ML18018A687
| ML18018A687 | |
| 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 | |
| NUDOCS 8308190243 | |
| Download: ML18018A687 (7) | |
Text
REGULATORY FORMATION DISTRIBUTION,'S EM ('RIDS)
DOCKET 8¹ 05000400
~05000401 05000402-05000403 NOTES:
CE'SSION NBR; 8308190243 DOC ~ DATE'3/08/12 NOTARI'ZED:
NO FACIL:50 400 'Shearon Hanr i's Nuclear Power.Planti Uni,t ii <<Carol.i.na 50 401 'Shear on Harris Nuclear Po~er Plantr Unit 2g Carolina 50 402 'Shearon Harriis Nuclear 'Power Planti Unit 3< 'Carol=ina
'50 403 Shear on Harris Nuclear Power Planti Unit 4p <<Carolina AUTH~ NAME AUTHOR AFFILIATION MCDUFFIErM~'A ~
'Carolina Power,8 Light <<Co, "RBCIP,'NAME RECIPIENT AFFILIATION DKNTONiH<RS
.Office of Nuclear
<<Reactor Regulationr,Director
SUBJECT:
For wards r esponse;to Structur.'al 'Engineer jng Branch draft 'SER Open Item'5 r e structural <<effect of cancelation of Units >3 8
4>Details 8, revised FSAR figures will be submi,tted as FSAR
~amend
- in Sept.
OISTRI8UTION iCOOE: '8001S COPIES iRECEIVEO:L'TR J.'NCL.
I, SIZE<<
TITLE: Licensing Submi.ttal:
PSAR/FSAR Amdts 8, Related -Correspondence RECIPIENT IO CODE/NAME, NRR/DL/ADI.
NRR LB3 LA LICITRAiM~
01 INTERNAI s ELD/HDS1 IE'/DEP ER/EBB '36 IE/DEQA/QAB 21 NRR/DE/CEB ii NRR/DE/EQB 13 NRR/DE/MEB 18, NRR/DE/SAB
'24 NRR/DHFS/HFEB40, NRR/DHFS/PSRB
.NRR/DSI/AEB
'26 NRR/DSI/OPB.
10 NRR/DSI/ICSB ib NRR/OS I/PSB 19 NRR/DSI/RSB
'23.
'GN2 EXTERNALS ACRS 41<<
DMB/OSS (AMDTS)
0 1
0
<<3 1
1 1
2
'2 1
1 1
1 1
1 1
1 1
-1 1
1 1
1
,1 1
3
,6 6
1 1
1 1
1
'RECIPIENT ID CODE/NAME NRR L",B3 BC KADAMBIr'P
-01=
IE FILE.
IE/DEPER/IRB "35 NRR/DE/AEAB NRR/DE/EHEB NRR/DE/GB 28 NRR/DK/MTEB 17
- NRR/DE/SGEB 25 NRR/DHFS/LQB 32 NRR/DL'/SSPB NRR/DS I/ASB NRR/DSI/CSB 09 NRR/DS I'/HETB. 12 B
22 L..
04 RH/DDAMI/MI8 BNL(AHDTS ONLY)
FEMA REP DIV "39 NRC PDR 02'TIS tCOPIES L'PTR ENCL 1
0 1
1 1-, 1<>>
O ili I'e( k>>
((
- qgV,
'l
~
~
g Pfl1( I 1>> I nfl
>>I )f(>(I I
I I
I gt((le,)[trt c)'ll I t-y>>(PH I>>
,I I
l fHrf t(I)(e
'(1 19 I >>'H '>>>>
I I
0
'Itw l
e j'W I il N
tf l)g I, 'll ef I I
I I) e,'f I II H l(
I til fe 'I 1(i Ih, il 'I'l (ft g;I ff
)I I
le (Ie ef lf, f
f(~),
I I
)J>>jO l(t ig i(('i, ')
f A
ffH)I ff (y Ie I
I 1
I 0 ef
~>>>>
If f g
T p
gg)Qg, Carolina Power & Light Company AUG 13 3983 SERIAL:
LAP-83-380 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
STRUCTURAL ENGINEERING BRANCH
Dear Mr. Denton:
Carolina Power
& Light Company hereby transmits one original and forty copies of a response to a Shearon Harris Nuclear Power Plant Draft Safety Evaluation Report Open Item.
This response is for the Structural Engineering Branch Open Item No.
5 relating to the structural effect of the cancellation of Units 3 and 4.
Details and revised Final Safety Analysis Report (FSAR) figures will be submitted as an FSAR Amendment in September.
Yours very truly,
~
~
'. A. McDuffie Senior Vice President Engineering 5 Construct'ion LSW/cfr (7669NLU)
Attachment CC; Mr. S.
B. Kim (NRC-SEB)
Mr. E. A. Licitra (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)
)Ii 8308i90243 8308i2 PDR ADOCK 05000400 E
PDR 411 Fayettevllle Street o P. O. Box 1551 o Raleigh, N. C. 27602
~
/tH
Shearon Harris Nuclear Power Plant Draft Safety Evaluation Report Open Item 5 (FSAR Section 3.8 NRC Question 220.2)
The question addresses the effect of cancelling Units 3 and 4 on Units 1 and 2
from a structural design point of view.
For example, wind and tornado-missile loads on the containment building may have changed.
To date, the staff has received inadequate response.
~Res ense Design changes to the SHNPP configuration as a result of cancellation of Units 3 and 4 have been completed.
Changes to the Seismic Category I structures have been evaluated to assure continued compliance with the design basis as set forth in the FSAR.
A number of structures were eliminated in their entirety, since they were seismically independent structures on which construction has not yet been started.
These include:
Unit 3 and 4 Containment Buildings Unit 3 and 4 Reactor Auxiliary Buildings Unit 3 and 4 Tank Building Unit 3 and 4 Diesel Generator Building A number of seismic category one structures were completed as designed, even though they were common facilities.
Completion was the most practical solution where significant construction had already taken place, and where a
change in seismic response to installed equipment for Units 1 and 2 could result from a revised configuration.
These structures include:
Fuel Handling Building Diesel Generator Fuel Oil Storage Building Emergency Service Water Screening Structure Waste Processing Building One additional change was required by the deletion of Units 3 and 4.
The west side of the Fuel Handling Building and Waste Processing Building had previously been protected by the now deleted buildings.
As a result of their new exposure, all of the doors and penetrations in the west wall will be sealed or missile protected as needed.
In addition, a seismically designed retaining wall is being constructed adjacent to the west wall to ensure these structures are not exposed to earthen pressures or soil structure interactions not accounted for in their seismic design.
The Emergency Service Water/Cooling Tower Intake Structure was the only Class I building to be redesigned.
The north wall of the 3/4 side of the structure was built in its entirety; the remaining portion of this side of the structure was constructed from Elevation 190 MSL to 223 MSL.
The design changes considered building stabili,ty as well as stiffness to maintain a
consistent seismic response for the Unit 1/2 side equipment.
(7669NLU cfr)
OIL%EL FutL OIL UIELOA
~ Ab Q '."
/5 9~
T '/bJ Q LTHb Q PRAb g T'1 1
~
~
1 E
- Erg TE
~
.,'I ~-
CATLOOltf I bUILDIHQ4 PLEI HT l6LANO ccrrETAIHMKHT bUILDIHQ RIACTOR AUTEILIARTbUILOI~
run. xAr OLIHa $ UrELoAowa bAT bUILDIH4 wA'IITK lraocK551Hd bUILPIH4 Dll5lL 4lHIRATPC bUILPIH4 TANX bUILDII a OILS!L FURL OII %1OR*dt Tax bUILDIHS DKl'0+lC AT CCib
- b frxb WPbg r 04'x bg C
3 r
.:: LEtotog Et1EKcEtkY oEKYK.E IJRfEK
~mt46 5]kUQUKE, fuqfc~i EHGQ olcv aEMcE wKKlaeug f~ HNNr alx0c1'UK Ab rrt4$
QRAb I.g r.
Mo rt.i',
~ ~ I l,.
~'
~ ~
I Loth I EI'RAb ig LTD b Q Lcm IWt.bg Pa g PP*b g LTxb Ql gc.D o0imC mMCD
--6K' mltLDl4 ~oHp cfcDm txsv,O orAVeUimdc, HnbiFlm
~ ~
gumJ QC~CTJO 6REEM, "
e 'LIl f
~"
ceN6E