ML20209E296

Responds to NRC Re Deficiencies Noted in Equipment Qualification Insp Rept 50-298/86-28.Corrective Actions:Encl Documentation Package Eqdp 235, T & B STA-KON Connectors, Generated to Address Thermal Aging Effects

ML20209E296
Person / Time
Site:	Cooper
Issue date:	04/16/1987
From:	Trevors G NEBRASKA PUBLIC POWER DISTRICT
To:	Gagliardo J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
CNSS877215, TAC-68378, NUDOCS 8704300018
Download: ML20209E296 (32)

Text

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j Mr. J. E. Gagliardo, Chief Reactor Projects Branch U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive Suite 1000 Arlington, Texas 76011

Subject:

Supplemental Information Regarding Inspection Report 50-298/86-28

Dear Mr. Gagliardo:

This letter is written in regard to your letter dated April 1, 1987, which transmitted the Equipment Qualification (EQ) Inspection Report 50-298/86-28.

Therein you indicated that certain deficiencies existed within our FQ Program.

Specifically, Appendix A, Item 7. and Appendix B, Paragraph 4.f(8) (Item Number 298/8628-07) both discuss inadequate qualification of interface cabling to Fenwal/Patel Temperature Switches. This issue was identified as requiring our immediate attention during a telecon involving NRC representatives (Messrs. J. Jaudon, R. Ireland, and A. Johnson) and members of the CNS staff on April 6, 1987. As agreed upon during the telecon, contained herein is supplemental information which supports our contention that the interfacing cable splices are fully qualified to D0R guidelines. For ease of understanding, the two aforementioned specifics from your letter are repeated below, followed by our response.

Appendix A, Item 7.

Contrary to (f) and (k) of 10CFR50.49, end Section 5.1 of the DOR Guidelines, the EQF for Fenwal/Patel temprature switches, Model No.

01-170230-090, EQDP 220A, did not adequately establish qualification because of failure to base the qualification of the interfacing cable splices on full accident conditions, including service life for radiation and aging ef fects. The T& B STA-KON friction crimped splices were qualified for steam testing only (Paragraph 4.f(8), 50-289/8628-07).

Appendix B, Paragraph 4.f(8), EODP 220 and 220A, Fenwal/Patel Temperature Switches. Models 01-170020-090 and 01-170230-090 These switches are located throughout the plant and are placed near the main steam lines. The switch monitors the ambient temperature and in the f event of a steam leak will actuate when the area temperature reaches

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190*F increasing. The switches are used for a high energy line break (llEl.B) accident and must operate for one hour post accident.

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J. E. Gagliards April 16, 1987 Page 2 EQDP 220A did not adequately establish qualification because of failure to base the qualification of the interfacing cable splices on full

accident conditions including service life for radiation and aging The splices are constructed by using Thomas and Betts STA-KON effects.

friction fit crimped connectors with loose black barrel sleeves covering the connections. The EQDP documented these splices qualified to interface Class 1E instruments to field cables with the qualification l based on a steam test only. Contrary to Section 5.1 of the DOR Cuidelines, there was no documentation or data to support a full accident

{ environment with an analysis or subsequent test reports which would be required to completely qualify these splices for their application.

Also, during the NRC walkdown inspection it was noted that the field installation of the interfacing cable splices is dependent upon the l

confined space inside of the conduit to keep the loose barrel sleeve in i

place over the electrical connection; this represents poor design and installation practice. This item is considered a Potential Enforcement / Unresolved Item (50-298/8628-07).

j RESPONSE Our original interpretation of Section 5.1 of the DOR guidelines was that the steam test of the electrical connections between the temperature switches and the field wiring was adequate to establish qualification. A discussion of this test was addressed in EQDP 220, Section F.5, " Functional Testing". EQDP i 220 is the source document for the Fenwal/Patel Temperature Switches and, as such, contains the key document references. EQDP 220A is a supplement to l EQDP 220 and was developed to cover additional temperature switches which were qualified after EQDP 220 was written.

As a result of the Inspection Report and your recent telecon, we realized that our documentation inadequately addressed radiation and thermal aging effects.

l Subsequently, a unique documentation package, EQDP 235, was generated, entitled, "T & B STA-KON Connectors". This EQDP is included as Attachment A

to this letter for your reconsideration. In the EQDP, the steam test envelopes the required pressure, temperature, and humidity for the stated accident times. An analysis is also included for radiation and thermal aging, i This documentation package substantiates the qualification for the connectors, I as permitted in DOR Cuidelines, Section 5.1.

l In a separate but related matter, during the NRC walkdown inspection, the reviewer noted that field installation of the interfacing cable splices is l dependent upon the confined space inside of the conduit to keep the loose barrel sleeve in place over the electrical connection. The reviewer noted

i. that this represents poor design and installation practice. However, this i installation has proven to be adequate in service and is effectively controlled via Station Surveillance Procedure 6.2.1.6.1, " Steam Line Break j Detection Temperature Switches Change Out for Calibration".

l t

i

J. E. Grgliardo April 16, 1987 Page 3 If you have any questions regarding this response, please contact me or G. R. Horn at Cooper Nuclear Station.

V

. A. Trevors Division Manager of Nuclear Support GAT:JMM:SJJ:ya Attachment cc: U.S. Nuclear Regulatory Commission Regional Office, Region IV NRC Resident Inspector Cooper Nuclear Station l

l 4

, i INFORMATION ONLY EQUIPMENT QUALIFICATION DATA PACKAGE I

PACKAGE NUMBER: 235 EQUIPMENT TYPE: STA-KON Connectors RA18-250F (Female)

MODEL NUMBER: 18RA-250T (Male) MANUFACTURER: Thomas and Betts PREPARED BY:

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DATE: -/d"37 CHECKED BY: %C hc.\ os DATE: 4- f b-[

APPROVED BY: , DATE: W"/d ~ 7 I' d i

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PACKAGE NUMBER: 235 PAGE 1 0F 29

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, s INFORMATION ONLY EQUIPMENT QUALIFICATION DATA PACKAGE RECORD OF REVISION PACKAGE NUMBER: 235 EQUIPMENT TYPE: STA-KON Connectors RA18-250F (Female)

MODEL NUMBER: 18RA-250T (Male) MANUFACTURER: Thomas and Betts REVISION REVIEWED EFFECTIVE NUMBER DATE BY CHECKED APPROVED PAGES DESCRIPTION OF CHANGE PACKAGE NUMBER: 235 . PAGE 2 0F 29

)

I i L6 INFORMATION ONLY '

EQUIPMENT QUALIFICATION DATA PACKAGE I s TABLE OF CONTENTS A. Purpose.

B. Procedure. j C. References. g D. Equipment Description. f

\

1. Manufacturer.

2. Component. 1

3. Model Number (s).

L

4. System (s).

5. Plant Identification Number (s).

6. Location (s).

E. Environmental And Functional Parameters.

9

1. Normal Environment.

a. Installed Life,

b. Temperature.

c. Pressure. ,

d. Relative Humidity. ,

e. Radiation. t ,

2. Accident Environment. t

a. Limiting Accident.

b. Operating Time.

c. Temperature.

d. Pressure.

c. Relative ilumidity.

f. Chemical Spray.

g. Radiation.

h. Submergence.

3. Normal Functional Requirements.

4. Accident Functional Requirements.

PACKAGE NUMBER: 235 PAGE 3 0F 29

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', . , INFORMATION ONLY EQUIPMENT QUALIFICATION DATA PACKAGE i

i P. Equipment Evaluation. .g i-

!ri 1. Test Specimen Evaluation. i

\

. ;2. Similarity Of Tested Equipment To Installed Equipment.

s i,

, . 3. TestSequenceEjaluation. (

4. Service Conditions.

s ,

{  !

a.- Operating Time.

b. Temperature Conditions. ]i

c. Pressure Conditions.

d. Relative Humidity.

' ,* e. Chemical Spray.

f. Radiation.

g. /.ging.

( 1. Mechanical Wear Aging.

2. Thermal Aging.

's i h. Synergistic Effects.

. i. Submergence.

7

5. Functional Testing.

/ 1 l

G. Condiusion.

11 . Response to NRC IE Notices / Bulletins.

'1

,I . Equipment Qualification Maintenance Requirements.

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1 3 PACKAGE NUMBER: 235 PAGE 4 0F 29

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0 m INFORMATION ONLY EQUIPMENTQUALI{ICATIONDATAPACIAGE l t ,

I i

A. Purpose. ,

- The purpose of this evaluation is to determine if the qualification documentation available for the Class IE equipment in the Cooper Nuclear Station provides reasonable assurance that it will perform its required function in the specified accident environment.

B. Procedure. ,

The evaluation will be performed in accordance with Enclosure 4 of .

! IE Bulletin 79-01B [2] and CNS Engineering Procedure 3.12.2, Rev. 3 [14].

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! PACKAGE NUMBER: 235 PAGE 5 0F 29 i

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INFORMATION ONLY EQUIPMENT QUALIFICATION DATA PACKAGE C. References.

1. Test Report on Steam Accident Simulation of T & B STA-KON Connectors,

Patel Report PEI-TR-870100-02, Rev. A, dated December 16, 1986, D.I. 2302.

2. Environmental Qualification of Class 1E Equipment, NRC Office of Inspection and Enforcement Bulletin No. 79-OlB, dated January 14, 1980, D.I. 1410.

3. ROC f rom M. Chatham to G. Elam, "T & B DBE Test Mounting", dated April 8, 1987 D.I. 2352.

4. " Temperature Switch Current Leakage for Connector Qualification",

D.I. 2291.

5. SWEC Radiation Calculations, SWEC Report 13095.31 Rev. 1, dated August 15, 1985, D.I. 2082.

6. Accident Profiles for EQ, dated August 17, 1985, D.I. 2097.

7. CNS DC 86-140, "EQ Flooding Modifications", dated December 16, 1986, D.I. 2300.

8. PERAL Calculations for PVC Sleeving, D.I. 2350.

9. CNS Functional Assurance Program, Master Equipment List, Revision 7, dated August 20, 1985, D.I. 2139. (See Note 1)

10. G.E. Specification 22A2928, Rev. 2, dated April 16, 1971, D.I. 004,

11. EQDP 46, Accident Environment.

12. EQDP 220, Patel/Fenwal Temperature Switches.

13. Standard IEEE 650-1979, Appendix E, " Cycling of Connectors", D.I. 2351.

14. CNS Engineering Procedure 3.12.2, Rev. 3, dated September 4, 1986, D.I. 2200.

15. EPM Letter, R. Lemos (EPM) to J. Flaherty (CNS) Master Equipment List Validation, dated March 2, 1987, D.I. 2353.

16. CNS Surveillance Procedure 6.2.1.6.2, Rev. 3, " Steam Line Break Detection

. Temperature Switch Calibration".

NOTE 1: The T & B connectors shall be included in the next revision of this document.

PACKAGE NUMBER: 235 PAGE 6 0F 29

INFORMATION ONLY EQUIPMENT QUALIFICATION DATA PACKAGE D. Equipment Description.

The Thomas and Betts electrical connectors (RA18-250F/18RA-250T) and plant supplied PVC insulation sleeving are electrical interfaces for the Patel/Fenwal temperature switches [12]. The interfaces have been used for temperature switches since initial operation of CNS.

1. Manufacturer.

Thomas and Betts.

i

2. Component.

l Crimped electrical connections with PVC insulation (plant supplied) for CNS temperature switches (steam leak detectors).

3. Model Number (s).

STA-KON Connector P/N's:

RA18-250F (Female crimp connector) .

18RA-250T (Male crimp connector).

4. System (s).

MS, HPCI, RCIC, RHR, RWCU.

5. Plant Identification Number (s).

The subject connectors and insulation assembly is used as the electrical

- interface for the following CNS temperature switches:

COMPONENT IDENTIFICATION CODE 6. LOCATION (S) ENV. PROFILE

• OP. TIME

• MS-TS-121,122,123,124: A,B,C,D R-903 Steam Tunnel B 1 Hour HPCI-TS-101,102,103.104: A,B R-903 Inj. Viv. Rm. R 8 Hours j

HPCI-TS-101,102,103,104: CD R-881 SW Torus D 8 Hours HPCI-TS-125,126,127,128: A,B,C,D R-859 SWQ-HPCI F 8 Hours RCIC-TS-79,80,81,82: A,B,C,D R-859 NE Torus D 1 Hour RHR-TS-150,151,152,153: A,B,C,D R-881 NW, SW Torus .D 8 Hours RHR-TS-154,155,156,157: A,B,C,D R-903 RHR RX Rm. I 8 Hours RHR-TS-158,159,160,161: A,B,C,D R-931 RHR RX Rm. I 8 Hours "

RWCU-TS-81A-H R-931 RWCU Hx Rm. K 1 Hour RWCU-TS-150,151: A,B,C,D R-931 RWCU HX Rm. K 1 Hour RWCU-TS-152,153,154,155: A,B,C,D R-931 RWCU Pump Rm. J,T 1 Hour i RWCU-TS-156,157,158,159: A,B,C.D R-881 SE Torus D 1 Hour

• [ Reference 9, 15]

PACKAGE NUMBER: 235 PAGE 7 0F 29

INFORMATION ONLY EQUIPMENT QUALIFICATION DATA PACKAGE E. Environmental And Functional Parameters.

1. Normal Environment.

Parameter Reference

a. Installed Life.

40 years. [10]

b. Temperature.

180* F, maximum. [See Note 1 below]

c. Pressure.

Atmospheric; -1.0" to -0.1" WG. [11]

d. Relative Humidity.

40% normal; 20%-98% range. [11]

e. Radiation.

t Included in accident radiation dose. [5]

l NOTE 1: Per the Control Room log dated April 9, 1987, plant temperatures outside the drywell should not exceed 180*F (plant temperatures are recorded once per day). Corrective measures are taken once temperatures exceed 180*F. Therefore, for conservatism, the normal ambient service temperature is assumed to be 180*F.

PACKAGE NUMBER: 235 PAGE 8 0F 29

. . . - . -- . .=. -.

INFORMATION ONLY EQUIPFENT QUALIFICATION DATA PACKAGE

2. Accident Environment.

Parameter Reference

a. Limiting Accident.

HELB. [6,11]

b. Operating Time.

8 Hours. [15]

c. Temperature.

296*F (Profile I, worst case). [6,11]

See enclosed Profiles,

d. Pressure.

31.6 psia (Profile R, worst case). [6,11]

. See enclosed Profiles.

e. Relative Humidity.

j 100% R.H. [11]

f. Chemical Spray.

None. [Ill j

g. Radiation.

} 2.132 x 10 R, gamma (MS equipment). [5]

4 5.418 x 10 R, gamma (RWCU equipment). [5]

5.12 x 10 R, gamma (HPCI, RCIC, RHR equipment). [5]

h. Submergence.

None. [7]

PACKAGE NUMBER: 235 PAGE 9 0F 29

INFORMATION ONLY EQUIPMENT QUALIFICATION DATA PACKAGE PROFILE B 24" MSLB IN MAIN STEAM TUNNEL TRANSIENT IN MAIN STEAM TUlmEL 300 T = 2. 87 "F 30 P= 3 a.'l P5M 250 g

( "

2 3 S e S 200 m

T {o.

O f @

15 - I

• M "' P I '"I' V N -

150 T= t % (,

• F l l I i 1 //

0 50 100 150 200 250 Time (Seconds) t ,.

FIGURE I References (6, 11]

PACKAGE NUMBER: 235 PAGE 10 0F 29 w- __ ___ ___

INFORMATION ONLY EQUIPMENT QUALIFICATION DATA PACKAGE PROFILE T 3" RWCU LINE BREAK IN RWCU PUMP ROOM TRANSIENT IN RWCU PUMP ROOM, ELEVATION 931'6" 250 T= . tis 'F i

? C 200 *v Y 20 e 3 -

s e

u u

f615.1 psia r-154 F E.

15 O T= AIMOSPhede -

150$

1 1 I I I //

0 50 100 150 200 250

- Time (Seconds)

FIGURE 2 References (6, 11]

PAGE 11 0F 29 PACKAGE NUMBER: 235

~

IblFORMATION ONLY EQUIPMENT QUALIFICATION DATA PACKAGE PROFILE D 10" IIPCI LINE BREAK IN TORUS AREA TRANSIENT IN TORUS AREA, ELEVATIONS 859'9" AND 881'9" 20 -

250 7 T= 2.I'l* F , C t i L 3 P: 15.9 psia. T " M 1. F 200

• 8 15 - P = Atmosoheric.'

B C

a 150 E 0 t S

A: e 10 -

100 I I I I I //

0 50 100 150 200 250 Titae (Seconds) l FIGURE 3 References {6, 11]

i I PACKAGE NUMBER: 235 PAGE 12 0F 29

fNFORMATION ONLY EQUIPMENT QUALIFICATION DATA PACKAGE PROFILE I RHR LINE BREAK IN RHR RX ROOM TRANSIENT IN RHR HX ROOMS, ELEVATION 903'6" AND 931'6" 3

n T -#16*F 25 -

250 9 .

o. 20 h Isin. -

200

., T= 111 F S E O 150 h 15 7 Alrn Ml2})Prie P

10 - - 100 1 i i i i //

0 50 100 150 200 250

. Time (Seconds)

FIGURE 4 References.[6, Il}

235 PAGE 13 0F 29 PACKAGE NUMBER:

+~w - - - . - - , ---,a-m . , 7 , -m 4

- --ee --

INFORMATION ONLY EQUIPMENT QUALIFICATION DATA PACKAGE i

PROFILE F llPCI LINE BREAK IN HPCI ROOM TRANSIENT IN HPCI ROOM, ELEVATION 859'9" 300 Y= E9*F 25 --

250 9 C N j9 -

200 20

- P n,2p;(

d o

15 -

P = At rilosj)he>,1a 150 n< y 10 - - 100 I I I 1 i / /

0 50 100 150 200 250 Time (Seconds)

FIGURE 5 References [6, 11]

PACKAGE NUMBER: 235 PAGE 14 0F 29

INFORMATION ONLY EQUIPMENT QUALIFICATION DATA PACKAGE PROFILE R HPCI LINE BREAK IN INJECTION VALVE ROOM TRANSIENT IN INJECTION VALVE ROOM, ELEVATION 903'6"

~

% US F 9=31.6 psia. ~

30 - ~

n a

9 T= 2ol F ,

1 / / -

200

• vp. 25 -

f g

n T=190T M Y

8 m -

150 y e

f 20 m

t-l'oo is - P: Atmosoharie.

i i i i i /LL 200 250 500 50 100 150 0

Time (Seconds)

FIGURE 6 References (6, 11]

PACKAGE NUMBER: 235 PAGE 15 0F 29

INFORMATION ONLY EQUIPMENT Qt!AI.IFICATION DATA PACKAGE PROFILE K RWCU LINE BREAK IN REACTOR BUILDING, ELEVATION 931'6" TRANSIENT IN Tile RWCU HX ROOM, ELEVATION 931'6" 25 -

T = 233*F,

-250 20 -

- -200 P = 21.9 psia T= 176*F 15 - T (*F P _ Atmospheric

~

150 10 -

- - 100 0 / /

50 100 ISO 200 250 # /

Time (seconds)

FIGURE 7 References (6, lll PACKAGE NUMBER: 235 PAGE 16 0F 29

INFORMATION ONLY i EQUIPMENT QUALIFICATION DATA PACKAGE PROFILE J HPCI LINE BREAK IN THE INJECTION VALVE ROOM TRANSIENT IN THE RWCU PUMP ROOM AND THE GENERAL FLOOR AREA, ELEVATION 931'6" 17.F

---250 P = 15.3 psia P = Atmospheric 15.0- .

. ~~

C T = 208'F P (psia)

T= 163*Fi, T (*F)

' f--150 T = 160*F

12. 5 --

- -100 100 150 200 250

!W 500 0 50 Time (seconds)

FIGURE 8 References (6, 11}

PACKAGE NUMBER: 235 PAGE 17 0F 29

,- o INFORMATION ONLY EQUIPMENT QUALIFICATION DATA PACKAGE

3. Normal Functional Requirements.

Provide electrical interface for steam leak detector temperature switches.

4. Accident Functional Requirements.

Provide electrical interface for temperature switches used to monitor area temperature for leak detection.

235 PAGE 18 0F 29 PACKAGE NUMBER:

m INFORMATION ONLY EQUIPMENT QUALIFICATION DATA PACKAGE

, F. Equipment Evaluation.

This evaluation will be performed in accordance with Enclosure 4 of IE Bulletin 79-01B [2].

Report (s): Test Report on Steam Accident Sinulation of T & B STA-KON Connectors, Patel Engineers Report No. PEI-TR-870100-02, Rev. A

[1].

1. Test Specimen Evaluation.

The test assembly consisted of four Thomas and Betts STA-KON connector pairs (RA18-250F and 18RA-250T) insulated with commercially available (CNS supplied) PVC sleeving (3/8" diameter). The connector pairs were mounted directly to a ground plate inside a NEMA-4 junction box. The test specimens were assembled by CNS personnel such that the test assembly was representative of actual installations [1].

1 During steam accident testing the internals of the junction box were exposed directly to the steam environment conditions [3].

2. Similarity of Tested Equipment To Installed Equipment.

i The . tested equipment is judged to be a representative model of CNS field installations based on 1) test materials being the same as used in the plant (i.e., RA18-250F/18RA-250T connectors and plant supplied 3/8" PVC 3

tubing), 2) electrical loading during DBA testing was the same as required i for temperature switch operction, 3) mounting of the specimens in the junction box was similar to field installations (i.e., specimens mounted directly to a ground plate via cable ties, whereas the connections for field installations are confined in condulets such that the PVC tubing is restrained over the connections), and 4) the test specimens were assembled by CNS personnel using common plant practice, as used in making field installations. In addition, the test assembly was exposed directly to saturated steam conditions during test via unsealed conduit [3]. This test configuration demonstrates the worst possible case at CNS.

i

3. Test Sequence Evaluation.

The connector assembly test program was performed in the following l

sequence:

l i

Functional Test Steam Accident Test Functional Test This test sequence was performed as specified by the D0R Guidelines, i Section 5.1 [2]. Thermal and radiation aging are addressed in Sections F.4.g.2 and F.4.f of this EQDP, respectively. Therefore, the test sequence is acceptable.

PACKAGE NUMBER: 235 PAGE 19 0F 29

INFORMATlON ONLY EQUIPMENT QUALIFICATION DATA PACKAGE

4. Service Conditions,

a. Operating Time.

1) Required:

8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. [15]

2) Reported:

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. [1]

3) Discussion:

The test program operability time (Figure 9) exceeds the required time. Therefore, operability time is satisfied.

b. Temperature Conditions. ,

1) Required:

. 296*F (Profile I). [6, 11]

2) Reported:

i.

304*F (Figure 9) [1]

f

( 3) Discussion:

The peak test temperatures (304*F) envelopes the worst case plant profile (Profile I) peak temperature. Therefore, the l

temperature requirements are satisfied.

l I

PACKAGE NUMBER: 235 PAGE 20 0F 29

600 Legend Required Temp. .

Actual Temp. y ;' ,Y y Required Press.- - - - -

g Actual Press. -:  : ;

n -

+

C 350 a

m

= IP, sec 5 min E ac tual actual N 304'F c -

300 30 sec ~

~ required r ukNd 32 min m O

actual @

2,57'f j 52 psig m ,

g 250 -

- 50 y 29 23 hrs 33 min o w

requQd , c actual ;g gi

,, w A CC

' ' " F " "

X m 200 a

er 23.5 hrs a5 required gx 3 N

~ " -% s 150 9

, 19 ps19 - 20 S

, -f >

• / U 11 Psi 9 n 100 O m / l' i ' -

" ha 10

/ x w

/ l g

~ / [o y

/ \ --t

/ o O a v )

m 2

~

To O

• 2 t-~

M

~.' .

INFORMATION ONLY EQUIPMENT QUALIFICATION DATA PACKAGE

c. Pressure Conditions.

1) Required:

31.6 psia (16.9 psig, Profile R). [6, 11]

2) Reported:

52 psig (Figure 9). [1]

3) Discussion:

The peak test pressure (52 psig) envelopes the worst case required accident peak pressure (16.9 psig) . Therefore, the pressure requirements are satisfied, f d. Relative Humidity.

1) Required:

j 100% R.H. [11]

) 2) Reported:

Saturated steam (100% R.H.). [1]

3) Discussion:

The media used during the accident simulation test was saturated

! steam [1]. Therefore, the relative humidity requirements are i satisfied.

i PACKAGE NUMBER: 235 PAGE 22 0F 29

. lNFORMATION ONLY

, EQUIPMENT QUALIFICATION DATA PACKAGE l

e. Chemical Spray.

, 1) Required:

Not applicable. [11]

2) Reported:

i None. [1]

3) Discussion:

Chemical spray is not postulated for equipment located outside containment.

9 I

l

f. Radiation.

I

! 1) Required:

0 5.418 x 10 Rads, gamma. [5]

i 2) Reported:

1.9 x 10 Rads, gamma. [8]

3) Discussion:

The worst case radiation requirements are exceeded by a factor i

of 3.5 when compared to the radiation damage threshold of the non-metallic material (PVC). Therefore, the radiation require-3 ments are satisfied.

i, l

PACKAGE NUMBER: 235 PAGE 23 0F 29

- . - - - . , . . - , . . . - - - - _ = . . ---..-.--.--- - - -- - . . . - - - - - - - . - - ,

INFORMATION ONLY EQUIPMENT QUALIFICATION DATA PACKAGE

g. Aging.

1. Mechanical Wear Aging.

a) Required:

40 cycles. [See Discussion]

2) Reported:

Not applicable.

3) Discussion:

The connection assemblies are used to interface CNS steam leak' detectors (Patel/Fenwal temperature switches) to CNS plant cable. Per Reference 16, the temperature switches are calibrated every outage where the connectors are disconnected /

connected once. Calibration of the temperature switches results in 40 connect / disconnect cycles of the connectors over a 40 year plant life (40 outages, assuming intervals of 12 months). Per IEEE 650-1979, Appendix E [13], cycling of connectors for low duty cycles will not create any age-related i

failure mechanism. Cycling the connectors 40 times over a 40 l year plant life is judged to be a low duty cycle; thus, mechanical wear testing is not required. Therefore, the mechanical wear aging requirements are satisfied.

J l 2. Thermal Aging.

l a) Required:

40 years at 180*F, worst case. [See Section E.1.b]

b) Reported:

> 40 years at 180*F. [8]

c) Discussion:

The only safety related non-metallic material used in the connector assembly is the plant supplied polyvinyl chloride

! (PVC) insulation. Using Arrhenius methodology, PVC has an expected life of 96.5 years at 180*F [8]. Therefore, the connector assembly is judged to have a qualified life of 40 years at the worst case CNS service temperature requirements.

PACKAGE NUMBER: 235 PAGE 24 0F 29 i

- - . _ . . _ ,, _. _,_,_____.__,,_._ _ _. _ ,.._ _ .. _ - - _ _ _ , _ - . . _ . . ~ _ , - - - . _ . . . _ _ . _ . . , _ _ _ . , _ _ _ _ . _ . . _ _ _ _ _ . _ .

INFORMATION ONLY EQUIPMENT QUALIFICATION DATA PACKAGE

h. Synergistic Effects.

1) -Requi. red:

Not applicable. [2]

2) Reported:

Not applicable.

3) Discussion:

Synergistic effects are not required to be addressed for DOR qualification. [2]

i. Submergence.

1) Required:

Not applicable. [7]

2) Reported:

i Not applicable.

l

3) Discussion:

Submergence is not postulated at CNS. [7]

i i

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5. Functional Testing.

The subject electrical interfaces described in Reference I were exposed to accident environments in excess of CNS requirements. The test configuration demonstrated a less than one milliampere current leakage throughout DBA testing. Per Reference 4, this is an insignificant level of leakage and does not affect operability. Therefore, the functional requirements are satisfied.

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G. Conclusion.

The preceding qualification evaluation has shown that the equipment described in Section D of this report is qualified for its intended use. This evaluation was performed in accordance with the guidelines set forth in Enclosure 4 of IE Bulletin 79-01B.

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-a 4 (NFORMATION ONLY EQUIPMENT QUALIFICATION DATA PACKAGE H. Response to NRC IE Notices / Bulletins:

Applicable X Not Applicable IE Notice No.86-104 Disposition:

Butt splice connectors supplied by G.E. failed (excessive leakage current) during environmental qualification tests for Commonwealth Edison. Four samples were removed from the Quad Cities Nuclear Power Station and were subjected to testing. The test samples were identical to those connectors installed at Dresden. The connectors in question were nylon insulated butt splices, used for 12 to 22 gauge, and were supplied by Amp, Thomas and Betts, or Hollingsworth.

The connectors used for the steam leak detectors at CNS are Thomas and Betts RA18-250F/18RA-250T connectors insulated with 3/8" PVC tubing. CNS performed steam exposure tests in excess of CNS requirements on test specimens representative of installed configurations.

The test samples never exceeded 1 mA of leakage current throughout the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> steam test. This leakage current has been determined not to affect function of the steam leak detection system. Therefore, the subject connector configurations are qualified for CNS applications.

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INFORMATION ONLY EQUIPMENT QUALIFICATION DATA PACKAGE I. Equipment Qualification Maintenance Requirements:

SOURCE CNS PM MAINTENANCE ITEM DOCUMENT NUMBER COMMENTS

( S.P. 6. 2.1.6.1

1. Change out of temperature N/A N/A switches.

(1) Surveillance Procedure - Steam Line Leak Detection Temperature Switch Changeout for i

Calibration 4

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