ML20040G858

Part 21 Rept Re Rotation of Inboard babbit-lined Bearing Mount Causing Partial Blockage of Oil Supply.Caused by Lack of Antirotation Pin or Device.Set Screw Installed in Upper Half of Bearing Mount to Prevent Rotation

ML20040G858
Person / Time
Site:	Browns Ferry
Issue date:	02/03/1982
From:	Parris H TENNESSEE VALLEY AUTHORITY
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
REF-PT21-82-559-000 PT21-82-559, PT21-82-559-000, NUDOCS 8202160544
Download: ML20040G858 (7)

Text

,

s TENNESSEE VALLEY AUTHQftflg pggg y 3 CH ATTANOOGA. TENNESSEE 3)40'l A I* I A CEOPf*i.

500A Chestnut Street Tower II February 3, 198 g4 ql, gy Mr. James P. O' Reilly, Director U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement

Region II 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303

Dear Mr. O'Reilly :

TENNESSEE VALLEY AUTHORITY - BROWNS FERRY NUCLEAR PLANT UNIT 3 - DOCKET No. 50-296 - FACILITY OPERATING LICENSE DPR 10 CFR -21 REPORT A routine inspection of the unit 3 reactor core isolation cooling turbine revealed that the inboard babbit-lined bearing had rotated in. its bearing mount and caused partial blockage of the oil supply.

If the bearing had rotated in the mount for any length of time, it would have resulted in rendering the reactor core isolation cooling system inoperable.

This problem which is reportable under 10 CFR 21 was reported to me on February 3,1982.

The enclosed Part 21 report contains additional information about this matter.

Very truly yours, TENNESSEE VALLEY AUTHORITY A-A^

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s H. G. Parris Of Manager of Power U

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100 ys OFFICIAL Cg&

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An Equal Opportunity Employer w

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... Tennessee Valley Author 4 Form BF 119 o

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' Browns Ferry ' Nuclear. Plant Page 1 of 2 BF 15.2 9/1/81 i

J EVALUATION LOGIC FOR PART 21 i

PROBLEM:

During routine inspection of the unit 3 RCIC Terry Turbine,it was revealed that'there was no ant'irotation device in the inboard bearing.

IDENTIFIED BY: LER BFRO 50-

/

, Trouble Report #

Corrective Action Report Quality Assurance Survey Audit Other Routine Inspection

/

._ / This problem does not involve material defect, inadequate design, or fabrication error and is not subject to 10CFR21 reporting in accordance with DPM N77A14.

I or

/ X/ This problem involves a material defect, inadequate design, or fabrication error and is evaluated as follows:

I.

Deficiency of a plant security system:

Yes No 1.

Could defect create a substantial safety hazard?

/

/

/x/

If yes, report as Part 21.

.II.

Is the component necessary to ensure:

1.

The integrity of the reactor coolant boundary?

/

/

/x/

2.

The capability to shut down reactor and maintain it in a safe shutdown condition?

/x /

/

'/

3.

The. capability to prevent'or mitigate the conse-quences of accidents which could result in a potential offsite exposure comparable to those referred to in 10CFR100.11?

/

/

/x/

Ill.

Is defect in a basic component one that has been accepted for ownership?

/x/

/

/

Installed for use or operation?

/x/

/

/

. If a yes in II and III above, could defect create a sub-stantial safety hazard?

/

/

./ x /

If yes

. report as Part 21.

1

Form BF 119 Tennessee, Valley Authority' /-

Page 2 of 2 Browns Ferry Nuclear Plan't BF 15.2 9/1/81 EVALUATION LOGIC FOR PART 21 (Continued)

IV.

Is defect in a basic component:

Yes No A condition that could contribute to exceeding of safety limit?

/

/

/X /

If yes, to one of II and IV above, report as Part 21.

Recommendation:

/

/

This problem is not reportable, or

/X /

This problem is reportable and included in LER or Part 21 Report, form BF

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1/28/82 Submitted:

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iewer Date Reviewed:

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7 - 2.-f L Qualit? 'As rande Su rv's Date Approved:

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/ 1 f-/91 PORC, Clfdirman

' Date

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4 2w Retention:

Period - Lifetime; Responsibility - Document Control Supervisor R

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QA PROGRAM RELATED.

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Page 6

tal. IF0]AM Part lli, Sec 1

N77A14 Atyachment 1

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Revised 3/p)/81 PART 21 REPORT _

~~

References Plant Browns _ ferry Soclane Plant Component or System Identification Unit 3 RCIC_. Terry._Turbina Turb_ip_e,,Cg.

Supplicr of Component General _Elmtric._Co. Terry _Steau

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Nature of Defect or Noncompliance

.rhn_ inboard._Ierry._Inrbine shaf Lbearing_..

-did not have an antirotation pin or device.

The shaft bearing could have rotated in.ts 4

Extent of Sa f ety llaza rd failure of the RCIC pump-turbine.

mount _yfth subs _equent

~

12/29/81 Date Which Defect or Noncompliance was Dir: covered Number of Ident.ical Components in Use 3 Terry Turbines I.ocation of Components Jrowns _ Ferry Nu_g. lear Plant __ units 1, 2 and 3.

Located in the Reactor Building.

Corrective Action Taken or To Be Taken Install 1/4 inch, 20 threads per Screw extends into Jach,_ set screw in upper half of bearing mounts.

bearing _and p.revents rotation.

Requi red to Complete Act inn _48_ hours. requiUed to i_nstall Length of Time

,pn_t_irotation set screw.

lias defect or noncompliance been reported previously? Yes /[~/ No /d~/

If yes, by what means?

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General Revision im n

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QA PROGRAtl RELATED Ref N 0QAM Part 111, Sec 1

Pace 7 Attachme.e-;

N77A14 Revised 6/25/81 PART 21 INALUATION SilEET

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Does the problem involve:

1.

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

_ No /X/_

procurement document).

Yes / /

If yes, go to C 2.

Condition or circumstance that could contribute

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to exceeding a safety limit na defined by plant

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13 technical specifications.

Yes / / No /X[

If yes, go to B l

3.

Departure of a delivered component or service from the technical requirements of a procurement document.

Delivery occurs upon acceptance by NUC PR (e.g., ac receipt inspection).

Yes /7 No /X/_

If yes, go to B 4.

Deviatton in a portion of the plant which has been transferred (final trannfer) to NUC PR.

Yes / T No /7 If yes, go to C y

Annwer all 4 questions above.

If all "No's",

STOP llERE.

If any "Yes's",

W continue as indicated by the applicable "C0 T0" statement.

3, Is component necessary to ennure:

1.

The integrity of the reactor coolant presnurc Yes / [ No d Q

2.

The capability to shut down the reactor and

_, No //

W maintain it in i safe shutdown condition Yes /X/

3.

The capability to prevent or mitigate the

_ No g/_

consequences of accidents Yes {/

Is security system deficiency involved?

Yes /_7 No [

If all "No's", STOP liERE - If any "Yes's" - CO TO C C.

Couta the aefect have causea a substantial D

safety hazard? (By definition, iten A2 constitutes a substantial safety hazard.)

Yes /_Y No /_/_

If "No",

this item is not reportable - If yes, this item is reportabic under Part 21.

O, Is this item reportabic by NUC PR under Part 21?

Yes [ No O Evaluated By I,

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