PLA-2357, Forwards Rev 1 to Inservice Insp Program Plan & Response to 840912 Request for Addl Info on Program.Rev to Program Is Result of Addl Relief Requests Identified & Editorial Changes Deemed Necessary.Fee Paid
| ML18040B093 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 12/19/1984 |
| From: | Curtis N PENNSYLVANIA POWER & LIGHT CO. |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17139C765 | List: |
| References | |
| PLA-2357, NUDOCS 8412270395 | |
| Download: ML18040B093 (53) | |
Text
REGUt ATO INFORMATION DISTRIBUTION STEM (RIDS)
ACCESSiON NBR; 8412270395 DOC ~ DATE: 84/12/19 NOTARIZED; NO DOCKET FACIL:50-387 Susquehanna Steam Electric Stations Unit 1~ Pennsylva 05000387 AUTH BYNAME AUTHOR AFFILIATION CURTIS~N,Ns Pennsylvania Power Il Light Co, RECIP,NAME RECIPIENT AFFILIATION 8
SCHHENCERzAs Licensing Branch 2
SUBJECT:
Forwards Rev 1 to inservice insp program plan 8 response tol0912 request for addi info on program,Rev to program is :
"-=-
result of addi relief requests identified 8.editorial changes deemed necessary,Fee paid>
orslsisovioN coos:
Aosvo copiss Rscsivso:cvR J ENcc L srzs: /~s @
TITLE:
OR Submittal: Inservice Inspection/Testing RECIPIENT ID CODE/NAME NOTES! 1cy NMSS/FCAF/PM, LPDR 2cys Transcripts.
OLs07/17/82 5~ "SW WaPc~~s RECIPIENT COPIES ID CODE/NAME LTTR ENCL NRR LB2 BC 01 7
I COPIES LTTR ENCL 05000387 INTERNALs ACRS ELD/HDSQ N
~TEB EG F I I 16 10 1
19 1
04 1
1 ADM/LFMB NRR/DE/MEB 15 NRR/DL/TAPMG RGN1 EXTERNAL LPDR NSIC NOTES'3 2
2 05 3
NRC PDR NTIS 02 TOTAL NUMBER OF COPIES REQUIRED:
ITTR 32 ENCL
Pennsylvania Power & Light Company Two North Ninth Street
~ Allentown, PA 18101
~ 215 i 7705151 Norman W. Curtis Vice President-Engineering
& Construction-Nuclear 215/770-7501 DEC g g )98]
Director of Nuclear Reactor'Regulation Attention:
Mr. A. Schwencer, Chief Licensing Branch No.
2 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20555 SUSQUEHANNA STEAM ELECTRIC STATION REQUEST FOR ADDITIONAL INFORMATION ON UNIT 1 ISI RESPONSE
& REVISION 1
TO UNIT 1 ISI PROGRAM PLAN ER 100450 FILE 841-4
&,4899 PLA-2357 Docket No. 50-387
Reference:
(1) PLA-1732 dated 6/30/83 (2) Letter from A. Schwencer to N. Curtis dated 9/12/84.
Dear Mr. Schwencer:
Under Reference (1)
PP&L transmitted its Inservice Inspection Program for Susquehanna Unit 1 in accordance with License Condition 2.C.10 of Facility Operating License No. NPF-14 for your review and approval.
This letter transmits a revision to this program (Revision
- 1) and the response to your comments (Reference (2)) on our previous submittal of the program.
The revision to our program is the result of additional relief requests which have been identified and some minor nontechnical or editorial changes we deemed necessary.
Also attached are ISI Classification Boundary Drawings for your use.
Pursuant to 10CFR170.22, the appropriate fee is enclosed.
We trust the Commission will find this submittal satisfactory.
Very truly yours, N.
W. Curtis Vice President-Engineering
& Construction-Nuclear Attachments (see list of Attachments immediately following) cc:
M. J.
Campagnone NRC R.
H. Jacobs NRC Susq.
SES R. A. McBrearty NRC Region I 8412270395 841219 PDR ADOCK 05000387 8
List of Attachments Section 1:
Response
to Request for Additional Information on the Susquehanna Unit 1 ISI Program Section 2:
Susquehanna Unit 1 Inservice Inspection Program Rev.
1 (Note:
ISI Classification Boundary Drawings are enclosed as part of this revision and a list of these drawings follows this page.)
Attachment
//1 ISI-T-107.0, Component Listing & ISI 10 Year Plan Attachment
//2 Weld and Hanger Identification Isometrics Attachment
/f3 Component Identification Drawings Attachment
/l4 Selected Pages from ISI-T-111.0, Selection Document for ISI Class 1 Piping Welds, Category B-J Attachment 85 Selected Pages from ISI-T-113.0, Equivalent of One Loop Calculation of ISI Class 2 Piping and ISI-T-114.0, Selection Document for ISI Class 2 Piping Welds, Category C-F Attachment 86 PPKL ISI Ultrasonic Procedures
List of ISI Classification Boundary Dravings Enclosed ISI ORAWING NUMBER'NIT DEBC<9'PTICN I
i DRAbQNG NUMBER ISI.M.IOO I IS&%I.IOI~ "
ISHl.109 ISI.M4IO ISI-M-Ill-l ISIS.lll.2 ISI-M 112 ISI4l425.4 ISI M 125 5 Sl-I+04
~
SI.M.159 ISHl.141 ISHl 142 ISI-M-145 ISHH44 ISHI.I47 81-hH49 814l l50
'SI4H514 81+I-5I R ISI+I452 ISI4l455 ISHl 55 ISI-M.56 ISHHB6 SI-M.Rill ISIS.2112 I ANDR I AND 2 I AND 2 LEGEND lL'SYMBOLS MAIN STEAM SERVICE WATER SERVICK VIATER EMERGENCY SERVICE WATER EMERGENCY SERVICE Wl,TER RHR SERVIC.: YIATER PROCESS SAMPUIIG PROCESS SAflPLING DIESEI AUXILIARIES MSIV LEAKAGE COhTROL NUCLEAR BOILER NUCLEAR Boll ER VESSEL INSTRUMENTATION REACTOR RECIRCULATION REACTOR WATER CLEAlHJP CONTROL ROD DRIVE PART 8 STANDBY LIQUQ CONTROL.
REACTOR CORE ISOLATION COOLING RCIC TURBINE-PIMP RESIDUAL HEAT REMOVAL RESIDUAL HEAT REMOVAL CORE SPRAY FUEL POOL COOLING a CLEANUP HIGH PRESSURE COOLANT INJECTION HPCI TURBINE ANO PUMP CONTROL STRUCTURK CHILLED WATER EMERGKNCY SERVICE WATER RHR SERVICE WATER C.I95R50.1 C 195251 C 85252 C.I95P55 C.193254.1 C.85254.2 C.83235 C-83256 4 C.195236 5 CW5257 C 85256 C.195259 C-195240 C-195241 C-IM242 C-195245'-193244 C-193245-C-85R46 0 193R47.I C-193247 2 C.
195246'-195249 C. 195250 C-193251 C-195252 C. 193253 0195254
ATTACHMENT /l4 Selected pages from document ISI-T-110.0, Selection Document for ISI Class 1 Piping Welds, Category B-J.
ATTACHMENT 85 Selected pages from document ISI-T-113.0, Equivalent of One Loop Calculation of ISI Class 2 Piping; and ISI-T-114.0, Selection Document for ISI Class 2 Piping Welds, Category C-F.
~
P 5
t I
8 pgq N
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R0 4P '>/A't'ii 2 ~AS,W>'"
P)"2 IST-T-111. 0 Revision 1
( 114. 4001. 0219 )
SELECTION DOCUMENT FOR ISI CLASS 1
PIPING WELDS/
CATEGORY B-J SUSQUEHANNA STEAM ELECTRIC STATION UNIT 1
Prepared for:
Pennsylvania Power and Light Company Prepared by:
NUTECH Engineers, Inc.
Chicago, Illinois AE/SUPPLIER DOCUMENT REYIEW CATEOOROI
'~'ANVTACTVRIH/LPROCESSINO.
~US DAS INTENDED AYPROCEED. DOCVMENT MAYSE CATEOORY 2 AS NOTED IMAIIECHANCES AS
~OV'N ANDRESUSMIT1 MANVPACTVRIN(L PROCESSINO. ACTMTYMAYPROCEED.
DOCUMENT /WITH CHANCES> MAY8E CONSIDEREDACCEP'IED.
CATEOORYS
~~~/@
CORRECTANDRESVSMIT.
SHALLNOT PROCEED.
0 PROCESSINO, ACTIVITY CATEOORYI ~~~
ACCEPTANCE NOT li UKFOR L ORO PVRPOSES ONLY.
ACCEPTANCE OP THLS DOCVMENT/DNAWINO DOES NOT RE LIEYE AE/SUPPLIER PROM PULLCOMPLIANCEWITHCONTRACT OR PVRCHASE ORDER 8SOU IREMENTS, SIONATVRE P.O/CONTRACT H
,7 gi Prepared by:
Issu d by:
PPSL TWO ILNINTHST ALLENTOWN.PA I8IOI R.
C.
Bean Project Engineer J.
Mar in Engineeri g Director Approved by:
Date:
J.
M. Clauss, P. E.
Engineering Manager
0-
Q M 0 M W
v I
mv-I p V O
Isometric Number (Rev. no.)
System:
Core Spray TABLE 2.0-1 ISI CLASS 1
WELD COUNT
SUMMARY
B9.11 B9 ~ 12 B9 ~ 21 B9 ~ 22 B9 ~ 31 B9 32 B9 40 Number of Welds by Item Number ISI-DCA-107-1 (0)
ISI-DCA-107-2(0)
ISI-DCA-109-1 (0)
ISI-DCA-109-2( 0) 11 11 4
4 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 Total 30 Sys tern:
Feed@a ter ISI-DLA-101-1(0)
ISI-DLA-102-1(0)
ISI-DLA-103-1(0)
ISI-DLA-104-1( 0)
IS I-DLA-104-2( 0)
ISI-DLA-104-3 ( 0)
ISI-DLA-104-4(0) 6 40 6
11 11 11 9
0 1
0 1
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0
~
0 0
0 0
0 0
0 0
0 0
0 0
0 Total System:
High Pressure Coolant In ection IS I-DBA-102-1 ( 0) 12 Total 12 0
0 0
0 0
0 iI
Vl H
r-I lAr.
I p
CD TABLE 2'-2 Core Spray System Selections, Item No.
89 '
1 Weld Total =
30 25% of 30
~
8 WELD NUMBER 1 ~
DCA1071-FW-5 COMPONENT DESCRIPTION RED<<SE EKT SELECTION BASIS High Stress Intensity and High Cumulative Usage INTERSECTING LONGITUDINAL SEAM WELD (B9 ~ 12)
None 2.
DCA1072-FW-5 RED-SE EKT High Stress Intensity and High Cumulative Usage None 3
DCA1 071-1-B 4 ~
DCA1071-2-B 5 ~
DCA1072-1-A P>>RED Random Random Random None None None 6e DCA1072-2-A 7 ~
DCA1 091-1-D 8 ~
DCA1092-FH-4 E-P FH-P Random Random Random None None None SUMMARy OF SELECTED WELDS 1 ~
DCA1 07 1-FW-5 2 ~
DCA1071-1-B 3 ~
DCA1 071-2-B 4 ~
DCA107 2-FW-5 5
DCA1072-1-A 6
DCA1072-2-A 7 ~
DCA1091-1-D 8 ~
DCA1092-FW-4
CATSDOHT I CATfDORYf ASISVSSVfllOOCUAISHTHfylfly
~g. HAHVTACTVHIIHLAHQCSSSIHQ USSD AS IHTfHDfD
'~
AS HQTSDHAAHSCHAHQSSAS
~ VITHAHDIlfSVSVITT HAHVAACTUHVHf DQCUVCHT IITITHCHAHQSSI IAATSf AIIQCfSSHHL ACTIylyyIAATAHQCffD, CQHSIDfIISDACCtHIfD ACCfSTAHCS OfTIHSDOCUI4fHT/DHAIHWODOSS HOTIItUfyf AflSVSHVfHAIIQIASULI. CQIAAfIAHCSTTITHCQHTHACTQH AVHCHASfOHOSII HSOUVKIAfHTS ISI-T-113
~ 0 Revision 1
( 114. 4001. 0217)
SSSI TWOKINWTHST AAACTll~g+SIOI EQUIVALENT OP ONE LOOP CALCULATION FOR ISI CLASS 2 PIPING WELDS SUSQUEHANNA STEAM ELECTRIC STATION UNIT 1 Prepared for:
Pennsylvania Power a Light'ompany Prepared by:
'NUTECH Engineers, Inc..
Chicago, Illinois Prepared by:
M.
C auss, P.E.
Engineering Manager Issued by:
B. Martzn, P;E.
Engineering Director I
Approved by:
M. Claussf P.E.
Engineering Manager Date:
8/30/84 Deleted References to MSIV LC Loop F-
>A/ W
TABLE 2. 4 - /
SVSV~:CC/-e 5/(~y Sy>>~ O, Loo
- Summa, Item No. CJ, /J ASME Section XI', 1974 Edition Through Summer 1975 Addenda Equivalent of One Loop Calculation Per IWC-2411(b)
Revision 0
To4< 4 C'/~u~z
'Prepared by e/~ A Date Reviewed by Da e
System Circulates Reactor Coolant (25K of the equivalent of one loop to be examined each interval)
System Does Not Circulate Reactor Coolant (12.5X of the equivalent of one loop to be examined each interval)
Loop Number C5
-G~('S'c z
Cx'-&~
(".S'oJ" C~ Gers C~ $'og Equivalent of One Loop (8 of C
onents)
(3 Interval 8of Components o iw O.i~
a /~~
Oid~
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ISI-T-113.0 Revision dag/g64c:ncr pg..2 /
TABLE 3
. 0 SYSTEM: /pl-< Qp pq v 5'yZP<~,
Loon Summarv, Item No. C>. ~ (
/
ASME Section XI, 1974 Edition Through Summer 1975 Addenda Equivalent of One Loop Calculation Per IWC-2411(b)
Revision 0
Wohrp A 5'/~ass.
Prepared by iR'c. ~ 4 C Reviewed by eh/84 Date Date System Circulates Reactor Coolant (25K of the equivalent of one loop to be'examined each interval)
System Does Not Circulate Reactor Coolant (12.5X of the equivalent of one loop to be examined each interval)
Loop Number Equivalent of One Loop (8 of Co onents)
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3 SYSTEM: CPI r Zpl'Cp'p'Itls, Loo
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~
ASME Section XI, 1974 Edition Through Summer 1975 Addenda Equivalent of One Loop Calculation Per IWC-2411(b)
Revision 0
Ko/p~ A C'/uuzs Prepared by B/7 84 Date Reviewed by F'
Date Loop Description and Number System:
COI't Loop Description CD/ <
of Components in Each Loop Ncnber of Loops
~
Cr T/Oa 1 ~
CA b eS~ IOn
$r
~
7
~ '7e~
g~f-p~/ej g>)p S OC7/ah I
e Clrcnlates Reactor Coolant X
Does Not Clrcnlate Reactor Coolant E uivalent of One Loo Item Number 1 Loo No. of
.Ecpxiva-A
+
B
+
C
'+ 'D
+
E
+
F Total-. Loo s
~
lent C5. 11 C5.12 C5.'21 C5.22 C5. 31 C5.32 (1) 1980 Edition through and including Winter 1980 Addenda Item Numbers are used to determine examination requirements t
ISI-T-113. 0 Revision dag/g64c:ncr pg. 3-/w
Loop TABLE 2
. 6
- 2 (coot'd)
Number of Com onents, bv Item Number Isometric Number Rev Source C5.11 C5.12 C5.21 C5.22 C5.31 C5.32
+ Loop Q'&/
Zzz -
-ice-t."
PAL I I a
c>
e c
O Loop Loop ISI-T-113co Revision Ci dag/g64c:ncr
TABLE 3. 0 BFBTEM: C<fr ~Pro/ Kj'5 ~r+, Loo C Z C!FJ.
ASME Section XI, 1974 Edition Through Summer 1975 Addenda Equiv'alent of One Loop Calculation Per IWC-2411(b)
Revision 0
Ko$~ Q C'/cpugs.
Prepared by Date Reviewed by Date Loop Description and Number of Components in'ach Loop System.
CO/'
Number.of Loops Loop Description CPt f:
f.
c c7
~ ~
m T e condone 7+
70 7%hK Tg 7 88 7 c'c t) 738 gc'cT/oh
/
e Fc 7
c 5c;
~oh Circulates Reactor Coolant Does Not Circulate Reactor Coolant E uivalent of One Loo Item Number-1 Loon No.. of Eauiva-A
+
B
+
C
+
D
+
E
+
F Totslt.Loons lent C5. 11 C5. 12 C5.21 C5.22 C5.31 C5.32 (1) 1980 Edition through and including Winter 1980 Addenda Item Numbers are used to determine examination requirements t
ISI<<T-113. 0 Revision~
dag/g64c:ncr pg. 2-/7
TABLE ~.+ - Y (cont'd)
, +RN Cz trc R Ieamerric Number Rev pe HN-'ource Number of Comnonents bv T.tern Number C5.11 C5.12 C5.21 C5.22 C5.31 C5.32 c:
d o
d a
Loop buoy XSI-T-113e0 Revision Cr dag/g64c:ncr pg..g./P
TABLE 2.O STSTEM: Cute 5 arty SyJ"/c'In, Loo
( 5 ASME Section XI, 1974 Edition Through Summer 1975 Addenda Equivalent of One Loop Calculation Per IWC-2411(b)
Revision 0
To/p 4 C'l~uss Prepared by Nb/Z4 Date Reviewed by Date Loop Description and Number of Components in Each Loop System: Care'umber of Loore Loop Description Cut'e' Sc 0'
u f 7i'e
/l 7 e wain
/ht, Ta The )>
c.'gzjhc Circulates Reactor Coolant Does Not Circulate Reactor Coolant E uivalent of One Loo Item Number-1 C5.11 C5.12 C5.21 C5.22 C5.31 C5.32 Loo No.
of Equiva-A
+
B
+
C
+
D
+
E
+
F Total-. Loo s lent tcP6l 0 w~ =De-v (c
(1) 1980 Edit'on through and including Winter 1980 Addenda Item Numbers are used to determine examination requirements ISI-T-113. 0 Revision 0 dag/g64c:acr pg. 2-/7
~ Loop C5 lro 2 TABLE ~.~ - W (cont'd)
Number of Com onents, bv Item Number Reomecric Number Rev Source Ts'Z h9/.?joe-I 0
~PAL C5.11 C5.12 C5.21 C5.22 C5.31 C5.32 Q p C'~-&Z L5'2 h'88 /op a-0 Pj'r L C~
5 l"'
t.t o
C L..p Cj-6~~
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a o
g g
c!
C co ISI-T-113.0 Revision 0'ag/g64c:ncr pg. g-acr
TABLE ~CI SYSTEM: Col O 5 piO u t p rim ',
Looo Cf &'OP ASME Section XI, 1974 Edition Through Summer 1975 Addenda Equivalent of One Loop Calculation Per IWC-2411(b)
Revision
~oh< W. C'/russ Prepared by AT/7184 Date
- ~4>
Reviewed by Date Loop, Description and Number System:
Cc~rc 5'oop Description Cdi'e Centi 7o of Components in Each Loop Number of Loops ~'
c c i "Co
~on 3~~l~i-F~
Five Circulates Reactor Coolant Does Not Circulate Reactor Coolant E uivalent of One Loo Item Number-1
~ C5. 11 C5.12 Loo No. of Equiva-A
+
B
+
C
+
D
+
.E
+
F Total+Loo s
~
~j.~p 75~25 0
t 0
=
O'O-,
A"
= ID C5.21 C5.22 C5.31 C5.32 (1) 1980 Edition through and Mcluding Winter 1980 Addenda Ttem Numbers are used to determine examination requirements ISI-T-113.0 Revision G'ag/g64c:ncr
+ Loop Qo'<
Number of Comnonents, b
Item Number Teometrdc Number Eev Bource C5.11 C5.12 C5.21 C5.22 C5.31 C5.32 C'
pi<<
D Loop CS'Cc'+
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c 8d'/
7 z
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0 o
ci ci c7 0
ISX-T-113. 0 Revision O
dag/g64c:acr
TABLE 3
. 0 SYSTEM: Carr.sprue 5'y~yrm, Loan CS'oo ASME Section XI, 1974 Edition Through Summer 1975 Addenda Equivalent of One Loop Calculation Per IWC-2411(b)
Revision
.0 Wy/p+ C/ou~s Prepared by fy/~/Z4 Date Reviewed by Va e
Loop Description and Number of Components in Each Loop System:
CC'/'C' Number of Loops Loop Description C>r<
u c.
c~
hS.. "" CPIPtntcn
~oar T T e u;~
ot'r u
/-educer '~Tg<
~ 73~
c t'
7i ere Clroulates Reaotor Coolant~ Does Not Clroulate Reaotor Coolant E uivalent of One Loo Item Number-1 LOOD No. of Equiva-A
+
B
+
C
+
D
+
E
+
P Total-.'oo s
. len't C5. 11 I
C5. 12 C5.21 C5.22 C5.31 C5.32 (1) 1980 Edition through and including Winter 1980 Addenda Item Numbers are used to determine examination requirements ISI-T-113.0 u
Revision G
dag/g64c:ncr pg
TABLE~0
~ ( cour'd)
Loop CS'ipcod Isometric Number 25< -QP-Ie i
$$~ CZ()-ie'-2 Rev tp 0
Source Number of Components bv Item Number C5.11 C5.12 C5.21 C5.22 C5.31 C5.32 Loop C5
/duiM
.d ll 0
o d
a o
Loop Loop ISI-T-113eo Revision dag/g64c:acr pg 3 -Q+
TABLE ~C/
P SYSTRM: Cc>fe.gP/'oy J/J /r/Jl, Loo C+ C K ASME Section XI, 1974 Edition Through Summer 1975 Addenda Equivalent of One Loop Calculation Per IWC-2411(b)
Revision Wohn C fuus-~
Prepared by A//~//Zy Date Reviewed by Date Loop Description and, Number of Components in Each Loop opa H
c
/
/Z System: /'c'umber of Lo Loop Description dd'/'C o/Jc ter e
F /
/ ~J&c c fd c'c /
v
/ c~/o k8 Lice /Ue Clrcclates Reactor Coolact X Does Rot Clrcclate Reactor Coolact E uivalent of One Loo Item Number 1 Loon No. of Ecru.va-A
+
B
+
C
+
D
+
E
+
P Total-.'oons lent C5.11 C5.12 C5.21 C5.22 C5.31 C5.32
/
(1) 1980 Edition through and including Winter 1980 used to determine examination requirements Addenda Item Numbers are ISI-T-113.0
- Revision ~~,
dag/g64c:ncr
SABL'E 3
. 0 - f (cour'S)
A Loop CS'$'Og Isometric Number Rev Source Number of Components, bv Item Number C5.11 C5.12 C5.21 C5.22 C5.31 C5.32 0
Pj4lrl Q
0 PP~L 25'cA./o7)
~)
Pr~~i c'r' 0
0 Loop Loop ISI-T-113 c 0 Revision dag/g64c:ncr pg.
g d6
TABLE 2
. 0 S'YSTZM: Care Zp~o 5'p /~m, Loo CS
&Op7 ASME Section XI, 1974 Edition Through Summer 1975 Addenda Equivalent of One Loop Calculation Per IWC-2411(b)
Revision
~4< N C'hu~~
Prepazed by fp/7/fpSf Date Reviewed by g
F'ate Loop Description and Number of Components in Each Loop System:
~O~ < +
c Noebeo of Loope~
Loop Description 5 'orp. '.
~c
~
r 7
/ at. Fru Nc1 c'0 o/e f 0 7h t L. )
7.>>Ski C617 r ~
Circulates Reactor Coolant Does Not Circulate Reactor Coolant E uivalent of One Loo Item Number-1 C5. 11 C5.12 C5.21 C5.22 C5.31 C5.32 LOOD No.
of-Equiva-A
+
B
+
C
+
D
+
E
+
P
~ Total-.Loo s (1) 1980 Edition thzough and including Winter 1980 Addenda Item Numbers are used to determine examination requirements ISI-T-1'13. 0 Revision dag/g64c:ncz pg. 2 P7
+ Loop ~ Go7 TABLE 2
. 0 7
(coco'd)
Number of Comnonents, bv Item Number Isometric Number Rev Source C5.11 C5.12 C5.21 C5.22 C5.31 C5.32
+ Loop ~d'<7 0
0 G
0 Loop G')
g Ec Loop ISI-T-113e0 Revision dag/g64c:ncr
ISI-T-114 '
Revision 2
114.4001.0206 SELECTION DOCUMENT FOR ISI CLASS 2
PIPING WELDSF CATEGORY C-F Prepared for:
Pennsylvania Power and Light Company Prepared by:
NUTECH Engineers, Inc.
Chicago, Zllinoisl AONIFSUEIIOOCUNENT NKYIKW CATKOO~I
.KCCEETKO NANVFACIUSVAKFNOCKSS>>g VSEO AS INTKNOEO CATKOONYK
.yggy AS NOTES>>WCE CHANCES AS SSNNANIT1 NANVFACIVIIINQ,
~NOCKSstNQ. ACTMTYNAYFIIOCEEO.
COCVNKNTIWIINCHANOESI RAT SS CO>>SICK>>SO ACCKPLEO.
CATEOONTS Q+~~
CONIIKCTANONESUSANT.
I, IKFSOCESS>>NK, ACIIYllY CATKOONYA
~ ACCEPTANCE NOT
~VNFOSKS ONlY.
Prepared by:
Approved by:.
~SKKalNOIKNST>>EST AAKSFITOWIKFA 1 S101 7 S]
R.
C.
Bean Project Engineer J
B. Martin, P.E.
Engineering Director Approved by:
I/
F ~
J.
H. Clauss F
P. E.
Engineering Manager Date:
z7/g+
8/30/84 Deleted Loop
TABLE 2.0-3 Core S ra Selections, Cate o
C-F*
Total Welda to be Examined per Interval:
12 A.
Item No.
C5.11 Loop Number
~
Weld Number Component Descri tion Selection Basis CS-G01 1.
HBB1041-FW-6 2.
HBB104 2-2A-E T-P Terminal End-Containment Random CS-G02 3.
HBB1041-FW-3 P-T Random CS-G03 4 ~
HBB1042-4-B P-FL Terminal End-Pump CS-G04 5 ~
GBB1011-FW-5 6 ~
GBB1014-1-A P-FL Random Terminal. End-Pump CS-G05 7 ~
GBB1012-1-B 8 ~
GBB10 14-8-A P-FL Terminal End-Anchor P-FL Terminal End-Anchor CS-G06 9.
GBB1013-3A-B P-P Random CS-G07
.10 ~
GBB1032-FW-3 E-V Terminal End-Containment B.
Item No.
C5. 21 CS-G06 11.
DBB1131-1-B-C 12 'BB1132-FW-5 P-P Dissimilar Metal Welds P-P Dissimilar Metal Welds (1)
See Document ISI-T-113. 0 IS1-T-114.0 Revision 1
2-,7
Section 1
Response
to Request for Additional Information on the Susquehanna Unit 1 ISI Program The following information constitutes PP&L's response to your letter, A. Schwencer to N. Curtis dated 9/12/84.
Note that all information presented is based on the latest revision of the Susquehanna Unit 1 ISI Plan which follows this section.
ISI PROGRAM Question 81:
Although the initial ISI Program submittal contained a Section 5.0 titled, "Inservice Inspection Program Tables,"
a similar section was not included in the revised plan.
Provide a revised edition of these tables reflecting the current code requirements and the inspection isometric drawings, which are essential for the staff evaluation of the ISI Program.
Response
81:
f The format of "the ISI Program Plan was significantly revised since the initial submittal of 1/27/81.
The intent of the revised, latest format is to provide a brief summary of the applicable Code requirements for Susquehanna 1 and also provide an obvious indication via reference to a Relief Request - where Code requirements could not be met, thereby, illustrating complete compliance for those components not specifically called out for relief.
For a more in-depth view, attached please find "For Information" copies of the following documents:
Attachment 81)
ISI-T-107.0, Component Listing and ISI 10 Year Plan Attachment
//2)
Weld and Hanger Identification Isometrics Attachment
/f3)
Component Identification Drawings The above documents provide a comprehensive view of the Susquehanna 1 ISI Program by identifying all plant components subject to the examination requirements of ASME Section XI 80W80.
Question f/2:
The code requirements for extent and frequency of examination under examination Categories B-J and C-F, Pressure Retaining Welds in Piping, depend on the weld configuration.
In particular, welds in areas of high stress, dissimilar metal welds, welds at terminal ends and branch connections, and welds at structural discontinuities require examination during each interval.
In the material to be provided under 1 above, indicate the method that these specific requirements were applied to determine the extent and frequency of examinations under Categories B-J and C-F and illu~>>~+a hv exsmpl~
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Response
P2:
The selection basis for components within Code Categories BJ and CF are discussed in relief request BIRR-10 and IRR-3, respectively, in Section 7.0 of the Inservice Inspection Program Plan.
In addition, further clarification is presented in Notes 2 and 3 in Section 10.0.
Attached please find "For Information" excerpts from the following documents:
Attachment
/f4)
ISI-T-111.0, Selection Document for ISI Class 1
Piping Welds, Category B-J Attachment 85)
ISI-T-113.0, Equivalent of One Loop Calculation of ISI Class 2 Piping; and ISI-T-114.0, Selection Document for ISI Class 2 Piping Welds, Category CF.
These documents provide supporting documentation for all weld selections in Categories BJ and CF.
The Core Spray system has been arbitrarily chosen for an example.
Question f/3:
In the ISI Program, Table 6.0 page 8 of 18 omits "Code Category B-M-1, Item Number B12.31: Valves Nominal Pipe Size
> 4 in."
Please discuss the omission of this item.
Response
f/3:
Code Category B-M-1, Item Number B12.31 was inadvertently omitted from Table 6.0.
- However, no Susquehanna 1 components within the jurisdiction of the ISI program meet this description; therefore, the omission bears no impact on the Program.
This item will be added for completeness in a subsequent revision.
Question N4:
No examination procedures were referenced in the ISI Program that would allow the staff to determine that suitable ultrasonic procedures are being used for detecting inservice flaws.
Are the following documents that were cited during PSI review still applicable?
(a)
AI Nuclear Energy Services, Inc., Document No.
80A2770 Rev.
3 5/18/79:
Ultrasonic Examination, General Requirements, Pennsylvania Power and Light Company, Susquehanna Steam Electric Station Units 1 and 2.
(b)
AI Nuclear Energy Services, Inc., Document No.
80A2771 Rev. 4, 8/8/79:
Ultrasonic Examination Procedures for Piping Welds, Susquehanna Steam Electric Station Units 1 and 2.
e (c)
- FF107160, 8856-M166-15-4, Specifications No. ISE-QAI-322, Rev. 3, 4/2/78:
Ultrasonic Examination of Similar and Dissimilar Metal Welds for Susquehanna.
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If there are newer applicable revisions, please reference them and summarize any significant changes.
1
Response
84:
The procedures referenced during the PSI review are no longer applicable.
The following procedures are, enclosed under Attachment f!6 for your review:
PP6L No.
Title TP-ISI-332 Measuring and Recording Search Unit Location and Maximum Signal Amplitude Data During Ultrasonic Weld Exams TP-ISI-307 Manual Ultrasonic Examination of Austenitic Piping Welds TP-ISI-309 Manual Ultrasonic Examination of Austenitic Thin Wall Piping Welds While we will use additional UT procedures for ferritic piping, TP-ISI-307 and TP-ISI-309 are specifically intended to be used for the detection of IGSCC.
As an aside, TP-ISI-307 has been demonstrated at the EPRI NDE Center using the Nine Mile Point samples per IE Bulletin 83-02.
While TP-ISI-309 has not been demonstrated due to the unavailability of service induced cracked
- samples, PP6L has done a parametric evaluation between the two procedures and has concluded TP-ISI-309 adequately addresses the techniques necessary to detect IGSCC.
Please note that these procedures have gone through an approval process but still are subject to change.
Question f/5:
In Reference 3, Item c, PP&L states, "The Inservice Inspection Program will include requirements for augmented periodic ultrasonic and liquid penetrant testing to determine the inservice integrity of feedwater nozzles in accordance with the schedule in NUREG 0619, Table 2, Routine Inspection Intervals and the provisions of Section 4.3, 'Inspection'.
"Identify the section of the plan that addresses this commitment.
Response
85:
Section 8.0 of the Inservice Inspection Program Plan lists compliance with the augmented inspection commitments of NUREG 0619 as committed to in other NRC correspondence.
Specific details such as a listing of affected components-may be found in the AUG3 section of Attachment
//1 to this letter.
Question I/6:
Reference 4 (under Item IV, Response to Guidance in NUREG 0803, Table 5.1) stated that the ISI program has been revised to include ISI of the SDV piping, commensurate with Section XI inspection requirements for Class 2 piping.
Identify the section of the plan that addresses this commitment.
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Response
86:
Section 8.0 of the Inservice Inspection Program Plan lists compliance with the augmented inspection commitments of NUREG 0803.
Since the Control Rod Drive SDV piping and components have been classified asSection XI Class 2 in the SSES UI/1 ISI program, details may be found in the Control Rod Drive System Section of Attachment ill.
RELIEF RE UESTS IRR-4 Question:
Relief is requested from the volumetric examinations.
Will an internal visual or surface examination be made of the pressure retaining welds in the Core Spray and RHR pumps if the pumps are disassembled for maintenance?
Response
This relief request has been revised to include a VT-3 examination of the welds made accessible during pump motor removal or disassembly for maintenance.
IRR-7 Question:
Relief is requested from 100% volumetric examination requirements for feedwater inlet nozzles N4A and N4D due to geometric restrictions.
In the ISI Program it was stated that the 60-degree segments of the two feedwater inlet nozzles N4A and N4D that cannot be inspected automatically will be examined manually to the extent possible.
Please provide sketches of Nozzles N4A and N4D, showing dimensions and proximity to Nozzles NllA and NllB and a narrative description of the reason that full volumetric examination cannot be accomplished using., a combination of automated and manual scanning techniques.
Also indicate approximately what fraction of the 60-degree segment not covered by automatic inspection can adequately be covered by manual inspection.
Response
Figure 1 illustrates the approximate dimensions/clearances for the N11A,B instrumentation nozzles to the N4A,D feedwater nozzles.
Figure 2 illustrates the nozzle to vessel weld details and the 80 W
80 Section XI examination volume.
For a complete manual examination 45'nd 60' available scan paths of approximately ll" and 15.5" from weld centerline, respectively, are necessary.
Inadequate scan paths exist for both the 45'nd 60'anual scans for approximately nine (9) inches (30')
of nozzle circumference.
Given the available scan path, and allowing 11/16" and 7/8" for 45'nd 60'espectively-shoe to beam exist point distances, approximately 65% of the required volume cannot be examined using a 60'ngle beam, while 35% cannot be examined using a
45'ngle beam.
Due to the clearances required Xor the automated equipment, no examination can be performed for a full 60'egment of the weld.
Depending on specific access provisions in each location, it is anticipated that 50-60% of the area missed by the automatic equipment may be manually examined.
Actual coverage will be evaluated on completion of the initial manual exams.
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