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Forwards Promatec 860217 Part 21 Rept Re Defective Matl Used in Fire Stops to Determine Applicability to Plant
	ML20140B194
Person / Time
Site:	South Texas
Issue date:	03/07/1986
From:	Gagliardo J; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:	Goldberg J; HOUSTON LIGHTING & POWER CO.
References
	REF-PT21-86 NUDOCS 8603240008
	Download: ML20140B194 (2)
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MAR-0 71986 .

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. Gentlemen: <, 4 D'

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0 r !This'; forwards a copy of a lettor from Promatec, dated February 17, 1986, .

f for yourtinformation. This -letter was'a' 10 CFR Part 21- report concerning.

defective' material used in; fire stops and. may be applicable to the

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Sincerely,.

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-M J. E. Gagliardo

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J. E. Gagliardo; Chief.

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' Reactor Projects Branch .

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Enclosure:

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Houston Lighting'& Power Company-V , ~ ATTN: . M. Wisenberg,Pianager, ~

Nuclear Licensing

-P.'0.-Box-1700 ,

Houston, Texas- 77001-Brian Berwick,' Esquire '

5 e Asst. Attorney General "

Environmental Protection'Div.

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P. 0? Box.12548, Capitol Station ~

. . Austin ,~ - Texas ' 78711.l, -

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' Citizens Concerned-About: -

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c>< Nuclear Power. Inc. '

.Christic Institute - - .

' s' ;1324 North: Capitol Street' , . 'i--

Washington,!D.C. 20002, + * -

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- IbharlesLBechhoefer, Esquirel A

: Chairman,' Atomic Safety & . Licensing . -

. Board ~

' U.S. ' Nuclear Regulatory Commission ^ , ,

, Washington,-- DC : l20555i " _

i,Dr. James C. Lamb, III' R

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' 313 Woodhaven Road <

l Chapel-Hill, North Carolina 27514-

. Frederick IJ. Sho'n -

$N / Administrative Law ~ Judge -

? . Atomic Safety and Licensing Board

' U.S. Nuclear Regulatory Comission 1 ' Washington, DC. 20555 R$yGoldstein, Esquire . _

Gray, Allison and Becker f%., "

100 Vaughn Building

807. Brazos .

Austin, Texas' 78701 Texas Radiation Control Program Director.

' b'cc distrib, by RIV: '

.RPB DRSP Resident Inspector- R. D. Martin, RA x Section Chief, .RPB/C RSBL

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g: - PROGLESSIVE MATUUALS AND TECHNOLOGES. INC.

Q.100.020 February 17, 1986 $@$bb U.S. Nuclear Regulatory Co nmission 611 Ryan Plaza Drive, Suite 1000 .//

Arlington, Texas 76011 " -

Attention: Mr. Robert Martin Administrator, Region IV

Reference:

10 CFR Part 21 - Notification of Defects Centlemen:

Pursuant to the provisions of 10 CFR Part 21 - Reporting of Defects and Non-compliance, notification is hereby given of the existense of defective con-duit seals at Waterford 3 and other nuclear generating stations as identified herein. Final information leading to this report was obtained on February 13, 1986 at 12:00 p.m. and verbal notification as required by 21.21 (2) was given on February 14, 1986 at 8:36 p.m. to Mr. David Powell, U.S. Nuclear Regulatory Commission, Washington, D.C.

l Information contained in this report is based on fire tests performed on two

(2) existing seal configurations and subsequent preliminary evaluations con-ducted by B&B PROMATEC, Incorporated and Louisiana Power & Light Company.

l Details are as follows:

l (1) PROMATEC conducted a series fire tests on two (2) penetration / conduit

! seal configurations that are presently installed at various nuclear generating stations in accordance with the requirements of ASTM E119, l 814 and IEEE 634. The initial purpose of the tests was to ascertain the effects " pull rope" extending through conduit seals would have on the ability of such seals to perform their intended function. While

! " pull rope" was shown not to be a factor in the ability of the seals l to perform their intended function during initial tests, both conduit seals failed to perform properly causing the seal configuration them-selves to become suspect.

l Additional tests were conducted with the same configurations deleting

" pull ropes" to determine design integrity of the seals. The config-urations and characteristics tested are as chown on attachments 1 Q ll W5$Y'v ]py. []Y l P.O. BOX 4672 e HOUSTON, TEXAS 77210 e (713) 690-5240

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Form No: QC-13

. LETTER OF TRANSMITTAL 03/0i/80

. Rev 1 09/01/80 FEDERAL EXPRESS Rev 2 - 04/01/83 g A"

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dev 3 - 09/25/94 021-052-732 (Ref. p 0006]

DEPARTMENT: QAME TRANSMITTAL NUMBER: 100/928 TO: U.S. Nuclear Reaulatory Commission DATE: 2/18/86 JOB NO: MISC.

611 Ryan Plaza Drive. Suite 1000 RE:

Arlinoton. Tx. 76011 ATTN: Administrator. Recion IV-Robert Mart,in l

_ GENTLEMEN:

WE ARE SENDING YOU: (XX ) ATTACHED ( ) UNDER SEPARATE COVER

( ) DRAWINGS ( ) COPY OF LETTER ( ) SPECIFICATIONS

( ) QUALITY ASSURANCE PROGRAM ( ) QUALITY CONTROL PROCEDURES

( ) PRODUCTION PROCEDURES ( )

( )

COPIES DATE SERIAL NO. DESCRIPTION 2 2/18/86 0.100.020 5 oaoe letter with 3 attin3_ats THESE ARE SUBMITTED: ( ) FOR APPROVAL ( ) AS REQUESTED

( ) FOR REVIEW AND COMMENT (xx ) FOR YOUR USE ( ) RETURNED FOR

( ) CORRECTIO l REMARKS: // 4 . > s /

COPY TO:

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SIGNED: [#>>we/MM[A-

! TITLE: QualityCNrolSecrby [

!!!!!!!!;!!!!!!!!! !!!!!!!!!!:itii!!i-iiili!!!!!!!!!!!!!!lili*i!!!!!!!!!!ii':iii!!!!!!:i!!!!!!!!!li.I.!!!!!!!!!?!!Iiiiiiiiiiiiii!!!'!!ll!!!ll!!I!!!!!!!!

PLEASE NOTE: RETWN YELLOW ACXNOWLEDTENT CCPY TO B&B INS 11ATICN, IT. Include any coments in space provided.

TRANSHITTAL: ( ) COMPLETE ( ) NOT COMPLETE ( ) DISCREPANCIES NOTED BELOW l Returned

! by:

Title:

Date:

1 P.O. BOX 4672, HOUSTON, TEXAS 77210. (713) 690-5240 l White (Original)- Addressee; Yellow - ACKNOWLEDCDDIT Return to sender; Pink - File Copy

To: Administrator, Region IV Q.100.020

/ From: Randal W. Brown Page 2 of 5 and 2, and~as further described below.

1.0 Test Penetration Characteristics One 8" x 8" blockout and one 8" x 20" blockout in a 12" thick concrete slab with two (2) conduit penetrators as described below and detailed on drawing no. B-519 (attachment 1).

1.1 4" diameter x 27" long steel conduit 1.2 40% actual fill of IEEE 383 rated cables. Cables were a total length of 62" and extended a minimum 36" above the slab.

1.3 Conduit extended a minimum 1" above the top of the slab

'and a minimum 12" into the furnace below the slab. Cable fill and mix within each conduit was similar to the ANI/

MAERP requirement of one-third 16 GA/2 cond (Representing instrumentation cable), one-third 12 GA/7 cond (Represen-ting control cable), and one-third 300 MCM/1 cond (Repre-senting power cable).

2.0 Penetration and Conduit Seal Characteristics 2.1 Materials used in installation consisted of:

2.1.1 Damming and cable separation - Alumina Silica F1-berous Material (Bulk and Board).

2.1.2 Penetration and conduit seal - Dow Corning 3-6548 Silicone RTV Foam 2.2 Penetration and conduit seal configurations were as fol-lows:

2.2.1 Configuration 1097b.1 - Conduit seal with a minimum depth of 6" plus 1" damming as measured from the top of the slab; penetration seal with a minimum' depth of 10" plus 1" damming as measured from the top of the slab.

1 2.2.2 Configuration 1097b.2 - Conduit seal with a minimum

. depth of 6" plus 1" of damming as measured from the top of the slab; penetration seal with a 6" depth plus 1" of damming as measured from the top of the slab. ,

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To: Administrator, Region IV Q.100.020 From: Randal W. Brown Page 3 of 5 3.0 Test Characteristics 3.1 'Thermocouples were located in accordance with the require-ments of IEEE 634 and ASTM E119 as shown on drawing no.

B-520 (attachment 2),

3.2 The prepared test slab assembly was exposed to the standard time temperature' curve established by ASTM E119 for a period of three (3) hours with the following results:

3.2.1 Configuration 1097b.2 - Thermocouple F-19 exceeded the maximum allowable with a temperature of 401o F at 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , 23 minutes and a three (3) hour reading of 6590 F.

3.2.2 Configuration 1097b.1 - Thermocouple F-25 exceeded the maximum allowable with a temperature of 401o F at 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , 14 minutes and a three (3) hour reading of 446o F.

3.3 While no flame through was noted on the unexposed side and hose stream tests did not cause openings, heat transmission as indicated by the field thermocouples exceeded the max-imum temperature requirement of 325o F above ambient. An autopsy was performed and resulted in the discovery that both conduit seals were reduced to ash.

3.4 Although the affected seals did not meet the full three (3) hour requirement for heat transmission, both configurations are operable up to the time periods referenced in para-graphs 3.2.1 and 3.2.2, respectively.

(2) 1.he requirement to install conduit seals at the fire barrier was in-cluded in design specifications for various stations in ordar to comply with Branch Technical Position 9.5.1-29 (3). ' Preliminary investigations by Louisiana Power & Light Company and B&B PROMATEC indicate that the defective configurations are probably of a generic nature affecting an unspecified number of nuclear generating sta-tions.

The number and locations of all affected stations cannot be deter-mined by Louisiana Power & Light Company or B&B PROMATEC as various utilities and seals contractors may have designed and installed simi-lar configurations. Preliminary investigations by Louisiana Poker &

Light and B&B PROMATEC has determined that the following stations and i

L

To: Administrator, Region IV Q.100.020 From: Randal W. Brown-Page 4 of 5 licensees are likely to be effected, as a minimum:

WATERFORD 3......................... Louisiana Power & Light Co.

4

GRAW GULF 1. . . . . . . . . . . . . . . . . . . . . . . . Mississippi Power & Light Co.

NUCLEAR ONE 1. . . . . . . . . . . . . . . . . . . . . . . Arkansas Power & Light Co.

SHEARON HARRIS 1.................... Caro 11na Power & Light Co.

4

WOLF CREEK.......................... Kansas Gas & Electric Co.

CALLAWAY 1.......................... Union Electric Co.

Various organizations have participated in the design and installa.

tion of penetration and conduit seals at the locations identified thus far. Evaluations to determine the number and locations of all defective seals is expected to be an extensive, time consuming opera-tion that would require the collective efforts of all affected orge-nizations. Evaluations are currently in progress by B&B PROMATEC and Louisiana Power & Light for Waterford 3. ,

(3) Other tests were conducted satisfactorily to provide potential cor-rective actions that may be taken for those seals determined to be unacceptable for the operability time periods previously referenced.

j Possible corrective action measure include:

1 (a) Evaluation of affected conduit seals to determine if exception

! can be taken to the required three (3) hour rating.

(b) Rework.of conduit seals that can not be excepted from a three

'(3) hour rating by installing:

(1) Installing a 3" depth silicone RTV foam seal boxed off with 1" alumina silica board at the conduit. termination point (attachment 3). This would also require the installation.

i of an additional 6" depth seal at the nearest accessible point on the continuous run side of the conduit.

! (2) Installing an additional 6" depth conduit seal at the nearest accessible point on the continuous run side of the conduit.

. Due to the apparent generic nature of this condition, it is requested that i assistance and/or direction by the NRC be given in order that we may proceed in the proper manner.

l l

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To: Administrator, Region IV Q.100.020 l From: Randal W. Brown Page 5 of 5 J

Please contact the writer at (713) 690-5240 at you earliest convenience.

Sincerly yours, PROMATEC

-1 M

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ML20140B194

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