ML20245G041

Advises That Corrective Actions for Significant Deficiency & Part 21 Rept Re Unqualified Nupro Valve Seals Completed & Resolved,Per 890707 Rept.Only 98 Nupro Test Valves Furnished on GE Racks & Addl 17 Valves Provided for Other Racks

ML20245G041
Person / Time
Site:	Limerick
Issue date:	08/08/1989
From:	Hunger G PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
REF-PT21-89-133-000 PT21-89-133, PT21-89-133-000, NUDOCS 8908150173
Download: ML20245G041 (2)

Text

10 CFR 50.55(e) d PHILADELPHIA ELECTRIC COMPANY NUCLEAR GROUP HEADQUARTERS 955-65 CHESTERBROOK BLVD.

WAYNE. PA 19087 5691 (215) 640-6000 l

August 8, 1989 Docket No. 50-353 License No. NPF-84 l

U.S.

Nuclear Regulatory Commission ATTN:

Document Control Desk Washington, D.C.

20555

SUBJECT:

Limerick Generating Station, Unit 2 Significant Deficiency Report NUPRO Valve Seals-Additional Information l'

REFERENCE:

Significant Deficiency Report No. L2-89-44 Final Report dated July 7, 1989 Gentlemen:

The referenced letter identified a deficiency at Philadelphia Electric Company's (PECo's) Limerick Generating Station, Unit 2 regarding unqualified NUPRO valves.

That letter indicated that 99 NUPRO brand test valves had been installed in instrument lines on racks furnished by General Electric Company (GE).

Further review has identified that only 98 NUPRO test valves were furnished on GE racks, and that an additional 17 NUPRO test valves were provided for other instrument racks.

The assessment of and corrective action for this I

deficiency were identified in our July 7, 1989 letter as replacement of all NUPRO valves with valves that do not contain viton seals prior to initial criticality.

This letter provides a clarification of the corrective actions taken.

The NUPRO valves were replaced for GE rack installations, as originally described, with valves that do not contain viton seals.

Additionally, the non-GE rack-installed valves were " replaced" in function by adding an ASME valve in the line to provide the isolation / pressure boundary function.

These corrective actions have been completed and PECo considers this significant deficiency resolved.

8908150173 890808

((Qf

{DR ADOCK 0500 3

AJ.S.; Nuclear. Regulatory Commission

' August 8, 1989 4

Page 2

' gl' s

If you have any further questions regarding significant'

' deficiency. reports, please contact the Senior Licensing Engineer for Limerick, Mr. Rod Krich, at (215) 640-6775.

i Very truly yours, l

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• i i

G. A. Hunger, Jr.

Director I

Licensing Section Nuclear Support Division cc:

W.

T.

Russell, Administrator, Region I, USNRC T.

J.

Kenny, USNRC Senior Resident Inspector, LGS l

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