ML18018A670
| ML18018A670 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 08/12/1983 |
| From: | Mcduffie M CAROLINA POWER & LIGHT CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| LAP-83-381, NUDOCS 8308190002 | |
| Download: ML18018A670 (7) | |
Text
REGULATOR NFORNATION,DISTRIBUTION S<<EN (RIBS)
~Ay AccessION NBR: 8308190002, DOC, DaTE: 83/08/12 NOTARIZED:
NO DOCKET 0
".f'AQ'll';SO<<u00 "S6earon 'Havris.Nucleai'ower Plant~
Uni,t ir Carolina 05000u00
."50-u01'Shearon,Havr is.Nuclear
.Power P'lant<
Uni,t 2~ Carol'ina 05000u01 AUTH~ AAME AUTHOR AFF/LIATKON MCDUFFIE g M s A ~
)cai o l ina <<Pow'er 8,'i ght>>co,,
'SCII NAME.
AECIP IDENT AFF ILIA'TION OEA fONg H'Rs
.Office of Nuc fear Reactor>>'Regulationi..oivector-SUBJEGT:
. For wavds <<vesponse<<[to Mat l s Engineering Branch <<draf~t "SKR Open Item ?76 re Reg Guide i.uB,Pos'itions C,6r,7r,'8 "8
~ 10 on ASME iCode Case allowabl'es.
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, Carolina Power & Light Company AUG 131983 SERIAL:
LAP-83-381 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 RESPONSES MATERIALS ENGINEERING BRANCH
Dear Mr. Denton:
Carol1na Power
& Light Company hereby transm1ts one orig1nal and forty copies of a response to a Shearon Harris Nuclear Power Plant Draft Safety Evaluation Report Open Item.
This response is for the Materials Engineering
- Branch, and is CP&L Open Item Number 276.
Yours very truly, LSW/tda (7670NLU)
Attachment M. A. McDuff1e Senior Vice President Engineering
& Construction cct Mr. D. Terao (NRC-MEB)
Mr. E. A. Licitra (NRC)
Mr. G. P. Maxwell (NRC SHNPP)
Mr. J.
P. O'Reilly (NRC-RII)
Mr. Travis Payne (KUDZU)
Mr. Daniel P.
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) 8308190002 8308i2 PDR ADOCK 05000400 E
FDR 411 Fayetteville Street o P. O. 8ox 1551 o Raleigh, N. C. 27602
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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 ense:
The CPGL posi.tion on Regulatory Guide 1.48 is stated below.
The SHNPP pro)ect.meets the intent of this guide as described below:
NSSS Westinghouse supplied c'omponents are designed using the stress limits and loading combinations -presented in Sections 3.9.1 and 5.2 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.
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 CD 6a and C.6b These positions are not applicable to the Shearon Harris Project.
BOP systems will not utilize ASME Code Class 2 and 3 vessels designed to ASME Section VIII, Division 1.
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 thos'e required by Regulatory Position C.8.a(1).
The emergency loading of Regulatory Position C.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.
L 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(1),
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.
J
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 3.9.3-8 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 con)unction 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 3.9.3-8.
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 670NLOlcv)