ML20236G064
| ML20236G064 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 07/30/1987 |
| From: | Gagliardo J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Trevors G NEBRASKA PUBLIC POWER DISTRICT |
| Shared Package | |
| ML20236G066 | List: |
| References | |
| NUDOCS 8708040118 | |
| Download: ML20236G064 (1) | |
See also: IR 05000298/1986028
Text
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-In Reply Refer To:
Docket: 50-298/86-28
Ji 30 IW
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Nebraska Public Power District
ATTN: George A. Trevors
Division Manager - Nuclear Support
P. 0. Box 499
Columbus, NE
68601
Gentlemen:
Thank you for your letters . dated April 16,1987, April 29,1987, and
June 17, 1987, in response to our letter dated April 1,1987. The
information you have supplied is under review.
I
Sincerely,
.
Original Sigml by:
J. E. GAGLIARDO
,
i
J. E. Gagliardo, Chief
Reactor Projects. Branch.
'
cc:
f
Guy Horn, Division Manager
of Nuclear Operations
Cooper Nuclear Station
P. O. Box.98
Brownville, tiebraska
68321
Kansas Radiation Control Program Director
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Nebraska Radiation Control Program Director
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April 16, 1987
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APR 211987
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Mr. J. E. Gagliardo, Chief
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Reactor Projects Branch
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,
U. S. Nuclear Regulatory Commission
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Region IV
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611 Ryan Plaza Drive
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Suite 1000
Arlington, Texas 76011
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Subject:
Supplemental Information Regarding Inspection Report 50-298/86-28
j
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 EQ 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/Patr.1 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 repeatet
below, followed by our response.
Appendix A, Item 7.
Contrary to (f) and (k) of 10CFR50.49, and Section 5.1 of the DOR
Guidelines, the EQF for Fenwal/Patel temperature 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), EQDP 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
event of a steam leak will actuate when the area temperature reaches
190*F increasing.
The switches are used for a high energy line break
gu
ped * %]
(HELB) accident and must opers e for one hour post accident.
_ - --_-__
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- J.
E. Gegliardo
.
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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
l
accident conditions including service life for radiation and aging
)
effects.
The splices are constructed by using Thomas and ,Betts STA KON
j
friction fit crimped connectors with loose black barrel sleeves covering
I
the connections.
The EQDP documented these splices qualified to
I
interface Class 1E instruments to field cables with the qualification
I
based on a steam test only.
Contrary to Section 5.1 of the DOR
Guidelines, 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
confined space inside of the conduit to keep the loose barrel sleeve in
l
place over the electrical connection; this represents poor design and
installation practice.
This item is considered a Potential
Enforcement / Unresolved Item (50-298/0628-07).
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
220 is the source document for the Fenwal/Eatel Temperature Switches and, as
such, contains the key document references.
EQDP 220A is a supplement to
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.
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.
This documentation package substantiates the qualification for the connectors,
as permitted in DOR Guidelines, Section 5.1.
In a separate but related matter, during the NRC walkdown inspection, the
reviewer noted that field installation of the interfacing cable splices is
dependent upon the confined space inside of the conduit to keep the loose
barrel sleeve in place over the electrical connection.
The reviewer noted
that this represents poor design and installation practice.
However, this
installation has proven to be adequate in service and is effectively
controlled via Station Surveillance Procedure 6.2.1.6.1,
" Steam Line Break
Detection Temperature Switches Change Out for Calibration".
m
.
,
,
J. E. Gagliardo
4
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' April 16, 1987
Page 3
.
If you have any questions regarding this response, please contact me or
l
G. R. Horn at Cooper Nuclear Station.
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.
A'. Trevors
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Division Manager of
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Nuclear Support
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GAT:JMM:SJJ:ya
Attachment
cc:
U.S. Nuclear Regulatory Commission
Regional Office, Region IV
,
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NRC Resident Inspector
'
Cooper Nuclear Station
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INFORMATION ONLY
EQUIPMENT QUALIFICATION DATA PACKAGE
,
PACKAGE NUMBER: _
-235
EQUIPMENT TYPE:
STA-KON Connectors
RA18-250F (Female)
!
MODEL NUMBER:
18RA-250T (Male)
W'UFACTURER:
Thomas and Betts
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PREPARED BY:
--
DATE:
CHECKED BY: %C Ac.
DATE: 4- f b-[
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W"/[~ 7
APPROVED BY:
DATE:
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PACKAGE NUMBER:
235
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INFORMATION ONLY
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EQUIPMENT QUALIFICATION DATA PACKAGE
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RECORD OF REVISION
1
PACKAGE NUMBER:
235
EQUIPMENT TYPE:
STA-KON Connectors
RA18-250F (Femalc)
MODEL NUMBER:
18RA-250T (Male)
MANUFACTURER:
Thomas and Betts
' REVISION
REVIEWED
EFFECTIVE
NUMBER
DATE
BY
CHECKED
APPROVED
PAGES
DESCRIPTION OF CHANGE
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PACKAGE NUMBER:
235
PAGE
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INFORMATION ONLY
EQUIPMENT QUALIFICATION DATA PACKAGE
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TABLE OF CONTENTS
!
.
A.
' Purpose.
!
B.
Procedure.
C.
References.
D.
Equipment Description.
1.
Manufacturer.
2.
Component.
3.
_Model Number (s).
-
,
4.
System (s).
.
-
-
5.
Plant Identification Number (s).
6.
Location (s)..
E.
Environmental And Functional Parameters.
1.
Normal Environment.
a.
Installed Life,
b.
Temperature.
c.
Pressure.
d.
Relative Humidity,
e.
Radiation.
2.
Accident Environment.
' Limiting Accident.
a.
b.
Operating. Time.
c.
. Temperature.
,
d.
Pressure.
'
e.-
Relative Humidity.
f.
Chemical' Spray.
g.
Radiation.
h.
Submergence.
,
3.
Normal Functional Requirements.
4.
. Accident Functional Requirements..
i
PACKAGE NUMBEP:
235
FACE
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INFORMATION ONLY
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EQUIPMENT QUALIFICATION DATA PACKAGE
F.
Equipment Evaluation.
.l.
Test Specimen Evaluation.
2.
Similarity Of Tested Equipment To Installed Equipment.
3.
Test Sequence Evaluation.
4.
Service Conditions.
a.
Operating Time.
j
b.
Temperature Conditions.
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c.
Pressure Conditions.
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d.
Relative Humidity.
e.
Chemical Spray.
f.
Radiation.
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g.
Aging.
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1.
Mechanical Wear Aging.
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2.
Thermal Aging.
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h.
Synergistic Effects.
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1.
Submergence.
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S.
Functional Testing.
G.
Conclusion,
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H.
Response to NRC IE Notices / Bulletins.
I.
Equipment Qualification Maintenance Requirements.
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PACKAGE NUMBER:
235
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INFORMATION ONLY
(
EQUIPME!!I QUALIFICATION DATA PACK.4GE
A.
Purpose.
The purpose of this evaluation is to determine if the qualification
documentation available for the Class 1E 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 Procedu e 3.12.2, Rev. 3 [14].
.
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PACKAGE NUMBER:
235
PAGE
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INFORMATION ONLY
EQUIPMENT QUALIFICATION DATA PACKAGE
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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 IE Equipment, NRC Office 'of
Inspection and Enforcement Bulletin No.79-01B, dated January 14, 1980,
D.I. 1410.
3.
ROC from M.
Chatham to G. .Elam,
"T & B DBE Test Mounting", _ dated
April'8, 1987, D.I. 2352.
4.
" Temperature Switch current Leakage ' for Connector Qualifica tion,
-
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. -(Sec 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
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INFORMATION ONLY
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EQUIPMENT QUALIFICATION DATA PACKAGE
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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.
,
1
Thomas and Betts.
2.
Component.
J
Crimped electrical connections with PVC insulation - (plant ~ supplied) for
CNS temperature switches (steam leak detectors).
I
.
3.
Model Number (s).
1
STA-KON Connector P/N's:
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RA18-250F (Female crimp connector).
18RA-250T (Male crimp connector).
]
4.
System (s).
l
5.
Plant Identification Number (s).
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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
HPCI-TS-101,102,103,104: C,D
R-881 SW Torus
D
8 Hours
HPCl-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 RRR HX Rm.
I
8 Hours
RHR-TS-158,159,160,161: A,B,C,D
I
8 Hours
RWCU-TS-81A-H
R-931 RWCU Ex Rm.
K
1 Hour
RWCU-TS-150,151: A,B,C,D
R-931 RWCU IOC Rm.
K
1 Hour
!
RWCU-TS-152,153,154,155: A,B,C,D
R-931 RWCU Pump Rm.
J.T
1 Hour
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RWCU-TS-156,157,158,159: A,B,C,D
R-881 SE Torus
D
1 Hour
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- [ Reference 9, 15]
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PACKAGE NUMBER:
235
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INFORMATION ONLY
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EQUIPMENT QUALIFICATION DATA PACKAGE
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E.
Environmental And Functional Parameters.
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1.
Normal Environment.
!
Parameter
Reference
a.
Installed Life.
40 years.
[10]
b.
Temperature.
180*F, maximum.
[See Note 1 below]
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c.
Pressure.
~
Atmospheric;
-1.0" to'-0.1" WG.
[11]
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d .,
Relative Humidity.
!
40% normal; 20%-98% range.
[11]
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e.
Radiation.
i
Included in accident radiation dose.
[5]
NOTE 1:
Per the Control Room log dated April 9, 1987, plant temperatures
j
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.
>
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PACKAGE NUMBER:
235
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INFORMATION ONLY
EQUIPMENT QUALIFICATION DATA PACKAGE
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2.
Accident Environment.
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Parameter
Reference
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a.
Limiting Accident.
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HELB.
[6,11]
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4
b.
Operating Time.
I
8 Hours.
[15]
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c.
Temperature.
,
a-
296*F (Profile I, worst case).
[6,11]
See enclosed Profiles.
_
.
d.
Pressure.
,
l
31.6 psia (Profile R, worst case).
[6,11]
See enclosed Profiles.
e.
Relative Humidity.
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100% R.H.
[11]
l
f.
Chemical Spray.
None.
[11]
g.
Radiation.
6
2.132 x 10
R, gamma (MS equipment).
[5]
6
5.418 x 10
R, gamma (RWCU equipment).
[5]
5
l
5.12 x 10
R, gamma (HPCI, RCIC, RHR equipment).
[5]
h.
Submergence.
None.
[7]
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PACKAGE NUMBER:
235
PAGE
9
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INFORMATION ONLY-.
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EQUIPMENT QUALIFICATION DATA' PACKAGE
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PROFILE B
24' MSLB IN MAIN STEAM TUNNEL
TRANSIENT IN MAIN STEAM TUNNEL
300
-
T = 2. 8 7 "f
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P= 3 9 c5'4
3g
250
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100
150
200
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FIGURE 1
References (6, 11]
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PACKAGE NUMBER:
-235
PAGE
10
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INFORMATION ONLY
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EQUIPMENT QUALIFICATION DATA PACKAGE
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PROFILE T
3".RWCU LINE BREAK IN RWCU PUMP. ROOM
TRANSIENT IN RWCU PUMP ROOM, ELEVATION 931'6"
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250
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T=Alrricsphecie
130 S.
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50
100
150
200
250
Time (Seconds)
FIGURE 2
References [6, 11]
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PACKAGE NUMBER:
235
PAGE
11
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EQUIPMENT QUALIFICATION DATA PACKAGE
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PROFILE D
10" HPCI LINE BREAK IN TORUS AREA
TRANSIENT IN TORUS AREA, ELEVATIONS 859'9" AND 881'9"
250
e
20
-
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2
T=111 F
.
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15.9 psia.
T:l(11 F - 200 *
8
P:
$ 15
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P = Atmospheric.
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50
100
150
200
250
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Time (Seconds)
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FIGURE 3
References [6, 11]
PACKAGE NUMBER:
235
PAGE
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-INFORMATION ONLY
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PROFILE-I
.RHR LINE BREAK IN RHR RX ROOM
-
TRANSIENT IN RHR HX ROOMS, ELEVATION 903'6" AND 931'6"
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100
150
200'
250
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Time (Seconds)
FIGURE 4
References.[6, 11]
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235
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INFORMATION ONLY
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EQUIPMENT QUALIFICATION DATA PACKAGE-
PROFILE F
llPCI LINE BREAK IN HPCI ROOM
TRANSIENT'IN IIPCI ROOM, ELEVATION 859'9"
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300
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T=.W1 F
25
'-
250
-
9.
'-C
f
j
2
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200 {
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u
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P= Atmos}3her1e_
-
150
i
15
-
m
e
<
s
.
10
100
!
-
-
l
-
1
I
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//
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0
50
100
150
200
250
1
Time (Seconds)
!
FIGURE 5
References (6, 11]
.
PACKACE NUMBER:
235
PAGE. -14
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EQUIPMENT-QUALIFICATION DATA PACKAGE
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.
.
PROFILE R
HPCI LINE BREAK IN INJECTION VALVE ROOM
TRANSIENT IN-INJECTION VALVE ROOM, ELEVATION 903'6"
.I
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3
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p.195 F
T=31.6psla-
,
,
230
-
30
-
C
Q
'
-
-T: 201 F,
i
$25
"
200 S
/
/
-
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e
T= 190"F
%
y
0
a
150 &
-
8 20
-
A
m
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P: Atmospheric-
-
15
-
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0
50
100
150
200
250
'500
Time (Seconds)
-
i
FIGURE 6
References [6, 11]
PACKAGE NUMBER:
235
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INFORMATl0N ONLY
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EQUIPMENT QllAI.1FICATION DATA PACKAGE
PROFILE K
RWCU LINE BREAK IN REACTOR BUILDING, ELEVATION 931'6"
TRANSIENT IN THE RWCU HX ROOM, ELEVATION 931'6"
25 -
T = 233".F
-250
o
20 -
-
--200
-
P = 21.9 psia
T=
176*F
--
15
T (*F
-
P = Atmosnherie
--
150
10 -
- 100
{
0
50
ll
100
- /
200
250
Time (seconds)
FIGURE 7
References [6, 11]
PACKAGE NUMBER:
235
PAGE
16
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INFORMATION ONLY
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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 93186"
l7.5-~
- -250
P=
15.3 psia
P = Atmospheric
15,0
_
N - T = 208'F
-- 00
P (pt.ia)
T = 163*F
T (*F)
i
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' V-- 150
12.5 -
--100
//+500
0
50
100
l'50
200
250
Time (seconds)
FIGURE 8
References (6, 11]
I
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PACKAGE NUMBER:
235
PAGE
17
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INFORMATION ONLY
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EQUIPMENT QUALIFICATION DATA PACKAGF
-3.
Normal Functional Requirements.
Provide electrical interface for steam leak detector temperature switches.
1
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_
-
4.
Accident Functional Requirements.
j
Provide electrical interface for temperature switches used to monitor area
temperature for leak detection.
PACKAGE NUMBER:
235
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18
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29
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_ -
_ _ ______
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INFORMATION ONLY
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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 Simulation of T 5 ' 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
i
representative of actual installations [1].
'
Durit.g steam accident testing the internals of the junction box were
,
exposed directly to the steam environment conditions [3].
.
-
2.
Similarity Of Tested Equipment To Installet Equipment.
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
tubiag), 2) electrical loadint during DBA testing was the same as required
j
for temperature switch operation, 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
installation.s.
In addition, the test assembly was exposed directly to
saturated steam conditions during test via unsealed conduit [3].
This
test configuration detsnstrttes the worst possible case at CNS.
3.
Test Sequence Evaluation.
The connector assembly test program was performed in the following
sequence:
Functional Test
Steam Accident Test
Functional Test
This test sequence was performed as specified by the D0R Guidelines,
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 cequence is acceptable.
PACKAGE NUMBER:
235
PAGE
19
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29
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INFORMATl0N ONLY
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EQUIPMENT QUALIFICATION DATA PACKAGE
4.
Servics.
.aitions.
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.
,
.
-
l
l
b.
Temperature Conditions.
1)
Required:
296*F (Profile I).
{6, 11]
2)
Reported:
304*F (Figure 9)
[1]
3)
Discussion:
The peak test temperatures (304*F) envelopes the worst case
plant profile (Profile T) peak temperature.
Therefore, the
temperature requirements are satisfied.
PACKAGE NUMBER:
235
PAGE
20
0F
29
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-
-
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:
l
The peak test pressure (52 psig) envelopes the worst case
required accident peak pressure (16.9 psig) .
Therefore, the
pressure requirements are satisfied.
c-
-
.
d.
Relative Humidity.
1)
Required:
100% R.H.
[11]
2)
Reported:
Saturated steam (100% R.H.).
[1]
3)
Disct'ssion:
The media used during the accident simulation test was saturated
,
steam [1].
Therefore, the relative humidity requirements are
satisfied.
l
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PACKAGE NUMBER:
235 _
PAGE
22
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29
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lNFORMATl0N ONLY
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EQUIPMENT QUALIFICATION DATA PACKAGE
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e.
Chemical Spray.
1)
Required:
Not applicable.
[11}
2)
Reported:
None.
[1]
3)
Discussion:
Chemical spray is not postulated for equipment located outside
containment.
v
-
.
.
f.
Radiation.
1)
Required:
6
5.418 x 10 Rads, gamma.
[5]
2)
Reported:
1.9 x 10 Rads, gamma.
[8]
3)
Discussion:
The worst case radiation requirements are exceeded by a factor
of 3.5 when compared to the radiation damage threshold of the
non-metallic material (PVC).
Therefore, the radiation require-
ments are satisfied.
PACKAGE NUMBER:
235
PAGE _ 23
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29
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INFORMATION ONLY
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FQUIPMEN'.' QUALIFICATION DATA PACKAGE
g.
Aging.
1.
Mechanical Wear Aging,
a) Required:
40 cycles.
[See Discussion]
2) Reported:
Not applicable.
,
l
l
3) Discussion:
'
l
The connection assemblies are used to fr.terface 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
~
l
.
results in 40 connect / disconnect cycles of the connectors over
l
l
a 40 year plant life (40 outages, assuming intervals of 12
months). Per IEZE 650-1979, Appendix E [13],, cycling of
!
connectors for low duty cycles will not create any age-related
failure mechanism. Cycling the connectors 40 times over a 40
l
year plant life is judged to be a low duty cycle; thus,
I
mechanical wear testing is not required. Therefore, the
mechanical wear aging requirements are satisfied.
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
I
(PVC) insulation. Using Arrhenius methodology, PVC has an
I
expected life of 96.5 years at 180*F [8]. Therefore, the
l
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
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29
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EQUIPMENT QUALIFICATION DATA PACKAGE
h.
Synergistic Effects.
,
1) Required:
Not applicable.
[2]
,
2) Reported:
,
Not applicable.
3) Discussion:
Synergistic effects are not required to be
addressed for DOR qualification.
[2]
o
-
.
i.
Submergence.
1) Required:
Not applicable.
[7]
2) Reported:
Not applicable.
3) Discussion:
Submergence is not postulated at CNS.
[7]
PACKAGE NUMBER:
235
PAGE
25
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INFORMATION ONLY
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1
5.
Functional Testing.
i
'
The subject electrical interfaces described in Reference 1 were exposed to
accident environments in excess of CNS requirements.
The test
configuration demonstrated a less than one mil 11 ampere current leakage
throughout DBA testing. Per Reference 4 this is an insignificant level of
3
leakage and does not affect operability. Therefore, the functional
requirements are satisfied.
i
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235
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EQUIPMENT QUALIFICATION DATA PACKAGE
G.
Conclusion.
The preceding qualification evaluation has shown that the equipment described
fn Section D of this report is qualified for its intended use. This evaluation
was perfonned in accordance with the guidelines set forth in Enclosure 4 of
IE Bulletin 79-01B.
'
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235
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27
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(NFORMATION ONLY
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EQUIPMENT QUALIFICATION DATA PACKAGE
]
,
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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 Stition and'were subjected'to.
,
testing. The test samples were. identical to those connectors installed at
i
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.
l
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
,
,
l
representative of installed configurations.
!
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~
.
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.
PACKAGE NUMBER:
235
PAGE
28
0F
29
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_ _ _ _ _ . _ _ . _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ _
,.
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_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
. . . . .
INFORMATION ONLY
-
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EQUIPMENT QUALIFICATION DATA PACKAGE
)
1.
Equipment Qualification Maintenance Requirements:
SOUaCE
MAINTENANCE ITEM
DOCUMENT
NUMBER
COMMENTS
(
1. Change out of temperature
N/A
N/A
S.P. 6.2.1.6.1
switches.
(1) Surveillance
Procedure - Steam
I
-
Line Leak Detection
Temperature Switch
Changeout for
-
,
Calibratio.1
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235
PAGE
29
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