ML20210B966

Forwards Util Significant Deficiency Repts Received Since Case Providing Repts to Board

ML20210B966
Person / Time
Site:	Comanche Peak
Issue date:	04/30/1987
From:	Ellis J Citizens Association for Sound Energy
To:	Bloch P, Jordan W, Mccollom K Atomic Safety and Licensing Board Panel
References
CON-#287-3298 OL, NUDOCS 8705060057
Download: ML20210B966 (37)

Text

1 329f CIiN0006 04/30/87 00tHEiU UM

• N/A CASE letter to Board attaching Potential 10 CFR 50.55(e)

W m -4 P33 Items (SDAR s)

N/A N/A 0FFL:..-

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00CKLfinis ' WICF.

BRANCW C A S E==

2.14/946 okk6 (CITIZENS ASSN. FOR SOUND ENERGY)

April 30, 1987 Administrative Judge Peter B. Bloch Dr. Kenneth A. McCollom U. S. fiuclear Regulatory Commission 1107 West Knapo Street Atomic Saf ety & Licensing Board Stillwater, Oklahoma 74075 Washington, D.C.

20555 Dr. Walter 11. Jordan 881 W. Outer Drive Oak Ridge, Tennessee 37830

Subject:

In the Matter of Texas Utilities Electric Company, el _a_1,.

1 Application for an Operating License Comanche Peak Steam Electric Station Units 1 and 2 Docket Nos. 50-445 and 50-446 -O d Potential 10 CFR 50.55(e) ltems To assist the Board in its desire to be kept up-to-date on matters of potential significance, CASE is attaching copies of the potential 50.55(c) items (SDAR's, or Significant Deficiency Analysis Reports) which we have received since we provided the Board with such items on March 20, 1987.

It is our intention to periodically continue to provide these SDAR's unless the Board indicates otherwise (unless we have to put exhibit numbers on each).

Respectfully submitted, CASE (Citize ns Association for Sound Energy)

M rs.) Juanita Ellis, Prestient cc Service List. with Attachment.

0705060057 070430

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DH ADOCK 0500 5

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Log # TXX-6360 File # 10110

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P7 903.11 9

g Ref. # 10CFR50.55(e)

TilELECTRIC l

March 27, 1987 i,r.u,.ee a ne, arm U. S. Nuclear Regulatory Commission ATTN:

Document Control Desk Washington, DC 20555 I

I

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKETS NOS. 50-445 AND 50-446 l

IMPACT OF HELB TEMPERATURES ON QUALIFIED EQUIPMENT OUTSIDE CONTAINMENT SDAR:

CP-84-12 (INTERIM REPORT)

Gentlemen:

On June 4,1984, we verbally notified your Mr. D. Hunnicutt of a deficiency l

i involving the environmental qualification of equipment outside containment for i

high energy line breaks (HELB). This is an interim report of a potentially i

reportable item under provisions of 10CFR50.55(e). Our latest interim report, logged TXX-6179, was submitted on December 18, 1986.

The evaluation of cable temperatures in the area of concern is continuing. A preliminary analysis has indicated that the cable sheath *emperatures in the main steam penetration area exceed the temperature to which tb cables were qualified.

Currently, engineering has identified all affected essential cables in the area of concern. An analysis of the elevated temperature effects on those cables, wnich includes consideration of raceway size and the insulating effect of any fire barrier material, is in progress. The results of this analysis, currently scheduled for completion by April 30, 1987, are required to determine the impact of this issue upon the safety of plant operations.

We will submit our next report on this issue no later than May 28, 1987.

1 Very truly yours, MOC W. G. Counsil l

BSD/amb c - Mr. E. H. Johnson, Region IV Hr. D. L. Kelley, RI - Region IV Mr. H. S. Phillips, RI - Region IV mis.,,,,, o ~ si,, i n si n.u, im. moi l

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E Log # TXX-6420 P9 File # 10110

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c 903.9 r

C Ref: 10CFR50.55(e) nlELECTRIC April 28, 1987 Lmurow ine PresuArne U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

SUBJECT:

COMANCHEPEAKSTEAMELECTRICSTATION(CPSES)

DOCKET NO. 50-445 THERMOLAG ON CONDUIT SUPPORT SDAR: CP-85 42 (INTERIM REPORT)

Gentlemen:

On October 26, 1986, we notified you (TUGC0 Letter TXX-6049) that the deficiency involving the possible adverse effect of the substitution of rectangular and oversized preformed sections of thermolag on conduit installations is reportable under the provision of 10CFR50.55(e). Our most recent interim report was logged TXX-6153, dated December 12, 1987.

We are continuing our evaluation and enticipate submitting our next report by July 31, 1987.

Very tr ly yours, W. G. Counsil By:

Al$1/

G. S. Keeley O

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Manager, Nuclear uc sing DAR/mlh c - Mr. E. H. Johnson, Region IV Mr. D. L. Kelley, RI - Region IV Mr. H. S. Phillips, RI - Region IV

= sorin oine sireei i..n ni 04is.i<se 7520s

M Log # TXX-6408

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File # 10110 L

4 903.8 E

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Ref: 10CFR50.55(e)

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RIELECTRIC April 27, 1987 Wmsene G. Comunit fww.e %ce erramar U. S. Nucleai' Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 SEISMIC CATEGORY II PLATFORMS SDAR:

CP-85-53 (INTERIM REPORT)

Gentlemen:

On December 20, 1985, we verbally notified your Mr. R. Hall of a deficiency involving Seismic Category 11 platforms. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e).

Our last interim report, logged TXX-6246, was submitted January 30, 1987. On April 22, 1987, we received an extension for submitting this report from Mr. I. Barnes to May 1, 1987.

Subsequent to our most recent report, several discussions involving engineering, construction and quality personnel have occurred in order to combine the corrective action for this issue and other related issues into one comprehensive plan. Currently, we anticipate finalizing this plan later this month.

Our next report will be submitted to you on or before June 19, 1987.

Very truly yours,

% ll W. G. Counsil By:

G. S. Keeley h

/-

Manager, Nuclear Licegling JCH/mlh c - Mr. E. H. Johnson, Region IV Mr. D. L. Kelley, RI - Region IV Mr. H. S. Phillips, R1 - Region IV

1. O North Ohve Street LB BI Dahas. Tem 7201

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E Log # TXX-6348 File # 10110 C

909.2 C

Ref # 10CFR50.55(e)

TilELECTRIC

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March 26, 1987 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 SERVICE WATER SYSTEM LEAKAGE SDAR:

CP-86-07 (INTERIM REPORT)

Gentlemen:

s On April 11, 1986, we notified you by our letter logged TXX-4762 of a deficiency involving weld failure and coating degradation in the Service Water System which we deemed reportable under the provisions of 10CFR50.55(e).. This is an interim report submitted to status corrective actions implemented on Unit I to date.

Our latest interim report, logged TXX-6351 was submitted on January 30, 1987.

Pipe coating inspections have been completed on the accessible piping in the Train "A" Service Water System with coating repairs implemented on the identified problem areas. Weld repairs have been implemented where previously identified.

The completion of design modification ECN-426, alleviates the erosion / corrosion effects associated with cavitation downstream of the 1-SW-023 valve for Train "A".

A fabricated pipe spool of ASTM 316 Stainless Steel has been installed downstream of the valve.

Insulating gaskets and sleeves provide electrical isolation between disimilar materials.

A Train "B" field weld in the stainless steel line 2-SW-1-302-150 3 (Ref. TXX-4762) has been radiographed a_nd an ultrasonic test performed on the surrounding area. As a result of the above test and related deficiency a complete weld analysis will be performed when Train "B" is out of service.

Presently Train "B" is scheduled to be out of service at the end of March 1987.

Further an investigation will be conducted to determine whether this problem is limited to the identified areas.

• o %,nn ome weet ino n o m. kom n w

TXX-6348 March 26, 1987 Page 2 of 2 A Service Water System inspection program similar to the above will be scheduled for 11 nit 2 after completion of the Unit I corrective actions.

SWEC Engineering (Boston) is performing a corrosion study to provide recommendations to alleviate corrosion problems in the service water system.

This report is scheduled to be issued by June 15, 1987.

We anticipate submitting our next report no later than July 15, 1987.

Very truly yours, b' s std W. G. Counsil By:

G. S. Keeley ed-Manager,NuclearL) censing DAR:ef c - Mr. E. H. Johnson, Region IV Mr. D. L. Kelley, RI - Region IV Mr. H. S. Phillips, RI - Region IV 4

1 E

Log # TXX-6357 P9 File # 10110 Ref #

FR50.55(e) nlELECTRIC E.UIiI,Y,,,,,,,

March 27, 1987 U. S. Nuclear Regulatory Commission Attn:

Document Control Desk Washington, D.C.

20555

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 ELECTRICAL PENETRATION ASSEMBLIES SDAR: CP-86-10 (INTERIM REPORT)

Gentlemen:

On April 24, 1986, we notified you by our letter logged TXX-4774 of a deficiency involving the electrical penetration assemblies (EPA's) supplied by Bunker Ramo which we deemed reportable under the provisions of 10CFR50.55(e).

This is a follow-up interim report submitted to status corrective action implemented to date. Our last interim report, logged TXX-5044, was submitted September 26, 1986.

As noted in our previous report, the EPA modules supplied by Bunker Ramo will be replaced by modules supplied by Conax. Rework in Unit I has begun and is currently scheduled for completion by May 25, 1987.

Rework in Unit 2 has also begun and is currently scheduled for completion by November 30, 1987.

We expect to submit our next report by July 10, 1987.

Very truly yours,

( 2 66 W. G. Counsil WJH/dl c - Mr. E. H. Johnson Region IV Mr. D. L. Kelley, RI - Region IV Mr. H. S. Phillips, RI - Region IV w sorin oine sirevi i si ni n.ii... reu,73:oi

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log # TXX-6362

"" 9 File #10110 J::

903.7 Ref# 10CFR50.55(e) itIELECTRIC March 27, 1987

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imsans he tremirm U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.

20555

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 COMMODITY INSTALLATIONS AT SECONDARY WALL DESIGN GAPS SDAR: CP-86-12 (INTERIM REPORT)

Gentlemen:

On February 27, 1986, we verbally notified your Mr. T. Westerman of a deficiency involving attachments at, or in close proximity to, design gaps between secondary walls and adjacent walls / floors. This is an interim report of a potentially reportable item under the provision of 10CFR50.55(e). Our,

last interim report was logged TXX-6234, dated January 21, 1986.

The methodology for evaluation of commodities attached to, or in close proximity to, adjacent structures or walls has been developed. Specifically, wall displacements are to be determined during a seismic event and compared to allowable commodity movements for acceptability.

Currently, a Design Base displaceme(DBD CS-19) is being developed to define these maximum wall Document nts.

Evaluation of the commodities bridging gaps between secondary walls and adjacent structures is scheduled to be completed by the end of May,1987 for Unit I and common areas. Unit 2 will be scheduled after the completion of Unit 1.

A Commodity Clearance Program is being developed for commodities installed in close proximity, but not attached to, secondary walls. The program will establish a matrix of displacements for all commodities and associated structural elements including secondary walls. Maximum displacements will be based on the above DBD CS-19.

The maximum movement matrix will be utilized through a multi-discipline walkdown for as-built clearance acceptability. A definitive completion schedule will be submitted with our next report.

During evaluation of the issue, we have additionally discovered that secondary wall designs did not consider commodity support loadings.

Therefore, our evaluation effort has been expanded to include the methodology for determining the structural adequacy of these walls.

40 North mne Nrret iHH 1) Alm. fese 75201

5 TXXo6362 March 27, 1987 Page 2 Following a full analysis of these issues, an evaluation will be made regarding the effects on the safety of plant operations had these conditions gone uncorrected.

We will submit our next report by June 3, 1987.

Very truly yours,

//

$1Hidt W. G. Counsil JCH/ef 1

c - Mr. E. H. Johnson, Region IV l

Mr. D. L. Kelley, RI - Region IV Mr. H. S. Ph,1111ps, RI - Region IV l

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E Log # TXX-6379 P9 File #10110 1

903.11

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C Ref# 10CFR50.55(e)

MIELECTRIC April 3, 1987 4.,,,,,, s., er,,,s,,,,

U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.

20555

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50 445 AND 50 446 JET IMPINGEMENT LOAD REVIEW SDAR:

CP-86-13 (INTERIM REPORT)

Gentlemen:

On March 5,1986, we verbally notified your Mr. T. F. Westerman of a deficiency involving a computer entry error which could invalidate portions of the jet impingement load review for high energy piping. This is an interim report of a potentially reportable item under the provision of 10CFR50.55(e).

Our last interim report, logged TXX-6231, was submitted on January 21, 1987.

The schedule for the completion of our review and the issuance of a final Engineering Evaluation Report is May 22, 1987. Our next report will be submitted no later than June.24, 1987.

Very truly yours, j,' Y j 'j9;g, W. G. Counsil JCH/mlh c - Mr. E. H. Johnson, Region IV Mr. D. L. Kelley, RI - Region IV Mr. H. S. Phillips, RI - Region lv a sinn ons, w oi i is u oe... hu, nmi

.. -. o Log # TXX-6332

. File # 10110 910.3 Ref # 10CFR50.55(e)

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March 20, 1987 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.

20555 SUSJECT: COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50 446 INSTRUMENTATION INSTALLATIONS l

SDAR: CP 86-19 (INTERIM REPORT)

Gentlemen:

I i

i On March 21, 1986, we notified you of a reportable item involving the installation of steam service pressure transmitters (see TXX-4824). This is a follow-up interim report to status the corrective actions for a reportable item under the provisions of 10CFR50.55(e). Our last interim report was logged TXX-6235 dated January 21, 1987.

l The scope of this item has been expanded to include corrective action implementation for 50AR$: CP-86-16, " Fire Effects on Instrumentation Tubing,"

i CP 86 50, "Unistrut Spring Nuts on Instrument Supports," CP 86 70, " Elevated Temperature Effects on Instrument Supports and Tubing," and CP 86 77,

" Instrument Tubing Minimum Wall Thickness", all of which were previously reported under the provisions of 10CFR50.55(e).

4

+

We have completed a comprehensive evaluation of instrument installations with i

proposals to relocate them as necessary. The design engineering package is in an internal review cycle.

Engineering is in the process of evaluating correspondence, design documentation and technical chemistry reports covering zine contamination of j

and fire effects on stainless steel tubing. The scope of corrective action will be forthcoming after completion of this study.

We are implementing a program to assure proper alignment and torquing of j

unistrut nuts.

Installation specifications and design drawings are being revised and retraining of affected personnel will be scheduled.

I We are in the process of revising instrument tubing layout design criteria to

{

include the provision that makes the layout compatible with hi temperatures caused by a postulated Loss of Coolant Accident (gh environmental LOCA) event.

This criteria is. based on ASME Code Case N 47 which specifies the strain limits for a "one time" event.

l i

4Hil North Olne httett i H Ml llallas. Ittas ?$.NI l

I i

. s TXX-6332 March 20, 1987 Page 2 of 2 We are currently evaluating the instrumentation tubing minimum allowable wall thickness criteria previously established. After completion of the evaluation, a walkdown and reinspection of tubing is planned.

Procedures and checklists are being established to implement the walkdown.

We are currently evaluating instrument support types for load capacity and the ability to accommodate a High Energy Line Break (HELB) load.

All the above instrumentation evaluations are scheduled to be completed on or before June 30, 1987. Our next report will be submitted on or before July 31, 1987.

Very truly yours,

[

t W. G. Counsil By:

LJ J

'G. 5. Keeley eV 7-Manager,NuclearLice/ sing GLB/dl c - Mr. E. H. Johnson - Region IV Mr. D. L. Kelley, R!

Region IV Mr. H. S. Phillips, RI - Region IV

Log # TXX-6335

.9 File # 10110 C

909.5

-r Ref # 10CFR50.55(e) 1UELECTRIC I,['[,MT,a,,,,

March 23, 1987 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.

20555

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 DIESEL GENERATOR LUBE OIL SUMP TANK FOOT VALVES SDAR: CP-86-31 (INTERIM REPORT)

Gentlemen:

On August 22, 1986, we notified you by our letter,' logged TXX-4975, of a deficiency involving the possible failure of the rubber facing on foot valves mounted in the diesel generator lube oil sump tank, which we deemed reportable under the provisions of 10CFR50.55(e). This is an interim report submitted to status corrective action implemented to date.

Installation of the Unit One replacement rubber facings is complete. Unit Two replacement rubber facings will be installed upon completion of the lube oil flush of the diesel generator system. The Unit Two rubber facing installation is currently scheduled for completion by April 15, 1987.

We will submit our next report on this issue no later than July 13, 1987.

Very truly yours, Wf?!

W. G. Counsil RWH/dl c - Mr. E. H. Johnson - Region IV Mr. D. L. Kelley, RI - Region IV Mr. H. S. Phillips, RI - Region IV mo s.nn oi.,e succi iau noarm, mn

M Log # TXX-6404 F%

File # 10010 903.I1 Ref: 10CFR50.55(e) 1UELECTRIC April 24, 1987 Wilsam G. Counset Emun.e Vwe hesunent U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446

_ E RU WALL EMBEDDED CONDUIT SLEEVES SDAR:

CP-86-32 (INTERIM REPORT)

Gentlemen:

On April 21, 1986, we verbally notified your Mr. T. F. Westerman of a deficiency involving thru wall embedded conduit sleeves which have not been identified tiy number and may be overfilled. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). Our latest interim report, logged TXX-6105, was submitted November 21, 1986.

Collection of the Unit I as-built data, needed to complete the technical evaluation of this issue, is approximately 50 percent complete. To date, 27 nonconformance reports have been issued to document deficiencies relating to embedded conduit sleeves. These deficiencies were identified during collection of

,the as-built data.

The collection of Unit 1 as-built data is currently scheduled for completion by May 22, 1987.

The technical evaluation of this issue upon the safety of plant operations is currently scheduled for completion by September 25, 1987. Upon completion of the evaluation, as-built data for Unit 2 will be obtained.

The schedules for Unit 2 will be provided in our next report.

We will submit our next report on this issue no later than October 30, 1987.

Very truly yours,

~

hb.'h hu r W. G. Counsil By:

N G

S. Keeley

/

Manager, Nuclear Licenying RSB/mlh

'I c - Mr. E. H. Johnson, Region IV Mr. D. L. Kelley, RI - Region IV Mr. H. S. Phillips, RI - Region IV SU Mrsh Ohve Street LB 81 Danas. Teens 73201

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

Log # TXX-6405 F

File # 10110

=

903.9

.=

=

Ref # 10CFR50.55(e) 1EIELECTRIC April 74, 1987 Wmism G. comanit twas,e va rw,e,a U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.

20555

SUBJECT:

COM/tNCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 ANCHOR BOLTS SUPPLIED BY HILTI SDAR: CP-86-51 (INTERIM REPORT)

Gentlemen:

On July 17, 1986, we verbally notified your Mr. I. Barnes of a deficiency involving a condition cited at another nuclear facility in which anchor bolts supplied by Hilti do not meet average ultimate tensile loads in certain sizes as published by the supplier. Our latest interim report, logged TXX-6343 was submitted on March 20, 1987.

Evaluation of the problem by the vendor (Hilti) resulted in the concern being limited to 1/2 inch diameter Hilti Kwik Bolts with design embedments of 3-1/2 inches and larger. This evaluation resulted in the issuance of NRC Information Notice 86-94, "Hilti Concrete Expansion Anchor Bolts," reporting a reduction in ultimate tensile capacity values for the 1/2 inch diameter Hilti Kwik Bolts.

Our evaluation of this concern is continuing. We will to submit a follow-up report by July 8, 1987.

Very truly yours, h.

W. G. Counsil By:

G. S. Keeley

/

~

Manager,NuclearLic$1ng c - Mr. E. H. Johnson - Region IV Mr. D. L. Kelley, RI - Region IV Mr. H. S. P;iillips, RI - Region IV 400 North Olive Street LB SI Dallas. Texas 73201

9 Log # TXX-6358

==

File # 10110 9

903.9- f}} Ref. # 10CFR50.55(e) a 1UELECTRIC w,,,,,,.<,,, March 27, 1987 I sn urne t ur bruarne U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES) DOCKETS NOS. 50-445 AND 50-446 LARGE BORE PIPING AND SUPPORTS SDAR: CP-86-36 (INTERIM REPORT) Gentlemen: On June 9,1986, we verbally notified you of a reportable item involving the scope of plant modifications resulting from the project's pipe support reverification program (see TXX-4844). This is a follow-up interim report on a reportable item under provisions of 10CFR50.55(e). Our latest interim report logged TXX-6296 was submitted on February 20, 1987. The continuing engineering evaluation has not identified any additional instances which are considered reportable pursuant to 10CFR50.55(e). The attached list shows the support modifications issued to date. The evaluation is continuing and we anticipate submitting our next report by June 12, 1987. Very truly yours, ) /f/!ht?hn ' W. G. Counsil BSD/amb Attachment c - Mr. E. H. Johnson, Region IV Mr. D. L. Kelley, RI - Region IV Mr. H. S. Phillips, RI - Region IV 410 %rth Ome Mrret i H hl D.6.n. Tem ~$201 J

TXX-6358 March 27, 1987 Attachment ,Page 1 of I ~ ATTACHMENT LARGE BORE PIPE SUPPORT MODIFICATIONS Number of Mn11 Cateaory Modifications

• 1 Prudent 849 Recent Industry Practice 1337 Adjustment 889 Cumulative Effects 1366 2

Prudent 1012 Recent Industry Practice 360 Adjustment 345 Cumulative Effects 560 Changes in these figures from the last report represent not only identification of further modifications but a recategorization of certain supports. 8 / e 4 J

Log # TXX-6343 _== File # 10110 P9 903.9 1 C Ref # ICCFR50.55(e) = = TUELECTRIC March 20, 1987 w.n,. c.c. w r. .v.,,,e e., nua.,, U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES) DOCKET NOS. 50-445 AND 50-446 ANCHOR BOLTS SUPPLIED BY HILTI SDAR: CP-86-51 (INTERIM REPORT) Gentlemen: On July 17, 1986, we verbally notified your Mr. I. Barnes of a deficiency involving a condition cited at another nuclear facility in which anchor bolts. supplied by Hilti do not meet average ultimate tensile loads in certain sizes as published by the supplier. Our latest interim report, logged.TXX-6238, was submitted on Jcnuary 27, 1987. Evaluation of the problem by the vendor (Hilti) resulted in the concern being limited to 1/2 inch diameter Hilti Kwik Bolts with design emoeoments of 3-1/2 inches and larger. This evaluation resulted in the issuance of NRC Information Notice 86-94, "Hilti Concrete Expansion Anchor Bolts " reporting a reduction in ultimate tensile capacity values for the 1/2 inch diameter Hilti Kwik Bolts. Our evaluation of this concern is continuing; we expect to submit a follow-up report by April 24, 1987. Very truly yours, bh.. GU W. G. Counsil '/h' l, A M{* /WIM,! By: G. S. Keeley, c-Manager, Nuclear Licensing GLB/dl c - Mr. E. H. Johnson - Region IV tir. D. L. Kelley, RI - Region IV Mr. H. S. Phillips, RI - Region IV jew) %rth Olne Street l..it al Da;Ln...us 75201 _)

e# 1 C 903.8 C Ref # 10CFR50.55(e) TUELECTRIC %dham G. (oumel e m om, u, e,,us,,,, March 23, 1987 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES) DOCKET NOS. 50-445 AND 50-446 POLAR CRANE SUPPORT STRUCTURE SDAR: CP-86-62 (INTERIM REPORT) Gentlemen: On October 3,1986, we notified you by our letter logged TXX-6011 of a deficiency involving a misinterpretation of the polar crane load cases which we deemed reportable under the provisions of 10CFR50.55(e). We have submitted an interim report logged TXX-6239, dated January 26, 1987. This is an interim report submitted to status corrective action implemented to date. In previous reports, we concluded that reduced loading exists for the polar crane support structure. An analysis of the acceptability of the crane rail structure for these reduced loads is continuing. We will submit our next report no later than June 8, 1987. Very truly yours, [ 547240 l W. G. Counsil i RWH/dl l l c - Mr. E. H. Johnson - Region IV Mr. D. L. Kelley, RI - Region IV Mr. H. S. Phillips, RI - Region IV 100 North Olne Street t..B MI Dal.a. Teus 75201

M Log # TXX-6391 MM File # 10110 j 903.9 _= r Ref: # 10CFR50.55(e) nlELECTRIC April 16, 1987 mmam c. co.asir f uerutne bce Premkar U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES) DOCKET NOS. 50-445 AND 50-446 PIPE SUPPORT INSTALLATIONS SDAR: CP-85-63 (INTERIM REPORT) Gentlemen: By letter logged TXX-6027, dated October 16, 1986, we notified you of a reportable item involving pipe support construction deficiencies. This is a follow-up interim report on a reportable item under provisions of 10CFR50.55(e). Our last interim report was logged TXX-6260, dated February 2, 1987. Currently, physical inspections of large and small bore pipe' supports are in process as part of the Hardware Validation Program.' This program will assure that pipe supports meet the established design, fabrication, installation and regulatory criteria. Rework, as required for acceptance, will be documented for each support. Approximately 19,261 supports are involved in the unit 1 and common area program. The estimated completion date, as previously reported to you, is September 1, 1987. Unit 2 inspections will be performed as part of the normal final inspections required for support certification. Our next report will be submitted on or before July 20, 1987. Very truly yours, bb.Counsilh~wn W. G fk!' f

1. ILdh/

By: L G. S. Keeley / u __ Manager,NuclearLipnsing c - Mr. E. H. Johnson - Region IV Mr. D. L. Kelley, RI - Region IV Mr. H. S. Phillips, RI - Region IV l 40.%crth Ohve.kreet LB $l Dallas. Teus 7201 { ]

= Log # TXX-6336 r. File # 10110 C 909.5 r C Ref # 10CFR50.55(e) 1UELECTRIC Wlham G. ( ounut Luenount inr Premient I l U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES) DOCKET NOS. 50-445 AND 50-446 C0ATINGS FOR UNIT 2 DIESEL FUEL OIL TANKS SDAR: CP-86-64 (INTERIM REPORT) Gentlemen: On September 4,1986, we verbally notified your Mr. I. Barnes of a deficiency involving the protective coatings for the Unit 2 diesel fuel storage tanks. We have submitted interim reports, logged TXX-6013 and TXX-6263 dated October 3, 1986 and February 6, 1987, respectively. We have completed our assessment of Nuclear Regulatory Commission Information Notice 87-04 impact on this issue and find it does not affect oer evaluation. However, our evaluation of this issue with regard to the safety of plant operations is continuing. We will submit our next report on this issue no later than May 22, 1987. Very truly yours, f T W. G. Counsil RWH/dl c - Mr. E. H. Johnson - Region IV Mr. D. L. Kelley, RI - Region IV Mr. H. S. Phillips, RI - Region IV 410 North Olne Street I. H 51 Daile. Tesa 75201

'N Log # TXX-6327 -== File # 10110 P """ 903.9 -] Ref. # 10CFR50.55(e) 1UELECTRIC %,,, c, %, March 19, 1987 f.m uttw h e Hrudem U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES) DOCKET NO. 50-445 PRE-0PERATIONAL VIBRATIONAL TEST CRITERIA SDAR: CP-86-67 (INTERIM REPORT) Gentlemen: On September 26, 1986, we verbally notified your Mr. Ian Barnes of a potential deficiency regarding the design calculations and tests used to qualify the Pre-Operational Piping Vibration Program. Our last report was logged TXX-6290, dated February 19, 1987. We have concluded that the deficiency identified above is reportable under the provisions of 10CFR50.55(e).

l DESCRIPTION OF PROBLEM A review of the CPSES criteria document " Pre-Operational Vibration Test Program",

Issue 1, June 1980, indicated that the mathematical formulas used to determine stress endurance limits, allowable deflections, and flexibility characteristics of certain piping systems may not have been accurate. All vibration calculations and test results were evaluated to determine the validity of the original calculations i in accordance with established CPSES procedures. The evaluation has yielded the following results:

1. Two test data points (from a total of 21 system tests) were found to exceed the allowable deflection limits.

2. The measured direction of deflection movement was not clearly identified in all instances.

3. The test deflections were measured in only one direction in some cases.

Deficiency I was the result of an inadequate design review to verify the accuracy of mathematical formulas used to determine allowable deflection limits. I m %rth Ome Street i H *I Dahat leus '520 t l l

~TXX-6327 March 19, 1987 Page 2 of 2 A*. Deficiencies 2 and 3 were the result of a failure tc adequately incorporate documentation requirements into the vibration test procedures. SAFETY IMPLICATION In order to evaluate the safety significance of item 1 above, a rigorous analysis would have to be conducted to determine the stresses induced in the piping and pipe supports by the excessive deflections. However, as a result of items 2 and 3 above, the extent of any additional test data which exceed allowable deflection limits is indeterminate. This information could only be retrieved by returning the piping systems to their original 1980 configuration and repeating the vibration test. This is neither practical nor useful. We have no reason to believe that a'ny of the undocumented vibration test data exceeded the allowable deflection limits. However, it is conservatively assumed that had this condition remained undetected, the integrity of affected piping systems may not have been assured. CORRECTIVE ACTION As a result of ongoing work and/or modifications to the piping systems as part of the piping and pipe support systems requalification program, it is necessary to repeat the steady state vibration testing. The re-test will resolve all the above Concerns. To prevent recurrence of items 1, 2 and 3, a new vibration test procedure has been issued for Unit 1. The start of testing is scheduled for September 1987. Our next report will be issued no later than October 22, 1987. Very truly yours, At/ 't NC W. G. Counsil )/. ~ /. { By : / ' -, '( G. S. Keeley & Manager,NuclearL\\[ censing BSD/amb c - Mr. E. H. Johnson, Region IV Mr. D. L. Kelley, RI - Region IV Mr. H. S. Phillips, RI - Region IV

e# 1 L 2 909.1 C C Ref #10CFR50.55(e) TUELECTRIC DJSL7,s,.,,, March 27, 1937 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES) DOCKET NOS. 50-445 AND 50-446 SUPPORT OF CLASS IE WIRING SDAR: CP-86-69 (INTERIM REPORT) Gentlemen: On October 2,1986, we verbally notified your Mr. I. Barnes of a deficiency regarding the failure to incorporate specific restraining / support requirements defined by IEEE Standard 420-1973, " Class IE Control Switchboards," into project specifications and procedures. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e) Our most recent interim report was logged TXX-6225, dated January 21, 1987. We requested and received a two week extension until March 27, 1987 in,providing a response to this deficiency during the March 13, 1987, telephone conversation with Mr. I. Barnes. Preliminary evaluations indicate that in the event these conditions had remained uncorrected no condition adverse to the safety of plant operations would exist. Documentation supporting our position is currently in the final stages of review. Our next report will be submitted no later than April 27, 1987. Very truly yours, M'.' daad W. G. Counsil By: A-G. S. Keeley C Manager, Nuclear Liiensing DAR:ef l c - Mr. E. H. Johnson, Region IV Mr. D. L. Kelley, RI - Region IV Mr. H. S. Phillips, RI - Region IV 440 %rth One Street l BM D i e. Ic w '$20!

M Log # TXX-6406 =M File # 10110 L 4 909.1 E Ref # 10CFR50.55 1EIELECTRIC ^E wm

c. counwi faccurne Ver Pre,sdern U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.

20555

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES) DOCKET NOS. 50-445 AND 50-446 SUPPORT OF CLASS 1E WIRING SDAR: CP-86-69 (INTERIM REPORT) Gentlemen: On October 2,1986, we verbally notified your Mr. I. Barnes of a deficiency regarding the failure to incorporate specific restraining / support requirements defined by IEEE Standard 420-1973, " Class 1E Control Switchboards," into project specifications and procedures. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). Our most recent interim report was logged TXX-6328, dated March 27, 1987. Documentation supporting our position is currently in the final stages of review. We anticipate submitting our next report no later than May 29, 1987. Very truly yours, W. G. unsil i By: v. G. S. Keel ey-- Manager, Nuclear ensing [ DAR/gj I c - Mr. E. H. Johnson - Region IV Mr. D. L. Kelley, RI - Region IV i Mr. H. S. Phillips, RI - Region IV 4 ,wo hortts Ouve Suret LB 81 Dadas, Texas 75:01 i

Log # TXX-6359 -== File # 10110 P9 903.9 =. -] Ref. # 10CFR50.55(e) 1EIELECTRIC w m.- c.c w March 27, 1987 Dreutnw inr />rudent U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES) DOCKETS NOS. 50-445 AND 50-446 l SMALL BORE PIPING AND SUPPORTS SDAR:. CP-86-72 (INTERIM REPORT) Gentlemen: On June 9,1986, we verbally notified you of a reportable item involving the scope of plant modifications resulting from the project's pipe support reverification program (see TXX-4844). This is a follow-up interim report on a reportable item under provisions of 10CFR50.55(e). Our latest interim report logged TXX-6297 was submitted on February 20, 1987. r The continuing engineering evaluation has not identified any additional instances [1 which are considered reportable pursuant to 10CFR50.55(e). The attached list shows the support modifications issued to date. The evaluation is continuing and _4' we anticipate submitting our next report by June 12, 1987. ~ Very truly yours, W. G. Counsil BSD/amb Attachment c - Mr. E. H. Johnson, Region IV Mr. D. L. Kelley, RI - Region IV Mr. H. S. Phillips, RI - Region IV 400 North Olne Street L H. 81 Dallas Tem 75201 1

.TXX-6359 March 27, 1987 Attachment ..Page 1 of 1 ATTACHMENT SMALL BORE PIPE SUPPORT MODIFICATIONS Number of Unit Cateaory Modifications

• 1 Prudent 23 Recent Industry Practice 87 Adjustment 185 Cumulative Effects 136 2

Prudent: . J 2'. ^ Recent Industry Practice 17 Adjustment 46 Cumulative Effects 20 s

• Changes in these figures from the last report represent not only identification of further modifications but a recategorization of certain supports.

S I l l l l l l i

Log # TXX-6315 9, File # 10110

L 903.9 Ref # 10CFR50.55(e) 1UELECTRIC I.IIdN,,a,.,,,

March 20, 1987 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES) DOCKET NOS. 50-445 AND 50-446 ASME SNUBBER ATTACHMENT BRACKETS SDAR: CP-86-73 (INTERIM REPORT) Gentlemen: On October 20, 1986, we verbally notified your Mr. Ian Barnes of a deficiency involving installation of ASME snubber attachment brackets. Our last interim report was logged TXX-6188, dated December 23, 1986. On March 6, 1987, we requested and received a two week extension until March 20, 1987, to provide our next report. We have concluded that this issue is reportable under the provisions of 10CFR50.55(e), and the required information follows: DESCRIPTION OF PROBLEM A drawing review of all ASME snubbers was conducted to verify the adequacy of swing clearances. 1063 snubbers were identified as having attachment brackets with attributes that could potentially result in restricted movement and/or binding of the snubbers. As a result of field examinations, this number was reduced to 165. An evaluation of the 165 supports was conducted in which the predicted pipe movements were compared to the field verified swing angle data. A summary of the evaluation results follows: - 83 supports were determined to have sufficient field verified swing angle 1 to accommodate the predicted pipe movement. - 15 supports were determined to be unnecessary in a previously initiated pipe support requalification effort and are being deleted. - 30 supports are being modified as a result of the pipe support requalification effort (but not as a result of this deficiency). - 16 supports have been identified as having less clearance than required by analysis and are being modified to correct the situation. I 400 North Olne Street i.H MI Dallas lew ?$201 i

.n =' TXX-6315

• March 20, 1987 Page 2 of 3

- 3 supports have no safety related function nor impair the safety related function of other components and are therefore being removed from further evaluation. - 18 supports are under further evaluation. i Several causes for the deficiencies have been identified. 1. Certain sizes of struts and snubbers may use interchangeable rear attachment brackets. These rear attachment brackets were kept mixed in the same bulk storage bin. Although this practice was considered acceptable for rear bracket types XRB-06 and XRB-08, it may have been unacceptable when strut rear attachment brackets of a later edition (SRRB-06 and SRRB-08) were used with the corresponding size snubber. I 2. Theforwardbracketsforsize3(SMF)snubbersthatarefabricategatthe minimum specified "c-c" dimension do not have the full required 5 swing when pinned to a rear bracket. 3. Size 10 snubbers, depending on which revision of rear bracket was used and wgich fabrication tolerances were employed, may not have the full required 5 swing, t SAFETY IMPLICATION The supports deleted or modified by the requalification effort are not being analyzed in their origina' ccnfiguration to determine the safety significance (as this is neither practical cr useful). Rather, it is conservatively assumed that these supports, the supports yet to be analyzed, and the supports being modified as a result of this deficiency, may have had inadequate swing clearances - sufficient to impair their ability to perform their required safety function. i CORRECTIVE ACTION To prevent recurrence of deficiency 1, the bulk storage bins have been purged of all SRRB-06 and SRRB-08 strut rear attachment brackets. Additionally, future shipments of rear attachment brackets of these sizes will consist only of the XRB i type. Corrective actions to prevent racurrence of deficiencies 2 and 3, are still under review and will be provided in our next submittal. As previously noted,16 supports are being modified as a result of this deficiency. The evaluation of the remaining 18 supports is scheduled for completion by May 15, 1987. 4 J

~ TXX-6315 March 20, 1987 Page 3 of 3 We will submit our liext report no later than June 12, 1987. Very truly yours, W. G. Counsil By: D. S. Keeley 3 Manager, Nuclear Lice ng BSD:lw c-Mr. E. H. Johnson, Region IV Mr. D. L. Kelley, RI - Region IV Mr. H. S. Phillips, RI - Region IV i i i I L a

y.;.- e E Log # TXX-6363 P9 File # 10110 C 908.3 Ref # 10CFR50.55(e) 1tELECTRIC EINN7,$a,,, March 30, 1987 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION.(CPSES) DOCKET NOS. 50-445 AND 50-446 OVER-TORQUED WESTINGHOUSE AR RELAYS SDAR: CP-86-79 (INTERIM REPORT) Gentlemen: On November 7,1986, we verbally notified your Mr. T. Westerman of a deficiency involving the possible overtightening of the contact cartridge terminal screws on the Westinghouse AR Relays. This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). We have submitted interim reports, logged TXX-6141 and TXX-6253 dated December 5, 1986, and January 27, 1987, respectively. Conceivably, overtightening of the terminal screws could have deformed the stationary contact assembly, reduced contact overtravel, and resulted in a loss of contact continuity. These terminal screws have a specified torque requirement of 9.5 0.5 inch-pounds. The accuracy of the torque wrench used at CPSES may have allowed an overtorqued or undertorqued condition on the terminal screws. The accuracy of the torque wrench, when set for 9.5 inch-pounds, allowed a range of 9.5 1.5 inch-pounds. Preliminary review results have indicated that no material deformation would occur (at 11.0 inch-pounds) which would cause the relay contact to malfunction. Additionally, it was previously thought that some torque wrenches used for this application had a calibration range which did not encompass the Westinghouse specified. range. Our evaluation has determined that all torque wrenches used had a calibration range which encompassed the Westinghouse specified range (9 to 10 inch-pounds). However, review of contact operability for their qualified life is continuing.

• O North Oine Street I 18 %I D4a.it lesa, '520)

i.. TXX-6363 4' March 30, 1987 Page 2 of 2 We are continuing our evaluation and anticipate submitting our next report by' June 22, 1987. Very truly yours, W. G. Counsil G. S. Keeley Manager,NuclearLicMsing RDD/dl c - Mr. E. H. Johason - Region IV Mr. D. L. Kelley, RI - Region IV Mr. H. S. Phillips, RI - Region IV e.

ei a

==

Log # TXX-6383

---====

File #10110 903.9 Ref: 10CFR50.55(e) TUELECTRIC April 3, 1987 w,n... <.a mma i m utne a u r l'rrmerm U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES) DOCKET NOS. 50-445 AND 50-446 CABLE TRAY HANGER SPLICE WELDS SDAR: CP-86-82 (INTERIM REPORT) Gentlemen: On January 6,1987 we notified you by our letter logged TXX-6201 of a deficiency involving certain welds which are used to splice cable tray hangers (CTHs) channel sections end-to-end to form posts which we deemed reportable under the provisions of 10CFR50.55(e). This is an interim report submitted to status corrective action implemented to date. The CTHs of Unit I have been subjected to an as-built program. The CTHs without thermolag have been visually examined and the locations where this condition has occurred are noted on the as-built drawings. Each condition will be " repaired" or " reworked" in accordance with established project procedures. CTH's with potential hidden splice welds due to installed thermolag are being investigated as follows: A) To determine whether splice welds exist on the post and tier members of the CTH's, nondestructive testing (UT) is being utilized on members which are channels 62" or less in length (for C8 channels or larger, UT can be performed up to 84" or less length). B) Where the potential condition is identified by UT, the thermolag will be removed to provide for visual confirmation. C) Thermolag will also be removed from all supports where UT produces indeterminate results or cannot be utilized (e.g. CTH members over the lengths specified above) to verify the subject condition. w wnn oine street i. n u naius. Tew 75mi

TXX-6383 April 3,1987 Page 2 of 2 4 UT has been performed on over 1173 hangers to date which has identified 14 splice welds with this deficiency. Each condition which is determined to be unacceptable by engineering evaluation will be " repaired" or " reworked" in accordance with established project procedures. Some instances of the subject condition have been identified in Unit 2. The cases identified to date have been corrected as part of the design verification program.. (Problems of inaccessibility due to thermolag installation are not of concern in Unit 2.) Identification of.the subject condition and any necessary corrective action will continue for Unit 2. The cause of this construction deficiency is attributed to a lack of specific direction regarding problems encountered during the " original" fabrication and installation of the cable tray hangers. The following Construction Procedures, which address cable tray and hanger installation for Units 1 and 2, have been revised to correct this condition. -ECP-10, Rev. 9 (Unit 1) Issued January 13, 1987 " Cable Tray Hanger Installation" -ECP-10A, Rev. 4 (Unit 2) Issued September 8, 1986 " Cable Tray Hanger Installation, Unit 2" We will submit our next report no later than July 17, 1987. Very truly yours, b s nt,l W. G. Co ill 1 U Il-LL.cL L / By: G. S. Keeley. / ' Manager, Nuclear Li6ensing I DAR/amb c - Mr. E. H. Johnson, Region IV Mr. D. L. Kelley, RI - Region IV Mr. H. S. Phillips, RI - Region IV )

..-.. c. l l e

r1

Log # TXX-6338

""" 9 File # 10110 J::

908.3 = C Ref. # 10CFR50.55(e) TU=LECTRIC March 20, 1987

f. mums i a e heudent U. S. Nuclear Regulatory Commission ATTN:

Document Control Desk Washington, DC 20555

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES) DOCKET NOS. 50-445 AND 50-446 SEPARATION BARRIER MATERIAL ON POWER CABLES AND POWER RACEWAYS SDAR: CP-86-83 (INTERIM REPORT) Gentlemen: 5 On December 8,1986, we verbally notified your Mr. Ian Barnes of a deficiency involving the use of Separation Barrier Material (SBM) on power cables and power raceways.- This is an interim report of a potentially reportable item under the provisions of 10CFR50.55(e). Our last interim report submitted was logged TXX-6281, dated February 13, 1987. The discrepancy involves the installation of thermal SBM on power cables and/or power raceways without derating of the cables' power carrying capacity (ampacity). We have completed our calculations and have concluded that, due to significant conservatism in cable sizing design, the subject cables and cables in raceways did not exceed their insulation temperature rating during start-up testing. The thermal barri.er material is in the process of being removed from the power cables and power raceways. However, in order to determine safety significance, we are continuing the process of determining if the cable sizing design was sufficiently conservative to allow for the necessary cable ampacity derating with SBM in place. Our evaluation will determine the impact of this issue on the safety of plant operations during its 40 year design life. JJ10 hrth ()lne Street l..tl 5 3 l).!!i n. ,on 75201

TXX-6338 March 20, 1987 Paga 2 of 2 e an We expect to submit our next report by June 5, 1987.

t Very truly yours, Ad M W. G. Counsil i'

.. f sy. G. S. Keeley & Manager, Nuclear Li nsing R 2:~ 7-WJH:1w c - Mr. E. H. Johnson - Region IV Jic Mr. D. L. Kelley, RI - Region IV RE-Mr. H. S. Phillips, RI - Region IV-4 %= g-e 50

H Log # TXX-6397 File 7 10110 h i Ref # 10CFR50.55(e). = = 1UELECTRIC April 15, 1987 wm m c. c-si Enecwne bne Preuarnt U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES) DOCKET NOS. 50-445 AtlD 50-446 PLUG WELDING ON EMBEDDED CHANNELS SDAR: CP-87-04 (INTERIM REPORT) Gentlemen: On March 16, 1987, we verbally notified your Mr. I. Barnes of a deficiency involving base metal damage on the embedded channels for one of the Unit 2, 6.9Kv Switchgear. Specifically, cracks were observed in the plug welds made to repair grout holes in the embedded channels. This is an. interim report of a potentially reportable item under the provisions of 10CFR50.55(e). The Nonconformance Report (CE-87-7-S) initiated to document this issue has been dispositioned " repair" by adding a new mounting detail for the entire switchgear train. The design document (DCA 20986) detailing the grout hole repair will be reviewed for proper weld details. This evaluation and a review of similar electrical installations will be performed to determine the generic implications, if any, of this issue. These results are required to determine the impact of this issue upon the safety of plant operations. We will submit our next report on this issue no later than June 17, 1987. Very truly yours, wtJY$ f( L W. G. Counsil / By: N G. S. Keeley / Manager, Nuclear Licp6 sing DAR/gj c - Mr. E. H. Jonnson - Region IV Mr. D. L. Kelley, RI - Re;: ion IV Mr. H. S. Phillips, RI - Region IV a um oine sweer ta si ca u re w 15:01 L_.}}