ML18018A700

Retransmits Response to Draft SER Open Item 276 Re Reg Guide 1.48,correcting Heading on 830812 Ltr

ML18018A700
Person / Time
Site:	Harris
Issue date:	08/17/1983
From:	Zimmerman S CAROLINA POWER & LIGHT CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
RTR-REGGD-01.048, RTR-REGGD-1.048 LAP-83-389, NUDOCS 8308220112
Download: ML18018A700 (6)

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1 REGULATORYMFORMATION DISTRIBUTION "S EM .(RIDS) I ACCESSION NBR 8308220112, DOC ~ DATE'3/08/17 NOTARIZED;: NO DOCKET

.FACIL:50 4b0 "Shearon'ar ris Nuclear 'Power Plantr ..Uniit-.ir <<Car ol ina: 05000400

.50 401 Shear on Har r is'-.Nuclear Power Pl anti Uni,t 2r <<Car olina 05000401 AUTH~NAME AUTHOR AFFILIATION ZIMRKRMaN,S,RE 'Carolina Power8 Light Co, RE'CIP~NAME- RECIPIENT AFFILIATION DENTONrH ~ RE Office of Nuclear 'Reector Regulationr,Director

SUBJECT:

, Rotr ansmi.ts response <<to dra f t 'SER Open -I-tern 276 <<re Reg j Guide 1,48'or necting heading on,830812 l< I DISTRIBUTION CODE: B001'S lCOPIES "RECEIVED L,TR B.NCL.,$ ,'SIZE;. j g TITLF: Li censing"Submiit ta 1: ~:PSAR/FSAR 'Amdts '.8, Re 1 ated<<Cour<<espondence 1 NOTiES: <<COPIES RECIPIENT. <<COPIES 'ECIPIENT'O 'CODE/NAME GTTR ENCL ID CODE/NAME LTiTR ENCL< NRR/DL/ADL 0 'NRR LB3 BC 0 NRR I.B3* LA 1 ~ -0 KADAMBIrP 01 -1 1 INTERNALS -ELD/HDSl 1 0 IE -FILE 1 IE/DEPER/EPB <<36 IE/DEPER/IRB <<35 1 .1 IE/DEQA/QAB '21 1 NRR/DE/AEAB e0 1i 11 'RR/DE/CEB ,1* NRR/DE/EHEB 1 1 NRA/OE/EQB 13 2 2 NRR/DE/GB'8 '2 "2 )) NRR/OE/MKB 18 NRR/OK/MTEB 17 1 .NRR/OE/SAB '24 1 NRR'/DE/SGEB 25. 1 -1 NRR/OHFS/HFEB40 1 1 NRR/DHFS/LQB i32 1 .1 NRR/OHFS/PSRB 1 NRR/DL/SSPB .1 0 NRR/DSI/AEB 26 1 1 NRR/DS I/ASB 1 NRR/DSI/OPB 10 i NRR/DSI/CSB "09 '4 1 NRR/DS I/IiCSB 16 1 1 NRR/DSI/METB 12' .1 NRA/DS I/PSB 19 1 1 RAB 22" -1 .1 NRR/DSI/RSB 23 1 1 R G.F 1 RGN2 3 RM/ AMI/MI8 .0 EXTERNALS ACRS 6 BNL(AMDTS ONLY;) 1-. '2 1 DM&/OSS' (AMOTS) 1 1 FEME REP .DIN 39 1 .1= .LPOR" 03 1 NRC PDR i NSXC 0.9 i 1 .NTIS ,i rTOTAL NUMBER OF 'COPIES 'REQUIRED; LTTR '53 ENCL,46 . 1 IF HH < W a 3 H 1I H 3 I HHFl, I" II ) "I, I if F If arjj >'r" kl H fl ~<< 'Iff n ~ I Ht4 , FHk 'I g H ~ "1 J Wjl I )lklfp,1 qk F g>>I< IIW ] 1 I If If,fl ' k,,j "Hfflj, I llfg t (II 'id 0 "H jf 'I ~ Hl WH R Hl IIH li H I $ 'k llNW ff )fH;>If gkffkk kf I I g II H l, 41)k, jj Il ff fJ.Wjjf kf P "' f w,,jf -" r jj $ 0 kjjjL ' g ') I] 0 ij I "Ik 4I"if) ' I,) ,!Wl y Ill'I ljH H R HI lj 3 II I. I Ifnlfl, lk lf l I IWF W l'k'1 W H Ji R I R (,R lf ~ ) leaf R R 3 lk R 4 I( R kk I'l I I P gk kJ $ ] Il kf ",t~ I If N F jj W Form 244 SERIAL: LAP-83-389 Carolina Power & Light Company AUG 17 19B3 Company Correspondence U Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NOS ~ 1 AND 2 DOCKET NOS. 50-400 AND 50-401 DRAFT SAFETY EVALUATION REPORT RESPONSE MECHANICAL ENGINEERING BRANCH

Dear Mr. Denton:

Carolina Power & Light Company (CP&L) hereby retransmits one original and forty copies of the response to the Shearon Harris Nuclear Power Plant Draft Safety Evaluation Report CP&L Open Item 276. This response was previously submitted to the Staff in a letter dated August 12, 1983 (Serial: LAP-83-381) under the incorrect heading, "Materials Engineering Branch."

Yours very truly, S. R. mmerman Manager Licensing & Permits LSW/pgp (7700NLU)

Attachment cct Mr. D. Terao (NRC-MEB) Mr. Wells Eddleman Mr. B. C. Buckley (NRC) Dr. Phyllis Lotchin Mr. G. F. Maxwell (NRC-SHNPP) Mr. John D. Runkle Mr. J. P. O'Reilly (NRC-RII) Dr. Richard D. Wilson Mr. Travis Payne (KUDZU) Mr. G. 0. Bright (ASLB)

Mr. Daniel F. Read (CHANGE/ELP) Dr. J. H. Carpenter (ASLB)

Chapel Hill Public Library Mr. J. L. Kelley (ASLB)

Wake County Public Library 8S0Smoila 05000400 SSOBl7 PDR ADOCK E PDR

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s Shearon Harris Nuclear Power Plant Draft Safet Evaluation Re ort en Item 276 Provide a discussion giving a more detailed justification to Regulatory Guide 1 ~ 48; Regulatory Positions C 6, C 7, C.8, and C.10.

~Res oese:

The CPSL position on Regulatory Guide 1.48 is stated below.

The SHNPP project meets the intent of this guide as described below:

NSSS Westinghouse supplied components are designed using the stress limits and loading combinations presented in Sections 3.9.1 and 5 ' for ASME Code Class 1 components. The conservatism in these limits and the associated ASME design requirements precludes any component structural failure.

The operability of active ASME Code Class 1, 2, and 3 valves and active ASME Code Class 2 and 3 pumps (there are no active ASME Code Class 1 pumps) will be verified by methods detailed in Sections 3.9.1 and 5.2 for ASME Code Class 1 components and in Section 3.9.3 for ASME Code Class 2 and F

3 components.

The use of the above stated methods provides an acceptable alternate method to meeting the guidance of this Regulatory Guide.

Balance of Plant Regulatory Positions C 6a and C.6b These positions are not applicable to the Shearon Harris Pro)ect. BOP systems will not utilize ASME Code Class 2 and 3 vessels designed to ASME Section VIII, Division l.

Regulatory Position C.7 This position is not applicable to SHNPP. BOP systems at the SHNPP will not utilize ASME Code Class 2 vesels assigned to Division 2 of Section VIII of the ASME Code.

Regulatory Position C.8.a - The allowable stress for ASME Code Class 2 and 3 piping is not exceeded although the loading combinations listed in Table 3.9.3-7 are greater than those required by Regulatory Position C.8.a(l).

The emergency loading of Regulatory Position CD 8.a(2) is addressed in Table

3. 9.3-11 ~

Regulatory Position C.8.b For the faulted loading combination, Class 2 and 3 piping designed by Ebasco will meet the stress limits provided in Table

3. 9-3-11 ~

Regulatory Position C.10.a The allowable stress for ASME Code Class 2 and 3 pumps is not exceeded although the loading combinations listed in Table 3.9.3-7 are greater than those required by Regulatory Position C.10 a(l),

except where the pump bending stresses are insignificant when compared to the membrane stresses. However, in no case will membrane stress exceed 0.75 yield stress under these conditions.

~ ~

~ ~

0 Table 3.9 ~ 3-8 specifies an allowable stress for the emergency plant condition as required by Regulatory Position C.10.a(2). See the response to Regulatory Position C.6.a above.

Regulatory position C.10.a(3) The SHNPP Table 3 '.3-8 meets the guidance of the Regulatory Guide Note ll (since pump operability will be demonstrated as discussed in FSAR Section 3.9.2), except where the pump bending stresses are insignificant when compared to the membrane stresses. Therefore, for those materials where the allowable stress is limited by yield stress rather than ultimate stress, the primary membrane stress could slightly exceed the yield stress. Under these conditions, the safety function of the pump would not be impaired.

Regulatory Positions C.ll and C.12 Class 2 and 3 system pressure and temperature design conditions are determined for normal, upset, emergency and faulted plant conditions in conjunction with specified seismic events. A valve primary pressure rating is then specified to the manufacturer which is in excess of the limiting system pressure and temperature design conditions.

Therefore, the requirements of Regulatory Guide 1.48 are met.

In addition, allowable valve stress limits for specified plant conditions and seismic loadings are specified to the manufacturer as indicated in FSAR Table 3 '.3-8. These allowable stresses are generally more restrictive than those presently proposed by the ASME Task Group on valves.

FSAR Section 1.8 will be revised in a future amendment to reflect this response.

(7 670NLULcv)