PLA-1228, Forwards Updated Preservice Insp Program Info Re SER Issue 19.Revision Includes Preservice Exams Performed Subsequent to Util 810519,0616 & 820523 Submittals
| ML18031A387 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 08/20/1982 |
| From: | Curtis N PENNSYLVANIA POWER & LIGHT CO. |
| To: | Schwencer A, Schwercer A Office of Nuclear Reactor Regulation |
| References | |
| PLA-1228, NUDOCS 8208240151 | |
| Download: ML18031A387 (22) | |
Text
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ACCESSION NnH FACIL:50-3V7 50"388 Alj7 H ~ iVA i lE Cl>RTISiN ~ @ ~
REC IP. NAME SCHNEHCFHpA ~
REGULATuHf LNI-ORI'ATION DISTRIBUTION SY rEM (BIDS)
~ 820824,3151 OUC ~ DATE 82/08/20 NOTARIZED ~
iVO Susqueh;anna Steam Electric Stationi Unit ii Pennsylva Susquehanna Steam Electric Stationi Unit 2< Pennsylva AUTHOR At FILIATION Pennsylvania Power 8 Light Co ~
HECIl'Ic.V( AFFILIATION Licensing Branch 2
DISTRIBUTION CODE:
00015 COPIES RECEIVED:LTH 3 ENCL TITLE: PSAR/FSAR AMOTS and Related Correspondence NOTES:
SIZE:
Sl-'BJECT:
Forwards updated preservice insp program info re SER Issue 19 ~ Revision includes preservice exams perforn ed subsequent to util 810519i0616 6 820523 submittals
~
DOCKET 05000387 Ii CI ri t.
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RECIPIENT Io CODE/NA>E A/0 LI CEiVSNG LIC QR 42 LA ELD/HDS4 IE/DEP EPOS 35 NHH/OE/CEB 11
!4RH/OE/GB 28 NRR/DE/i~EB id i4RR/DE/GAB 21 b,RR/DE/SEB 2b NRR/OHFS/LQB 32 iVRH/OHFS/PTRB20 NHH/OS I/ASB 27 iVRR/DS I /CSB 09 iVHR/DSI/ICSB 1o iVRH/DSI/H48 2d NHR/DST/LGB 33 RG41 ACHS 4l DMB/DSS (AMOTS)
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PECIP IENT ID CDOE/NAt>E LIC BH P2 BC PERCHiR ~
01 IE FILE IE/DEP/EPLB 36 NRR/Oe/EOB NHR/OE/HGEB 30 NHR/DE/MTEB 17 NHR/DE/SAB 24 NHR/DHFS/HFEB40 NHR/DHFS/CLB 34 NHR/DSI/AEB 26 NRR/DSI/CP8 10 NHR/OS I/ETS6 12 VRR/OS I/PSB 19 NHR/DSI/RSB 23 04 RM AMI /RIB BNL(AMDTS ONLY)
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LTTR 59 ENCL 54
Pennsylvania Power 8 Light Company Two North Ninth Street
~ Allentown, PA 18101
~ 215 i 770 5151 Norman W. Curtis Vice President-Engineering 5 Construction-Nuclear 21 5 I 770-5381 AVG 30 198)
Mr. A. Schwencer, Chief Licensing Branch No.
2 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20555 SUSQUEHANNA STEAM ELECTRIC STATION SER ISSUE NO.
19 PRESERVICE INSPECTION PROGRAM REVISIONS ER 100450 FILE 841-2 PLA-1228 Docket Nos.
50-387 50-388
References:
letter dated 5/19/81 (PLA-813, Curtis to Schwencer) letter dated 6/16/81 (PLA-846, Curtis to Schwencer) letter dated 5/23/82 (PLA-1053, Curtis to Schwencer)
Dear Mr. Schwencer:
The attached information updates the preservice inspection program transmitted via the above referenced correspondence, Pages from the initial transmittal have been revised to include current information obtained as a result of preservice examinations performed subsequent to the last revision.
The following items are attached:
1.
Revision 3 of Relief Request 84 2.
Revision 2 of Relief Request 85 3.
Revision 2 of Relief Request 8'6 4.
Relief Request 8'll 5.
Relief Request fk12 6.
Relief Request 813 Please call if you have any questions.
Very truly yours, N. W. Curtis Vice President-Engineering
& Construction-Nuclear
""""""'808 z'4 O f $ [ Q
WELD IDENTIFICATION NUMBER CODE CATEGORY AND ITEM NUMBER SYSTEM AS)X NA URE OF 4 OF SCAN SECTION III CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION SAFETY IMPACT<<
VNB-B21-1-20B BJ B4.5 NUCLEAR BOILER PIPE TO ELBOW PIPE SUPPORT 20%
Weld cannot be isolated from the reactor coolant pressure boundary; however, leak de-tection systems detect leak-age.
Plant technical speci-fications 'require shutdown with leakage greater than 5 gpm-Lo RT and PT Reactor coolant pressure boundary leak detection system detect leakage.
Plant technical specifications re-quire plant shutdown with leakage greater than 5 gpm.
VNB-B21"1-20F BJ B4.6 MAIN STEAM PIPE TO BRANCH LUG 25%
RT and PT Weld is located within reac-tor coolant pressure bound-ary.
Leak detection system detects leakage.
Plant tech-nical specifications require plant shutdown with leakage greater than 5 gpm.
Relief Request Pi Rev.
3 7/15/82
WELD CODE CATEGORY IDENTIFICATION AND ITEM NUMBER NUMBER SYSTEM CONFIGURATION NATURE OF 4 OF SCAN OBSTRUCTION OBSTRUCTED ASME SECTION III EXAMINATION SAFETY IMPACT GBB-104-3-FW10 CF C2.1 PIPE TO VALVE WELDOLET 5w RT During normal plant power operation, welds are not under pressure.
During nor-mal system operation, signi-ficant leakage can effect pressure boundary of one RHR loop.
Leakage is detectable by leak detection systems or loss of system function.
Plant can be safely cooled down by unaffected RHR loop or main condenser.
DBB-114-1-7C CF C2.1 HPCI PIPE TO ELBOW 4 LUGS 25M Leak detection systems detect weld leakage, resulting in either manual or automatic isolation of the leak.
These lines are not required for normal safe shutdowns and alternate shutdown methods are available.
GBB-115-1-FW4 CG C2.1 RHR VALVE TO PIPE LAMINATIONS 13%
During plant power operation, weld not pressurized.
During normal system operation, sig-nificant leakage detected by leak detection systems.
Al-ternate shutdown cooling path is unaffected and condenser is available for cooldown.
Relief Request 84 Rev.
3 7/15/82
WELD CODE CATEGORY IDENTIFICATION AND ITEM NUMBER NUMBER SYSTEM ASME NATURE OF
% OF SCAN SECTION III CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION 'AFETY IMPACT" 15 1
5j'I 1
VNB-B21-2-17F BJ B4.6 MAIN STEAM PIPE TO BRANCH LUG CONNECTION 25%
RT and PT Weld is located within the reactor coolant pressure
- boundary, weld cannot be iso-.
lated.
Reactor coolant pres-sure boundary leak detection system detects leakage.
Plant technical specs require plant shutdown with leakage greater than 5 gpm.
VNB-B21-2-17B BJ MAIN STEAM PIPE TO ELBOW PIPE SUPPORT 174 RT and PT 1 ~
1'\\
~l 1 ~
! ~ii jl
- 11
, ~
I 1
l]
I 1
ll
~
~
i"'elief Request 84 Rev.
3 7/15/82
WELD CODE CATEGORY IDENTIFICATION AND ITEM NUMBER NUHBER SYSXEM ASHE NAXURE OF
'4 OF SCAN SECXION III CONFIGURATION OBSXRUCTION OBSTRUCXED EXAMINATION SAFETY IMPACT'BB-102-2-FW6 CG C2.1 PIPE TO ELBOW PIPE SUPPORT TOTALLY RT During normal operation of the CRD system, significant leakage will be detected by area radiation monitors.
Leakage can be manually iso-lated.
DBB-122-2-FW13 RWCU PIPE TO PIPE WALL PENETRATION TOTALLY Leak detection system detects weld leakage resulting in either manual or automatic isolation of the leak.
These lines are not required for normal safe shutdowns; alter-nate shutdown methods are available.
+Augmented Exam'.nation Per Susquehanna SES FSAR Section 6.6.8.
Relief Request b5 Rev..2 7/15/82
RELIEF REQUEST 5
6 I.
IDENTIFICATION OF COMPONENTS:
Class 1, Category BJ, pressure retaining welds in piping.
Class 2, Category CF and CG pressure retaining welds in piping.
II.
CODE REQUIREMENT:
Category BJ Table IWB-2600, Item Numbers B4.5, B4.6, B4.7 of the ASME Code, 1974 Ed'ition to Summer 1975 Addenda requires volumetric examination of 100%* of circumferential welds, longi-tudinal welds, and branch connections be performed completely as
- a. preservice examination requirement prior to inital plant start-u p Category CF/GG Table IWC-2600, Item Numbers C2.1, C2.2, C2.3 of the ASME Code, 1974 Edition to Summer 1975 Addenda requires volumetric examination of 100%
and 50%*, respectively of c'rcumferential discontinuity welds, longitudinal welds, and branch connection welds be performed completely as a preservice examination requirement prior to initial plant start-up.
ASME Appendix III, Winter 1975 Addenda, requires an angle beam examination of, the weld and required volume (the lesser of 4t or 1") be performed scanning both normal and parallel to the weld.
III.
BASIS FOR RELIEF:
Relief is required from the ASME Section XI examination requirements on the basis of inaccessibility of the weld and required volume due to geometric configuration.
Rev.
1 7/5/82
WELD CODE CATEGORY IDENTIFICATION AND ITEM NUMBER NUMBER
$"STEM ASME NATURE OF 4 OF SCAN SECTION III CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION SAFETY IMPACX VRR"B31-1-2U BJ
- B4.5 REACXOR RECIRCULATION FITTING LONGITUDINAL WELD PART GEOMETRY 74 RT and PX Weld is within the reactor pressure boundary and cannot be isolated.
RCPB leak de-tection systems detect leakage.
Plant technical specifications require plant shutdown with leakage greater than 5 gpm.
VRR-B31-1-2V BJ
~
B4.5 REACTOR RECIRCULATION FITTING LONGITUDINAL WELD PART GEOiKTRY RT and PT VRR"B31-1-3L BJ B4.5 REACTOR RECIRCULATION FITTING LONGITUDINAL WELD PART GENTRY RX and PT VRR-B31-1-3K BJ B4.5 REACXOR FITTING RECIRCULATION LONGITUDINAL WELD PART GEOiIETRY RT and PT u
VNB-B21-2-2C BJ B4.6 MAIN STEAM PIPE XO BRANCII PART GEOMETRY TOTALLY RT and PX Relief Request 86 Rev.
2 7/15/82
WELD CODE CATEGORY IDENTIFICATION AND ITEM N ABER NUMBER SYSTEM CONFIGURATION NATURE OF 4 OF SCAN OBSTRUCTION OBSTRUCTED ASME SECTIOiV III EXAMINATION SAFETY IMPACT'RR-B31-2-2U BJ B4.5 REACTOR RECIRCULATION FITTING LONGITUDINAL WELD PART GE011EIRY RT and PT Weld is within reactor cool-ant pressure boundary and cannot be isolated.
RCPB leak detection systems detect leakage.
Plant technical specifications require plant shutdown with leakage greater than 5 gpm.
HBB-lll-1-1A CF C2.1 ELBOW TO REDUCER PART GEOMETRY TOTALLY During plant power operation, weld is not pressurized.
During normal system opera-tion, significant leakage is detected by leak detection systems.
Alternate shutdown cooling path is unaffected and condenser is also avail-able for cooldom.
VRR-B31-2-10R BJ B4.5 REACTOR FITTING PART RECIRCULATION LONGITUDINAL GEOMETRY WELD 18'4 RT and PT Weld is within the reactor pressure boundary and cannot be isolated.
RCPB leak de-tection systems detect leakage.
Plant technical specifications require plant shutdown with leakage greater thani 5 gpm.
VRR-B31-2-lOS BJ B4.5 REACTOR RECIRCULATION FITTING LONGITUDINAL WELD PART GEOMETRY 18'4 RT and PT Relief Request bi6 Rev.
2 7/15/82
4 P
h cp WELD CODE CATEGORY IDENTIFICATION AND ITEM NUMBER NUMBER SYSTEM CONFIGURATION NATURE OF 4 OF SCAN OBSTRUCTION OBSTRUCTED ASME SECTION III EXQIINATION SAFETY IMPACT "
]
GBB"101-4-15BP CG C2.1 CORE SPRAY PIPE TO PIPE PIPE SCHEDULE VARIATION 504 During normal plant power operation, weld is not pres-surized.
During normal system operation, weld is under a maximum pressure of 460 psig.
Leak detection system detects significant leakage; plant can be safely cooled down by unaffected core spray loop.
DBB"122-1-FW25 RWCU ELBOW TO VALVE PART GEOMETRY TOTALLY Leak 'detection systems de-tect weld leakage, resulting in either manual or automatic isolation of leak.
These lines are not required for normal safe shutdowns and alternate shutdown methods are available.
DCB-102-1-FW2 BJ B4.5 FLUED.HEAD VALVE PART GEOMETRY 15+
Weld is not pressurized during plant power operation.
During normal system opera-
HPCI and RCIC are not required for normal shutdowns; cooldown can be achieved by unaffected RHR loop or the main con-denser.
DCA-109-2-FW2 BJ B4.5 CORE SPRAY FLUED HEAD TO VALVE PART GEOMETRY 12<
Relief Request 06 Rev.
2 7/15/S2
WELD CODE CATEGORY IDENTIFICATION AND ITEM NUMBER NUMBER SYSTEM ASME NATURE OF
'4 OF SCAN SECTION III CONFIGURATION OBSTRUCTION OBSTRUCXED EXAMINATION SAFETY IMPACT" DCA-109-1-FW2 BJ B4.5 CORE SPRAY FLUED HEAD TO VALVE PART GEOMETRY
- 12oJ, HBB-118-2-FW3 CG C2.1 CONTAINMENT ATMOSPHERE CONTROL VALVE TO FLUED HEAD PART GEOMETRY TOTALLY Weld is not pressurized during normal power plant operation.
During normal system operation, weld is exposed to a pressure of less than 10 inches of water.
Leakage is detectable during ILRX.
System is not re" quired for plant shutdown.
DBA-108-1-FW8 BJ B4.5 NUCLEAR BOILER FLUED HEAT TO VALVE PART GEO>KTRY TOTALLY Affects the reactor coolant pressure boundary;
- however, inside containment isolation valve performs RCPB isolation function.
Leakage would be detected by leak detection systems; plant may be shut-down using unaffected systems.
2s C
DBA"108-1-FW5 BJ B4.5 NUCLEAR BOILER VALVE XO ELBOW PART GEOMETRY TOTALLY VRR-B31-2-3N BJ B4.5 REACXOR RECIRCULATION FITTING LONGITUDINAL WELD PART GEOMETRY Weld is within reactor cool-ant pressure boundary and cannot be isolated.
RCPB leak detection system detects leakage.
Plant technical specifications require plant shutdown with leakage greater than 5 gpm.
Relief Request 86 Rev.
2 7/15/82
WELD CODE CATEGORY IDENTIFICATION AND ITEM NUIJEER NUMBER SYSTEM ASME NATURE OF W OF SCAN SECTION III CONFIGURATION OBSTRUCTION OBSTRUCTED EXAMINATION SAFETY IMPACT" VRR-B31-2-3P BJ B4.5 REACTOR RECIRCULATION FITTING LONGITUDINAL WELD PART GEO>IETRY 74 RT, PT Weld is within reactor cool-ant pressure boundary and cannot be isolated.
RCPB leak detection system detects leakage.
Plant technical specifications require plant shutdown with leakage greater than 5 gpm.
VRR-B31-2"2V BJ.
B4.5 REACTOR RECIRCULATION FITTING LONGITUDINAL WELD PART GEOMETRY
+Augmented Examination Per Susquehanna SES FSAR Section 6.6.8.
S-22/cak Relief Request 86 Rev.
2 7/15/82
PRESERVICE INSPECTION RELIEF RE UEST Pl l I.
IDENTIFICATION OF COMPONENTS:
Class 2, Category CF and CG pressure retaining welds in Core Spray (1P206A,B,C,D) and RHR (1P202A,B,C,D) pumps.
Category CF/CG Table IWC-2600, Item Number C3.1 of ASME Section XI, 1974 Edition to Summer 1975 Addenda requires full volumetric examination of 100% and 50%*, respectively, of pump casing welds.
These examinations must be performed completely as a preservice examination requirement prior to initial plant start-up.
- Excluding those exempt per IWC-1220.
III. BASIS FOR RELIEF:
Relief is required from the ASME Section XI examination requirements on the basis of inaccessibility of the weld and required volume due to pump installation.
IV.
JUSTIFICATION:
The justification for requesting relief from ASME Section XI examination requirements is as follows:
1.
The structural integrity of the pump pressure boundary has been established by ASME Section III testing requirements.
2.
Accessible pump casing welds have been satisfactorily inspected to ASME Section XI.
3.
Pump installation meets manufacturer requirements.
V.'LTERNATE PROVISIONS:
Welds are inaccessible for alternate NDE methods.
Rev.
0, 6/18/82 S-19/cak
kJ~~VLO~~
QkPC~~4 %~ M ~W 4 <<<<<<<<<<4 G CI RELIEF REQUEST /!11 MELD IDENTIFICATION NUMBER CODE CATEGORY AND ITEM NUMBER SYSTEM CONFIGURATION NATURE OF OBSTRUCTION
% OF SCAN OBSTRUCTED (APPROXIMATE) 1P-206A,B,C-359-2-L2 CG C3.1 Core Spray Shell Longitudinal Seam Encased in Concrete Totally 1P-206B,D-359-1-2 CG C3.1 Core Spray Hub Flange to Shell Encased in Concrete Totally 1P-206A-359-2-Ll CG C3.1 Core Spray Shell Longitudinal Seam Encased in Concrete Totally 1P202A,B,C,D-359-1-2 CF C3.1 RHR Hub Flange to Shell Encased in Concrete Totally 1P202A,B,C,D-359-2-L2 CF C3.1 RHR Shell Longitudinal Seam Encased in Concrete Totally
.- 1P202A,B,C,D-359-2-2 CF C3.1 RHR Shell Circumferential Seam Encased in Concrete Totally 1P202A,BIC,D-359-2-L1 1P202A,B,C,D-359-2-3 1P202A,B,C,D-359-3-7 1P202A,B,C,D-361-2-6 1P202A,B,C,D-361-6-7 CF C3.1 CF C3.1 CF C3.1 CF C3.1 t
CF C3.1 RflR RHR RHR RHR RHR Shell to Bottom Head Encased in Concrete Totally Bottom Head to Bearing Housing Encased in Concrete Totally Discharge Elbow to Bottom Plate Flange Discharge Elbow to Sleeve Forging Encased in Concrete Totally Encased in Concrete Totally Shell Longitudinal Seam Encased in Concrete Totally Z-r',
Cg
<<p
')(
1P202A,B,C,D-361-7-8 CF C3.1 RHR Sleeve Forging to Top Closure Plate Encased in Concrete Totally Rev. 0, 6/18/82
RELIEF RE VEST i'll ASME SECTION III EXAMINATIOiI SAFETY IMPACT PT, RT PT, RT During normal plant power operation, weld is not pressurized.
During normal system is under a maximum pressure of 475 psig.
Leak detection system detects significant can be safely cooled down by unaffected core spray loop.
II If operation, weld leakage; plant PT, RT PT, RT PT, RT During normal plant power operation, weld is not pressurized.
During normal system is under a maximum pressure of 460 psig.
Leakage can be detected by leak detection affect one RHR loop.
Plant can be safely cooled down by unaffected RHR loop.
II It operation, veld system and can PT, RT PT, RT PT, RT
,PT, RT PT, RT PT, RT PT, RT Rev. 0, 6/18/82
PRESERVICE INSPECTION RELIEF REQUEST 812 I.i IDENTIFICATION OF COMPONENTS:
All Class 1 and Class 2'ntegrally welded support members for piping, pumps, valves, and pressure vessels.
The examination requirements for Code Category B-K-1 and C-E-1 have been upgraded to meet the requirements of ASHE Section XI 1977 Edition to. the Summer 1978 Addenda as follows:
Item Number
Examination Category Component Method Test Requirements B4.9, B6.5 B-K-1 Integrally Welded Volumetric Support Attachments or Surface*
Table IWB-2500-1 C3.10, C3.40, C3.70, C3.100 C-E Integrally Welded Surface**
Support Attachments Table IWC-2500-1
- See Figures IWB-2500-13,14,15.
+* See Figure IWC-2520-5.
III. BASIS FOR RELIEF:
Relief is required from the ASME Section XI examination requirements for the listed integrally welded support attachment on the basis of partial inaccessibility of the support for examination.
IV.
JUSTIFICATION:
The justification for requesting relief from ASME Section XI preservice examination requirements is as follows:
The structural integrity of the piping pressure boundary has been verified by ASME Section III testing requirements.
2.
Accessible portions of the welded attachments have been satisfac-
~ torily inspected to ASME Section XI.
3.
Limited inspection does not impact plant safety.
Rev. 0, 6/18/82
COHPONENT CODE CATEGORY IDENTIFICATION AND ITEM NUMBER NINBER GBB-106"1-H22 C-E C3.40 GBB-106"1-H5 C-E C3.40 HBB"110-3-H23 C-E C3.40 SYSTEM RHR RHR IUIR CONFIGURATION 4 LUGS 8 LUGS 8 LUGS HANGER STRAP 25'4 SURFACE Stress analysis calculations performed assuming the por-tion of inaccessible weld is non-existent indicate all lugs and local stresses are "
within allowable limits.
HANGER STRAP 2586 SURFACE Stress analysis calculations performed assuming the por-tion of inaccessible weld is non-existent indicate all lugs and local stresses are within allowable limits.
HANGER STRAP 25%
SURFACE Stress analysis calculations performed assuming the por-tion of inaccessible weld is non-existent indicate all lugs and local stresses are within allowable limits.
TOTAL AREA ASHE NATURE OF OBSTRUCTED SECTION III OBSTRUCTION (APPROXIMATE)
EXAMINATION SAFETY IHPACT HBB-110-1-H5 C-E C3.40 8 LUGS HANGER STRAP 25'4 SURFACE Stress analysis calculations performed assuming the por-tion of inaccessible weld is non-existent indicate all lugs and local stresses are within allowable limits.
GBB-101-4-H16 C-E C3.40 LUG PART GEOMETRY SURFACE Stress analysis calculations performed assuming the por-tion of inaccessible weld is non-existent indicate all lugs and local stresses are within allowable limits.
Relief Request 012.
Rev.
0 7/20/82
V.
ALTERNATE PROVISIONS:
Alternate nondestructive examination methods are not feasible due to restricted access.
MS:saw SA-1 Relief Reques t f!12 Rev. 0, 6/18/82
~
a PRESERVICE INSPECTION RELIEF REQUEST
/Iles I.'DENTIFICATIONOF COMPONENTS:
I Class 2 pressure retaining welds and pressure retaining nozzle welds in the Residual Heat Removal heat exchangers.
Category C-A of ASME Section XI, 1974 Edition to Summer 1975 Addenda requires volumetric examination of shell and head circumferential discontinuity welds and base material for one plate thickness beyond the edge of the weld joint.
Category C-B of ASME Section XI, 1974 Edition to Summer 1975 Addenda requires volumetric examination of 100% of the nozzle-to-vessel attachment welds.
These examinations must be performed completely,
- once, as a preservice examination requirement prior to initial plant startup.
III. BASIS FOR RELEIF:
Relief is required from the ASME Section XI examination requirements on the basis of partial inaccessibility of the weld due to design of the component.
IV.
JUSTIFICATION'.
The justification for requesting relief from ASME Section XI preservice examination requirements is as follows:
1.
The structural integrity of the pressure boundary has been verified by ASME Section III construction code testing requirements.
2.
Accessible portions of the welded attachments have been satisfactorily inspected to ASME Section XI.
V.
ALTERNATE PROVISIONS:
A surface examination will be performed on the unexamined areas.
Rev.
0 6/14/82 mp/449539
WELD IDENTIFICATION NOSER IE-205-A-R CODE CATEGORY AND ITEN %REER CA Cl. 1 SYSTEM CONFIGURATION SHELL TO HEAD NATURE OF OBSTRUCTION WELDED ATTACHMENT
% Of
~ SCAN OBSTRUCTED (APPROXIMATED) 15%
IE-205-A-A IE-205-A-AC IF;205-B-R CB Cl. 2 CA Cl. 1 CA Cl. 1 RHR RHR SHELL TO NOZZLE SHELL TO FLANGE SHELL TO HEAD ADJACENT WELD OUTLET NOZZLE WELDED ATTACHMENT 8%
7%
15%
IE-205-B-A IE-205-B-AC CB C1.2 CA Cl. 1 SHELL TO NOZZLE ADJACENT WELD SHELL TO FLANGE OUTLET NOZZLE 8%
7%
Relief Request 813 Rev.
0 6j'14/82
ASHE SECTION III EXAMINATION SAFETY IHPACT PT, UT, RT During normal plant power operation, weld is not pressurized.
During normal system operation, weld is under a maximum pressure of 460 psig.
Leak detection system detects significant leakage and can affect one MlR loop.
Plant can be safely cooled down by unaffected RHR loop.
PT, UT, RT PT, UT, RT PTI UT~ RT PTI UT, RT PT, UT, RT Relief Request 813 Rev.
0 6/14/82