ML20027D627
| ML20027D627 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 06/25/1982 |
| From: | WYLE LABORATORIES |
| To: | |
| Shared Package | |
| ML20027D618 | List: |
| References | |
| 26333-26, NUDOCS 8211080171 | |
| Download: ML20027D627 (36) | |
Text
- _ _ - - - - - - _ - - - - - - - -
\
M LAMM3 ENGINEERING Wyle Report No. 9611'-7A
$CitNTIFIC $4RVICES & $YSTEMS GROUP WESTERN OrgaATIONS, NORCO FACillTY 1841 HILL 110E AVENUE, NORCO, Calif 0RNIA 98760 EPORT Wyle Job No. 26333-26 ARIA CODE 714-7374871 TWX 910 3321204 TELECOPY (714) 7374878 Customer P.O. No.
50843 Total Pages this Report Date:
25 June, 1982 I
r ,
ENVIRONMENTAL QUALIFICATION EVALUATION OF CABLE SPLICES INSIDE CONTAINMENT l
FOR OMAHA PUBLIC POWER DISTRICT FOR USE IN FORT CALHOUN NUCLEAR GENERATING STATION, UNIT 1 L J l
PREPARED BY: /2.1h _
VERIFIED BY+ j mc - A-- - /
APPROVED BY, I QUALITY ASSURANCb OHZ3
)
~
8211080171 821101 PDR ADOCK 05000285 P PDR
REPORT NC M.onannas u son.=c scams a avsms onow westenN orenAnous.nosco tAoury 2
,,c, no TABLE OF CONTENTS Page No.
1.0 SCOPE................................................................ 3 1.1 Objective......................................................... 3 1.2 Applicable Qualification Standards, . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 Specifications, and Documents 1.3 Equi pm en t Descri ption . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 1.4 Saf ety-Related Functions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 2.0 DEFINITION OF SERVICE CON DITIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 2.1 Nor mal Operating Conditions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 2.2 FS A R D B E Co nditions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 3.0 AGING EVALUATION CRITERI A . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 3.1 Evaluation of Susceptibility to . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 Radiation Degradation 3.2 Evaluation of Susceptibility to . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 Time / Temperature Related Mechansims 4.0 EVALUATION ..................................................... 8 4.1 Aging............................................................ 8 4.2 Relative H umidity Ef f ects . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 4.3 De si gn Basis E ven t . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 4.4 In-Containmen t inspection . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15 4.5 Te s t S pe ci m ens . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 4.6 Evaluation Sum mar y . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18 5.0 C O N C L U S IO N S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 19 R E F E R E N C ES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 0 Figure 1 Insulation of "E" Cable Connections . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 22 Figure 2 Containment Temperatures Following LOC A . . . . . . . . . . . . . . . . . . . . . . . . . . 23 Figure 3 Containment Pressure . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 24 Figure 4 SER Section 3.3, MSLB Temperature Curve . . . . . . . . . . . . . . . . . . . . . . . . . . . 25 Table 1 C able D es cription . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 26 Table 2 Cable Splice Identification . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 27 Table 3 A gi n g M a t r i x . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 3 Table 4 Evaluation Sum mary of . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 31 Cable Splices at Transmitters Table 5 Evaluation Sum mary of . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 32 Cable Splices at the 480 V Containment Vent Fan Motor Lead Wires Table 6 Evaluation Sum mary of . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 3 The 480 V Containment Vent Fan Motor Splices at the Electrical Penetrations Table 7 Evaluation Sum mary of . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 34 Original Plant Cable Splices at Electrical Penetrations Table 8 Evaluation Sum mary of . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 35 TMI Modification at Containment Penetrations Lead Wire Splices (Raychem WCSF-N)
Table 9 Evalua tion Sum mary of . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 36 Cable Splices at Solenoid Valves
REPORT NO.
usonarones $CENTWW: $UMCES & SYSTEMS GAOUP woman openArious,nonco rAam ,,,, ,o 1.0 SCOPE This document was prepared by Wyle Laboratories for Omaha Public Power District (The District) for safety-related cable splices installed inside containment at Fort Calhoun Nuclear Generating Station, Unit 1.
1.1 Objective The purpose of this report is to present an environmental qualification evaluation in accordance with the requirements of IE Bulletin 79-OlB, including an aging analysis of six tyys of cable splices for safety-related electrical equipmsnts inside containment.
1.2 Applicable Qualification Standards, Specifications, and Documents 0 Wyle Laboratories Western Test and Engineering Quality Assurance Manual 380, dated June 1,1981 o IE Bulletin No. 79-OlB, Enclosure 4, " Guidelines for Environmental Qualification of Class IE Electrical Equipment in Operating Reactors,"
January 14, 1980.
o IE Supplement No. 2 to Bulletin 79-01B, " Environmental Qualification of Class IE Equipment," September 30,1980.
26333-26 sem-c saavcas a svanus oaoue 4
m oPERATloNE Mosco FACluTV pac,g pg3 1.0 SCOPE (CONTINUED) 1.3 Equipment Description The subject equipment consists of the six types of cable splices listed below for six electrical cable size and multiple conductor combinations (Table 1). For details see Tables 2 and 3 and Figure 1.
- 1) , Cable Splices at Transmitters y 2) Cable Splices at the 480 V Containment Vent Fan Motor Lead Wires
- 3) The 480 V Containment Vent Fan Motor Splices at the Electrical Penetrations
- 4) Original Plant Cable Splices at Electrical Penetrations
- 5) TMI Modification at Containment Penetration Lead Wire Splices (Raychem WCSF-N)
- 6) Cable Splices at Solenoid Valves 1.4 Safety-Related Functions
- The specific safety-related functions of the cable splice components are described in the following paragraphs:
o Cable Splice: provides the electrical paths for safety-related electrical circuits.
O Insulation: provides the necessary electrical isolation to eliminate unwanted electrical paths.
O Heat Shrink Tubing: provides a vapor and liquid (chemical) seal covering the insulation of the cable and connectors. For certain splices, heat shrink tubing is also insulation.
O RTV Silicone Rubber: provides a vapor and liquid (chemical) barrier over the heat shrink tubing of the cable splice.
1
26333-26 REPORT NO-a scamwc seances a systaus onour y
PAGE NO 2.0 DEFINITION OF SERVICE CONDITIONS The following environmental service conditions have been specified by the District 20,29, 30:
Normal FSAR Design Basis Event (DBE*)
o Temperature 84F(29C) 305F(152C) Maximum **
O Relative Humidity 9015% 100 %
0 Pressure Atmospheric 60 Psig Maximum 0
( Chemical Spray N/A Boric Acid Solution (2500 ppm Boron) 0 Radiation 3.42 x 105 1.12 x 106 to 3.0 x 107 Rads, gamma, j depending on the location (see Table 3)**
- i O Time:
a) Transmitters Continuous Continuous b) Solenoid Intermittent Note I c) Containment Intermittent Continuous Vent Fan d) Cable Continuous Continuous Temperature and pressure profiles are given in Figures 2 and 3 The DBE is a loss of coolant accident (LOCA).
This is Main Steam Line Break (MSLB) temperature, used in lieu of lower 288F LOCA temperature per SER Section 3.3 Response 30, This is the total calculated integrated dose for 40 years plus accident 28, NOTE 1 After the first few seconds into a DBE situation, all the solenoids in containment move to their fail positions with the exception of the following:
The Long Term Core Cooling Solenoids (238,239,240) are required to operate in a DBE situation.
The Reactor Coolant Solenoid (HCV-438 A & C) moves to its fail position which is the open position, and is driven closed in a DBE.
The Auxiliary Feedwater (HCV-1107A,1108A) move to their fait position which is their open position, and are driven closed in a DBE.
Charcoal Spray may operate intermittently in a DBE, HCV-864,865.
Purge system, HCV-881 and 882, move to their fail position which is their open position and are driven closed in a DBE.
I
I M *^---
_ SOENTIFIC $4fMCES & SYSTEMS 9t0UP REPORT NO.
~
WW11W NTiole,IMO PACluTY ,,g, ,,o b
3.0 AGING EVALUATION CRITERIA The following sequence of steps were used to evaluate the non-metallic materials in each splice with respect to their safety-related functions under normal and Design Basis Event l (DBE) conditons.
3.1 Evaluation of Susceptibility to Radiation Degradation The approach for evaluating the components for their radiation resistance is a four step
[ process:
- 1. Review the individual materials of construction as provided on the contract specific l materials list.
- 2. Research Wyle Laboratories Aging Library for information on threshold levels, severe damage levels, degradation characteristics, and failure criteria.
- 3. List threshold level for radiation damage in the aging matrix.
- 4. Evaluate the item based on potential degradation and ability to perform its design function af ter exposure to the specified radiation dose.
It is generally recognized that metallic and inorganic materials are immune to radiation degradation at the specified dose, hence, the evaluation is focused on the non-metallic (organic) materials. <
3.2 Evaluation of Susceptibility to Time / Temperature Related Mechanisms Deterioration due to thermal aging is insignificant for metallic and inorganic materials under the specified environmental conditions. Therefore, component aging is based on the non-metallic (organic) materials.
For many organic materials, it is known that the degradation process can be defined by a single temperature-dependent reaction that follows the Arrhenius equation:
k = A exp (-(Ea/kb T)) (1) w here, k = reaction rate A = frequency factor exp = exponent to base e Ea = activation energy (eV) kb = Boltzmann's Constant (8.617 x 10-5 eV/oK)
T = absolute temperature (OK) l t _-_
M"-
sce wesaavcuwsw caou.
REPORT NO.
6 NN PtoSCO PAClufY pgg g 7 3.0 AGING EVALUATION CRITERIA (CONTINUED) ,
j 3.2 Evaluation of Susceptibility to Time / Temperature Related Mechanisms (Cont'd)
It is further noted that, for many reactions, the activation energy can be considered to be constant over the applicable temperature range. Equation (1) can be transformed into a slope-intercept form of a linear equation which yields the expected life:
In (life) = (Ea/kB) (1/T) + Constant (2) l Since the materials follow an Arrhenius relationship, the requirement at one time and temperature can be transferred to another set cf time / temperature coordinates using the relationship t1 = t2 exp ((Ea/k B )(1/T 1 - 1/T2)) (3) where, t1 = Calculated life at temperature T1 t2 = Expected life at T2 (Equation 2)-120 T1 = Accident temperature (max)
T2 = Normal service temperature When the expected life obtained from equation (2) at the normal service temperature (84F) exceeds the specified service life (40 years) by a conservative factor of three, equation (3)
, is used to calculate the equivalent life at the accident temperature from the expected life minus 120 years. The factor of three is used for conservatism to account for uncertainties such as variations in the postulated temperatures and durations.
This will demonstrate life in excess of the normal service condition (conservatively estimated to be 120 years) and provide a mechanism for comparing the remaining life of a material at the accident temperature with the postulated accident duration.
For example for Polyolefin, with a degradation parameter of 86% loss of electrical strength (Table 3, item No.1):
Normal calculated life = exp ((Ea/kB)(1/T) + (Intercept))
where, Ea = 0.86 eV Intercept = -15.04707 For a baseline temperature of 84F (29C)(normal service condition)
T = 29C + 273 = 302K life = exp ((9980.2716)(1/302)- 15.04707) life = 6.56 x 107 hours0.00124 days <br />0.0297 hours <br />1.76918e-4 weeks <br />4.07135e-5 months <br /> (7,496 years)
M --
scemcse=censme=c ou, REPORT NO-
~
m oPWAflofe,8800C0 FAQUTY ,,og go 3.0 AGING EVALUATION CRITERIA (CONTINUED) 3.2 Evaluation of Susceptibility to Time / Temperature Related Mechanisms (Cont'd)
Then 7,496 years - 120 years = 7,376 years For an accident temperature of 305F (152C)(accident service condition) ti = t2 exp ((slope)(1/T1 - 1/T2))
tt = equivalent calculated accident !!fe at 30$F t2 = 7,376 years Tt = 152C + 273 = 425K T2 = 29C + 273 = 302K then tt = (7,376 years x 365 days / year) exp ((9980.2716) (1/425 - 1/362))
t1 = 189 days Based on the above calculation,it is demonstrated:
a) Calculated normal life of 120 years at 84F (29C) b) Calculated accident life of 189 days at 305F (152C)in addition to 120 years normal life.
If the calculated life at the normal operating temperature does not exceed the service life (40 years) by a multiple of 3, then a case by case analysis will be carried out.
t
MMM REPORT NO. 26333-26 sCitPsTIFIC SERVICES & SYSTEMS GRoVP q*
WESTERN oPERAfloNs, NoRCo FACluTY PAGE No 4.0 EVALUATION 4.1 Aging An aging analysis was done to determine the susceptibility to time / temperature and radiation related mechanisms.
Damage levels and calculated lives for normal operation and DBE conditions were determined solely on the individual effects of radiation and time / temperature related mechanisms.
Contract specific materials lists were provided by The District for the purpose of evaluation.
4.1.1 TIME / TEMPERATURE EFFECTS The Aging Matrix (Table 3) contains a list of the non-metallic materials used in each splice, the data used in this evaluation, and the calculated lives (normal and accident) for each of the splices.
A review of calculated lives, normal and accident, (Table 3) indicates insignificant thermal aging at the specified normal and accident environmental temperatures.
Certainly, calculated expected life is only a theoretical life, but it demonstrates that each material will have a qualified life, for a normal service, of greater than 40 years, plus accident and post accident life.
4.1.2 RADIATION EFFECTS 4.1.2.1 Gamma Radiation Effects The threshold levels for radiation induced damage were determined per section 3.1. The radiation threshold level of each material was compared to the required dose specified in Table 3. Where the radiation threshold level of a material is greater than the required dose by a margin of +25%, or test data exists where test conditions envelop the required dose, the effects of radiation exposure were judged to be insignificant.
A review of Table 3 indicates insignificant radiation aging.
4.1.2.2 Beta Radiation Effects The following analysis is based on the methodology presented in the DOR Guidelines.
t
MMM REPORV NO.
SCIENTIFIC SERVICES & SYSTEMS GROUP WESTERN OPERATIONS, NoRCo FACluTY 10 PAGE No 4.0 EVALUATION (CONTINUED) 4.1 Aging (Cont'd) 4.1.2.2 Beta Radiation Effects (Cont'd)
The beta dose is reduced by a factor of ten within 30 mils of the surface of electrical cable insulation. An additional 40 mils (for a total of 70 mils) results in another factor of ten reduction in dose. Any structures or other equipment in the vicinity of the equipment of interest would act as shielding to further reduce beta doses.
If the plant specific beta radiation dose is not available, the generic dose of 2 x 108 rads could be used.
It can be shown, by assuming a conservative unshielded surface beta dose of 2.0 x 108 rads and considering the shielding factors discussed above, that the beta dose to radiation sensitive equipment internals would be less than or equal to 10% of the total gamma dose to which an item of equipment has been qualified. Then that equipment may be considered qualified for the total radiation environment (gamma plus beta). If this criterion is not satisfied the radiation service condition should be determined by the sum of the gamma and beta doses.
4.1.2.2.1 Qable Splices at Transmitters These cables splices are located inside conduits which shield them from beta radiation.
Therefore, the effects of beta radiation would be insignificant.
4.1.2.2.2 Cable Splices at the 480 V Containment Vent Fan Motor Lead Wires.
These cable splices are located inside terminal boxes 20 and covered with RTV 3145 which shield them from beta radiation. Therefore, the effects of beta radiation would be insignificant.
4.1.2.2.3 The 480V Containment Vent Fan Motor Lead Splices at the Electrical Penetration These cable splices are exempted from the effect of beta radiation because of the R.T.V.
covering. Since the R.T.V is about 1/8 inch thick 2 (125 mils), the beta dose is reduced by a factor of 1000. The beta dose is then 2 x 105 rads. This beta dose is less than ten percent of the gamma dose and the effects of beta radiation are considered insignificant.
4.1.2.2.4 Original Plant Cable Splices at Electrical Penetrations The effects of beta radiation are considered insignificant due to the RTV coating as in
, 4.1.2.2.3.
'i ..
REPORT NO-usonaronas scautwc sanvcts a sysTrus opour gg wesTenN OPERATIONS.NotCo FACluTY pang uo 4.0 EVALUATION (CONTINUED) 4.1.2.2.5 TMI Modification at Containment Penetration Lead Wire Splices (Raychem WCSF-N)
The effects of beta radiation are considered insignificant because this cable splice was tested to gamma radiation of 2.0 x 108 (Ref. 3), which is greater than the total integrated gamma plus beta dose.
4.1.2.2.6 Cable Splices at Solenoid Valves -
These cable splices are located inside condulets20 which shield them from beta radiation.
Therefore, the effects of beta radiation would be insignificant.
4.2 Relative Humidity Effects Relative humidity is not considered a significant aging mechanism for the subject splices.
For insulation systems, humidity is usually not the primary failure mechanism. As noted in Reference 25, with respect to motor insulations, "In most cases, moisture plays only a secondary role in the f ailure. It does not produce the damage in the insulation. The insulation wears away or cracks for other reasons. Moisture merely provides a direct electrical pathway between these matured devices and ground." Therefore, effect of humidity was considered insignificant for this application.
In addition to the above it is judged that the combination of high temperature / pressure steam and chemical spray is a more severe environment than 100% relative humidity.
Original Plant Cable Splices at the Electrical Penetrations and TMI Modification at Containment Penetration Lead Wire Splices (Raychem WCSF-N) were subjected, without failure, to a LOCA test (high temperature / pressure steam) with chemical spray environments. Therefore, immunity to relative humidity was demonstrated by more severe test conditions.
For the Cable Splices at the Transmitters, Cable Splices at the 480 V Containment Vent Fan Motor Lead Wires and the 480 V Containment Vent Fan Motor Splices at the Electrical Penetrations, the RTV coating provides an excellent seal over the splice thus causing the effects of humidity to be insignificant.
The splices at Solenoid Valves are double Pentube heat shrink tubing and are located inside a condulet system 20 Therefore, the effects of humidity are considered insignificant.
l
_ _ _ _ _ _ _ ___ J
N REPORT NO. 2b333-2b
$CIENTIFIC SERVICES & $YSTEMs GRoVP I W! STERN OPERATIONS, NoRCo FACluTY PAGE NO.
g 4.0 EVALUATION (CONTINUED)
! 4.3 Design Basis Event (DBE) l
} The DBE is a Loss of Coolant Accident (LOCA).
Each splice was evaluated for the following LOCA environments:
- 1. Thermal Aging
- 2. Radiation Aging
- 3. Temperature
- 4. Pressure
- 5. Chemical Spray 1
- 6. Relative Humidity
- 7. Submergence A summary of these evaluations is given in Tables 4 through 9.
4.3.1 THERMAL AGING Based on the evaluation presented in Section 4.1, the effects of thermal aging during a LOCA are insignificant.
4.3.2 RADIATION AGING Each cable splice was evaluated for the total integrated dose plus accident (LOCA),
Section 4.1.2.
Based on the evaluation presented in section 4.1.2, the effects of radiation aging during a LOCA are insignificant.
TMI modification at Containment Penetratton Lead Wire Splices (Raychem WCSF-N), and Original Plant Cable Splices at Electrical Penetrations interface with teflon insulated cables. The effects of 1.12 x 106 (Table 8) and 1.36 x 107 (Table 7) rads gamma respectively on teflon must be addressed by test because the Raychem test 3 and Franklin Institute (l) tests were conducted without teflon insulated cables.
Because of the high radiation level, a test, in lieu of analysis, must be used to demonstrate qualification of the interface.
I
\ _ _ _ _ _ _ _ _ _ _ _ _ _ _
l MMM REPORT NO. 2b
[ $CitNilHC sERVIC!s & SYSTEMS GRo'JP i W13 FERN oPERAT!oN$.NoRCo FACIUTY PAGE NO g
4.0 EVALUATION (CONTINUED) 4.3 Design Basis Event (DBE) (Cont'd) 4.3.3 TEMPERATURE i Figure 4 shows the SER Section 3.3 response 305F temperature profile. The shaded area is the MSLB 305F temperature profile, in excess of peak LOCA temperature. The cstimated duration of this hypothetical condition will not be greater than 5 minutes.
A review of calculated lives for the materials used in each type of cable splice showed that each individual material is capable of withstanding 305F far longer than 5 minutes as shown in Table 3.
4.3.3.1 Cable Splices at Transmitters As indicated in Section 4.3.5.1, these splices are covered with a LOCA qualified Dow Corning 3145 RTV adhesive / sealant 4 . This RTV has good dielectric properties over a wide temperature range and will withstand long term exposure at 482F (250C)27, The sealant will also withstand steam (to 200C) and has withstood a 100,000 hour0 days <br />0 hours <br />0 weeks <br />0 months <br /> aging test at 200C 4. Dow Corning has reported " Steam at 245F could, in time, sof ten Dow Corning 3145, but 20 minutes would be considered a minor exposure"4 Because the exposure to high temperature is for only a short time, there should be no adverse effects on the Dow Corning 3145 RTV.
4.3.3.2 Cable Splices at the 480V Containment Vent Fan Motor Lead Wires Dow Corning 3144 RTV adhesive / sealant's ability to stand up to the adverse conditions of a LOCA is documented by the Fisher Controls Company valve actuator tests 7 . Test parameters included temperatures in excess of 288F, pressure in excess of 60 psig, and a 100% saturated steam environment.
Furthermore,3144 RTV will withstand long term exposure at 250C (482F)27, It is concluded that the short time exposure at high temperature will not have an adverse effect on this splice.
4.3.3.3 The 480V Containment Vent Fan, Motor Lead Splices at the Electrical Penetrations This cable splice will withstand the short time exposure of 305F per analysis presented in l section 4.3.3.1 above.
. - . .. .. .. .s_
M REPORT NO. 26333-26 SCIENTIFIC SERVICis & $YSTf;AS oRoVP WESTERN oPERAfloN$. NoRCo FACIUTY RAGE No l4 4.0 EVALUATION (CONTINUED) 4.3 Design Basis Event (DBE) (Cont'd) 4.3.3.4 Original Plant Cable Splices at Electrical Penetrations Figure 4 includes the Franklin Test estimated average temperature of 297F. The 17F increase (305F-288F) over the calculated LOCA temperature curve is plotted as the SER Section 3.3 MSLB Temperature Curve. By inspection, it can be seen that the amount of heat added during testing was significantly greater than that required by the hypothetical SER Section 3.3, MSLB Temperature Curve (LOCA curve plus 17F). Note the logrithmatic scale and that Area B is a major increase over Area A. Therefore, the Franklin Tests are judged to be conservative compared to the DBE temperature profile with its 305F imposed peak temperature.
Some test temperatures reached 302F while others were as low as 295F. This represents a range of undershoot from 3 to 8 degrees. Since the SER Section 3.3, use of 305F was established for the upper regions of the containment, and the electrical penetation splices are in the lower-middle elevations, the 3 to 8 degree difference for about 52 seconds can be taken into account by establishing the materials capability to withstand higher temperatures.
The material evaluation in Section 4.3.1 and 4.3.3.1 shows the capability to withstand 305F temperatures so materials in the splice should withstand a short exposure at 305F.
4.3.3.5 TMI Modification at Containment Penetration Lead Wire Splices (Raychem WCSF-N)
These splices have been tested to temperatures up to 390F which exceeds the required temperature by 85F3.
4.3.3.6 Cable Splices at Solenoid valves The material evaluation in Section 4.3.1 and 4.3.3.1 shows the capability to withstand 305F temperatures so materials in the splice should withstand a short exposure at 305F.
4.3.4 PRESSURE No accident pressure test data exists for the cables splices listed below:
a) Cable Splices at Transmitters j b) Cables Splices at the 480V Containment Vent Fan Motor Lead Wires c) The 480V Containment Vent Fan Motor Splices at the Electrical Penetrations d) Cables Splices at Solenoid Valves I
I I
M REPORT NO SCIENTIFIC $ERVICES & $YSTEMS GeoVP WESTERN OPERATION $, NotCo FActuTY PAGE NO 13 j
4.0 EVALUATION (CONTINUED) 4.3 Design Basis Event (DBE) (Cont'd) 4.3.4 PRESSURE (Cont'd) l The effects of pressure are significant when chemical spray is present to cause shorting of the conductors due to voids or poor adhesive properties of the splice. The splice construction technique should minimize the possibility of voids. RTV alone exhibits excellent adhesive properties4 7 Original piant Cable Splices at Electrical Penetrations and TMI Modification at Containment Penetration Lead Wi e Splices have been tested for a LOCA condition witii a pressure equal or greater than 60 psigl 3 4.3.5 CHEMICAL SPRAY 4.3.5.1 Cable Splices at Transmitters These splices are potted with Dow Corning RTV 3145 adhesive / sealant 4 . The sealant will withstand steam up to 392F (200C), and chemical spray for the DBE conditions specified l in section 2.2.
Each cable s the splices 20,plice is sealed in a condulet which prevents chemical spray from getting to A chemical spray environment during a LLuA should be insignificant.
4.3.5.2 Cable Splices at the 480V Containment Vent Fan Motor Lead Wires i
These splices are covered with Dow Corning RTV 3144 adhesive / sealant. Due to the RTV i
sealant, the splice system will not be subjected to chemical spray during a LOCA (Ref. 7).
l l The RTV 3144 sealant will effectively seal off all environments from the underlying i Scotch brand tapes and the splice, except for radiation. The RTV 3144 also is not l
adversely affected by boric acid solutions in excess of 5%7 .
These splices are contained within a sealed NEMA conduit and terminal box system 20, The physical layout of the conduit is such that chemical spray would have to travel f against the direction of gravity inside the conduit to reach the splices during the 2 to 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> operating time requirement 20, The effects of a chemical spray environment during a 2 to 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> LOCA should be insignificant.
I I
I ~
REPORT NC-seemc seams n emius aaour m openAfloNE NOACO PACluTY pact no 16 l
4.0 EVALUATION (CONTINUED) 4.3.5.3 The 480V Containment Vent Fan Motor Splices at the Electrical Penetrations These splices use G.E. RTV silicone to seal the final end tabs of the Irrasil tape. A layer of Scotch P33 tape is installed over the entire splice. An investigation of this splice indicates that its composition would allow it to withstand the effects of chemical spray during a LOCA5 .
The SPT has,an outstanding resistance to steam and hot water 5 It also has excellent resistance to acids. The s!!icone tape and RTV both exhibit good, high-temperature characteristics and chemical resistance.
To insure operability of the splice, the splices are coated with Dow Corning RTV 3145 adhesive / sealant4 . This mitigates the chemical spray from attacking the splice.
Therefore, the effects of chemical spray environment during a 2 to 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> LOCA should be insignificant.
4.3.5.4 Original Plant Cable Splices at Electrical Penetrations The effects of chemical spray environment during the LOCA should be insignificant per i Section 4.3.5.1 above.
4.3.5.5 " TMI Modification at Containment Penetration Lead Wire Splices (Raychem l WCSF-N) j l
l These splices are LOCA qualified per Wyle Report No. 58442-13 .
The tested chemical spray consisted of 6200 ppm of boron,50 ppm of hydrazine buffered to a pH of 10.5 with trisodium phosphate.
The test conditions far exceed the required plant conditions specified in Section 2.2.
4.3.5.6 Cable Splices at Solenoid Valves These cable splices are covered with double heatshrink tubing and are contained within a sealed NEMA condulet and conduit system 20 The physical layout of the conduit is such that chemical spray would have to travel against the direction of gravity inside a conduit to reach the splices during the LOCA which prevents chemical spray from getting to the splice. ,
4.3.6 RELATIVE HUMIDITY Based on the evaluation presented in Section 4.2, the effects of relative humidity during a
, LOCA are insignificant.
l I
m . _ - _ . _ _ _ _ - - - - - - .
N REPORT NO- 2b333~2b sCIENTWC SERV 6CEs & SYSTEMS GROUP WESTERN oPERAfloNs, NoRCo FACluTY g7 PAGE too l
l 4.0 EVALUATION (CONTINUED) 4.3.7 SUBMERGENCE As reported by The District, the cable splices are above flood level (SCEW Sheets p. 5-49 ,
through 5-52), therefore no effects of submergence are considered in this report.
4.4 In-Containment Inspection On November 5 and 6,1981, an inspection of splices was performed for the purpose of the "as constructed" splices at Fort Calhoun8 The District's Licensing Action Log, item 00266, commitment to perform the inspection during the 1981 refueling outage was completed. The significant results of the District's and Wyle's in-containment inspection are as follows:
Original Plant Cable Splices at Electrical Penetration The inspection of a splice after disassembly verified that the pertinent design data of the "as constructed" equipment conforms to document FSK-E-329, Sheet 3, the Fort Calhoun l Construction Inspection Data Report (CIDR) of 1973 and the test specimen description of i
Test Report F-C33488 . The pertinent design data which was selected to verify the assumptions of Wyle Preliminary Report 9 include, but are not limited to the following:
)
- 1. Double heat shrink tubing over butt splice -
- 2. Drain wire has boot and associated splice in double heat shrink
- 3. Relative spacing between butt splices j 4. Materials
! a. RTV
- b. GE Irrathene
- c. Scotch 33 In addition, subsequent discussions with the District's Field Maintenance Electricians on November 5,1981, pointed out that the materials of Items 4a, b, c, were recognizable and identifiable as the proper materials. These District personnel participated in construction and start up of Fort Calhoun.
The first purpose of the cable splice disassembly was to ensure continued plant operation by demonstrating that assumptions 2,3,4, and 5 of Reference 9 regarding the penetration lead wires were met. Specifically, the "as constructed" penetration lead wire splices were similar to those used in the April,1972 Franklin Institute Test, Report F-C3348, by having two layers of heat shrink over each butt splice in lieu of cne layer (including the drain j
wire), and the drain wire had a boot of heat shrink over it. The second purpose was to gather sufficient data to assist in the evaluation / verification of the cable splice similarity analysis (tested specimens versus installed splices) of assumption 1 of Reference 9.
I
N REPORT NO. b soENilHC SERVICES & SYSTEMS group WESTERN oPERATloNS, Notr.o FACluTY PAGE NO t3 s
4.0 EVALUATION (CONTINUED) 4.5 Test Specimens Similarity Evaluation Industry experience regarding cable splice qualification, suggests that the multiconductor cable splice is the limiting case. The sealing or pressure boundary function of keeping f liquid / chemical spray out of the conductor area is more difficult to obtain for a ~
multiconductor splice than for a single conductor or lesser number of conductors splice.
X 4.6 Evaluation Summary See Tables 4 through 9 for details.
Effects of LOCA environment are considered negligible for Cable Splices at the Solenoid Valves for a one minute LOCA operating time requirement. However, the District must take exception to the one hour margin criterion of the DOR Guideline. Otherwise a test or replacement must be considered. Material analysis shows no adverse effects. Also, the solenoids fail in a safe position. Accordingly, continued plant operation is justified, and if the one hour criterion with the requirement for accident test data is envoked, then a test or replacement program must be considered. '
For the Cable Splice at the Transmitter taking into account the single heat shrink tube potted with RTV inside an enclosed condulet, the LOCA operational time requirement of 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> and the material analysis shows no a'dverse effects. Continued plant operation <
is justified. As no accident test data is available, a test or replacement program must be considered.
TMI Modification at Containment Penetration Lead Wire Splices, Raychem WCSF-N, meet IEEE-323-1974. The Original Plant Cable Splices at Electrical Penetrations meet the DOR Guidelines by a combination test and analysis. However, because neither was tested with Teflon insulated cable, a test program is needed to demonstrate qualification for,the Teflon interface at the levels indicated in Tables 7 and 8.
Cable Splices at the 480V Containment Vent Fan Motor Lead Wires and the 480V Containment Vent Fan Motor Splices at the Electrical Penetrations evalua: ion shows good use of RTV to seal the splices. The material analysis shows that the individual splice components have no adverse effects from normal and accident conditions and continued plant operation is justified. As no accident test data exists, a test plan or replacement is needed.
J
26333-26 M-
. REPORT NO- ._ ___
1, westuen openanons,nonco racany ,,,, no
5.0 CONCLUSION
S
- 1. Based upon the inspection at Fort Calhoua and the engineering evaluation done to date, it has been determined that insufficient accident test data is available to support full qualification in strict accordance with DOR Guidelines of IE Bulletin 79-OlB for the cable splices listed below. The specific deficiency is lack of accident test data on the splice.
a) Cable Splices at the 480V Containment Vent Fan Motor Lead Wires (LER 80-l 007) b) The 480V Containment Vent Fan Motor Splices at the Electrical Penetrations (LER 80-007) c) Cable Splices at Solenoid Valves except for HCV-238,239, and 240) d) Cable Splices at Transmitters (LER 80-006)
As presented in Section 4.0 above, from an engineering and analysis point of view, the above splices are capable of safe operation before, during, and after a LOCA for the time period required to operate. Therefore continued operation is justified.
- 2. Original Plant Cable Splices at containment penetration using original plant doubig heat shrink splices tested per April,1972 Franklin Institute Test Report F-C33481 are qualified except for interface with teflon insulated cable which must be tested.
- 3. Containment penetration lead wire splices using Raychem splices are qualified per May,1980, Wyle Test Report No. 58442-1 3 , except for the interface with Teflon insulated cable which must be tested.
1
REPORT NO SCIENimC SERVICES & SYSTEMS GRoOP WESTERN oPERATloNS, NoRCo FACluTY PAGE NO 20 REFERENCES
- 1. Qualification Tests of Cable Splices Under Simulated Reactor Containment Service Conditions, Franklin Institute Final Report F-C3348, dated April 1972.
- 2. Fort Calhoun File No. FC-643-80, dated 6 June ,1980.
- 3. Environmental Qualification Test Report of Raychem WCSF-N nuclear in-line cable splice assemblies for Raychem Corporation, Menlo Park, California, Wyle Report No. 38447-1, dated 15 May,1980.
- 4. Dow Corning letter dated March 24, 1980;
Subject:
Dow Corning 3145 RTV and adhesive / sealant integrity.
, 5. LER 80-007, Fort Calhoun Station, Unit 1, Docket No. 05000285, attachment No.1.
- 6. Standard Handbook for Electrical Engineers, Tenth Edition.
- 7. Enclosure 9, Containment Fan Cooler Motor Splices. Omaha Public Power District, Fort Calhoun Station, Unit 1, Electrical Equipments Evaluation Report.
- 8. Wyle Quality Inspection Record by E.3. Gerloff; subject: Penetration Splice, dated November 11,1981.
- 9. Wyle Report, 26333-02; subject: Preliminary Assessment Report on Cable Splices Inside Containment for Fort Calhoun Sation, Unit 1, dated January 29,1981.
- 10. Enclosure 8, Material Analysis of Containment Penetration Cable Splices for Radiation Effects, for Fort Calhoun Station, Unit 1, Electrical Equipments Evaluation Report.
- 11. Fort Calhoun Station, Unit 1, File No. I l405-E-150, 151, Cable and Conduit Schedule, Fort Calhoun.
- 12. "Raychem Flamtrol- Qualification to IEEE Standard 383," Library Code 281-80A
- 13. " Report on the Effect of Radiation on Electrical Insulating Materials," C. L. Hanks and D. 3. Hamman, REIC Report No. 46, June,1969, Battelle Memorial Institute, Library Code 299-80
- 14. " Thermal Aging Program for U.L. Recognition," T. C. Hampton, Dow Corning, Library Code 465-81
- 15. "The Effect of Nuclear Radiation on Elastomeric and Plastic Materials," R. W.
King, et. al., Battelle Radiation Effects Center, REIC Report No. 21, September 1, 1961, Library Code 286-80
- 16. Thermal Life Data for CC 2115,2116 Silicone Rubber Wire Insulation, Continental Wire and Cable Company, June 30,1978, Lbirary Code 337-80A l
1
REPORT NO.
sen,macsen=cas a svsmeoaour wasteHN oPERAMoNE,NOACO FAQUTY y3 pang , o REFERENCES (CONTINUED)
- 17. Varflex Corporation, U.L. File No. E63450 (Varflo Sleeving), January 17, 1979, Library Code 446-81.
- 18. " Wires and Cords for Original Equipment Manufacturers," General Electric Company, No. WCC-2, Library Code 135-79A
- 19. "Raychem Corporation WCSF Thermal Aging Data," EDR-2001, Library Code 360-80
(
- 20. Omaha Public Power District, letter dated March 2,1982.
Subject:
Operational time requirement of Safety Related Equipment Inside Containment; NEMA rating of Condulets at Pressure Transmitter and Solenoids and Terminal Box at Containment Vent Fan Motor, and Composition of Chemical Spray.
- 21. Radiation Resistance of Bishop Materials, Physical and Electrical Properties for Bishop l'3 tape provided by George Foote, Manager, Inside Sales. Bishop Electric, Cedar Grove, NJ.
- 22. " Wires and Cords for Electrical Appliance and Equipment Manufacturers", General Electric Company, Library Code 185-79A.
- 23. " Insulations and Jackets for Control and Power Cables in Thermal Reactor Nuclear Generating Stations," Robert B. Blodgett and Robert G. Fisher, IEEE Transactions on Power Apparatus and Systems, Vol. PAS-88, No. 5, May,1969, Library Code 226-79A
- 24. Fort Calhoun File No. FC-765-2617, dated May 18,1972, " Insulation of "E" Cable Connection", Drawing No. XA-545-E462.
- 25. Industrial Motor Users Handbook of Insulation for Rewinds, L.J. Rejda and Kris Neville, Elsevier,1977, Wyle Library Code 255-30.
- 26. Telecon of S. Gharakhanian, Wyle Laboratories, Nerco, Ca., and George Congdon (Inside Sales), Dow Corning Corporation, Midland, Michigan, January 14, 1982.
Subject:
RTV 3144.
- 27. Information about Silicone Elastomers, 3145 RTV, Dow Corning Corporation, Form No. 61-34913-80.
- 28. Enclosure 11, Expected Radiation Dose Levels In-Containment Omaha Public Power District, Fort Calhoun Station, Unit 1, Electrical Equipments Evaluation ' Report.
- 29. Telecon of Jim Thompson, Wyle Laboratories, Norco, Ca., and Mike Capella, Omaha Public Power District, Omaha, Nebraska, April 21, 1982.
Subject:
Containment Temperatures for Fort' Calhoun Nuclear Generating Station, Unit 1.
- 30. Omaha Public Power District, Fort Calhoun Station, Unit 1, Electrical Equipment Qualification Report, SER Section 3.4, Enclosure 1, Enclosure 6 (pages 6-49 through 6-52) and Enclosure 12.
_ _ _ _ _ _ _ . _ _ _a
gmm REFCOT NO.
SCIENTIFIC $ERVICES & $YSTEMS GROUP 22 WESTERN OPERATIONS, NORCO FACluTY PAG ( NO
/
EE.ECTRICAL PEllETRATION CANISTER OT WADS Ot" IRRAfttENE $PT TAPE
/
STEEL JACEET IAYERS OF IRRAT1tEt4E SPT TAPE POLYSUtICHE INSUIATIOtt
%" IRRASJL SILICONE RUBBER TAPE t' TRANDED CONDUCTOR izi h u s *
\%3 t ,,.,,,n.
j . >
~
mwQ%g%T iff'""'
- 2a e bgv s la e e- 1=~!
IEEX INJT .
ONNECTOR NEOPltEHE JACEL f Ovt.R Mt.I'E INSUIATION
A812 PEllETRATION COtWMIC10R R.T.V. 3145 FIGtn E 1 INSUtATION or "E" CADLE CONNECTIOt45 FOR CONTAINMENT VENT FAN FIGURE 1*
INSULATION OF "E" CABLE CONNECTIONS OReference 24 1
L _ _ _ _ _ _ _ _ _ . _ _ _
g 26333-26 REPORT NO-l Sc!ENTIFIC $ERVICES & $YSTEMS GROUP 23
- WESTERN OPERATIONS, NORCO FACIUTY PA03 W
. . i e iesig i i ia ieiig i i a iiiisl e i '}.:
f,,,__,,,,,,,f~ CONTAINMENT PRESSURE 300 - 50--
! ; / .,,' ~ ~ ,' ~ -
- / s s :
. I s -
, n b :. I s* CONTAINMENT ATMOSPHERE G he I s TEMPERATURE Ui 40-~
t s :: / 'N ' 6 :
!! i
- g. ;
a j
/ SUNP WATER TEMPERATURE N N o id i
1 -
/ g -
- / \ E 302:
- / \
- / \ ;
g 200 -- / g -
- l \ : -
i :' \
- O~
- \N 2
\
- 32' DOUBLE EHOED BREAK, MINIMUM SAFETY INJECTION g :
- 3 SPRAY PUMPS ,1 SPRAY HEADER. \
g \:
l 3 \ 10 -~
NN :
s
! 'N. [
100 ' ' ' ' l ' ' ' ' 'l ' ' ' ' 'l i iE 10 10 0 1000 TIME (SECONDS)
FIGURE 2 CONTAINMENT TEMPERATURES FOLLOWING LOCA i
t t - ____ _ __ ___ _
I g 26333-26 REPORT NO.
SCIENTIFIC SERVICES & SYSTEMS GROUP 24 WESTERN OPERATIONS, NORCO FACluTY PAGI *
.o _
.i ,
,,,,,ii , ,
e :
rf '
m n --
I i @ @ @ @ E 3
y 40 -
fh : -
w : :
'a : :
g- .
' 3o L
<r -
@32"StiGLE ENDED . DREAM, NO SAFETY -
lg ; ItuECTON, 3 SPRAY PUMPS, i SPRAY llEADER -
'y :
@24" SEJGLE EllDED DREAK, NO SAFETY :
I HJECTION, 3 SPRAY PUMPS, l SPRAY ltEADER _
..~ @ 18" SilGLE EtOED BREAK, ido SAFETY ~_
[ -
ItuECTOtl, 3 SPRAY PUMPS,1 SPR AY llEADER -[
! @l2"SitlGLE ^ EtIDED BEEAH, to SAFETY !
3 .
It# JECT 0tl 3 SPhAY PUMPS,1SPRAYHEADER[
,o -
i i i il,oo o,- i i i i i i iil . . . , , ,,,,,il -
a woo TIME (SECOHOS)
FIGURE 3 CONTAINMENT PRESSURE
\;
e
- _ _ _ _ _ _ _ _ _ . i
f MMM REPORT NO.
SCIENTIFIC SERVICES & $Y$TEMS GROUP 25 WESTERN OPERATIONS, NORCO FACillTY PAGE NO i
a 4 I 6 i t e s 3 : aig i i a a a i ag i
, isl Franklin Institute Test !
~
SER Section 3.3 Average Test Temperature .: -
- MSLB Temnerature Curve Dwell 297F For 100 Minutes or 6.000 Seconds .~
~
Ah}VME. . ,(@lAiHMENT
/ -
300 L ..enw^= PRES%w ._5URE / sa
'w.,,,~, N - _
- /
/
f
/
%q -
') '
_1 -
+j.
/ / %
p , / w ,'s N.J'N..-- m. , ,,w;; .,a;t :< .1 I
- / f j CONh',tiMMENT ATMOSPHEREi, $ tj ~
, Di Q s TEMPERAMRE J~ 7""""'"O a [- f I
's N
i q.j 6 . ! .:
/ NL . .
s ?
ci
/ I N'
/ l s V. l} hi,; - e):
s %. -em;:-
a Y-
. j '
\ d ii} [ . 2 j !
3 : / AREA A E g 2
s \':
F : /
- ME30
- / AREA B C 8 \
\
\ ;: .:i :-4:e.
l i
200 - /
. / - \ \' .cm - ::!- s
- / l
\
\
V q 1
./
\\ -Q.4:
l
- /
l \
kN
- \
32" DOUBLE ENDED BREAK , MINIMUM SAFETY INJECTION \ !
- N .
N -
3 SPRAY PUMPS l $ PRAY HEADER. i
. s -
3 l-
\N 102 N
52 Seconds - s ;
i N 's,:.
eil , i .,I , , , :
100' i i e i i i i i i .
, , , '8l00 10 goo TIME (SECONDS)
FIGURE 4 i SER SECTION 3.3 MSLB TEMPERATURE CURVE l
l
~
REPORT NO SCENTIFIC SERVICES & $YSTEMS GROUP 26 western OPERATIONS, NORCo FACIUTY PAGE NO TABLE 1 CABLE DESCRIPTION I.D. Cable No. No. Type Function 319 W-10 1/C 300 MCM Containment Vent Fan Motors 325 W-21 3/C #10 480 V, 3 @ Power for Motor Operated Valves (MOV) 328 W-38 3/C #12 120 V,1 @ Control for MOV and 120 VDC on PC1849 330 W-40 4/C #12 120 VDC Control to Solenoids and
. Limit Switches i
331 W-41 7/C #12 120 V,1 0 Control for MOV and HCV 1107A and HCV 1108A 4
323 W-57 2/C #14 TS Pair Drain Wire Using all Instruments i
1 k _ _ _ _ _ _ . _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ . . _
f 26333-26 REPORT NO.
._- -.m-m OPERAM N N 27 pagg no TABLE 2 CABLE SPLICE IDENTIFICATION Exposure to item I.D. (Cable Splices) Cable (Cable Splices) (Cable Splices) Containment Screws
- Reference No. No. Materials No. Type Description Manufacturer Atmospherer Page No. No.
l t 330 Polyolefin W-40 4/C f12 Splices at Trans- Amp & American No* 6 50 (Enc.78 323 Dow Corning W-17 2/C fit mitter Pamcor LER-80-006) 3145 RTV Clear TS Pair 15 ingle heat 10,4 shrink splice) 2 31?A 1.5cotch Tape f 70 W-10 t/C 300 Cable Splices at 3M Company & No *
- 6-38 (Enc. f ?)
- 2. Bishop Tape F3 MCM the 480V Containment Bishop 7 3.5cotch Tape #88 Vent Fan Motor Lead 5.Dow Cornmg Wir es (V A-3A, 313, 3144 RTV 7C 7D)
! ) 3196 l.Irrathane $PT Tape W-10 t/C 300 The 480V Contain- General Electric Yes 6-52 (LER 30-007) 2.trrasil Tape MCM ment Fan Motor Lead 3
- 3. Scotch Tape f 33 5pfb es at the 4.Dow Caning Elerthcal Pene-314)RTV tratics 4 32) Polyolefin Original Plant Amp & Penniube Yes e-49 (Enc. 78 328 Neoprene W-213/C fl0 Cable Splices at X A-545E-462) 330 Dow Corning W-38 2/C f12 Electrical Pene- 10 331 3141 R TV 040 4/C F12 trations, 323 Clear W-417/C P12 (double W-571/C F14 heat shrink)
T5 Pair S Cross-linked Poly. TM1 Modification at WCSF-N Yes N/A )
olefin 5-ill? Containment Pene. Raychem Adhesive (Hotmelt tration Lead Wire Polyethylene Copoly- Splices mer) e Polyolet m W-40 4/C f t2 Splices at Amp & American No* 6-49 W-512/C f14 Solenoid Valves Pamcor T5 Pain (double heat steink splice) l
- Inside Condulets fReference 11 "Inside Terminal Bou 5ystem Component Evaluation work Sheet f
t
+ . _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . _ _ _ - - _ _ _____-_-_-___-___-_________a
l Tant.E 3 Report No. 26333-26 AGirr. MATRIX Page No. 28
'8 ## l ' C 11lk'C' "
aren S E "V " * "dd'3 7 3"86 sta>t etArmit Amuru twrt.RI AIS Afdl HEftAl#G
,, HADIATIOld 8NAI. Accing:rrr Aerivatsors ant pcte:stevi t>AMAGE: (hAns) talpptA1. ACCl[ggrr i Cable splices at Transmitter Tei;lperature (1) Polyolefin (1)5.0 x 108 120 189 (2)
(days)
AMP & American Pamcor 84F (29C) 305F (152C) 0.86 (Ref.12)
Relati ,e ilumidity (2)3145 RTV (Ref.13)
(2)2.5 x 107 120 > 120 9015% 100 % 1.67 (Ref.14) (Ref. 4)
P essure Atmospheric Max. 60 psig R, diation 3.42 x 105 rads 3.0 x 107 rads 2 Cable Splices at the 480V Cor.tais me .t Ten perature (1) Scotch Tape f 70 (1)l.0 x 106 120 > 120 (3)
Vent Fans Motor Lead Wires 84F (2YC) 305F (152C) (silicone rubber) (Ref.15) 3M Company & Bishop Electric Relati e ilumidity I.64 (Ref.16) 9015% 100 % - (2) Bishop Tape #3 (2)2.0 x 108 120 52 l P essure (polyethylene base) (Ref. 23) (days)
Atmoshperic Max. 60 psig assumed polyethylene '
R. diatior. 1.1! (Ref. 21) l 3.42 x 105 rads 1.92 x 107 (3) Scotch Tape f 88 (3)l.9 x 107 120 73 (3)
Vinyl plastic (poly- (Ref.15) (days) vinyl chloride assumec) 1.19 (Ref.17)
(4)3144 RTV (4)l.02 x 108 120 >l 20 (4)
(assumed clear (Rei. 7)
RTV 3145) 1.67 (Ref. I4) 1 1
TAllLE 3 I Report No. 26333-26 AGING MAlltlX Page No. 29
'" d"T^ "
- T'***' '
- Ekvin: eram:Tims gy )
'((f artH tiarant u tiska:H HAtrHI As.*s Atate 3
pamaxs Holmas. urs ot trr AcTavATim un:pcarslev) twwa: IpAns) ta'4mAI. ACCIDENT 3 The 480V Containment Vent Fan Mol, >r Tei iperature (1)lrrathene (1)5.0 x 107 120 34 Splices at the Electrical Penetration 84F (29C) 105F (152C) SPT Tape (Ref. 23) (days)
General Electric Relat se ilumidity (Ethylene Propylene 9015% 100 % Rubber) 1.34 (Ref. 22 i ressure (2)lrrasil (2)l.0 x 106 120 >120 (5,3)
Atmospheric Max. 60 psig Silicone Rubber Tape (Ref.15)
R idiation (irradiated silicone 3.42 x 105 rads 1.12 x 106 ra< , rubber) 1.64 (Ref.16)
(3) Scotch Tape #33 1.6 x 107 120 73 Vinyt plastic (Poly- (Ref.15) (days) vinyl chloride assumes )
1.19 (Ref.17)
(4)3145 RTV 2.5 x 107 120 >l20 1.67 (Ref.14) (Ref. 4) 4 Original Plant Cable Splice Teriiperature (t) Polyolefin (I)3.0 x 108 120 189 at Electrical Penetrations 84F (29C) 305F (152C) 0.86 (Ref.12) (Ref.13) (days)
Amp. & Penntube Relati ce ilumidity (2) Neoprene (2)l.0 x 106 120 4 (days) (6) 9015% 100 % l.05 (Ref.18) (Ref.15)
P essure (3)3145 RTV (3)2.5 x 107 120 >l20 Atmospheric Max. 60 psig 1.67 (Ref.14) (Ref. 4)
Ri diation 3.42 x 10 5' rads 2.5 x 107 5 TMI Modification at Containment All the condition s are the same (1)Polyoteiin (1)5.0 x 108 120 55 (7)
Penetration Lead Wire Splices as item No. 3 abave Crosslinked (Ref.13) (days)
Raychem WCSF-N 1.29 (Ref.19)
(2) Adhesive (2)3.7 x 107 120 52 (flotmelt Polyethylene: (Ref.15) (days)
Copolymer) 1.1 I (Ref. 21) 6 Cable Splices at Solenoid All the condition s are the same Polyotefin 5.0 x 108 120 189 Valves as item No. 4 at>ive 0.86 (Ref.12) (Ref.13) (days)
Amp - American Pancor
MMM REPORT NO. 2b333 b SCIENTIFIC SERVICES & SYSTEMS GRour WESTERN OPERATIONS, NoRCo FACluTY PAGE 2 30 TABLE 3 REMARKS (1) Unless otherwise noted, Calculated Accident Life listed is in addition to 120 years Calculated Normal Life.
(2) Has shown to exhibit excellent radiation resistance when irradiated to levels of 5.0 x 107 rads, gamma (Ref.10).
(3) Satisfactory test results were obtained when subjected to radiation fields in the neighborhood of 30-100 x 106 (Ref. 7).
(4) Dow Corning no longer manufactures RTV 3144; the replacement product is RTV 3145 clear, which is basically the same product (Ref. 26, 27).
(5) An investigation of this splice indicates that its composition would allow it to withstand the LOCA conditions (Ref. 5).
(6) Has been irradiated to levels of 5,10, and 25 x 106 rads by the Penntube Plastics Co., with no evidence of degradation as a result of these exposures (Ref.10).
(7) This splice system has been tested to a radiation dose up to 200-290 x 106 with satisfactory results (Ref. 3).
t I
MMM REPORT NO. b ~b saENTalC $ERVICES & $YSTMS GRoOP WESTERN oPERATlONS, NoPCO FA CIUTY 3g PAGE NO TABLE 4 EVALUATION
SUMMARY
EQUIPMENT: Cable Splices at Transmitters EVALUATION RESULTS PARAMETER PLANT TEST ANALYSIS REMARKS Thermal Aging 40 years - 120 years at Section 4.1.1 (Normal and DBE) 84F plus DBE at 305F Radiation Aging 3.0 x 107 -
5.0 x 107 Section 4.1.2 (Rads)
Temperature (F) 305 -
305 Section 4.3.3 Pressure (psig) 60 -
60 Section 4.3.4 Chemical Spray 2500 ppm Protected by Section 4.3.5 Boron RTV 3145 Relative 100 - 100 Section 4.2 Humidity %
Submergence Flood level -
Above Flood SCEW Sheet Elev.1000.9' Level p. 6-50 t
MMM REPORT NO_ b333~2b
$OENTIFIC $ERVICES & $YSTEMS group WESTERN OPERATION $, NoRCo FACluTY PAGE NO 32 TABLE 5 l EVALUATION
SUMMARY
EQUIPMENT: Cable Splices at the 480V Containment Vent Fan Motor Lead Wires EVALUATION RESULTS PARAMETER PLANT TEST ANALYSIS REMARKS Thermal Aging 40 years - 120 years at Section 4.1.1 (Normal and DBE) 84F plus DBE at 305F Radiation Aging 1.92 x 107 -
1.0 x 108 Section 4.1.2 (Rads)
Temperature (F) 305 -
305 Section 4.3.3 Pressure (psig) 60 -
60 Section 4.3.4 Chemical Spray 2500 ppm -
Boric acid Section 4.3.5 Boron in excess of 5%
Relative Humidity % 100 -
100 Section 4.2 Submergence Flood level -
Above flood Scew Sheet Elev.1000.9' level p. 6-51
MMM REPORT NO. 2b333-26
$CENilFIC SERVICES & $YSTEMS GROUP WESTERN oPERAnoNS, NORCo FACluTY PAGE No 33 TABLE 6 EVALUATION
SUMMARY
EQUIPMENT: The 480V Containment Vent Fan Motor Splices at the Electrical Penetrations EVALUATION RESULTS PARAMETER PLANT TEST ANALYSIS REMARKS Thermal Aging 40 years - 120 years at Section 4.1.1 (Normal and DBE) 34F plus DBE at 305F Radiation Aging 1.12 x 106 -
1.6 x 106 LER 80-007 (Rads) Section 4.1.2 Temperature (F) 305 -
305 Section 4.3.3 Pressure (psig) 60 -
60 Section 4.3.4 Chemical Spray 2500 ppm -
Protected by Section 4.3.5 Boron RTV 3145 Relative 100 - 100 Section 4.2 Humidity %
Submergence Flood level -
Above flood SCEW Sheet Elev.1000.9' level p. 6-52
)
l l
f M REPORT NO_ 2b333-20 soENTIFIC SERVICES & systems GROUP WESTERN OPERATIONS, NoRCO FACluTY PAGE NO TADLE 7 EVALUATION
SUMMARY
EQUIPMENT: Original Plar.t Cable Splices at Electrical Penetrations EVALUATION RESULTS PARAMETER PLANT TEST ANALYSIS REMARKS Thermal Aging 40 years -
120 years at Section 4.1.1 (Normal and DBE) 84F plus DBE at 305F Radiation Aging
- 1.36 x 107 * -
2.5 x 107 Section 4.1.2 Temperature (F) 305 285-295 305 Section 4.3.3 Pressure (psig) 60 60 Section 4.3.4 Chemical Spray 2500 ppm 1% pH 9.5 Protected by Section 4.3.5 Boron RTV 3145 Relative 100 100 Section 4.2 Humidity %
Submergence Flood level -
Above flood SCEW Sheet Elev.1000.9' level p. 6-49
- Application has teflon insulated lead wires as interface. Need test to confirm splice will perform safety function under radiation.
MMM REPORT NO. 26333-26
$CENTIFIC SERVICES & $YSTEMS GROUP Wi$ FERN OPERATIONS NoRCO FACluTY PAGE NO 35 TABLE 8 l EVALUATION
SUMMARY
EQUIPMENT: Containment Penetration Lead Wire Splices (Raychem WCSF-N)
EVALUATION RESULTS PARAMETER PLANT TEST
- ANALYSIS REMARKS Themal Aging 40 years 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br /> 120 years at Section 4.1.1 at 150C 84F plus DBE at 305F Radiation Aging ** 1.12 x 106 *
- 2.0 - 2.9 5.0 x 108 Section 4.1.2 x 108 Temperature (F) 305 390 305 Section 4.3.3 Pressure (psig) 60 66 Section 4.3.4 Chemical Spray 2500 ppm 6200 ppm Section 4.3.5 Boron Boron Relative 100 100 100 Section 4.2 Humidity %
Submergence Flood level -
Above flood SCEW Sheet Elev.1000.9' level p. 6-52
- Wyle Test Report No. 58442-1 (Ref. 3)
- Application has teflon insulated lead wires as interface. Need test to confirm splice will perform safety function under radiation.
I REPORT NO-sc==c es=ces a syst=s =
women OPEmADONU80 ECD PAQUTY 36 I
TABLE 9 EVALUATION
SUMMARY
EQUIPMENT: Cable Splices at Solenoid Valves EVALUATION RESULTS PARAMETER PLANT TEST ANALYSIS REMARKS Themal Aging 40 years 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br /> 120 years at Section 4.1.1 at ISOC 34F plus DBE at 305F Radiation Aging 1.36 x 107 -
5 x 108 Section 4.1.2 Temperature (F) 305 --
305 Section 4.3.3 Pressure (psig) 60 - 60 Section 4.3.4 Chemical Spray 2500 ppm -
Protected by Section 4.3.5 Boron NEMA condulet and conduit system Relative Humidity % 100 -
100 Sectin 4.2 Submergence Flood Level -
Above flood level Scew Sheet Elev.1000.9' p. 6-49
n..- - a a a - - . -- -- -
s - - . - - -
h:
'. t ATTACHMENT l
l I
l 0
l l
\
l l
r i
N - _ .._ _ _ _ -- _ . . - . - - - - - - - . - . . - ---- - - - - ------ - - - - - - -