ML19331D945

Significant Deficiency Rept Re Loose Impeller Cap & Jam Nuts on RHR Pump 1A.Caused by Inadequacy of IR Recommendation Re IE Circular 79-19.Util Has Informed I-R That Recommendation Will Not Resolve Problem

ML19331D945
Person / Time
Site:	McGuire, Mcguire
Issue date:	08/28/1980
From:	Parker W DUKE POWER CO.
To:
References
10CFR-050.55E, SD-369-80-14, SD-370-80-10, NUDOCS 8009040383
Download: ML19331D945 (2)

Text

r DUKE POWER COMPANY Powns Benmixo 422 Socra Cuencu Srmant, CeAmtorTz. N. C. asa4a wiwe. o. Paa nen.s a. August 28, 1980 v.c p.e...., tit ....c. 4.c. to.

Stgam P.cowCTiose 37 3-do83 Mr. James P. O'Reilly, Director U. S. Nuclear Regulatory Comission

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

Re: McGuire Nuclear Station -

~

Unit 1 and 2 Docket No. 50-369, -370

Dear Mr. O'Reilly:

Pursuant to 10CFR 50.55e, please find attached Significant Deficiency Report SD 369/80-14, '70/80-10.

1 Ve truly yours,

. /N

< , , , _ _J . -

William O. Parker, Jr.

LJB:ses Attachment cc: Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Comission Washington, D. C. 20555 B

$0/1ll Sl 80 090403g3

l

DUKE POWER COMPANY MCGUIRE NUCLEAR STATION Report Number: SD-369/80-14, -370/80-10 Report Date: August 28, 1980

' Facility: McGuire Nuclear Station, Unit I and 2 Identification of Deficiency: Loose Cap and Jam Nuts on Residual Heat Remeval Pump Description of Deficiency:

On July 29, 1980, Mr. W. H. Bradley and Mr. P. R. Herran advised Mr. Virgil Brownlee, NRC, of the following design deficiency. During replacement of mechanical seal on RHR pump 1A, the impeller cap nut and jam nut were found to be loose.

This type pump (Ingersoll-Rand 8x20 WD) was the subject of IE Circular 79-19 in September of 1979, identifying a loose impeller locking device problem.

Of the three fixes presented in the circular, Duke employed the I-R recommenda-tion of increased torque (from 215 ft-lb to 250 ft-lb) on the referenced nuts.

For this particular pump, the increased torque did not resolve the problem.

Analysis of Safety Implications:

The I-R 8x20 WD is used on McGuire Units 1 and 2 in Residual Heat Removal and Containment Spray applications (2 RER pumps and 2 containment spray pumps per unit). Loss of one RHR pump would increase normal cooldown time for plant shutdown and would delete redundancy in containment spray and safety injection systems. Loss of one containment spray pump would delete redundancy in the containment spray system.

Corrective Action:

I-R repair kits have been ordered for each of the McGuire RHR and NS pumps

(.eight pumps total / ten kits ordered). Unit 1 installation should be completed by October 27, 1980. Other Duke nuclear projects will be reviewed for similar I-R pump applications and additional repair kits will be ordered and installed as appropriate.

Duke has informed I-R that the higher torque did not preclude loosening of the cap and jam nuts for this particular pump application.

l

. . ~ ~ , , - --, ,.