ML17261A595

Responds to NRC 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
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 FAC IL: 50-244 AUTH. NAME OBER> R. W.

REC IP. NAME RUSSELL> W. T.

8709100204

.DOC. DATE: 87/09/01 NOTARIZED:

NO DOCKET ¹ Robert Emmet Ginna Nuclear Plant>

Unit 1>

Rochester G

05000244 AUTHOR AFFILIATION Rochester Gas 5 Electric Corp.

RECIPIENT AFFILIATION 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:

IEOID COPIES RECEIVED:LTR J ENCL g SIZE:

TITLE: General (50 Dkt)-Insp Rept/Notice of Violation Response NOTES: License Exp date in accordance with 10CFR2> 2. 109(9/19/72).

05000244 REC IP IENT ID CODE/NAME PDi-3 PD INTERNAL:

AEOD NRR MORISSEAU> D NRR/DREP/EPB NRR/DRIS DIR OE E

MAN> J RE FILE FILE 01 COPIES LTTR ENCL 1

1 1

1 1

1 1

1 1

1 1

1 1

REC IP IENT ID CODE/NAME STAHLE> C DEDRO NRR/DOE* DIR NRR/DREP/RPB NRR/PMAS/ ILRB OGC/HDS2 RES DEPY GI COP IES LTTR ENCL 2

2 1

1 1

1 2

2 1

1 1

1 ERNAL:

LPDR NSIC 1

1 1

NRC P DR 1

1 TOTAL NUMBER OF COPIES REQUIRED:

LTTR 20 ENCL 20

>R.,>RAPIOr,

~ 89 EAST AVENUE, ROCHESTER, N,Y. 14649 0001 ROGF

'l" L'

CIRC,>>

~

~

September 1,

1987

, C~CP<<O'lC

..ig ~ <.oar:Ie 646-2700 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 for responding to NRC/IE Bulletins, and, if necessary, will revise our procedures.

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 ADOCK 05000244 6

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 flexibilityanalysis 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 flexibilityeffects 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 Number

~stem Method of Attachment Anchor Bolt Factor of Safety t

T eFS N732 N733 N734 N735 N740 N741 N744 N745 AFW-3 AFW-4 AFW-5 AFW-6 AFW-7 AFW-8 AFW-9 AFW-10 AFW-ll AFW-12 AFW-13 SW SW SW SW SW SW SW SW SAFW SAFW SAFW SAFW SAFW SAFW SAFW SAFW SAFW SAFW Anchors set in concrete Anchors set in concrete Expansion anchor bolts Expansion anchor bolts Anchors set in concrete Anchors set in concrete Expansion anchor bolts Expansion anchor bolts Welded to str. steel Welded to str. steel Welded to str. steel Welded to str. steel Welded to str. steel Welded to str. steel Expansion anchor bolts Expansion anchor bolts Expansion anchor bolts Expansion anchor bolts Expansion anchor bolts'ee Note 1

See Note 1

3/wedge/8.4 1/shell/6.4 See Note 2

4/shell/2.73 See Note 2

See Note 1

See Note 1

See Note 3

See Note 3

4/wedge/27.0 2/wedge/5.24 See Note 2

4/wedge/15. 96 2/wedge/5.26 See Note 2

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 8 LINEAR Q COMPONENT STANDARD CODE CLASS MAX.DESIGN TEMP.( F)

PREDICTED PIPE MOVEMENT (INCHES) 0 001 Y

0 OO(

Z~

REFERENCE DESIGN DRAWINGS Pi< ING 0->CI+-4Z,B ISOMETRIC C +~I ~~ SHT. 9 STRUCTURAL ANALYSIS CODE

(-C-IOO

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FORME.PLY pCQ-c)3 DESIGN MECHANICALLOADS

+Y NORMAL UPSET EMERGENC FAULTED TESTING Fx FORCE (LBS.)

Fy tlat lo t R.2.6C)

C)

Fx MOMENT (IN.-L85.)

My Mz

+X RIGHT HAND CAR 7 E SIAN COORDINATE SYSTEM NOTES:

GENERAL-C 0:i 8 'R (. C T I i I N LIViil'

('~'" ",I

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>'q r,<(%IF'HE DESIGN, FABRICATION ANO ERECTION OF THIS PIPE SUPPORT IS AND SHAI.L BE IN ACCORDANCE WITH SPECIFICATIONS:

AGEE, SPEC. NCI2lg 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 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<VCTL)RALLY

<GOVT B> IITINCj HOL6 5

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AND

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NUCLEAR SAFETY RELATED yg~ AEV'0 PfR RM C.

COMM</'I I

i'3 P.~V'D. PER 'IGNI-R6-l5<4-

%Illy ALL SIGNATURES AHD REVISIOHS OH THIS SHEET PERTAIN TO ALL SHEETS ASSOCIATED WITH THE PIPE SUPPORT INDICATED BELOW CONSTRUCTION REV. MADE

~A A5 SQ(UY CHKD.

0 E SC R I P T I0 N HP

~~G'PIR DATE DATE RELEASED FOR.

APPR CLlF 8-7 RE.LEAM fr/

R E VI SION 5 O 044824-005 SCALE:

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~

CHK, JECT HA STATION (E1VR-2512)

GIL8ERT ASSOCIATES, IHC.

ENGINEERS 8 CONSULTANTS READING, PA.

DATE 314.')

PIPE SUPPORT MK-C(-O B,(

TITLE iLJ ~ I-8I S 382- '55&

DRAWING NUMBER OBG.A SHEET IO-I-Sl REV.

ITEM NO.

REQD.

PART NO.

D ESCRI P TION

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GILBERT ASSOCIATES, INC.

ENGINEERS E CONSULTANTS READING, PA.

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LIENT ROCKESTER GAS AND ELECTRIC CORPORATIO

~M~A sTATIOH

( EWR-Zei2)

GILBERT ASSOCIATES, INC.

EHGIHEERS & COHSULTAHTS RKAOIHG, PA.

PIPE SUPPORT M<-CCO-8a TITLE

l S-52-~m ORAWIHG HUNBER 056 C SHEET REY.

NUCLEAR SAFETY RELATED

DESIGN DATA:

TYPE OF SUPPORT Ej PLATE AND SHELL

5) LINEAR 0 COMPONENT STANDARD CODE CLASS MAX.DESIGN TEMP.( P)

PREDICTED PIPE MOVEMENT (INCHES) e ~D.

e.

Y~

~ o.ozc REFERENCE DESIGN DRAWINGS P IP ING 5-3 0 '4 - o Z3 ISOMETRIC C-MI 3RSHT. 2 STRUCTURAL +

ANALYSIS CODE Pop<KR,u. ~(=H-Rz DESIGN MECHANICALLOADS NORMAL UPSET EMERGENC FAULTED TESTING Fx FORCE (LBS.)

Fy I('o I 4

+ 0 CS

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My Mz

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GEHERAli 2

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THE DESIGN, FABRICATIONAND ERECTION OF THIS PIPE SUPPORT IS AND SHALL BE IN ACCORDANCE WITH SPECIFICATIONS:

G 8 SP'(=C,IVIE; I2 I g

NA NA ALLWELDS 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 OO NOT APPLY TO ITEMS MARKED WITH AN ASTERISK IN THE BILL OF MATERIALS. THESE ITEMS WERE PURCHASED AND INSTALLED PRIOR TO 1980.

e DISPOSITIO REMo VE E'XISr I rV C e FI SE.

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NONE LIENT

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GILSERT ASSOCIATES, INC.

EHGIHEERS 8 CONSULTANTS READING, PA.

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3 TITLE DRAWIHG HUHBER SHEET REVS DATE 11 IB Sl Il ZS.81 gg

/-7

NO.

ITEM REOD.

+

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PART NO.

O'ESCRIPTION A

+" SCV 4O PIPFX l2 ~i "LC.(REF;5 MATERIAL SPECS.

R.

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" Pl ATC 5" X B"x I/2" PLATE, u7 0

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+

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GILBERT ASSOCIATES, INC.

ENGINE E RS E COHSULTAH7 5 READING, PA.

PIPE SUPPORT MK-CCU - I S6 TITLE S -382-35'(c ORAWING NUMBER ISG 8 SHEET REY

D ESI GN DATA:

TYPE OF SUPPORT 8 PLATE AND SHELL K LINEAR Q COMPONENT STANDARD CODE CLASS MAX.DESIGN TEMP.( F)

PREDICTED PIPE MOVEMENT (INCHES)

X-C.COG

'f OE OOO Zo obO REFERENCE DESIGN DRAWINGS I IPING ISOMETRIC C-36( "358SHT.

ILAA ANALYSIS CODE S W - 100 0 Fop-ME.R.LY SwAH. Z,2.

DESIGN MECHANICALLOADS NORMAL UPSET EMERGENC FAULTED TESTING Fx FORCE (LBS.)

Fy Fr Mx MOMENT (IN.-L8S.)

My Mr RIGHT HAND CARTESIAN COO R D IN AT E 5 YST EM NOTES:

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CONSTRUCTION

( I+IT~ I 9 ('S,9 I

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~ 9+TPP GENERAL-THE DESIGN, FABRICATION AND ERECTION OF THIS PIPE SUPPORT IS AND SHALL BE IN ACCORDANCE WITH SPECIFICATIONS:

.NA HA I

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 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 ISl lQg HOLE, 451TH STOL)("TURAQ 4ROQ T.,lH ACCOBDA14C.E 041'T 8 l4E.-lZL~ thLhtk44 El'ASE PLAHE.~ '4'iQ lE.'5 ~( CANNEL SECTlqhl&~

ASLlD SHIM, IDI AWE.e NUCLEAR SAFETY RELATED pe REV'D.

PER.

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<>- Ek) IIi D E SC R I P T I0 II

-/.p ~/~l /

APPR DATE DATE CLlt=WW REUFP ~4 RELEASED FOR APPR.

R E VISION 5 W.O. 044824-005 SCALE:

NONE LIEN T OCHESTER GAS AND ELECTRIC CORPORATIO SIGN MADE CHKD.

PIPING ENGINEERING APPROVALS EW SEE C SR K ~

OJKCT HA STATION (EWR-2512)

DATE 8.IO 8 SZ4 8I PIPE SUPPORT

>8 Zi 9-23.SI QiZ4 I'5'I GILBERT ASSOCIATES, INC, ENGINEERS S CONSULTANTS READING, PA.

TITLE DRAWIHG NUMBER SHEET MK-swU-l9Cc s-382-356 l9 (

A REV.

e

NP.

PART REQD.

NO.

DESCRIPTION 4 'C H'. 4O P I PE X 9 ~re,"

L G. ( RE.P.

"4 HILri K~iK.

clt l4iui~uw CoI4c,. ~.-ze iO" ~ LO"~W "~TE, ~ -W "4 QOI Z~

6 "K5" K 3/

"EIL,VE'I CHANNEL W O.'-I2."

cur,yg z~i<

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I LQ7 MATERIAL SPECS.

4,10+

r

+

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A N

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PLLITE.MS TO BE CE,N TERE D UNt 655 NOTE D IF. '~

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EXiSt I HS Lu& %RATION,-

a" (PGF.) (R6F,)

LOCATION PLAN QUAILI AR.V BUILDING JECT NA STATION (EWR-2512)

GILBERT ASSOCIATES, INC.

ENGINEERS E CONSULTANTS READING, PA.

FOR SIGNATURES AND REVISIONS, SEE GAI SHEET A

LIENT QCHESTER GAS AND ELECTRIC CORPORATIO PIPE SUPPORT MK-Swu-19' TITLE NUCLEAR SAFETY RELATED s-382-858 l9t B

SHEET REVS DRAWING HUNBER

DESIGN DATA:

TYPE OF SUPPORT (8 PLATE AND SHELL 5f LINEAR 0 COMPONENT STANDARD CODE CLASS MAX.D E SIGN T EMP. ( F)

PREDICTED PIPE MOVEMENT (INCHES)

X'.oC o Y O.ooo Z 0 OC)O REFERENCE DESIGN DRAWINGS PIPING 0-SO L-69+

ISOMETRIC C~l 3B3SHT.

STRUCTURAL D 4++

ANALYSIS CODE SW IOOO FoRMCRLY SWAH-iQ DESIGN MECHANICALLOADS

+Y NORMAL UPSET EMERGENC FAULTED TESTING Fx FORCE (LBS.)

Fy

+O Fx Mx MOMENT (IN.-LBS.)

My Mz RIGHT HAND CARTESIAN COOR DIHATE SYST EM NOTES:

CONS 8 RU(:Tl()N 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 EV PE~

R4v-I-

-L tlM kN I'4D 0'&PCS IGNI( Q~ IQ.+

EV',

h PI PI[ S

~ h(-.vt 4a S F VOl RS~ Gy.

E RWCR

'/-yi, NUCLEAR SAFETY RELATED ALL SIGNATURES AND REVISIONS ON THIS SHEET PERTAIN TO ALL SHEETS ASSOCI ATED WITH THE PIPE SUPPORT INDICATED BELOW CONSTRUCTION V~c REV. MADE CHKD.

AK-BU) I I

0 E SC RIP 7 ION

'PPR DATE DATE C.LIEN,'7 RE~KS~

RELEASED FOR APPR.

R E VISIONS W.O. 044824 005 SCALE:

NONE LIENT

'OCHESTER GAS AND ELECTRIC CORPORATIO sIGN MADE CHKD.

PIPING ENGINEERING APPROVALS SW 898 C PE K lOJECT HHA STATION (EWR-2512)

DATE 6'Gal B24 8I PIPE SUPPORT 0-23-8 9/Z4/6'i GILBERT ASSOCIATES, INC.

ENGINEERS B CONSULTANTS READING, PA.

MK-SWU-l98 TITLE S-382-~SS DRAWING NUMBER IQG A

SHEET REV.

NOo ITEM REOD.

I' PART NO.

DESCRIPTION "WglIg< KWlY ~aT ~ P.'QIaim<~Qo~c li"XlZ.'

>1 "PLATE, ~r'4 1 "p.7

'LATE Z" x l"x'Jh" PLATE C.$~4"l CORNEL/

t

'LJT'ATERIAL SPECS.

SASS A

1 l

~H. 4O PIPE,

'7RNCH ON '.F ) A-l066 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~,

FREK ro hAow E.

3 I

I I

I I

I I I I

I 420'lPE'L. Z54'-Cc" (ReF')

IYZ r~ I/g 9a SECTION A A FLOOR E.L-SAIPAg QA gA

~OT~'.. SWARF I mr~ CI~~ Z.> MOTE ROTKYEQ TO FRCILITAT 2 HILTI INSThCCTIOH.

LOCATIOH P LAH AUXII IAR'II BUILD IHG JECT HA STATIOH (EWR-2512)

,GILBERT ASSOCIATES, IHC.

EHGIHEERS B CONSULTANTS READING, PA.

FOR SIGNATURES ANO REVISIONS, SEE GAI SHEET A

LI EH T 1CHESTER GAS AHD ELECTRIC CORPORATIO PIPE SUPPORT MK-5WU-I 9B TITLE S -382 -3~6 DRAWING NUMBER

IRK, 8

SHEET REV.

NUCLEAR SAFETY RELATED

PLATE' PI@I=

QQ~~CHIDM gE. CEroTERE.D I" <top)

FORNgP(LY 5VVAH l@

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 I0 f4.

SECTION C C FOR SIGHATURES AHD REVISIONS, SEE GAI SHEET A

LIGHT

)CHESTER GAS AND ELECTRIC CORPORATIO INHA STATIOH (FMR-ZQIZ)

PIPE SUPPORT NUCLEAR SAFETY RELATED GILBERT ASSOCIATES, IHC.

ENGINEERS d, CONSULTANTS READING, PA.

MK-SWu-Iee, TITLE DRAWING NUMBER l98 C

SHEET REY.

'