ML20100R417
| ML20100R417 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 02/13/1992 |
| From: | Graham J SOUTHERN COMPANY SERVICES, INC. |
| To: | |
| References | |
| CIVP-A-096, CIVP-A-96, NUDOCS 9204090068 | |
| Download: ML20100R417 (24) | |
Text
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Joseph H. Farley :melear Flant - Unita 1 and 2 Environmental Oualificat f or - Taped splices LST-NS-2647 F-M.04.09 Mr. J. E. Carlington Alabama Power Company ,
Birmingham, Alabama
Dear Mr. Carlington:
As recuested by Mr. David Joces, attached is SCS-NST's assessment of the environmental cualification of "V" t.,w taped splices found at Plant Farley on certain power circuits.
The aat .nsmeet concludes that there is reasonable assurance that the splices evaluated were cualified and would have performed their recuired safety function under postulated TNP accident conditions.
Should you have any cuestions, please contact me at er'.ension 7955.
Sincerely yours,
, ,m I.
tris-, .r- /
Jacoueline S. Craham Huclear Safety Engineer-IO Approved by:
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. B. long General Manager Nucleer Safety and Fuel JSc/CRP/1g ,9 -12W xc J. R. Crane fr K. C. Gandhi a g B. J. George D. B. Jones
,4' h C. Langford Uh.
.c J. Iove J. N. McLeod y2 f, C. R. Pierce A .,
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R. C. Woodfin/
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.< 0067066 ENVIRONMENTAL QUALIFICATION ASSESSMENT OF "V" TYPE TAPD SPLICES USED AT JOSEPH M. FARLEY NUCLEAR FIANT UNITS 1 AND 2 PRIOR to OCTOBER, 1987 REFUELING.
OUTAGE epATed Byl e d r- ) AT Reviewed Bys M /0 Jf87 Approved By: ,p
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0067067 Table of Contents i "L' I. History y II. Identification of Splices i III. Industry Testing of Taped Splices 1 IV. Assessment 2
V. Conclusion .
5 VI. References 5
1 4
9 e
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______m._______ _ _ _ _ __ _ _ _ _ _ _ _ - - _
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,' 1. History 0007068
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During an E0 valkdown, initiated by E0 findings at another nuclear facility, Alabama power Company (APC) discovered splices in a "V" type .
configuration which lacked adeounte cualification documentation on ASCO solenoid valves, motor operated valves (HOV), and fan motors. Although all of the inspected splices were replaced with oualified Raychem splices a program was initiated to provide reasonable assurance that the "V" type Okonite and vinyl tape splices were cualified for theit service life plus a postulated Design Basis Event (DBE) at the end of that service life.
A conservative assumption was made that the splices were installed during the initial construction of Farley Nuclear Plant (FNP). Commercial operation of FNP-2 was 07/30/81, FNP-1 was 12/01/77.
Based on this assumption a 15 year service life was used.
The NRC was notified of a potential problem by Licensee Event Report No.
LER 87-012-00 on July 30, 1987. Tbrther reviews, evaluations, and testing was conducted concerning the splice issue and this effort described to the NRC during the Environmental Qualification Neeting of September 24, 1987.
II. Identification of Splices During the walkdown as each splice was replaced it was categorized by configuration, composition, and overlap characteristica. A Detail Number was assigned to each splice category to serve as an
(
identification number. The Detail Number is an alpha-numeric designator based on the splice composition (alpha) and tape overlap (secuential nuate r) .
following: The type of tape used on each splice is designated by the T,0konite T-95 Tape N Okonite No. 35 Tape V Vinyl Tape - Scotch 33+
i Table 1 identifies the splices, their location, and cualification recuirements.
of the eouipment Table 2 defines the function and operability reouirements affected.
through 8. Splice illustrations are shown in Figures 1 III. Industry Testing of Taped Splices Several variations of taped splices have been tested by the nuclear industry. Favorable results have been achieved using various configurations and environmental parameters.
the data available on the cualification of "V" Table 3 ' summarizes some of type taped splices.
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, IV. Assessment 0007069 '
( .
The purpose of this evaluation is to demonstrate that the Okonite and vinyl taped splices are cua11fiable and would perform their reouired safety functions under the postulated FNP accident conditions.
A. Thermal Aging The specimens removed from FNP had not suffered any degradation due to natural aging. The specimens evaluated in the Wyle-Ceco reports were subjected to the following thermal aging temperatures and times with minimal recorded degradation.
tbterial Temp Time Life Comments Okonite T-95 115'c 179 bra. 40 yrs. Outer layer became
& No. 35 -
brittle but no evidence of cracking Kerite Tape 115*C 190 hrs. 40 yrs. Outer layer became brittle but no evidence of cracking.
Scotch 17, 70 130*C 279 hrs. 30 yrs. Had a 1/2" long by 1/4"
& 130C deep crack in both the outer and inner layers of tape. However this splice successfully completed the cualifi-cation program.
Scotch 17, 70 130*C 170 hrs. 15 yrs. Changed color from a
'& 1300 shiny black to a dull gray. Tape intact, no cracking.
Scotch 33+, 1130*C 482 hrs. 30 yrs. Changed color from a 130C shiny black to a dull gray. Tape intact, no cracking.
Scotch 33+, 130*C 241 hrs. 15 yrs. Changed color from a 130C shiny black to a dull gray. Tape intact, no cracking.
Okonite T-95 130'c 352 hrs. 40 yrs. Became brittle but outer
& No. 35 layer was intact. Still shiny after thermal aging. .
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, A. Thermal Aging (Continued) 0067070
(
Based on the thermal aging test results schieved by Wyle and other testing groups combined with the fact that the splices removed from FNp-2 exhibited no thermal degradation it can be concluded that the splices in Table 1 were preconditioned to their end of life conditions with no visible degradation.
B. Radiation Aging The specimens removed from FNP did not abow any signs of degradation due to radiation aging. The specimens evaluated in the Wyle-Ceco reports showed no physical changes af ter normal radiation czposure of 16.0 megarada, except that the outer layer of the Scotch tape splices became shiny. In the BVR portion of the Wyle-CECO report the specimens were exposed to an accident dose of 1.21 x 108 rads with no physical changes in the Kerite samples. The Okonite and Scotch tape samples developed a dull film and small cracks on the outer jacketing tape. However, these cracks did not contribute to any splice failures.
In the PWR portion of the Wyle-CECO report the specimens were erposed to an accident dose of 1.84 x 108 rada.
Again there was no physical change to the Kerite samples while the Okonite samples developed a shiny film and small cracks on the outer jacketing tape.
C. Chemical Effects Chemical sprays were present in each of the evaluated test reports (Table 3). Chemical spray did contribute to a test anomaly in the Wyle-Ceco report. Specimens B4, Z11 and Z12 failed due to arcing.
Z11 and Z12 Kerite tape splices failed early into the test but B4, an Okonite splice, failed after 14 hrs. - 26 min. in to the LOCA test.
The Kerite splices arced at a point 6 inches from the splice, where the aluminum specimen tag was attached. The Okonite splice arced at the "V" due to a build-up of chemical spray and water in the splice causing it to arc against the enclosure. Other specimens similar in construction passed the cualification test with no anomalies reported.
While chemical spray does have the potential to cause the curraat to short to ground the spray does not have a caustic effect on the tape.
D. Rumidity NUREG-0588 specifies that the " effects of relative humidity need not be considered'in the aging of electrical cable insulation." Since cable splices are extensions of the cable insulation humidity does not naed to be considered.
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E. Temperature and Itessure (DBE) 0067071
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The maximum composite temperature and pressure for inside containment at FNP are 378'T and 48.0 psig, respectively. All of the test reports evaluated, with the exception of the Fitzpatrick report PEI-TR-840704 Rev B, tested the splices at pressures eaual to or above 50 psig. This pressure adeouately envelopes the FNP pressure recuirements.
The maximum temperature peak of the reports evaluated was 360'F in the Wyle KE017859-02P report. Thermal las analysis, SCS-NSF Calculation F-87-03, has shown that the inner layers of tape would not reach temperatures higher than 360*F due to the short lived temperature peak experienced in the MSLB/LOCA composite curve and the fact that the splices are enclosed in junction boxes or conduit.
F. Operational Recuirements The operational reouirements of the coutpment is considered since reported failure of some splices did occur af ter a significant amount of testing time.
Using the information contained in Table II b, the following equipment have splices which are covered in this evaluation:
TPNS No. MOV No.
01E14V004 HOV 3321B-A 01E23v022B MOV 3528B-A Q1N12SV3235A --
Q1N23SV3227AC --
01N23SV3227BA --
Q1N23SV3227BC --
01N23SV3227CA --
Q1N23SV3227CC --
Q2N23SV3227CA --
Valve 01E14V004 is a containment isolation valve which isolates on a '
Phase "A" signal (FSAR Section 7.3). Such an isolation would occur at the start of an accident, before the containment sprays are initiated. Therefore, the splices in this valve are expected to be operable when recuired during the accident. Per FSAR Table 6.2-31 this valve is not required to function once closed. Therefore, the associated power circuits would not be energized so subsequent failure of the splice would not open the valve.
Valve 01E23V022B is an inside containment isolation valve in the post accident sampling line. The operator may open this valve to perform post-accident sampling post-LOCA. The testing evaluated in this report provides reasonable assurance that the valve will operate when called upon. In addition, an independent sampling .
source is available in the event of valve failure.
I
l
, F. Operational Recuirements (Continued) 0h067072
(
The remaining eauipment is all located outside containment in the Main Steam Room. Ibis area vents to the outside environment.
Therefore, af ter the break is isolated, the area cuickly recovers to ambient temperature and humidity conditions. Therefore, this eautpment will not be in a high temperature saturated steam environment for a long period of time. In addition, testing was performed with a ecustic spray while the main steam room eoulpment experiences no such spray. The testing evaluated in this assessment supports the conclusion that the splices would operate when recuired. This conclusion can be reached because a significant amount of time in a saturated steam environment with a caustic spray was recuired to cause any splice failure.
V. Conclusion This evaluation establishes the cualification of the Okonite and vinyl taped splices found and removed from the ASco solenoid valves, MOVs, and fan motors at FNP. Based on the testing information obtained as long as the splices do not short to ground the connections will perform their intended safety functions. All of the splices were partially protected from the outside environment by junction boxes or conduits. This protection is beneficial when considering the ahort operating time of the eauipment involved (Table 2).
(
It is therefore concluded that there is reasonable assurance that the splices removed from FNP (Table 1) were analifiable and would have performed their required safety function under the postulated FNP accident conditions.
Additional testing at Wyle Laboratories of Okonite and 3M Tape Splice assemblies further supports the ability.of these splices to perform in their intended functions during normal and DBE conditions.
VI. References
- 1. Wyle Test Report 17859-02P " Qualification Test Program on Raychem Nuclear Cable Splices, Okonite Tape Splices and Kerite Tape Splices as Installed on Various Wire Insulations at CECO's Zion, Byron and Braidwood Nuclear Generating Stations", March 11, 1987.
- 2. Wyle Test Report 17859-02B " Qualification Test Program on Raychem Nuclear Cable Splices, Okonite Tape. Splices, Karite Tape Splices, Scotch Tape Splices and AMP Butt Splices as Installed in Various Wire Insulations at CECO's LaSalle, Dresden, and Quad Cities Generating Stations", March 11, 1987'.
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IV. References (Continued)
(
- 3. Technical Report PEI-TR-840704-1 Final Report on the Qualification of Parallel Splice Insulation Systems Used on Power and Control Cables in the James A. Fitzpatrick Nuclear Power Plant, April 6, 1984.
- 4. Test Report 870429, Rev 1. "Punctional Test Program For Tape Splices Used in the Calvert Cliffs Nuclear Power Plant, Baltimore Gas and Electric", May 12, 1987.
- 5. Test Report Not PEI-TR-842900-1, Rev A. " Final Test Report on Okonite Tape Splice Insulation for Power & Control Cables and Rockbestos Pyrotrol III and Firewall III Cables", Kay 8,1985.
- 6. 14tter From R. P. Mcdonald to J. N. Grace, Dated 09/30/87, Environmental Qualification Meeting of September 24, 1987.
- 7. Joseph H. Farley Nuclear Plant - Unit 1 Ideensee Event Report No.
LER 87-012-00, 07/30/87.
- 8. Interim Staff Position on Environmental Qualification of Safety-Related Electrical Eaulpmenta NUREG-0588, Rev. 1.
- 9. Calculation F-87-03 Farley luclear Plant Units 1 & 2, Thermal Lag Analysis of Electrical Splices Wrapped in Okonite No. 35 Tape Exposed to MSLB.
- 10. Letter from J. E. CarlinEton to File, Dated 09/08/87, Environmental Qualification Splice Testing (Hinutes of August 21, 1987 meeting at FNP to discuss "as-found" aplices on HOVs, cooler fans and solenoid valves).
- 11. Nuclear Safety and Fuel Policy and Procedure Manual, Appendix C -
Guidelines for Preparation of Environmental Oualification Report Evaluation Checklist for Farley Nuclear Plant. Rev. 07/08/87.
l 12. Earley Nuclear Plant Units 1 and 2 Final Safety Analysis Report l
Update.
- 13. Letter from W. G. Hairston, III to J. D. Woodard, Dated 10/09/87, Environmental Qualification Test Results on Okonite and 3M Tape Splices.
- 14. Unit 1 Technical Specifinations Table 3.6-1.
- 15. P&ID D175010 Rev. 8, titled Containment Cooling Purge System.
1341F l
- m .
Table 1 Identification & Incation of Splices Splice DBE Conditions Detail No. Configuration Voltage Location Temperature Pressure Radiation Group 1 (Vinyl Tape)
- V03 "V" Type Splice 600V Main Steam Room 308'F 5.8 pelg 2 M Rade-
- V04 In-Line Butt Splice 600V Containment 378*F 48.0 psig 50 M Rads V05 In-Line Butt Splice 6007 Containment 378*F 48.0 pelg 50 M Rads Group 2
.(Vinyl Tape &
Okonite No. 35)
VN06 "V" Type Splice 600Y Main Steam Room 308'F 5.8 psig 2 M Reds Containment 378*F 48.0 psig 50 M Rads Group 3 (Viny 1/O . nite No. 35/ Vinyl)
VTV01 In-Line Butt Splice 6007 re * * ---
- 378*F 48.0 peig 50 M Reds VTV02 In-Line Butt Splice 600V Containment 378*F 48.0 psig 50 M Rads Group 4 (Okonite No. 35)
NO3 "V" Type Splice 1207. Main Stesa Room. 308*F 5.8 psig- 2 M Rads N06 "V" Type Splice 120V Main Steam Room 308'F 5.8 pelg 2 M Rads
- Representative examples of Worst Case Splices.
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f Table 2 Farley Nuclear Plant f Faulpment Function and Operating Time i 1 r i
Splice Detail No. TPNS No. MOV No. _ s Manufacturer Function
, Containment I
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-VTV01 -01E14v004- MOV331 'B-A Reliance VTV02' Containment to Atmosphere Differential Pressure Q1E14V004 MOV3318B-A Reliance V04 Q1E14V004 Containment to Atmosphere Differential Pressure L MOV33185-A Reliance Containment to Atmosphere Differential Pressure 705 01514V004 MOV3318B-A Reliance
-VN06 Containment to Atmosphere Differential Pressure Q1E23V0225 MOV35288-A Relian' Containment to Sample Point of Hydrogen Analyses a i Main Steam Room VN06 01N12SV3235A -
ASCO N06 Steam to Auxiliary Feedwater Pump 01N235V3227AC -
ASCO' N06 Q1N235V3227BA Auxiliary Feedwater Pump Discharge Wrottling Flow '
ASCO NO3 Q1N23SV3227BC , -
Auxiliary Feedwater Pump Discharge Throttling Flow .
ASCO Auxiliary Feedwater Pump Discharge Drottling Flow
- NO3, N06 Q1N23SY3227CA -
ASCO I
NO3 Q1N23SV3227CC Auxiliary Feedwater Pump Discharge %rottling Flow ASCO Auxiliary Feedwater Pump Discharge Drott11ng Flow t
V03 Q2N235V3227CA -
.ASCO l Auxiliary Feedwater Pump Discharge Drottling Flow- !
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Table 3 '
Industry Testing of Taped Splices Wyle NEQ 17859-02B & 17859-02P Co w w ealth Edison Splice LOCA Qual. Voltage /
Material Configuration Temp / Press Radiation Life Ostrent Specimen NEO 17859-02B Okonite T-95 & "V" Type Splice 360*F/55 psig 1.84EB Rad 40 yrs. 528V/6.7A B4*
No. 35 Tape W/No Tape in 528v/6.7A B5 Crotch 528V/10A B6 528v/15A B7 Terite Tape "V" Type Splice 360*F/55 psig 1.84E8 Rad 40 yrs. 528v/6.7A Z7 328v/6.7A Z11**
528v/6.7A 212**
- 528V/6.7A Z13 l
NEQ 17859-02P l l
Scotch 17, "V" Type Splice 355*F/53.1 psig 1.84 M Rad 30 yrs. 328v/6.7A D3 70 & 130 C -
15 yrs. 528v/6.7A D20 Scotch 33+, "V" Type Splice 355*F/53.1 psig 1.84E8 Rad 30 yrs. 328V/6.7A D4 130 C 15 yrs. 528v/6.7A D21 15 yrs. 528v/6.7A 01 30 yrs. 528V/6.7A Q2 15 yrs. 528v/6.7A Q3 30 yrs. 528V/6.7A 04
- Failed 14 hr. - 26 min. inte the LOCA Test
- Failed within 11 min. into the LOCA Test due to o arcing of the specimen identification tag. O c3 M
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Table 3 (Continued)
Industry Testing of Taped Splices Patel Report PEI-11t-842900-1 Rev A J. A. Fitzpatrick Nuclear Power Plant Splice ,
4 LOCA Qual.
Material Configuration Specimen Temp / Press Radiation Life Voltage l Okonite T-95 & Crimped parallel splice No. 35 Tape w/ splicing cement 1" overlap 3-1 360*F/50 psig 1.2E8 Rad 40 yrs. 696V
. 1-1/2" overlap 4-1 360*F/50 psig 1.2E8 Rad 40 yrs. 6967 w/o splicing cement 1" overlap 1-1 360*F/50 psig 1.2E8 Rad 40 yrs. 696V 1-1/2" overlap 2-1 360*F/50 psig 1.2E8 Rad 40 yrs. 696V Bolted parallel splice w/ splicing cement .
1" overlap 3-2 360*F/50 psig 1.2E8 Rad 40 yrs. 696V 1-1/2" overlap 4-2 360*F/50 psig 1.2E8 Rad 40 yrs. 696V w/o splicing cement 1" overlap 1-2 360*F/50 psig 1.2E8 Rad 40 yrs. 696V 1-1/2" overlap 2-2 360*F/50 psig 1.2E8 Rad 40 yrs. 696V Crieped butt splice ,
w/ splicing cement 1" overlap 3-3 360*F/50 psig 1.2E8 Rad 40 yrs. 696V 1-1/2" overlap 4-3 360*F/50 psig 1.2E8 Rad 40 yrs. 696V w/o splicing cement 1" overlap 2-3 360*F/50 psig 1.2E8 Rad 40 yrs. 696V 1-1/2" overlap 2-3 360*F/50 psig 1.2E8 Rad 40 yrs. 696V Series bolted lugs v/ splicing cement 1" overlap 3-4 360*F/50 psig 1.2E8 Rad 40 yrs. 696V 1-1/2" overlap 4-4 360*F/50 psig 1.2E8 Rad 40 yrs. 696V w/o splicing cement C}
en l' overlap 1-4 360*F/50 psig 1.2E8 Rad 40 yrs. 696V -a 1-1/2" overlap 2-4 360*F/50 psig 1.2E8 Rad 40 yrs. 696V CD
-4
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____a-
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Table 3 (Continued)
Industry Testing of Taped Splices Patel Report PEI-TR-C40704 Rev B J. A. Fitzpatrick Nuclear Power Plant Splice LOCA Material Configuration 4
Qual. Voltage Specimen Temp / press Radiation Life Ostrent Okonite T-95 & Parallel crimped splice C 270*F/12 psig 1.lE7 Rad 40 yrs.
No. 35 Tape 600VAC/24A Parallel crisped splice
! 1" overlap-no tape in crotch D3 270*F/12 psig 1.1E7 Rad 40 yrs. 600VAC/24A T-95 in crotch DS 270*F/12 psig 1.1E7 Rad 40 yrs. 600VAC/24A Parallel bolted splice .
1" overlap-no tape in crotch D4 270*F/12 psig 1.IE7 Rad 40 yrs. 600VAC/24A T-95 in crotch D6 270*F/12 psig 1.1E7 Rad 40 yrs. 600VAC/24A O
CD
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Table 3 (Continued)
Industry Testing of Taped Splices Baltimore Ces & Electric Co. Report 870429 & 870505 Calvert Cliffs Maclear Plant.
Splice LOCA Qual. Voltage Material Configuration Specimen ' Temp / Press Radiation Life Ctarrent EPR/PVC "Y" Type Splice A' 296*F/48.5 psig 2.0E8 Rads 13 yrs. 50VDC/12MA EPR/PVC "V" Type Splice B 296*F/48.5 psig 2.0EB Rade 13 yrs. 120VAC/120MA EPR P1ysefe "V" Type Splice C 296*F/48.5 psig '
2.0E8 Rads 13 yrs. 480VAC/10A 2117 PVC Polyolefin. In-Line Splice E 296*F/48.5 psig 2.OEB Rads 13 yrs. 50VDC/12MA Polyseal/PVC "V" Type Splice F. 296*F/48.5 psig 2.0E8 Rads 13 yrs. 120VAC/120MA-PVC Bolted Splice C' 296*F/48.5 'peig 2.0E8 Rads 13 yrs. 120VAC/120MA w
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0067080
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FIGURE 3 SPLICE ILLUSTRATION
0067083
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(2.) HALF LAPPEb LA1ERS OF VIN 1L TAPE
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0067084 (2) half lapped layers of Vinyl tape
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(E) half lapped layers of Okonite T-95 (2.) half lapped layers of Vinyl tape l 'E
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FIGURE 5 SPLICE ILLUSTRATION
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(2) half lapped layers of Vinyl tape 0067085 (E) half lapped layers of Okonite T-95 (2) half lapped layers of Vinyl tape 4
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