ML17263A287

Informs That Util in Process of Procuring Replacement SGs for Plant in Ref to NRC Ltr Re 10CFR50 Mod of GDC-4 Requirements for Protection Against Dynamic Effects of Postulated Pipe Ruptures & GL 84-04

ML17263A287
Person / Time
Site:	Ginna
Issue date:	05/13/1993
From:	Mecredy R ROCHESTER GAS & ELECTRIC CORP.
To:	Andrea Johnson NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
GL-84-04, GL-84-4, NUDOCS 9305190297
Download: ML17263A287 (5)

Text

ACCELERATF DOCUMENT DISTRI UTION SYSTEM REGULAT INFORMATION DI'STRIBUTION STEM (RIDS)

ACCESSION NBR:9305190297 DOC.DATE: 93/05/13 NOTARIZED: NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G

05000244 AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.

Rochester Gas 6 Electric Corp.

RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R.

Project Directorate I-3

SUBJECT:

Informs that util in process of procuring replacement SGs for plant, in ref to NRC,7590-01, "10CFR50 Mod of GDC-4 Requirements for Protection Against Dynamic Effects of Postulated Pipe Ruptures"

& GL 84-04.

DISTRIBUTION CODE:

AOOID COPIES RECEIVED:LTR I

ENCL 0 SIZE:

TITLE: OR Submittal: General Distribution NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).

05000244 RECIPIENT ID CODE/NAME PDl-3 LA JOHNSON,A INTERNAL: NRR/DE/EELB NRR/DRCH/HICB NRR/DSSA/SPLB NUDOCS-ABSTRACT OGC/HDSl EXTERNAL: NRC PDR COPIES LTTR ENCL RECIPIENT ID CODE/NAME PD1-3 PD NRR/DORS/OTSB NRR/DSSA/SCSB NRR/DSSA/SRXB OC~B RE@

01 NSIC COPIES LTTR ENCL NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTETH CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-31 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEEDI TOTAL NUMBER OF COPIES REQUIRED:

LTTR 16 ENCL

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ROCHESTER GAS AND ELECTRIC CORPORATION o

89 EAST AVENUE, ROCHESTER N. Y. 14649-0001 ROBERT G MECREDY Vice President Clnna Nuclear Production TELEPHONE AREACODE 716 546 2700 May 13, 1993 U.S. Nuclear Regulatory Commission Document Control Desk Attn:

Allen R. Johnson Project Directorate I-3 Washington, D.C.

20555

Subject:

Application of Leak Before Break Technology, GDC-4 R.E.

Ginna Nuclear Power Plant Docket No. 50-244 Ref. (a):

Nuclear Regulatory Commission, 7590-01, "10CFR50 Modification of General Design Criteria 4 Requirements for Protection Against Dynamic Effects of Postulated Pipe Ruptures,"

Statement of Considerations.

(b):

NRC Letter, D. C. DiIanni to R.

=W. Kober (RG&E), "Docket No. 50-244, (Generic Letter 84-04)", dated September 9,

1986.

Dear Mr. Johnson:

Rochester Gas and Electric is in the process of procuring replacement Steam Generators for the R.

E.

Ginna Nuclear Power Plant.

The process of establishing the design specification for these generators has led us to conclude that it is desirable to clarify the design basis of the R.

E.

Ginna Nuclear Power Plant regarding the dynamic effects of primary system pipe ruptures.

In Reference (a) the NRC indicates that if it can be demonstrated that the probability of pipe rupture is extremely low, the dynamic effects of the pipe

rupture, i.e.

missile generation, pipe

whipping, pipe break reaction

forces, jet impingement

forces, decompression waves within the ruptured pipe and dynamic or non-static pressurization in

cavities, subcompartments and compartments, can be excluded from the design basis of the unit.

The statement of considerations specifically excludes the applicability of this rulemaking to emergency core cooling systems,

'containments, and environmental qualification.

By reference b, the NRC approved the use of this rulemaking for primary system piping for the R.

E. Ginna Nuclear Power Plant.

While the rulemaking (Reference (a)) explicitly discusses piping supports, it does not discuss internals of reactor coolant system components.

It is our interpretation that the rulemaking is agtsiggggp to internal components, as long as the functionality of 9305190297 930513 PDR ADQCN 05000244 PDR

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the Emergency Core Cooling System or Containment are not adversely affected by the component.

It is our intention that the design basis for internal, non-pressure boundary components of the steam generator, specifically the primary side divider plate, reflect this rulemaking.

Therefore the dynamic effects of primary system piping ruptures need not be included in the design basis of this plate.

This is consistent with the conversations of May 7 and 10'993 between Mr. George Wrobel (RGGE) and Mr. James Norberg and Mr. Jay Rajan of the NRC.

Very truly yours, Robert C. Mecr dy BJF4284 Attachment xc: Mr. Allen R. Johnson (Mail Stop 14D1)

Project Directorate I-3 Washington, D.C.

20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector