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{{#Wiki_filter:REGULATORY le<FORMATION DISTRIBUTION SYS rM (RIDS)g ACCESSION NBR:7906210193 DOC~DATE: 79/06/18 NOTARIZED:
{{#Wiki_filter:REGULATORY le<FORMATION DISTRIBUTION SYS rM                   (RIDS) g ACCESSION NBR:7906210193                 DOC ~ DATE: 79/06/18       NOTARIZED: NO                     DOCKET" 0 F'ACIL:50-240 Robert Emmet Ginna Nuclear Planti Unit 1p Rochester                                 G   05000204 AUTH, NAME                 AUTHOR AFFILIATION NHITE REC it ~ D ~
NO DOCKET" 0 F'ACIL:50-240 Robert Emmet Ginna Nuclear Planti Unit 1p Rochester G 05000204 AUTH, NAME AUTHOR AFFILIATION NHITE it~D~Rochester Gas 8 Electric Corp.REC IP, NAME REC IP IENT AFFILIATION STELLOiV, Division of Operating Reactors SUBJECT;For wards addi info re P>'IR feedwater lines in r esponse to NRC 790525 request,H/3 oversize drawings, DISTRIBUTION CODE;A001S COPIES RECEIYED:LTR ENCL SIZE: TITLE: GENERAL DISTRIBUTION FOR AFTER ISSUANCE OF OPERATING LIC N 0 T E 8 0~sr~&#x17d;~~y~~m~m~~~j~wek+~~ge/y~~~~yel'pa~~~Qtw~~
IP, NAME Rochester Gas 8 Electric Corp.
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REC IP IENT AFFILIATION STELLOiV,                   Division of Operating Reactors SUBJECT;       For wards addi info re P>'IR feedwater lines in r esponse to                       NRC 790525     request,H/3 oversize drawings, DISTRIBUTION CODE; A001S               COPIES RECEIYED:LTR             ENCL           SIZE:
~ya\m~g~~~yy~~gowloNwpwohmm~w~~~
TITLE:     GENERAL DISTRIBUTION FOR AFTER ISSUANCE OF OPERATING                       LIC N0 TE 8 0 ~sr~'~ ~y ~~m~m~~~j~wek+~~ge/y~~~~yel'pa~~~Qtw~~ fyky&4f~~oyelwygmpf ~ya\m~g~~~yy~~gowloNwpwohmm~w~~~
RECIPIENT RECIPIENT COPIES ID.CODE/NAME ID CODE/NAME.
RECIPIENT                               RECIPIENT                   COPIES ID .CODE/NAME                           ID CODE/NAME.               LTTR ENCL ACTION:         05 BC     ORB WM INTERNAL: 01         EG   F   F           1      1      02 NRC PDR                      1      1 12 I                       2      2          TA/EDO                      1      1 15 CORE'ERF BR             1     1     16 AD SYS/PROJ                   1      1 17 ENGR BR                1            18 REAC SFTY BR                 1       1 19 PLANT SYS BR            1     1     20 EEB                          1       1 21 EFLT TRT SYS                  1     22 BRINKMAN                      1       1 EXTERNAL: 03 LPDR                          1             04 NSIC                          1       1
LTTR ENCL ACTION: 05 BC ORB WM INTERNAL: 01 EG F F 12 I 15 CORE'ERF BR 17 ENGR BR 19 PLANT SYS BR 21 EFLT TRT SYS EXTERNAL: 03 LPDR?3 ACRS 1 1 2 2 1 1 1 1 1 1 1 16 16 02 NRC PDR TA/EDO 16 AD SYS/PROJ 18 REAC SFTY BR 20 EEB 22 BRINKMAN 04 NSIC 1 1 1 1 1 1 1 1 1 1 1 1 1 1 lL>N RS'A~@TOTAL NUMBER OF COPIES REQUIRED: LTTR 38 ENCL 38  
                ?3 ACRS                  16    16 lL>N RS'A~@
'f~v>0 tC y ViZZZZ IiiiiiiiIiii il(ssisifkl(/iiiiiiiiiiiii ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.Y.14649 LEON D, WHITE, JR, VICE PRESIDENT TEI.ERIIONC AREA CODE Tld 546-2700 June 18, 1979 Mr.Victor Stello, Jr., Director U.S.Nuclear Regulatory Commission Division of Operating Reactors Office of Nuclear Reactor Regulation Washington, D.C.20555  
TOTAL NUMBER OF COPIES REQUIRED: LTTR                   38   ENCL       38
 
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y ViZZZZ       IiiiiiiiIiii il(ssisifkl( / iiiiiiiiiiiii ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.Y. 14649 LEON D, WHITE, JR,                                                             TEI.ERIIONC VICE PRESIDENT                                                      AREA CODE Tld   546-2700 June 18, 1979 Mr. Victor Stello, Jr., Director U.S. Nuclear Regulatory Commission Division of Operating Reactors Office of Nuclear Reactor Regulation Washington, D.C.                       20555


==Subject:==
==Subject:==
Victor Stello, Jr.letter dated May 25, 1979 Xnformation Requested on PWR Feedwater Lines R.E.Ginna Nuclear Power Plant, Unit No.1 Docket No.50-244  
Victor Stello, Jr. letter dated May 25, 1979 Xnformation Requested on PWR Feedwater Lines R.E. Ginna Nuclear Power Plant, Unit No. 1 Docket No. 50-244
 
==Dear Mr.                    Stello:==
 
Enclosed is            a copy of our response to the subject letter.
Very  truly yours, P
L. D. White, Jr.
Enclosure
 
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Response  to Victor Stello, Jr. Letter Dated May 25,        1979 Information Requested on PWR Feedwater Lines R.E. Ginna Nuclear Power Plant, Unit No. 1 Docket No. 50-244 Desicen Gilbert Associates drawing D-304-083 shows plan views of the main feedwater piping to steam generators A and B inside containment. The elevation views are shown in Sections D-D and A-A on Gilbert Associates drawing D-304-084.
Pipe supports FW  1, 2, 4, 6, 10, 81, 80, 8 and 7 are spring hangers. Pipe restraints FW  3, 5, and 9 are snubbers. There are no valves located in the main feedwater piping  inside  containment. Details of the pipe and fittings are contained in Gilbert Associates Line Specification No.
900-1. Copies of the drawings and line specification are enclosed.
: 2. (a)  The  results of the original piping stress analyses for Ginna  Station may be found in a June 9, 1969 submittal to the AEC entitled "Additional Information on Seismic Design of Class I Piping". Additional stress analyses of the main feedwater piping inside containment were performed in 1973 and 1976. A summary of the stresses      calculated in the most recent analyses is      shown below:
Thermal            Pressure      Deadweight Stress              Stress          Stress SG1A Maximum    3979  psi        2858  psi      480  psi Nozzle      1488              2858            250 SG1B Maximum    3846              2858            695 Nozzle      1184              2858            388 (b)  Fatigue analyses have been performed for portions of the main steam and feedwater piping at Ginna Station. However, the main feedwater piping inside containment was not included in these analyses.
Fabrication H~istor
: 1. (a)  The feedwater  ring  and thermal  sleeve material is    ASTM A106 Grade B.
(b)  The steam generator feedwater nozzles are SA 336, Code Case 1332, Para. 5a-5d.      This material was later incorpo-rated in the Code as SA 508 Class 2.
(c)  The main  feedwater  piping is  ASTM A106  Grade C, seamless pipe with  ASTM A234  Grade  WPB  pipe  fittings.
 
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: 2. (a)  Feedwater nozzle  to pipe elbow welds were made using gas tungsten arc welding (GTAW) with a backing ring for the root pass and shielded metal arc welding (SMAW) for com-pletion. The filler metal was E7018. Preheat was main-tained at > 200'F and post weld heat treatment was at 1150'F + 25'F. The weld ends were a J-groove with a 1/16 inch land as shown in detail G of drawing D-304-084.
(b) Piping welds made using GTAW with a K insert for the root pass and SMAW for completion. The filler metal was E7018.
Preheat was maintained at P 75'F and post weld heat treat-,
ment at 1150'F + 25'f. The weld ends were compound groove with a 1/16 inch land as shown on Gilbert Associates drawing B-312-003.
(c) The sparger has a thermal sleeve which  is installed into the feedwater nozzle using a press fit.
: 3.      The feedwater nozzle to elbow, elbow to reducer, and reducer to piping welds at each steam generator were radiographically examined following original fabrication.
Those radiographs were recently reviewed and found acceptable as indicated in the attached letter to John C. Noon from Albert  E. Curtis dated June 1, 1979.
4 ~    The feedwater piping was fabricated to the requirements of ASA Code for Pressure Piping, B31.1-1955.
: 5.      Feedwater piping was specified as seamless ASTM A106-64 Grade C with supplementary tests S2, S3, and S4 to be performed on 'both ends of one length from each heat..
Preservice/Inservice Ins ection and 0 eratin Histor A preservice inspection in accordance with ASME BEPV Code, Section XI was not performed. Hydrostatic testing and radiographic examination of the feedwat,er piping welds as indicated in item B-3 above was performed.
2.(a) The B steam generator feedwater nozzle to pipe elbow weld was examined in 1976 using the magnetic particle technique and found acceptable.
(b) The 14  inch reducer to pipe weld near the B steam generator nozzle was radiographically examined in 1973 and ultra-sonically examined in 1976 following water hammer and vibrat,ion problems discussed below. The welds were found to be acceptable.
: 3. (a)  The feedwater nozzle to elbow, elbow to reducer, and reducer to pipe welds at each steam generator and the two feedwater pipe to containment penetration welds will be radiographically examined during the 1980 refueling outage.
The remainder of the feedwater piping inside containment will be examined over the  life of the plant. as required by ASME BGPV Code Section XI.
 
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The  feedwater  piping wel ds out sid e containment are being in accordance with the "Inservice Inspection inspected Plan for High Energy Piping Welds at Robert E. Ginna Nuclear Power Station". All welds in this program have been previously inspected at least once.        All design basis break locations will be    examined  once  more  during the 10 year inspection interval.
Two (2) transients which could be characterized as "water hammer" have occurred in the feedwater system at Ginna Station. The first transient occurred on July 22, 1973 and was reported to the U.S. Atomic Energy Commission in a letter dated August 21, 1973 to Mr. John F. O'eary, Director, Directorate of Licensing. The second occurred on June 17, 1975 and was reported to the U.S. Nuclear Regulatory Commission in a letter dated July 17, 1975 to Mr. Robert T. Carlson, Chief, Facilities Construction and Engineering Support Branch, Region I.
Flow induced vibration of the steam and feedwater piping at Ginna Station was experienced during the        first  few years of plant operation. An extensive program of vibra-tion monitoring, fatigue analysis,      and  modification    was performed to resolve this problem. The modifications included upgrading as well as addition of pipe supports and restraints. The results of the analyses showed that the additional stresses due to flow induced vibrations could safely be accommodated by the affected piping systems.
There have been two types of feedwater control used at Ginna Station. From startup to January 1978 hydrazine injection was used to control pH and oxygen. In 1978 a full flow deep bed polishing system was put on line and          pH control was changed to NH4OH addition.
The control parameters remained essentially the        same  for both periods:
: 1. pH                      8.8-9.2
: 2. dissolved oxygen      0-5 ppb
: 3. N2H4                  5-20 ppb From  startup until November 1974 small condenser leaks (C 0.25 gpm) were tolerated    until repairs could be made since sodium or chloride concentration increases were small ((1 ppb). From November 1974 until January 1978 all volatile treatment was used and any detectable leak (< 200 cc/min) was repaired within 24 hours.      Since 1978 the polishers have been in service continuously.
 
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SP-5291 12-23-66 4:2    Line  S  ecifications Line  S ecification  No. 900-1 Rating:    1550 psig/450~F Service:  Feedwater Steam Generator Vent Steam
    ~Pi e Seamless  Carbon  Steel, ASTM A106-64,    Grade  C 8" and  larger - Schedule 100 6" and smaller - Schedule 80 Supplementary tests S2, S3 and S4 shall be performed on both ends          of  one length from each heat on all sizes 2-1/2" and larger.
F~ittin  s 2-1/2"  and  larger -  Carbon Steel, ASTM A234, Grade WPB, same schedule as pipe, butt weld 2" and smaller      - Forged carbon  steel,  ASTM A234> Grade WPBy 3000 PSIp socket weld Joints 2-1/2"  and  larger - Butt weld 2" and  smaller      - Socket weld Flanged              - Forged Carbon Steel,    ASTM  A105-64, Grad'e  II, 2-1/2"  and larger -  900j/ R.F. welding neck 2" and  smaller    -  15008 socket weld Gaskets              - Flexitallic gasket Style    CG  Type 304 SS  and asbestos filler Stud Bolts          - ASTM  A193-62T, Grade B7 Hex Nuts            - ASTM  A194-62T, Grade 2 GILBERT ASSOCIATES, INC.
 
SP-5291 12-23-66 Line S  ecification  No. 900-1 (Cont'd.)
Valves 2" and Smaller            2-1/2"  and Lar  er Rating              600 PSI                    900 PSI Ends                Socket Weld              'utt  Weld Construction        OSS(Y                      OSRY Body                ASTM A105  Grade II        ASTM  A216, Grade  WCB Bonnet              Bolted                    Pressure Seal Stem                ASTM A182  Grade F6        ASTM  A182, Grade F6 Seating .
Stellite                  Stellite GILBERT ASSOCIATES, INC.
 
0 Rochester Gas and Electric Corporation Inter-OfFice Correspondence June 1, 1979
$ UgJQQT Review    of Feedwater Piping to S team Generator Nozzles Radiographs TO:      Jack C. Noon, Assistant Superintendent                            Ginna  Station On May 31, 1979 the radiographs of the feedwater piping to steam generator nozzle welds for both the A and B Steam Generator were reviewed to verify weld quality and that there are not any stress risers associated with original end prep, the welds reviewed were as follows and are shown on the attached Figures B-12 and B-13:                  '
A  S/G FW1001EE                              18" elbow to nozzle SFW1001DD10                          18."  elbow to reducer SFW1001DD9                            Reducer to 14" 'pipe B  S/G FW1005-BB                ~            18" elbow to nozzle SFW1005-AA7                          18" e.lbow .to reducer SFW1005-AA6                          Reducer to 14" pipe The  results of this review were very good. These welds are of excellent quality and the weld end preps show a smooth contour when comparing relative densities across the weld root to the end of the weld prep. Therefore, I .would con-clude that these welds are installed as designed and would not develop a similar problem as has been found at the D. C. Cook Nuclear Plant.
If you have any further questions, please contact me.
Albert  E. Curtis  III Welding  6 NDE  Engineer Level  III, RT
        .AEC:dmaE2 xc:    L. D..White, Jr.
L. S. Lang B. A. Snow J. E. Arthur
                ~. C.R;":Schuler'.
Huston C. R. Anderson M. J. Saporito
 
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I
 
FW IOOI Z3-PH FW  1001 24 SFW    1001 88 3 FW  1001 Z3                          FW 1001  AA                                        FW    lool    CC FW 1001 A A PS                            FW    1001 CC    PH FW IOOI ZZ FW IOOI X SFW    1001 CCI FW 1001 W            FW 1001  ZI SFW  1001 882-PH FW 1001  Y                                                                              SFW 1001 CC2 SFW    1001    CC2  PH FW 1001 OD FW    1001 DD      PH Og4 SFW 1001 DDI e                                                                                  SFW 1001 Oo 2 FW 1001 2 FW 1001  88 4'p SFW  IOOI 882                                                SFW    1001 EE Cg SFW I OOI 003
                                                                                                  /p              SFW      1001 DDIO SFW 1001 DD3-PH                                            /eh SFW  1001  DD4 SFW  IOOI DD 5                                                IS X  14  REDUCER SFW 1001  006 SFW 1001    009 NOMNAL DIAMETER        14        IB                                                              /y SCI IEOILE            100        100                                                                    Srw IOOI OOB NNAIML THICIQIESS      0.838    1.156 SFW    1001 ODT MATERIAL              C/8 I4    FEEDWATER      LOOP    A STANNRD FEE OWA TER R. E. GINNA F. CASTRO
                                                                                                    . 30 MAY 75 A-3084 950 FIGURE    8-12


==Dear Mr.Stello:==
V ~
Enclosed is a copy of our response to the subject letter.Very truly yours, P L.D.White, Jr.Enclosure tI 4 4>v)~e ,I Response to Victor Stello, Jr.Letter Dated May 25, 1979 Information Requested on PWR Feedwater Lines R.E.Ginna Nuclear Power Plant, Unit No.1 Docket No.50-244 Desicen Gilbert Associates drawing D-304-083 shows plan views of the main feedwater piping to steam generators A and B inside containment.
NOMBIAL IXAMETER         14             18 SCHEOVLE                100           100 HOMINAL THICKNESS        0.958       1.15 6 MATERIAL                C/5             C/5                       rw 1005-nn-ps sfnenko                                                            SFW 1005 AAI FW   1005- W   Pl 1 FW 1005- AA FW   1005   W SFW   100$    Aaf                          100$
The elevation views are shown in Sections D-D and A-A on Gilbert Associates drawing D-304-084.
SFW       AA2 FW  100$ -V-PS SFW 1005-21 sTEAM GENERATOR IB                                                     PEH. 404 CONf. ON   SIEET   2 18  XI4 REOVC ER FW   1005   WI FW   1005 88                                                                    FW  1005    X sFw    loos  AAB                                                                    SFW   1005- XI SFW    1005 AAS SF W  1005-AA4                                                                        FW 1005- 2 SFW   1005-Y2-PH SFW   1005-Ans                                                                        SFW  ICOS-XI-PH SFW    1005 - Y2 I'W  100$ -Yl FW    1005-  Y X = SUPPORT     MEMBER SFW    1005-  X2 l4     FEED WATER   LOOP   B INSIDE     CONTAINMENT                                FEEOWATER IL E. GINNA SIIEET  I  OF  2                                F. CASTRO 29   MAY 75 A-3084 948 FIGURE 8-13}}
Pipe supports FW-1, 2, 4, 6, 10, 81, 80, 8 and 7 are spring hangers.Pipe restraints FW-3, 5, and 9 are snubbers.There are no valves located in the main feedwater piping inside containment.
Details of the pipe and fittings are contained in Gilbert Associates Line Specification No.900-1.Copies of the drawings and line specification are enclosed.2.(a)The results of the original piping stress analyses for Ginna Station may be found in a June 9, 1969 submittal to the AEC entitled"Additional Information on Seismic Design of Class I Piping".Additional stress analyses of the main feedwater piping inside containment were performed in 1973 and 1976.A summary of the stresses calculated in the most recent analyses is shown below: Thermal Stress Pressure Stress Deadweight Stress SG1A Maximum 3979 psi 2858 psi 480 psi Nozzle 1488 2858 250 SG1B Maximum 3846 2858 695 Nozzle 1184 2858 388 (b)Fatigue analyses have been performed for portions of the main steam and feedwater piping at Ginna Station.However, the main feedwater piping inside containment was not included in these analyses.Fabrication H~istor 1.(a)The feedwater ring and thermal sleeve material is ASTM A106 Grade B.(b)The steam generator feedwater nozzles are SA 336, Code Case 1332, Para.5a-5d.This material was later incorpo-rated in the Code as SA 508 Class 2.(c)The main f eedwater piping is ASTM A106 Grade C, seamless pipe with ASTM A234 Grade WPB pipe fittings.
C A 1 A)/Jl v C II J'I 2.(a)Feedwater nozzle to pipe elbow welds were made using gas tungsten arc welding (GTAW)with a backing ring for the root pass and shielded metal arc welding (SMAW)for com-pletion.The filler metal was E7018.Preheat was main-tained at>200'F and post weld heat treatment was at 1150'F+25'F.The weld ends were a J-groove with a 1/16 inch land as shown in detail G of drawing D-304-084.(b)Piping welds made using GTAW with a K insert for the root pass and SMAW for completion.
The filler metal was E7018.Preheat was maintained at P 75'F and post weld heat treat-, ment at 1150'F+25'f.The weld ends were compound groove with a 1/16 inch land as shown on Gilbert Associates drawing B-312-003.(c)The sparger has a thermal sleeve which is installed into the feedwater nozzle using a press fit.3.The feedwater nozzle to elbow, elbow to reducer, and reducer to piping welds at each steam generator were radiographically examined following original fabrication.
Those radiographs were recently reviewed and found acceptable as indicated in the attached letter to John C.Noon from Albert E.Curtis dated June 1, 1979.4~5.The feedwater piping was fabricated to the requirements of ASA Code for Pressure Piping, B31.1-1955.
Feedwater piping was specified as seamless ASTM A106-64 Grade C with supplementary tests S2, S3, and S4 to be performed on'both ends of one length from each heat..Preservice/Inservice Ins ection and 0 eratin Histor 2.(a)A preservice inspection in accordance with ASME BEPV Code, Section XI was not performed.
Hydrostatic testing and radiographic examination of the feedwat,er piping welds as indicated in item B-3 above was performed.
The B steam generator feedwater nozzle to pipe elbow weld was examined in 1976 using the magnetic particle technique and found acceptable.(b)The 14 inch reducer to pipe weld near the B steam generator nozzle was radiographically examined in 1973 and ultra-sonically examined in 1976 following water hammer and vibrat,ion problems discussed below.The welds were found to be acceptable.
3.(a)The feedwater nozzle to elbow, elbow to reducer, and reducer to pipe welds at each steam generator and the two feedwater pipe to containment penetration welds will be radiographically examined during the 1980 refueling outage.The remainder of the feedwater piping inside containment will be examined over the life of the plant.as required by ASME BGPV Code Section XI.
o)'!x ,I 4 1 N'E P'S'I 1 l The f eedwater piping wel ds out sid e containment are being inspected in accordance with the"Inservice Inspection Plan for High Energy Piping Welds at Robert E.Ginna Nuclear Power Station".All welds in this program have been previously inspected at least once.All design basis break locations will be examined once more during the 10 year inspection interval.Two (2)transients which could be characterized as"water hammer" have occurred in the feedwater system at Ginna Station.The first transient occurred on July 22, 1973 and was reported to the U.S.Atomic Energy Commission in a letter dated August 21, 1973 to Mr.John F.O'eary, Director, Directorate of Licensing.
The second occurred on June 17, 1975 and was reported to the U.S.Nuclear Regulatory Commission in a letter dated July 17, 1975 to Mr.Robert T.Carlson, Chief, Facilities Construction and Engineering Support Branch, Region I.Flow induced vibration of the steam and feedwater piping at Ginna Station was experienced during the first few years of plant operation.
An extensive program of vibra-tion monitoring, fatigue analysis, and modification was performed to resolve this problem.The modifications included upgrading as well as addition of pipe supports and restraints.
The results of the analyses showed that the additional stresses due to flow induced vibrations could safely be accommodated by the affected piping systems.There have been two types of feedwater control used at Ginna Station.From startup to January 1978 hydrazine injection was used to control pH and oxygen.In 1978 a full flow deep bed polishing system was put on line and pH control was changed to NH4OH addition.The control parameters remained essentially the same for both periods: 1.pH 2.dissolved oxygen 3.N2H4 8.8-9.2 0-5 ppb 5-20 ppb From startup until November 1974 small condenser leaks (C 0.25 gpm)were tolerated until repairs could be made since sodium or chloride concentration increases were small ((1 ppb).From November 1974 until January 1978 all volatile treatment was used and any detectable leak (<200 cc/min)was repaired within 24 hours.Since 1978 the polishers have been in service continuously.
~4 E SP-5291 12-23-66 4:2 Line S ecifications Line S ecification No.900-1 Rating: 1550 psig/450~F Service: Feedwater Steam Generator Vent Steam~Pi e Seamless Carbon Steel, ASTM A106-64, Grade C 8" and larger-Schedule 100 6" and smaller-Schedule 80 Supplementary tests S2, S3 and S4 shall be performed on both ends of one length from each heat on all sizes 2-1/2" and larger.F~ittin s 2-1/2" and larger-Carbon Steel, ASTM A234, Grade WPB, same schedule as pipe, butt weld 2" and smaller-Forged carbon steel, ASTM A234>Grade WPBy 3000 PSIp socket weld Joints 2-1/2" and larger-Butt weld 2" and smaller Flanged-Socket weld-Forged Carbon Steel, ASTM A105-64, Grad'e II, 2-1/2" and larger-900j/R.F.welding neck 2" and smaller-15008 socket weld Gaskets-Flexitallic gasket Style CG Type 304 SS and asbestos filler Stud Bolts Hex Nuts-ASTM A193-62T, Grade B7-ASTM A194-62T, Grade 2 GILBERT ASSOCIATES, INC.
SP-5291 12-23-66 Valves Line S ecification No.900-1 (Cont'd.)Rating Ends Construction Body Bonnet Stem Seating.2" and Smaller 600 PSI Socket Weld OSS(Y ASTM A105 Grade II Bolted ASTM A182 Grade F6 Stellite 2-1/2" and Lar er 900 PSI'utt Weld OSRY ASTM A216, Grade WCB Pressure Seal ASTM A182, Grade F6 Stellite GILBERT ASSOCIATES, INC.
0 Rochester Gas and Electric Corporation Inter-OfFice Correspondence June 1, 1979$UgJQQT Review of Feedwater Piping to S team Generator Nozzles Radiographs TO: Jack C.Noon, Assistant Superintendent
-Ginna Station On May 31, 1979 the radiographs of the feedwater piping to steam generator nozzle welds for both the A and B Steam Generator were reviewed to verify weld quality and that there are not any stress risers associated with original end prep, the welds reviewed were as follows and are shown on the attached Figures B-12 and B-13: 'A S/G FW1001EE SFW1001DD10 SFW1001DD9 18" elbow to nozzle 18." elbow to reducer Reducer to 14"'pipe B S/G FW1005-BB~SFW1005-AA7 SFW1005-AA6 18" elbow to nozzle 18" e.lbow.to reducer Reducer to 14" pipe The results of this review were very good.These welds are of excellent quality and the weld end preps show a smooth contour when comparing relative densities across the weld root to the end of the weld prep.Therefore, I.would con-clude that these welds are installed as designed and would not develop a similar problem as has been found at the D.C.Cook Nuclear Plant.If you have any further questions, please contact me.Albert E.Curtis III Welding 6 NDE Engineer Level III, RT.AEC:dmaE2 xc: L.D..White, Jr.L.S.Lang B.A.Snow J.E.Arthur~.R;":Schuler'.
C.Huston C.R.Anderson M.J.Saporito H~I FW IOOI X FW 1001 W FW IOOI Z3-PH FW 1001 Z3 FW IOOI ZZ FW 1001 Z I FW 1001 Y FW 1001 24 FW 1001 AA FW 1001 A A PS SFW 1001 882-PH SFW 1001 88 3 FW lool CC FW 1001 CC PH SFW 1001 CCI SFW 1001 CC2 Og4 e FW 1001 2 FW 1001 88 SFW IOOI 882 SFW I OOI 003 SFW 1001 DD3-PH SFW 1001 DD4 SFW IOOI DD 5 SFW 1001 006 4'p Cg/p SFW 1001 CC2 PH FW 1001 OD FW 1001 DD PH SFW 1001 DDI SFW 1001 Oo 2 SFW 1001 EE SFW 1001 DDIO/eh IS X 14 REDUCER NOMNAL DIAMETER SCI IEOIL E NNAIML THICIQIESS MATERIAL STANNRD 14 IB 100 100 0.838 1.156 C/8 I4 FEEDWATER LOOP A SFW 1001 009/y Srw IOOI OOB SFW 1001 ODT FEE OWA TER R.E.GINNA F.CASTRO.30 MAY 75 A-3084 950 FIGURE 8-12 V~
NOMBIAL IXAMETER SCHEOVLE HOMINAL THICKNESS MATERIAL sfnenko 14 18" 100 100 0.958 1.15 6 C/5 C/5 SFW 100$Aaf rw 1005-nn-ps SFW 1005 AAI FW 1005-AA SFW 100$AA2 SFW 1005-21 F W 1005-W Pl 1 FW 1005 W FW 100$-V-PS sTEAM GENERATOR F W 1005 88 sFw loos AAB SFW 1005 AAS SF W 1005-AA4 SFW 1005-Ans SFW 1005-Y2 I'W 100$-Yl FW 1005-Y SFW 1005-X2 IB 18 XI4 REOVC ER PEH.404 CONf.ON SIEET 2 FW 1005 WI FW 1005 X SFW 1005-XI FW 1005-2 SFW 1005-Y2-PH SFW ICOS-XI-PH X=SUPPORT MEMBER l4 FEED WATER LOOP B INSIDE CONTAINMEN T SIIEET I OF 2 FEEOWATER IL E.GINNA F.CASTRO 29 MAY 75 A-3084 948 FIGURE 8-13}}

Latest revision as of 12:52, 4 February 2020

Forwards Addl Info Re PWR Feedwater Lines in Response to NRC 790525 request.W/3 Oversized Drawings
ML17244A558
Person / Time
Site: Ginna Constellation icon.png
Issue date: 06/18/1979
From: White L
ROCHESTER GAS & ELECTRIC CORP.
To: Stello V
Office of Nuclear Reactor Regulation
References
NUDOCS 7906210193
Download: ML17244A558 (17)
v • d • e


Text

REGULATORY le<FORMATION DISTRIBUTION SYS rM (RIDS) g ACCESSION NBR:7906210193 DOC ~ DATE: 79/06/18 NOTARIZED: NO DOCKET" 0 F'ACIL:50-240 Robert Emmet Ginna Nuclear Planti Unit 1p Rochester G 05000204 AUTH, NAME AUTHOR AFFILIATION NHITE REC it ~ D ~

IP, NAME Rochester Gas 8 Electric Corp.

REC IP IENT AFFILIATION STELLOiV, Division of Operating Reactors SUBJECT; For wards addi info re P>'IR feedwater lines in r esponse to NRC 790525 request,H/3 oversize drawings, DISTRIBUTION CODE; A001S COPIES RECEIYED:LTR ENCL SIZE:

TITLE: GENERAL DISTRIBUTION FOR AFTER ISSUANCE OF OPERATING LIC N0 TE 8 0 ~sr~'~ ~y ~~m~m~~~j~wek+~~ge/y~~~~yel'pa~~~Qtw~~ fyky&4f~~oyelwygmpf ~ya\m~g~~~yy~~gowloNwpwohmm~w~~~

RECIPIENT RECIPIENT COPIES ID .CODE/NAME ID CODE/NAME. LTTR ENCL ACTION: 05 BC ORB WM INTERNAL: 01 EG F F 1 1 02 NRC PDR 1 1 12 I 2 2 TA/EDO 1 1 15 CORE'ERF BR 1 1 16 AD SYS/PROJ 1 1 17 ENGR BR 1 18 REAC SFTY BR 1 1 19 PLANT SYS BR 1 1 20 EEB 1 1 21 EFLT TRT SYS 1 22 BRINKMAN 1 1 EXTERNAL: 03 LPDR 1 04 NSIC 1 1

?3 ACRS 16 16 lL>N RS'A~@

TOTAL NUMBER OF COPIES REQUIRED: LTTR 38 ENCL 38

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y ViZZZZ IiiiiiiiIiii il(ssisifkl( / iiiiiiiiiiiii ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.Y. 14649 LEON D, WHITE, JR, TEI.ERIIONC VICE PRESIDENT AREA CODE Tld 546-2700 June 18, 1979 Mr. Victor Stello, Jr., Director U.S. Nuclear Regulatory Commission Division of Operating Reactors Office of Nuclear Reactor Regulation Washington, D.C. 20555

Subject:

Victor Stello, Jr. letter dated May 25, 1979 Xnformation Requested on PWR Feedwater Lines R.E. Ginna Nuclear Power Plant, Unit No. 1 Docket No. 50-244

Dear Mr. Stello:

Enclosed is a copy of our response to the subject letter.

Very truly yours, P

L. D. White, Jr.

Enclosure

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Response to Victor Stello, Jr. Letter Dated May 25, 1979 Information Requested on PWR Feedwater Lines R.E. Ginna Nuclear Power Plant, Unit No. 1 Docket No. 50-244 Desicen Gilbert Associates drawing D-304-083 shows plan views of the main feedwater piping to steam generators A and B inside containment. The elevation views are shown in Sections D-D and A-A on Gilbert Associates drawing D-304-084.

Pipe supports FW 1, 2, 4, 6, 10, 81, 80, 8 and 7 are spring hangers. Pipe restraints FW 3, 5, and 9 are snubbers. There are no valves located in the main feedwater piping inside containment. Details of the pipe and fittings are contained in Gilbert Associates Line Specification No.

900-1. Copies of the drawings and line specification are enclosed.

2. (a) The results of the original piping stress analyses for Ginna Station may be found in a June 9, 1969 submittal to the AEC entitled "Additional Information on Seismic Design of Class I Piping". Additional stress analyses of the main feedwater piping inside containment were performed in 1973 and 1976. A summary of the stresses calculated in the most recent analyses is shown below:

Thermal Pressure Deadweight Stress Stress Stress SG1A Maximum 3979 psi 2858 psi 480 psi Nozzle 1488 2858 250 SG1B Maximum 3846 2858 695 Nozzle 1184 2858 388 (b) Fatigue analyses have been performed for portions of the main steam and feedwater piping at Ginna Station. However, the main feedwater piping inside containment was not included in these analyses.

Fabrication H~istor

1. (a) The feedwater ring and thermal sleeve material is ASTM A106 Grade B.

(b) The steam generator feedwater nozzles are SA 336, Code Case 1332, Para. 5a-5d. This material was later incorpo-rated in the Code as SA 508 Class 2.

(c) The main feedwater piping is ASTM A106 Grade C, seamless pipe with ASTM A234 Grade WPB pipe fittings.

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2. (a) Feedwater nozzle to pipe elbow welds were made using gas tungsten arc welding (GTAW) with a backing ring for the root pass and shielded metal arc welding (SMAW) for com-pletion. The filler metal was E7018. Preheat was main-tained at > 200'F and post weld heat treatment was at 1150'F + 25'F. The weld ends were a J-groove with a 1/16 inch land as shown in detail G of drawing D-304-084.

(b) Piping welds made using GTAW with a K insert for the root pass and SMAW for completion. The filler metal was E7018.

Preheat was maintained at P 75'F and post weld heat treat-,

ment at 1150'F + 25'f. The weld ends were compound groove with a 1/16 inch land as shown on Gilbert Associates drawing B-312-003.

(c) The sparger has a thermal sleeve which is installed into the feedwater nozzle using a press fit.

3. The feedwater nozzle to elbow, elbow to reducer, and reducer to piping welds at each steam generator were radiographically examined following original fabrication.

Those radiographs were recently reviewed and found acceptable as indicated in the attached letter to John C. Noon from Albert E. Curtis dated June 1, 1979.

4 ~ The feedwater piping was fabricated to the requirements of ASA Code for Pressure Piping, B31.1-1955.

5. Feedwater piping was specified as seamless ASTM A106-64 Grade C with supplementary tests S2, S3, and S4 to be performed on 'both ends of one length from each heat..

Preservice/Inservice Ins ection and 0 eratin Histor A preservice inspection in accordance with ASME BEPV Code,Section XI was not performed. Hydrostatic testing and radiographic examination of the feedwat,er piping welds as indicated in item B-3 above was performed.

2.(a) The B steam generator feedwater nozzle to pipe elbow weld was examined in 1976 using the magnetic particle technique and found acceptable.

(b) The 14 inch reducer to pipe weld near the B steam generator nozzle was radiographically examined in 1973 and ultra-sonically examined in 1976 following water hammer and vibrat,ion problems discussed below. The welds were found to be acceptable.

3. (a) The feedwater nozzle to elbow, elbow to reducer, and reducer to pipe welds at each steam generator and the two feedwater pipe to containment penetration welds will be radiographically examined during the 1980 refueling outage.

The remainder of the feedwater piping inside containment will be examined over the life of the plant. as required by ASME BGPV Code Section XI.

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The feedwater piping wel ds out sid e containment are being in accordance with the "Inservice Inspection inspected Plan for High Energy Piping Welds at Robert E. Ginna Nuclear Power Station". All welds in this program have been previously inspected at least once. All design basis break locations will be examined once more during the 10 year inspection interval.

Two (2) transients which could be characterized as "water hammer" have occurred in the feedwater system at Ginna Station. The first transient occurred on July 22, 1973 and was reported to the U.S. Atomic Energy Commission in a letter dated August 21, 1973 to Mr. John F. O'eary, Director, Directorate of Licensing. The second occurred on June 17, 1975 and was reported to the U.S. Nuclear Regulatory Commission in a letter dated July 17, 1975 to Mr. Robert T. Carlson, Chief, Facilities Construction and Engineering Support Branch, Region I.

Flow induced vibration of the steam and feedwater piping at Ginna Station was experienced during the first few years of plant operation. An extensive program of vibra-tion monitoring, fatigue analysis, and modification was performed to resolve this problem. The modifications included upgrading as well as addition of pipe supports and restraints. The results of the analyses showed that the additional stresses due to flow induced vibrations could safely be accommodated by the affected piping systems.

There have been two types of feedwater control used at Ginna Station. From startup to January 1978 hydrazine injection was used to control pH and oxygen. In 1978 a full flow deep bed polishing system was put on line and pH control was changed to NH4OH addition.

The control parameters remained essentially the same for both periods:

1. pH 8.8-9.2
2. dissolved oxygen 0-5 ppb
3. N2H4 5-20 ppb From startup until November 1974 small condenser leaks (C 0.25 gpm) were tolerated until repairs could be made since sodium or chloride concentration increases were small ((1 ppb). From November 1974 until January 1978 all volatile treatment was used and any detectable leak (< 200 cc/min) was repaired within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Since 1978 the polishers have been in service continuously.

~

4 E

SP-5291 12-23-66 4:2 Line S ecifications Line S ecification No. 900-1 Rating: 1550 psig/450~F Service: Feedwater Steam Generator Vent Steam

~Pi e Seamless Carbon Steel, ASTM A106-64, Grade C 8" and larger - Schedule 100 6" and smaller - Schedule 80 Supplementary tests S2, S3 and S4 shall be performed on both ends of one length from each heat on all sizes 2-1/2" and larger.

F~ittin s 2-1/2" and larger - Carbon Steel, ASTM A234, Grade WPB, same schedule as pipe, butt weld 2" and smaller - Forged carbon steel, ASTM A234> Grade WPBy 3000 PSIp socket weld Joints 2-1/2" and larger - Butt weld 2" and smaller - Socket weld Flanged - Forged Carbon Steel, ASTM A105-64, Grad'e II, 2-1/2" and larger - 900j/ R.F. welding neck 2" and smaller - 15008 socket weld Gaskets - Flexitallic gasket Style CG Type 304 SS and asbestos filler Stud Bolts - ASTM A193-62T, Grade B7 Hex Nuts - ASTM A194-62T, Grade 2 GILBERT ASSOCIATES, INC.

SP-5291 12-23-66 Line S ecification No. 900-1 (Cont'd.)

Valves 2" and Smaller 2-1/2" and Lar er Rating 600 PSI 900 PSI Ends Socket Weld 'utt Weld Construction OSS(Y OSRY Body ASTM A105 Grade II ASTM A216, Grade WCB Bonnet Bolted Pressure Seal Stem ASTM A182 Grade F6 ASTM A182, Grade F6 Seating .

Stellite Stellite GILBERT ASSOCIATES, INC.

0 Rochester Gas and Electric Corporation Inter-OfFice Correspondence June 1, 1979

$ UgJQQT Review of Feedwater Piping to S team Generator Nozzles Radiographs TO: Jack C. Noon, Assistant Superintendent Ginna Station On May 31, 1979 the radiographs of the feedwater piping to steam generator nozzle welds for both the A and B Steam Generator were reviewed to verify weld quality and that there are not any stress risers associated with original end prep, the welds reviewed were as follows and are shown on the attached Figures B-12 and B-13: '

A S/G FW1001EE 18" elbow to nozzle SFW1001DD10 18." elbow to reducer SFW1001DD9 Reducer to 14" 'pipe B S/G FW1005-BB ~ 18" elbow to nozzle SFW1005-AA7 18" e.lbow .to reducer SFW1005-AA6 Reducer to 14" pipe The results of this review were very good. These welds are of excellent quality and the weld end preps show a smooth contour when comparing relative densities across the weld root to the end of the weld prep. Therefore, I .would con-clude that these welds are installed as designed and would not develop a similar problem as has been found at the D. C. Cook Nuclear Plant.

If you have any further questions, please contact me.

Albert E. Curtis III Welding 6 NDE Engineer Level III, RT

.AEC:dmaE2 xc: L. D..White, Jr.

L. S. Lang B. A. Snow J. E. Arthur

~. C.R;":Schuler'.

Huston C. R. Anderson M. J. Saporito

H ~

I

FW IOOI Z3-PH FW 1001 24 SFW 1001 88 3 FW 1001 Z3 FW 1001 AA FW lool CC FW 1001 A A PS FW 1001 CC PH FW IOOI ZZ FW IOOI X SFW 1001 CCI FW 1001 W FW 1001 ZI SFW 1001 882-PH FW 1001 Y SFW 1001 CC2 SFW 1001 CC2 PH FW 1001 OD FW 1001 DD PH Og4 SFW 1001 DDI e SFW 1001 Oo 2 FW 1001 2 FW 1001 88 4'p SFW IOOI 882 SFW 1001 EE Cg SFW I OOI 003

/p SFW 1001 DDIO SFW 1001 DD3-PH /eh SFW 1001 DD4 SFW IOOI DD 5 IS X 14 REDUCER SFW 1001 006 SFW 1001 009 NOMNAL DIAMETER 14 IB /y SCI IEOILE 100 100 Srw IOOI OOB NNAIML THICIQIESS 0.838 1.156 SFW 1001 ODT MATERIAL C/8 I4 FEEDWATER LOOP A STANNRD FEE OWA TER R. E. GINNA F. CASTRO

. 30 MAY 75 A-3084 950 FIGURE 8-12

V ~

NOMBIAL IXAMETER 14 18 SCHEOVLE 100 100 HOMINAL THICKNESS 0.958 1.15 6 MATERIAL C/5 C/5 rw 1005-nn-ps sfnenko SFW 1005 AAI FW 1005- W Pl 1 FW 1005- AA FW 1005 W SFW 100$ Aaf 100$

SFW AA2 FW 100$ -V-PS SFW 1005-21 sTEAM GENERATOR IB PEH. 404 CONf. ON SIEET 2 18 XI4 REOVC ER FW 1005 WI FW 1005 88 FW 1005 X sFw loos AAB SFW 1005- XI SFW 1005 AAS SF W 1005-AA4 FW 1005- 2 SFW 1005-Y2-PH SFW 1005-Ans SFW ICOS-XI-PH SFW 1005 - Y2 I'W 100$ -Yl FW 1005- Y X = SUPPORT MEMBER SFW 1005- X2 l4 FEED WATER LOOP B INSIDE CONTAINMENT FEEOWATER IL E. GINNA SIIEET I OF 2 F. CASTRO 29 MAY 75 A-3084 948 FIGURE 8-13

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