.y.

,

.

.

PHILADELPHIA ELECTRIC COMPANY2301 M ARKET STREET

P.O. DOX 06990

PHILADELPHIA. PA.19101

(215)041 4502

vna rwassua nt.. ....... .. ....."'" August 16, 1983

Mr. A. Schwencer, ChiefLicensing Branch No. 2Division of LicensingU. S. Nuclear Regulatory CommissionWashington, D.C. 20555

Subject: Limerick Generating Station, Units I and 2Response to Core Performance BranchDraft Safety Evaluation Report

Reference: E. J. Bradley to A. Schwencer letter datedJuly 8, 1983

File: GOVT l-l (NRC)

Dear Mr. Schwencer:

The re f e rence letter transmitted draft responses to theCore Performanae Branch Draft Safety Evaluation Report Items2, 3, 8 and 9 concerning Fuel Rod Mechanical Fracturing andFuel Assembly Stritetural Damage From External Forces. Theresults provided were preliminary evaluations consistent withthe BWR 4 /5 fuel depign. The Limerick specific fuel lift andpeak acceleration analysis results are now available and arecontained in the attached draft FSAR page changes to be incorporatedinto the FSAR scheduled for August, 1983.

Sincerely,

.,d RP 4/

RJS/gra/88

Copy to: See Attached Service List

Boolifl

0308190174 830016PDR ADOCK 05000352E PDR

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

*. _ _ -

eem

.

.

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 faultedconditions for the CRD housing supports are provided inTable 3.9-6(ac).

3.9.1.4.9 Fuel Storage Racks

Examples of the calculated stresses, and stress limits for thefaulted conditions for the new and spent fuel storage racks areshown in Table 3.9-6(c).

Fuel Ch:nn:fc l' j v._ AL- _i}g_u, e ,-.*(~ '*--2 . 0 ' 4 10

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

i~

.........., ..... .re... - sv wue tou2 Leoi ...

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 isclassified under essential components, per the requirements of10 CFR, Part 50, Appendix A. This equipment and other equipmentwhose failure would degrade an essential component is defined inSection 9.1 and is classified as Seismic Category I. Thesecomponents are subjected to an elastic dynamic finite elementanalysis to generate loadings. This analysis utilizesappropriate seismic floor response spectra, and combines loads atfrequencies up to 33 H2, in three directions. Imposed stressesare generated and combined for normal, upset, and faultedconditions. Stresses are compared, depending on the specificsafety class of the equipment, to allowables of Industrial Codes,ASME, American National Standards Institute (ANSI) or Industrialstandards, or American Institute of Steel Construction (AISC).

I3.9.1.4.12 Seismic Category I Items Other than NSSS

'

The stress allowables for statically applied loads, of Appendix Fof 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 arecalculated using dynamic load factors, time history analysis, orany other method that assumes the elastic behavior of thecomponent.

The limits of the elastic range are defined in Paragraph 1323 ofAppendix F for the code components. The local yielding due tostress concentration is assumed not to affect the validity of the

( assumptions of elastic behavior. The stress allowables ofAppendix F for elastically analyzed components are used for code

3.9-27

i|

I

,

'

.

DRAFT|

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~ssp 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 |h* irre/LadeI,yypresen Iel in Re4 3.9-17. Th< resa ls ;n3 ace <len.it.n

s.wwprohtle.> as4 feel it f + 3p ar< a.unensed 1,e

Takle J.9-G(1).|

.

4

.

.

}r1

|| \

l

|

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

DRAFT !~

'

m, ,,,

( 3.9-11 E. Wilson, and S. R. Nickell, " Application of the FiniteElement Method to Heat Conduction Analysis," NuclearEngineerino 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 Wileyand Sons, Inc. (1963).

3.9-14 Sample Analysis of a Class I Pipino System, prepared bythe Working Group on Paping (SGD, ScIII) of the ASMEBoiler 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 ShutdownEarEhquake (SSE) and Loss-of-CooTant Accident (LOCA)Loadinos, NEDE-21175-7, GeneralElectricCompany(gg,f/r f g py.

4.N c v c mi c: 19'i h I .

3- P3.9-18 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 EquipmentDepartment (July 1968).

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

3.9-21 Ana'lytical Model for Loss-of-Toolant Analysis inAccordance 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 FinalReport, NEDE-21821, General Electric Co. (March 1978).

( l

3.9-97 Rev. 20, 05/83,

_ - _ _ _ _ _ . . .-.

LGS FSAR $ |

i

( TABLE 3.9-6 (Page 1 of 2) |

LOADING COMBINATIONS, STRESS LIMITS, AND ALLOWABLE STRESSES|

|

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

,

3.9-6A Load Combinations and Acceptance Criteria for ASMEClass 1, 2, and 3 NSSS Piping, Equipment, andSupports

3.9-6(a) Reactor Pressure Vessel and Shroud Support Assembly |

3.9-6(b) Reactor Vessel Internals and Associated Equipment |

3.9-6(c)' Reactor Water Cleanup Heat Exchangers |

3.9-6(d) Class 1 Main Steam Piping |

3.9-6(e) Class 1 Recirculation Loop Piping |

3.9-6(f) Not Used|

3.9-6(g) Main Steam Relief Valves |

3.9-6(h) Main Steam Isolation Valve |

3.9-6(i) Recirculation Pump|

3.9-6(j) Reactor Recirculation System Gate Valves|

3.9-6(k) Class 3 Safety / Relief Valve Discharge Piping j

3.9-6(1) Standby Liquid Control Pump |

3.9-6(m) Standby Liquid Control Tank|

j

3.9-6(n) ECCS Pumps|

3.9-6(o) RHR Heat Exchanger|

3.9-6(p) RWCU Pump|

3.9-6(q) RCIC Turbine|

3.9-6'r) ECIC Pump|

( 3.9-((s) Tusl Storage Racks|

Rev. 19, 04/83

___ _____ - _______ _ ___

11

' LGS FSAR |

' TABLE 3.9-6 (Cont'd) (Page 2 of 2) |

3.9-6(t) 'High Pressure Coolant Injection Pump |

3.9-6(u) Not Used |

3.9-6(v) Control Rod Drive Housing |

3.9-6(w) Jet Pumps |

3.9-6(x) -Net 'ood [ge / Afjemh/g (I,3c/wdig Cha n"*IJ |J

3.9-6(y) LPCI Coupling |

3.9-6(z) Not Used |-

3.9-6(aa) Control Rod Guide Tube |

3.9-6(ab) Incore Housing |

3.9-6(ac) Reactor Vessel Support Equipment; CRD HousingSupport

3.9-6(ad) Not Used |

3.9-6(ae) HPCI Turbine

||

(| Rev. 19, 04/83|

. - ___ - ____________ _______ ___ _ ._

_ _ _ _ _ _ _ _ _ _ _ _ .

.

{ LGS FSAR .h

TABLE 3,9-6(x)

Section (x) of this table is not used.

NS6$(

[ DLLOco w G gggg7

7ABce 3. s - c, cyj

|

_=. . .. . . . .

- - ______ _

e . . . ,- , , . , ,

, . # ". -._ - _u ! - , .

ii' 10 ( d 'i l i !' i 0.-

! t.I{.''j~

. . . .-- :-

F'

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I' I',!:!|| !! i f ! :l' i- i ' j f || |, |g- '[jj !j ' ;. ..i ! j g- . . .'

-

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1 .

i|j j/63 F M ; |I4 4 .: : ,

,, i,,. a ,

[ j l' Ii ! i I <

t M | 1! i- t

i TABE:: 3.9 4A)_ j.

Irurt, AssEdLtj (1ktutiNc cmuuttt.'; . q , i . g g. in.o u . i iH: 'M,1 . ! . ; u .! . i!

'

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ti P

itjMii,

;.

h(,. ' r ., i .

.

|I h| . I f |iIIll Il !)Ij Phk ' Evalat8a* 8881E' ' ~

! i [ Prhkiry Lop fype _ geeletalfon. I _' Accelefat{pa''-iAcceptaece Criteria 1.oad in r ; , ' ,

.

j j j!---

AccdlerationEpy;[ elopeit'orizontal,Directio;n: Morizontal.Acheleration 2. (, Cr t 3,(,@ f| f j.- . -i i-

;

qirj)r,p|; 33j q;y pt|V:!-P|lr a r gi ;' '

i4 [f J iPeakPnes[soeI G I- s L l..d '!. Ii$u,';|f |i

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ii l !! is h' r, i ]il j-|! [: j!|}!

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f 2.(,i Vert est Accelerati6es n.o Gi et . ir .,

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' ! 'J1 |i' { l iifkI 'I', {'Lt !b'2/ .ShN Shidd'dE K ri:k4dke

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nores | | gThe evalmadian basis. ..

(t) Evaluation Basis deelerations andEvaluations are concained in NEDE-2ti?5i3-P,

|, ,syceleration envelbpe'is' de. fined by 's coincident SC vertical acceleration with the 3.6C hErdzeital ~

~

r 'k;heceleraylon, Thi'3.'6C horiiontal value'is dadsced 11ncirly to sere'as'the corfesponding vittical.-

~,

; . | ?, ~ i - ---ij sbeeleratioWji re;tised]freii 8 ;teil2 f's.!! ' , ;, - ]I:. ! [ i: j- d i; .J: ~*t''

1 -

tif1's $a i Ahp tiI1 ! Say aw e m uaitu s e n :a 's, d Ley U.'5 'sdupe anei n euw uw1 s we.w,i==={! 2) t t

m injg p: .j 1; p rr; p w . o t .m-

mpirigaiemaang-

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hfe t ihdl ths,tb N b nN#di .iic a h.r): iIaMNlit(I$ w w i # m .ns % # . c e o p p % . g w ;y ia vt. th, ,-

1 sh : i a p .-4

.

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - ____ __ _ _ _ _ - _ _ _ _ _ _ _ -