ML17244A458

Summary of 790313-14 Meeting W/Util,Westinghouse & Eg&G at Plant Site Re Systematic Evaluation Program Topic III-5.A, High Energy Line Break Inside Containment. W/List of Attendees

ML17244A458
Person / Time
Site:	Ginna
Issue date:	04/04/1979
From:	Jabbour K, James Shea Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
TASK-03-05.A, TASK-3-5.A, TASK-RR NUDOCS 7904200288
Download: ML17244A458 (13)

Text

MEETING SUNDRY DISTRIBUTICiif; Docket R

Local PDR ORB45I2 Readying HRR Reading

}L R, Denton E, GCase V. Stello P,.

Vo'}1mer t1. Russell B. Grimes T. J. Carter

0. Eisenhut D. Dao'Is D. Zfemann P.

Check G. Lafnas A. Sckencer R. Reid T

Ippollto V. Hoonaz G. Knfghton D. Brlnkman

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Shea GELD OISE(3)

H, Smooth R. Fraley, ACRS(l6)

K. H. Qabbour C. Hofmayer P. A. D)Benedetto R. N. Stephens D. R.

Buchanan TERA 78042908gIt OFFICE~

EVRNAMEW DATE~

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1979 Docket No.60-244 LICENSEE:

Rochester Gas 5 Electr fc Corporation (RGSE)

FACILITY:

R. E. Gfnna Nuclear Power Plant

SUBJECT:

SUE%)ARY OF MEETING HELD ON NRCH 13-14, 1979 Representatives of the Nuclear Regulatory Cotpmfssfon (NRC) and RG5E met at the R. E. Ginna site to discuss the Systematic Evaluation Program topic III-S.A, High Energy Line Break Inside Containmen, on Harch 13-14, 1979.

A list of attendees fs,provided as Attachment 1.

Following brief introductory discussions on the purpose of the visit, health physics (radiation exposure)'and securfty orientatfon, and individual whole body radiation counts, the group dressed in protective clothing and entered the Ginna containment structure.

The purpose of containment entry was to view from different locatfons within containment the high and moderate energy piping layout and supports relative to pipe break inside containment.

Hfth this objective, piping, compartmentatfon, electrical cable trays, safety systems including instrumentation and other components that could be affected by pipe whip or jet impingement in the unlikely event of a pipe break were assessed.

Individual whole body radiation counts vere repeated on exit from containment..

7 A summary of the ma)or items discussed follows:

RGSE has utilized the effect or fented approach (for evaluating the high energy line break effects) described fn the attachment to the NRC letter to RGRE dated September 7, 1978.

This approach postulates a high energy pipe break inside contai'nment near safety equipment and analyzes the capability of the remaining systems to safe'ly shutdown the reactor.

Licensee representatives discussed the 'fnteractbon of the breaks (pipe whip and jet impingement) with the safety systems required to shutdown the plant, i.e.

Emergency Core Cooling Systems (ECCS) and Engineered. Safety Features (ESF).

Based on the study of fifteen piping systems

.(Attachment 2) they concluded that breaks in eleven piping systems result in acceptable pfpe H~ifp and $~t finpfngeme~t con'sequencws, that fs the reactor can be shutdown safely.

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197g (1) fn general damage to one of the two primary reactor coolant loops does not affect the other loop or associated safety features for emergency core cooling and (2) most of the small diameter high energy piping was eliminated from further evaluation of pipe break consequences on the basis that a broken pipe can not sfgnfffchntly damage other pfpes of equal or greater size and strength.

The licensee concluded that breaks in four piping systems must be investigated further to determine ff postulated breaks in these lines would have unacceptable consequences.

These four systems are:

o Hafn Steam o

Hain Feedwater o

Pressurizer Surge o

Accumulator Discharge into Reactor Coolant System The important targets which may be impacted by main steam or feedwater line breaks are containment, steam generator, and crane suppor t columns.

The evaluatfons made by the licensee did not postulate a single faflure to occur simultaneously with the assumed pipe break.

2.

The NRC representatives requested the licensee to comp'lete the detaf'led documentation of the effects of each break on ECCS and ESF required for safe reactor shutdown, to include the get fmpfngement effects on cables and cable trays inside containment and, to provide assurance that the electrical integrity of necessary equipment is maintained.

30 The NRC representatives requested the licensee to perform the interaction study for breaks in the pressurized portion of the Residual Heat Removal (RHR) 'line (f.e. on the primary coolant loop side of the remotely operated RHR valve) and their effects on steam generator supports in reactor coo'lant loop A and pump supports in reactor coolant loop B.

The applicability of the mechanistic approach for postulating break locations was discussed.

Me stated that a minimum of two intermediate breaks should be postulated for each pfpfng run in addition to termfnal ends as stated in Regulatory Guide 1.46 and NRC Standard Review P'lan 3.6.2.

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Tho licensee stated that the effects of all postulated breaks on component supports and piping supports lave been considered in their evaluations, Nevertheless, the NRC representatives indicated that this matter should be revfewed further, for all systems; particularly for the reactor coolant jump and pressurizer supports.

6.

The NRC representatives requested copies of the analytical work performed on the Residual Heat Removal System and the Nafn Steam L'ine; to'how their adequacy under normal and faulted conditions.

Information on the following pipfng systems may be requested later:

o Reactor Coo'lant System o

Pressurizer Surge Line o

Accumulator Discharge Line to RCS o 'tafn Feedwater Line 7t The licensee noted that one ff a postulated break in the accumulator in)ection line resulted in pipe whip or get impinge-ment that damaged the Residual.Heat Removal System used for normal plant: cooldown the reactor could be maintained in the hot shutdown condition until the damaged RHR system could be restored to operating condition.

The NRC representatives requested that RGSE identify all equipment and systems available under such a postulated condition to maintain the plant fn a safe condition during the interim when the RHR system is unavailable to cool and depressurfze the reactor primary coo'lant system.,

The licensee also noted the low probability of failure fn this line due to low stresses.

The 1 fcensee requested that augmented In-Service-Inspection (ISI) be considerod for the main steam and feedwater lines in lieu of postulating break locations fn these lines.'

The NRC representatives requested the licensee to study the pipe whip and jet impingement effects of the breaks postulated under NRC TASK ACTION PLAN {TAP) A-2 and to consider these effects for postulated breaks fn the primary coolant loop at locations other than those required in TAP A-2 using either the mechanistic or effect oriented approach.

The NRC representatives

'agreed to further review the interface between A-2 and SEP Topic III-G.A to assure that there is no unnecessary duplication of effort.

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APR 4 lg7g At the conclusion of the meeting RGSE agreed to document the areas discussed

.above. It was est)mated that the effort could be completed

$ n three or four months Nhfch

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@3th the HRC,Systemtfc Evaluation Program.

A firm schedule for accompl,)shing the objectives wi'll be presented to HRC when the scope of vlrk and RGtlE resources have been more clearly ident)fled.

Kahtan Jabbour SEP Branch Division of Operat)ng Reactors Attachments:

1.

Ust of Attendees 2.

RGSE letter dtd 8/9/79 James J.

Shea, Project Manager OperaNng Reactors'ranch 42 0)vis]on of Operating Reactors Ccf See next page OFFICE~

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Mr. Leon D. White, Jr.

APR 4 1979 CC Lex K. Larson, Esquire

LeBoeuf, Lamb, Leiby 5 MacRae 1757 N Street, N.

W.

Washington, D..C.

20036 Mr. Michael Slade 1250 Crown Point Drive Webster,.New York 14580 Rochester Committee for Scientific Information Robert E. Lee, Ph.D.

P.

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Box 5236 River Campus Station Rochester, New York 14627 Jeffrey Cohen New York State Energy Office Swan Street Building Core 1, Second Floor Empire State Plaza

Albany, New York 12223 Director, Technical Development Programs State of New York Energy Office Agency Building 2 Empire State Plaza

Albany, New York 12223 Rochester Public Library 115 South Avenue Rochester, New York 14604 Mr. Leon D. 0lhite, Jr.

Vice President Electric and Steam Production Rochester Gas 5 Electric Corporation 89 East Avenue Rochester; New York 14649 Mr. Robert C.

Neer'edy Rochester Gas 5 Electric Corporation 89 East Avenue Rochester, New York 14649

ATTACHltENT l LIST OF, ATTENDEES RG8E P,

C. Mflkens M, Bockus G. 'Hrobel R. C. fhcredy EGM R, C. Guenzler 0.

K. f)orton

'estfnqhouse K. Chang J. d. Shen K. N, Qabboor C. Hofmayer P, A. 0$ 8enedetto R. N, Stephens ORRICa~

dURNAMCW DATE~

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