ML20080C131

Forwards Draft FSAR Page Changes in Response to Core Performance Branch Draft SER Re Specific Fuel Lift & Peak Acceleration Analysis.Results Will Be Incorporated Into FSAR Scheduled for Aug 1983

ML20080C131
Person / Time
Site:	Limerick
Issue date:	08/16/1983
From:	Kemper J PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	Schwencer A Office of Nuclear Reactor Regulation
References
NUDOCS 8308190174
Download: ML20080C131 (9)

Text

.

, .y PHILADELPHIA ELECTRIC COMPANY 2301 M ARKET STREET P.O. DOX 0699 0

PHILADELPHIA. PA.19101 (215)041 4502 vna rwassua nt August 16, 1983 Mr. A. Schwencer, Chief Licensing Branch No. 2 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

Limerick Generating Station, Units I and 2 Response to Core Performance Branch Draft Safety Evaluation Report

Reference:

E. J. Bradley to A. Schwencer letter dated July 8, 1983 File: GOVT l-l (NRC)

Dear Mr. Schwencer:

The re f e rence letter transmitted draft responses to the Core Performanae Branch Draft Safety Evaluation Report Items 2, 3, 8 and 9 concerning Fuel Rod Mechanical Fracturing and Fuel Assembly Stritetural Damage From External Forces. The results provided were preliminary evaluations consistent with the BWR 4 /5 fuel depign. The Limerick specific fuel lift and peak acceleration analysis results are now available and are contained in the attached draft FSAR page changes to be incorporated into the FSAR scheduled for August, 1983.

Sincerely,

.,d RP/

4 RJS/gra/88 Copy to: See Attached Service List Bool ifl 0308190174 830016 PDR ADOCK 05000352 E PDR

?Gk*et#FEMiWMNELMdh?NiMSMM"!dCAY3eu. .

m ee cc: Judge Lawrence Brenner (w/o enclosure)

Judge Richard F. Cole (w/o enclosure)

Judge Peter A. Morris (w/o enclosure)

Troy B. Conner, Jr., Esq. (w/o enclosure)

Ann P. Ilodgdon, Esq. (w/o enclosure)

Mr. Frank R. Romano (w/o enclosure)

Mr. Robert L. Anthony (w/o enclosure)

Mr. Marvin I. Lewis (w/o enclosure)

Judith A. Dorsey, Esq. (w/o enclosure)

Charles W. Elliott, Esq. (w/o enclosure)

Jacqueline I. Ruttenberg (w/o enclosure)

Thomas Y. Au, Esq. (w/o enclosure)

Mr. Thomas Gerusky (w/o enclosure)

Director, Pennsylvania Emergency Management Agency (w/o enclosure)

Mr. Steven P. IIershey (w/o enclosure)

Angus Love, Esq. (w/o enclosure)

Mr. Joseph II. White, III (w/o enclosure)

David Wersan, Esq. (w/o enclosure)

Robert J. Sugarman, Esq. (w/o enclosure)

Martha W. Bush, Esq. (w/o enclosure)

Spence W. Perry, Esq. (w/o enclosure)

Atomic Safecy and Licensing Appeal Board (w/o enclosure)

Atomic Safety and Licensing Board Panel (w/o enclosure)

Docket and Service Section (w/o enclosure)

LGS FSAR

( 3.9.1.4.8 Control Rod Drive Housing Supports Examples of the calculated stresses and stress limits for faulted conditions for the CRD housing supports are provided in Table 3.9-6(ac).

3.9.1.4.9 Fuel Storage Racks Examples of the calculated stresses, and stress limits for the faulted conditions for the new and spent fuel storage racks are shown in Table 3.9-6(c).

• AL- _i}

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(~ '*--2 . 0 ' 4 10 Fuel Ch:nn:fc l' j v._

7. .J ' . / taded!m c Wotll W sT V1 T E KT 0 6) THg H E47 JHGGT - -

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. n are contained in Refs 3.9-16 and 3.9-1/. 72 ^ ;- = hm //en I end fed Ib't j fr.3 $st

.s.i.4.11 Refueling Equipment Refueling and servicing equipment which is important to safety is classified under essential components, per the requirements of 10 CFR, Part 50, Appendix A. This equipment and other equipment whose failure would degrade an essential component is defined in Section 9.1 and is classified as Seismic Category I. These components are subjected to an elastic dynamic finite element analysis to generate loadings. This analysis utilizes appropriate seismic floor response spectra, and combines loads at frequencies up to 33 H2, in three directions. Imposed stresses are generated and combined for normal, upset, and faulted conditions. Stresses are compared, depending on the specific safety class of the equipment, to allowables of Industrial Codes, ASME, American National Standards Institute (ANSI) or Industrial standards, or American Institute of Steel Construction (AISC).

I 3.9.1.4.12 Seismic Category I Items Other than NSSS The stress allowables for statically applied loads, of Appendix F of ASME Section III, Winter 1972, are used for code components.

For noncode components, allowables are based on tests or accepted standards consistent with those in Appendix F of the code.

Dynamic loads for components loaded in the elastic range are calculated using dynamic load factors, time history analysis, or any other method that assumes the elastic behavior of the component.

The limits of the elastic range are defined in Paragraph 1323 of Appendix F for the code components. The local yielding due to stress concentration is assumed not to affect the validity of the assumptions of elastic behavior. The stress allowables of

( Appendix F for elastically analyzed components are used for code 3.9-27 i

l I

DRAFT l

3.8. I.'t.1o Fani Ane~bly ( T.,c.tvdins ch<nm !)

GE T5W R. 4o el a.semLly One.l J;ny e.bam,e/) ele siyn 6ve r ,

y o,n< ly 4tesi vn e% d.r , and ev<.lvr+ ion reau its , inc ladtnj lhats afpliesLIs to & Ps a l+e d con ds-4 /* < s a r e.

con 4rinst In Rch 3. % -I t. sJ 3. s - s 1 . Ev<lask~s sp o e t f.c. +a the lim e rte.k. leal a.ssenl/te.t hoe beert ferkrmed in s e e.. < J a.a. w1Ih lh* irre/LadeI,yy presen Iel in Re4 3.9-17. Th< resa ls ;n3 ace <len.it.n prohtle.> as4 feel it f + s.ww 3p ar< a.unensed 1,e Takle J.9-G(1).

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( 3.9-11 E. Wilson, and S. R. Nickell, " Application of the Finite Element Method to Heat Conduction Analysis," Nuclear Engineerino and Desion, 4 (1966).

3.9-12 E. Wilson, " Structural Analysis of Axisymmetric Solids,"

AIAA Journal, 3 (112) (December 1965).

3.9-13 P. J. Schneider, Temperature Response Charts, John Wiley and Sons, Inc. (1963).

3.9-14 Sample Analysis of a Class I Pipino System, prepared by the Working Group on Paping (SGD, ScIII) of the ASME Boiler and Pressure Vessel Code (December 1971).

3.9.15 , Not used.

3.9-16 BWR Fuel Channel Mechanical Desion and Deflection, NEDE-21354-P, General Electric Company (September 1976).

3.9-17 BWR[3fi 1 Assembly Evaluation of Combined Safe Shutdown EarEhquake (SSE) and Loss-of-CooTant Accident (LOCA)

Loadinos, NEDE-21175-7, 4.N c v c mi c: 19'i h I GeneralElectricCompany(gg,f/r f g py .

3- P 3.9-18 Assessment of Reactor Internals Vibration in BWR/4 and BWR/5 Plants, NEDE-24057-P (Class III) and NEDO-24057 (Class I), General Electric Company (November 1977).

3.9-19 Desion and Performance of G.E. BWR Jet Pumps, APED-5460, General Electric Company, Atomic Power Equipment Department (July 1968).

3.9-20 H. H. Moen, Testino of Improved Jet Pumps for the BWR/6 Nuclear System, NEDO-10602, General Electric Company, Atomic Power Equipment Department (Jun? 1972).

3.9-21 Ana'lytical Model for Loss-of-Toolant Analysis in Accordance with 10 CFR Part 50, Appendix K, NEDE-20566, Proprietary Document, General Electric Company.

3.9-22 Stress Report for the Target Rock 6 x 10 Relief Valve, Model 4 7567F; 4th Edition, McGraw-Hill, 1965.

3.9-23 Boilino Water Reactor Feedwater Nozzle /Sparcer Final Report, NEDE-21821, General Electric Co. (March 1978).

( l 3.9-97 Rev. 20, 05/83 ,

LGS FSAR $ l i

( TABLE 3.9-6 (Page 1 of 2) l LOADING COMBINATIONS, STRESS LIMITS, AND ALLOWABLE STRESSES l l

The following is a list of the tables that give the design loading combinations, allowable stresses, and calculated stresses for the major mechanical safety-related components in the plant and referenced in Section 3.9. ~

3.9-6A Load Combinations and Acceptance Criteria for ASME Class 1, 2, and 3 NSSS Piping, Equipment, and Supports 3.9-6(a) Reactor Pressure Vessel and Shroud Support Assembly l 3.9-6(b) Reactor Vessel Internals and Associated Equipment l 3.9-6(c)' Reactor Water Cleanup Heat Exchangers l 3.9-6(d) Class 1 Main Steam Piping l 3.9-6(e) Class 1 Recirculation Loop Piping l 3.9-6(f) Not Used l 3.9-6(g) Main Steam Relief Valves l 3.9-6(h) Main Steam Isolation Valve l 3.9-6(i) Recirculation Pump l 3.9-6(j) Reactor Recirculation System Gate Valves l 3.9-6(k) Class 3 Safety / Relief Valve Discharge Piping j 3.9-6(1) Standby Liquid Control Pump l 3.9-6(m) Standby Liquid Control Tank j l

3.9-6(n) ECCS Pumps l

3.9-6(o) RHR Heat Exchanger l 3.9-6(p) RWCU Pump l

3.9-6(q) RCIC Turbine l 3.9-6'r) ECIC Pump l

( 3.9-((s) Tusl Storage Racks l

Rev. 19, 04/83

1 1

' LGS FSAR l TABLE 3.9-6 (Cont'd) (Page 2 of 2) l 3.9-6(t) 'High Pressure Coolant Injection Pump l 3.9-6(u) Not Used l 3.9-6(v) Control Rod Drive Housing l 3.9-6(w) Jet Pumps l 3.9-6(x) -Net J

'ood [ge / Afjemh/g (I,3c/wdig Cha n"*IJ l 3.9-6(y) LPCI Coupling l 3.9-6(z) Not Used l 3.9-6(aa) Control Rod Guide Tube l 3.9-6(ab) Incore Housing l 3.9-6(ac) Reactor Vessel Support Equipment; CRD Housing Support 3.9-6(ad) Not Used l 3.9-6(ae) HPCI Turbine ll

(

l Rev. 19, 04/83 l

{ LGS FSAR .h TABLE 3,9-6(x)

Section (x) of this table is not used.

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