ML20039C144

Final Deficiency Rept Re Failure of RHR Sys LPCI Injection Valve 1F017-B,initially Reported 811120.Locking Mechanism Devised to Attach anti-rotation Pin to Stem Collar.Also Reported Per Part 21

ML20039C144
Person / Time
Site:	Susquehanna, North Anna
Issue date:	12/18/1981
From:	Curtis N PENNSYLVANIA POWER & LIGHT CO.
To:	Haynes R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
REF-PT21-81 10CFR-050.55E, 10CFR-50.55E, PLA-981, NUDOCS 8112280489
Download: ML20039C144 (4)

Text

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-PP&L TWO NORTH NINTH STREET, ALLENTOWN, PA.18101 PHONE: (215) 770 5151 NORMAN W. CURTIS Vice President-Engmeenng & Construction-Nuclear 7745381 December 18, 1981 lir. R. C. Haynes q Director, Region I O D U. S. Nuclear Regulatory Commission NY 631 Park Avenue Mp b ,

King of Prussia, Pennsylvania 19406 Cf gEC NT/g*; ~

SUSQUEHANNA STEAM ELECTRIC STATION O /,0 FINAL REPORT OF A DEFICIENCY INVOLVING / . u 7-%

THE FAILURE OF RHR SYSTEM LPCI [. -t y 2cr INJECTION VALVE 1F017-B 's A ERs 100450/100508 FILE 821-10 \ 'X pLA- 981 *C-M

Dear Mr. Haynes:

This letter serves to provide the Commission with a final report of a deficiency relating to the Failure of RHR system LPCI injection valve 1F017-B. The deficiency was originally reported under the provisions of 10CFR50.55(e) to Mr. E. C. McCabe of NRC Region I by Mr. A. R. Sabol in a meeting in the NRC Region I office on November 20, 1981. The information contained in this report is submitted pursuant to the provisions of 10 CFR 50.55(e).

The attachment to this letter contains a description of the problem, its cause, safety implications, and the corrective action.

Since the details of this report provide information relevant to the reporting requirements of 10CFR21, this correspondence is considered to also discharge any formal responsibility PP&L may have in compliance thereto.

We trust the commission will find the information forwarded by this letter to be satisfactory.

Very truly yours,

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N. W. urtis Vice President-Engineering & Cor:struction-Nuclear MHC:jmk i

Attachment

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ggggggQ489 811210 P E N N S Y LV A NI A POWER & LIG HT COMP ANY g DR ADOCK 05000

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December 18, 1981 SSES PLA-981 100450/100508 821-10 cc: Mr. Victor Stello (15)

Director-Offi:e of Inspection-& Enforcement U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Mr. G.-Mcdonald, Director (1)

Office of Management Information & Program Control U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Mr. Gary Rhoads U. S. Nuclear Regualtory Commission P.O. Box 52 Shickshinny, PA 18655 I

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December 18, 1981 SSES PLA-981 100450/100508 821-10 Attachment to PLA-981 FINAL REPORT SUBJECT Failure of SSES Unit I RHR System LPCI Injection Valve 1F017B during test operation.

DESCRIPTION OF PROBLEM PP&L NCR 81-525 documented the failure of LPCI Injection Valve 1F017B to operate . An anti-rotation collar and pin assembly which is designed to assure that valve operator motion during valve cycling is translated into axial valve' stem movement, became disengaged from the collar, thereby rendering the valve inoperable. Additionally, Anchor Darling, the valve supplier, failed to show the anti-rotation collar assembly on the drawings supplied to PP&L for this valve.

CAUSE OF DEFICIENCY The anti-rotation pin is attached to the stem collar by a nut on the end of the pin (see attached drawing items 33-37). Anchor Darling failed to provide a locking mechanism that would prevent the nut from loosening and completely -

backing off. Consequently, this nut loosening and pin disengagement did occur on valve 1F017B resulting in the failure.

ANALYSIS OF SAFETY IMPLICATION The valve is located in the LPCI line to the reactor and its safety function is to throttle during shutdown cooling to both control the rate of cooling and to preclude RHR pump runout.

The problem is limited to the two LPCI injection mode valves for each unit, i.e. 1F017A&B for Unit I and 2F017A&B for Unit II. Only these four valves have this particular stem anti-rotation device which, in fact, was uniquely designed for these valves.

i The failure is considered a significant deficiency in design that is reportable under 10CFR50. 55 (e) .

CORRECTIVE ACTION Anchor Darling has submitted a revised drawing (attached) which shows the anti-rotation pin and collar assembly. The drawing indicates that the nut and pin are to be drilled and lock wired to prevent loosening.

Bechtel has issued NCR 8486 to control this deficiency and assure that the valves conform to the revised drawing.

Corrective Action will be complete prior to fuel load.

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