ML20101R944

Part 21 Rept Re Defective Mounting Bolts Supplied by Unistrut Corp on Level Switches for Scram Discharge Vol Tanks.Initially Reported on 850117.Personnel Trained on Identifying Specified Bolt Matl

ML20101R944
Person / Time
Site:	Browns Ferry
Issue date:	01/18/1985
From:	Parris H TENNESSEE VALLEY AUTHORITY
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
REF-PT21-85, REF-PT21-85-044-000 PT21-85-044-000, PT21-85-44, NUDOCS 8502050139
Download: ML20101R944 (5)

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7 TENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE s74ot 500A Chestnut Street Tower II  !

Ja ua ,14) 55 U.S. Nuclear Regulatory Commission Region II

. ATTN: Mr. James P. O'Reilly, Regional Administrator 101'Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323

Dear Mr. O'Reilly:

TENNESSEE. VALLEY AUTHORITY - BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, AND 3 -

DOCKET NOS. 50-259, -260, -296 - FACILITY OPERATING LICENSES DPR-33,.DPR-52, AND DPR 10 CFR 21 REPORT .

During the unit 3, cycle 5 outage, level switches for the CRD scram discharge volume tanks were installed. While this installation was ongoing plant personnel identified a problem associated with the mounting screws and nuts

'for the level' switches. Different grade nuts and screws had been used for seismic mounting of the level switches. Upon further review, it was determined that unit 1 had the same problem. An analysis performed by TVA engineers determined the existing bolts as installed meet the specified design

-load requirements. However, a safety problem could develop if during maintenance the personnel were to torque the bolt to the value specified in plant instructions for the higher grade bolt that should have been installed.

-This would result in "overstressing" the associated nut, resulting in a possible failure mode. The bolting material on unit 3 has been replaced with ASTM A449 material. Work was completed July 30, 1984. Unit 1 bolting material will be replaced during the next scheduled outage, which is planned for June 1, 1985.

In the interim, action will be taken to ensure maintenance personnel are made aware of the torque requirements of the existing bolts. To avoid further occurrence of installation of incorrect mounting screws and nuts, appropriate plant personnel have been trained on identifying specified bolt material.

The bolting material used was supplied by the Unistrut Corporation through b & S Electric Supply Company. The bolting material supplied to TVA was not of the required grade, which resulted in the installation of different grade bolts and nuts. ASTM 307 bolting material was used instead of the specified ASTM A449 bolting material. The supplier, B & S Electric Supply Company, attested in an August 14, 1984 letter to TVA that the material shipped was correct.~Further correspondence with the Unistrut Corporation identified the material in question: cap screw as grade 2 and the nut as ASTM A570 GR 33 material. The supplier and manufacturer of the bolts which were supplied to

-TVA in a " mixed grade" are as follows:

Supplier: .B & S Electric Supply Company, Inc.

610 Wendell Court Atlanta, Georgia 30336 Manufacturer: Unistrut Corporation Un 'u No. HHCS025150EG. OmdAL COPY WAN$Uo!$$j!,

S pg An Equal Opportunity Employer I s #' /[

Mr. James P. O'Reilly January 18, 1985 This problem is reportable under 10 CFR 21 and was reported to J. P. Darling (acting 'in my absence) on January 17, 1985. J. A. Domer of my staff made verbal notification to Dave Verrelli of your staff on January 17, 1985. .The enclosed Part 21 report from Browns Ferry contains additional information on this matter.

Very truly.yours, TEN SS VALLEY AUTHORITY t

G. Parris Manager of Power and Engineering Enclosure

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on Tcnn:ss;e Vcilty Authority Fcrm BF 119

, g . Browns Ferry Nucl::ar Plant Page 1 of 2 BF 15.2 BF 15.23 5/30/84 EVALUATION LOGIC FOR PART 21 L PROBLEM:

Reference:

CAR 84-052/DR 84-0166 (Mixed grades of bolts received) as IDENTIFIED BY: Ouality Control Inspector M A. Does' the problem involve:

a

1. Failure of goods and services to comply with applicable NRC requirements (regardless of whether these requirements are included in the procurement

, document). Yes / / No /X/ (if yes, go to D)

2. A procured basic component failure resulting in a condition or circumstance that could contribute to exceeding a safety limit as defined by plant

.. technical specifications. Yes /X/ No / / (if yes, go to B)

. 3. Departure of a delivered component or service from the technical requirements of a procurement document. Delivery occurs upon acceptance I by NUC PR (e.g. , at receipt inspection). Yes / X / No / / (if yes, go to B)

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B. Is component necessary to ensure:

3

1. The integrity of the reactor coolant pressure boundary Yes / / No / X/

2. The capability to shut down the reactor and maintain it Yes / X/ No / /

, in a safe shutdown condition (example, IEEE Class 1E Electrical, Seismic cat. '1)

3. The capability to prevent or mitigate the consequences Yes / X/ No / /

of accidents

4. Is security system deficiency involved? Yes / / No / X/

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_"_Y_ .e.s_' s_"_ _ _ .G_ _O_ _T_ O_ _ _D_ _ . . . . . . . . _ _ _ _ _ .

• C. Evaluation for Services 1.

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• If this is a repair service, would the item being repaired be procured as a " Commercial Grade" item?

If "Yes",10 CFR 21 does not apply, go to Yes / / No / /

"E."

If "No", gr to C-2.

l *** 2. Could the service being procured cause a defect in a basic :.omponent or are the services connected with Yes / / No / /

the de' egn, inspection, testing, or consulting services important to safety that are associated with a basic I **

component. If "Yes",10 CFR 21 applies. Go to "E . "

If "No", 10 CFR 21 does not apply; go to "E."

Il h * ..........

D. Could ..........____

the defect have ........___..___............___

caused a substantial safety hazard? .._________...........___..

Yes / X / No / /

(By definition, item A2 cc,nstitutes a substantial safety hazard. )

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, E. Is this item reportable by NUC PR under Part 21? Yes /X / No / /

• Revision i'

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• Form BR 119 Tennessee Valley Authority -

• --- * ' 6. Page 2 of 2 Browns Ferry Nuclear Plant '

r. , BF 15.2 ,

BF 15.23 5/30/84 EVALUATION LOGIC FOR PART 21 (Continued) ,-

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• Submitted: f_

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/Date

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'f lb LN Reviewed: . K, Id e / P ,' ' / " i I/ / I [6 f Compliance Gtaff Supervisor Date 'f Approved: v#t  ! / / 6 S PORC Chc rman I/ ate

cc: Compliance Supervisor

- Retention : Period - Lifetime; Responsibility - Document Control Supervisor

. s NOTE TO PORC CHAIRMAN: This is a Part 21 (non LER). Special handling l is required per BF 15.23. Return to Compliance for I transmittal to Chatt.

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'* Addendum m

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, P y- Tennessee Valley Authority Browns Ferry Nuclear Plant Page 1 Form DF 145 -

BF 15.23 7/2G/82 Attachment 1 Part 21 .

L PART 21 REPORT Report # _ . -

9 Plant mp Referen ces _ c,, c,.,._,,

@ CAR 84-052/DR 84-0166 Unistrut No.

Component or System Identification mtCS0251150EG Supplier of Component B&S Electric Supply Co..' Atlanta. CA.

Nature of Defect or Noncompliance and Cause Bolt is of higher strength than required part.

68'.

O Extent of Safety Hazard _Could lead to overstressina of nut y if torcued ner maintenance tables m -

Date Which Defect or Noncompliance Was Discovered 12-5.86

n. Number of Identical Components in Use -

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I.ocation of Components -

Level switches for scram discharge volume

_ unit 1 - see CAR for details Corrective Action and Recurrence Control Taker. or To Be Installed Taken bolts ok per drawing installation valves - To be replaced next suitable outage - See CAR closcout for details.

C3 Expected Completion Date By next refueling outage, lias defect or noncompliance been reported previously? Yes / / No /x/

If yes, by what means?

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