ML18230A088
| ML18230A088 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 09/20/1976 |
| From: | Jackie Jones Carolina Power & Light Co |
| To: | Rusche B Office of Nuclear Reactor Regulation |
| References | |
| Download: ML18230A088 (20) | |
Text
NI(C FO>>y 106 I2 70)
U.S. NUCLI:ABBEGULATOAY 1ISSION NRC DISTRIBUTION Fon PART 60 DOCI(ET MATERIAL DOC
$0 Oo A.
0%
I'-ILE NUMOEA TO:
MR B C RUSCHE LETTEB OBIGINAL COPY NOTOAIZED UNC LASS IF I E D FROM:
CPIIL RALEXGH NC J A JONES PAOP INPUT FOAhil DATE OF DOCUMENT Q,o~gfo DATE RECEIVED
. )4 NUMOEB OF COPIES BECEIVED DE S C B IP TI0 N LTR NOTORIZED 9-20>>76 TRANS THE FOLLOWING.. ~.
ACKNOW',~gg 88 I'tITIhgg~
pLAH1 NA>E+Q~y,g~~ Q+QQAs I-Q ENCLOSU BE ENCLOSURES 1 8o 2; A COMPARISON OF SHEARON HARRXS CONTAINMENT STRUCTURIKOAD.....ENCLOS 3; A COMPARXSON OF SHEARON HARRIS CONTAINMENT INTERNAL'STRUCTURE LOAD..ENCLOSURE II; LOAD COMBINATIONS FOR SEISMIC CAT I STRUCTURES....
ENCLSOURE 5p INDEX TO POSITIONS'N CODESp S
. STANDARDS, AND REG GUIDES............
CERTAIFICATE OF SERVICE....SHOWING SVC D OF LOAD COMBINATIONS BEING SERVED UPON MR.
VASSAR P.
SHEARONp CHAIRMAN BOARD OF CTY COIIMXSSXONERS OF WAEZ COUNTY P 0 BOX 550 RALEIGHp NC ~ ~ ~ ~ ~ ~
~ ET ALo ~ ~ ~
~ ~ ~
~ ~ ~ ~ ~
SAFETY ASSXGNFD AD:
~anawr>> r>>TRv:
PROJECT MANAGER:
XC.
ASST' .'OR ACTION/INFO RMATION ASSI NFD AD ~
BRANCH CHTEF'PRO fANA
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0- OL5 1'ILE OELD INTERNALD SYSTEMS SAFETY HEXNEIIAN SCHROEDER IST R I BUT ION BENAROYA SITE gA ENV 0
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E GOSSXCK 6 STAFF'XPC CASE HANAUER I A'RLES.
PROJECT tfANAGEIfEN BOYD P
COLLINS HOUSTON PETERSON MELTZ HELTEMES SKOVIIOLT LPDR:
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ASLB:
ACILS CYS IIOLDXNG NAC FOAM 1D5 {2 70)
ENGINEERING MACCARRY KNXGHT SX1REXL p"; ~.
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REACTOR SAFE'IIY ROSS NOVAK ROSZTOCZY CHECK AT 6 I SALTZMAN RUTBERG EXTERNALDISTRIBUTION NAT LAB'FG.
VXE LA PDR CONSULTANTS XPPOLXTO KXRKWOOD OPERATXN REAC 0 S
OPERA NC' ISENII SHAO BAER BUTLER'RIMES l
> 2.~.;
BROOKHAVEN N ULRXKSON ORNI.
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CONTROL NUMBER
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~ aegutatory File Cyi 0
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- M i'> J Carolina Power 8 ight Cgmpyn Septem r 2(~~),
9 Mr. Benard C. Rusche, Director c+>
~,W ei~,
p
]O Office of Nuclear Reactor Regulation U.
S. Nuclear Regulatory Commission Washington, D.
C.
20555
'rj(
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RE:
DOCKET NOS. 50-400 50-401 50-402 AND 50-403
Dear Mr. Rusche:
As a result of recent discussions with your staff, we are enclosing the following information:
Enclosures 1 and 2; a comparison of Shearon Harris Contain-ment Structure load combinations and load factors to those of ASME/AC1 359-1975.
Enclosure 3
a comparison of Shearon Harris Containment internal structure load combinations to those of Standard Review Plan 3.8.3." ; a comparison of Sheaxon Harris load combinations for Seismic Category X structures other than Containment to those of Standard Review Plan 3.8.4. ; index to positions on codes, standards, and regulatory guides referenced'n Standard Review Plans 3.7 and 3.8.
Should you have further questions,.xegaxding this information, please contact us.
Yours very truly, JAJ/dkm Enclosures J,$, Joes Executive.Vice President Engineering, Construction
& Operation Jt
~)>>J I~ r "j'M
'~ p ~,gyc Sworn to and subscribed before ~e this 20th day of September, 1976.
Notary Public My Commission expires:
October 19, 1980 336 FayetteVllle Street
~ P. O. BOX 1551
~ Raleigh, N. C. 27602
t 1
N e
UNITED STATES OF &KRICA NUCLEAR REGULATORY COMMISSION In the Matter of
)
)
CAROLINA POWER
& LIGHT COMPANY
)
)
(Shearon Harris Nuclear Power Plant
)
)
Units 1, 2, 3, and 4)
)
Docket Nos.
50-400 50-401 50-402 50-403 CERTIFICATE OF SERVICE This is to certify that a copy of the letter dated September 20, 1976, to Mr. Benard C. Rusche from Mr. J.
A. Jones regarding Shearon Harris Nuclear Power Plant structure load combinations has this 20th day of September been served upon the following government officials by deposit of the same in the United States mail addressed as follows:
Mr. Vassar P.
- Shearon, Chairman Board of County Commissioners of Wake County Post Office Box 550 Raleigh, North Carolina 27602 Mr. Ben Wimberly, Chairman Board of County Commissioners of Chatham County Post Office Box ill Pittsboro, North Carolina 27312 Office of Intergovernmental Relations 116 West Jones Street Raleigh, North Carolina 27603 Mr. Dave Hopkins Environmental Protection Agency
'1421 Peachtree
- Street, N. E.
Atlanta, Georgia 30309 A copy of this letter has also been served this day upon each member of the Atomic Safety and Licensing Board, and other appropriate NRC personnel by deposit of the same in the United States mail'ddressed as follows:
5
Ivan W. Smith, Esq.
Atomic Safety and Licensing Board Panel U. S. Nuclear Regulatory Commission Washington, D.
C.
20555 Mr. Glenn O. Bright Atomic Safety and Licensing Board Panel U.
S. Nuclear Regulatory Commission Washington, D.
C.
20555 Dr. J.
V. Leeds, Jr.
Post Office Box 941
- Houston, Texas 77001 Mr. Nathaniel H. Goodrich, Chairman Atomic Safety and Licensing Board Panel U. S. Nuclear Regulatory Commission Washington, D.
C.
20555 Secretary U.
S. Nuclear Regulatory Commission Washington, D.
C.
20555 Attention:
Chief, Public Proceeding Staff Mr. Thomas S. Erwin Post Office Box 928 115 West Morgan Street Raleigh, North Carolina 27602 Mr. C. A. Barth Regulatory Staff Counsel U.
S. Nuclear Regulatory Commission Washington, D. C.
20555 Jesse C. Brake, Esq.
Department of Justice Post Office Box 629 Raleigh, North Carolina 27602 Richard E. Jones Associate General'ounsel Carolina Power 6 Light Company Business Address:
336 Fayetteville Street
- Raleigh, N. C.
27602 Business Telephone:
Area Code 919 828-8211 Dated:
September 20, 1976
ig
ENCLOSURE (1)
ASHE/AC1, 359-1975 EDXTXON TABLE-3230-1 LOAD COfllBlb!Al'lOPJS AND LOAD FACTORS O
L P
P>>
Pe T>>
To Te Eo F~
W W>>
ffo
>>in Rc 'c Hh>>.=.
Category Service:
Test 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1 0
~
~
~
~
~
~
~ ~
~
~ ~ ~
Construction Normal
~
h
~ ~
1.0 1.0 1.0 1.0
~
~
~
1 0
~ ~,
~
~
~
1.0...
1.0 Severe environmental h
e Factored:
1.0, 1.0 1.0 '........
1.0
'I.O 1.0 1.0......
~..
'l.o 1.0
~
~ I
~
~ ~
1.0 1.3~
1.0 1.0 1.3 1.0 1.0 1.0 1.0 1.0 1.0 1.0 Severe environmental 1.0 1.0 1.0
~
~
~
1 0 1.0 1.0 1.0
'I.O h
~
~
1.5 I
I
~
~
~
~ h 1'.0 1.0 1.0 Extreme environmental 1.0,...
h
)
h I
~
~ ~ ~
Abnormal h'bnormal!Seve'rcenvironntental 1.5 1.0 1.25...
1.25..:
1.0 1.25...
1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0
~
~ ~ }I h
~
~ ~
~ ~ ~
1.0 1.25 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0
~
h 1.25 1.0 1.0
~
~.
1.0
~ ~
h
~
~
Abnormal}Extrcme environmental 1.0 1.0 1.0 1.0 1,0 1.0......
1.0
,}I...'
NOTE:
~
~W'>>'1) Includes all tcn>potary construction toe<ling during and after construction of containmcnt.
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ENCLOSURE (2)
, 2.
l k
ji 30 4.
CONTAINMENTSTRUCTURE LOAD COMBINATIONS AND LOAD FACTO,RS Test Pressure C = (1.0+ 0.05) D + 1.OPT+ 1.08+'-'1.0S r
Normal Operating C = 1.5 (D + To + TLo) + 1.8L'+ 1.08 + 1.OS Non-Accident Pressure C = (1.0 +.05) (D + To + TLo) + 1.25IN (or IP) + 1.08 + 1.OS Operating Basis Earthquake C = (1.0 + 0.05) (D + To + TLo) + 1.25E + 1.08 +
1.QS'.
, 6.
." 7 Hurricane C = ('I.'0 + 0.05) (D + To + TLo) + 1.25Hu + 1.08 + 1.OS Design Basis Earthquake C = (1.0 + 0.05) (D + To + TLo) + 1.OE' 1.08 +
1.OS'ornado C = (1.0 <<0.05) (D + To + TLo) + 1.0W + 1.08 + 1.OS 8.
k 9
Loss Of Coolant Accident C = (1.0 + 0.05) D + 1.5P + 1.0 (T" + TL") + 1.08 + 1.OS Loss Of Coolant Accident With OBE C = (0.0 + 0.05) D + 1.25P + 1.0 (T,'
TL') + 1.25E + 1.08 +
1.OS'0.
Loss Of Coolant Accident With Hurricane C = ('I.O + 0.05) D + 1.25P + 1.0 (T'+ TL') + 1.25 Hu + 1.08 + 1.OS k
, 11.
Loss Of Coolant Accident With DBE C = (1.0 + 0.05) D + 1.OP + 1.0 (T + TL) + 1.OE' 1.08 +
1.OS'ote:
'Buoyant force and earth load are to be included only when they increase net load on section; omitted when they decrease net toad on section.
1t lt
LOAD COMBINATION DOCUMENT SHNPP - PSAR NRC - SRP 3.8.3 NORIlAL OPERATING NORMAL SHUTDOVN OPER. BASIS EARTHQUAKE PLUS NOIL OPERATING OPER.
BASIS EARTHQUAKE PLUS NORMAL SHUTDOWN C
1.5 (D + L' T) + 1.8A C= 1.5 (D + L' T + F) + 1.8L C~ 1.25 (IH.L' T + A + E).
C~.9 (D+L') + 1.1E + (1.0+0.1)
(%+A)
C~ 1. 25 (IH-L'+T+F+E)
C
~ 9 (IHL'+F) + 1.1E + (1.0+ 0.1)
T U= 1.4D + 1.7L U
.75 (1.4D + 1.7W1.7T.+ 1.7Ro)
Not given as a load combination U~ 1.4D + 1.7L + 1.9E U
~ 75 (1.EN.1.7L+1.9E+1
~ 77o.+
1 7Ro) ~
Not given as a load combination PLUS NORIlAL OPERATING C~ (1.0+.1)
(DI.T + L' A) +1.0E'~
D + L + To + Ro-W E' C
DBE PLUS NORMAL SHUT DOWN C~ (1.0 +.1)
(D + T+L'F) +1.0E'ot given as a load combination ACCIDENT C
(1.0 + 0.1)
(D+T) + 1.5P + 1.25(L'+M)+A+Q U
IH-17fTa + Ra + 1.5 Pa ACCIDENT PLUS OBE ACCIDENT PLUS DBE C~ (1.0 +.1)
(IH-T) + 1.25(PBf+L'+E) + A+
C~ (1.0+
~ 1)
(IH.T+L'+A) +1.0, (P+E'+M+Q)
U~ IH.L+Ta+Ra+1.25 Pa+1.0Q+1.25E U~ IH-Isl-Ta+Ra+1.0Pa + 1.0Q + 1.0E'
J
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Enclosure (4)
LOAD COMBINATION DOCUMENT SHNPP PSAR NRC SRP 3. 8. 4.
NORMAL OPERATING C= 1.5 (D+L'4T) + 1.8 (L+A) + 1.0B + 1.8S U= 1.4 (D+B) + 1.7 (L+S)
U=.75
[1.4(D+B) + 1.7(L+S+To+Ro)]
OPERATING BASIS EARTHQUAKE C= 1.25 (D+L'+L"+A+E+S'+T) + 1.0B C=.90 (D+L'+L") + 1.1 (T+E) + 1.0S' 1.0B U= 1.2(D+B) + 1.9E U= 1.4 (D+B) + 1.7 (L+S) + 1.9E U=.75
[1.4(D+B) + 1.7(L+S+To+Ro)+1.9E]
HURRICANE C= 1.25 (D+L'+L"+A+Hu+T) + 1.1S + 1.0B C=.90 (D+L'+L") + 1.1 (S+T+Hu) + 1.0B U= 1.2 (D+B) + 1.7H U= 1:4 (D+B) + 1.7 (L+S+N)
U=.75
[1.4(DI.B) + 1.7(L+5+I7I.T<rlRo)]
TORNADO C= (1.0+.1)
(D+L'+L"+A+S+T) + 1.0 (W+N-B)
U= D+B+L+S+To+Ro+H DESIGN BASIS EARTHQUAKE C= 1.0 (D+L'+L") + 1.0 (A+E'+S'+B+T)
U= D+B+L+S+To+Ro+E PIPE OR EQUIPMENT ACCIDENT C= (1.0+.1)
(D+L'+L"+S) + 1.0B + 1.5PA + 1.0 (A'+TA,)
U= D+B+L+S+Ta+Ra+1.5Pa PIPE OR EQUIP.
ACCIDENT PLUS OBE C= 1.0 (D+L'+L"+TA,+A'+S'+B) + 1.25PA, + 1.0Q + 1.25E U= D+B+L+S+Ta+Ra+1.25Pa+1.0Q+1.25E PIPE OR EQUIP.
ACCIDENT
'PLUS DBE C= 1.0 (D+L'+L"+TA,+A'+S'+B) + 1.0PA, + 1.0Q '+ 1.0E'=
D+B+L+S+Ta+Ra+1.0P +1.0Q+1.0E' LEGEND:
Q= Y
+ YJ + YM r
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~
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CI I
~
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ENCLOSURE (5)
INDEX TO POSITIONS ON CODES, STANDARDS AND REGULATORY GUIDES REFERENCED IN STANDARD REVIEW PLANS 3.7 AND 3.8 SRP 3.7 PSAR PAGE NO.
3.7.1 3.7.4 3.8.1 R.
G. 1.60 R.
G. 1.61 R.
G. 1. 12 SRP 3.8 ASME/ACI 359 R.
G. 1.70 R.
G. 1. 10 R.
G. 1. 15 R.
G. l. 19 R.
G. l. 55 R.
G. 1.18 R.
G. 1.35 See Page 1.4 30 See Page 1.4 31 See Page 1.4 12 See Enclosures 1 and 2
FSAR will meet 1.70 format and content where possible See Page 1.4 ll See Page 1.4 12 See Page 1.4 13 See Page 1.4 29 See Page 1.4 12A Does not apply to SHNPP See Page 1.4 17 3.8. 2 3.8.3 ASME Sect.III, Div. I
'ubsection NE R.
G. 1.57 R.
G. 1.70 I
ASME Sect.III, Div. I Subsection NF ACI 318-71 AISC Specification ASME/ACI 359 ASME Sect. III, Div.I Subsection NE R.
G. 1.55
'NSI N45.2.5 Does not apply to SHNPP See Page 1.4 - 29 FSAR will meet 1.70 format and
'content where possible Equipment was ordered
& purchased prior to implementation of Subsection NF See Page 5.5-1 See Page 5.5-1 And Section 3.1.2, Page 5E-4a
.See Enclosures 1
6 2
Not applicable no portions of internal containment structure are of steel frame design
. See Page 1.4 29 See R.
G. 1.94 Position on Page 1.4 -51
+The personnel air locks, equipment hatch, valve chambers, and components of each shall be designed in accordance with the ASME Code,Section III, Class MC, Subsection NE.
0
~
~
4 1
~ ~
~.
3.8.4 3.8.5 R.
G. 1.70 R.
R.
ASME/ACI 359 R.
G. 1.70 FSAR will meet 1.70 format where possible Does not apply to SHNPP See Page 1.4 29 See Page'.5-1 See Page 5.5-1 and Section Page 5E-4a FSAR will meet 1.70 format where possible See Page 5.5-1 See Page 5.5-1 and Section Page 5E-4a See Enclosures 1 and 2
FSAR will meet 1.70 format where possible and content 3 ~ 10 2$
and content 3.1.2, and content
ya we 4
4