ML17158B127

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Discusses 930708 Meeting W/Util in Rockville,Md Re Spent Fuel Pool Issues at Plant.Informs That NRC Plans No Further Action in Matter
ML17158B127
Person / Time
Site: Susquehanna  Talen Energy icon.png
Issue date: 03/05/1996
From: Cooper R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To: Byram R
PENNSYLVANIA POWER & LIGHT CO.
References
EA-95-224, NUDOCS 9603120347
Download: ML17158B127 (3)


Text

March 5, 1996 EA 95-224 Mr. Robert Byram Senior Vice President - Nuclear

. Pennsylvania Power and Light Company 2 North Ninth Street Allentown, PA 18101

SUBJECT:

SPENT FUEL POOL ISSUES AT SUSQUEHANNA

Dear Hr. Byram:

On July 8,

1993, the NRC and the Pennsylvania Power and Light (PP&L) Company met in Rockville, Maryland, to discuss spent fuel pool issues at Susquehanna.

At the July 8, 1993 meeting, your Hanager of Nuclear Technology provided specific information concerning the standby gas treatment system's (SGTS) design capabilities (temperature and humidity) and the effects of condensation on the duct-work for the SGTS if boiling were to occur in the spent fuel pool.

At the July 8, 1993 meeting, your Hanager of Nuclear Technology stated that the SGTS would be able to accommodate increased condensation from a boiling spent fuel pool.

Based on more thorough spent fuel pool boiling analyses completed by PP&L after the July 8, 1993 meeting, PP&L concluded that the SGTS would be degraded and/or inoperable due to condensation in the SGTS duct-work for a dual unit boiling spent fuel pool event.

Therefore, the statement made by your Manager of Nuclear Technology at the July 8, 1993 meeting was not comprehensive because condensation would degrade the system after some period of time.

The NRC concluded that our questions regarding SGTS design temperatures and humidities at the July 8, 1993 meeting could conceivably have been narrowly construed by the Manager of Nuclear Technology, and were subsequently answered in a correspondingly narrow context.

The NRC also concluded that information provided regarding condensation in SGTS duct-work was based on the best information available, although the Manager of Nuclear Technology did not discuss a detailed basis for his response.

Therefore, the NRC is not planning any further action in this particular matter.

In accordance with 10 CFR 2.790 of the NRC's "Rules of Practice,"

a copy of this letter will be placed in the NRC Public Document Room.

No response to this letter is required and your cooperation with us in this matter is appreciated.

Sincerely, ORIGINAL SIGNED BY:

Docket Nos.

50-387; 50-388 License Nos.

NPF-14; NPF-22 9603I.20347 960305 PDR ADOCK 05000387 8

PDR Richard W. Cooper, II, Director Division of Reactor Projects

~]>(

Mr. R. Byram CC:

H.

G. Stanley, Vice President - Nuclear Operations J.

M. Kenny, Nuclear Licensing G. T. Jones, Vice President Nuclear Engineering G. Kuczynski, Plant Manager R.

R. Wehry, Nuclear Licensing M. M. Urioste, Nuclear Services

Manager, General Electric C.

D. Lopes, Hanager - Nuclear Security W. Burchill, Manager, Assessment Services H. D. Woodeshick, Special Office of the President J.

C. Tilton, III, Allegheny Electric Cooperative, Inc.

Nuclear Safety Information Center (NSIC)

Commonwealth of Pennsylvania

Hr.

R.

Byram Distribution:

Region I Docket Room (with concurrences)

D. Vito, ORA D. Holody, ORA J. Joustra, ORA E. Wilson, OI J. White, DRS A. Blough, DRS E. Kelly, DRS W. Pasciak, DRP R. Urban, DRP K. Gallagher, DRP D. Screnci, PAO (2)

NRC Resident Inspector PUBLIC Distribution:

(Via E-Hail)

W. Dean, OEDO C. Poslusny, Project Manager, NRR J.

Shea, Project Manager, NRR Inspection Program
Branch, NRR (IPAS)

J. Stolz, NRR J.

Lieberman, OE J.

Gray, OE J. Beall, OE R. Hoefllng, OGC gAi/re g/2//gc DOCUMENT NAME:

G:ItBRANCH4IiSFP.SUS To receive a copy of this document, indicate in the box 'C'y wit ut attachment/enclosure

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