ML18018A700
| 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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NOTiES:
REGULATORYMFORMATION DISTRIBUTION "S EM.(RIDS)
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 ft 'SER Open -I-tern 276 <<re Reg j
Guide 1,48'or necting heading on,830812 l< DISTRIBUTION CODE: B001'S lCOPIES "RECEIVED L,TR B.NCL.,$ ,'SIZE;. TITLF: Licensing"Submiit ta 1: ~:PSAR/FSAR 'Amdts '.8, Re 1 ated<<Cour<<espondence 'ECIPIENT'O 'CODE/NAME NRR/DL/ADL NRR I.B3* LA INTERNALS -ELD/HDSl IE/DEPER/EPB <<36 IE/DEQA/QAB '21 'RR/DE/CEB 11 NRA/OE/EQB 13 NRR/OE/MKB 18 .NRR/OE/SAB '24 NRR/OHFS/HFEB40 NRR/OHFS/PSRB NRR/DSI/AEB 26 NRR/DSI/OPB 10 NRR/DS I/IiCSB 16 NRA/DS I/PSB 19 NRR/DSI/RSB 23 RGN2 1 1 ,1* 2 1 1 1 1 1 0 2 1 1 1 1i 1 1 1 3 <<COPIES GTTR ENCL 0 1 ~ -0 RECIPIENT. ID CODE/NAME 'NRR LB3 BC KADAMBIrP 01 IE -FILE IE/DEPER/IRB <<35 NRR/DE/AEAB NRR/DE/EHEB NRR/DE/GB'8 NRR/OK/MTEB 17 NRR'/DE/SGEB 25. NRR/DHFS/LQB i32 NRR/DL/SSPB NRR/DS I/ASB NRR/DSI/CSB "09 NRR/DSI/METB 12' RAB 22" R G.F '4 RM/ AMI/MI8 <<COPIES LTiTR ENCL< 0 -1 1 1 1 .1 e0 1 1 '2 "2 1 1 -1 1 .1 .1 0 1 1 .1 -1 .1 1 .0 1i )) EXTERNALS ACRS DM&/OSS (AMOTS) .LPOR" 03 NSXC 0.9 6 1 i 1 1 1 BNL(AMDTS ONLY;) FEME REP.DIN 39 NRC PDR '2 .NTIS 1 1-. 1 .1=i,i rTOTAL NUMBER OF 'COPIES 'REQUIRED; LTTR '53 ENCL,46 ~<< >'r" 3 H H 1 1I H 3 I
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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, LSW/pgp (7700NLU)
Attachment S.
R.
mmerman Manager Licensing
& Permits cct Mr. D. Terao (NRC-MEB)
Mr. B. C. Buckley (NRC)
Mr.
G.
F. Maxwell (NRC-SHNPP)
Mr. J.
P. O'Reilly (NRC-RII)
Mr. Travis Payne (KUDZU)
Mr. Daniel F.
Read (CHANGE/ELP)
Chapel Hill Public Library Wake County Public Library Mr. Wells Eddleman Dr. Phyllis Lotchin Mr. John D. Runkle Dr. Richard D. Wilson Mr. G. 0. Bright (ASLB)
Dr. J.
H. Carpenter (ASLB)
Mr. J.
L. Kelley (ASLB) 8S0Smoila SSOBl7 PDR ADOCK 05000400 E
0 Sg c' C
F s'
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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 3 components.
F 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 willnot 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.
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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 willbe revised in a future amendment to reflect this response.
(7 670NLULcv)