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{{#Wiki_filter:f>                         RKGULIAITOR                 VFORPIAITiION Dli S TRIBUT~IObll                 TKNI (RODS)"
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                                            @MD, Carolina Power & Light Company SERIAL: LAP     83-135 MAY  11 1983 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 CONTAINMENT SYSTEMS BRANCH
@MD, Carolina Power & Light Company MAY 11 1983 SERIAL:
LAP 83-135 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 CONTAINMENT SYSTEMS BRANCH


==Dear Mr. Denton:==
==Dear Mr. Denton:==
 
Carolina Power
Carolina Power & Light Company hereby transmits one original and forty   copies of the response to the Shearon Harris Nuclear Power Plant Draft Safety Evaluation Report (DSER) Open Item No. 59.
& Light Company hereby transmits one original and forty copies of the response to the Shearon Harris Nuclear Power Plant Draft Safety Evaluation Report (DSER)
Carolina Power @Light           Company   will be     providing responses     to other Open Items   in the DSER shortly.
Open Item No. 59.
Yours very       truly, M. A. McDuffie Senior Vice President Engineering & Construction PS/kj r    (6729PSA)
Carolina Power @Light Company will be providing responses to other Open Items in the DSER shortly.
Attachment CC:     Mr. Yun-Seng Huang (NRC-CSB)                           Mr. Wells Eddleman Mr. N. Prasad Kadambi (NRC)                             Dr. Phyllis Lotchin Mr. G. F. Maxwell (NRC-SHNPP)                           Ms. Patricia T. Newman Mr. J. P. O'Reilly (NRC-RII)                           Mr. John D. Runkle Mr. Travis Payne (KUDZU)                               Dr. Richard D. Wilson Mr. Daniel F. Read (CHANGE/ELP)                         Mr. G. 0. Bright (ASLB)
Yours very truly, PS/kj r (6729PSA)
Chapel Hill Public Library                              Dr. J. H. Carpenter (ASLB)
Attachment M. A. McDuffie Senior Vice President Engineering
Wake County Public Library                              Mr. J. L. Kelley (ASLB) 8305ihOOi7 8305ii PDR ADDCK   05000400     !
& Construction CC:
E                  PDR                                                                           goo'11 Fayettevllle Street o P. O. Box 1551 I Raleigh, N. C. 27602
Mr. Yun-Seng Huang (NRC-CSB)
Mr. N. Prasad Kadambi (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 Ms. Patricia T. Newman Mr. John D. Runkle Dr. Richard D. Wilson Mr. G. 0. Bright (ASLB)
Dr. J.
H. Carpenter (ASLB)
Mr. J. L. Kelley (ASLB) 8305ihOOi7 8305ii PDR ADDCK 05000400 E
PDR goo'11 Fayettevllle Street o P. O. Box 1551 I Raleigh, N. C. 27602


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OPEN ITEM 059:
Acceptance of the design-basis pipe break for the reactor cavity subcompartment analysis is contingent on acceptance of the mechanically constrained limit on the postulated cold leg or hot leg pipe rupture size and flow area (150 in. ).
(SEC:
6.2.1.2)


OPEN ITEM  059:
===RESPONSE===
Acceptance of the design-basis pipe break for the reactor cavity subcompartment analysis is contingent on acceptance of the mechanically constrained limit on the postulated cold leg or hot leg pipe rupture size and flow area (150 in. ). (SEC: 6.2.1.2)
TO OPEN ITEM 059:
RESPONSE  TO OPEN ITEM 059:
Westinghouse assumed a
Westinghouse assumed a 150 in. 2 rupture area when analyzing for asymmetric loads in the reactor cavity. Using this area as the maximum allowable break area, Ebasco designed the reactor vessel hot and cold leg restraints.
150 in.
Westinghouse, then, using geometric parameters from the restraints calculated the actual rupture areas of approximately 32 in. 2 for the hot leg and 90 in. 2 for the cold leg. Since these areas are enveloped by the assumed 150 in. 2 break area the reactor cavity subcompartment analysis is conservative.}}
rupture area when analyzing for asymmetric 2
loads in the reactor cavity.
Using this area as the maximum allowable break
: area, Ebasco designed the reactor vessel hot and cold leg restraints.
Westinghouse,
: then, using geometric parameters from the restraints calculated the actual rupture areas of approximately 32 in.
for the hot leg and 90 2
2 in.
for the cold leg.
Since these areas are enveloped by the assumed 150 2
in.
break area the reactor cavity subcompartment analysis is conservative.}}

Latest revision as of 05:23, 7 January 2025

Forwards Response to Draft SER Open Item 59 Re Containment Sys.Reactor Cavity Subcompartment Analysis Conservative
ML18018A528
Person / Time
Site: Harris  
Issue date: 05/11/1983
From: Mcduffie M
CAROLINA POWER & LIGHT CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
References
LAP-830135, NUDOCS 8305160017
Download: ML18018A528 (5)
v • d • e


Text

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RKGULIAITOR VFORPIAITiION DliS TRIBUT~IObll TKNI (RODS)"

r

~'CCESSION NBR: S305160017'OCt. O'ATKl3/05'/1l VOiTlARIZEO" NO F'AC<ILIs50 400 Shealr onr Halrr.is>> Vtuc'lea'r Power: P4anti U'nil ti ii

~ Carollijna<

50 401 Shee'roti Ha'rri s", VUc;ice'r P'over Pile'ntg J'ni ti 2i" C'ar olliinai AUTH ~ iV ALKI AUTHOR WFFCLIIAITKON MCOUFFCEliM'.A~.,

Ch'rolldnal Poweel

& Llighti Cbl.,

REClIPiVAi4IEI RKCIIPCKN<TI AFFLLIIATIONI DENTOrV'g H ~ R ~.

Olff ice olf< Nucl'ea'r Reabtor." Regul alta one Dlirector:

SVBVECIT': For weirds resoones tol dralf t SKR'i Ooenr Itebi 59'e Conte!jnmehti Sys.Rba'ctolr:

centi ty, subcomoartmenti a'nell ysi s: conservati ve.

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@MD, Carolina Power & Light Company MAY 11 1983 SERIAL:

LAP 83-135 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 CONTAINMENT SYSTEMS BRANCH

Dear Mr. Denton:

Carolina Power

& Light Company hereby transmits one original and forty copies of the response to the Shearon Harris Nuclear Power Plant Draft Safety Evaluation Report (DSER)

Open Item No. 59.

Carolina Power @Light Company will be providing responses to other Open Items in the DSER shortly.

Yours very truly, PS/kj r (6729PSA)

Attachment M. A. McDuffie Senior Vice President Engineering

& Construction CC:

Mr. Yun-Seng Huang (NRC-CSB)

Mr. N. Prasad Kadambi (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 Ms. Patricia T. Newman Mr. John D. Runkle Dr. Richard D. Wilson Mr. G. 0. Bright (ASLB)

Dr. J.

H. Carpenter (ASLB)

Mr. J. L. Kelley (ASLB) 8305ihOOi7 8305ii PDR ADDCK 05000400 E

PDR goo'11 Fayettevllle Street o P. O. Box 1551 I Raleigh, N. C. 27602

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OPEN ITEM 059:

Acceptance of the design-basis pipe break for the reactor cavity subcompartment analysis is contingent on acceptance of the mechanically constrained limit on the postulated cold leg or hot leg pipe rupture size and flow area (150 in. ).

(SEC:

6.2.1.2)

RESPONSE

TO OPEN ITEM 059:

Westinghouse assumed a

150 in.

rupture area when analyzing for asymmetric 2

loads in the reactor cavity.

Using this area as the maximum allowable break

area, Ebasco designed the reactor vessel hot and cold leg restraints.

Westinghouse,

then, using geometric parameters from the restraints calculated the actual rupture areas of approximately 32 in.

for the hot leg and 90 2

2 in.

for the cold leg.

Since these areas are enveloped by the assumed 150 2

in.

break area the reactor cavity subcompartment analysis is conservative.

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