ML17262A672

Responds to NRC 911023 Request for Addl Info Re Containment Integrity.Util Decided to Monitor Radial Displacement of Containment at Approx Same Locations Monitored During Preoperational Test

ML17262A672
Person / Time
Site:	Ginna
Issue date:	12/03/1991
From:	Mecredy R ROCHESTER GAS & ELECTRIC CORP.
To:	Andrea Johnson NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
NUDOCS 9112110030
Download: ML17262A672 (6)

Text

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REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCELERATED DISTRIBUTION DEMONSTION SYSTEM ACCESSION NBR.: 9112110030 DOC. DATE: 91/12/03 NOTARXZED:

NO FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G

AUTH.NAME

=

AUTHOR AFFILIATION MECREDY,R.C.

Rochester Gas 6 Electric Corp.

RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R.

Project Directorate I-3 DOCKET 05000244

SUBJECT:

Responds to NRC 911023 request for addi info re containment integrity.Util decided to monitor radial displacement of containment at approx same locations monitored during preoperational test.

DISTRIBUTXON CODE:

A001D COPIES RECEIVED:LTR ENCL SIZE:

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

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RECIPIENT ID CODE/NAME PD1-3 LA JOHNSON,A INTERNAL: NRR/DET/ECMB 7D NRR/DOEA/OTS B11 NRR/DST/SELB 7E NRR/DST/SRXB 8E OC/LFMB RgG, FII'E 0~

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rIIIIIIIII Arm EElggl/I I~$IIZII ROCHESTER GAS AND ELECTRIC CORPORATION o

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nte 89 EAST AVENUE, ROCHESTER N.Y. 14649-0001 ROBERTG MECREDY Vice President Cinna Nud ear Production December 3, 1991 TELEPHONE AREACODE 71B 546 2700 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Allen R. Johnson Project Directorate I-3 Washington, D.C.

20555 H

Subject:

Ginna Containment Integrity Request for Additional Information R. E. Ginna Nuclear Power Plant Docket No. 50-244

Dear Mr. Johnson:

This letter transmits to you the additional information requested by you in your October,23, 1991 letter.

The treatment of the discussion on containment radial displacements for various modes of behavior, as stated in RG&E's July 11, 1991 letter, needs clarification. In that letter, Run Name RGE03 was stated to be the lower bound condition for radial displacement due to internal pressure because of the uncracked concrete assumption.

This has apparently caused confusion because of its labeling in Table 1 as "Seismic Only." RG&E failed to explain that the displacements that are plotted on Figure 2 were determined by analyses that used the boundary conditions and material properties as listed for Run Names RGE03, RGE08, and RGE12.

Those analyses were done with consistent loads, i.e., dead load, prestress and pressure.

The displacement for RGE03 that is shown on Figure 2 is ~no for a seismic loading.

(Table 1 has been noted to reflect these statements).

RG&E at no time attempted to match the SIT displacements with analytical models.

RG&E's goal was to determine the behavior of the containment for a wide range of boundary conditions at the base and demonstrate that the existing design provided adequate margins of safety for all possible conditions.

Since RGE03 utilized uncracked concrete properties circumferentially, it was expected that this would represent a lower bound on radial displace-ments due to internal pressure.

RGE08 and RGE12, with fully cracked concrete properties circumferentially, should present an upper bound on these displacements even with a wide "1ii2ii0030 9'ii.203

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range of rotational constraints (RGE08 is pinned, RGE12 is fixed). The plots on Figure 2 confirm our expectations in that the displacements obtained at the time of the SIT are in fact bounded by the analyzed upper and lower boundary conditions.

RG&E has also decided to monitor the radial displacement of the containment at app-roximately the same locations monitored during the pre-operational test.

These measure-ments willbe taken during the next scheduled leak rate test in 1993.

More extensive measurements have been judged not to be cost effective.

I trust that this response adequately addresses your request for additional information.

Very truly yours, Robert C. Mecredy LAS'Dwzi258 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

Case Reference Chart - Shell Model Run Name Load Cases (I)

Appticable Base Boundary Conditions Material Pro itios (nods Modulus Poisson (I)

Tie.Rods Tangential Verfical Rotational Radial Mer)dional Circumforencial Domo Redo h4bs/h sl si sl RADIAL SLIDINQ NO RADIAI.

SLIDINQ SEISMIC ONLY CONSTANT HOOP REINFORCEMENT SEISMIC ONLY PINNED ROTATIONAL RESISTANCE INCREASINQ FIXED PINNED ROTATIONAL RESISTANCE INCREASINQ FIXED SEISMIC ONLY Inactive Inacfive Acthro

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RGEOI D.PS,P,2E RGE02 D.PS,P.2E Yr RGE03 DPSP2E Eo~PS,PS RGE05 D.PS,P,2E RGE06 D PS P 2E 4.ICE+06 4.ICE+06 4.10E+06 Uncracked 0.15 Uncracked 0.15 Uncrackod 0.15 U~naa can 0

Uncrackod 0

Uncracked 0

Fixed Rxod Free Fixed 4.IOEi06 Free Fixed Free Fixed 4.10Er06 Free Rxod Free Froe 4.10E106 2E 2E 2E 3818@9 3II18O9 3a18 9

nactive Inacfive Active ixod Fixed Free Fixed 4.IOEr06 Free Rxed Free Fixed 4.(0Er06 Fice

'ixed foe roe

4. 0 i06 D,PS,P 0 PSP Flxi Fixird Fixed Fixed Fixed Fixed Fixed Fixed Rxod Fixod 4.10EI06 4.10Ei06 4.IDEr06 4.(DEr06

)JOEi06 4.10Er06 4.IDEr06 4.IOEr06 4.10Et06 0

Rober Varios Rebar Varies Rober Varies Robar Varies Rober Varios Robar Varies Rober Varios Robar Varies Robar Varios b

Var' S.,2 D,PS,P,2E D,PS,P,2E D,PS,P.2E D~PS,P~2E D,PS,P,2E D,PS,P,2E D,PS,P.2E D,PS,P,2E D PS~~P2E D,PS,P,2E D,PS,P.2E D,PS,P,2E Free Free Free Free Free Fixed Fixed Fixed Fixed hd (90-180') Fxd (72-1 804) Fxd (81-180') Fxd Fixed Free Rxod 3.00Ei01 Rxed 9.00EiOI Rxed 3.00Ei02 Fixed

'ixed Fixed Free Fixed 3.DOE+01 Fixed 9.00EiDI Fixed 3.DOE+02 Fixed F

d

,P D.PS,P D,PS,P-D.PS,P DPSP Cracked 0

Crackod 0

Cracked 0

Cracked 0

Cracked 0

Cracked 0

Cracked 0

Cracked 0

ackod 0

AcSve Acfive Acfive Acfive Active GE09 RGE10 RGE11 GE12 G

14 RGE15

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RGEIS RGE) 7 GE 1 8 D,PS,P D.PS,P D.PS,P D,PS,P DPSP Inactive Inactive Inactive Inacfive Ina cbve RGF20 RGE21 RGE22 2E 2E 2E Acfive Inactive Inactive Free Free Free Fixed Free Fixed Free Fixed Free 4.IDENT 06 4.10E+06 Uncrackod 0.15 4.ICE r06 4.ICE+06 Uncracked 0.15 4.10E<06 Robar Varios Cracked 0

GE07 f),PS, 2

2 Active Unor 2 Rixed Free Free 4.10E+06 4.10E+06 Uncracko 0.15 (I) D ~ Dead Weight PS Tendon Prestross P

60 psi Internal Prosure (2) Uner ~ Tho tangential stillness associated with the steel containment liner TABLE1 This computer model, with the listed boundary conditions and material properties, was used in a subsequent

analysis, using a combination of dead, prestress, and pressure

loads, to obtain the displacements shown on Figure 2.

DEAD LOADS PRESTRESS, AND PRESSURE STAUCTUAALIATEQAITYTEST

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ROK03 RGK05 o

ROE12 QlMg IQ W

O4 05

'x I

4 CS LLl 3 3

10 E2

.3 RADIALDISPLACEMENT (IN.)

.4 CONTAINMENTRADIALDISPLACEMENT FIGURE 2