ML17328A235
| ML17328A235 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 12/20/1989 |
| From: | Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Davis A NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| AEP:NRC:0775AQ, AEP:NRC:775AQ, NUDOCS 8912270248 | |
| Download: ML17328A235 (36) | |
Text
ACCELZR'ATED DI BUTION jDEMONSTRA, N
SYSTEM REGULATORY FORMATION DISTRIBUTION S
,EM (RIDS)
ACCESSION NBR:8912270248 DOC.DATE: 89/12/20 NOTARIZED: NO DOCKET FACIL:50-315 Donald C.
Cook Nuclear Power Plant, Unit 1, Indiana a
05000315 50-316 Donald C.
Cook Nuclear Power Plant, Unit. 2, Indiana a
05000316 AUTH.NAME AUTHOR AFFILIATION ALEXZCH,M.P.
Indiana Michigan Power Co. (formerly Indiana 6 Michigan Ele RECIP.NAME
'ECIPIENT AFFILIATION DAVISPA.B.
Document Control Branch (Document Control Desk)
SUBJECT:
Responds to concerns raised during 891113-1204 insp re environmental qualification-terminal boxes 6 splices.
DISTRIBUTION CODE:
AOOID COPIES RECEIVED:LTRl ENCL L SIZE: 8aL TITLE: OR Submittal: General Distribution NOTES:
RECIPIENT ID CODE/NAME PD3-1 LA GIITTERPJ.
INTERNAL: NRR/DET/ECMB 9H NRR/DST 8E2 NRR/DST/SZCB 7E NUDOCS-ABSTRACT OGC/HDS1 RES/DSIR/EZB EXTERNAL: LPDR NSIC
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RECIPIENT ID CODE/NAME PD3-1 PD NRR/DOEA/OTSB11 NRR/DST/SELB 8D NRR/DST/SRXB 8E OC/LFMB ILE 01 NRC PDR COPIES LTTR ENCL 1
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TOTAL NUMBER OF COPIES REQUIRED:
LTTR 21 ENCL 19
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Indiana Michigan Power Company P.O. Box 16631 Cofumbus, OH 43216 AEP:NRC:0775AQ Donald C.
Cook Nuclear Plant Units 1 and 2
Docket Nos.
50-315 and 50-316 License Nos.
DPR-58 and DPR-74 ENVIRONMENTAL QUALIFICATION-TERMINALBOXES AND SPLICES U. S. Nuclear Regulatory Commission Document, Control Desk Washington, D.
C.
20555 Attn; A.
BE Davis December 20, 1989
Dear Mr,
Davis This letter responds to concerns raised by your staff during an inspection of the environmental qualification program at the Donald C.
Cook Nuclear Plant.
During the inspection, which was conducted the weeks of November 13, 1989 and December 4, 1989, the following items were categorized as unresolved issues:
1)
Applicability to terminal block qualification reports to the installed configuration at the Cook Nuclear Plant.
The specific issue was the use of top entry conduits and the need for weep holes in the terminal boxes.
2)
A review of anomaly number 6 in the Wyle Test Report NEQ-45603-1 and an assessment of its affect on the Cook Nuclear Plant MOV control circuits.
3)
Review of the use of Scotch 70 tape on Raychem splices.
4)
Review of the use of Okonite, Okoprene tape on motor termination splices.
These issues are addressed below.
Terminal Box uglification The qualification tests for the Marathon 1600 series terminal blocks (Wyle Test Report, Reference
- 1) and the Penn Union 6000 series terminal blocks (Conax Test Report, Reference
- 2) have been
- reviewed, and compared with the conditions that would exist at the 8912270248 891220 PDR ADOCK 05000315 i J
P PNU
l
'1
, ~
Mr. A. B. Davis AEP:NRC:0775AQ Cook Nuclear Plant following a postulated steam line break outside of containment.
The test conditions for the Marathon 'test are given in Table 1, the test conditions for the Penn Union test are given in Table 2, and the profile for the postulated accident is given in Table 3.
A comparison of the Marathon test, configuration with the Cook Nuclear Plant configuration is given in Table 4.
Figures 1 through 3 provide a temperature history for the test and the postulated accident.
Based on the comparisons in Table 4, it can be seen that where there are differences between the Cook Nuclear Plant configuration and the Wyle test configuration they are counter balanced by the peculiarity of the application.
The Wyle test needed a Nema 4
enclosure to qualify the terminal block for 30 days of chemical spray.
At the same time the weep holes were necessary for the proper drainage of a NEMA 4 enclosure.
The Cook Nuclear Plant configuration uses a non watertight terminal box which was used in the testing of the Penn Union terminal blocks.
The open conduit (top entry) and the weep holes used in the Marathon test configuration guaranteed steam intrusion and condensation of the steam on the terminal blocks.
There is no difference from the Cook Nuclear Plant configuration since for an outside containment application (no chemical spray),
no NEMA 4 enclosure is required and proper drainage without weep holes is assured as proved by the Penn Union terminal block test.
The question has been, asked whether the conduit opening into a cable tray in a HELB area could serve as a channel for water running down through the conduit to the terminal box and shorting the terminal blocks.
The Cook Nuclear Plant design standards specify that "all Engineered Safeguards System and Reactor Protection System troughs require covers with the exception of the troughs installed in the Control Room Cable Vault" (Specification DCC-EE-605-QCN).
PDS-1175 (Figure 4) requires one-inch holes every 2 ft. in the bottom of the cable trays for drainage purposes.
Holes are stamped from inside out to eliminate any rough edges projecting inside the tray, and eliminating the possibility of water pooling in the tray, Further PDS-1183 (Figure 5) specifies conduit the cable tray horizontally at the top of the tray (the cables must be brought up from the tray and into the horizontal conduit).
From these specifications and standards, it can be seen that only steam (a gas) will be able to enter the conduit, but only during the 10 minutes outside containment DBE (Reference 3).
On the
Mr. A.
BE Davis AEP:NRC:0775AQ contrary, during the Wyle test, the steam environment was present for 30 days.
Chemical spray was also present but its effect may have been minimized by the NEMA 4 enclosure.
However, during the 118-hour Conax test, both steam and chemical spray were able to enter the unsealed Cook Nuclear Plant terminal box configuzation.
It seems evident that during the 118 hours0.00137 days <br />0.0328 hours <br />1.951058e-4 weeks <br />4.4899e-5 months <br /> of the Conax test, more water spray and steam entered the terminal boxes and impacted the terminal blocks than is likely to happen following a 10-minute high energy line break (HELB) outside containment at Cook.
Likewise, during the 30-day Wyle test, despite the use of a NEMA 4 enclosure, the weep holes in the enclosure and the open top entry conduit would allow steam and water spray to enter the enclosure.
It is our opinion that the 30-day test sub]ected the terminal blocks to conditions more severe than would occur during a short duration (10-minute) steam line break.
The levels of margin present during these tests as compared with the postulated environments where the terminal blocks need to remain functional plus the foregoing discussion between the tested and installed configuration leads to the conclusion that the Cook Nuclear Plant terminal block installation, with top entry conduit and without terminal box weep holes, will remain functional following an outside containment HELB at Cook Nuclear Plant.
W le Test Re ort - Anomal Number 6
Desczi tion of Anomal "On December 31, 1981 the fuses in the leakage current circuit of both remaining boxes were blown.
The cause of the blown fuses was a voltage spike resulting from an abrupt reapplication of facility power, which had been off for approximately 15 minutes."
Evaluation In reviewing this anomaly for applicability to the Cook Nuclear Plant configuration one should consider the following:
1.
The valve actuator control circuits at Cook Nuclear Plant (Figure 6) (the EQ application for Marathon 1600 series) are not fused.
Mr. A. B. Davis AEP:NRC:0775AQ The control circuit (220 VAC) is fed from a 600 VAC power circuit through a low power control transformer (see attached control circuit schematic, typical).
A momentary disturbance (voltage spike) in the control circuit will not generate enough current to trip the 600 VAC circuit protective device (circuit breaker).
In our experience, for the 600 VAC circuit breaker to trip on a secondary side fault, this needs to be a relatively long lasting, bolted (low resistance) fault that would cause the control transformer to fail. It is for this reason (momentary spikes, faults-, etc.), that AEPSC does not fuse control circuit secondaries and instead elects to sacrifice the control transformer.
Due to Appendix R concerns, a testing program was carried out in 1985 at AEPSC Electrical Engineering Laboratory to determine if a fault that developed in the secondary side of a control transformer would take the MCC out once the control transformer blew up.
To find out what would happen, each size of starter and control transformer was tested by bolting a fault to the secondary side of the control transformer.
The results of the tests were reported in Test Report ¹CL-552 (July 29, 1985),
The required modifications (metal barriers for size 1 FVR starters only) were installed under design change
¹RFC-DC-12-2882.
For the purposes of this analysis the relevant fact is that it took approximately 50 seconds (from 41.5 seconds to 55.8 seconds) for a bolted fault on the secondary side of the transformer (220 VAC) to damage the transformer.
- Clearly, a bolted fault of 50 seconds duration cannot be characterized as a "voltage spike."
These tests, therefore, proved that a voltage transient in the control circuit will not instantaneously trip the power circuit and prevent valve operation.
2.
Anomaly ¹6 happened on December 31, 1981, at least 12 days into the LOCA test.
- However, we are claiming terminal block qualification for survival in a 10-minute HELB outside containment environment only.
For both the above reasons, we consider this anomaly (¹6) to have no impact on the environmental qualification of the Marathon 1600 series terminal blocks for outside containment control circuit applications at Cook Nuclear Plant.
Mr. A. B. Davis AEP:NRC:0775AQ Scotch 70 Ta e
The Cook Nuclear Plant splicing procedure (Specification DCC-EE-176-QCN) contains directions to abraid the cable outer jacket to produce a dull surface for at least three inches from the end of the wire. It also has directions to slide a piece of tubing previously installed on the cable conductor over the splice such that at least two inches extends beyond the edge of the conductor.
It appeared to the inspector that this would leave one inch of wire unprotected.
Also, the inspector questioned our use of Scotch 70 tape as it had not been included in the environmental qualification tests.
The one inch difference provided in the specification is to make sure that the splice is not shrunk over the asbestos braid jacket:
but rather over the smooth insulation material to guarantee a
water tight connection.
At the same time, Scotch ¹70 silicone tape is used to prevent the now loose jacket from unravelling.
The Raychem splice qualification, successfully tested without this added protection, can only be enhanced by the tape addition.
We believe there is not question of material incompatibility between the Raychem heat shrink tubing and the Scotch ¹70 silicone tape.
Also, Raychem "Nuclear Products Compatibility Statement" (Reference
- 3) states that "Raychem knows of no incompatibility of its nuclear compounds and adhesives on typical polymeric cable insulating materials currently sold into the nuclear power industry."
We, therefore, conclude that the Cook Nuclear Plant splicing procedure is sound and our Raychem splices environmentally qualified.
Okonite Oko rene uglification Standard power cable motor terminations at Cook Nuclear Plant were environmentally tested during the spring of 1978 at Westinghouse,
- Ontario, Canada test facilities.
The test reports specifies that motor terminations were constructed in accordance with AEP Electrical Design Standards 1-2-EDS-613-2.
Tested samples were E3 and E4 utilizing splicing compound tape Scotch
¹23, and P3 and P4 utilizing splicing compound tape Bishop W962 (AEP Bill of Materials 1788, item ¹692).
Although the test report makes no mention of the Neoprene
- tape, the following consideration are nevertheless relevant:
0 C~
Mr. A. B. Davis AEP:NRC:0775')
The test program was undertaken specifically for AEP, to test AEP standard connections.
2)
The test report specifically states that motor connections were made in accordance with AEP standard drawing 1-2-EDS-613-2
~
3) 1-2-EDS-613 Revisions 1 and 3, (Figures 7 and 8), clearly indicate that the fourth step in the construction of the motor connection is the application of "3 half-lapped layers of Neoprene tape" (AEP Bill of Material 1788 item ¹695).
4)
A letter written to D. V. Shaller (Cook Nuclear Plant manager at the ti dated May 19, 1978 (Attachment 1) from the AEP electrical engineer responsible for the test clearly states; "The
'E'eries of test samples used Scotch ¹23 tape for B/M item 692 and the 'F'eries of test samples used Bishop W962 for B/M item 692.
Both'amples used Okonite "Okoprene" Neoprene tape for B/M item 695."
We have not been able to locate Revision 2 of the standard,
- however, from the text of the letter and a review of Revisions 1 and 3 it can be ascertained that Revision 2 was the same as Revision 3 except for the following:
a.
In Step 3 of the procedure, Revision 2 simply read:
"Apply half-lapped splicing compound tape (M. E. ¹ b.
In Step 4 of the procedure, Revision 2 simply read:
"Apply 3 half-lapped layers of Neoprene tape (M. E.
¹
) II Thus the instructions in the Revision 2 of the standard, refer to the use of generic materials for the motor connections.
After the Westinghouse-Canada test qualified the Scotch 23, Bishop W962 and Okoprene tapes, the standard was revised to eliminate the generic instruction and direct that specific manufacturers be used for EQ reasons.
The 1-2-EDS-613-3 version is therefore the exact description of what was tested at the Westinghouse Ontario labs.
There may be several reasons why the test report makes no mention of the Neoprene tape.
For one, reports written at that early period were not very good at documenting the details of the test.
In addition, it may have been felt that the "Splicing" compound was what needed qualification.
The Neoprene tape in this view may be considered to play a structural rather than an electrical role in building the motor connection.
4 0
Mr. A. B. Davis AEP:NRC:0775AQ Whatever the reasons may have been for neglecting to mention the inclusion of the Neoprene tape in the test, the records of 1-2-EDS-613 Revisions 1 and 3 plus Mr. T. E. King letter previously quoted leaves no room for doubt that the Okonite-Okoprene Neoprene tape was environmentally tested and qualified together with the Scotch and Bishop tapes.
Conclusion Based on our evaluation of the environmental qualification documentation, we believe that our terminal blocks and splices are qualified for their intended use.
References 1.
Wyle Test Report NEQ-45603-1 2.
Conax Test Report IPS-339 3.
IMPELL Report 01-0120-1524 This document has been preparedfollowing Corporate procedures that incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned.
Sincerely M.
. Al xich Vice President MPA/eh Attachment cc:
D. H. Williams, Jr.
A. A. Blind, Jr.
- Bridgman R.
C. Callen G. Charnoff M. Kopp - Region III NFEM Section Chief NRC Resident Inspector
- Bridgman
Table 1
Marathon Terminal Block Qualification Parameters Tem erature Profile 345 F
325 F
290 F
3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> 50 hours 28 Days Pressure 97.7 psia peak Chemical S ra Duration 30 Days Radiation Ex osure 200 Mrads Tested Confi uration Inside NEMA 4 enclosure top conduit entry conduit opened inside test chamber two 1/4-inch weep holes diagonally Results:
The specimens which were powered with applied voltages of 132 VAC and 264 VAC complied with all requirements.
Table 2
Penn Union Terminal Block Test Parameters Tem erature Profile 340 F
250 F
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 117 hours Chemical 'S ra Duration 118 hours0.00137 days <br />0.0328 hours <br />1.951058e-4 weeks <br />4.4899e-5 months <br /> Pressure 26.7 psia Radiation None Required Tested Confi uration Cook Nuclear Plant installation standards (except one may also find top entry conduit terminal boxes at Cook).
Terminal Boxes:
1 hinged cover 1 bolted cover No Weep Holes Results Specimens powered with applied voltage of 600 volts.
Test items performed satisfactorily under test conditions and passed the requirements of this test.
Table 3
Postulated Accident, Parameters Tem erature Profile 400 F (430 F Spike) 340 F
15 seconds 10 minutes Pressure 15 psia (20 psia spike) 50 seconds Installed Confi uration Hinged Cover Terminal Boxes Bolted Cover Terminal Boxes
'I 4
A
'h
Table 4
Comparison of Marathon Test Configuration and Cook Nuclear Plant Configuration W le Marathon Test Confi uration Cook Nuclear Plant Confi uration 1.
Top entry conduit 1.
Top entry conduit 2,
NEMA 4 enclosure; conduit opening into chamber; two 1/4-inch weep holes.
2.
Non-Watertight enclosure; conduit opening into HELB area; No weep holes.
3.
Tested for inside containment environment including 30 days of chemical spray.
3.
Outside containment application only; No chemical spray; 10,minute steam environment,
1
+
A N
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ATTACHMENT TO AEP:NRC:
0775AQ
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Eh'MERICAH ELE RIC P
K
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s'KRYIC<
CORPORATIOH A
WC~ SV~<K OATFc StJb JKCTi May 19, 1978 C.
Cook Pla Material Cont 1 of Insulating Tapes FROJ4i TO:
T. E. King D. V. Shaller Bridgman Qualification tests of electrical connections made inside the containment on safety related motor term'nal connections have been performed at the Westinghouse-Canada test facility at Hamilton, Onta"'o, Canada and will be report " on test reports C ~PO-326 and C i D-343.
The tested sar:.ples
=-re identified as El, E2, E3, E4, F', F2, F3 and F4 and consis" of a connect'on
-. de in accordance w'th drawing 1-2-EDS-613-:,
"600 V Motor Terr,'nations".
The "=" series of test samples sed Scotch
=:23 tape
=or 3/M Item 692 and the. "F" series o
=est samples used Bishop N962 for 3/M Item 692. Both samples used Okonite "Okoprene" neoprene tape for B/M Item 695.
Both the Bis.-.op W962 and Scotch 023 tapes were used on 600 volt motor connections in the Unit 1 and 2 reactor containments.
We must assure ourselves that any remake of. the..motor connections of safety related motors inside the containment use only materials which have been qualified by t".e above test.
To accomplish the above objectives, may 1 sugges=
the =ollowing:
1.
The stock material cards for the suh;ect tates use gpss the item numbers for Bill o Rater'al l788Por identification.
2.
The reference to the system M and
="number be deleted from the stock cards since his num"er includes tapes which have not been qualified for nuclear containments.
3.
Identify Scotch 523 and Bishop W962 as the only acceptab'e replacement tape for Item 692.
4.
Identify Okon'e Okoprene neoprene tape as the only acceptable replacement tape for Item 695.
5.
Obtain suitable quantities of the acceptable tapes for stores requi ements.
6.
Return all non conforming material to I and M central s "crea =or re'sue and use outside
- 0. C. Cook Plant.
IHT RA SY STEii
Oy,'
May 18, 1978 By copy of this letter I am requesting the Electrical Design Section to revise 1-2-EDS-613 to delete the references to the M and E Number.or B/M Items 692 and 695 and insert a
note identifying Scotch
"'23 or Bishop 8962 tape for Item 692 and Okonite Okporene tape for iten 695.
In addition, a similar revision is requested for B/M Items 592 and 695 in 8/M 1788/(.
,,( g/ff Approved TEK/jal CC R.
S.
R.
R.J.
C.
S.J.
R.
\\
N.
c ere Jr.
A.
B r H. H~ itz N. Juj sen F. Kro ger D. Gore - ~B idgman Crow - Srxagman J. Trippy Bridgman F. Steitzel Bridgwan L. Dudd'ng Bridgman T. E. King
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