ML17261A595

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Responds to NRC 870730 Ltr Re Deviations Noted in Insp Rept 50-244/87-11.Corrective Actions:Pipe Supports Redesigned to Use New Hilti Kwik-Bolts in Place of Existing shell-type Anchor Bolts.Revised Support Drawings Encl
ML17261A595
Person / Time
Site: Ginna Constellation icon.png
Issue date: 09/01/1987
From: Kober R
ROCHESTER GAS & ELECTRIC CORP.
To: Russell W
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
IEB-79-02, IEB-79-2, NUDOCS 8709100204
Download: ML17261A595 (32)


Text

REGULATORY INFORMATION DISTRIBUTION SYSTEM (BIDS)

ACCESSION NBR 8709100204 .DOC. DATE: 87/09/01 NOTARIZED: NO DOCKET ¹ FAC IL: 50-244 Robert Emmet Ginna Nuclear Plant> Unit 1> Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION OBER> R. W. Rochester Gas 5 Electric Corp.

REC IP. NAME RECIPIENT AFFILIATION RUSSELL> W. T. Region 1> Office of Director

SUBJECT:

Responds to NRC 870730 ltr re deviations noted in Insp Rept 50-244/87-11. Corrective actions: pipe supports redesigned to use new Hilti Kwik-Bolts in place of existing shell-type anchor bolts. Revised support drawings encl.

DISTRIBUTION CODE:

TITLE: General IEOID COPIES RECEIVED:LTR (50 Dkt)-Insp Rept/Notice of J ENCL Violation gResponse SIZE:

NOTES: License Exp date in accordance with 10CFR2> 2. 109(9/19/72). 05000244 REC IP IENT COPIES REC I P IENT COP IES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PDi-3 PD 1 1 STAHLE> C 2 2 INTERNAL: AEOD 1 1 DEDRO 1 1 NRR MORISSEAU> D NRR/DOE* DIR 1 1 NRR/DREP/EPB 1 NRR/DREP/RPB 2 2 NRR/DRIS DIR 1 1 NRR/PMAS/ ILRB 1 1 OE E - MAN> J 1 1 OGC/HDS2 1 RE FILE 1 1 RES DEPY GI 1 FILE 01 1 1 ERNAL: LPDR 1 . 1 NRC P DR 1 1 NSIC 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 20 ENCL 20

>R.,>RAPIOr, ~ 89 EAST AVENUE, ROCHESTER, N,Y. 14649 0001 ROGF L'

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, C~CP<<O'lC CIRC,>> ~ ~

..ig ~ <.oar:Ie 646-2700 September 1, 1987 Mr. William T. Russell, Regional Administrator U.S. Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, PA 19406

Subject:

Inspection No. 50-244/87-11 R.E. Ginna Nuclear Power Plant Docket No. 50-244

Dear Mr. Russell:

This letter is ROTE's response to Inspection Report 87-11, transmitted by the NRC's July 30, 1987 letter from William V. Johnston to Roger Kober. In the Inspection Report, RG&E was requested to respond to the two Notices of Deviation, and to: 1) document the scope and results of the static equivalent analyses performed for selected portions of the Standby Auxiliary Feedwater and Service Water systems, 2) provide the status of the anchor bolt replacements, and 3) provide the schedule for completion of the Ginna long-term Seismic Piping Upgrade Program. This information is provided in Attachments 1 and 2.

In addition to these two Notices of Deviation, Section 6 of the Inspection Report noted that "...the licensee's QA Manual and Qh. Procedures Manual could be improved in the area of addressing requirements imposed by NRC/IE Bulletins".

RG&E is evaluating our processes necessary, will revise our procedures.

for responding to NRC/IE Bulletins, and, if Ve truly yours, Roger W. Kober Attachments xc: U.S. Nuclear Regulatory Commission Document Control Desk (Original)

T. Polich Ginna Resident Inspector 8709'f00204 87090i PDR 6

ADOCK 05000244 PDR ~g bl

~hi

ATTACHMENT l RESPONSE TO NRC INSPECTION NO. 50-244/87-ll As a result of the inspection conducted on Nay 5-8< 1987I the following deviation was identified.

Deviation A:

I.E. Bulletin 79-02< Pipe Support Base Plate Design Using Expansion Anchor BoltsI Revision 1 Supplement 1 permitted continued plant operation given the following two conditions were satisfied:

a. For the pipe support as a unitI the factor of safety compared to ultimate strength is equal to or greater than two.
b. For the anchor bolts the factor of safety is equal to or greater than two and for the support steel the original design factor of safety compared to ultimate strengths xs'et.

This supplement further specified that "Any support not satisfying the criteria should be classed as inoperable and the Technical Specification action statement met..."

Action Item 2 of the Bulletin 79-02 required that the licensee verify that the concrete anchor bolts have minimum factors of safety of 4e0 for wedge type anchors and 5.0 for shell type anchors. The licensee committed in the July 6I 1979 response to provide verification of the factor of safety for all Seismic Category I support anchor bolts.

Contrary to the licensee's commitment< the licensee did not have calculations to demonstrate the factors of safety for all supports subject to the Bulletin requirements."

R~es ense=

Prior to July 6I 1987 Rochester Gas and Electric completed an interim assessment for concrete expansion anchor bolt factors of safety. This assessment was performed at the request of NRC Staf f and was a result of the findings of NRC Inspection No. 87-11.

Inspection 87-11 determined that the Service Water (SW) system in the screen house and the Standby Auxiliary Feedwater (SAFW) system were not included in the RGEE Seismic Piping Upgrade Program.

This Upgrade Program is the means by which RGGE addressed the long term concerns of NRC IE Bulletin 79-02. In order to determine whether potential problems might exist for the subject systems in terms of the 79-02 criteriaI an interim assessment was made of the factors of safety for the expansion anchor bolts of the subject pipe supports.

As was suggested by a Staff consultant< an equivalent static analysis was performed on two representative sections of piping.

The pipe support loads from this conservative analysxs were combined for a "worst case" condition of Deadweight + Maximum Thermal + SSE. These pipe support loads were then used to calculate anchor bolt factors of safety. For wedge-type anchor bolts with an initial calculated factor of safety less than 8> a base plate flexibility analysis was performed. Bolt loads were then re-evaluated to account for plate flexibility. For the supports with a factor of safety of 8 or greater< sufficient margin exists to ensure that the factor of safety is not reduced below 4 with plate flexibility effects and no plate analysis was performed at this time.

For the SN system in the screen house> the selection of the section of piping to be analyzed was made based on the physical configuration of the piping. This system consists of two parallel trains connected by a smaller cross-connect. The two trains are virtually identical in layout and have the same numbe'r of supports with expansion anchor bolts. The train with the slightly shorter pipe run was selected to reduce the time required for piping analysis modeling. The section of the SAFW systems chosen was based o'n the portion most important from a plant safety 'stand-point. Therefore> the portions of the system from the containment penetrations to the main feedwater piping were reviewed and the shorter section was selected to minimize the piping analysis modeling time and the time for completion of the interim assessment.

The analysis results for the calculated factors of safety for the expansion anchor bolts associated with the SW line range from 2.73 to 8.4. The range of anchor bolt factors of safety for the SAFN line were found to be from 2.48 to 27.0. A complete summary of the results of the analysis is attached. Based on the results of this assessment and the conservative approach taken in the analysis> RG6E has a high degree of confidence that the supports of the subject systems are acceptable in terms of the requirements of 79-02 for the interim condition. RGGE is currently in the process of making a complete evaluation of the piping of the subject systems. The supports associated with these lines will be evaluated to criteria which are similar to that of the completed Seismic Piping Upgrade Program. The initial engineering for this Seismic Piping Upgrade scope extension has been started but a detailed schedule has not yet been developed. It is currently expected that'ngineering will proceed on a schedule such that any support modifications can be started during the 1988 refueling outage. Completion of construction activities are expected to be completed by the end of the 1989 refueling outage.

U MARY OF E ULT F R I ER M AN H R B LT FAC OR OF SAFETY EVALU N Pipe Support Method of Anchor Bolt Factor of Safety Number ~stem Attachment t T eFS N732 SW Anchors set in concrete Note 1 N733 SW Anchors set in concrete See Note 1 N734 SW Expansion anchor bolts 3/wedge/8.4 1/shell/6.4 See Note 2 N735 SW Expansion anchor bolts 4/shell/2.73 See Note 2 N740 SW Anchors set in concrete See Note 1 N741 SW Anchors set in concrete See Note 1 N744 SW Expansion anchor bolts See Note 3 N745 SW Expansion anchor bolts See Note 3 AFW-3 SAFW Welded to str. steel AFW-4 SAFW Welded to str. steel AFW-5 SAFW Welded to str. steel AFW-6 Welded to str. steel AFW-7 SAFW Welded to str. steel AFW-8 AFW-9 SAFW SAFW Welded to Expansion bolts'ee str. steel anchor bolts 4/wedge/27.0 AFW-10 SAFW Expansion anchor bolts 2/wedge/5.24 See Note 2 AFW-ll SAFW Expansion anchor bolts 4/wedge/15. 96 AFW-12 SAFW Expansion anchor bolts 2/wedge/5.26 See Note 2 AFW-13 SAFW Expansion anchor 2/wedge/2.48 See Note 2 Notes:

l. Not subject to 79-02 criteria.
2. Base plate analysis performed.
3. Per piping analysis, support is in compression only.

ATTACHMENT 2 RESPONSE TO NRC INSPECTION NO. 50-244/87-11 As a result of the inspection conducted on Nay 5-8I 1987I the following deviation was identified.

Deviation B:

I.E. Bulletin 79-02, Action Item 4I requires that each anchor bolt used in piping system supports must be inspected unless it can be

'established that tension loads do not exist. The licensee's July 6 and December 7I 1979 responses to Bulletin 79-02 committed to reanalyze supports within the scope of the bulletin prior to initiation of inspection and testing.,

Contrary to the licensee's commitmenti the licensee records disclosed that Seismic Upgrade Program modifications performed to some piping systems made it possible for some compression-only supportsi that had load changes> to be subjected to tension loads.

This situation exists in five supports of a Seismic Category I

.system. At the time of thzs NRC inspection the licensee had not inspected the anchor bolts in these supports for proper installation< specified size and type."

~Res ense:

At the time of the NRC inspection> the disposition of supports for IE Bulletin 79-02 was compared against the support modifications for the Seismic Upgrade Program. This comparison identified five supports which had not had the anchor bolts inspected for proper installation and which were now indicated as having tensile bolt loads. Subsequent detailed review of the latest support infor-mation determined that> in fact> one support still had no tensile loadsi while the remaining four supports remained unresolved.

Since the support configuration for these four supports did not allow adequate confirmation of the anchor bolt znstallationi the supports were re-evaluated to install new bolts.

The pipe supports were redesigned to use new Hilti Kwik-Bolts in place of the existing shell-type anchor bolts. This new bolt configuration was designed in accordance with the requirements of NRC IE Bulletin 79-02. The modifications of the four supports including new anchor bolts> have now been completed. Copies of the revised support drawings are attached. Note that the Inspection Report incorrectly identifies these supports as being in the Standby Auxiliary Feedwater system and the Service Water system in the screen house. These supports are actually located on systems which were modified as part of the original Seismic Upgrade Program scope. The attached drawings are for supports CCU 86I CCU 156I SWU 196 and SWU 198

I DESIGN DATA:

TYPE OF SUPPORT I3 PLATE AND SHELL REFERENCE DESIGN DRAWINGS 8 LINEAR Pi< ING 0->CI+-4Z,B Q COMPONENT STANDARD ISOMETRIC C +~I ~~ SHT. 9 STRUCTURAL CODE CLASS ANALYSIS CODE (-C- IOO ~

MAX.DESIGN TEMP.( F)

FORME.PLY pCQ-c)3 Z~

PREDICTED PIPE MOVEMENT (INCHES) 0 001 Y 0 OO(

DESIGN MECHANICAL LOADS +Y FORCE (LBS.) MOMENT (IN.-L85.)

Fx Fy Fx My Mz NORMAL UPSET tlat lo

+X EMERGENC FAULTED t R.2.6C)

C)

RIGHT HAND CAR 7 E SIAN COORDINATE SYSTEM TESTING C 0:i 8 'R (. C T I iI N NOTES: LIViil' ('~'" ",I ' )~ ~ >'q r,<(%IF'HE GENERAL-DESIGN, FABRICATION ANO ERECTION OF THIS PIPE SUPPORT IS AND SHAI.L BE IN ACCORDANCE WITH SPECIFICATIONS:

AGEE, SPEC. NCI2lg NA ALL WELDS SHALL BE MADE WITH ELECTRODES HAVING A MIN.TENSILE STRENGTH OF 60,000

/ NA PSI ~

MOVEMENTS AND FORCES ARE BASED ON NORMAL OPERATING TEMPERATURFS THE ABOVE NOTES DO NOT APPLY TO ITEMS MARKED WITH AN ASTERISK IN THE BILL OF MATERIALS. THESE ITEMS WERE PURCHASED AND INSTALLED PRIOR TO I980.

6'XLSTlb4$ SA55 PL@ TV ) FEHCHQR BOLTS) CHQgNPLS) AND GROL)7 STI<V CTL) RALLY <GOVT B> I ITINCj HOL 6 5 ) td A<<-ORDA446 W~ TH KE Al - XVSreu. iaW &VS'Lh, TC.> H>LTI 5, CHgghlBL SEC.'Tlt)A& AND &HIM PLATE..

NUCLEAR SAFETY RELATED ALL SIGNATURES AHD REVISIOHS OH THIS SHEET PERTAIN TO ALL SHEETS ASSOCIATED AEV'0 Pf R RM C. COMM </'I i'3 yg~ I WITH THE PIPE SUPPORT INDICATED BELOW P.~V'D. PER 'IGNI-R6-l5<4- %Illy CONSTRUCTION

~A A5 SQ(UY HP CLlF 8-7 RE.LEAM fr/

REV. MADE CHKD. 0 E SC R I P T I 0 N ~~G'PIR DATE DATE RELEASED FOR. APPR R E V I SION 5 O 044824-005 SCALE: NONE L)KNT MADE CHKO. PIPING ENGINEERING APPROVALS N, H CHK,

~

'OCHESTER GAS ANO ELECTRIC CORPORATIO RLS e JECT HA STATION (E1VR-2512)

SIGN DATE 314 .') iLJ ~ I-8I IO-I-Sl PIPE SUPPORT GIL8ERT ASSOCIATES, IHC.

ENGINEERS 8 CONSULTANTS MK-C(-O B,( S 382- '55& OBG .A READING, PA. TITLE DRAWING NUMBER SHEET REV.

NO. PART MATERIAL ITEM REQD. D ESCRI P TI ON

'f NO. SPECS.

~E "ct) HILT l KwllC BOLT Hlo. EeS.= ZV "

I2."x l2" X>i' E'LATE. SA aH C4x 5.4. CHANNEL

" Flap T&NC-HLON "I ~ Co1 T4 soil 5ABS

~ 4 x 2 "2 ' G.

~ " PLATE 7"x Yz" L8 TE EF.'yZ'x 6 l 7Nx I q" x 8" x TELIC)c~CGS To SvIV S~le PLWWE..

FORHlF-R,'LY ACH-93

4. lO" PlPE FL. 2,72.'- lo~" (REF. )

C 0 "I 5 T R U C T I 0 N

+v 7a PAl BE 2

r=

IO-4o 0

l ~

(RE.F

,0 p SECTION A A LOCATION PLAN AoxILIAFIY BUILDING FOR SIGHATURES AHD REYISIOHS, SEE GAI SHEET A

.LIENT OCHESTER GAS AND ELECTRIC CORPORATIO OJECT NUCLEAR SAFETY RELATED NNA STATION (EWR-2512)

PIPE SUPPORT GILBERT ASSOCIATES, INC.

ENGINEERS E CONSULTANTS MK-ccu r S -382-G~ OS< 8 3 READING, PA. TITLE ORAWIHG HUIIBER SHEET REVS

Iz FOR ME.RLY ACH-9Z I'0'~p)~ (mI.) 5 STANCHION \ S, CEN 7ERKD ON PLATE, NO WE.'LD (mp)

I'/~

(TYF.')

I 8)-EXi~r. HOZE:S C

SECTION LOC4TE, I X Z 4 C.VT'GUT IN C HATCHEL RCLATIVE, jO QA'I STTN6-"

LVQ L,CWT'ID'. m N -]et SECTION C -C FOR SIGNATURES AHD REVI SIGHS, LIENT SEE GAI SHEET A l

ROCKESTER GAS AND ELECTRIC CORPORATIO NUCLEAR SAFETY RELATED

~M~A sTATIOH ( EWR- Zei2) PIPE SUPPORT GILBERT ASSOCIATES, INC.

EHGIHEERS & COHSULTAHTS M<-CCO- 8a S-52-~m 056 C RKAOIHG, PA. TITLE ORAWIHG HUNBER SHEET REY.

DESIGN DATA:

TYPE OF SUPPORT Ej PLATE AND SHELL REFERENCE DESIGN DRAWINGS

5) LINEAR P IP IN G 5 -3 0 '4 - o Z3 ISOMETRIC C-MI 3RSHT. 2 0 COMPONENT STANDARD STRUCTURAL +

CODE CLASS MAX.DESIGN TEMP.( P) ANALYSIS CODE Y~

PREDICTED PIPE MOVEMENT (INCHES) e ~D.

~ o.ozc e.

Pop<KR,u. ~(=H-Rz DESIGN MECHANICAL LOADS FORCE (LBS.) MOMENT (IN.-LBS.)

Fx Fy Fx My Mz I('o I NORMAL 4 UPSET + 0 CS EMERGENC +Z FAULTED + C)J RIGHT HAND CARTESIAN oB COORDINATE SYSTEM TESTING

(;

,CHANNEL),AND G Roui. 'STAvc ( RooT E.)(I M /A6- M<E 5 l q /J C.('.OROhtuC E U>>TH M< IZ l. Pw~, HI a.>'s ('.ehvnta SWT I oil S NUCLEAR SAFETY RELATED ALL SIGNATURES AHO REVISIOHS OH THIS AS EV' Cg L ~ CCIQM~75 NT. Fi.s SHEET PERTAIH TO ALL SHEETS ASSOCIATED WITH THE PIPE SUPPORT IHDICATED BELOW gE/'D E=L-R 13PII-Rb- i5Z'I CONSTRUCTION AS BuIL.T PFR FCR 25IC,- 5 I' l RLS ,'Ja e~ e '/.~1.~ IE t/(7 CLlg,kl I EE.Lt A SF REV. MADE CHKD. DESCRIPTION I klT APPR DATE DATE RELEASED FOR APPR ~ R E V I SION S W.O. 044824-005 SCALE: NONE LIENT MADE CHKD PIPING ENGINEERING APPROVA 5 te ( ~ HSS I PS 'OCHESTER GAS AND ELECTRIC CORPORATIO SIGN 6 ~A PgZ) JECT NA STATION (EWR-2512) DATE 11 IB Sl Il ZS.81 gg /-7 I~ LL 'bZ PIPE SUPPORT GILSERT ASSOCIATES, INC. EHGIHEERS 8 CONSULTANTS MK-CCU-I S(o S-382- BS(JD I SCc A 3 READING, PA. TITLE DRAWIHG HUHBER SHEET REVS NO. PART MATERIAL ITEM REOD. O'ESCRIPTION NO. A SPECS. +" SCV 4O PIPFX l2 ~i "LC.(REF;5 + I I I C~ x Q.R CHANNEL. X/I i/p "X 3" X I/z." PLATE 'I. u7 R. SA 36 0 c.. EMQ=Z~ IO" x IO" W 3 " Pl ATC 5" X B" x I/2" PLATE, 5" X 6," X THiCK IO . UI I IMI ED I '- > +LL TIO."I: AS NQI'Elg ~ ig a ~ ~ ~,,a i 'nhl~Ti I ~ ) NOTE 'hLL ITEMS ,.C.EHTERED EXCEPT. AS NOTED FCI < M~WI Y ACH-97 CT YP) 4a -)IU 0 EL,Z:7Z'"9" (aalu 5 /~/is bb NOT l gp 7 VlKLb + + ll (mp) 2 (A) - 4HOLa Ib 5QZF; J.OCATE',.L",X R" SECT. B-B .C.O TQ V.T IN .... (PA) GA CIIANnEL>ELhTlK Ines@ EL.2 7 I "o ln ( R.'EI'.> ( RR'F.) 4 O'.'o', ia I 5'-9 t.'Q.Kv. ) SECT. A-A LOCATION PLAN AUXILIARY BUILDING FOR SIGNATURES AND REVISIONS, SEE GAI SHEET A LI EH T 'CHESTER GAS AND ELECTRIC CORPORATIO ECT NUCLEAR SAFETY RELATED A STATION (EWR-2512) PIPE SUPPORT GILBERT ASSOCIATES, INC. ISG ENGINE E RS E COHSULTAH7 5 MK- CCU - I S6 S -382-35'(c 8 READING, PA. TITLE ORAWING NUMBER SHEET REY D ESI GN DATA: TYPE OF SUPPORT 8 PLATE AND SHELL REFERENCE DESIGN DRAWINGS K LINEAR I IPING Q COMPONENT STANDARD ISOMETRIC C-36( "358SHT. CODE CLASS ILAA MAX.DESIGN TEMP.( F) ANALYSIS CODE SW - 100 0 PREDICTED PIPE MOVEMENT (INCHES) Fop-ME.R.LY SwAH. Z,2. X-C.COG 'f OE OOO Zo obO DESIGN MECHANICAL LOADS FORCE (LBS.) MOMENT (IN.-L8S.) Fx Fy Fr Mx My Mr NORMAL UPSET EMERGENC FAULTED RIGHT HAND CARTESIAN COO R D IN AT E 5 Y ST EM TESTING ~zf g CONSTRUCTION I+IT~ I 9 ('S,9 I iE s. ~ 9'w ~ 9+TPP NOTES: ( ~ ~ 9 ~ PS GENERAL-THE DESIGN, FABRICATION AND ERECTION OF THIS PIPE SUPPORT IS AND SHALL BE IN ACCORDANCE WITH SPECIFICATIONS: .NA HA ALL WELDS SHALL BE MADE WITH ELECTRODES HAVING A MIN.TENSILE STRENGTH OF 60,000 PSI. I NA MOVEMENTS AND FORCES ARE BASED ON NORMAL OPERATING TEMPERATURES THE ABOVE NOTES DD NOT APPLY TO ITEMS MARKED WITH AN ASTERISK IN THE BILL OF MATERIALS. THES ITEMS WERE PURCHASED AND INSTALLED PRIOR TO 1990. DISPOSITION R,E.hA~E E.XlST 'LM~ QPl5t. PI A'Te bACPOR BOLTS'HANNEl.h,)GR FILL E X I Sl l Qg HOLE, 451TH STOL)("TURAQ 4ROQ T.,lH ACCOBDA14C.E 041'T 8 l4E.-lZL ~ thLhtk44 El'ASE PLAH E.~ '4'iQ lE.'5 ~( CANNEL SECTlqhl&~ ASLlD SHIM, IDI AWE.e NUCLEAR SAFETY RELATED pe REV'D. PER. R6+ F (.OMNENW ALL SIGNATURES AND REVISIONS ON THIS <<llhlASI PE5Z ~ 8 'I 24 SHEET PERTAIH TO ALL SHEETS ASSOCIATED WITH THE PIPE SUPPORT INDICATED BELOW A5-EssuILI 4K<V'IJ hC.N-REV. MADE CHK 0. <>- Ek) II i PF.R D E SC R I P T I 0 II >5 APPR DATE /C -/.p ~/~l DATE CONSTRUCTION / CLlt=WW REUFP RELEASED FOR ~4 APPR. RE VI SION 5 W.O. 044824-005 SCALE: NONE LIEN T MADE CHKD. PIPING ENGINEERING APPROVALS EW SEE C SR K ~ OCHESTER GAS AND ELECTRIC CORPORATIO SIGN OJKCT HA STATION (EWR-2512) DATE 8.IO 8 SZ4 8I >8 Zi 9-23.SI QiZ4 I'5'I PIPE SUPPORT GILBERT ASSOCIATES, INC, ENGINEERS S CONSULTANTS MK-swU -l9Cc s-382-356 l9 ( A READING, PA. TITLE DRAWIHG NUMBER SHEET REV. e NP. PART MATERIAL DESCRIPTION REQD. NO. 4 'C H'. 4O P I PE X 9 ~re," G . ( RE.P. SPECS. 4,10+ "4 HILri K~iK. cl t l4iui~uw CoI4c,. ~.-ze L iO" ~ LO" ~W "~TE, 6 "K5" K 3/ "EIL,VE'I ~ -W "4 QOI Z~ CHANNEL W O.'-I2." cur,yg z~i< '.x,l'/z."xP/+" PLAT U THI(KNE.SS TO UI Q I LQ7 r + ~ P T I IMMIT"i3:" l'IS.'>O'IQ'I: A N ".~ '0f 'i .":;~T 0{ R (,AI.'QTRIJCTIOI'I ~ ~ FORME.RLY SWAH- Z.2. N0TE.: vi I PLLITE.MS TO BE TNP. R, CE,N TERE D UNt NOTE D 655 F. '~ L r 0 g Zi. ZS<'-c" (~~1=,b r l4" )PE 1 I I/Z ih Wl~ I'/Z, S F Cv l O+ ' -B +B l5P; 8 I + PLC-b.,a S F~hf'TO MOVE. SA( PA FL.E,L 2.53 -o ~ i"!j ~ ~ e q4 i ~ ~ ~ 1 , -o ~;,-~ (REF) 1 i~ ~ ~HllP~F a" LCCnrF I" X 2,'IZ.", CUTOOT PI CH ~HEI ~L .. (PGF.) (R6F,) 1 reELn TiVE,, TO %RATION,- EXiSt I HS Lu& SECTI ON LOCATION PLAN QUAILI AR.V BUILDING FOR SIGNATURES AND REVISIONS, SEE GAI SHEET A LIENT QCHESTER GAS AND ELECTRIC CORPORATIO JECT NUCLEAR SAFETY RELATED NA STATION (EWR-2512) PIPE SUPPORT GILBERT ASSOCIATES, INC. ENGINEERS E CONSULTANTS MK-Swu-19' s-382- 858 l9t B READING, PA. TITLE DRAWING HUNBER SHEET REVS DESIGN DATA: TYPE OF SUPPORT (8 PLATE AND SHELL REFERENCE DESIGN DRAWINGS 5f LINEAR PIPING 0-SO L-69+ 0 COMPONENT STANDARD ISOMETRIC C ~l 3B3SHT. CODE CLASS STRUCTURAL D 4++ MAX. D E SIGN T EMP. ( F) ANALYSIS CODE SW IOOO PREDICTED PIPE MOVEMENT (INCHES) FoRMCRLY SWAH- iQ X'.oC o Y O.ooo Z 0 OC)O DESIGN MECHANICAL LOADS +Y FORCE (LBS.) MOMENT (IN.-LBS.) Fx Fy Fx Mx My Mz NORMAL UPSET +O EMERGENC FAULTED RIGHT HAND CARTESIAN COOR DI HAT E SYST EM TESTING CONS 8 RU(:Tl()N NOTES: L!'i'l".0 ~ '."!', "".', I.) '.: A5 Il')[t. ) GENERAL-THE DESIGN, FABRICATION AND ERECTION OF THIS PIPE SUPPORT IS AND SHALL BE IN ACCORDANCE WITH SPECIFICATIONS: RC CE. SmC. ME-IZI NA NA ALL WELDS SHALL BE MADE WITH ELECTRODES HAVING A MIN.TENSILE STRENGTH OF 60,000 PSI. MOVEMENTS AND FORCES ARE BASED ON NORMAL OPERATING TEMPERATURES THE ABOVE NOTES DO NOT APPLY TO ITEMS MARKED WITH AN ASTERISK IN THE BILL OF MATERIALS. THESE ITEMS WERE PURCHASED AND INSTALLED PRIOR TD 9988. ~DIEPOEITIOSA: IKlAOVA= EAlSTSNSCN eYSNKE. F'LA'TE.ASSCHOR BOAT& CHANNELS II GRDLSi PlLL EX'IaT)>4% HOI 6, Vl)TH STPUCTURA< CqPOU'T lQ ACCORDANCE 44 lTH-hhE-l2i - Xt45WWLL MEW eASE, PI AWE., Ala'<Ga ~ C,4AN4K4 SKMIO&$, A.E4Q Swam PI KTQ NUCLEAR SAFETY RELATED EV . PE~ R4v- tlM ALL SIGNATURES AND REVISIONS I- -L kN ON THIS I'4D 0'&PCS IGNI( Q~ IQ.+ SHEET PERTAIN TO ALL SHEETS ASSOCI ATED WITH THE PIPE SUPPORT INDICATED BELOW EV', h PI PI[ S h(-.vt 4a '/-yi, ~ S F VOl RS~ Gy. E RWCR CONSTRUCTION V ~c AK- BU) I I C.LIEN,'7 RE~KS~ REV. MADE CHKD. 0 E SC RIP 7 ION 'PPR DATE DATE RELEASED FOR APPR. R E VISIONS W.O. 044824 005 SCALE: NONE LIENT MADE CHKD. PIPING ENGINEERING APPROVALS SW 898 C PE K 'OCHESTER GAS AND ELECTRIC CORPORATIO sIGN lOJECT DATE 6'Gal B24 8I 0-23-8 9/Z4/6'i HHA STATION (EWR-2512) PIPE SUPPORT GILBERT ASSOCIATES, INC. ENGINEERS B CONSULTANTS MK-SWU-l98 S-382-~SS IQG A READING, PA. TITLE DRAWING NUMBER SHEET REV. NOo PART ITEM REOD. NO. DESCRIPTION 'LJT'ATERIAL SPECS. I' "WglIg< KWlY ~aT ~ P.'QIaim<~Qo~c li"XlZ.' >1 "PLATE, ~r'4 "p.7 SASS 'LATE '.F 1 A Z" x l" x'Jh" PLATE C.$ ~4"l CORNEL/ t ~H. " 4O PIPE, '7RNCH ON ) A-l066 1 l 3" X X,'C S ro O (Suim Rl A,TP FORMERLY SWAH 1C) 71 CO.: ..;.:r:,IrI I 'y$ ,'I<<> I ~ ~ ",'jIA I ~ PQ M<1,I.,) . 'I,'.I;'.sP: . r,,P I'n<",f I r I;I~, 420'lPE'L. I I Z54'-Cc" I I (ReF') I I I I I FREK ro I IYZ 9a hAow E. 3 r~ I/g SAI PAg FLOOR E.L-QA gA SECTION A A ~OT~'.. SWARF I mr~ CI~~ Z.> MOTE ROTKYEQ TO FRCILI TAT 2 HILTI INSThCCTIOH. LOCATIOH P LAH AUXII IAR'II BUILD IHG FOR SIGNATURES ANO REVISIONS, SEE GAI SHEET A LI EH T 1CHESTER GAS AHD ELECTRIC CORPORATIO JECT NUCLEAR SAFETY RELATED HA STATIOH (EWR-2512) PIPE SUPPORT ,GILBERT ASSOCIATES, IHC. EHGIHEERS B CONSULTANTS MK-5WU- I 9B S -382 -3~6 IRK, 8 READING, PA. TITLE DRAWING NUMBER SHEET REV. FORNgP(LY 5VVAH l@ PLATE' PI@I= QQ~~CHIDM gE. CEroTERE.D I" <top) 2,"(~v8 >'"(reap) SE CT ION B B ~ 0"" S T R 0 C T I O g PU % p~ . EKE: LOCATE'. I" X Z'lz" CUTQOT IN CHANNEL RELATIVE TO EPISTIN& LUG LOC,Al I 0 f4. SECTION C C FOR SIGHATURES AHD REVISIONS, SEE GAI SHEET A LIGHT )CHESTER GAS AND ELECTRIC CORPORATIO NUCLEAR SAFETY RELATED INHA STATIOH (FMR-ZQIZ) PIPE SUPPORT GILBERT ASSOCIATES, IHC. ENGINEERS d, CONSULTANTS MK-SWu- Iee, l98 C READING, PA. TITLE DRAWING NUMBER SHEET REY. '