GO2-83-855, Forwards Response to FSAR Question 110.44 in NRC .W/One Oversize Drawing.Aperture Card Is Available in Pdr.Response W/O Encl
| ML17277A857 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 09/21/1983 |
| From: | Sorensen G WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17277A858 | List: |
| References | |
| GO2-83-855, NUDOCS 8309300257 | |
| Download: ML17277A857 (20) | |
Text
REGULATORYIYFORMATION DISTRIBUTION SlEM (RIBS)
ACCESSION NBR!8309300257 DOC ~ DATE: 83/09/21 NOTARIZED; NO FACIL;50 397 lfPPSS Nuclear Pr ojecti Unit
?E Nashington'ublic Powe
'AUTH BYNAME AUTHOR AFFILIATION SORENSENrG.CD l<ashington Public, Power Supply System RECIP ~ NAME RECIPIENT AFFILIATION SCH4ENCER,A, Licensing Branch 2
SUBJECT:
Forwards response to FSAR Question 110 ~ 04 in NRC 830803 l tr ~ H/one oversize drawing. Aperture Card is available in PDR ~
DOCKET 0'5000397 I
DISTRIBUTION CODE: Bools COPIES RECEI TITLE: Licensing Submittal:
PSAR/FSAR
.NOTES:
REC IPIENT COPIES ID CODE/NAME LTTR ENCL NRR/DL/ADL 1
0 NRR LB2 LA 1
0 RECIPIENT ID CODE/NAME NRR LB2 BC AULUCKER~
01 COPIES LTTR ENCL 1
0 1
1 VED: LTR ENCL SIZE:.
Amdts 8, Related Correspondence INTERNAL: ELD/HDS2 IE/DEPER/EPB 36 IE/DEQA/QAB 21 NRR/DE/CEB 11 NRR/DE/EQB 13 NRR/DE/MEB 18 NRR/DE/SAB 2Q NRR/DHFS/HFEBGV NRR/DHFS/PSRB NRR/DS I/AEB 26 NRR/DSI/CPB 10 NRR/DSI/ICSB 16 NRR/DSI/PSB 19 NRR/DSI/RSB 23 RGN5
'EXTERNAL~
ACRS 1
DMB/DSS (AMDTS)
LPDR 03 NSIC 05 1
0 3
1 1
1 1
2 2
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
3 3
6 6
1 1
i 1
c~'.
IE F ILE IE/DEPER/IRB 35 NRR/DF/AEAB NRR/DE/EHEB NRR/DE/GB 28 NRR/DE/MTEB 17 NRR/DF/SGEB 25 NRR/DHFS/LQB 32 NRR/DL/SSPB NRR/DS I/AS8 NRR/DS I/CSB 09 NRR/DSI/METB 12 NRR/DSI/RAB 22 0/4 RM/DD
/MI8 BNL(AMDTS ONI Y)
FEMA~REP DIV 39 NRC PDR 02 NTIS 1
1 1
1 0
1 1
2 2
1 1
1 1
1 1
0 1
1 1
.1 1
1 1
1 1
1 0
1 1
1 1
i 1
-1
'TOTAL NUMBER OF COPIES REQUIRED:
LTTR 53 ENCL 06 I
"1 f')'f1>>
i>>
$ >> 4')f<<i~
'i)r '<<fr, wf 7
>> f l 'l ii N )I I 4 ii I 4.I 'li j
)41<
i 1,
'1 f 4>>fi 4 ii" >>
~
N ~
III Iw,', ~4)ih NJ
~
i
)I Ii I,I llw>>'
7rfk)<<4
<<$i 7 N)i w,N>>
II INN.)<<
F N.<<<<fan <<
l r>>NN<<4>>'<<rp "e "(1 Nff
- i.'1l
'4<<i,fr>> I'<<
>>'1 N )IN wit
>>f i~ fw
<< I '
)4II r',)I 7 <<N")I,N "li X
4 1
q'Iy,i t
.I II' II 4 'll+
1 Ih e
t l
e l
i
!l e
e
,4, 7
,j>>w<<,<
', Ng
',,W)W pi', )I~
<>
<<l) ll 3 INI Jt e
k
<<'N>>,i 9<<',
UY
)
I j"'0 7N II,'I i N7 X-I
'I il 4$'i)N g lli>>
il>>N P
Washington Public Power Supply System P.O. Box 968 3000 George Washington Way Richland, Washington 99352 (509) 372-5000 September 21, 1983 G02-83-855 Docket No. 50-397 Director, Nuclear Reactor Regulation Attention:
Mr. A. Schwencer, Chief Licensing Branch No.
2 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.
C.
20555 Dear Mr. Schwencer t
Subject:
NUCLEAR PROJECT NO.
2 SUPPLY SYSTEM
RESPONSE
TO FSAR QUESTION 110.44
Reference:
(a)
Letter, A. Schwencer (NRC) to DW Mazur (SS),
dated August 3, 1983, subject, "FSAR questions 110.41, 110.42, 110.43 and 110.44" The Washington Public Power Supply System hereby provides a reply to FSAR question 110.44 which was submitted as an attachment to reference (a) above.
Our reply consists of this letter and 2 attachments.
If you have any questions or desire further information, please contact Pat Powell, Manager, WNP-2 Licensing.
Very truly yours, G.
C. Sorensen, Acting Manager Nuclear Safety and Regulatory Program GCS:PWH:ch
Attachment:
cc:
Mr. R.
Mr.
W.
Mr. A.
Auluck -
NRC S.
Chin - BPA D. Toth -
NRC Resident Inspector 0>
p,o(
I t
(1)
Attachment 1 - Response (2)
Attachment 2 - H-501, Sheet 3
Attachment 1
FSAR uestion 110.44 Section 3.9.3.4 of your FSAR states that all piping and component supports are designed in accordance with Subsection NF of the ASME Code.
Provide the criteria used for the other elements of construction, in addition to design.
As stated in Footnote 2 to SRP 5.2.1.1 construction includes materials, fabrication, examination, testing, inspection and installation as well as design.
Provide sufficient graphic detail so that the bound-aries to which the above construction criteria elements including design are clearly specified.
The graphic sketches should provide information for all items in the support load path from the component being supported to the building structure, including any supplementary steel.
The purpose of this request is to assure continuity of construction criteria across any jurisdictional boundaries in the support load path.
Su 1
S stem Res onse On August 5, 1983, the Supply System responded 'to an NRC Region V Notice of Deviation on the matter of NF boundaries.
That communication is pro-vided as part of this response for purposes of clarity:
Nonce o Seven As a aesuLt o$ Che. ~nspe~n conducCed on May 1-91,
- 1989, and accordance nit'h Che NRC En(once mnC Po~y, 10 CFR P~
2 Append.xC, 47 FR 9887 (March 9, 1982),
Che, (olZoemg devon Was Me~+.ed:
Pace,graph 9.2.9 o$ Che FSAR aCaCes Chat papkngagCem auppo~
ahaLL be, appease Joe Che co rponenCs supposed as degned by Che. ASME Code Sation III.
The ASME Code, Smtian III NF-15 10(d) depnes
- a. nonLetegutL ape auppoM as one. ekie.h "beau on Che pcesame boundary,y co nponmt" and NF-1511 aCaCes ChaC "Che j~&~onaE boundary b~een a
buL Ming a~~e and a non-~e gcaE supp'ha%
be Che.
am$ ace o$ Che buiZNngs~~e."
Co~y Co Che above.,
on Ap~ 9,
- 1982, Che, mchktecC en~eeJr, Lsaued cbtmein g H-50 1, aheeC Cue, Ntu.ch aQoued non-LnCeauxL suppo~
Co be extuded (con;Che cons~an andLnspe~on rceq~enenCs o$
ASME Se~on III, subdeacon NF even Chouse Che non-~eguzL auppo~
extend beyond Che buiXNn g am$ ace s~~e inCo Che juekeN~onaL boundary o$ Che, ASME Code,."
You ~e hereby aequesCed Co cubit'o CRQ ofhce eLtkin CkiXty day o$ Che, daCe o$ CRQ Nonce,
- a. uv~en 6CaCenenC oe 'e~n~n
Jw
~
'\\ )
P
ae gvcckn o Che W', m o $ dev~on, ducru.bin o comeeCive. a~n
- Caken, Che au~
achieved (oa eomeeCive aCepa Chat me planned),
and Che date when eomeeCive a~n uccLL be, e'o npleCed.'u L
S sC'emRM orue:
(to Notice of Deviation)
The, Supply SydCem poa~on ~n weaved Co Che, Nonce o$ Vev~on ~
Chat'he, du6jeeC auppo~ me Ln quuCion beeuue, o$ Nffweneu in ASME Code, inCmpaeCcction and Chat ce avuKe6a ofketmprceCaCion, eqcu.valency b~een
- Che, NF and AISCZuppoM nenb~ 4u been de, noH6~ed.
NNP-2 co nnciCCedk n Che, FSAR Co dna'o nponenC auppo~ in accordance cath Che, N~nCei 1973 Addenda ~n oMw Chat Che. du~grc tully o$
NF could be med.
TkQ damn mu a, volley upocade o$ ~crux wince Che.
nandaCocy code mould have. been Sum~
1973.
Co nponenC duppo~ undn Sum~
1973 Would have, been duagced xn aeeojcdanee uLth ANSI 831. 7-1969 foe ASME Clara 1 and 831.
1-1967 foe ASh(E Maw 2 043.
NF se~n um ~Ltended Co pcovMe deck gt ~u
$o<
supp'e,nba'fu.ch connecC AISC heal bcuLNn a rrerb~ and 6Candaed eo npo-neet duppo~.
Thee teu no ASh(E de$Zeition Joe b~cLin aa~eCcvcu.
F~hm, ASME Code, ~nCecpr.eZaWoru have, ~nNcaCed ChaC Che cequifce-zeete o$
NF 1000 (j~~onaL boundatu.m) me only a. gudeline and ChaC M ~ Che Owns a aMponeib Mty Co degne Che.'ode, j~-
NeCionaL bounduu.u.
The (olio+ing ASME Code, ~nCecpc~cone
~'$y Chic ltuponbib LLty: III-1-78-47; III-1-78-58; III-80-5 1; and III 138.
Thee ~nCwpeeCaCiom rcepeaCedly aCaCe Wo Arne aupone~b~u:
dePruMon o$ Che j~&eCionaL boun@su.u and maurutnee o$ co~b Mty b~een boundatu'.u and eomuponding Lomb.
The. Supply SyaCe.m hm't boCh rceqcurcene~.
AC 0JNP-2, Che ~u o$ NF me need (ojc Che du~gI o$
boCh ASME and Che AISC auppoM mnbeu.
The naCeuuLe open.fied and Che allow-able, aWu6ae cued me MenCieaL.
0!elan o ased Joe Che, AISC auppojcC ne~
Che, jcequifcene~
o( Che AS
- 01. 1ihn~al code.
No XnpaeC Cm&ng m aequiJced by ekChn code foe AISC oc Che, ASME auppo~.
The. pu'.neipaL N.))neneee b~een AISC 6uppo~
and ASME auppo~ m ~n Che ~w$ en, o('aCeruM
'tu.ng and.mCeuaL 46tceab~y o$ duppoM'enb~
and an Che non-d446t~ve 'excni~on o$
ASh(E CGua 1 auppoM rienbeu )olio+ing err.eon.
The. ASME Code, dou noC eeq~e Che we o$ an auCho~zed
~eepecCoe, Code, 8aCa aepo~
oe Code dCanping o$
ASME auppo~
$oa MNP-2.
Foe Clie eeuone a~ed above, and beemue Xhe FSAR cornktmnt o$
ducgi Co ASME Subamtion NF eu',
ee beLieve Chat Aerce ~
eqcu'.vaLency b~een Che NF and AISC 6uppoM nonbe/u.
Aditi onaLLy, Ae SuppLy Syhiem m coM~4ent e&k ~ndueWy puxctice, havana c$ not Lde~caL NF boundaru'.u m Xhe (oLLoeing pLaete:
PaLo Verde 1,
2, and 3
So~ Tent 1 and 2
San Ono)ce 2 and 3
(iloL( Meek CaLLouey Vo~e No come~ve a~on hm been When oe ~ pLanned ~h. ceded N Ae AISC/NF boundary, however a, ekuu.+cation o$
FSAR pxiuxgcaph 3.2.3 teil be. Inde by Septenbefi 1,
1983.
In summary, the above response stated that the jurisdictional boundary between ASME Section III, Subsection NF and AISC members has been designated consistent with code requirements and also discusses the equivalency of design for component support members regardless of jurisdictional boundary.
guestion 110.44 requests additional information regarding construction practices for NF and AISC members.
The attached table provides summary information regarding the construction requirements in the areas of inspection, fabrication, mater ials, examination, and testing.
Each support is categorized as either guality Class I or guality Class II dependent upon the safety significance of the system being supported.
This quality classification and the applicable code dictate generic construction requirements.
The construction requirements for any particu-lar support can be easily established by using design drawing H-501 in conjunction with the support detail.
When a jurisdictional boundary exists within a particular support, the applicable code requirements and construction practices are selectively applied to the individual members.
As stated previously, the design of all supports for ASME piping is equivalent to ASME-NF regardless of jurisdictional boundary or quality class.
All ASME and AISC support members meet applicable code and quality requirements, for example, NF support members meet ASME material require-ments and are fabricated using ASME IX welding requirements whereas AISC members meet ASTM material requirements and are fabricated using AWS welding requirements.
The above response identified principal differ-ences in the construction of NF and AISC support members.
Those material traceability differences do exist on certain AISC members;
- however,
recent reviews indicate that no differences exist in the nondestructive examination of ASME Class I NF support members as previously stated due
'o the absence of such welds in the AISC scope.
In terms of construction continuity the basic differences are:
- 1) AISC guality Class I members may not have the material identification markings required of NF 1 or NF 2 component support members (NF 2151, 4122),
- 2) AISC ASCII materials may not have been procured under a
10CFR Part 21 material
- program, and 3)
AISC ASCII materials may not have been subject to ASME material control and verification requirements during receipt or installation.
It should be noted that AISC guality Class II support members are fab-ricated using essentially the same procedures as AISC gCI although trained field engineers rather than gC inspector s are used for verifi-cation activities.
No substantial differences exist in the construction practices other than those cited above; minor differences do exist between the applic-able codes referenced on the following table such as weld qualification parameters.
SUMMARY
OF COMPONENT PORT CONSTRUCTION PRACTICES - TRACT 215 v
'0 SUPPORT GROUP CODE REQUIREMENT <
INSPECTION FABRICATION CUTTING WITHIN ASME NF BOUNDARY-COMPONENT SUPPORTS FOR ASME SECTION III CLASS 1
(NF1)
QC VERIFICATION REQUIRED NO 3RD PARTY (ANI)
INVOLVEMENT ALL WORK CONFORMS TO NF-4000 WITHIN ASME NF BOUNDARY-COMPONENT SUPPORTS FOR ASME SECTION III CLASS 2 & 3 (NF2 & NF3}
QC VERIFICATION REQUIRED NO 3RD PARTY (ANI)
INVOLVEMENT ALL WORK
'CONFORMS TO NF-4000 AISC gCI STRUCTURE FOR A'SME PIPING SYSTEMS SEISMIC I OR II QC VERIFICATION REQUIRED ALL WORK CONFORMS TO AISC SPECIFICATION FOR THE DESIGN FABRICATION &
ERECTION OF STRUCTURAL STEEL FOR BUILDINGS 1.23.1,2,3
& 8
,AISC ASCII STRUCTURE FOR ASME PIPING SYSTEMS-8 EISMIC I
OR II.,
NO QC VERIFICATION REQUIRED ALL WORK CONFORMS TO AISC SPECIFICATION FOR THE DESIGN FABRICATION &
ERECTION OF STRUCTURAL STEEL FOR BUILDINGS 1.23.1,2,3
& 8 BOLTING ALL WORK
'CONFORMS TO NF-4000 ALL WORK
'CONFORMS TO NF-4000 ALL WORK
'CONFORMS TO AISC SPECIFICATION FOR THE DESIGN FABRICATION &
ERECTION OF STRUCTURAL STEEL FOR BUILDINGS 1.16 1.23.4
& 5 ALL WORK CONFORMS TO AISC SPECIFICATION FOR THE DESIGN FABRICATION &
ERECTION OF STRUCTURAL STEEL FOR BUILDINGS 1.16 1.23.4
& 5 WELDING ALL WELDING QUALIFICATION AND WELDERS QUALIFICATION TO ASME IX AL'L"..WELDING QUALIFICATION AND WELDERS QUALIFICATION TO ASME IX ALL WORK CONFORMS TO AISC SPECIFICATION FOR THE DESIGN FABRICATION &
ERECTION OF STRUCTURAL STEEL FOR BUILDINGS 1.23.6 AWS D1.1*
CONFO/lk TO AISC SPECIFICATION FOR THE DESIGN FABRICATION &
ERECTION OF STRUCTURAL STEEL FOR BUILDINGS 1.23.6 AWS D1.1*~
N N II N0 ff
MATERIAL OTHER NF1 NF2 5 NF3 AISC QC I AISC -
QC II PHYSICAL ALL MATERIAL ALL MATERIAL
.'-MEETS THE.
'- "-.'EETS-THE..:;"
REQUIREMENTS REQUIREMENTS OF NF-2000 OF NF-2000 MEETS *
.ASTM MATERIAL SPECIFICATION MEETS
- ASTM MATERIAL SPECIFICATION PROCUREMENT QUALITY TRACEABILITY h~
QUALITY PROGRAM FOR MATERIAL
- CONFORMS.
TO NF-2610, INCLUDING SMALL PRODUCT EXEMPTION FROM FULL NA/NCA-3700 PROGRAM I
TRACEABILITY OF ALL MATERIAL EXCEPT SMALL PRODUCTS IS REQUIRED BY PROGRAM AND
- CODE, ALL MATERIAL IS REQUIRED TO BE CONTROLLED (SEE NF-2610)
MATERIAL DOES NOT NEED 7)% ITY PROGRAM AS EXEMPTED BY NF-2610 (b)5(c)
MATERIAL EXEMPTED FROM FULL NA/NCA-3700 PROGRAM TRACEABILITY OF ALL MATERIAL EXCEPT SMALL PRODUCTS IS REQUIRED.'.
ASME CODE DOES NOT REQUIRE TRACEABILITY (SEE NF-2610 (b)
AND (c)
AND NF-2130).
MATERIAL IS REQUIRED TO BE CONTROLLED ( SEE NF-2610).
MATERIAL PROCURED THROUGH QUALITY PROGRAM.
DOCU-MENTATION RE-QUIRED'MTR OR CERTIFICATE Of CONFORMANCE (NOTE:
EXCEPT FOR BOLTING MATERIAL OVER 2" IN DIAMETER, AISC QC 1 5 NF]
SMALL PRODUCTS 5 ASME NF2 5 NF3, PROGRAM REQUIRE-MENTS AT WNP-2 FOR BPC ARE IDENTICAL)
TRACABILITY OF MATERIAL EXCEPT SMALL PRODUCTS IS REQUIRED AISC DOES NOT REQUIRE TRACE-ABILITY.
(SEE SECTION 5
OF CODE OF STANDARD PRACTICE FOR STEEL BUILDUPS 5 BRIDGES)
MATERIAL IS REQUIRED TO BE CONTROLLED.
ASTM MATERIAL SPECIFICATION WITH NO QUALITY PROGRAM REQUIREMENTS EXCEPT CMTR ON FILE TRACEABILITY OF MATERIAL IS NOT
- REQUIRED, Blfl MATERIAL IS REQUIRED TO BE IDENTIFIED.
~
I t,
t I
lli
WELD ROD NF]
ALL WELD ROD FRVCURED BY WBG AND BPC WAS QUALIFIED FOR ASME USE NF2 & NF3 AISC " QC I AISC -
QC II EXAMINATION PRIMARY MEMBER FULL PENETRATION BUTT WELDS **
THIS TYPE WELD REQUIRES RADIOGRAPHY PER NF-5320 THIS TYPE WELD ONLY REQUIRES VISUAL PER NF-5360 VISUAL
'AGNETIC PARTICAL INSPECTION IN CERTAIN CASES VISUAL INSPECTION ONLY PRIMARY MEMBER PARTIAL PENETRATION &
FILLET WELDS OVER 1" **
PRIMARY MEMBER PARTIAL PENETRATION &
, FILLET WELDS UNDER 1"
& ALL SECONDARY MEMBER WFLDS THIS TYPE WELD REQUIRES PENETRANT OR MAGNETIC PARTICLE TEST-ING PER NF-5340 OR 5350 THIS TYPE WELD ONLY REQUIRES VISUAL PER NF-5360 THIS TYPE WELD ONLY REQUIRES VISUAL PER NF-5360 TH'IS'YPE WELD ONLY REQUIRES VISUAL PER NF-5360 VISUAL OR MAGNETIC PARTICAL INSPECTION IN CERTAIN CASES' THIS TYPE WELD REQUIRES VISUAL INSPECTION ONLY VISUAL INSPECTION ONLY VISUAL'NSPECTION ONLY TESTING THE-REQU1RE-MENTS OF NF-'6000 ARE-MET. THE FOLLOWING ARE INSPECTED:
1
),.LOCAT.ION')
-"DIRECTION'.
3.). COLD LOADS..
- 4) TRAVEL THF REQUIRE-MENTS OF NF-6000 ARE.MET.
THE FOLLOWING ARE INSPECTED:
1)
LOCATION 2)
DIRECTION 3
COLD LOADS 4)
TRAVEL THE-FOLLOWI'NG*,
ARF:"INSPECTED; 1)
LOCATION
- 2) DIRECTION I
THE-FOLLOWING-
'QRF'NSPECTED:
R.-)
LOCATION
'2-) -DIRECTION
- ALL SPRING
- CANS, VARIABLE SUPPORTS, CONSTANT SUPPORTS, AND SNUBBERS ARE UNDER ASME ARTICLE NF IF ON ASME PIPING.
- FEW. IF. Al<Y COMPONENT. SUPPORTS ARE-DESIGNED OR FABRIGATED WITH THESE TYPES-.-
OF WELD.,
- REINSPECTION O~ISC MEt'IBERS DURING THE..QUALITY REVERIFICATION PROGRAM UTILIZED ALTERNATIVE,ACCEPTANCE'RfTERIA (QVI 09)
AS DISCUSSED IN FOOT NOTES TO"FSAR TABLE 3.8-9.
II l
n r ~ ~ r F
ll
'4 gL ~ l
~
I
~ 4 II t 'E \\
~ M ill/
~
~~J~~
li ifH gp
'() )'fQ
'i r$
> (
" ~!'%G:.lv "f'w 4
J I
1 "E
'COPIES LTTR ENCl 1
0 i
01 REGULATORY NFORMATION DISTRIBUTION SY Et1
('RIOS)
~p ACR'ESSTON NBR:8309300257 OC ~ DATE: 63/09/21 NOTARI'D! NO DOCKET FACIL:50-3Ir7 NPPSS 'Nuclear Projects Unit 2~ Nashington Public Powe.
05000397 AUTH,AAME AUTHOR AFF II.IATION' SARENSENqG.CD Washington Public Power Supply System RECIP ~ NAME RECIPIENl'FFILIATION SCHNENCERrA ~
Licensing Branch 2
SUBJECTS Forwards response to FSAR Question 110.44 in. NRC 830803 ltr,Response w/o encl.N/one oversize drawing>Aperture car'.d is available in PDR.
a r Z(
DISTRIBUTION COBE:
BQOIS COPIES RECEIVES:L'TR + ENCL ~SIZE TITLE: Licensing Submittal; PSAR/FSAR Amdts L Related CorrespondenceOTES:
RECIPIENT COPIES RECIPIENT Io CODE/NAME LTTR ENCL IO CODE/NAME NRR/OL/AOL 1
AUlUCKr R ~
INTERNAL: ELD/HDS2 IE/OEPER/EPB 36 IE/DEQA'/QAB 21 NRR/OE/CEB 11 NRA/DE/EQB 13 NRR/OE/MEB 18 NRR/DE/SAB 24 NRR/OHFS/HFE840 NRR/DHFS/PSRB NRR/OS I/AEB 26 NRA/DSI/CPB 10.
NRR/OS I/ICSB 16 NRR/OS I/PSB 19 NRR/OS I/RSB 23 RGN5 EXTERNAL: ACRS 41 DMS/DSS (AMDTS)
LPDR 05 NSIC 05 6
6 1
1
~ 1 1
1 1
1 BNl(AMDTS ONLY)
FEMA REP DI Ir 39 NRC PDR 02 NTIS 1
0 IE FILE 1
3 IE/OEPER/IRB 35 1
1 1
NRR/DE/AEAB 1
1 NRR/DE/EHEB 1
2 2
NRR/OE/GB 28 2
1 1
NRR/DE/tPITEB 17 1
1 1
NRR/DE/SGEB 25 1
1 1
NRR/DHFS/LQB 32 1
1 NRR/Ol/SSP8 1
1 1
NRR/DSI/ASB 1
1 NRR/OSI/CSB 09 1
1 1
NRR/DSI/METB 12 1
1 1
22 1
G F '4 3
RH At1I/I1IB 1
1 0
1 1 ~
0 ir 1.
1lr 0
1 ii Xgc M"
~~u ~~XQWW~ch~&4 TOTAL NUMBER OF COPIES REQUIRED:
LTTR 53 ENCL 46
fp
)I T 444,34fplf
) K>>C'.<4 ">4'+4 I f
),.II rj f,<<)r ~",
i 'qhhCp
~
I p
'I ll Xj gag arf
,I)ff rp,
>>h 4
i, y )~
~<
<<~ I '<4 j
i It
>>i pp f )'hl 4 g "f
if h>>
, rh 4
~ <4 q'JCr ih q,il It 3I J Jp'"h lg
) j 4
ylI
))'h~ ~
plj" g f
f f f,~, )
il f'
i
'll 4)))
lft ip
<<ra rg f
I
~ t 4
, >>rr 1~
wwwc=-mme aye~ <<p.LI J9>>
3)
Np)3)) [r I 'h l4
~ f I
I
,4T II P
~
/
h f
Ih i)4
<<Ipk H
Ph Ih lp rh II pp, p
4 "lh I'r (V
J 4
< Ii<<'ih)
YX f 4 4~)h
)
li i) Il 4
)3 4
h 4' 4 4<< '>>')
>4 ')
9)ij
~f lj<<T fT
~
~
< ~
Washington Public Power Supply System P."O. Box 968 3000 George Washington Way Richland, Washington 99352 (509) 372-5000 September 21, 1983 G02-83-855 Docket Ho. 50-397 Director, Nuclear Reactor Regulation Attention:
Mr. A. Schwencer, Chief Licensing Branch Ho, 2
Division of Licensing U.
S.
Nuclear Regulatory Commission Washington, D.
C.
20555
Dear Mr. Schwencer:
Subject:
NUCLEAR PROJECT NO.
2 SUPPLY SYSTEM
RESPONSE
TO FSAR QUESTION 110.44
Reference:
(a)
dated August 3, 1983, subject, "FSAR questions 110.41, 110.42, 110.43 and 110.44" The Washington Public Power Supply System hereby provides a reply to FSAR question 110.44 which was submitted as an attachment to reference (a) above.
Our reply consists of this letter and 2 attachments.
If you have any questions or desire further information, please contact Pat Powell, Manager, WNP-2 Licensing.
Very truly yours, cM G.
C. Sorensen, Acting Manager Nuclear Safety and Regulatory Program GCS:PWH:ch
Attachment:
cc:
Mr.
R.
Mr.
W.
Mr. A, (1)
Attachment 1 - Response (2)
Attachment 2 - H-501, Sheet 3
Auluck -
HRC S.
Chin - BPA D. Toth -
NRC Resident Inspector OOI gj ee4~
g.5o
)
83093O025 OgoQ039~
---j Bg0921 pgR ADPCV pDR A
4 Cc
~"
~
~ )
k~
l 4> ho)
J
'l 1 l l
c