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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
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[Table view] Category:TEST REPORT
MONTHYEARML17263A3221993-04-30030 April 1993 Reactor Containment Bldg Integrated Leakage Rate Apr 1993, Ginna Nuclear Station. ML17250B0221989-05-31031 May 1989 Reactor Containment Bldg Integrated Leakage Rate. ML17251A7911986-03-31031 March 1986 Reactor Containment Bldg Integrated Leakage Rate Test. ML17309A3531984-08-15015 August 1984 1984 Steam Generator Eddy Current Exam Summary Rept. W/850306 Ltr ML17254A8901984-06-26026 June 1984 Startup Physics Testing Program. ML17255A7181984-01-31031 January 1984 Containment Vessel Tendons, 1983 Surveillance Final Rept ML17255A7191983-12-31031 December 1983 Containment Vessel Tendons Stress Relaxation Properties of Retensioned Wires. ML17256A6831983-04-15015 April 1983 Level Control Valve 427 Fuse Coordination - Ginna Station. ML17256A4281982-12-15015 December 1982 Reactor Containment Bldg Integrated Leak Rate Test,May 1982. ML17255A6891982-11-16016 November 1982 Dynamic Collapse of Steam Generator Tubes. ML17256A9771982-05-18018 May 1982 Addendum 1, Lab Collapse Tests, Revision 0,to Steam Generator Evaluation,Ginna Steam Tube Failure Incident, 820125,RE Ginna Nuclear Power Plant. ML17256A9811982-05-18018 May 1982 Addendum 3, Phase II Metallurgical Exams, Revision 0,to Steam Generator Evaluation,Ginna Steam Generator Tube Failure Incident,820125,RE Ginna Nuclear Power Plant. ML17256A9831982-05-18018 May 1982 Addendum 4, External Tube Loading Test, Revision 1 to Steam Generator Evaluation,Ginna Steam Generator Tube Failure Incident,820125,RE Ginna Nuclear Power Plant. ML17256A9791982-05-18018 May 1982 Addendum 2, Lab Fatigue Testing, Revision 0,to Steam Generator Evaluation,Ginna Steam Generator Tube Failure Incident,820125,RE Ginna Nuclear Power Plant. ML17256A8541982-04-26026 April 1982 Steam Generator Evaluation,Ginna Steam Tube Rupture Incident,820125,RE Ginna Nuclear Power Plant. ML17258A2041981-09-21021 September 1981 Adequacy of Station Electric Distribution Sys Voltages. ML17258A7461981-01-29029 January 1981 to App C-Ginna Station Inservice Pump & Valve Testing Program for 810101 Through 901230. ML17250A5991980-07-31031 July 1980 Piping Stress Analysis Rept,Rhr Sys,Section 200. ML17250A5901980-07-31031 July 1980 Re Ginna Nuclear Power Plant,Seismic Upgrading Program Piping Stress Analysis,Main Steam Sys,Section 200. Main Steam Containment Drawing Encl ML17250A5861980-07-31031 July 1980 Piping Stress Analysis Rept,Rhr Sys,Section 250. ML17249A9101980-04-11011 April 1980 Revised Pages 4,6 & I-2,Table 3 & Figure 1-A for Evaluation of Prestressed Tendon Forces. ML17249A3371979-11-20020 November 1979 Evaluation of Prestressed Tendon Forces. ML20081C0311976-02-28028 February 1976 Reactor Containment Bldg Integrated Leak Rate Test ML17258A1351973-11-12012 November 1973 Qualification Tests for Modular Penetration 5 Diameter (Prototype B1). ML17244A5781966-09-16016 September 1966 Submits Info Re Seismic Qualification of Mechanical & Electrical Equipment & Fluid & Electric Distribution Sys. Includes Test Repts,Tech Specs & Oversized Drawings 1993-04-30
[Table view] |
Text
WESTINGHOUSE PROPRIETARY CLASS 3 SDTAR-80-'05- 05 R. E. GINNA NUCLEAR POWER PLANT SEISMIC UPGRADING PROGRAM PIPING STRESS ANALYSIS REPORT RESIDUAL HEAT REMOVAL SYSTEM, SECTION 250 ANALYST: C, Ng H. A. Massie APPROVED:
F. Loceff, Man ger Structural 5 Seismic Technology WESTINGHOUSE ELECTRIC CORPORATION NUCLEAR TECHNOLOGY DIVISION JULY 1980 RMlJLNMY !NIL'l<H HL3 MPY 8009gyg gag
TABLE OF CONTENTS PAGE
- 1. 0 SYSTEM DESCRIPTION Extent of Piping 1.2 Specifications.
1.3 Loading Conditions 1.3.1 Operating Modes 1.3.2 Seismic Environment 1.4 Static Displacement of Anchors 2,0 ANALYSIS 2.1 Piping Stresses and Loads 2.1.1 Basic Stress Criteria 2.1.2 Branch Bending Moments I
2.2 Nozzle Load Evaluation 10 2+3 Yalve Load Evaluation
~ 3.0 RESULTS OF STRESS ANALYSIS AND LOAD EVALUATIONS 14 3.1 Support Description and Load Summary 15 3.l.l Displacement at Supports 19 3.2 Stresses 24
'3.2.1 Height 3.2.2 Normal Operation
'.2.3 Most Severe Mode of Operation 3.2.4 OBE 3.2.5 SSE 3.3 De flecti ons 49 3.3.1 Hei ght 3.3.2 Normal Operation 3.3.3 Most Severe Mode of Operation 3.3.4 OBE 3.3.5 SSE 3.4 Valve Load Summary 64 SDTAR-80-05-05
- TABLE OF CONTENTS, I
PAGE APPENDIX A Allov able Stress / Response Spectra B MESTDYN Input Da'ta 73 C ISOMETRIC C-381-354, Sheet 1, Revision D 79
(
D REFERENCES 80 SDTAR-80.-05-05
- 1. 0 SYSTEM DESCRIPTION 1.1 Extent of Piping: [1j, $ 2j 10" line from intermediate anchor RH-9 to reactor coolant loop A.
There are no significant Branch'ines in this portion of the RHR piping. See drawing C-381-354.-1, Rev. D for details.
1.2 Specifications
[3j 10" AC-2501R Design Conditions: 680'F, 2510 psig Pipe: Seamless A376 Type 316 Schedule 160.
Fittings: Seamless, butt, weld A403 WP316, Schedule 160.
Flanges: Forged, welding neck, A182F316, 1500 O'F, Schedule 160.
1.3 Loading Conditions 1.3.1 Operating Modes The operating modes for the RHR system are summarized in reference (4). The environments for RHR 250 are listed under fl'uid line 1 where it extends from loop A to valve 701.
'the normal and most severe conditions are:
Fluid Line Temp. 'F Pr ess. PSIG Normal 612.2 2235 Loss of Load 1 643 2628 SDTAR-80-05-05
1.3.2 Seismic Environment D
The seismic envi'ronment is represented by linear acceleration response spectra at various floor elevations, linear accelerations due to torsiona1 response of the buiIding, and relative displacements of anchors and supports. The torsional response of the containment building and interior 'structure has negligible effect', due to the rigidity of these structures.
The response spectra and floor displacements are based on a dynamic response analysis'f the containment, interior structure or other building supporting seismic class piping. For this nroject, Gilbert Associates, Inc., has performed this analysis and summarized their results in Ginna Station Seismic Upgrading Program, Reactor Building Seismi'c Analysis, 'December 21, 1979.
That document provides response spectra along two orthogonal horizontal lines and'the vertical for each node in the GAI dynamic analysis. For piping which is attached between several node points, no single set of response spectra will adequately describe the piping environment. To assure conservative results in such cases, a combined spectrum for each direction is obtained by using the highest acceleration of any adjacent node at each frequency. The resul.t is a response spectra envelope.
For the subject system, the following building node points are adjacent to the piping or equipment supports:
BUILDING NODE ADJACENT PIPING SUPPORTS OR EQUIPMENT r+7z<l o~ svÃUc7vd /zan S DTAR-80-05-05
The response spectra, for these points and the response spectra envelope are shown graphically in Appendix A. The coordinate system for, these spectra is not, in general, coincident with the coordinate system used for the piping model. Figure A.2-2 jndicates the orientation of the horizontal axes of each'system. Prior to analysis, the piping system model is rotate) such that it aligns with the spectra coordinate. axes.
Note that it is sufficient to align -Z (piping) with Y (structural) since the signs are of no consequence in such an elastic, seismic anal ysi s.
Y (STRUCTURAL),
/
NORTH
/
/
/
/.
/
/
/
/ X (PIPING) 29' (STRUCTURAL)
Z (PIPING)
FIGURE A.2-2: COORDINATE SYSTEMS S DTAR-80-05-05
Rotation of the piping model by -29'ill align the two systems.
The displacements rela'tive to ground of the building structures at points of support or equipment attachment are summarized below:
SUPPORT OR EQUIPMENT VERT. R .10 R .10 R .1 SOPPY'7 rloogs y,c~j'. OC CW o. choo/
- Units: radians and inches Each displacement component at each location represents a separate loading condition. Only displacements which can be transferred to the pip ng through the supports are included. A vertical support, for instance, can only transfer vertical displacement from the building to the piping. The net effect of all component displacements at all points of support is estimated by summing the absolute value of the results for each component at each point.
SDTAR-80-05-05
To reduce the number of cases that must be considered, a suppo'rt (or group of supports with identical displacements) can be assigned zero .displacements. The other displacements are then reviseh;to give the same relative displacements.
Only the remaining non-zero displacements need be used as loading conditions. Farithe subject system, these relative displacements are given below:
RELATIVE DISPLACEMENT IN STRUCTURAL COORDINATES*
0,0'O 3 3 SUPPORT OR EQUIPMENT VERT. RX,10 Ry.10 RY,10 0, 00/ 0. doo ~ 2< .
Suan r -
sloops
- Zero displacement indicates attachment at the chosen base location.
Note that since these displacements are in structural coordinates, each component must be rotated +29'o the piping coordinates before inclusion in the piping model.
The subsequent rotation of the piping model will then result in specification of the displacements in the structural coordinates as indicated.
+Relative displacements as shown above are small (',ess than 1/16"), therefore, anchor displacements due to earthquake are included in the analysis.
SDTAR-80-05-05
1.4 Static Displacements The displacements 'of anchors due to thermal expansion and other static conditions are summarized iri, Table 1.4-1.
S DTAR-80-05-05 V
.TABLE 1'.4-l: STATIC DISPLACEMENTS SYSTEM: z /Z> < WEsT PREPARED BY aMo
-s'ECTION:
CHECKED BY:
REFERENCE(S): C81 cH ZZ ye ~ 7P (31- cio-zu.>s/ <~wc. ~>6 Compt. Therm. Thermal Growth
'quipment Descri pti on Node Mode DX DY DZ no. no. in in ln 5/o z '. w4/ -o.&8 9 -o. zr8-Thermal Mode I:
Thermal Mode II:
Thermal Mode III:
Thermal Mode IY:
..8$ X S DTAR-80-05-05
2.0 ANALYSIS .
2.1 Pi ping 2.1.1 Basic Stress Criteria ~
According to criteria established for this project, piping included in this scope is to satisfy the requirements of equations ll, 12 and either 13 or 14 of ANSI B3l.lb-1973, "Summer Addenda" to Power'.Piping ANSI 831.1-1973. These equations govern allowable moments due to sustained loads
- (deadweight), occasional loads {seismic), and thermal expansion loads, respectively. Relative seismic anchor displacement effects must be included'.in equations 12, 13 or 14.
Poo0 75 1 MA B31.1-11 z
n PD 0.75 i MA 0.75 i MB
+ + B31.1-12 z z.
n i M B31.1-13 Z A PDo 0 75 i MA i Mc 831.1-14 Z Z h A n
M A
= resultant moment due to weight and other sustained loads, in-lb.
M 8
= resultant moment due to occasional loads such as fluid flow transients and earthquake, in - lb.
M c
= range of resultant moments due to the thermal expansion, in - lb.
P = internal design pressure, psig SOTAR-80-05-05
h D
0
= outside diameter:of pipe, in.
tn'ominal wall thickness of component, in, stress intensification factor* from appendix D, B31.16 - 1973 0.75 i > 1.0 Z = section modulus, in's 3
described in B31.16 - 1973, section 104.8.4.B.
Sh
= basic material allowable stress at maximum temperature.
SA
= allowable stress range for expansion stresses.
k = 1.2 for occasional loads acting less than lA of the time.
Analytical procedures for=checking compliance with these equations include a distributed mass deadweight analysis, lumped mass
. response spectra seismic analysis, and a thermal flexibility analysis. These procedures g4~~are implemented by the computer program WESTDYN, which determines loads and displacements at all chosen cross< sections, associated stress levels as defined by equations 11,'2 and 13, and reactions at all support and equipment connections. MESTDYN input is prepared by program MESGEN from a data base established by program PAGES.
Three coordinate systems have been consolidated in this analysis.
The piping geometry is described in the PAGES program input using the GAI piping drawing coordinate system, with north along the negative Z axis. For inside containment systems, this data is altered using program ANZEIT which transforms the model to a system parallel to the GAI structural coordinate system, which has the positive Y axis inclined 29'ast (clockwise) of north. The SDTAR-80-05-05
piping geometry is thus specified in a coordinate system
'\
whose axes are parallel to the response spectra axes used by GAI for the 'containoient and interior structure. The third coordinate system is local and is described when used in this documentation. ~,
'.2 Nozzle Load Evaluation Loads imposed on equipment nozzles must meet the following criteria unless specific allowable loads are known, in which case those loads must not be exceeded.
(1) axial force L 0.01 S A Y
(2) bending moment 4 0.1 SYZ (3) torsional moment L 0.2 SYZ (4) shear force < 0.01 SYA where S Y
= yield stress of nozzle at operating temperature from ASNE Section III 2
cross sectional area of pipe, in
~
A =
Z = section modulus of pipe These allowables apply for the following loading conditions:
a) Normal condition -- deadweight plus maximum operating thermal b) Oesign condition OBE earthquake plus maximum operating thermal plus deadweight S DTAR-80-05-05 10
2.3 Valve Load Evaluation Valves are classified as either active or inactive. Operation of an active valve is required for a cold shutdown. All other valves are calssified as inactive;q For 'inactive valves, it is necessary to assure that the pipe valve,inferface meets the criteria for piping stresses. The valve load criteria discussed below apply only to active valves.
VALVE TYPE STRESS LIMITS ON VALVE ENDS Swing Check 0 max S Y
~bending '
0 torsion <0.50.5 S SY Safety, open %ax. ' ..
Safety, closed refer to vendor's specifications Other ~max '" Y
~bendin '
+torsion 0.50 S 0
max
= maximum principal stress
= - 2 2 2 0.5 (H + S + (H S ) + 4 S ) S 0-bbending di
= maximum fiber stress due to bending
= Mb/Z 0-ttension i
= maximum fiber stress due to torsion
= Mt/2Z SDTAR-80-05-05
S Y
= yield stress at design. temperature for ASNE SA-376, type 316 for stainless steel valves and ASIDE SA-106 grade B for carbon steel valves.
'a Z = section modulus of piping Mb
= resultant bending moment '
t = torsional moment H = P o t,ro 2
+ r.i 2 )/{ro 2 - r. 2 )], poop stress P = operating pressure 0
0
= pipe outside radius r.,1 = pipe inside radius L = P 0
Lr.1 /{r-0 -.' r. )], longitudinal pressure stress F =. Fx/A
'X
= axial load B =M/Z S
0
= F+B+L r
S torsion V = 2FS/A FS
= shear force SDTAR-80-05-05 l2
Active valves may bechecked for compliance with these criteria by manual calculhtion using loads from the piping analysis or automatically by using program VAlVE. This program is linked to the piping anlaysis output file from which it obtains all necessary load data for each valve.
SDTAR-80-05-05 13
Results of Stress Anal sis and Load Evaluations Stresses are satisfactory for all the loading conditions in the as-built system, however, valve 700.- does not satisfy the valve criteria. By removing the variable spring'anger RH-ll, the maximum principal stress at the end of valve 700 is reducecl significantly, while the stresses in the piping system still satisfy equations 1.1, 12, 13 or 14. RH-10 preloaded.
SDTAR-80-05-05 14
SUPPORT DESCRIPTIC,'i A"D LOAD S'"i'>'RY SYSTEH: PEST ause +rrs 7- Prwogra,~ PPEPARED BY: C'. ~>C SECTION: CHECKED BY:
. SUPPORT-DESCRIPTION LINE OF ACTION STIFFNESS ( ~/P'S bid )
Axial, Horizontal Transverse, Horizontal, Vertical Other (Specify)
Jt ~EX 61~/ i' 5 +tv '~ r )c 7/v'F/. ~'<. fic~ ~gg g/gQ g+g LOAOS (kips, in-kips)
FX cY I FZ NX HY I NZ ANALYSI S/tl0" E I
Deadv ei ght 2.22 t-///9 )// 2+ .29771 Is'7 7Z y6'c'~Qwz uuc I
SeisrtIic, OBE +/, gp ~4<> -"I~P.9 r Z+
Thermal I +7 o./3 I'74 Thermal I I 8.2/ 9~.K'//7,/t'eismic, Thermal III SSE -'>"-'n "F 3<l=g-'iy/.g THER,'ML I: s '-r. l-i<" <P'=<~:~'~~
THERMA'L I I:
THEVmL III:
SDTAR-80-05-05 15 RM-9
SUPPOR D S'IPTIOsl hssD L DAD SL~l-'Y SYSTEM: Res/auzc. ~~ra r pz~~c ac. PPEPARED BY: Q. n 'C~
SECTION: zo og g~o CHECKED BY: JCQ C '> ~ yo
" SUPPORT: 9- 9 C'c W r =so CC'HDS'ESCRIPTION LINE OF ACTION . STIFFNESS (+/l +//~ ~
Axial, Horizontal Transverse, Hori zontal
~ . Vertical Other (Specify) 0,'r r"P/'-: IR s AAWc.P 857 'KaQ ~g7rrr rg g ~ryan ~gg
.LOADS (kips, in-kips) (cc err@. eoozaiirrr z re= sr~ri"~ .
FX FY FZ MX MY I MZ ANALYSI S/NODE Deadweight' 0. /g o./6 /~.77 ~+88lil8 24'sJ Seismic. OBE j,g ~Z /
Thermal I P9. o rsvp Q5i /8 Thermal II 47+, d Thermal III Ev-C iuag Seismic, SSE f.8 7 THERMAL I: /k/'"> ~g-q<g gP~P'rjck/
THERMAL II: ~nsz os THERMAL III: gya(wZg7/c~ 2ooy + sos
~~v>O('s rCri~ >~~~
r w/~~~iom 4~. <<~'cwE SDTAR-80-05-05 16 r ~Arirr Q VO VfÃiVCE RH-9 C OHCV ~As S'W'7ro~ 2~
SUPPORT DESCCIPTIOi A'iD LgnD SU. r" PY s
SYSTEM: R~Si "c ~~ airer rs~uv~~ PREPARED BY: c~'Cv SECTION: CHECNED BY:
SUPPORT: A'h'-ZO DESCRIPTIOH I
LINE OF ACTION STIFFNESS ('<rr'S/<rr' Axial, Horizontal Transverse, Horizon al Vertical Other (Specify)
PE=SF i Z~~ a: l SZS g-ip' LOADS (kips, in-kips)
FX FY [ n yX MY i NZ ANALYSIS/HOD Dead~eight -/ 93 6'CnJC5M Woo Seisriic. OBE
~o.r+
Thermal I ~ -O.dc7 Thermal II -c7. 9/
Thermal II I Sei smi c, SSE THERMAL I: n'.i mn~ OP=-ar.-;i=el Indicate north THER~NL I I: ~ . -s o.
THERI"AL I I I:
C "9
SDTAR-BII-05-05 17
SUPPORT D".SCRIP IGli AND LOAD S""'RY SYSTEM-
'ECTION:
SUPPORT:
RFS/&4k? C.
)8>-/2
+/F87 // WO/tAL- PREPARED BY:
CHECKED BY. .f C'. n 'C>>
./ < <i'~
DESCRIPTION LINE OF ACTION STIFFr, ESS ( K/,"'5/ /rz )
Axial, Horizontal 58z Transverse,'Horizontal Vertical Other (Specify)
C CiCD C~wP ~ /J.".z s"c~i T~ / 4 ~ /~X C
LOABB (k i ps, i n-k i ps)
FX FY l FZ MX MY 1 MZ AHALYSI S/NODE Deadweight 0 dZ 87 )'/4~A W~ ~Wo Seismic s OB< ~ g~5>
Thermal I 7.+4 Thermal II c'.og Thermal III Sei smi c,, SSE ZG.so I
THERMAL I: rt 'i'"~:<s'- Cl~ZW/i7 Cn/
Indicate north THERYJlL II: o~ c~ caen 29' THERtNL III:
SDTAR-80-05-05 18
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APPENDIX A
'ALLOMABLE STRESS The allowable stresses for use with equations (ll),
(~14) of the Summer Addenda, Power Pi in ANSI 831.1 determined in accordance with the requirements of S B31.1-1973. Specifically,
'.SA ' (1.25Sc + 0.25 Sh SA allowable stress range S
C basic material allowable stress at minimum (
from the Allowable Stress Tables.
I Sh
= basic material allowable stress at maximum (
from the Allowable Stress Tables.
f = stress range reduction factor for cyclic cor number, N, of full temperature cycles over t years during which system is expected to be from Table 102.3.2,C. .
The Allowable Stress Tables are in Appendix A of BSl.l-l cycles are full temperature cycles, an equivalent number cycles is used to determine f.
N " NE rl 5
Nl r2 5
N2 ...rn 5 Nn where N E
= number of cycles at full temperature change.
expansion stress, SE, has been calculated by Eq. (13).
N 1...N N
n
= number of cycles at lesser temperature rl. r2..rn = sTl aTE'T2 aTE,...ATr aTE 65 SDTAR-80-05-05
Applicable values for this system are summarized in the following table.
Operating Mode i **
- c n i N
- l. ~c ss oa co8o 2.
3.
4, 5.
N = .zc 7c oo ri = l for the'mode with aT = aT E
~This value is NE for the mode with AT. = ATE.
Using this value of N, f as obtained from Table 102.32,C is t According to the indicated references, the materials used and the basic allowable stress and the allowable stress range from Eq.'1) are:
Material Ref. S Sh Ref. SA
- l. ggyp 7-y/gp/ C'- SZ/-Z~ -/ > /g T //iZ 31.1 page 9W 2.
3.
S DTAR-80-05-05 66
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SDTAR-80-05-05 Agp](i ]VKNI
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SEC'GRHR?
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RGRHR?<<SEvs 56V .Ov?2 ..4949 ]3,2bo 3.2]8 98.346 HGRHR2seSK 72 RGRHR?<<SKC'fy()
RGRHR2<<SE:i.; yg,l.vg Vku4ffA'i PAGES y4LyE NUHBER 7]V k(gkHR?oSK 73 RGRHR2 SK '. B<<4N78Fi'upt.S vul.pa<: .u K-l4db) 5 wEv< kGRHH2<<SK 74 RGRHR2<<SEvi bbu 57V ~ 0458
. I orb 13,25v 3,218 '98,346 R(iRHH2<<SK 75 RGRNR?<<SESi.i]u.~ >IV 59') kGRHk2<<SL 76 RGRHR2 SEii. -)y. IQH P)u 59V <<~3 ffl ci, 2'-'d eovdl 13~2'bv ].QVQE 03 RGHHR2<<SE 77 RGRHRZ<<SE,Si,'.t]u'i >IV eov RGRHR2<<SE 78 RGRHR2<<SEvi= yg SE-( r]u-;,
0)0 ou V evv V li?ff ~ 2765 ]3,?bo 3 ']B 'V8,346 R(ikHk2<<SE HGkHH2<<SE 79 80 RQRHRZ bev RGRHR2<<SEe> v~> o b]v pu57 ,r 184V 13,25v 3e2]8 98,S46 HGHHR?<<BK 8]
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UNLABELED JLDf'L SDTAR-80-05-05 HASTf' AUf) I Ti I "E> l 78 CA "0 > "L uf'DaTE 1,3~498q77 ~ 06/27/8 17 %
LIST uF Cu~r uL. AC f I V~~ af 0/UR I ~AG T I >96 1 HGRHR2~SE eb RGRHR2"SEEL VIV 6SV lsd 000 354 0 OPVO XGRHH2oSE 87 RGRHR2~SECR 0>o 660 0 F 0000 5 ~
kGRHR2+SE 88 RGRHR2~SESECTIU'i OO0 69V RGXHH2SE 89 OOV 670 0 0000 3,39o veooyo RGRHR2 SEGR ~
HGRHR2~SE 90 RGRHR2>SEI T OOV b70 le >00 XGRHR? SE 9l Oro 0,0000 .614 Ve0000 RGRHR2~8f:GR RGRHH2~SECH 68C'90 10.750o l. 12SV 12 'bo kGRlik2egE RGRHH2e OE 92 9$
OOV 0 0>>00 190 V S >>000 RGRHR2 ~ SECR ~ ~
XGHHk2~SE 94 RGRHR2 SESECT ION o90 9101 kGRHR2SE 95 OV0 700 0.0>>00 6bf 0.00vo RGRHR2~SE,CR ~
21050 kGRHH2eSE 96 RGRHR2~SECH 2>F300 Pi 10 kGRHR2 Sg, 97 RGRHR2~SEHA 12 2.68o 1642"e 1 98 RGRHR2 SECH !vv Plol Q F 0000 1 '17 OsOOVQ kGRHX2eSE JOlt HS V,V loy75 11125 JUINHS RGRMR2"SESR I'~0 910l g,n 1 ~ 417
SUMMARY
uF UPDATE. IOENTIFIERS>>ITHIN DECK ~ kGRHHi:~St.
IOENTIFIEX TUTAL ACT I~L RGRHR? SE, JOINTS LIS'I uF Gut,'f'<LE AC f IVt g AND/OR Ii4ACTIVE CAHD+ IN XGXHR2lgDK kGRHR2-~f.'GHHR2eOK RGRHR2 OK*DE.CK XGknk2 MK RGRHR2 OK~CALL RGRHR2 l p RGRHR2~OK4CALL RGRHX2"<<V RGRHR2-OK*CALL RURHR2~DK RGHHk2~UK RGHHk2 DK XGBHX2~DK 1
2 4
5 RGRHR2~OKEt<O XGXHK2aDK 6 RGRHR2 OK<<f;Uk SURTAX Y Ut't UAT4 IDf.VTIF I<MS iilT HI<~ DECK XbXHXC~UA IDEiw'f lF I gli TUf AL ACTI >t-'
kGRHX2~0t(
REFERFfICES
- 1. Piping IsM:etric C-301-354-1, Pevision D, Gilbert Associates, Inc.,
October 8, 1979.
- 2. F3ow DIagram 33013-436, Pevision E, Rochester Gas and Electric Corporaticn, 's nua.y 4, 1900.
- 3. Egu~i)rr..)it~Sio~ll".:".'pic;r>, 601, Revision ufo. 2 to E-Spec. G569866 k'estingf7ouse f'.i<.~:t7'ic l.orporation, Atomic Power Division, April 29, 1966.
- 4. Residual ffeat P~oioval System Anal sis Desi n Conditions, R. E, Gin>>a hucfear Pciier Plant, October, 1979.
S. Reactor "uildino Seismic Analysis Pesronse Spectra, Ginna'Station So>smic Upsy'd(l".ng Program, Gilbert associates, inc., December 21, 'I979.
- 6. Orthographic Piping Drawi'ng D-304-611, Revision VII, Gilber Associates, Inc.
- 7. Orthographic Piping Drawing D-304-612, Revision IV, Gilbert Associates, Inc.
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