' REFERENCE l l
- 22. Review the test results on a X ; Reference 2 relative comparison basis :.pgs. 10-2, 10-10 (i.e., performance para- Note 11 meters of the baseline tests ,
versus those during the various tests). Were there any anomalies or major discrepancies?
- 23. If so, was it satisfactorily X Reference 2 explained in the report? I 'pgs. 10-2, 10-10 l Note 11 IX. SEQUENCE
- 24. Was the same test specimen X Reference 2,
- p. 4-1 subject to the entire test sequence including aging tests?
- 25. Compare the test sequence X performed for this report ! l against your understanding l I of what test and procedures 1 are required as per IEEE I l 323-1974 and any applicable I daughter standard for this equipment. Do you believe ,
the report meets the intent of these standards? I l l
X. TEST SET-UP
- 26. Was the test measuring X l Reference 2 equipment (TME) calibration pgs. 8-1, 8-2 & l addressed in the report? 13-1 XI. MAINTENANCE REQUIREMENTS
- 27. Are maintenance requirements X and component replacement intervals specified to 1 -
maintain qualified life?
1
< Revision 0 0002L Page 7 of 13
l Public Service Company of New Hampshire E.Q. A!sessment Report l Seabrook Station E.Q. File No. 113-19-02 NUREG-0588, CATEGORY I OVALIFICATION REPORT REVIEW CHECKLIST (continued) L YES NO NA REFERENCE XII. INSTALLATION INTERFACES
- 28. Have installation interfaces ' X Note 12 required to maintain qualification been identified in the test report? .
If yes, explain in a note.
- 29. Has the actual plant instal- X Reference 9 lation been identified and Note 1 evaluated?
I I I l l l
l l
l l
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Revision 0 0002L Page 8 of 13
Public Service Company of New Hampshire E.Q. Assessment Report Seabrook Station E.Q. File No. 113-19-02 NOTES
- 1. This equipment has the ID number EDE-CBL-6C. Reference 1 (Appendix A) and Reference 7 identify the particular RG-58 cable specified and provided to the plant under Purchase Order 9763.006-113-19. The scope
~of this E Q. File only concerns the RG-58 coaxial instrument cable
- listed in References 1 1.nd 7'(cable code TA6Y). The RG-11 Triaxial and 7 RG-11 and RG 59 coaxial instrument cables shown in References 1 and 7 j are evaluated in E.Q. File 113-19-01.
! The RG-58 cable tested was taken from a reel of cable supplied under
, Purchase Order 9763.006-113-19 (Reference 7) and stored at the Seabrook site. Reference 2, p. 3-1 details the cable tested and shows the same (TA6Y) cable code as specified in Reference 1 (Appendix A) and supplied to the plant (Reference 7). Therefore, the Reference 2 document is the report of actual sequential testing of the same RG-58 coaxial cable used in the plant, j 2. Figure 1 shows a comparison of the worst case (inside containment) a postulated accident' temperature versus time profile (Design Envelope) to the LOCA test temperature profile. The test profile plotted is the second transient, or LOCA test (Reference 2, p. 10-9). The margin
, transient was not plotted because the cable was not completely energized for the duration of this transient due to overheating problems associated with the test monitoring and power supply equipment (Reference 2, p. 10-10). Additionally, the Figure I test profile was plotted with a 40 second shift to the left to envelope'the initial rise of the plant accident profile.
The Figure 1 comparison plot demonstrates that the test was more severe than, and conservatively envelopes, the postulated plant design temperature envelope. Deviations between the test and postulated profile are only for a duration of 150 and 200 seconds and are
, considered insignificant given the test time above 4000F and the '
overall increased temperatures of the test versus the plant profile.
Further, if the actual LOCA/MSLB profile (Reference 11, p.1, Figure 2) was plotted instead of the accident design envelope, then no deviations I would be found. Therefore, the test temperature conditions are considered more than adequate in demonstrating the qualification of the RG-58 cable should it be exposed to the plant postulated worst case harsh environmental temperatures during LOCA or MSLB.
1 The margins of the test over the plant specific profiles suggested by
!EEE Std. 323-1974 for temperature (+150F) and pressure (+10%) were met during testing. Reference 4 shows adequate margin with respect to test
! duration and specified equipment operating time.
i 3. The limiting environmental zones for radiation are zones PB-4, PB-15A, i PB-18andPB-19(Reference 11). There is no Class 1E electrical j equipment in zones PB-4 and PB 19 (Reference 8); therefore, the maximum j
total integrated normal and/or accident radiation dose for which Revision 0
- 0002L Page 9 of 13 i
Public Service Company of New Hampshire E.Q. Assessment Report Seabrook Station E.Q. File No. 113-19-02 NOTES 1 (continued) qualification must be demonstrated is the 2.0 x 108 rads found in zones PB-15A and PB-18 (Reference 11). Per Reference 2, p. 8- the cable testspecimensreceivedaminimumtotaldoseof2.2x10g, rads.
- 4. Total integraded dose has been simulated by exposure to gama field radiation. Beta radiation doses are less significant than gama radiation doses due to the low penetration power of beta in comparison to gamma rays of equivalent energy. Therefore, the ionization caused by gamma radiation will be at least equal to or more severe than beta exposure and the use of a gama field to simulate beta plus gama in-plant exposure is acceptable.
- 5. The qualified life of the cable has been conservatively evaluted at the cable design maximum continuous conductor temperature of 7500 (1670F)
(Reference 2, p. 6-1, Reference 3. Item 3 and Reference 1 p. B1). The RG-58 cable is instrument cable and will only carry very low current loads in the plant. Therefore, the normal operating state of the cable will be one of little or no conductor heat rise, and the use of the maximum continuous conductor temperature to establish qualified life is conservative.
- 6. To convert from parts per million (ppm) of Boron to percentage concentration of boric acid by weight, multiply ppm by the ratio of the molecular weight of boric acid (H3803 ) to that of Boron by 100.
Therefore:
molecular weight of Boric Acid x 100 =
ppm x molecular weight of Boron
_30L0 x 61.8 x 100 = 1.7% H3 B03 by weight 100 T03 .
- 7. Submergence qualification is not required because these cables are not located in any areas of the plant where they would be submerged subsequent to design basis events (Reference 9).
- 8. The seismic qualification of cable is not required by IEEE Std. 383-1974.
- 9. Test acceptance criteria is stated in Reference 2, p. 1-2 based on the requirements of IEEE stds. 383-1974 This criteria is acceptable with respect to demonstrating the satisfactory performance of the RG-58 cable when exposed to plant specific normal and accident environmental conditions. In the Reference 10 (p. 5-2) Test Plan, an additioDal acceptance criterion for the insulation resistance (IR) (1 x 100 ohms) of the primary insulation is also stated for baseline testing. This criterion was used to ensure that the cable specimens were not damaged durin delivery from the plant to the test laboratory. Further, if any IR va ue of less than 1.0 x 106 ohms was measured for the primary insulation during testing, it was evaluated by plant IAC personel, a
Revision 0 0002L Page 10 of 13
Public Service Company of New Hampshire E.Q. Assessment Report Seabrook Station E.Q. File No. 113-19-02 NOTES (continued)
- 10. In the Reference 2 (p. 1-2) test report, test acceptance criteria are identified in accordance with IEEE Std. 383-1974. These criteria were established based on the use of this RG-58 cable as Train A Associated cable in the plant. Reference 1 (p. A1), Reference 7 and Reference 2 (p. 3-1) establish this cable as being colored black with a red trace.
References 5 and 6 establish that this is a Train A Associated cable and the performance requirements are to carry voltage and current (remain intact) when exposed to accident environmental conditions and not fail in a manner detrimental to plant safety. The failure mode is defined as insulation failure resulting in a short to ground of the conductor. The performance requirements are met if the acceptance criteria in the Reference 2 (p. 1-2) test report are met. Further, the insulation resistance measurements made during each test phase and during the LOCA simulation can be compared with the baseline results as an indicator of insulation performance.
An analysis of the test results shows the following:
- a. With the exception of a portion of the initial margin transient, all specimens remained energized with 600 volts and the 1.0 amp specified current. The specimens were not continuously energized during the margin transient because of problems associated with the test setup (Reference 2, p. 10-10).
Further, the margin transient was not used to envelope the plant profile, as sufficient margin existed in the LOCA or second transient (See Figure 1 and Note 2).
- b. The specimens withstood the post-test high potential voltage withstand test with an applied potential of 80 VAC/ mil of insulation thickness (3200 VAC) for five minutes in water after '
being wrapped around a mandrel having a diameter of approximately forty times the cable insulation diameter.
- c. Insulation resistance (IR) showed very little permanent variation from the baseline measurements to the final post 30 day LOCA test results. The IR for several specimens dropped in the range of 10D ohms with one as low as 4.1 x 104 ohms (Speciment #2 9 t = 15.4 hrs.). However, the variation of IR with temperature is a trait observed in many cable tests and was expected. All specimens returned to at least 100 ohms by 18.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> into the test, with values on the order of 109 ohms measured at the end of the test. The low IR values recorded during the margin transient were the result of test setup overheating, as discussed in Reference 2, p. 10-10. Overall, the measured IR demonstrates the integrity of the cable throughout the test sequence.
l l
Revision 0 0002L Page 11 of 13
Public Service Company of New Hampshire E.Q. Assessment Report Seabrook Station E.Q. File No. 113-19-02 NOTES (continued)
In summation, acceptance criteria was defined, plant specific performance criteria was met, and the test results show that the RG-58 cable will perform its function during postulated plant environmental conditions and will not fail in a manner detrimental to plant safety.
- 11. The two anomalies resulting from the test (Reference 2, pgs. 10-2 and 10-10) were due to the rough handling of the test specirens and the overheating of the test monitoring circuit, respectively. Each is adequately described and resolved in the test report, and none of them had any impact on the satisfactory test results.
- 12. Although no specific requirements are specified to maintain the qualification of the cable, it is apparent that qualified splices and terminations are required for the cables to be qualified for use in the plant. The qualification of splices and terminations are addressed as generic items in separate qualification files.
i Revision 0
, 000tL Page 12 of 13 l
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APPENDIX A BILI. OF MATERI AL SEABROGE STATION INIITS 1 & 2 SPECIALTY CABLE (1) (2) (3) (4) (5) (6) (7) (8) (9) (10) MINIMUM TYPE , OVERALL CONDUCTOR SHIELD PURCHASE ITEM CABLE CABLE C00000CT0t JACEET SIZE AMC NUMBER TYPE ORDER QTY- CABLE NO. VOLTACE (FUseCTIOes) COLOR C0thR (STRANO) CDeEUCTORS (COVERACE) FEET CODE
- 1. 2500 vde Triamial N/A Red fl8 (7m) I Braid 25,000 UAlf (ac-II, (901 Min.)
- 2. 2500 vde Triasial N/A White #18 (7m) I - Braid 25,000 tah2t (ac-II, , (901 Min.)
- 3. 2500 vJe Trianial N/A Blue ' #18 (7m) I Braid 7,000 UA3Y (RG-11, (901 Min.)
- 4. 2500 vJe Triasial N/A Yellow #18 (7m) 1 Braid 7,000 4144T .
(ac-II. (901 Min.)
- 5. 2500 vJe Triamial N/A Black With #18 (7m) I Braid 60,000 UA67 (ac-II, Red Trace (901 Min.)
- 6. 2500 vde Commist N/A Black With #18 (7m) I Braid 5,000 TA6T (RC-II, Red Trace (901 Min.)
7pg 7. 1000 vac Coaxial N/A Black With #21 (19m) 1 Braid 60,000 TA6Y-
;;; (ac-58, med Trace (901 Min.)
., g 8. 1000 vac Cosnial N/A Red #24 (7m) 1 Braid 5,000 Tn9T l
?yp (ac-59, (951 Min.)
y y 9. 1000 vac Coaxial N/A lAnite #24 (7m) 1 Braid 5,000 TA2Y
, (ac-59, (951 Min.)
$ 10. 5000 vac Coasial N/A Black With #24 (7m) 1 Braid 5,000 TA6U g[ (mC-59, med Trace (951 nin.)
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--" APPENDII 5 . . _ . . -
SEI.I.ER'S DATA T11 AXIAL COAX 1AL .
- 1) Minimum allowable temperature during installation -30 oC
- 2) Maximum continuous conductor temperature 75 oc
- 3) Maximum emergency overload conductor temperature 130 oC
- 4) Maximum short circuit conductor tesperature 250 oC
- 5) Tercent copper conductivity at 0.'. 96 :
- 6) State if copper conductors are c.ted cr uncoated Ceared
- 7) State the type insulttions . a) by Seller's trade None name and~ * - - - -
b) by generie name Palvethe . : 1ees State the insulatico curing process Irradiation 8) Cross-1(aked Does the stated itsulation coItain fillers? TTS 9) Cive the generie chemical names and purposes of major fillers
- 10) State the type of covers a) by Seller's trade Exane name b) by generic name Polvolefin State the cover curing process Irradiation 11)
Cross-linked Does the stated e d e'r contain fillers? Yes 12) Give the generic chemical names and purposes
- 1 of major -fillers Cive the percentage halogen content of insulation 8' 13) by weight Appendix 3 Spec. No. 9763-006-113-19 Page No. 31 .
?acy of7
" * - - - - -e. = = = = ~
- 14) Cive the percentage halogen content of covers 13.5 %
by weight
- 15) State cable interstices materials by generic names N/A
- 16) Is the conductor ineclation fire-retardant? YES
- 17) Is the completed cable fire retardant? Yts
- 18) Insulation physical & aging properties Tensile strength, unaged, L35./SQ. IN. 1600 Ultimate elongation, unaged- 200 :
Aging 1500C 168 Ers: Tensile Strength, 1400 L35./SQ. IN. , Elongation 150 : Czone resistance after'24'Ers at ozone concentration of 0.025,to 0.030% (I z vol.) Pass
- 19) Insulation electrical properties at room temp. (15.68C) and IPCIA thick-ness Insulation resistance negoba constant 50,000 Dielectric power factor N/A Dielectric constant 2.5
- 20) Electroendoesoais test - Insulation electrical properties at quoted thick-nesses and voltage stress af ter 26 weeks immersion at 900C with a constant negative 600 vott de potential applied (4FCEA EM-60 Method)
Dielectric power factor N/A Dielectric constant N/A Stability factor N/A
- 21) Give the guaranteed' radiation resistance in terus of total integrated rad dose, rad dose rate, cable life in years. Does this radiation resistance include a design basis event? Explain.
(See I.OCA Data) Appendiz 5 Spec. No. 9763-006-113-19 Page No. 32 (L .DY __wa - - -- -. _ _ _
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- 22) CopperMirrorCorrosionTest(ASEED2671)
Insulation, Aging 1210C, 16 Hrs. percent 5 : , transparency Jacket, Aging 1210C, 16 Brs. percent 5 : transparency other organic material (specify) percent N/A : transparency
- 23) State effect of pulling lubricant, MINEARLLAC H-23 (BENTONITE), on cable properties. Applicable to cosz & trias only. Recommend wire tube, y-er or velocity bentonite (ivory snow flakes cheapest & hest)
- 24) State the IPCKA speelfication(s), or other specifications, applicable to the design, manufacture, and testing of the propesed insulation and covers.
MIL-C-17
- 25) Fire Analysis Approx.
Auto ignition temperature of couplete cable, OF 12000F Heating value of combustibles (insulation, j ack e t , fillers etc.) BTU /L3. 9100 State crygen indes of cable insulation, fillers and cover. 27
- 26) Does cable contain sabestos in any form? No
- 27) Cive type and tradename of cable end seal to be provided Dip Seal Plastie - DS 57a9 - Yellow l
Appendix 5 S pe c . No. 9763-006-113-19 Page No. 33 ' n
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c.q . Fac Alo . / G-li-oz. M gereaa e a Test Report No. 24843-89N-2 Page Nos. TEST REPORT FOR ENVIRONMENTAL QUALIFICATION TESTING OF COAXIAL INSTRUMENT CABLES (RG 58) FOR NEW HAMPSHIRE YANKEE A DIVISION OF PUBLIC SERVICE P.O. BOX 300 SEABROOK, NH 03874 Purchase Order No. 61917
, Date 22Iff88 Preparedby:[imoth(/J.
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Rottf, Associate Engineer NTS/Acton 533 Main Street, Acton, MA 01720 pp b [ u- Date 2234 S$ Kdith G. Whittles, Engineering Manager NTS/Acton KT/RPT/2484389N.NH2
Af TABLE OF CONTENTS ERCTION PAGE NO 1.0 PURPOSE AND ACCEPTANCE CRITERIA 1-1
2.0 REFERENCES
2-1 3.0 TEST ITEM DESCRIPTION 3-1 4.0 TEST SEQUENCE 4-1 5.0 BASELINE FUNCTIONAL 5-1 6.0 THERMAL AGING 6-1 7.0 POST-THERMAL FUNCTIONAL 7-1 8.0 RADIATION EXPOSURE 8-1 9.0 POST-Il! RADIATION FUNCTIONAL 9-1 10.0 LOCA SINULATION 10-1 11.0 POST-LOCA FUNCTIONAL 11-1 12.0 RESULTS AND CONCLUSIONS 12-1 13.0 TEST EQUIPMENT LIST 13-1 14.0 PHOTOGRAPHS 14-1 15.0 LOG SHEETS 15-1 16.0 DATA SHEETS 16-1 Report No.24843-89N-2 Page No. 1
i i 1.0 PURPOSE AND ACCEPTANCE CRITERIA 1.1 Purpose The purpose of this document is to descr.ibe the testing which was conducted during environmental qualificat.'on testing of ITT Surprenant RG 58 Coaxial Cable supplied by New Hampshire Yankee. Section 3.0 of this report provides specific identification of the subject test specimens. The intent of the test program is to demonstrate the ability of the coaxial cables to perform satisfactorily during and following exposure to postulated in-service and end-of-life accident environment simulations. As detailed herein, the cable qualification program was conducted in accordance with the guidelines of IEEE Std. Nos. 323-1974 and 383-1974. The tested environmental conditions reported herein are based on the test sequence, duration and f environmental parameters reported in Franklin Research Report No. F-A5550-8. Per the stipulation of New Hampshire Yankee, the vertical flame test described within Section 2.5 of IEEE 383-1974 was not required for any test specimen. The subject program was conducted in accordance with the provisions of NTS/Acton's Quality Assurance Manual. This fact ensured compliance with all pertinent provisions of 10CFR, Part 21, 10CFR, Part 50, 49 and 10CFR, Part 50, Appendix B. Report No.24843-89N-2 Page No. 1_l
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i 1.0 PURPOSfLAND_ACCKETANCE CRITERIA (continued) Ten cablo camplos were submitted f or testing. Six of the ton samples were subjected to aging tests (thermal and radiation aging). The remaining four samples were retained as unaged items to be subjected only to LOCA tests. The LOCA testing was compiated using four aged and four unaged cable specimens. The remaining two aged specimens were set aside as spares prior to LOCA testing.' The eight tested 1 specimena were divided into two groups (specimens 1,2,7 and 8 in Group 1 and specimens 4,6,9 and 10 in Group 2) . the Group 1 specimens were subjected to only the first fif teen days of LOCA exposure. The Group 2 specimens continued though the entire thirty day test duration. This report documents only the testing of the 30-Day LOCA test group. The 15-Day LOCA test ifroup program is documented in NTS/Acton Test Report No. 24843-89N-1. . 1.2 Aqssplance criteria the test s pecimens were considered to have mot the requirements of IEEE STD . 383-197 4, Section 2.4, if they (a) remained energized with client specified potential and current during the steam, chemical-spray, and high-humidity exposure, and (b) passed a final bond test at a diameter 40 times the cable diameter and an ac high-potential-withstand test at 80 V per mil L Roport tio.21 m -nti-1 Page flo. 1_22
1.0 PURPOSE AND ACCEPTANCE CP.ITERIA (continued) 1.2 Acceptance Criteria (continued) 1 of insulation thickness. It was assumed that the first criterion was met if the total leakage / charging current of the specimens connected to an energizing source for potential did not exceed approximately 1.0 A. 1 1 1 I Report No.24843-89N-2 Page No. 1.]
2.0 REFERENCE REGULATIONS AND DOCUMENTS 2.1 New Hampshire Yankee Purchase Order No. 61917. l 2.2 IEEE383-1974 Institute of Electrical and Electronics Engineers, Standard for Type Test of Class 1E Electric Cables, Field Splices, and Connections for Nuclear Power Generating Stations. 2.3 IEEE323-1974 Institute of Electrical and Electronics Engineers, Standard for Qualifying Class Electric Equipment for Nuclear Power Generating Stations, i 2.4 10CFR50 Appendix B - Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants (1973). 2.5 10CFR21 - Reporting of Defects and Noncompliance (1977). 2.6 10CFR50.49 - Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power Plants. 2.7 NEP 160 - Environmental Qualification lEQ) Program. 2.8 Franklin Research Institute Report Number F-A5550-8, j dated January 14, 1983 2.9 HTS /Acton Test Procedure No. 24843-89N, Revision 1 2.10 Attachment 1 to NTS/Acton Report Nurchers 2484 3-89N-1 and 24843-89N-2; four LOCA profile thermal chart recordings. 2.11 Attachment 2 to NTS/Acton Report Numbers 24843-89N-1 I and 24843-89N-2; Visicorder oscillographic recordings t of test item electrical leading during LOCA. 2.12 Attachment 3 to NTS/Acton Report Numbers 24843-89N-1 and 24843-89N-2; Z-Fold Chart Recording of thermal ; aging exposure. ; 2.13 NTS/Acton Test Report Number 24843-89N-1. Report No.24843-89N-2 l Page No. 2-1 r i
3.0 TEST ITEM DESCRIPTION Each cable was inspected upon its receipt at NTS/Acton to document the pre-test condition of each test item. Each item was tagged with a unique identification number. This number remained unchanged throughout the test program. The test specimen description is as follows: Cable Type: RG-58 type coaxial cable with 0.040 inch thick irradiation cross-linked polyethylene insulation and 0.029 inch thick Exane (irradiation cross-linked polyolefin) jacket Manufacturer: ITT Surprenant Cable Code: TA6Y (Seabrook Cable Code) Cable Color: Black w/ Red Tracer i Sample Length: Fifty (50) feet No. of Samples: Ten (10) The test samples were numbered one through ten and were
- divided into test groups as follows
l Group No. Agtd Uneged 1 1, 2 7, 8 2 3, 4 9, 10 3(Spares) 5, 6 N/A I J l I f Report No.24843-89N-2 Page No. 1-1 i
4.0 TEST SEQUENCE Following receipt and inspection, the cables were subjected to environmental and performance testing in the following sequence:
- 1) Baseline Functional
- 2) Thermal Aging
- 3) Post Thermal Aging Functional
- 4) Irradiation
- 5) Post-Irradiation Functional
- 6) Cable Preparation and LOCA Setup
- 7) LOCA Simulation (First 15 Days)
- 8) Post-15-Day LOCA Functional on Group 1 only ,
- 9) LOCA Simulation (Second 15 Days)
- 10) Post-30-Day LOCA Functional on Group 2 only Unaged test specimens 7, 8, 9 and 10 were not subjected to the thermal aging, post thermal aging functional or radiation aging tests. However, these specimens were subjected to post-irradiation functional testing because these functional tests >
were completed after the samples were fixtured in the autoclave prior to the start of the LOCA test sequence. The scope of this report covers the testing on Group 2 test items. NTS/Acton Test Report No. 24843-89N-1 covers testing on the Group 1 test items. Report No.24843-89N-2 Page No. 4-1
l 5.0 BASELINE FUNCTIONAL Subsequent to receipt and inspection at NTS/Acton, the cables were subjected to Baseline Functional Testing. The cables were wrapped around steel mandrels having a diameter of approximately twenty times the cable diameter. Each test item was secured to its mandrel via sager TY25M Tyraps. A minimum cablw length of ten feet was in contact with the mandrel surface. The cable ends were trimmed to permit electrical measurements. 5.1 Continuity check Using an ohmmeter, the conductor and shield of each cable was checked for continuity. The results were recorded on test data sheets (see Section 16.0). 5.2 Insulation Resistance Insulation resistance measurements were made between the center conductor and the shield, and between the shield and the mandrel. The insulation resistance tests were performed by applying a 500 Vdc potential to the conductor for a minimum of one minute, measuring the insulation resistance, and then repeating the test for the shield. The insulation resistance was measured using an I.R. Bridge and the results were recorded on data sheets (see Section 16.0). Report No.24043-09N-2 Page No. 5 1
l 4 6.0 THERMAL AGING Subsequent to the Baseline Functional Test, the cables were l subjected to thermal aging at a temperature of 302'r for 168 hours. The cables were placed in a forced hot air aging chamber as attached to the mandrels. Test Sample Mos. 1, 2, 3, 4, 5 and 6 were in the aging oven during the aging process. Samples 7 through 10 were retained as unaged samples and subjected only to baseline and post-irradiation (pre-LOCA) functional tests and the LOCA tests. Aging temperature was recorded continuously on a strip chart recorder. The thermal aging parameters were based on the following information provided by New Hampshire Yankee I Design Conductor Temp.= 167'r (75'C) ) Weak-Link Material = Irradiation Cross-linked Polyethylene Activation Energy = 1.26ev (150*C) Aging Temperature = 302*r Aging Time = 168 hours Qualified Life = 40 years The listed design conductor temperature, activation energy, aging time and temperature specified are based on existing qualification data provided by the manufacturer for the identical cable insulation and jacketing materials tested in Reference 2.0, Repcrt No.24843-89N-2 Page No. jd
7.0 POST THERMAL AGING FtJNCTIONAL Following completion of thermal aging testing, the test cables were removed from the aging chamber. The samples were observed to be not as pliable as they were prior to the aging process and they were slightly discolored (darkened) . the cable jacket showed no visible signs of crackitig and the cable code, manufacuter's name, model number and rating and red tracer were clearly readable. The samples were subjected to it$antical functional tests as those specified for baseline functional testing, except that the cables and mandrele were submerged in tap water in a 50 gallon plastic drum for a minimum of one hour prior to measuring insulation resistance, and the insulation resistance of the shield was measured between the shield and the water. All i results are included on the data sheets in Section 16.0. l A New Hampshire Yankee representative was present at NTS/Acton to witness the post-thermal aging functional test. i J j Report No. 2 4 8 4 3-89N-2 Page No. 2-1
8.0 PADIATION Subsequent to the post-thermal aging functionals, test samples 1, 2, 3, 4, 5, and 6 were packaged in two cardboard boxes. They were placed carefully in paper insulation to protect the samples during shipping and handling. The boxes containing the test samples were shipped to Isomedix's radiation facility in Whippany, New Jersey and tested in the sealed bcxes. At Isomedix, the specimens were exposed to a Cobalt-60 gamma field at a minimum dose rate of 0.73 x 106 rads per hour providing a minimum T. I .D. of 2.2 x 100 rads. Halfway through the exposure, the specimens were rotated 180 degrees to insure a more uniform dose. Dosimetry was performed using Harwell Red Perspex dosimeters, utilizing a Bausch and Lomb Model 1001 Spectrophoto-meter as the readout instrument, or an equivalent dosimetry system. This system which in calibrated directly with Atomic Energy of Canada, Limited (AECL) is traceable to NBS. A copy of the correlation report is available upon request. Irradiation was conducted at ambient temperature and pressure for the Isomedix facility. A certificate of irradiation is included herein. Report No.24843-89N-2 Page No. M
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10.0 LOCA SIMULATION The following test was performed to simulate the postulated LOCA at the end of the cable service life. 10.1 Calibration Run Prior to performing the LOCA test, a calibration run was performed to demonstrate system capability. The calibration run was performed to the transient conditions. 10.2 Test Fixturina tach cable test specimen was previously wrapped around a steel mandrel whose outside diameter was approximately twenty (20) times that of each test item (Section 5.2). Four aged specimens and four unaged specimens were placed in the LOCA Chamber. The eight specimens were divided into two groups, each group having two aged and two j unaged specimens. I ] Report No.24843-89N-2 Page No. lQ-l s
N , 10.0 LOCA SIMULATION (continued) 10.2 Test Fixturina (continued) The fixtured test units were placed over horizontal metal rails inside NTS/Acton Test Autoclave No. 1. The , loose portions of the cable samples were rested on a horizontal metal perforated plate. The cable ends were trimmed to permit electrical connection to a terminal strip immediately outside the l chamber. The cable specimens were of suf ficient length to [ l
' allow each specimen to be brought through a sealed autoclave t
penetration (three part alumina epoxy) without need for any special connection within the autoclave. The minimum test [ specimen length physically located in the autoclave was 30 ; i 1 feet. Monitoring wires were connected to the terminal block at the chamber and then run to a remote monitoring / load setup in the temperature-controlled LOCA control room. The monitoring setup schematic is included in Section 15.0. Test specimens 1,2,7, and 8 (Group 1) and 3,4,9 and 10 (Group 2) were originally to be fixtured in the autoclave. However, specimens 5 and 6 were inadvertently installed instead of specimens 3 and 4, and specimen 5 was damaged f during fixturing and replaced by specimen 4. i i . i ! l I 1 1 ! , Report No.24843-89N-2 l 1 c Page No. 19-2 !
Y l r I 10.0 LOCA SIMU1ATION (continued) i i 10.2 Test Finturina (continued) l The Inadvertent use of specimens 5 and 6 (designated spares) had no impact on the satisf actory outcome of the test because all of the aged samples (pos. 1,2,3,4,5 and 6) were equally tested to environmental conditions prior to the LOCA sequence. The original designation of specimens 5 and 6 as spares prior to the start of any testing was purely arbitrary. Upon the fixturing of all specimens in the autoclave r and the preparation of the penetrations, specimen 5 was l found to be mangled and its outer jacket, metal shield, l a insulation and conductor severed where the cable is secured ! to the mandrel with the tywrap. This mechanical damage was I judged to be the result of mishandling during iixturing in I j the autoclave because the separation of the metal shield ! and conductor would not be environmentally induced. i Therefore, specimen 5 was removed and replaced by specimen 4' t i f 10.3 Test condition Monitorina NTS/Acton used three (3) Type 'J' thermocouples to monitor the LOCA simulation test. One thermocouple (T 1) was placed approximately 2* from the steam outlet, one i l thc amouple (T2) W88 Placed one inch off the test fixture i Report No.24843-89N-2 L Page Mo. 10-3 , i I
10.0 LOCA SIMULATION (continued) 10.3 Test Condition Monitorina (continued) on the left hand side near the steam outlet, and one thermocouple (T 3 ) was placed on the right hand side furthest from the steam outlet approxJmately one inch of f the test fixture. Autoclave pressure was monitored using a calibrated pressure transducer. All four chamber monitoring channels were continuously recorded on a Gould thermal strip chart recorder. 10.4 Test Ites Ioadina ' The test cable conductors were wired in series and energized with an AC potential of 600v at a test current of 1.0 ampere. The cable shields, mandrel and test vessel were at ground potential. The test circuit was assembled such that the applied potential would be interrupted if the leaking / changing current exceeds approximately 1.0A. This was accomplished by inclusion of an in-line fuse. 10.5 Test Item Monitorina The test items were energized as detailed in Section 10.4 during the LOCA simulation with the following exception: Report No.24843-89N-2 Page No. M
10.0 LOCA SIMULATION (continued) 10.5 Test Item Monitorina (continuard) The circuit was de-energized to perform I.R. measurements as detailed in Sections 5.0 and 7.0, at the following test intervals. (See figure on page 10-7):
- 1) Atter interconnection of the test specimens and placement of the sample sets on the base fixture, test specimens submerged.
- 2) At a test temperature of 346*r, at approximately the 1.5 hour mark.
- 3) At a minimum of once per day during LOCA.
- 4) After LOCA, at ambient conditions, while still fixtured in the autoclave, with the specimens covered wit.h water.
Voltage drop across the monitoring circuit load was monitored continuously during the test and recorded on visicorder paper. 10.6 Chemical Sorav The test cables were subjected to a chemical-spray exposure in accordance with the prof 11e shown in the following figure. Presh chemical spray was used for a minimum of one (1) hour at each dwell at 346*F(174*C); thereafter, the spray solution was recirculated from the pool of solution collected in the bottom of the vessel. The chemical spray l consisted of 3000 ppm boron as boric acid, 0.064 molar Report No.24843-89N-2 l Page No. 10-5 l
10.0 IDCA SIMULATION (continued) 10.6 Chemical Spray (continued) sodium thiosulfate, and sufficient sodium hydroxide to obtain a pH of 10.5 at room temperature. The spray was applied et a total flow rate of 0.63 gal / min, which was calculated to provide a spray intensity of approximately 0.15 (gal / min)/ft2 over the cylindrical area of the mandrels. I i l Report No.24843-89N-2 Page No. 19-1 l
346*F(174'C)/113ths/mI (779tPO 90'T(199'C)/ll3ths/m2 g77 ,gp,) , 199 39e !N$tLAT!!N 346'r(174*C)/ll3ths/mI (779tPa) h RC3 335'T(160*C)/95ths/m I(655kPa) 174 346 ( h 3I7'I(154*C)/70tb[/m (403kPa) {158 {317 200*f(136'C)/351bs/m 2 (24kPO N 130 N g 200 '
.1 230'F(!!0*C)/10 tbs /m (696 d !!0 W 230 '
1 140'T , (A0'C) l--- 3 CNCC g day _ ICA E CM! CAL PRAY M.MID SPRAY CCN31TIONS I 60 140 2.25 10.2 5 DAYS DAYS i 0 12 MIN 3 HR 0 12 MIN 3 HR 5 24 54 246 HR 30 DAYS RCSET TIMER PRCTCST TOP c cs gs ELAPSED TIMC Report No.2_4843-89N-2 Page No. E
New Hampshire Yankee LOCA Test Margin Transient Temp. (deg F) Pressure (psig) 450 , 150 Temperature 400 h - Pressure 350 -
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1 10.0 LOCA. SIMULATION (continued) 10.7 EDCA Gimulation The LOCA Simulation consisted of injecting steam into the autoclave to achieve the temperature / pressure prof 11e shown in the figure. Subsequent to achieving the transient condition the chemical condensate submerged NTS/Acton's ( , immersion heater and saturated conditions were maintained by the immersion heater. All eight specimens were subjected to the margio transient and 15 days of the 30-day LOCA test. At the 15 day mark, the LOCA test was interrupted and both groups of j specimens were subjected to an immersed insulation i 1 resistance test. Group 1 was then removed and subjected to a voltage withstand test. The remaining four samplos (Group :
- 2) were then subjected to the remaining 15 days of the 30-4 day LOCA test.
During the margin transient the in-line fuse blew at ! 3850 s9conds into the test; however, no cable failure could I ] be found. The fuse was replaced and blew again at 5000 t seconds. Again the fuse was replaced; however, it blew P whenever power was applied. Insulation resistance readings taken in all samples showed no failures had occurred and g therefore, the resolution of this problem centered on the t i test setup. t l 4 Report No.24843-89N-2 l Page No. 10-10 ; i s I l
10.0 LOCA .SIMULATIOtt (continued) 10.7 kOCA Simu14115tB (continued) In pursuit of a resolution to the fuse problem, it was noted that the test circuit connections, fuses and resistors, monitoring equipment and IR bridge were all located adjacent to the autoclave in an open area outside of the air conditioned autoclave control room. With outside air temperatures in the order of 100'r and the autoclave operating, the temperature of the air around the equipment c ultry was estimated to be at least 125'r. It was trwtofor concluded that fuss problems were heat related and that all equipment would be moved inside the air conditioned control room after the completion of the margin transient. Once moved into the control room, the fuse never blew during the remainder of the test. Further, the cooling of the IR bridge resulted in stabilized readings. Repo rt No. 2 4 8 4 3-19,ti-1 Page No. 10-11
11.0 POST LOCA FUNCTIONALS Post-LOCA functional testing consisted of immersed insujition resist.ence testing and voltage withstand t ting. e Th'se post-LOCA functional tests were conducted on specimen group two at the end of the thirty days of LOCA test. A New Hampshire Yankee representative was present to witness all Post-LOCA activities and specimen handling. Voltaae Withstand Test The cables were rerooved from the mandrels, straightened and then re-wrapped around mandrels having a diameter of approximately forty times the cable diameter. The cables and mandrels were immersed in tap water and subjected to a voltage withstand test for five (5) minutes at a potential of 80 Vac/ mil (3200 Vac). The leakage current was measured after five (5) minutes of energization and recorded on a data sheet. Report No.24843-89N-2 Page No. 11-1
Y 12.0 RESULTS AND CONCLUSIONS Results Comparison of functional test data for the aged samples and unaged samples shows some acceptable decrease in insulation ability due to the thermal aging and irradiation. Also, during LOCA, some decrease in insulatiori property was observed, however, the insulative ability of the inner insulation recovered to a point which is actually better than the unaged samples. This characteristic has been demonstrated in other cable test programs. The mechanical properties of the aged samples were degraded by exposure to the environmental conditions. It should be acted, however, that the aged samples were handled more than the unaged samples and that despite excess handing coupled with insulation embrittlement, the cables performed satisfactorily. Also, the mandrel diameter used during the test program was slightly less than the minimum bend specified by the manuf.seturer, constituting an overtest of the mechanical properties of the insulation materials. The cable specimens maintained continuity throughout the test program and demonstrated their ability to carry the specified potential and current continuously throughout the LOCA exposure. The inner insulation each of sample 3 withstood a 80V per mil (3200 Vac) liigh potential withstand test. Report tio. 2 4 8 4 3-89ti-2 Pago tio. 12-1
13.0 TEST ECUIPMENT LIST l I I l l Report tio. 2 4 84 3-8 9 tJ-2 Page tio. 1B l
hf TEST EOUIPMENT LIST INVENTORY NUMBER: RE389 ITEM: TEMPERATURE !!ECORDER MANUFACTURER: OMEGA MODEL NO. RD250-24 SERIAL NUMBER: EA59A017 RANGE: -100 TO +4000F ACCURACY: 12.5'F CALIBRATION DUE: 11/88 INVENTORY NUMBER: CH325 ITEM: HI TEMP. OVEN MANUFACTURER: DUVAL MODEL NO. N/A SERIAL NUMBER: CH325 - RANGE: AMBIENT TO 6000F ACCURACY: 120F CALIBRATION DUE: UWCE INVENTORY NUNBER: ZB327 ITEM: MEGORMMETER MANUFACTURER: GENERAL RADIO MODEL NO.: 1862C SERIAL NUMBER: 2477 RANGE 0.5 MEGOMMS TO 2 M MEGOHMS, 100/500 VOLTS ACCURACY: 13% CALIBRATION DUE: 06/88 INVENTORY NUMBER: PA312 ITEM: HI-POT MANUFACTURER: ASSOCIATED RESEARCH MODEL NO.: 404 SERIAL NUMBER: 404570 RANGE: 60 Hz, 0-2.5 KVA ACCURACY: 15% CALIBRATION DUE: 10/08 INVENTORY NUMBER: ML574 ITEM: DIGITAL MULTIMETER MANUFACTURER: FLUKE MODEL NO.: 8840A SERIAL NUMBER: 4382012 RANGE: DC VOLTS: 0-1500 AC VOLTS: 0-750 AC+DC CURRENT: 0-2 AMPS . RESISTANCE: 0-20 MEGOMMS
, ACCURACY: SEE MFGR'S MATUAL CALIBRATION DUE: 11/88 Report No. 24843-89N-2 Page No. J_]-2
INVENTORY NUMBER: PI391 ITEM: DIGITAL PH METER MANUFACTURER: ORION RESEARCH MODEL NO.: 701A SERIAL NUMBER: A52810 RANGE: 6 TO 8 PH ACCURACY: 1.002 PH, 1.1mV CALIBRATION DUE: 05/89 INVENTORY NUMBER: PI402 ITEM: DIGITAL PRESSURE INDICATOR MANUFACTURER: JAY MODEL NO.: 3502-8 SERIAL NUMBER: 10306 RANGE: 0 TO 150 PSI ACCURACY: 11.0 PSI ~ CALIBRATION DUE: 07/88 INVENTORY NUMBER: PI403 ITEM: DIGITAL PRESSURE IND.'CATOR MANUFACTURER: JAY MODEL NO.: 3502-8 SERI AL NUMBER: 10307 RANGE: 0 TO 350 PSI ACCURACY: 11.0 PSI CALIBRATION DUE: 07/88 INVENTORY NUMBER: PI404 ITEM: DIGITAL PRESSURE INDICATOR MANUFACTURER: JAY MODEL NO.: 3502-8 SERIAL NUMBER: 10308 RANGE: 0 TO 150 PSI ACCURACY: 11.0 PSI CALIBRATION DUE: 07/88 INVENTORY NUMBER: PI406 ITEM: PRESSURE GAUGE MANUFACTURER: U.S. GAUGE MODEL NO.: 0-160 SERIAL NUMBER: N/A RANGE: 0 T3 160 PSI ACCURACY: 11.0 PSI CALIBRATION DUE: 07/88 Report No. 24843~B9N-2 Page No. 1)~1
INVENTORY NUMBER: PI415 ITEM: FLOW METER MANUFACTURER: FISHER & PORTER MODEL NO.: 10A1755 SERIAL NUMBER: 8103A1004 RANIE: 0.2 TO 1.9 GPM ACCURACY 13% CALIBRATION DUE: 07/88 INVENTORY NUMBER: PI416 ITEM: FLOW METER MANUFACTURER: FISHER & PORTER MODEL NO.: 10A1755 SERIAL NUMBER: 8103A1004 RANGE: 0.2 TO 1.9 GPM ACCURACY: 13% CALIBRATION DUE: 07/88 INVENTORY NUMBER: PI443 ITEM: PRESSURE TRANSDUCER MANUFACTURER: C.J. ENTERPRISES MODEL NO.: CJDL-4010 SERIAL NUMBER: 1917 RANGE: 0 TO 150 PSI ACCURACY: 12% CALIBRATION DUE: 07/88 INVENTORY NUMBER: PI449 ITEM: PRESSURE TRANSDUCER MANUFACTURER: VIATRAN MODEL NO.: 218-28 SERIAL NUMBER: 173475 RANGE: 0 TO 200 PSI ACCURACY: 1.5% SPAN CALIBRATION DUE: 07/88 INVENTORY NUMBER: TI326 ITEM: DIGITAL TEMPERATURE INDICATOR MANUFACTURER: OMEGA MODEL NO.: 199 SERIAL NUMBERi 19843 RANGE: -245 TO +199'F ACCURACY: 11.5'F CALIBRATION DUE: 07/88 Report No. 24843-89N-2 Page No. 11-1
INVENTORY NUMBER: TI334
. ITEM: DIGITAL TEMPERATURE INDICATOR MANUFACTURER: OMEGA MODEL NO.: 199 SERIAL NUMBER: 19862 RANGE: -245 TO +199'T ACCURACY: 11.5'F CAL 1BRATION DUE: 07/88 ' INVENTORY NUMBER: TI352 ITEM: DIGITAL TEMPERATURE INDICATOR MANUFACTURER: OMEGA MODEL NO. 199 SERIAL NUMBER: 43242 RANGE: -178 TO +1400'F, TYPE "J" 0.1F RESOLUTION ACCURACY: 11.5'T CALIBRATION DUE: 07/88 INVENTORY NUMBER: TI375 ITEM: DIGITAL TEMPERATURE INDICATOR MANUFACTURER: OMEGA MODEL NO.? 650JX SERIAL NUMBER: NONE RANGE: -245 TO +1999'F ACCURACY: 1l'F CALIBRATION DUE: 07/88 s
INVENTORY NUMBER: TP338 ITEM: THERMOCOUPLE PROBE MANUFACTURER: OMEGA MODEL NO.: TYPE J SERIAL NUMBER: NONE RANGE: -300 TO 1600'F ACCURACY: 12.2*F OR t.75% CALIBRATION DUE: 07/88 INVENTORY NUMBER: TP340 ITEM: DUAL THERMOCOUPLE FROBE MANUFACTURER: OMEGA MODEL NO.: TYPE J SERIAL NUMBER: NONE RANGE: -300 TO 1600*F ACCURACY: 12.2*F OR t.75% CALIBRATION DUE: 07/88 Roport No. 24843-89N-2 Page No. M
INVENTORY NUMBER: TP342 ITEM: THERMOCOUPLE PROBE MN,4UFACTURER: OMEGA MODEL NO. TYPE J SERIAL NUMBER: NONE RANGE: -300 TO 16000F ACCURACY: 12.2'F OR 1.75% CALIBRATION DUE: 07/88 INVENTORY NUMBER: TP343 ITEM: THERMOCOUPLE PROBE MANUFACTURER: OMEGA MODEL NO.: TYPE J SERIAL NUMBER: NONE RANGE: -300 TO 1600*F ACCURACY: 12.2'F OR 1.75% CALIBRATION DUE: 07/88 INVENTORY NUMBER: TP352 ITEM: THERMOCOUPLE PROBE MANUFACTURER: OMEGA MODEL NO.: TYPE J SERIAL NUMBER: NONE RANGE: -300 TO 16000F ACCURACY: 12.2'F OR i.75% CALIBRATION DUE: 09/88 INVENTORY NUMBER: RENTAL ITEM: TYPE J THERMOCOUPLE AMP MANUFACTURER: MODEL NO. TYPE J SERIAL NUMBER: 016139B RANGE: ACCURACY: CALIBRATION DUE: 03/89 INVENTORY HUMBER: RENTAL ITEM: TYPE J THERMOCOUPLE AMP MANUFACTURER: MODEL NO.: TYPE J SERIAL NUMBER: 0450970 RANGE: ACCURACY: CALIBRATION DUE: 03/89 Roport No. 24043-89H-2 Page No. 11-E
INVENTORY NUMBER: RENTAL ITEM: DC AMP MANUFACTURER: MODEL NO. SERIAL NUMBER: 1450985 RANGE: ACCURACY: CALIBRATION DUE: 03/89 l l Report No. 24843-89N-2 Page No. 13-7
M5f 14.O PHOTOGRAPHS l l l l [ t l Report No. 24843-89N-2 Page No. M l
S l 4 l 1 1 I Test Specimen Mounting, Steam Inlet Thermocouple Locations, one of Two Spray Nozzles I PRE-LOCA TEST i r t t i I I a I i Report.No. 24843-89N-2
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DAr i j Epoxy Feedthroughs in 12 Inch Side Flange, viewed from Inside Autoclave i i 4 PRE-LOCA TEST SETUP J l t l l l l Report No. 24843-89N-2
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i Report No. 24843-89N-2 Page No. M
hf Epoxy Feodthroughs and Excess Cable POST 15-DAT TEST Report tio. 2 4 8 4 3 -89ti-2 Page tio. 14d
n-15.0 LOG SitEETS Report tio. 2 4 8 4 3-89tt-2 Page tio. 11-1
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b f National Acton O! vision Technical 533 Main Street Systems Acton, MA 01720 DATA SHEET Job Number Dale 7'7'00 Page of Customer Public Servica of fleu Hampshire Speellicallon IEEE 323. IEEE 383. NTS/Acton Test Procedure 24843-89N Test Sample Coaxial instrument Cables ModellSerialNumber RG ER Te t Insulation Resistance Mode of Operation Mandrel 4. (1,/t g, l.R. 9 500 Vdc for 1 minute CABLE NO. l.R. C-S
- I.R. S-M *
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+
Tesi Technician IE oN Test Engineer I N N7 r t.e.s Eucronu:
National Acton Olvision Technical 533 Main Street Systems Acton, MA 01720 DATA SH EET
~
Job Number Date 78*00 Page of Customer Public Service of New Hampshire S ecif cation IEEE 323, IEEE 383, NTS/Acton Test Procedurt 24843-89N Test Sarnple Coaxial Instrument Cables Model/ Serial Number RG 58 Test Insulation Resistance Mode of Operation Mandrel (4, { 1,/t Remarks 1.R. 9 500 Vdc for 1 minute CABLE NO. l.R. C-S * !.R. S-M
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Test Techniclan IE ON Test Engineer I H 7 'T t e S EucroRMJ ,
National Acton Olvision Technical 533 Main Street Systems Acton, MA 01720 DATA SHEET
~
Job Number Oate , 7 *9 80 _Page Customer Public Service of New Harnpshire Specification IEEE 323, IEEE 383. NTS/Acton Test Sarnple Coaxial Instrument Cables Test Procedure 24843-89N ModellSerial Number RG RR Test Insulation Resistance Mode of Operation Mandrel [41f /t Remarks 1.R. 9 500 Vdc for 1 minute CABl.E NO. ' !.R. C-S * !.R. S-M
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bf National Acton Division Technical 533 Mala Street Systems Acton, MA 01720 DATA SHEET Job Number Date 7/O*80 Page of Customer Public Service of New Harnpshire IEEE 323, IEEE 383, NTS/Acton S ecificatloa Test orocedure 24843-89N Test Sarnple Coaxial Instrurnent Cables Model/ Serial Number M 59 Insulation Resistance Te5t Mode of Operation.. Mandrel (4.{1,/t Amarks I.R. 9 500 Vdc for 1 minute CABl.E NO. I.R. C-5
- 1.R. S-M
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' Test Technician I * ; b WE4WS Test Engineer I hH77(e5 CMC FORM
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- s 32g (a932g (ML674 N /
2 3 X 4 Soo Vds
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- C-S: cer ter conductor to shield S-M: sh< eld to mandrel 9 .
l a Test Techniclan NE ON Test Engineer .( M77tGS (McFoRM2
bf Nellonal Acton Olvision Technical 533 Main Street Systems Acton, MA 01720 DATA SHEET Job Number A$0b3~ N Date ? ' 12 b b pag, og Public Service of Neu Hampshire S ecification IEEE 323, IEEE 383, NTS/Acton Customer Test Procedure 24843-89N Test Sainpfe Coaxial Instrument Cables Model/ Serial Number RG 58 Te$t Insulation Resistance Mode of Operation Ma nd rel (41 f,/,
,g, I.R. 9 500 Vdc for 1 minute CABLE NO.
I.R. C-5
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t-M: shi eld to mandrel l . I Test Techalcian I 'N Test Engineer I k NT 3 EMO F0"
Nellonal Acton Olviston Technical 533 Main Street Systems Acton, MA 01720 DATA SHEET Job Number Date 713'80 Page of Public Service of New Hampshire IEEE 323, IEEE 383. NTS/Acton Customer S ec f cation Test Sample Coaxial instrument Cables ModellSerialNum t Te$t Insulation Resistance Mode of Operation Mandrel [4. 4, f,/4 s . I.R. 9 500 Vdc for 1 minute Roma h CABLE NO. I.R. C-5
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Test Technician IE ON Test Engineer . [ k ffTtes cueromur
f \ National Acton Olvision Technical 533 Main Street Systems Acton. MA 01720 DATA SHEET Job Number Date 7'/4" 6 D Page of Customer Public Service of fleu Hampshire Specification IEEE 323. IEEE 383, NTS/Acton Test Procedure 24843-89N Test Sarnple Coaxial Instrutnent Cables ModellSerial Number RG 58 Test Insulation Resistance Mode of Operation Mand rel (4.4 f,lt
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. . Ao m e-h 7I Test Technician **
Test Engineer
- I k N7'TLd3 (McFoRMi
I hhY l National Acton Division Technical 533 Main Street I Systems Acton MA 01720 DATA SHEET 1 Job Number Date 7'/I 00 Page of Public Service of New Hampshire Specification IEEE 323, IEEE 383 NTS/Acton Customer ; Test Procedure 24843-89N Test Sainple Coaxial Instrument Cables Modell, Serial Number RG 58 insulation Resistance Mandrel Tedt Mode of Operation [4. L f,/0. I.R. 9 500 Yde for 1 minute CABLE NO. l.R. C-S
- 1.R. S-M
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Test Technician - N 1 *N Test Engineer I M 7 'T L d 5 EMe romM 2
A9Ar National AClon Olvision Technical 533 Main Street Systems Acton, MA 01720 DATA SHEET Job Number Date l'/ $
- O O Page of Customer Public Service of flett Hampshire Specification IEEE 323, IEEE 383, NTS/Acton Test Sample Coaxial Instrument Cables Model/ Serial Number Te t insulation Resistance [Gt,,, 3,.ur) Mode of Operation Mandrel [4,4,1 j Remarks fruA 'I".P. @ an) of So day 5 1.R. 0 500 Vdc for 1 minute CH M1B eA. Ti 2 41
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Test Technician I *N Test Engineer -[ k N 7 'T t d 5 tucFoRM 5
National Acton Olvision Technical 533 Main Street Systems Acton. MA 01720 DATA SHEET Job Number N Date 7'd'dO Page of Public Service of New Hampshire Customer Specification IEEE 323, IEEE 383. NTS/Acton Test Procedure 24843-89N Test Sample Coaxial Instrument Cables Model/ Serial Number RG 58 Teit Insulation Resistance Mandrel Mode of Operation (4. l f,/0, g g y g4 g gugg 1.R. 0 500 Vdc for 1 minute (sam 645 p o. 7 t m I E A 5 d .) CABl.E NO. l.R. C-S
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Test Technician II oN Test Engineer
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r b National Acton Olvision Technical 533 Main Street Systems Acton, MA 01720 DATA SHEET
~
Job Number Date Page of Customer Public Service of New Hampshire IEEE 323, IEEE 383, NTS/Acton S ecification Test Procedure 24843-89N Test Sample Coaxial Instrument Cables ModellSerialNumber RG 58 Test Insulation Resistance Mode of Operation Pa ndrel
/
( 4. 4, f /, Remarks 80S7" 907AY L oc A . Ramorr I.R. 9 500 Vdc for 1 minute (6 A m Pus.t s 40T m d a GBs b ) CABLE NO. I .R. C-S * !.R. S-M
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National Acton Olvision Technical 533 Main Street Systems Acton, MA 01720 DATA SH EET Job Number Date_ 7./6.6 6 Page of Customer Public Service of New Hampshire Speellication IEEE 323, IEEE 383, NTS/Acton
~
Test Sample Coaxial Instrument Cables Model/Setlal Number Te5t Insulation Resistance Mode of 0peration Mandrel (4. 4. f,/. Remarks b3T 30 NY LOC A I5D d
- 9c%- I.R. 9 500 Vdc for 1 minute (A rre d- l H W R. S o A A)
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Test Technician N ON Test Engineer I h N77LES W: Fo"
National Acton Divlslon Technical 533 Maln Street Systems Acton, MA 01720 DATA SHEET Job Number Date 7/4*88 Page of Customer Public Service of New Hampshire Spec fication IEEE 323, IEEE 383, NTS/Acton Test Procedure 24843-89N Test Sample Coaxial Instrument Cables Model/ Serial Number RG 58 Te$t Insulation Res. stance Mandrel [4,4 f /t Mode of Operation Remarks OOST Se M Y LocA. b ore- I.R. 9 500 Vdc for 2 minute (APTER. l noun. song.) CABLE NO. l.R. C-S
- 1.R. S-M *
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tucFoAM2
National Acton Olvision Technical 533 Main Street Systems Acton, MA 01720 DATA SHEET Job Number 24843-89N Date 7 /4' 8 O Page of Customer Public Service of New Hampshire Specification IEEE 323, IEEE 383, NTS/Acton Test Procedure 24843-89N Test Sarnple Coaxial Instrument Cables Model/SerialNumber RG 58 Test Continuity Mode ol operation Non- operating, unpowered Remarks fost p o D AY L oc A b C HAmam2 j A F rar A / H ou e. S o A w CABLE NO. CONTINUITY ((,7uN4. 5 Hie d 2 N / 2
/ N 4 0.430 c.294 5
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l l I National Acton Olvision l Technical 533 Mah Street Systems Acton, M A 01720 DATA SHEET Job Number bM ~ SY Date )' /b 'O h Page- of Customer I/ N YAhT [6M H Specification N8 P[ 24943 Test Sample @'b (M # ModellSerial Number N 9 CD A*- cad ( Test VJL.W4h#~ (1) ESTM.d @ 3 2 m Va c Mode of Operation - AlNbf@ 4 0 9' A tPts Remarks l'tw at
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Oaar Mr. Ag3arvals ** 8 3 *' //3- / f 6 g/ M/ ,95 jgJ h As a follow-up to our pre-avard seating of August 12th. I have
, tavastigated coveral of your questions and provided the necessary answere below. +
p . A Q'*f*0 -g,1. Provide aztrapolation of M11 triu, to RG11 coax LOCA data
, provided by ITT. ITT Surprenant chose to LOCA test RG11 coax
'(e"2-Q[
, and RC59 coax since they are the two constructions we consi-dered most commonly used by nuclear f acilities. Since LOCA testing is very expensive to the manufacturer, only the best representative omspie of similar constructions :an be feasibly tested. Testing all constructions would be economically un-
. // 79- 0 ( f usible.
337.0 -oI specisteally aadr.sstas Rau triax, we f.1 that our coaxial 1DCA data is nere than adequate. The dimensions of the L1 coax and 11 trias are identical through the first shield. Couple this with the fact that the triaz has an additional soield and jacket of identical material as the shield and jacket of the LOCA approved coaz, and our conclusion is LOCA approval for RCL1 triaz. As additional information. I have enclosed . copy of our .1979 LOCA data when we did hue the RG11 triam approved, tiease note that the only reason we were not able me.use this data, was that we did nor have a main stream line break at 3900T. 3oth RG59U and RG110 coaz are covered by our new data enclosed. , I k's f eel similar concerning R058C/U LOCA appro a1. Since ve have chosen R059 for our LOCA program and have that approval, and RCSS has similar :enst: action details, we are confident i that, had it been submitted, it siso would have been approved. The :lc J2 Ak'O 1000 volt crosslinked ;olyelefin with a hy7alen jacket cable, whi:h we pr: pose to suoply for ite=s 11 6 1 of your inquire vill be ::vered under a separate LOCA appr val.
'.*t i ch we s p e c t to re:atve ft:n T anklin institute v. thin 1 weeks.
I 0% w - -,,
Mr. Cirish M. Aggarval Au gust 23, 1982 Page 2
- 2. Certify thermal aging of LOCA sa=ples.
ITT Surpreaant, hereby, certifies that we did thers41 age, as specified, samplas of all necessary cables submitted to Franklin Institute for St3/LOCA simulation during 1982. *
- 3. 14 sis for pre-aging 150*C for 168 hours.
I have attached a copy of our Arrhenius data show1ng that ,,, .. using a very conservative end of life value of 50: insulation elongation and testing at LS8'C. 136*C, and 12100, the cables t' have a p roj ect ed 40 ye ar lif e of 830C. Our pre-agius L500C , e at 164 hours gives us a 40 year life at 73*C. . s i 4 Aged and Unaged cable samples sust pass the flane test re quir e-seats Para. 2.3.6 (single conductors). Sia is to certify that all , cables RG11 tria2, RC11 ce u. RG59 coax, RC38 coax, and our proposed 2C f 2 AWG cross-lined polyo-lefin inrulated cable pass the stagle conductor flame tests referanced in Para. 2.3.6 for both aged and unaged samples.
- 3. IIII 383 vertical flame teets.
Per IIII 383 Table I vertical flame test refers to Para. 2.5.6. Para. 2.3.6 is the single conductor wire test in accordance with ASTf-D2220-68 referenced above.
- 6. All LOCA test simulation is done with Gamaa rediation, address beta requirement per Para 2.4.1.2 "Radiation Beta" 1.L I 108 RADS over 12 months at a urf mm race of 5.1Il06 g/gg,
- l It is our opin. ion that Cammes radiation is more seiere (penetra-cing) then Beta. We, therefore (worst case) have considered the total dosage to be calative Camma, considering the total camma plus Beta during design basis eveat to be 1.3Il08 RADS.
Ve feel very confident that our referenced coaxial cables can more than withstand both the Casuna rates of exposure and the total exposure. l
- 7. Chemical flow rate 0.42 373.
Since our material was tested using a chemical flow rate of 2.5 spe, we feel 0.42 373 would present no problems.
- 8. Extrapolate 1 year post LOCA.
Our LOCA data previously submitted is only 30 days Ln length. ! Although we have not received final printed reports from Frank in institute, we have received verbal confir=ation that we have I successfully passed our 100 day LOCA submittal. We vill continue P.his testing until 1 year is reached. Oncti tL=e allows the
.anct of the tast we su =it our IR "alves as extrapolated troof
- o. 1 year acceptability. ,
7
?CL (. 6 C) (s
Mr. Girish M. Aggarval Augus t 23, 1982 l Page 3 1 1 ne insulation resistance at the start of ;est was 1120 neg-chas. De insulation resistance af ter 100 days was 1010 meg-ohns. f.xtrapolating this data, our I.R. af ter 1 year would be approximately 700 seg-ches.
- 9. Long-ters water absorption data.
Attached are long-ters vatar absorption data for I.une 20 all vall. , I believe this should answer soet of the outstanding questions. If either yourself or Coorse Morris have additional questions, please , do not hesitate to call. at Ragards, 3
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International Telephont ;nd Telegraph C:rporatna h , .,- - Surprenant 0ivision I12Sternag Street Cnnten. MA 0!S10 ' (617))SS 6331 Telu 930451 TWX110 3471736 "AE*.wAt Act!C CHARAC IXISTICS OF 11 RADIATED CRC $5-ttNK!D P0t.Y!T"-(Y1.!NE 135UtATION. TCt COAXIAL CA3143. USING THE MtRMENIUS TECHNICUE t T*ie therv.a1 aging properties of irradiatM crost-linked polyethylene insulation ' for RG-11 AND 10-39 type coaxial and triszial esbles, were deternised using the Arrhenius technique of accelerated agint, for these materials. 154*C, somgles of tr.sulated conductor were aged in a circulating air even, set at 136 C and 121'C. At intervals depending on aging taaperature, samples of insulated i co iductor, cut f rom the coil of insulatml conductor, were removaHl f rom the oven
.ind cooled to room tempers,ture for several h&urs. The copper was removed and
- tubo of insulation tested for tensile strength and percent elongation on an tron nachine. These results were tabulated versus time of aging at the ,
.espective oves toeparatures. *esting of insulation was continued periodically, depending on the asias rate observed f ree previous dats. The "eed o f lif e" was evcorded who's the persant alongatian was rWuced to 50% of the original value at cash of the aging tsoperatutes. These data points were used to draw line A.
which represents t).e rate of aging for the irradiated cross-linked polyethylene insulation. , 4 t.ine I was ghesi drawn parallel to line A se that it would intercept Seven the 40(y) year days po ttit at 73 C. which ta the desige lif e and temperature rating. at 150*C was selected from line a for pre-aging purposes as noted in Locx report 1179-G1 (November 1979). 9 l CLQ h O 3
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E.Q. File No. I1319 02 Reference 4 Environmental Qualification of ITT Surprenant RG 58 Coaxial Instrument Cable Determination of Post Accident Operating Time By Newell K. Woodward - TENER A. L.P. September 6, 1988 Engineering Evaluatico Num5er 88 - 026 Prepared by (' d u d 4'Y2 f Q -
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'(Da(c) n (t>l(\d Reviewed by s e J b u v ,- _ 'M6 / d
( (Date) Approved by - 2*d.
/ / (Date)
Page 1 of 5
I 1 TABLE OF CONTENTS Seetion Illit fait 1.0 Purpose 3 2.0 Scope 3 3.0
Reference:
3 j 4.0 Method of Analysis 3 5.0 Basic Data and Assumptions 4 , 6.0 Summary Results 4 7.0 Body of Evaluation 4 i LIST OF FIGURES I Figure 1 - Temperature Profile Comparison , i l LIST OF ATTACHMENTS Attachment 1 - NTS/Acton Report No. 24843 89N 2, ! Environmental Qualification Testing of ! Coaxial Instrument Cable (RG 58) for j NHYD/PSNH, 7/22/88 (Excerpts). > Attachment 2 - Impell Calculation No. 0570 032 002, Profile i Extrapolation for ITT Surprenant Instrument i Cable, Revision I,11/5/86. f Attachment 3 - UEAC Specification No. 9763 006 113 19, Specification for Specialty Cable, , 9/20/82 (Execrpts). { t j l i l I i Page 2 of 5 l l
1.0 Puroote To extrapolate the data from the 30 day LOCA test to show that the RG 58 coaxial instrument cable is capable of performing its function for one year from the time of accident initiation.
'T 20 Score The evaluation applies only to the RG 58 cable tested in Reference I and used in Seabrsok Station, Unit No.1.
3.0 Refere9eet
- 1. NTS/ Action Report No. 24843 89N 2,' Environmental Qualification Testing of Coaxial Instrument Cables (RG 58) for NHYD/PSNH, 7/22/88 (Attachment 1).
- 2. UEAC Drawing No. 9763 F 300219, Service Environment Chart, Revision 19, 9/25/86.
- 3. Impe!I Calculation No. 0570 032 002, "Profile T.xtrapolation for ITT Surprenant Instrument Cable," Revision 1,11/5/86 (Attachment 2).
- 4. UE&C Specification No. 9763 00611319, "Specification for Specialty Cable," 9/20/82 (Attachment 3).
- 5. NP 1558, "A Review of Equipment Aging Theory and Technology,"
Franklin Research Center for EPRI,9/80. 4.0 Method of Analvtis The LOCA tempera ure test profile (Reference 1) and the Seabrook Containment Accident Design Temperature Envelope (Reference 2. Figure 2) sre plotted in Figure 1. The Arrhenius methodology is then used to determine the amount of time required for the cable when exposed to plant temperature conditions to experience the equivalent amount of aging which occurred during exposure to the tested temperature conditions. t Page 3 of 5 J
t' 5.0 Basic Dsts and Attumotions
- 1. The Activation Energy is 1.26eV as established for cables of the same insulation system in Reference 3 (p. 4).
- 2. The cable service temperature is conservatively assumed to be 167'F (75'C) instead of the post accident ambient temperature of 120'F shown in Reference 2 (Figure 2). The RG 58 cable is only used in low current '
instrument applications and, therefore, will not experience any L significant conductor internal heating. Therefore, evaluation at its design maximum continuous conductor temperature (75'C) is conservative (Reference 4, p. Bl). The 167'F temperature is shown in Figure 1 of [ this evaluation, t 6.0 Summary Results The ITT Surprenant RG 58 coaxial instrument cable is capable of withstanding l the postulated Seabrook worst case accident temperature environment for one year plus a large margin. 7.0 Body of Evaluation
- 1. The amount of degradation experienced by a device due to exposure to elevated temperature can be determined by the Arrhenius equation:
tt=te A/K[(t/T )i - (1/T )) (Reference 5, Sect. 4) l l l 4 l Where: ti = Service Time (Operating Time)(Hours) l \ l t: = Test Time (Hours) l A = Activation Energy (eV) l K = Boltzmann's Constant - g.617 x 10 5 eV/K ! Ti - Service Temperature (*K) T = Test Temperature (*K) i i
- 2. An examination of Figure I shows that both test and plant postulated temperature profiles are stabilized at a time of approximately 1.4 x 108 seconds (388.8 h r s.). The amount of test time at 260*F to be extrapolated in comparison with an equivalent aging time at 167'F is i
Page 4 of 5
from the clapsed test time of 500 hrs. to the end of the 30 day test (tend = 720 hrs.). This time duration of 220 hrs. is shown as A in Figure 1.
- 3. The desired cable post accident operating time is one year (8760 hours).
If the test time extrapolated begins at 500 hrs. of clapsed test time, then a review of Figure I shows that the test envelopes the postulated profile for the first 500 hrs, and the 220 hour period from 500 hours to the end of the test at 720 hours must be at least equivalent to 2260 hours (8760 hrs. 500 hrs.) in order for the one year operating time to be met. Therefore: g r. , , ,,, A/K[(1/T )-(1/T i )] Where: tg = Operating time to be found (>8540 hrs. for one year) t: = Test time = 220 hours A = Activation Energy = 1.26 eV K = 8.617 x 10 8 eV/K T i- Service Temperature = 167'F = 75'C = 348'K T = Test temperature from 500 to 720 hrs. of test time = 260*F = 126.7'C = 399.7'K Then: tt - 50,439 hours
- 4. In conclusion, if tg = 50,439 hours, then the cable test shows that the cable will withstand the accident temperature environment for one year with an additional margin of 42,179 hours (50,439 82G0 hours).
Page 5 of 5 i 1
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_ __ _. __ _ rostulated Accident (IEEF. a f. I, Fic o.c 7-) ._ ope. ares, Ti<se Seabrock Station: [f) /W,evnent l'iTo-' R- M 'T E S T PeoF . 6- PLOT r G b .15 LC< A hub teAussEu-h figure 1: Tempera ture Pro fiihen ~ . u :. Oa)s.y Tine ScAi_E 'is puoTT Gh to aTH A 'IU 5%b u no . Suer-r To LEG ~1(_C f hs poc To *4sfF *S gwnC h AT ~gynt-la n uss fla, , I
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g fn'Q tAlfERtk/G &A w A rix NE* AriACMt450T L Test Report No. 24843-89N-2 Page Nos. TEST REPORT FOR ENVIRONMENTAL QUALIFICATION TESTING OF COAXIAL IMSTRUMENT CABLES (RG S8) FOR NEW HAMPSHIRE YANKEE A DIVISION OF PUBLIC SERVICE P.O. BOK 300 SEABROOK, NH 03874 Purchase Order No. 61917 Prepared by: Date 22lt)'8 imoth . Rottf, Associate Engineer HTS /Ac on 533 Main Street, Acton, MA 01720 ppoe by , [ u- Date 227a 88 Kdith G. Whittles, Engineering Manager NTS/Acton KT/RPT/2484389N.NH2
t New Hampshire Yankee LOCA Test Temp. (deg F) Pressure (psig) 450 150 Temperature
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0 1 100 g,000 10.000 100.0 @ 000.Mt0.0@- y Time (sec) N Storting Conditions: Temp o t0= 130 Report No. 24843-89N-2 Pres O t0= 0 Page No.10-9
b y At u 11 roc k $0. Sis - A fins /Lf E'n i 2 c.u. = t.4,r c w = c a u w 0: v sn $s sz-j Calculat!ctvFrt:lem Nc: 0570-032-002 l g,. Profile Extracolation for ITT Surorenant Instru ent cacie c;;,ng DSC of New Hateshire p,g g Seabrook Statien J gee ,.e 0570 032-1661 i
- esqn in=uuR eimne:rs Refer to Table of Contents on page 2 of 6 Assumzuorts ce fer to Table of Contents en page 2 of 6 Metnac '
ce fer to Table of Contents on ; age 2 of 6 Remarxx The purpose of this calculation is to determine the sbility of ITT Surorenant Coaxial and Triaxial instrument Cables to withstand the postulated 1 year accident conditions based on its ability to function under a previous 30 day LOCA test. Ev* , NC. E/!$* N PERJOTM3 SY C-22 " AP ? RO'i !3 OA"3 l Original Issue Mdpk [Jg 0
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I l r TABLE OF CONTENTS I Section Pa ce 1.0 Purpcse 3 2.0 Scope 3 3.0 Re ference s 3 4.0 Methcc of Analysis 3 5.0 basic Data and Assumptiens 3 6.0 Surt.4ry Resul ts 3 7.0 Ecoy of Calculation 4 l l 7.1 Calculation of ktivation Energy 7.2 Pro file Extrapola tion i i l LIST OF FIGURES
- 1. Temperature Profile Comparisen LIST OF ATTAtmEN15
- 1. W-30454, IT1 ' t le tter to UEAC, catec 8/23/64.
- 2. EFRI 1556, prepared by Franklin Pesearch Center.
Septencer 1%G (Excerpts) hohle bsnN G & /TT L*-r..+
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l .0 Pu rpo se To extracolate the data frem the 30 cay 1.CCA test to show that the i ccdalal and triaxial cables are capable of operating for 1 year untAr acc1 cent conc 1tions. 2.0 Scote This cal:ulatt:n app'.ies :o Equi;.en: Cualification File No. 113-;?- 1 f:r Seabec:r. sta::cn Unt: 1 only. The cables are ITT Surprenant w : r. I cross linked ;: lye:r.ylene insula:1cn and exane jacket. 3.0 Re f erences
- 1. W-304!4, ITT's letter to UEAC, cated 8/2342 ( Attachment 1).
- 2. EFRI 1556, preparea by FrarAlin Research Center, leptencer ISEO
( Attachtent 2)
- 3. LEAC Orawing t.o. 9763-F-3CC219, Service Environment Chart, Rev.
19, 9/'5/46. I 4.0 Methcc of Analysis ' The Activatten Energy is calculated, using the Arrhenius Equation, from cata centa1neo in Re terence 1. The Arrhenius Methocology is then usec to cetermine the enount of tine requirec for a oevice exposed to plant temperature concitions to experience the equivalent al. cunt of aging which cccurrec curing exposure to the test temperature cuici ttens. 5.0 Basic Cata anc Assunptiens
- 1. Ttie encpoint temperature and time are per temperature profiles in Figure 1.
6.L Suecary Results The ITT Surprenant Cables are capable of withstancing the accioent, environment for 1 year plus a large margin. oe rsep w, e
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7.2 Profile Extrapolation The arrount of degracatien exrerienced by a cevice due to exposure to elevate 0 temperatures can ce ceterminec by tne Arrhenius equatien. L=B'E)FLA/(X*T)); (Ref. 2, Sectici 4)
'ahere La Tire to Reach a Specified Endpoint b= Constant A= Activatica Energy K = Bol tzman s Constant =8.617E *5 T. Temperature Solving for B Yieles; e =L* E1F L- A/( K'T))
For equivalent cegracation, B will be the same for exposure to ectn plant anc test temperature cencitions. Tes t Aging
- Pl ant Aging Mcwever, the plant aging is equal y the aging which results troni espesure to tne accicent envircnment plus the aging etch result fren. exposure to the nereal ancient temperature for scre length of tire calleo the thermal life, dich we are trying to oetermine.
There f ore ; Test Aging = kcicent Aging + Normal Aging (L'nkncwn) ano; Sur. o f L'EXF(- A/(X'T( Tes t))) = Sum o f L'EXP(- A/(X*T(kcicen t)))
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cich can easily be solved for' the thermal life X. In ortAr to use the abcVe equation, both the test ano accident profile have been envelo,.e4 by straight lines, each line a regien of the prottle (See Figure 1) anc the encpoints of these lines input to the program. I Each. region is then diviced into N intervals, the curation of the interval anc the average temperature over the Intenal are then input into t'hi Arrt.enius equation anc surgeo over all intervals. Pros /s. 8 4 4=a fla W 5 / W Leeng as *
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Uni t e d f.= gin e e r s and Co :rs e? .G :g r2, In c . :: ee.t ... f i; .;,,, , , , , 30 South 17th Street ... ..o wi , . . . . . . . . , . - Philaael;hia. FA
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Daa r W.r. A'g g a: .al *o ta=. i,3./a g gy A .f,y ,g .. , A.s a follow-up,to our pre-award nesting of August Mth. I have - investigated several of your questions and provided the necessary ansvers below. ,
.i 4 (f"f*C -2,1. Provide extrasotation of RGu trias, to RG1.1 coax LOCA data.
provided by -C". I""" S ut p renan t eno s e t o 10CA t as t RGU c o ax e"2-C( and Rc39 coax since they are the rvo constructions we consi-dered most cousson.17 used by nuclear f aci.11 ties. Since LOCA testing is very aziensive to the manuf acturer, only the best representative samole of similar constr ictions can be f easibly-tested. *est:ng all constructions vould be economically un--
//"/7-O[ feasible.. .
3 * *f C 3
- I . Specifically addressing R:n triax.' ve feel that our coaxial LOCA data is mo re t.han ad equat e . The di.nensions of the u ,
coas and M triaz are identical through the f t st shield. Coucle this with the fact that the ,trias has an additional-shield and jacket of idantical material as the shield and jacket gf the LOCA approved coax, and our conclusion is LOCA'.
, approval for RC U triaz. A,s additional infor=.ation. I have-enciesed a copy of our 1979 LOCA data ,vben we did have the. .
! M L1 triAx asproved. Please note that the only reason we , were not a b l e t o 'us e t his d a t a , va.s t ha t we d id r.o t hav e a. mata streaa line break at 3900T. Ioch. M590 ar.d RO11U coax-are covered by our n,ev data enclosed.
*'e
. f eel s t.=114r concerning K05 8C/D LOCA soproval. Sin c e ve- .
. have chosen M39 for our LOCA program and have that ap p ro va 1*. .
and M55 has st=tlar constraction details, we are con *1dene . that, had it been suba.itted, it also would have been approved.
"he 1/C .. ,- .. 0 v'oit crossitated polyoleft.: -ith a hy,alon jacant ca:le, wnt:n we pre,sose to supply f or 1:e=s 11 & l' of reur inou.m f.11 be covered under a seoarate LOCA aoprovs1..
vnich vu eweti ti* receive f t:s Trankli.n Insta:ute e.tnin I weekss.
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Mr.11rish M. Aggarval' Au gus t 23, 1982 , Fase 2
. Cartify thermal aging of LCCA samples.
!"; Surprenant, hereby, certifies that we did thermal age, as spect!1ed, sasrolas of all necessary cables subattted to Franklin hatitute for $* 1/t0CA staulation during 1982. '
- 3. 3asts for pre-aging 13000 for 168 hours.
I have attached a copy of our Arrhenius data shoving that , , , . using a very conse:-rative end of lif e value of 30* insulation , elongation and testing at 134'C,136'C, and 1:100, the cables .' have a proj ected 40 year lif e of 83*C. Our pre-aging 1.5000 , a' . at 164 hours gives us a 40 year lif e at 73*C. , 4 Aged and Unaged cable samples sust pass the flame test require = nants Para. 2.3.6 (single conductors). This is to certi!? 'that all cables RC11 trias, RC11* coax RC39 coax RC38 coax, and our proposed 2C f: Auc cr ss-lined polyo-lefin insulated cable pass the single conductor flame tests ref erenced in Para. 2.3.6 for both aged and usaged samples. t
- 3. IIII 383 vertical flame toets..
Per IIII 383 Table vertical flame test refers to Para. 2.3.6. Para.s2.3.6 is the single conducter wire test ta accordance with A521-Of:20-68 referenced above.
- 6. All LOCA test stJBulatioR is DOSS With GmmE4 radiatiCS, address '
Seta requirement per Para 2.4.1.2 lladiation 3 eta 1.4 1 10 8-RAD 5 over 12 montha ae a maximum raee ef 3.1Il06 1/ EE.. It is eur optaios that Camma radiation is acre severe (panetraa tiss) than leta. Ve. therefore (worst case) have considered-the total dosage to be cumulative Camma, considering the total-Gamma plus leta during desirs basta event to be 1.3Il08 RADS.
'Ve f eel vet 7 cetfident that our referenced coaxial ceales can withstand bot.h the Casma rates of er:posure and tho' more thaa ~
' total exposures ,
.4
- 7. Chemical flow tete 0.42 spe, Since our material was tested using a chemical flow rate of 2.3 gre, we feel 0.42 gpa would present no .problems, .
c -
- 8. Extrapolate 'l year post LOCA. ',-
Cur LOCA data prevsously su' o e.itted is only 30 days ta leagth. - Although we have not received final prtated resorts from Franklin. Institute, we have received verbal confirmatic'n' that we have. succe'ssfully passed our 100 day LOCA submittal. We vill continue. , this testing until 1 year is reacned. ;otil trae allows the. balance of the test, we sub_it our 11 -alves as extrasolated stooW of 1 year a::sptattlity.. , g t m
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. I P 3 of 6 1 Mr. Girish M. Asgarval
- August 13. 1982 Fate 3 The insulation resistance at the start of test was 1120 met-chas. De t=sulation resistance af ter 100 days was
- 1010 seg-chs. I.xtrapolatias this da'ta. our 1.7,. af ter 1 yaar would be approximately 700 ses-chas.
- 9. 1,.ms-ters water absoption data.
s1 Attached are 1:st-tarn water absorption data f or I::ase 20 a.C vall. , I believe this should answer sost of the outstanding questions. If either yourself or Oeorge Morr:.s have additiona.1 questions, please do not hesitate to call. 3 st P.agards.
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The t..ar-at aging properties of irradiated trasa-linked polyethviene insu1stien.
!ar R011.UG LO-59 type teaxial and triaxial caeles, were determined using the Arrr.entus to:hnique of accelerated aging for these materials.
set at 158'C. ranglas of ins 8 31sted conductor were aged ta a circulating air even,At latervals dependi 126 0 and 121 . conductor, cut free the ceil of Lasulated conductor were reseve( frim the eyes I ]
' ' couled to rees temperature for severst hours. The ceppar ves removed and
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tuba of insulation tested for tess'ils strength and per:ent alongation on an cran sachine. Wese results Testing were tabulated versus staa of aging at the , l
,respectivu eves temperatures. of insulaties was continued periodically.
I geoending en the asLas rate observed free prevleue data. The "end et life" was
- r,cerned wnen the percent alongatten was reduced to SCO ef the original value at ,
gagn et tne aging temperatutes. These data points were used to draw time A. vnich representa the rate of asias for the irrac81sted cross-link 6d polystaylene in sula t te s. . the 40 year Line I was jhen draws parallel to line A se that it would tacerceptsaves (7) days point at 75 0, vnich is the destga lif e and temperature rating, ;
. at
!!0 80 was selected f rom line a for pre-agtag purposes as noted La 130J' report 1;;1-01 (Seveneer 1979). ,
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g ug, p 05 b. 0 32 - t 9 A Review of Equipment Aging . 8 I. o 4 /r Theory and Technology
.. NP.1558 .
Research Project 8901 Property of ., Final Repcrt. Sectemcor 1990 Work Comoistec. Octocer 19"9,.u ;] .r., .
.4 3.y_ L =_.,.,.an e i. .e,,r- .
LIBRARY Prepared by ,
' FRANKUN RESEARCH CENTER . . .
, . ,. The Parkway at Twentietn Street Philadelphia. Pennsylvania 19103 Pnnetool Irwesti9ators * *
. S. P. Carfagno: .
R. J. Gesor>
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.- Electnc Parner Research laatituta ' ,.., ,.
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- - - 3412 Hillvew Awnue. ' '
Pan Asta. Caocnse ea30s 1 ' '* :. ' .' * . .
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- . EPRI.Proiect Manager . . , ,f * **
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- D. G. Caert. ,.
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Theories of Acinc_ w w .
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In the context of ectJament qualincation. agmg of components an,d matenals refers ! to the vananen of thett properne with time. the propertes of interest bemg those i related to the safery functon of the"component or matenal Althougn aging
. some:mes tmoreves,funcnonal cacabdity, the type of agmg of greatest mterest u that associated with ceteneranon of funcuenal capabdity. Asms mav cause changes in many proper:es of a matenal or a device;for prae: cal purposes. however, tne ag.
'ing of an ite.ra is measured by considen*3 only the few propernes most directly
, related to the' safety fune en. For example, the asms ofinsulanns matenals is often .
measured by the nrke vananen of the dielectne strength. smee this is the reist im-portant parameter for high voltage insulshon: however, the ame vananon of severall .. parameters ruch as de gam and base leakage must be considered when studvmg the agmg of transistors. Many physical stresses. both ia,temal and external, qm lead ter aging. Intemaj.. or operanonal, stresses Ji uch a's current, voltage, anci ohmic hianns in elec= cal. devices-are inherent in the operanon of the device; external stresses-such as am- -
- bient, temperature, radiacon (visible, samma, beta, neutron, ultraviolit. etc.) vibrp-
, tion or shock, or other mechanical and charmcal stresses (hurrudity, oxsdanun, etc.).
-.ongmate in the envuonmentu ,w .
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.Theoreccal relationships between a stress overa linuted range and.a"deteiora- -
tion or fasure, based on the phyncal or chemical processes takmg place. : e htown-
* . for so6te types of matenals and components. More commonly, espec. ally. for com- .
, , plex devices, the reianta of degradanon to stress, rests on empmcal knowledge, ori the ooservabon of agmg as a furwnm of nme and'sh msgrutude. In ruch cases.
th,e relatidrIczn "e considered vrjid only,if stansticaay ngru5 '~cant data have beem -
. . sathened over the range of internet; ;; .. ,- . . ,
-.. @eiIJutablish,e,d modeis reiaring agmA stras are the Arrhentum Ehuis andT - - -
Inverse Power formulanons. The dasste.! ', a of the first and third modeis is dis- . . cussed by Nelson (198. 419, 497, 4W) in great detad, and his pape s provide ', ~ references to other papers on the subject. Furtner decad is also provided in Secton- c
~ ~
s.. . 4.1 THE ARRHE.NTUS MODEL . . .
,,The Arthersuas Mocei is nauailsapplied to't'nermal agms in the form. ,,
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l 6 k - Boltzmann's constant (0.8617 a 10* eV/K) T = absolute temperature'K)
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4.2 11E EYRLNG MODEL
- h Emns model pmvide a thermodynanucally more nearly correct (600) formuL. !
tion and may include addmonal stress terms.- - K = ked - aT"exp(- hp(S(e . h (4.;; where - L = reaccon rate in the absence of applied stress K - reacnon .. tre in the presence of applied strus k = Boltzmann's constant- . . T - absolute temperatum
- a. b, c d and w. - expenmentally detemuned constants independen:. ( '
.., time, temperature, and stress S - a funcnon of the a'pplied stress 2 .,
d n =c q ' n
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,. 4.3' THE INVEPJiE POWER MODEL . .j The inverse power model can be applied to problerns such as thedatigue teseng +
metah the diefrctric breakdown of capacitors and 'the'acmg of mul5eemponent.
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. = stress (0 4., current, voltage, temperaturet -
,... 4A SPECIAL FORMS QF THE ARRHE:NTUS' EQUATION. ."
A general denvacon of the Armenius equanon is provided in Seenen 3.3.:. In :hu
. . ,' seenon, a discusmon of chenucal knencs is pen 4Jas arr mtrcouc=en to the Ar . .
, theruus 'moce6 also mciudad are spec:al forms of the'Ar.i. uus'equano'n anc' ex..
Mmpies of ther use in acenerated agiss applicanons .
,:+' -
. For a firsrerder ruecnon of,a matsnal. the ists of the macudn can be wnrien for-constant tempericure as. *-
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l h k' The Ndegree rule requaru No generally unwamated amumptions concerning activanon energy and tenperature range. The effort requumi to detemune wnemer the 10 degree or n. degree rule is a suf!Lnenth gooo approumanon is about the same as the effort required to use ths Anheni'us modelIn addicon. de Anhe.nus model has a theorecesi basu, whereas the 10. degree rule does not. It is bette to use 6e Ar. rhenms equanon with an assumed, albeit cor.servatrve, acevicen energy. 4.6 CONSIDERAEON OF VARIABI E SERVICE CONDIRONS Service conditons are rarely constant with rupect to a given scesa. Although a pasave device i.e., one which generates no self.heanng. may be mamtamed in : con. trol room environme'nt at a constant temperature throughout its life, thu is tne ex. ceccon ratner than the Nje. In general, a dewee will he erno;ed to a range ci temperatures for different umes at any one temocrature. Thu vanacen may :e regular (cyclic) or trregular. To a first appromrnacon 'the total tme at any pven temperettre governs the amount cf degradanon.Thm.is we may sum the =mes at the vanous temperature levels: however, this stillasves us the prooiem cicomoin. ing the aging at vanous tempetature levels. After combuung the ames at each temperature, we can denne . t4. = total ame rpent at temperature It i = 1.2.3. . . .n For some fixed degree of degradacon, we can wnte the Anhenius equation u-In (t /t.). = ,
- h. ,
T. .. some arbitrary' reference tersperature- - l t - tha tune assocuted with this temperature we solve this equanon for the t4 associ.ited with tix T4. Since all the ages ce now assocuted with the same temperature T., they may, be added
.t.= I:t ,
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., Dus time [or age) may be larger or smaMr than.the totil ame of semce. whien.
. is equal to . .
. t. = C .ts. .**-
.i *
, li we wuh to detemune a nngie tempesture for which thi degree of degrada.- non is tne same as that,oi the c;omained tempeturu T we aestn use the Armeruus: -{
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TEI3 DOCDG2fT IS NUCLEAR SAFETT WTTD HJTED ENGINEERS & CCNSTRUCTORS INC. 30 SOUTE 17TH STREET PEILADELF1f1A. PENNSTLVANIA 19101 SrtCIFICATION b N/A '68/8/4 EvA c.u a rds hl. O- . setCIAtrr CAstr 4 TTAC#NGA>r 3 IE FUBt!C SEITICE CONFANT OF NEV EAMPS1tIRZ SEABROCE STATION UNITS 1 & 2 Specification No. 9763-006-113-19 1r715I015 Datet h /8.C /S1 h- hea tr ee . chae w o/A Stt FEM aredt h h @ ' *- C.W. Morris Checked: D. W. (* i Q/A Review: y L j 5( E. Rubenstein l ApprovedI h _ G. M. Aggdrva F Approvedt > M C E. ShoaJs l c I of E i
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'..." AFFENDII 3 . . . -
SE11 Ell'S DATA TRIAIIAL COAXIAL , 1
- 1) Minimum alloweble temperature during installation -30 oC
- 2) Maximum continuous conductor camperature 75 oC
- 3) Maximum emergency overload conductor temperature 130 ,oc l
- 4) Maximum short circuit conductor temperature 250 oc
- 5) Forcent copper conductivity at 200C 96 %
- 6) State if copper conductors are coated or uncoated coated
- 7) State the type insulations . a) by Seller's trade None name and * -- -
- b) by generic name Polyeths- i k*ne
- 8) State the insulation curing process Irrediation Cross-linked
- 9) Does the stated insulation coItain fillers? TES Cive the generic chemical names and purposes of major fillers
- 10) State the type of covers a) by Seller's trade trane name b) by generic name Polvole fin
- 11) State the cover curing process treadiation cross-linked
- 12) Does the statad cove'r contain fillerst Yes Give the generic chemical names ar.d purposes of major fillers - 1
- 13) Cive the percentage halogen content of insulation 8' f by weight Appendix 3 Spec. No. 9763-006-113-19 Page No. 31 QQt 20 5
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l f~o c g N0o l l 3- 14 -0 2. I2GGER &cE 5~ SB 1'2 Amende nt 59 FSAR .M a y 1983 Seabrook Station's commitment to per form this " sting is also , described in Sub sec tion 14.2.6, which describe s Seab rook ; Station's interpretation of Regulatory Guide 1.63 Append ix A. > Section i.g. I J. Environmein ) a l E f fe :t s on Electric Equipment l l All equipment that must operate in a hostile environment during U . and/or subsequent to a design basis event are identified with their ambient environmental cond itions, and their qualifications are discussed in Section 3.11. ( l e. Ef fects of submerience on Electricst Equ ipvee n t 1 , l The response to RAI 430.62 presents an analysis of 'the e f fects of I submergence as a result of a 1,0CA on -electrical equipment. The results of this study indicate no detrimental ef fect upon the
- Class 1E electrical power sources as a result of submergence of electrical equipment following a 1.0CA. b..
k 8.3.1.3 Physical Identification of Safety-Related Equipment All cables, raceways and safety-related equipment are assigned to a particular channel or train. There are two redundant trains of power and controls, and four redundant channels of instrumentation. Each channel or train is assigned
, a particular color, as shown below:
Equipment Raceway Sepa.ation Group Nameplate Tag Cable Color A. Channel I and Train A Red Red Red Train A Associated Black Black w/ Red Tracer l B. Channel II and Train B White White White Train B Associated Black Black w/Vhite Tracer l 9 C. Channel III Blue Blue Blue D. Channel IV Yellow Yellow Yellow c:. Each piece of electrical equipment is marked w.;T the node number indicated on the design drawings, in the particular color corresponding to the channel or train to which that equipment is assigned. Similarly, trays and exposed condules are marked with color-coded markers. The cable jacket color code serves as its identification. The operator or maintenance craftsman needs only to observe the color of the nameplate of any piece of equipment or the cable jacket color to determine which channel or train it serves. For exceptions to the above cable and raceway identification criteria, see Subsection 8.3.1.a.k. tS e
- 8. 3- n t,hy , o (nq
I l SB 16 : Amendment 59 FSAR ,va y 1986 , I 1 l l t.3.1.a Indeoendence of Redundant Systems l
- a. General The Seabrook Station complies with the requirements of FSAR .
Appendix 8A. IEEE 384-19 74 and Regulatory Guide 1.75. Rev. 2. 3 These documents describe acceptable methods of complying with IEEE l 279-1971 and Criteria 3,17 and 21 of Appendix A to 10 CFR Part 50 l with respect to the physical independence of the circuits and electrical equipment comprising or associated with the Class IE power systes, the protection system, systems actuated or controlled by the protection system, and auxiliary or supporting systems that must be operable for the protection system and the systems it actuates to perform their safety-eplaced functions. Presertation of independence of redundant systems within the co'n trol boards and t a ll other field mounted racks is discussed in Subsection 7.1.2.2. g . s In accordance with the provisions of Section 4.5a and 4.6.2 of X FSAR Appendix 8A, Sections 4.5(1) and 4.6.1 of IEEE 384-1974, and Position C4 of Regulatory Guide 1.75, Revision 2, we have elected to associate all of cla Non-Class 1E circuits with Class lE circuits. 'this Eppiication of" as'sociated circuits altoss the plant
'n be designed with one less separation group; that is, instead of having five separation groups consisting of four safety-related separation groupa and one non-safety-related separation group, Seabrook has only four separation groups. The majog advantages of this approach are the ability to provide greater separation distances between the groups, as well as to reduce the raceway ,
system's exposure to fire. As a result of this design, all plant circuits are specifically assigned to one of the following four separation groups as noted in Figure 8.3-57:
- Croup A - Train A, Channel I and Train A Associated Circuits Group B - Train B, Channel It and Train 5 Associated Circuits Group C - Channel III Croup D - Channel IV The great majority of associated circuits are with Group A, a very limited number are with Group B, and none are with Groups C and D.
The circuits that are associated with Train A consist oft
- 1) Non-Class lE power, control, instrument circuits contained within the Nuclear Island.
- 2) Non-Class .E power, control, and instrumentation circuits that traverse the Nuclear Island boundary. ;
- 3) Non-Cl a s s lE power. control, and instrument circuits outside r the Nuclear Island.
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SB 1&2 Amendment 52 FSAR December 1983 The following analysis examines the design features and modes of l f ailure of associated circuits of each separation group to determine I any interaction and challenges with other separation groups. The l overall objective is to assure that the ability to achieve a safe t plant shutdown "adar design basis event (DBE) conditions is not I compromised. ! l (b. Train A Associated Circuit Analysis
- 1. Associated Circuits Contained within the Nuclear Island Non-C la s s 1E circuits that remain within the Nuclear Island are permitted to share the same raceway.as Train A Class 1E circuits. These circuits are classified as Train A Associated Circuits and are designed and installed to meet all the require-ments placed on associated circuits as required by the compli-ance documents listed earlier.
Challenges to Class 1E circuits, because of failure in an associated circuit, have been examined and determined to have no detrimental effect because: (a) When Class 1E power sspplies are utilized, failure of a Non-Class 1E sotor, load, or device connected to this power supply will be promptly isolated by operation of Class 1E protective devices. i Non-Class 1E loads connected to Class 1E buses are in I all cases protected by Class IE devices. The breakers protecting Non-Class 1E loads are coordinated such that ' f ailure of all Non-Class 1E loads, with proper
- operation of their own breakars, will not result in tripping of ,
the incoming breaker to the bus. Further, in the few cases where credit is taken for the incoming bus feeder breaker to provide backup protection ; to meet Regulatory Guide 1.63, the associated bus is dedicated to Hon-Class 1E loads only and, the refore, will ; not degrade a Class IE bus. (b) In cases where Non-Class 1E power supplies, such as . switchgear, notor control centers, and distribution panels are utilized, these are of identical design of , the Class 1E counterparts and have been purchased to the same specification requirements inclusive of quality control. Mounting of the hon-Class 1E power supplies ' within the Nuclear Island is identical to the mounting of their Class lE counterparts; theref ore, credit can be taken f or this equipment to function under DBE conditions.
'C r
z? og 3 o [s 3 8.3-41 7
l SB 1&2 Amendment 55 FSAR July 1985 l (c) All Non-Class lE prot;ctive circuit breakers will be l periodically inspected approximately once every five ! years according to a progree developed for the inspection of Non-Class IE equipment. This program will be in accordance with manufacturer's recommendations for main-tenance and inspections. Since Class IE and Non-Class IE protective devices are
- identical, any generic degradation such as setpoint drift, I manufacturing deficiencies, and material defects will be l
detected and corrected as a result of the rigorous program l performed on the Class 1E protective devices to satisfy the requirements of ANSI M-18.7-1976 and Regulatory Guide 1.631 therefore, credit can be taken for this equipment to function under DBE conditions. . (d) The probability of an ensuing fire is minielsed because all cables utill ed for these associated circuits are specified, designed, manufactured, and installed to the-same criteria as Class it cables. Factors that have been taken into consideration include flame retardancy, l non-propagating and self-extinguishing properties, splicing restrictions, appropriate limitations on raceway fill, cable pulling and termination requirements, appro-priate cable derating, and environmental qualifications. The above provisions and considerations used for the associated circuits during the construction phase of the plant will also be used during the operations phase. (e) Degradation of an associated circuit because of a raceway failure during a DBE, has been eliminated because all electrical raceway systems within the Nuclear Island are seismically analysed. . (f) Other design considerations that contribute to the integrity of these associated circuits aret l
- 1) Cables associated with one train are never routed
) in raceways containing class 1E or associated cable of another train or channel.
- 2) All cables for instrumentation circuits utilize shielded construction which minimises any unaccept-f able interaction between Class IE and associated circuits.
- 3) All circuits entering the reactor containment are provided with protective devices e.oeplying with Regulatory Guide 1.63. For exceptions see subsection 8.3.1.1.C.7(a). l 55 Based on the above design features and analysis, we do not !
consider these associated circuits to pose any challenges to any Class E circuits. Therefore, the sbility for safe p' ant ! shutdown under DBE conditions has not been jeopardized. e s ,.., e.3.c pki n ? 4 c; 3
1 l SB I & 2 A.m.i nilme n t 52 FSAR December 198)
- 2. Train A Associated Circuits that Traverse the Nuclear Island Boundarv For .1nalysis purposes, the associated circuits that traverse the Nuclear Island boundary can be further subdivided into two basic types: (a) those that have their protective device located in the Nuclear Island, and (b) those that have their protective device outside the Nuclear Island. It should be noted that there are a limited number of power cables in these categories.
(a) Associated Circuits that have Protective Devices Located in the Nuclear Island
~
These circuits are also designed and installed to meet
- all the requirements as outlined above in Subsections
,,8.3.1.4.b.1(a), (b), (c), (d) and (f). Though the raceway system outside the Nuclear Islaad is not seismically analyzed, this is of no concern because the circuit pro-tactive devices inside the Nuclear Island are assumed to p1rform their protective function. Concerns that dasign basis events such as a seismic event may cause high voltage cables that are not in seismically analyzed race-ways and not located in Category I buildings to interact with lower voltage cables are analysed below:
Recent seismic tests, performed on raceways representing typical installations on SEP plants, proved that the raceways can withstand seismic events with no significant failures. Since the typical non-seismic installation at Seabrook is superior to the tested SEP installations, it can be assumed that they will survive a seismic event. Failures of raceways resulting from collapse of the non-seismically designed buildings can be dismissed because the :onservative criteria and UBC seismic loading used in the construction of the building will ensure little likelihood of collapse. Not withstanding the preceding, any event involving the raceway system that can cause a higher voltage cable to come in contact with another lower voltage cable will first cause the higher voltoge cable to be grounded. Centributing factors to this are: 1) the cables are in grounded metallic trays or enclosures, 2) the 13.8 kV and 4.16 kV power cables are of armored construction, and 3) as indicated in Fig. 8.3-57, separate raceways are designated for the dif ferent voltage levels, 61 e *
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IN JTPELLO ECo FmE MO 3 + 01 (2W Ei2 ENC 6 S lecord of Conversation FJe n on_ n3 7.j u 3 Cecy: GRahner ABiswas GNoore 1 DGhosh l ), Te ecncee Meeting Otner .R8ergeron (PSNH) avwuu imw, 7 C.D. Greiman prem: N.K. Woodward C- cany' un f ema Engineer < A centracters Pnone No 215-422-3252 Date 10/8/85 Swoiect- Seabrook EQ: P.O. 113-18 - Summary of Conversation: Chuck and I discussed how Impell can identify which of the different cables in P.O.113-18 and the other cable specifications are connected to equipment which must perfonn a safety functon subsequent to accident events. The color coding of the outer jacket as defined in UEAC separation cocuments enables this detennination. Specifically outer jackets with the single solid color of red, white, blue, or, yellow cesignates cables for wnich perfonnance requirements such as !.R. and accuracy must be met during environmental qualificaton. Cable of other colors or color schemes must oniv remain intact (e.g. no shorting to ground). however, all Class lE cables as defined by the Specification must be environmentally quali f ted. , Chuck will fomard a copy of the UE2C separation document which cefines these color schemes so that it may be incluced in the EFs. NKW/jm
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n, o i,. i , 5 T.6Gi. GGM7l4iT QF NEW ri.A2GSHIRI. et al , , , " .,$'".'"*'...".'.*.,*"..',*.*""*' c/o United Engineers & Constructors Inc. Agents v.,qo r. ..gges a c:.s, uet:. x Post Office Box 700 Post Office Sox 700 Seabrook, New Ha=oshire 038;; AURCHaSER S aa b ro o k. New Ma=o s hir e 0 2 ! *:. g-ga'* of ; :cu . n :. IT*-Supranant Division a.u..t es .s e .c cu .ust star :
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_SPECIAI,"Y CA31.E Oasign, furnish, f abricate, test and deliver 11,ot of Spoeial Cable in accordarce with the folloving docu:. ants: A.lSpecificationNo. 9763.006-113-19, dated Septa =ber 20, 1982 c:nsisting i 6f Cover Page, Table of Contents, nineteen (19) reproduced typewritten pages, Tigure 1 three (3) pages of Appendix A, and three (3) pages of Appendix 3, attached hereto and made a part hereof.
- 3. Specification No. 9 763-QAS-3 Quality Assurance Adninistrative and Systes Requirements, Tor Safety Ralated Electrical Equipment. Revision 7 ldatedApril 11, 1979, consisting of Cover Tabis of Contents. Current Page l 1.1.stf.ng. Identification of C1anges, and thirty-nine (39) reproduced type-l vritten pages, already in your possession and sade a par: hereo f .
C. ! Specification No. 9763-EQ-1. Class II Equipment Qualification Require =ents, l Revtsion 7, dated Tebruary 19, 1976, consisting of Cover, Table of
! Contents, ten (10) reproduced typewritten pages and Oata to be sub=1sted wit f n.u hered h Proposal, D1 andconsisting D2, already.in of tvoyour (2) possession reproducedand typewritten made a part pages, hereof.
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TOTAL T17M DC.:"IRC PR: I . .
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- 1. 23,000 ft. UAi! Triax RG-11 Red $810.00 $ 20,250.00
- 2. 25,000 ft. UA2T Triax RC-11 Vhice $810.00 $ 20,250.00
- 3. 7,000 ft. UA3; Trtax P4-11 Blue $810.00 $ 5,670.00 4 7,000 ft. UA4T Triax RG-11 Tellev $810.00 $ 5.670.00
- 5. 60.000 ft. UA6; Triax RC-11 Black / Red f810.00 $ 48,600.00 C n:1. .u e d l . . . . . . . . . . . . . . . . . ~ . . . . ... ..... ...... .. ....... .........
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0 .et u =o i o t s c a s.fio = 1 .. ic t ITN QUMCI*Y DES CR!?*!0N PRICI/MI* ECCISION l 6. 10,000 ft. *A6* Coax RG-11 , lack / Rea $ 755.00 $ 7,550.00 l RC 's8 Black / Rad $250.00 $ 15,000.00 a 7. 60,000 f C. TA6T Coax
- 8. 5,000 ft. TA1T Coax RG-59 Red $225.00 $ 1.125.00
- 9. 5,000 ft. TA21 Coax RG-59 White $225.00 $ 1.125.00 TA6t.' Coax P4-59 Black / Red $225.00 $ 1,125.00 1
- 10. 5,000 ft.
l Pre =ium Price - 7endor to expedite delivery to October 6,1982. ITm QUMC JT _D,ESCRI?* 0N PRDC3 CA6 RG-11 Black / Rad $ 4,000.00
- 5. 25,000 ft. Irt.ax Prices are firs for delivery through January 14, 1983.
I TI'Ud.S OF PATMEC: l 1 ten (,10)/ not thirty (30) days. I SPECIAL CONDI!!ONS - Fors No. 9763-4224 Revi. sed May 20, 1951 consis ti.ns , of Cover Page. Table of Coqtants and eventy (20) reproduced typevet::en pages 1.s attached hereto and =ade a par: hereof. CAUL.'CIE: l.a accorcance with Article 9 of Special Conditions Tors 9763-4224 for a period of one (1) year f res date of co.sserci.Al operation. Two (2) unpri:ed copici of outside Purchase Orders are to be tubnitted to the attenti.on of . D. E. McCats, Manager - Expediting. Monthly progress charts outlining engineering, purchasisg, production and dativery status vill be sub_1::ed star:ing August 23, 1992. I Oo s:1..u e d
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o8seel'flo8 l ...C t itt no I 1 SHIPPING P0Cff: Leoninster, Massachusetts TOE. REQU 1ED TO P.GU7ACTURI: 12-14 tiEII.S /J4 dei!**IRY : I:ess 5 - 25,000 ft. (partial) vill star: delivery October 3,1982 Item 7 - 15,000 ft. (partial) will start delivery Oc:cber 15, 1992 Balanc.i of Iter:s 1 through 5, vill start delivery Nove=ber 19, 1982 Balance of Order vill star: delivery January 14.1983 (based on rslaase for f abrication October 8,1982) . M'*4-u:s real length produced vill be 1,000 f:. a aliveries accepted 7:30 a.c. to 3:00 p.e., Monday throu2h Triday only. except local holidays.
! Saller vill provide evo (2) week.s vri::en notifua:On for inspection or vitnessing of tests and, a subsequent 72 hour verbal confination. !
lattentionMr.D.E.McCaig. Invoices shall b's submitted in accordance with isstructions shown in See:Lon 12 of Special Condi:Lons Tom 9763-4226 Failure to co= ply with these instructions say result '.n retum of invoice f or correction, thus delaying pay ant. On all correspondence which is a reply to a UILC istter. the Seller shall ref erence is 1is letter heading the $3C nu=ber of Purchaser's trans_A::al. Tha $3" au=ber shall aivays be found balev the letter date on the Cover Page. C ='L*'** j (Uf EN
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Tagging shall be in accordance trich instructions is See Lon 7 of Special Conditions Tors 9763-4224 Sellar =ust show the amount 1seluded for transpor:acion as a separate
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I Supplement Equal E=ploysant Opportunity Tors 4079 (Rev. 2/$0) . censistisg of one (1) page pristed both sides. is attached hers:s and made a par hereof. , CCb71? MING 7E?JAL 00G AWA.CC TO AND ACOIFTID ST MR. JOC, 5:1 'T. AN A'w*7dCR!!A!!*7I RI?RISD*IA*17I 0F SE.LG. AUGUST 12, 1992. l. i i 1 I i
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=
y Post Office 8cm 8223 m uce m pnasa.#enia. P A 19101 February 13, 1985 v e caos SBU - 92605 File: 49-7 1.0.5.7.1 Cat: TICH Imoeil Corporation No Resoonse'Recuired 225 Broad Hollow Road - w
..elville, New Yorx. 117!.7 /$ p!/p Attention: Mr. N. Woodward Public Service Company of New Rampshire et al.
New Hampshire Yankee Division Seabrook Station Envirensental Zones Aa requested in the EQT'" project meeting of February 11, 1985, we have reviewed the location of Class 1E equipment in the plant to , decersine if any equipment 14 located it, areas containing radiation 9 levels above 2 x 100 Rads TID. Other than the in-line instrunntation in the reactor coolant piping inside containment, the only areas which contain radiation levels above 2 x lod Rads TID are the domineralizer cubicles at Elevation 2'-0" of the PAS (Radiation Zone 27 - Environ = ental zone PS-19) and the Chemical and Volume Control Tank Cubicle at Elevation 53'-0" of the PAS (Radiation Zone 16 - Environ =emtal Zone P3-4). Review of the Class 1E Equipment List (Drawing No. 9763-M-505300, Rev. 13) and the electrical conduit drawings 9763-T-310764, Rev. 18 and 9763-F-310768, Rev. 19 nas determined that these PAS areas contain no Class 1E or Reg. Guide 1.97 equipment or cables. If you have any further questions on this matter, please call me. Very truly yours, C.9. b
C. D. Crei=an Supervising EQT7 Engineer COG /frb cc: Messrs. R. J. DeLoach - YNSD SL J. DeVincentis - PSN940 2L W. Cloutier -
YNSD IL
- u. 5. Beckley -
PSNR 2L C. Thorr.as - PSNH 2L D. C. Mc!.ain - YNSD Start-Up IL C. M. Wiley - PSNH/YNSD Tield office IL N. K. Woodward - I=pell 3L R. Bergeron - 01/04 Site ea me-e:i.a m % n vm raan m ruu:crum e +== r... . . . . A 9 t I^'I
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l' b t'i w L G Q. FI L.E No (EEPEt2&XS 9 k c::vcEr.cL"'f iykaE February 2, 1986 0570-032-NY-156 Yankee At mic Electic Company 1671 'Jorcester Road Framingnam, Massacnusetts 01701 ATTDTION: Mr. William J. Cl outier . SU30ECT: Public Service Company of New Hampsnire Seabrook Station i
.. .. . .. . . _. . .-. ...... Environmental Qu ali fication of El ectrical Equ pment Summary of Class 1E Equipment Submerged as a Result of Design Bases Events Gen:lemen:
- n order to determine if any Class 1E equipment is su: merged sucsequent to Cesign Bases Events, Impell engineers s:ecifically identified in the plant ail equipment locatec below ::stulated flood l evel s. Upon identifying this equipment, further evaluations wnere perder- ed to determine if this equipment should be qualified for suomergence.
The results of this evaluation and a list of reference documents upon wnich it was basec are provided in the enclosed. Sheuld there be any questions regarding tha enclosed please c:ntact me at your earliest convenience, i Very truly yours, 44 # . /.4ll:' % Newell K. 'iooward Project Engineer NG/j m 1 c:: R. Bergeron (PSNH) J. Salvo (YAEC) 00
- s sac ro -c v 0v. te ao . vt."c.t. st.s ve t< u m . . sie. 4:: ): C lO
i l SLNMARY OF CLASS 1E ECUIPMENT SUBMERGED AS A RESULT CF DESIGN BASES EVENTS , E:ui:een: Vaul ts: Flooding in :ne E:ui: cent Vaults results frem a Mocerate Energy Line Brean (MELS). The flood elevation is (-)S5'-11" (Reference 1. Taoie l 3-2). Class 1E equiceent locateo below the flood elevation in tnese ; arear is ciscussec celow. 4 Pum:s CSS-7 9A and CSS-P-93 and pressure transmitter C35-PT-2314 are I located below tne flood elevation, but are not required for mitigation of the MELS (Reference 2, p.12), and are designated There fore , in Reference 3 as Oceraoility Coce C for tne MELS. submergence qualification need not be addressed. . The cable to instruments RH-FIS-610 and RH-FIS-611 has been supplied under F.0. 9753-006-113-17 and is located below the flood elevation. These instruments will not be submerged, but are required to mitigate the MELS (Reference 3). Therefore, su mergence qualification will be addressed for tnis cable. The cable codes are A01P and A02P for instruments RH-FIS-610 and 611, res;:ec ,1vely. Containment Building: The flood elevation in Containment is (-120'-8" (Re'erence 1). Flooding does not occur in environmental zones locatec Class 1E equiccent CS-3 CS-11, belowCS-12 tne flood and CS-13 (Reference 4). elevation in those areas of the Containment Building wnere flooding is postulated to occur is discussed below. Transmitter RC-FT 446 perforns no safety function subsequent to a LCC A or MSLS and is Operability Code C for these events (Reference 3). The equiceen listed belcw is installed belcw flood level but justifications fe. not addressing submergence qualifica:icn is provicec in RA: 430.62 (Reference 5) . CS-V -163 5:-FY-2427 RH-FY-2426 RH-IS-28 RH-FY-2164 SI-IS-2433 RH-ZS-27 51 rY-2416 SI-IS-2403 SI rY-2423 51 -Z 5-2413 SI-IS-131 RH-IS 49 51-Z5-134 SI-IS-160 SI-IS-2423 RM-RM 65353
$!-FY-24C9 pay 7 7
Gems c:ntainment buitding level transmitters C35-LE-2384-1 and CSS-LE-2385-1 are installed belcw tne flocc level, but will be qualifiec for submergence. Equipment 1.0. Nos. RC-TE-1318 anc RC-TE-1323 are also installed Delcw ficoc level. However, this equi: ment anc its camle is enca:sulated in a stainless steel snea:n anc will n:: :e affectec ty su: mergence. Instrument racks MM- R-1 ar. MM-IR 4 centain the Class 1E anc non IE equi;t:ent snown below (Re'erence 6). ! % :R 1 SI.FY-2404---.-l RH Y-2126-----! NG-FY a605 l SI-FY-2423 l SI-FY-2401 l ---No n 1 E RH-FY-2463 l---1E CS-FY-7400 l SI-FY-2427-----I RH FY-2407-----I . MM-!R 4 C S - FY -7 417 ----- l S I -FY - 2416. ---- l ---1 E RH-FY-2408 l RH-FY-2464-----l RMW-LY-17 8 i CS-FY -7 418 1 CS-FY-7419 l CS-FY-7403 i CS-FY-7447 l---Non 1E NG-FY-4608 i SI-FY-24C6 i I CS-FY-7413 SI-FY-2431 CS-FY-7 412 SI-FY-2434 i RC-LY 459-B l C S - FY-7 414 ----- l Per RA! 430.62 (Reference 5), all the above listed Class 1E equipment 1ccated on racks MM-IR-1 anc KM-IR 4 need not be accressed for su: mergence qualifica:1cn. For the ecui men: listed belew, the electric 41 cable to the equi: ment is ne cnly item submerged. Reference 3 snews
- ta :nese transmitters are C:eracility Code C for :ne Oesign casus evestS wnten cause ficccing insice containment. Thertfore, ne caole to :nese instruments neec not me cualifiec for submergence.
RC FT 415 RC FT 416 RC-FT 444 . RC-FT 434 RC-FT 435 RC-FT 436 RC FT 446 Y f7Gr y c .3 C
The caole to CC-FT-2175A is below flood level., However, tnis Them 41 Barrier Cooling System transmitter is ex;ected to be cesignated as 0:eracility Coce C and therefore, this caele need not ce qualifiec for su: mergence. The essles to valves SI-V-17, SI-V-32 and CS-V-149 are below tne f1::c level. A review of tne UE&C CASP sorting system snows ina: :ne follcwing l caole c:ces anc purchase orders are asscciated witn :nere valves, i l Valve Noce Cable No. Caols Coce P.O. I S I -V-17 V40 H15-Va0 K2J 111 H 41 -V40 AG2P 11b-03 17 H41 -V40/1 AC2P 113-17 H41-V40/2 A029 113-17 H41-V40/3 A32P 114-17 H55-V40 MA7R - 113-18 SI-V-32 V41 H18-V41 BC1J 113 03 H35-V41 A317 113-17 H 35-V41/1 A01P 113-17 H35-V41/2 A017 113-17 H35-V41/ 3 A31P 113-17 , H45-V41 MA6R 113-20 C S-V-14 9 V21 H19-V21 BCIN 113-03 H36-V21 A31P 113-17 H36-V21/1 A017 113-17 H36-V 21/2 AB1P 113-17 H4A-V21 MA6R 113-20 Submergence qualification will be addressed for tnese caeles. Mechanical Penetration Area: F1 coding in the Mechanical Penetration Area results fecm a ItELS. The ficoc elevation is (-)25'-11" (Reference 1, Taele 3-2). There are tnree items of Class 1E equi; ment locatec selcw flecc level tna are required to function wnen summergec. They are MM IR-17, RH-FT-618 anc RH-FT-619 (reference 3) . Rack MM-IR-12, ' ., t: ries, and tne transmitters are not qn=11fies for su:mer;en:o em 't , 1: is rec:mencec :nat they be relocatec aseve flocc level u .s - (* .an :e sn:wn :na c;eraoility f'of the MEL3 is not requirec. The Class 1E ecui; ment listed below is also insta11ec bel:w f t:cc level out is cesignated 0:erso111ty Code C for :ne MELS anc neet no: :e qualiff ec f:e su: mergence concitions (Reference 3). SI-FY-2419 C35-IS-2307 1 CSS-IS-2306-2 C35<T(-101A C35-TA -1013 C35-V-3 CBS-V-14 0 4I c' ff-
Terminal boxes EDE h3X-Y31, Y32, Y33, Y34, Y35, and Y36 are insta11ec : below flood level, but service only ne CSS equi; ment snown acove. Since
- ne above equipment need not func 1cn wnen su:mersec, tne ar;ument can ce mace na: tnese boxes also neec not function wnen summergee, however, Reference 3 designates nis ecui,=ent as Co. C ce A f:r all events. ::
is ree: emended tna :ne c:sracility cece for :nese boxes ce evaluatec fer enange :: C:. C:ce C f:r :ne MELS. The fo11cwing conduits are located belcw flood level: HVJ/RA 40C/RA, 4UA/RA, 4TZ/R A HTX/V A, 4TY/RA and 4VM/RA. A review of tne UEiC CASP sorting system sncvs tna ney carry caeles to RH-V-70, CS-V-142, CS-V-162, CS-V-166 anc MM ;R-12. A review of the Reference 3 Harsn Envir:nmen- Equi; men: Li st, snews ina only MM-IR-12 must func: ten curing tne MELS wnten causes su: mergence. Tne caoles associated witn :nis equi; ment anc :neir purenase orcers and caole codes are snewn belew: Caele No. Ca31e Cece Reel No. P.O. F2 6-GX8 AGli C5-11 113-17 GX8-L37 AG1P C5-20 113-17 F AS -GXS MA6R EU-118 113-06 FAS-GX8/1 MA6R EU-32 113-06 I F A6-GX8 "16R EU-30 113-06 . FAS-GX8 ' A6R EU-30 113 06 GXB-GX9 MC6R EW140 113-20 As instrument rect MM-IR-12 is also submerged (see 15: ;aragra:n of tni s section), tne resolution for the attacned casle sn: 1: De c:nsistent wi:n
- nat proviced for tne rack.
Main Steam and Feedwater Pi:e Chases: The only Class 1E equipment installed below tne HEL3 flood level (5'-5) 515, 544 anc 545. Per Reference (Reference 3, tney must 1. function during a HEL3. Table 3-2) is Fd-PT-514,They are not qualifiec fo submerged c:ncitions. These instruments are locatec on rac(s MM-IR-52A anc MM IR-523, wt;ose junction boxes are above flocc level. If relocated, care snr od N 'aken :nat tneir associated rack wirina is also relocatec 4:ove ' 1a f1 M c evel. RM-RM-6481 is siso located Defcw f1coc level, eut it is o; muir to to function wnen s : merged (Reference 31. Tne es:les :: valves MSD-V 44, MSD-V 45, MSO-V a6, and MS;-V 47 are : ele
- ne ficoc level . This e:ui: ment must function for HE' 3 events (Referen:t 3). Fr:m a review of tne UE&C CASP sorting system, :ne f 11: wing :a:1e ceces anc ;ur: nase orders are assc:iates witn :ne varicus valves.
Valve Noce Cable No. Cable C:ce F.C. CCO V!2/4 AG1P 113 17 M50-V 46 VE2 113-17 F27-VE2 A31P VE2 2X4/1 A31P 113 17 OCO.VE2 / 3 SC1N 113 C3 QQ, .$ CSS
valve Node Cable No. Cabl e Cc,g, P.O. Mg:-V-V45 VE1 CC3-VE1/4 AG17 113-17 F27-VE1 A31P 113-17 Gl u-VE1 A367 113-17 vel-IKa,1 ABl? 113-17 CC3-VE1/ 3 BC11 113-03 f MSD-V 44 VC0 CCS-3V0/4 AG1P 113-17 r27-VC0 A317 113-17 V00-IK2/1 AB1P 113-17 GY3.V00 M6A 113-23 003-VOC/3 51N 113-03 MSO-V 47 V!3 GY3-VE3 MA6A 113-20 001-VE3/3 BC1N 113-03 001 -VE3 /4 AG1P 113-17 F27 "E3 ABIP 113-17 YE3-IK2 A31P 113-17 TMse cables will be analyzed for 4utmergence. Three additional conduits are located belew flood level They are FUD/V A, FJG/VA and FJF/V A. A seiren of tne UE&C CASP sorting systems snows that tnese concuits carry caeles JW4-U:6 anc .iW7-Utc. The caele coce is MA6R anc the purenase orcer is 113-20 for be:n casles. Thi s caele coce is alreacy being evaluated for suomergence as it is attacnec to tne MSO valves listed amove. Cna cable tray runs north to south at elevation 4'-6 in tne ess pi:e enase. The tray, martec 86J1VA taru 86R1VA, contains cables wnien coerate both Class 1E and ncn IE equipment, seme of anten must operate during tne event wnica causes flocoing. For example, by using tne UEIC C A3D Sorting Systens, c2ble FS7/QV7 supplies powvr tu :nstrument VS-YT 6822. Fr m Reference 3 it can be dete**.ainec that tnis e uipment mus: functi:n curing tne HELB whicn causes the floccing. Therefece, snis ciele must function curir; the event also. Since :nese caoles are in an oct9 tray and Onere is no sera'.icn, all caeles in :nis tray are essamec to nave to remain intact ur submergenet :encitiens. Therefore, suceergence qualification wi . be accressed. A review of :ne UE&C CASP sortina fr al$ sy ine Jtemcaele snows the following containec ;urenast in nts tray. orcer numoers anc caele ceces Caole No. Caole Coce Reel No. P.O. 3, F Al / GLS MBir E '.'-0 6 11 i F A6/GL5 MA6A F.u-40 113 ,6
.lc
- F AS /53 C MA6A EU-34 11;-06
? 4, .' FA7/GL5 MA6R EU-34 113-06 N-i ^ F 47
- 0 MA64 EU 40 113-06 F37/GXS E;-06 113-06
/p F37/GX7 MS1R MSIR E -02 113-C6
$jv,j ,f FC1/GX6 MC;R EI-0 2 113-06
' g.*
FC1/GX. MIR E -02 413-06 (e
Caele No. Cable Code Reel No. P.O. FC1/GX7/1 MA1R EC-07 113-06 FC5/GX6 MA6R EU255 113-20 t FJC/GL5 MB6R EV-17 113-C6 FJ7/GL5 MA6R EU-32 113-06 ; FRS/H33 VC64 EX249 113-2C FRS/H49 VC6R EX250 113-20 FRS/M9/A VC6R EX249 113-20 FRS/H49/S VC5R EX136 113-20 FRi/H49/C VC6R EX-25 113-20 FRS/H49/0 VC64 EX2!1 113-20 FRS/H49/E VC6R EX253 113-20 FRS/H49/1 VC6R EX249 113-20 FR5/H49/2 VC6R EX250 113-20 FRS/H49/3 VC6R EX-25 ' 113-20 F RS /H49/4 VC6R EX249 113.-20 FR5/H49/5 VC6R EX249 113-20 FR5 /H49/6 VC6R EX249 113-20 FRS/H49/7 <C6R EX250 113-20 , FRS/H49/8 VC6R EX-25 113-20 , FR5/H49/9 VC6R EX249 113-20 F R5/JW4 MD6R EW164 113-20 1 F'tS/JWA/1 MD6R EW169 113-20 FRS/JW6 MC6R EW162 113-20 FRS/JW6/.1 MC6R EW162 113-20 FS7/0V7 MA6R EU224 113-20 FS7/0V8 MA6R EU224 113-20 F20/GX6 MA1 EC-02 113-06 < F20/GX6/1 MA1R EC-07 113-06 F20/GX7 MA1R EC-02 113-06 F20/GX7/1 MA1R EC-02 113-06 F36/SSE MA6R EU315 113-20 F60/GX6/1 MDIR EE-02 113-06 F60/GX7/1 MDI R E E-01 113-06 F77-GX6 NR1R FJ167 113-20 113-20 F7 7-GX7 NR1R FJ167 i F77-HM4/4 M01R EE-01 113-06 GL4/XF7 MD6A EW241 113-20 GX6/SW7 M56R E'l-f5 113-18 GX6/SW7 /1 MC4R EW371 113-20 GX6/SW7/2 MC64 EW371 113-20 GX5/IV0/1 MA1R EC-C8 113-C6 GX6/IV1/* MA1R EC-08 113-06 GX5/X3/1 MA1 R EC-08 113-C6 GX5/!1B/13 MA1R EC-02 113-06 GX7/GY1 f MC6R EW229 113-20 GX7/JW7 MC6R EW229 113-20 GX7/J'# /1 M564 EV-25 113-18 GY3/H2U !G6R EV349 113-20 G23/GLS MA6A EU311 113-20 G2G/GX5/5 M01R EE-02 113-06 G23/GL7/5 M01 R EE-G1 113-06 GIM/GL5/1 MA6A EU223 113-20 1 gr '"I Ok 7
Caele No. Cable' Code Reel No. P.O. G37/G3U PN60 JJ-01 113-06 . G3U/G3V PH60 J 0-04 113 06 Wa/JWa MS6R EV-25 113-18 H2M/093 VC6R EX318 113-20 ' 129/ 36 MA6R EU224 113-20 129/!36/1 N67 FH395 113-20 130/153 MA6R EU227 113-20 130/;36 MA6R EU-29 113-06 JW4 /P01 MA6R EU261 113-20 JWa/T6R MA6R EU255 123-20 JW4 /VRS MA6R EU-67 113-18 JW4/VU7 MA6R EU-97 113 06 GX7/I'4 /1 MA1R E0 06 113 06 GX7/IW3/1 MA1 R EC404 113-20 GX7/I%5/1 MA1R EC404 113-20 GX7/Z'J/1 MA1R EC-06 113-06 JW7 /P91 NR6R N 05 113-20 ! J'n7 /RC8 MA6R EU316 113-20 ' 4 JW7 /VR9 MA6R EU223 113-20 JW7/VU8 MA6R EU-28 113-06 JW7/V20 MA6R EU25f 113-20
, JW7/ZW7 MD6R EW241 113 20 -
JW7 /IX2 MD6R EW-24 113-06 JZ6/TOA ZA6R Not pulled as of 1/30/86 JI6/TCB IA6R JZ6 /T92/1 VC64 EX-25 113-20 JI6/T93/1 VC6R EX250 113-20 JZ7 /T92/1 VC6R EX200 113-20 JZ7/T93/1 VC6R EX212 111-20 Q20/025 MS6R EV-30 113-13 020/025/1 MA6R EU-62 113-18 024/025 M86R EV-29 113-18 . Q24/125/1 MA6R EU-23 113 06 l r i 4 [ [ ( l i
4 REFERENC ES
- 1. "Environmental Qualification of Electrical E:ui: en: :::e :an: :s ,
Safety *, Seacroca, Sta:1cn, Revision 2. Cc::cer 31,1985.
- 2. "Mccerate Energy Line Break Study", Seacreek Station, TP7, Revision 4 Maren, 1985.
L 3.
"Harsh Environmen Equi:eent Li st", UEiC Orawing 9763-M-3C0218, Revision 002, January 20, 1986, 4 "servica Envir:n=ent Chart" UEIC Orawing 9763-F-3CC219, Revisien i 17, July 22,1985.
- 5. Seacrook Statien FSAR, Menement 56, RA! 430.62.
G. "Class 1E Equiement List", UEAC Orawing 9763-M-505300, Revision 017, January 20, 1986. i 4 I v i 1 l 4 e P l
- - - - - * -- -,, -- - . - - - - s -, . - a -s-- - -- - -
)
1 1 ( i 2 R w O
fri.E hlG. ll b'l5 C l QM (?EFE2EWCE IC Test Procedure No. 24843-89N Page Nos. 24 Revision 1 dated 22 June 1988 TEST PROCEDURE FOR ENVIRONMENTAL QUALIFICATION TESTING OF COAIIAL INSTRUMENT CABLES (RG 58) FOR NEW HAMPSHIRE YANKEE A DIVISION OF PUBLIC SERVICE CO. OF N.H. P.O. BOX 300 SEABROOK, NH 03874 Purchase Order No. 61917 Prepared by: [N Date ^8
, aria @ .~ Drain,'NEQ Project Engineer /
NTS/Acton 533 Main Street, Acton, MA 01720 Reviewed and - Approved by: ' - M Date -
'G' _Rhittles,'En eer!.ng Manager KT/ PRO /2484389N.NHY
REVISION RECORD REVISION PAGE PARA. CHANGES OR APPROVED DATE MUMBER MUMBER NUMBER ADDITIONS g BY l I O --------------rIRst issue------------------------
'06/21/88l cover '
add: Co. of NH g sheet j 1-1 1.0 chng: degradation per- N formance to degration g 9 ., of performance chngswill not be com-ducted to is not required
!chng: 50,40 to 50.49 '
f 2-2 2.0 chng: 1973 to 1988 and 1977 to 1988 [' - g g del: 1st clause, 2 r.d sentence, 2nd para. f /
,, l l 3-1 "3.0 'chng: Implementation '
I to Instrumentation ) g g add: Seabrook cable code. o g chng:11mited DBE to , Test Spares I !. I 4-1 .0 add runctional to l l4 step 5 , I I 5-1 5.1 chng: Forwarded to, to provided to ,
, l ,
l,dels for their evalua , ,
; tion and approval Test Report No. 24843-89N
hf I REVISION RECORD !. REVISION ' PARA. CHANGES OR PAGE DATE NUMBER MUMBER MUMBER ADDITIONS ' APPROVED I BY l 0 --------------FIRST ISSUE------------------------ 06/21/88 5-1 '5.? addioach test item will
! be secured....
gehngstransmitted to 4 j provided . gg dels for evaluation p 6-1 6.0 chng: service temp to
, design conductor temp.
' add: Irradiated add:specified by NHY g
i i chng: 1.29 to 1.26 add: design conductor
' temp activation energy
),k -
' ({
l , chng: was to were
, dels the 1.29 ev activation energy... ,
, ,9-1 "9.0 ' add:A N.H. Yankee i I' j I representative... j j 1
l10-1
, 10.0 add: A l l , ,'10.2 gehng: The four to eight chngswill be to were u
l l u previously li l 'addisee section 5.1 l j !" , delt each test item i l will be... l l; I l, add: 4 aged specimens and l
! . !'four unaaed... ! l Test Report No. 24843-89N-
Y . e REVISION RECORD i REVISION PAGE PARA. , CHANGES OR ; APPROVEDj l DATE MUMBER lMUMBER. NUMBER I ADDITIONS , i BY ! l . . _. 1 0 -------------..rIRsr Issue------------------------ l !06/21/88l ' 10-3 10.4 lchng: changing to ' l charging I 10-3 10.4 adds as shown in fig - l 10-5. ,. . l adds at approximately... J ! 10-4 10.4 delt due to the l , duration... l dels circu). g add drop e.ross the g monitoring circuit
, load del 30-day LOCA 10-5 figure chng to reflect 30 day ) r l test not 100 day test g j j I
10-7 10.7 , adds shown in the flg.! ! l , on page 10-5 '
))'
11-1 l11.0 ' dels subsequent to ,
, LOCA testing... l'
. add: Post LOCA kt
;' functional testing I' 'I shall consist of...
I , i
'A-1 l dels a l l ! del: , and as e
' ' ?
' l'chng: all to ALL l add: will l l 1 i
, A-1 to h ladd: T.E. List ! '
l i i- A l l l . l ! ! ! ! ! l Test Report No. 24043-89N i
i Y TABLE OF CONTENTS SECTION PAGE NO 1.0 PURPOSE 1-1
2.0 REFERENCES
2-1 3.0 TEST ITEM DESCRIPTION 3-1 4.0 TEST SEQUENCE 4-1 , 5.0 BASELINE FUNCTIONAL - 5-1 6.0 THERMAL AGING 6-1 7.0 POST-THERMAL FUNCTIONAL 7I 8.0 RADIATION EXPOSURE 8-1 9.0 POST-IRRADIATION FUNCTIONAL 9-1 10.0 LOCA SIMULATION 10-1 11.0 POST-LOCA FUNCTIONAL 11-1 APPENDIX A - REPRESENTATIVE TEST EQUIPMENT LIST A-1 t Procedure No. 24043-89N Page No. 1 1
1.0 PURPOSE The purpose of this document is to describe the procedures which shall be followed during environmental qualification testing of ten (10) ITT Surprenant RG 58 Coaxial Cables supplied by New Hampshira Yankee. Section 3.0 of this procedure provides specific identification of the subject test specimens. The intent of the test program is to evaluate the performance and durability of the coaxial cables during and fo! lowing ecposure to postulated in-service and end-of-life accident environment simulations. Qualification acceptability of the cables will be dependent on their ability to withstand the specified environmental simulations without loss of physical integrity or degraustion of performance capability. As detailed herein, the cable qualification program shall be l conducted in accordance with the guidelines of IEEE Std. Nos. 1 1 320-1974 and 383-1974. Per the stipulation of New Hamprhtre l l Yankee, the vertical flame test described within Section 2.5 ot IEEE 383-1974 is not required for any test specimen. The subject program shall be conducted in accordanco with the provisions of NTS/Acton's Quality AsFurance Manual. ThiS f r.c t shall ensure compliance with all pertinent provirions of 10CFR, Part 21, luCrh, Part 50.49 and 10CFR, Part 50, Appendix B. Procedure No. 24843-89N Page No M
f 2.O RE F E R (!!CK_.EKGE&ILQt!S_.&l!Q._QQfdif1ElfIS 2.1 New Hampshire Yankee Purchase Order No. 61917. 2.2 IEEE383-1974 Institute of Electrical and Electronics Engineers, Standard for Type Test of Class 1E Electric Cables, Field Splices, and Connections for Nuclear Power Generating Stations. 2.3 IEEE323-1974 Institute of Electrical and Electronics Engineers, Standard for Qualifying Class I Electric Equipment for Nuclear Power Generating Stations. 2.4 10CFR50 Appendix B - Quality Assurance Criteria for Nuclear Power Plants and Fuel Heprocessing Plants (1988). 2.5 10CFR21 - Reporting of Defects and Noncompliance (1988). 2.6 10CFR50.49 - Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power Plants. 2.? HEP 160 - Environanental Qualification (EQ) Program. Procedure No. 24843-89N Page No. M
) _
i l l DM 3.0 TEST ITEM DESCRIPTION rour (4) Couxial Instrumentation Cables shall be subjected to the environmental and performance tests described in this procedure. Each cable shall be inspected upon its receipt at NTS/Acton to document the pre-test condition of each test item. Each item shall be tagged with a unique identification number. This number will remain unchanged throughout the test program. The test specimens shall consist of: Cable Type: Coaxial Manufacturer: ITT Surprenant Cable Code: TA6Y (Seabrook Cable Code) Cable Color: Black w/ Red Tracer Ssmple Length: Fifty (50) feet No. of Sar.ples: Ten (10) The test samples will be numbered one through ten and will be divided into test groups as follows: Group No. Aaed Unaged DBE Exposure 1 1, 2 7, 8 30-day LOCA Simulation 2 3, 4 9, 10 Limited DBE Test (Optional) 3 5, 6 N/A Test Spares Initially, only the Group I test specimens will be subjected to the test sequence described in Section 4.0 of this document. The remaining test items will be rese rved for any additional testing which might be deemed to be required by New Hampshire Yankee. Procedure No. 24843-89N Page No. 1-1
l Y 4.0 TEST ITEM SEQUENCE Following receipt and inspection, the cables shall be ! subjected to envitonmental and performance testing in the following sequence:
- 1) Baseline Functional
- 2) Thermal Aging
- 3) Post Thermal Aging Functional j 4) Irradiation
- 5) Post-Irradiation Functional
- 6) Cable Preparation and LOCA Setup
- 7) LOCA Simulation
- 8) Post-LOCA Functional r
i i l l L l I I i l
+
I l Procedure No. 24843-89N l i i Page No. 4-1 L E l
5.0 BMLF&lNE FUNCTIONAL Subsequent to receipt and inspection at NTS/Acton, the cables shall be subjected to Baseline Functional Testing. The results of these tests shall be used as a benchmark for comparison to the results of similar tests at critical points in the test program. This process shall provide a means of monitoring cable performance characteristics in order to identify and qualify any test item deficiency or verify qualification acceptability. 5.1 Continuity Check Using an ohmmeter, each conductor and shield of each cable shall be checked for continuity. Results shall be I recorded on test data sheets. Acceptance criteria The measured values (a total of twenty) shall be recorded on a test data sheet and subsequently provided to New Hampshire Yankee. 5.2 Insulation Registanqs i The cables shall be wrapped around mandrels having a diameter of approximately twenty times the cable diameter. ; Each test item will be secured to its mandret via Sager TY25M Tyraps. A minimum cable length of ten feet shall contact the mandrel surface. Insulation resistance measurements shall be made between the center conductor and Procedure No. 24843-89N Page No. 1-1
5.0 BASELINE FUNCTIONAL (continued) 5.2 Insulation Resistance (continued) the shield, and between the shield and the mandrel. The insulation resistance test shall be performed by applying a 500 Vdc potential to one conductor for a minimum of one minute. Af ter the one minute energization, the insulation resistance shall be measured using an I.R. Bridge and the l results shall be recorded on data sheets. Acceptance Criteria The measured insulation resistance shall be acceptable if it is greater than one megohm. The data chall be provided to New Hampshire Yankee. Procedure No. 24843-89N Page No. 1-2
N 6.0 THERMAL _ AGING Subsequent to the Baseline Functional Test, the cables shall be subjected to thermal aging. The cables shall be placed in a forced hot air aging chamber as attached to the mandrels. Only the test cables and spares (six cables total) shall be in the aging oven during the aging process. Aging temperature shall be monitored and recorded a minimum of twice daily. Thermal aging duration is based on the following information: Design Conductor Temp. = 167'F (750C) (specified by NHY) Weak-Link Material = Irradiated Crosslinked Polyethylene Activation Energy = 1.26eV (150'C) (specified by NHY) Aging Temperature = 302*F (specified by NHY) Aging Time = 168 hours (specified by NHY) Qualified Life = 40 years The previously listed design cor.ductor temperature, activation energy, aging time and temperature were specified by New Hampshire Yankee, based on existing qualification data provided by the manufacturer for the identical cable insulation and jacketing materials. Procedure No. 24843-89N Page No. f..1
7.0 POST THERMAL AGING FUNCTIONAL A New Hampshire Yankee representative may be present at NTS/Acton to witness the post-thermal aging functional test. Following complotJa.i of thermal aging testing, the test cables shall be subjected to identical functional tests as those specified for baseline functional testing, except that the cables and mandrels shall be submerged in tap water for a minimum of one hour prior to the insulation resistance test. Procedure No. 24843-89N Page No. 7-1
M S.0 PADIATION Subsequent to the post-thermal aging functionals, the test samples will be packaged in two cardboard boxes. They will be placed carefully An paper insulation to protect the samples during shipping and handling. The box containing the test samples will be shipped to Isomedix's radiation facility in Whippany, New Jersey and tested in the sealed box. At Isomedix, the specimens will be exposed to a Cobalt-60 gamma field at a dose rate not to exceed 1.0 x 106 rada per hout providing a T.I.D. of 2 x 108 rads +10% (2.2 x 108 rads). Halfway through the exposure, the specimens will be rotated 100 degrees to insure a more uniform dose. Dosimetry will be performed using Harwell Red Perspex dosimeters, utilizing a Bausch and Lomb Model 70 Spectrophoto-meter as the readout irstrument, or an equivalent dosimetry system. This system which is calibrated directly with Atomic Energy of Canada, Limited (AECL) is traceable to NBS. A copy of the correlation report will be available upon request. Irradiation will be conducted at ambient temperature and pressure for the Isomedix facility. Procedure No. 24843-89N Page No, M
Y 9.0 POST-IRRADIATION FUNCTIOK4 A New Hampshire Yankee representative may be present at NTS/Acton to witness the Post-Irradiation funtional and unpacking prior to LOCA simulation. Subsequent to completion of the garna irradiation exposure, the test specimens will be subjected to the identical functional tests as those specified for baseline functional testing, except that the cables and mandrels shall be submerged in tap water for a minimum of one hour prior to the insulation resistance test. 1 { i I { k I i l Procedure No. 24843-89N Page No. 1-1 l
10.0 14CA SIMULATION The following test will be performed to simulate the postulated LOCA at the end of the cable service life. 10.1 Calibration RED Prior to perfo mirig the LOCA test, a calibration run will be performed to demonstrate system capability. The calibration run will be pe rformed to the transient conditions. A New Hampshire Yankee representative may be present to witness the calibration run, if desired. 10.2 Test Fluturina Eight cable test specimens, each approximately ten feet in length, were previously wrapped around a steel mandrel whose outside diameter is approximately twenty (20) times that of each test item (see Section 5.1). Four aged specimens and four unaged specimens shall be placed in the LOCA Chamber. The eight specimens. shall be divided into two groups, each group having 2 aged and 2 unaged specimens. Both groups shall be subjected to the margin transient and 15 days of the 30 day LOCA test. At the 15 day mark, at New Hampshire Yankee's option, the LOCA test shall be interrupted and both groups of specimens shall be subjected to continuity and an immersed Insulation resistance test. One group shall then be removed and subjected to a voltage withstand test, as described in Procedure No. 24843-89N Page No. lQ-L
10.0 LOCA SIMULATION (continued) 10.2 Test Finturina section 11.0. The remaining four samples shall then be subjected to the remainder of the 30 day LOCA test. The fixtured test unito will then be placed onto a horizontal metal base inside NTS/Acton Test Autoclave No. 1. The cable ends will be trimmed to permit electrical measurements from outside the test autoclave. The cable specimens will be of sufficient length to allow each specimen to be brought through a sealed autoclave
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penetration without need for any' special connection within the autoclave. The heinimum test specimen length physically located in the autoclave shall be 30 feet. 10.3 Test condition Monitorina NTS/Acton will use three (3) Type "J" thermocouples to monitor the LOCA simulation test. One thermocouple (T I) will be placed approximately 2" from the steam outlet, one thermocouple (T2) will be placed one inch off the test fixture on the left hand side neair the steam outlet, and one thermocouple (T3) will be placed on the right hand side furthest from the steam outlet approximately one inch off f the test fixture. t Autoclave pressure will be monitored using a calibrated pressure transducer. I i i Procedure No. 2_(843-89N Page No. 1Q,_2 i
Y 10.0 y)CA SIMULATION (continued) 10.3 Test Condition Monitorina The environmental test conditions will be monitored during the LOCA simulation using a Gould Strip Chart Recording System (or equivalent instrument). 10.4 Test Item Londina Each test cable conductor will be energized with an AC potential of 600V at a test current of 1.0 amperes per conduc trar . The cable shields, mandrel and test vessel will be at ground potential . The test circuit will be designed l such that the applied potential will be interrupted if the leaking / charging current exceeds approximately 1.0A. 10.5 Test Item Monitorina l The test items will be energized as detailed in Section 10.4 during the LOCA simulation with the following l exception
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The circuit will be de-energized to perform I.R. measurements as detailed in Section 5.0 of this procedure at ! the following test inte rvals , as shown in the figure on page 10-5: l i
- 1) After interconnection c the tost specimens and placement of the samp?.s sito on the base fixture, test specimens submerged.
- 2) At the test tempe ra t u re of 346*P, as time permits, at approximately the 1.5 hour mark.
Procedure No. 24043-E18 Page No. 10-3 '
10.0 IX)CA SIMULATION (continued) 10.5 Test Item Monitorina (continued)
- 3) At a minimum of once per day during LOCA. If the IR reading monitored drops below 1 megohm, the recovery of the IR reading to megohm will be determined as a function of temperature by more frequent monitoring of readings within this period.
- 4) After LOCA, at ambient conditions, while still fixture in the autoclave, with the specimens covered with water.
Voltage drop across the monitoring circuit load will be monitored continuously during tho test. If failure occurs during the LOCA test, the failed test sample (s) will be identified utilizing the insulation resistance measurements described in this section of this procedure. Subsequent to isolating the failed sample (s), it will be jumpered out and the test circuit reenergized. This action would be a contingency plan allowing NTS/Acton to aidress failure if failure occurs. New Hampshire Yankee will be notified as soon as possible if failure occurs. 10.6 Chemical Soray ' The test cables will be subjected to a chemical-spray exposure based on the pec'ile specified. Presh chemical spray will be used for a minimum of one l (1) hour at each dwell at 346*r(174*C); thereafter, the spray solution will be recirculated from the pool of solution collected in the bottom of the vessel. The , Procedure No. 24843-81N Page No. LQ-i
346*F(174*C)/113 tbs /in2 (779tp ) 2 390'F(199'C)/113 tbs /in g779pp,) , h -!NSULAT!DN 346'r(174*C)/113 tbs /in2 (779(pg) ISTA CC 199 - 390 - s , p 335'F(168'C)/95Lbs/in 2 (655kPa)
.317'F(158'C)/70lb[/in (483kPa) 17 4 346
( h 280'F(136'C)/35 tbs /in 2 (24kPa) {158 {317 W w 138 W g 200
* *: 230*F(110*C)/10 tbs /in 2 (69kP 2 HR-w w DROP r 110 - 230 TO ,
I (60*C) - "CE _ R day 1HEMICA JEMICAL HUMID sPRA SPRAY CONDITIONS I 2.25 10,2 5 60 140 DAYT DAYS , [" _ 0 12 H!N 3 HR 0 12 MIN 3 HR 5 24 54 P46 HR 30 DAYS RESET T!MER u ALL PRESSURES ARE j PRETEST TEMP GAct pRgssyngs I ELAPSED T!ME J l Procedure No. 24843-89N Page No. E j
10.0 LOCA SIMULATION (continued) 10.6 Chemical Soray (continued) chemical spray will consist of 3000 ppm boron as boric acid, 0.064 molar sodium thiosulfate, and sufficient sodium hydroxide to obtain a pH of 10.5 at room temperature. The spray shall be applied at a total flow rate of 0.63 gal / min, which is calculated to provide a spray f.ntensity of approximately 0.15 (gal / min)/ft 2 over the cylindrical area of the mandrels, a l Procedure No. 24843-89N Page No. 10-6
Y 10.0 LOCA SIMULATION (continued)
, 10.7 LOCA Simulation The LOCA Simulation will consist of injecting saturated a
steam into the autoclave to achieve the temperature / pressure profile shown in the figure on page 10-5. Due to the length of the fixture, and autoclave volume, Acton anticipates varying temperatures internal to the , autoclave during transient conditions Therefore, thermocouple placement has been designed to demonstrate a general test condition envelope. Subsequent to achieving the transient condition i i the chemical condensate will submerge NTS/Acton's immersion heater and saturated conditions will be maintained by the immersion heater. At the conclusion of the LOCA test, at ambient conditions, photographs will be taken of the test samples, l i Procedure No. 24843-89N Page No. E
l I i S 11.0 POST-LOCA FUNCTIONALS Post-LOCA functional testing shall consist of continuity checks, and immersed insulation resistance testing and voltage withstand testing. These post-LOCA functional tests shall be conducted on one group of four specimens at the end of the first fifteen days of the LOCA test. The continuity checks and immersed insulation resistance test shall also be conducted for the second group of four specimens at the end of the first 15 days of the LOCA test. The second group of four specimens shall not be subjected to the voltage withstand test at this time. At the conclusion of the complete 30-day LOCA test thu second group of four specimens shall be subjected to continuity checks and immersed insulation resistance test while still fixture in the sealed chamber. Following these two tests, the chamber shall be drained and opened and the specimens shall be visually inspected for damage or deterioration. The specimens shall then be subjected to the voltage withstand test. A New Hampshire Yankee representative may be present to witness all Post-LOCA activities and specimen handling. Acceptance criteria The results of the post-LOCA functional tests will be forwarded to New Hampshire Yankee for their review and evaluation. Procedure No. 24843-89N Page No. M
4bAr 11.0 POST-LOCA FUNCTIONALS Voltaae Withstand Test *** - The cables will be straightened and then re-wrapped around mandrels having a diameter of approximately forty times the cable diameter. The cables and mandrels will be immersed in tap water for a minimum of one hour and subjected to a voltage withstand test for five (5) minutes at a potential of 80 Vac/ mil. The leakage current shall be measured after five (5) minutes of energization. l 1 l I i Procedure No. 24843-89N Page No. J1-2 l l
l l l I l hbY I APPENDIX A - REPRESENTATIVE TEST EQUIPMENT LIST The following equipment is representative of the test equipment to be used during this test program. Acton may use substitutions for test equipment, but the replacement equipment will have accuracies equal to or better than those listed in this Appendix. All calibrated test monitoring equipment used in this project will have certification traceable to the NBS. l l i I Procedure No. 24843-89H Page No. A .1 4
lEST EQUIPMENT LIST Test Report # Page NAME MFR. MODEL SER.NO. RANGE ACCURACY INV.# Cfl DATE , LCD Digital NTS/ CAL-5 OKP01 To 9hr/59 min /59sec Isec/ day FM322 Timer Acton Digital Fluke 8502-03 2215048 100 MV to 100' <0C .003% ML545 Multimeter 100 Micro o' ; to 1 A OC Digital Fluke 8050A 2876259 10 U to 1000 VDC .03% DC ML546 Multimeter 10mV to 750 VAC, true rms + 2 digits O to 20 megohm, res dB volt. Precision Omega CL-505 85014-0740 Type J.K,T E.R.S.B. THRM0 see Mfr ML564 Calibrator CPLE SrtLTR 100 RTD specs MEAS )+ 10V output: 0.5 ma 00TPUf! 0-130 ma input 0 to + 10V input Voltage Reference Heathsen EU16 6742265 0 - 100 VDC 4 ranges f, 3% PD504 Sou rce Power Supply Sorensen ORS 30-1 1549 0-30 VDC, 0-1 amp .03% PD320 Digital PH Meter Orion 701A A52810 6 to 8 pH + .002 ph PD391 Resea rch ,
+;.1 av Digital Pressure Jay 3502-8 10307 0 to 350 psi 11.0 psi PI403 Indicator Flow Gauge Fisher & 10A1755 8103Al- 0.2 to 1.9 GPM + 3% P!416 Porter 004A1
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Pressure Wlancko PP2-3239-1 0 to 350 psi Transducer + 21
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PI411 Heavy Duty OHAUS 20KG-15 lb e n t ... s . n.,.--- I Gm to 20 KGms + 1 gram PP395}}