ML20032A868

Manufacturer Stress Rept for Electrical Penetration

ML20032A868
Person / Time
Site:	Brunswick
Issue date:	03/01/1974
From:	Korner R WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:
Shared Package
ML20032A854	List: ML20032A853 ML20032A858 ML20032A861 ML20032A864 ML20032A868
References
IEB-79-01B, IEB-79-1B, PEN-RLK-7-11-73, NUDOCS 8111020488
Download: ML20032A868 (20)

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PEN-RLK-7-11-73 g

WESTil1GH'00SE ELECTRIC CORPORATION

.ELECTRCNIC TUSE DIVISION 4

P. O. BOX 284

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El.MIRA, NEW YORVs 14902

!ianufacturer's Stress Report for Electrical Penetration Contract CP141-9521-01-ilC-1 Brunswick #1 and #2 1

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Preface 1.1 Desien Parameter's.:.

These have been p(escribed in design specification prepared by UE&C.

1.2 Hermal Cenditicas The normal operating temperature of the electrical penetration

' will not exceed 150 F.

The internal working pressure will be 15 psig. External pr' essure at the containment.tnd wili vary from -0.5 psis to 2.0 psig. This is not the severest condition, hence no structural analysis will be made.

1.3 Accident Environ ent First 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> of accident the temperature will be 340 F with a maximum external prellure of 56 psig on the inboard end of the penetration.

t 1.4 Pressure Tegnerature Ra3 ne The penetration assembly shall be designed to a maximum pressure of 62 psig and a maximum temperature of 340 F.

l.5 Aonlicable ASME Code Section ill Class MC.

The penetration is a continuation of the containment vesse,1 pressure boundary.. (Code stamping is not, required since the containment vessel is concrete and metal, and is not subject to an extsting code.)

2.

Structural Analvsis

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The fillet weld shown in dwg. E2593 on the inboard end of the penetration is subjected to the highest stress.

Penetration class A, B, C, D & F are Pi to PI welds. Class E is a P1 to P8 weld.

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= 89 sq. inches P1 A1 F)

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= 62 x 89

= 5518 lbs.

A2 = 17 0 x L1

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Per HE3359.1 General Requirement under (b) the allowable stress value for a fillet weld is 49% of the stress value for the vessel material.

Penetration classes A, B, C, D, F are constructed with SA333 grade 6 vessel material.

Per table 1-10.1 this material has an Sm value of 0

16,500 psi at 360 F.

Sshear =.6 Sm =.6.. I,500 = 9,900 psi S llowable = 495 x 9,900 = 4851 psi.

a This compa res with 673 psi calculated.

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The design is satisfactory e

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Fenetration class E is constructed with an SA240 type 304 vessel material.

Per table 1-10.2, this material has an Sm value of 17,800 psi at 400 F.

Sshear =.6 Sm =.6 x 17,800 = 10,680

.Sallowable " 43% x 10,680 = 5233 psi This compsres with 673 psi calculated.

The design is satisfactory.

3.0 Thermal Analysis is unnecessary since the maximum temperature the assembly will be subjected to is only 340 F.

S values for this m

temperature were utill:ed,,

4.0 Fatione evaluation is also unnecessary since only a few cycles will be experienced in the forty year plant life.

5.0 Seismic analysis has been treated' by actual test conducted on each class of penetration.

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MEMORANDUM

$m!ted engineema-m

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No.

9527-058 OrricE:

PHILADELPHIA OcPT.

Reliability & Quality Assurance DATE:

October 17, 1980 To:

S. Rubin /R.N. Brey 11UO COPIES:

Ju Silverwood/RH Leonard BB Scott RR Cerzosimo 14U3 DC Marr 14U4 Fn:M:

D. M. Kelly /W. Majkowski 14U6 Project File File H-338-3 SueJEcT:.

Carolina Power & Light Company Brunswick Steam Electric Plant TRANSMITTAL OF MATERIALS EVALUATION OF WESTINGHOUSE ELECTRICAL PENETRATION ASSEMBLIES The materials of construction of the Westinghouse electrical penetration assemblies listed in the attached materials evaluation report have been reviewed, e.--

All of the electrical penetration assemblies evaluated have been judged acceptable for 30 day post-LOCA service.

W. Majk'owski Materials Engineer WM/ fbh Reviewed By:

_R'.E. Moore e es Supervising Engineer Corrosion Engineering l

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MATERIALS ENGINEERING EVALUATION 0F ETICTRICAL PENETRATION ASSEMBLIES FOR 30 DAY Post-LOCA SERVICE The electrical penetration materials of construction, excluding the metals, have been qualification tested per Reference 1 for steam, presere, temperature, flammability, corrosive outgassing and radiation. Tests for flammability, corrosive outgassing and radiation are complete and accept'able for all penetrations for the planned 40 year life of the plant. The evaluation of the materials suitability for 30 day post-LOCA service therefore must be judged on the basis of 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> tests for steam, pressure and temperature as reported '.n Reference 1, the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> tests of the prototype penetration modules as reported in References 82, 3, 4, 5 and basic materials properties which are available from manufacturers' literature and materials handbooks as referenced herein. The metallic components are relatively insensitive to the

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limits of the parameters being considered here and are therefore judged acceptable.

Testing of components per Reference I was performed at 175 C (347 F) for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> at 90 psig steam pressure followed by 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> at 150 C (302 F) at a steam pressure of 55 psig. Testing per References 2, 3, 4, 5, as applicabte to the respective types of penetrations was performed at 340 F for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> at 56 psig followed by 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> at temperatures ranging from 200 F to 302 F and reduced pressures.

The Reference 1 temperature-pressure profile is far more severe than that to which the materials would be exposed during an actual LOCA where the maximum temperature in containment peaks at less than 300 F at a maximum steam pressure of 50 psig and drops to about 170 F at 12-15 psig within twenty minutes.

Pressure and temperature subsequently decay asymtotically to ambient values at an assumed relative humidity of 1007..

The more severe temperature-steam-pressure exposures cited above can be considered an accelerated test program for the materials of construction and for the configuration of the penetration assemblies.

Based on a thorough evaluation of the referenced test data, the materials and penetrations are judged acceptable for 30 days of post-LOCA service. However, further consideration to justify this conclusion is presented in the following discussion of the various classes of penetrations for those materials unique to that penetration class.

5 C1. ASS B AND C PENETRATIONS Westinghouse drawing Nos. E-2453, E-2455, E-2456 Class B Plant Id. Nos.:

X-105B, X-105C, X-105D, X-105E, X-105G, X-105H, X-105K, X-105J Class C Plant Id. Nos.:

X-102A, X-102B, X-1020, X-102E, X-102F, X-102H The non-metallic materials used in the construction of Class B and C penerations, common to both penetratione, consist of the following:

1.

Polyform 105 heat shrinkable tubing 2.

Kynar heat shrinkable tubing 3.

Scotchcast XR-5126 epoxy potting compound 4.

Sylgard 185 epoxy potting compound 5.

Polyplate (polyester fiberglass filled) bracing disk 6.

Silicone rubber fiberglass insulation 7.

Okonite EPR insulation with neoprene jacket These materials have been individually evaluated with respect to water absorption, resistance to 100% relative humidity and maximum recommended service temperatures.

(Reference 8) These materials are relatively insensitive to moisture and their maximum service temperatures exceed the 170 F maximum temperature following the LOCA extreme conditions for which they were previously qualified.

CLASS E PENETRATION ASSEMBLIES Westinghouse drawing No. E-2458 Plant Id. Nos.:

X-100A. B. C.

D. E, F. C. H The materials unique to Class E penetrations are:

1.

Kovar - glass seal assemblies 2.

Raychem Coax and Triax cables 3.

Co'ax connectors (Amphenol)

The glass and Kovar (29 Ni - 17 Co - Fe alloy) are not sensitive to moisture so the seal assemblies are not affected by the 30 day exposure to high humidity at the stated time-temperature profile.

Raychem Flamtrol Coax and Triax cables are qualfication tesmed by Raychem per their Specification No. 60, Para. 4.3.3.3 at times, temperatures and steam pressures as follows:

+ 18 o

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at 340 F - O at 60 psig

+5 30 days at 200 F

-0 at atmospheric pressure Insulation testing of the cables is performed during and af ter this temperature-s team-pressure exposure.

These cables are therefore considered suitable for 30 days post-LOCA service.

Amphenol Coax connectors consisting of Amphenol No.82-503 (special) jack and No. 28650 (special) plug were subjected to LOCA temperature-pressure-humidity tests with the prototype penetration module (Reference 3) but were not subjected to radiation exposure.

Detailed evaluation of the materials of construction of these Amphenol connectors disclosed that the internal insulator in these connectors is radiation cross linked polyethylene (XLPE) as denoted by the "special" following the Amphenol part number.

XLPE has performed satis-factorily af ter being irradiated to 1.256 x 10 rads (Reference 1).

CLASS F PENETRATION Wertinghouse drawing Nos. E-2459, E-2842 Plant Id. Nos.-

X-104A. F The non-metallic materials used in the Class F penetrations are:

1.

Polyform 105 heat shrinkable tubing 2.

Scotchcast XR-5126 epoxy potting compound 3.

Scotchcast XR-5237 epoxy potting compound 4.

Stycast 2850FT epoxy potting compound 5.

"Q" resin epoxy potting. compound 6.

Polyplate (polyester fiberglass filled) bracing disk 7.

Polysulfone insulation o.

8.

Amphenol connectors (Silicone rubber insert)

These materials have been individually evaluated with respect to water absorption, resistance to 1007. relative humidity and maximum recommended service temperatures.

(Reference 8) These materials are relatively insensitive to moisture and their maximum service temperatures exceed the 170 F maximum temperature following the LOCA extreme conditions.

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RE FERENCES 1.

Design Approval Tests on Materials Used in Westinghouse Penetrations for the Brunswick Station of Carolina Power and Light Company.

2.

Westinghouse Accident Environment Test Report for Class B, C, D Penetrations, PEN-RLK-3-16-01, March 1973.

3.

Westinghouse Accident Environment Test Report for C1ssa E Penetration, PEN-RLK-02, March 1973.

4.

Westinghouse Accident Environment Test Reports for Class F Penetration, PEN-RLK-5-2;4-73, March 1975, with Addendum and Report #AB - 11/12/73.

5.

Westinghouse Report - The Qualification of a Modular Type Electric Penetration Following the Requirements of IEEE Standard #317 - 1972, PEN-TR-75-6, March 1975 with Addendum 1 and 2.

6.

Raychem Wire and Cable Division Specification 60, August 1973, 7.

Materials in Design Engineering, July 1960; How Radiation Affects Engineering Materials, Richaq4.E. Bowman; Radiation Effects Information

~ Center, Battelle Memorial Institute.

8.

Materials Engineering / Materials Selector 1972, 1975, 1976, 1979.

9.

Engineering Alloys, 5th Edition, Woldman & Gibbons.

10.

EPRI NP - 1558, A Review of Equipment Aging Theory and Technology, September 1980.

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C05T0:1 Hi3UlfiTED M :5 & CT.5LE CO.

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E:nere.! D& S!:.d TEST:

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PAR:

TEST tio.:

_ _ Autoclave Test:

-- L.O.C.A. Conditiens 377 Col 4D111oNING:

f DATE:

Sample received radiation doce of 10'3 rods.

Jan. 1" 1972 Tr*TEDBY4ed.i,.,_.-

PART. TYPE No.:

3

-%*'W. f LSS 1727D (.'ce conctruction belca;. )

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TEST REQUIReuerm:

,.. m u, lita: uiW.7 oaf F,oric Acid Spray -- 0.20 molar Loron nu hnric acid uith a TEMP.:

RH:

0.019 m< lar ::olu. ion of nodiun hydro <ide to give a pH of 3-8.5

.Inte of flor lean the:1 but not c,rca:er ther. 1 quart / min.

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(b) Alumin'xr.-M lar : shield l1" x 00,15", 2 lap C.255'

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Test No. 8714 CONTAII51Ei:7 TECT L: ass-o f-Coolan t Accident Evaluation 1.

Irradiate a sufficient length of shielded cable by gamma radiation tc a dose of 1 x 10D rads.

2.

Place a lensth of irradiated cable in an autoclave with at least e13ht feet exposed to the autoclave environment.

3 Expose the cable to the following autoclave conditions.

Throughout the autoclave cycle. the cable shall be sprayed with a solution of 0.23 molar boron as boric acid with the pH edjusted to 5 0 (min.) to 9.0 (max.)

with lithium hydroxide-(0.03 colar max.).

The relative humidity throughout the test shall be maintained at 100%.

(a)

Raise the temperldure to 2 EOF and the pressure to 60 pula (45 psi.-) minimum with the relative humidity at 100%.

Maintain this condition for 60 minutes.

After the cable has been at these conditions for at least 30 minutes, measure the insulation resistance at 500 volts de between

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adjacent conductors and between all conductors connected together and the shield.

(b)

Reduce the temperature to 205 - 215F and the pressure to 14.7 psia, maintaining the relativo humidity at 100%.

Maintain this condition for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

At the end of the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period, measure the insulation resistance at 500 volts de between ad.jacent conductors and between all conductors and One shield.

Alco, apply 600 volts ac for 5 minutes betueen conductors and between all conductors together and the shicid.

The cable shall be considered to meet the containment test if no breakdown occurs.

The voltage test shall be repcated at 1.5 kV ac for information only.

The insulation resistance and voltsge tests shall be made while the cable is still in the autoclave with the temperature at 205 - 215F at 14.7 psia and 100% relative humidity.

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f H-338-1 ronM noo MEM'ORAN DU M

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,@mited enginsars a_m a No.

9527.058 OFF!cE:

Philadelphia DEPT.

Reliability & Quality Assurance DATE:

October 15, 1980 D

S. Rubin /R.N. Brey 11U0 COPICS:

JB Silverwood/RH Leonard BB Scott RR Cerzosimo 14U3 DC Marr 14U4 FROM:

W. Majkowski 14U6 Proiect File File H-338 1 File (QA) 14U5

SUBJECT:

Carolina Power & Light Co.

Brunswick Steam Electric Plant Transmittal of Materials Evaluation of Boston Insulated Wire & Cable Co.

Instrumentation Cables The following instrumentation cables fabricated by Boston Insulated Wire

& Cable Company are similar in construction and use common materials of construction.

Materials were evaluated for the " worst" case in-containment condition.

These materials have been evaluated based on BIW test data for radiation exposure and 26 hour3.009259e-4 days <br />0.00722 hours <br />4.298942e-5 weeks <br />9.893e-6 months <br /> exposure to temperature-pressure-humidity data which exceed the initial 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> LOCA conditions. This data was supplemented by data from other sources for generically similar materials and general materials properties data.

On the basis of the above criteria, these cables are judged acceptable for 30 days post-LOCA service.

Cable Plant I.D. Nos. MA 16, MC 16, TC 16 XA 16, & XE 16 W. Majkowski Materials Engineer Reviewed By:

@ J)

R.E. Moore Supervising Engineer Corrosion Engineering

a EVALUATION OF BOSTON INSULATED WIRE AND CABLE CO. INSTRUMENT CABLES FOR 30 DAY POST-LOCA SERVICE Plant ID Nos. - MA 16, MC 16, TC 16 XA 16 & XE 16 The subject cables are similar in construction and utilize the following common non-metallic materials:

1 - Flame Retardent, cross-linked polyethylene (XLPE) insulation 2 - Aluminum / Mylar Film Tape (shield) 3-eoprene/ Glass Tape 4 - Neoprene jacket (s) (external covers)

RADIATION As reported in BIW Test No. 8714 (attached) a two conductor cable constructed of these materials was exposed to 1 x 108 rads of gamma radiation and was sub-sequently subjected to a 26 hogr, LOCA time-temperature-pressure profile at 100%

relative humidity for insulation resistance tests as follows:

10 minutes at 310 F - 80 PSIG 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at 284-291 g 55 PSIG 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at 210-212 F - 0 PSIG 23 hours2.662037e-4 days <br />0.00639 hours <br />3.80291e-5 weeks <br />8.7515e-6 months <br /> at 2120F -

- 0 PSIG Since cable No. TC 16 is used in containment which represents the worst case condition for all the subject cables, justification for OO day post LOCA service for this cable should qualify all of these cables.

The reported 1 x 108 rads of radiation exposure tgsting as reported by BIW does not meet the specification requirement of 1.1 x IT rads. However, supplement-ary data for the same generic material proves the respective material satisfactory for this application as follows:

1 - Neoprene was irradiated to 1.17 x 108 rads per Reference 1 without significant effect on elastomeric properties.

2 - Per Reference 2, XLPE as primary insulation was irradiated to 2.0 x 108 rads without significant loss of resistance or ductility. Reference 2 stategthat tensile strength of polyethylene at 1012 ergs per gram (C)

(^/10 rads) is 25% lower than initial tensile strength so that physical properties of the material are not seriously impaired by radiation doses 8

of 1.1 x 10 rads.

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4 3 - Mylar film exhibits ng change in tensile strength or elongation at doses up to 3 x 10 ergs per gram (C) (^> 3 x 10 rads). At 7

8 about 1 x 10 rads, Mylar tends to darken and become embrittled.

However, in this application as an aluminumized tape beneath the neoprene jacket, the loss of ductility of the Mylar is not per-tinent to the electrical performance of the cable (Reference 3).

8 The effect on glass of radiation doses of 1 to 2 x 10 rads is one of d iscoloration only which is not significant to the performance of the neoprene /

glass tape used in this cable (Reference 3).

_P_RESSURE - TEMPERATURE - HUMIDITY EXPOSURE The LOCA time-temperature profile consists of rapid heating to a peak temperature of about 290 F at 50 psig and drops to about 1700F at 12-15 psig within 20 minutes followed by subsequent temperature and pressure decay to near ambient values. Relative humidity (R.H.) is assumed to remain at 1007..

The BIW test temperature-pressure-relative humidity profile of 310 F for 10-15 minutes at 80 psig followed by one hour at 284-291 F at 0

50-55 psig far exceeds the LOCA peaks of 290 F at 50 psig for less than 20 minutes.

This constitutes a-far more severe test than the LOCA conditions.

Reference I certifies that a neoprene (Okoprene) jacketed cable "will pass an exposure to steam at 90 psig and 340 F for six hours and still satisfactorily function".

These conclusions are drawn from resistance tests between shield and conductor as well as conductor-to-conductor.

Actually impairment of cable performance would require moisture penetration through the neoprene jacket, through the aluminized mylar wrap and through the primary insulation of XLPE.

Permeation of moisture through the neoprene jacket alone would not result in a cable failure.

Neoprene's resistance to surface degradation is demonstrated by the following exerpt from Reference 4.

"An early jacketed cable that has been kept on an outtoor. test rack in a stressed condition since 1935 has yet to show detectable surface degradation".

The resist-ance of XLPE to the temperature-pressure humidity condition can be seen from Raychem Specification 60 for testing wire and cable insulation wherein generically similar-insulation is tested at 3400F at a steam pressure of 60 psig for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> followed by exposure at 200 F for 30 days.

On the basis of the tests performed and the above information, this cable is judged acceptable for 30 day post-LOCA Service.

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REFERENCES 1 - Westinghouse Electric Corp Report; Design Approval Tests on Materials used in Westinghouse Penetrations for the Brunswick Station of Carolina Power and Light Company; The Okonite Company, certification No. 1, Certification for Nuclear Environments.

2 - Raychem Corporation Catalog; Coax Data Sheets 10481 and 10483 3 - Materials in Design Engineering, July 1960; How Radiation Effects Engineering Materials, Richard E.

Bowman; Radiation Effects Information Center 4 - DuPont Catalog No.,A,86651, "DuPont Neoprene", Part 1, Page 4 4

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