ML20011A051: Difference between revisions
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* VALVE SY* PASS I 2 8M 2BC 2 tM 2BC 8 2-eM-asc-c [ | * VALVE SY* PASS I 2 8M 2BC 2 tM 2BC 8 2-eM-asc-c [ | ||
MANIFOLD 2-BM l/3H3 Lu 2 BM l/8HA-2 *SM*l/SH A-LU SEE DETAIL A00VE tr 28017 2 SM 1/Eria 2 eu 31tt.21 Nlj 2 BM-4/BHE J aM.4/gHo l j | MANIFOLD 2-BM l/3H3 Lu 2 BM l/8HA-2 *SM*l/SH A-LU SEE DETAIL A00VE tr 28017 2 SM 1/Eria 2 eu 31tt.21 Nlj 2 BM-4/BHE J aM.4/gHo l j | ||
| Line 1,082: | Line 1,082: | ||
C CC t HHHL S 8 SS 8 L3332 32 5 222 MMuM 4M6MMM I - | C CC t HHHL S 8 SS 8 L3332 32 5 222 MMuM 4M6MMM I - | ||
3 A | 3 A | ||
((/ | |||
6 T cSSS D3S8B f | 6 T cSSS D3S8B f | ||
O O22 2 2M222 M E E | O O22 2 2M222 M E E | ||
Latest revision as of 10:10, 15 March 2020
| ML20011A051 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 10/01/1981 |
| From: | Daltroff S PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0313, RTR-NUREG-313, TASK-A-42, TASK-OR GL-81-03, GL-81-3, NUDOCS 8110060400 | |
| Download: ML20011A051 (58) | |
Text
.
PHILADELPHIA ELECTRIC COMPANY 2301 M ARKET STREET P.O. BOX 8699 1881 1981 PHILADELPHIA. PA.19101 SHIELDS L. D ALTROFF nacNc p'nNc so.e October 1, 1981 Docket Nos. 50-277 50-278 W N
Mr. Darrell G. Eisenhut
$ghe8figbs-Division of Licensing d]~
OCI'J Olh kh
-m 4N44 U.S. Nuclear Regulatory Commission ' k *cer b Washington, DC 20555
(}-\g , sq
Dear Mr. Eisenhut:
Your letter of February 26, 1981, (Generic Letter 81-04) forwarded NUREG 0313, Revision 1, " Technical Report on Material Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping", which provides the NRC staff's acceptable methods for reducing intergranular stress corrosion cracking (IGSCC). Attached is our revised program for mitigation of IGSCC at Peach Bottom Atomic Power Station Units 2 and 3 based on the guidelines of NUREG 0313, Revision 1.
Our long term program presently includes replacement of selected piping with material that meets the criteria of NUREG 0313, Revision 1, and evaluation of the induction heating stress improvement (IHSI) process for inhibiting propogation of IGSCC.
We believe that our long term program will substantially reduce the need for augmented inspections and will enable us to return to inspecting in accordance with section XI of the ASME code and 10 CFR 50.55a.
Our program to replace selected piping with conforming material is proceeding at this time. Susceptible portions of the core spray lines on Units 2 and 3 and the reactor water clean-up suction line on Unit 3 have already been replaced. During subsequent refueling outages, we anticipate that we will replace the Unit 2 reactor water clean-up suction line and the residual heat removal head spray on both units, t
8110060400 011003 p DR ADOCM 05000277 PDR f (f1 l
4 Mr. Darrell G. Eisenhut Page 2 Although the IHSI process has not been accepted by the NRC as an alternative to augmented inservice inspection, NUREG 0313, Revision 1 indicates that this process may be permissible provided there is acceptable supportive data to warrant its use.
A Topical Report is being prepared by General Electric Company to support the IHSI process which we plan to forward for NRC consideration. We are presently evaluating this process as a potential long term solution to mitigate the effects of IGSCC.
In a letter dated April 26, 1976, from G. Lear, NRC, to E. G. Bauer, Jr., Philadelphia Electric Company, we were
- requested to revise our Technical Specifications so that future changes to the Inservice Inspection Program would not require operating license amendment requests. On May 4, 1977, we submitted a license amendment request proposing such a revision to the Technical specifications. In light of this licensing activity and our planned long term modifications to reduce augmented inspection requirements, we do not believe it is appropriate to propose a Technical Specification change 1.o incorporate the augmented inspection program.
1 If you have any questions or require additional information, please don't hesitate to call.
Very truly yours,
,f )
N/ d lJf !-
Attachment - /
=
e PROGRAM CO2 MITIGATION OF INTERGRANULAR STRESS CORROSION CRACKING IN AtMTENITIC STAINLESS STEEL OF PEAcn DOTTOM UNITS 2 5 1 NUREG-0313, REVISICN ONE Philadelphia Electric Company has reviewed the Peach Bottom Units 2 and 3 reactor pressure boundary piping and fitting material, including weld metal, to determine conformance with the material selection and process guidelines set forth in NUREG-0313, Revision 1, dated July, 1980.
NUREG-0313, Revision 1 was transmitted to Philadelphia Electric Company by Generic Letter 81-04 from Mr. Darrell G. Eisenhut dated February 26, 1981.
The review has determined that portions of the following piping systems, wnich connect to the reactor pressure vessel and are within primary containment up to and including the first isolation valve outside containment, do not appear to meet the guidelines of NUREG-0313, Revision 1 for minimizing stress corrosion cracking:
- a. Core spray lines
- b. Reactor head spray line
- c. Residual Heat Removal (RHR) (shutdown cooling) 1.ncs
- d. Reactor Water Clean-up line (for Unit 2 only)
- e. Reactor recirculation pump lines We intend to implement an augmented inservice inspection program on "non-conforming" portions of the above lines for bott: Units 2 and 3 whicn have been categorized as Class 1 ron-exempt components in accordance with the " Peach Bottom Atomic Power Station, Inservice Inspection Programs, Unit 2 and Common Plant, and Unit 3" as submitted by letters to Mr. George Lear from Eugene J. Bradley dated August 4, 1977 and January 23, 1978, respectively. There are no "non-conforming" Class 2 lines in either Peach Bottom Unit 2 or Unit 3. These inservice inspection programs arc based on ASME Boiler and Pressure Vessel Code, Section MI, 1974 Edition Uith addenda through Summer 1975 as required by 10CFR50.55a.
However, the guidelines of NUREG-0313, Revision 1 are not consistent with the above ASME Boiler and Pressure Vessel Code requirements. Consequently, we have developed an augmented inservice inspection program for selected "non-conforming" materials to meet the guidelines of NUREG-0313, Revision 1.
This augmented program is a revision to the supplemental inservice inspection program previously submitted by letter dated December 20, 1977 in response to NUREG-0313, Revision 0.
9 Tne augmented inservice inspection program will be performed during the periods when the reactors are shutdown for refueling. Our past experience at Peach Dottom indicates that the coordination and scheduling of non-destructive examination personnel and necessary support labor requires at least one month advance planning. The only period when such planning can be programmed is in conjunction with refueling outages.
Lased upon available information, we believe that Intergranular Stress Corrosion Cracking (IGSCC) of austenitic stainless steel linss has occurred at locations where high stresses result from the addition of toermal stresses to residual and pressure stresses on piping joints. As indicated in NUREG-0313, Revision 1, coolant flow conditions in these lines may also assist in creating a stress condition which contributes to IGSCC. Recognizino this potential, those lines with relatively stagnant, intermittent, or low flow have received special consideration for possible high stresses beca :: of thermal contributions. Upon consideration of industry experience, flow conditions, mir.imization of personnel radiation exposure, and stress rule indicies as calculated by General Electric Company (GE), we have established boundary locations in certain systems which will provide necessary assurance of pressure boundary integrity and a reasonably achievable examination program.
Lines, or portions thereof, which do not appear to meet the material and process guidelines of NUREG-0313, Revision 1 have been categorized as
" service sensitive" or "non-service sensitive" as defined in NUREG-0313, Revision 1. Isometric drawings of the subject lines are enclosed in addition to tables which define the scope of our proposed augmented program. The enclosed tables describe " service sensitive" and "non-service sensitive" lines; the number of examinations required in each category per line; a brief examination history of each line; and our proposed long term examination, mitigation, or replacement program.
- wdEG-0313, Revision 1 establishes requiremente for inservice inspection of Class 1 and Class 2 austenitic stainless steel lines based on successive examinations and inspection periods of 36 and 80 months. Much of the inservice inspection of the lines of concern has already been performed based upon the ASME Section XI, 1974 Edition with addenda through Summer 1975, 10 year inspection interval criterit. Portions of certain lines (i.e., core spray, RHR portions used for shutdown cooling, recirculation pump lines, reactor head spray, and reactor watec clean-up) have also had additional examinations to comply with NUREG-0313, Revision O. The augmented inservice inspection program described herein increases our inservice inspection of Class 1 "non-conforming lines," " service sensitive," and "non-service sensitive," to the criteria stated in NUREG-0313, Revision 1, within the constraints of perconnel availability and radiation exposure, while taking credit for examinations performed since the commercial operation of each unit.
Based on industry experience, we believe that welds with a stress rule index (SRI) of 1.2 or greater will be susceptible to intergranular stress corrosion cracking as discussed in NUREG-0313, Revision 1. We intend to inspect "non-conforming" service sensitive welds in accordance with the following guidelines, except as noted below. Service-sensitive welds with an SRI greater than or equal to 1.2 will be inspected during three consecutive reftal outages (18 month fuel cycle), then once every other refuel outage for three examinations, and then once every 80 months. Credit will be taken for examinations performed to date.
1 Service sensitive welds with SRI values of less than 1.2, and non-service sensitive welds 'ith SRI values of 1.2 or greater will be inspected once every 60 months, while taking credit for examinations performed since commercial operation of each unit. Non-service sensitive welds with an SRI value of less than 1.2 will be inspected once every 120 months. Where the SRI value is not known, both service se a,itive and non-service sensitive welds will be treated as if the SRI value was 1.2 or greater.
Certain "non-conforming" service sensitive welds exist in the recirculation system risers which have SRI values greater than or equal to 1.2. These liras have experienced no cracking history and have high flow conditions. They are located in high radiation fields (800-4,500 mr/hr). In caasideration of the high radiation dose associated with examination of these welds and the lack of any history of prior cracking, a representative sample of these welds will be inspected during each inspection period. It is planned to inspect those welds having an SRI equal to or greater than 1.2 in two risers per inspection period, one riser on each recirculation system loop. If cracking is found during any of these inspections, additional piping runs of this group will be examined in accordance with Paragraph IWB-2430 of the ASME Boiler and Pressure Vessel Code,Section XI, 1974 Edition, with all addenda through Summer 1975.
Additional "non-conforming" service sensitive welds exist in the RHR Shutdown Cooling Return Lines whi A have SRI values of 1.2 or greater. These lines also have no previous cract rg history and are located in high radiation fields (300-500 mr/hr). In consideration of the high radiation doce associated with examinations of these welds and the lack of any history of prior cracking, a representative sample of these welds will be inspected during each refuel outage. It is planned to examine those welds having an SRI equal to or greater than 1.2 in one return loop per inspection period. If cracking is found during any cf these examinations, the welds of this group in the other loop will be inspected in accordance with Paragraph IWB-2430 of the ASME Doller and Presourc VeLael Code,Section XI, 1974 Edition with all addenda through Summer 1975.
Several "non-conforiaing" service sensitive lines have been removed or had material replaced since NUREG-0313, Revision 0, was issued. The lines that have been removed include both the Control Rod Drive Return and the Reactor Recirculation Pump Discharge Valve By-pass Lines in Units 2 and 3. Those lines that have undergone material replacement (from 304 to 316L stainless steel) are portions of the Core Spray in Units 2 and 3, and the Reactor Water Clean-up in Unit 3. We intend to replace additional portions of "non-conforming" lines to the extent practicable in the future. In the event that other means which mitigate intergranular stress corrosion cracking are developed such as induction heating stress improvement (IHSI), we may utilize these means to bring "non-conforming" lines into conformance with NUREG-0313,
! ision 1. As mitigation methods are implemented, a revised augmented inspectinn
.- Jram will be submitted.
ISI Section Maintenance Division September 24, 1981
UNI? 2 NON-COXFOPTING. STR7 ICE SE'!SITIT: E DS (SRI e.1.2) hJREG Recuirement: 3-18 Konth. 3-36 Kenth. 1-80 Kenth Examinations "X" Denotes Exa.ination Perfor.ed to Date "O" Denotes Exa.inatiens to be Perfered
" " Denotes Exception to Examination Requirements ,
Weld' 18 Fonths 36 Xcnths 803enthe jvste Identificatien 1 2 3 1 2 3 1 ,P g .ned I:nc-Ten Prorran Rnctor 2-AEF-2 - - - - - - -
Conduct ininetion heating stresc it-Re circulation pr venent to inhibit propagation of Loop "A" 2- m -3 - - - - - - -
I.D. defects 2- m -h - - - - - - -
2-Ano-2 - - - - - - -
2-Ago-3 - - - - - - .
2-AHG-h - - - - - - -
2- m -2 - - - - - - -
2- N -3 - - - - - - -
2-isa-y - - - - - - -
2-AHJ-2 X 0 0 0 0 0 0 2-AEJ-3 X 0 0 0 0 0 0 2-AHJ-L 0 0 0 0 0 0 0 2- m -2 - - - - - - -
2-AEx-3 - - - - - - -
2-Anx k - - - - - - -
T1
- o UNIT 2 NON-CONFORMING, SERVICE SENSITIVE WELDfi (SRI e1.2)
NUREG Recuirerant: 318 Enth. 3-16 Month.1-80 Month Exaninations "X" Denotes Examinatien Perforced to Date "O" Denotes Examinations to be Performed
"" Denotes Exception to Examination Requirements Weld 18 Months 36 Months 80 Months System Identification 1 2 3 1 2 3 1 Planned Iong-Term Prosrea_m Reactor 2-BHA-2 X 0 0 0 0 0 0 Conduct induction heating stress in-Recirculation pr vement to inhibit propagation of
. Loop "B" 2-BHA-3 0 0 0 0 0 0 0 I.D. defects 2-BHA-h 0 0 0 0 0 0 0 2-BHB-2 _ - - - - _ -
2-BBB-3 - - - - - - - -
2-bub-k - - - - - - -
2-BHC-2 - - - - - - -
2-BHC-3 - - - - - - -
2-BHC-h - - - - - - -
2-BED-2 - - - - - - -
2-BHD-3 - - - - - - -
2-BHD-k - - - - - - -
2-BHB-2 - - - - - - -
2-BHP-3 - - - - ~ _ _
2-Bus-k - - - - - - -
O T2 m _
.' e UNIT 2 NON-CONFORMING, SERVICE SENSITIVE VELDS (SRI 2:1.2)
NUREG Reauirecent: 3 18 Month. 3-36 Month. 1 80 Month Examinations "X" Denotes Exanination Performed to Date "O" Denotes Examinations to be Performed
" " Denotes Exception to Examination Requirements Weld 10 Months 36 Months 80 Months System Identification 1 2 3_ 1 2 3 1 Planned Long-Term Program PER Shutdown 10-0-1 X X X 0 0 0 0 Conduct induction heating stress im-Cooling Suction 10-0-2 X X X 0 0 0 0 pvement to inhibit propagation of A.D. defects 10-0-14 X X X 0 0 0 0 10-0-6 X X X 0 0 0 0 10-0-7 X X X 0 0 0 0
~
Inservice inspect to ASME Section XI criteria in accordance with 10 CFR 50.55a RHR Shutdown 10-IA-8 X X 0 0 O O O Conduct induction heating stress im-Cooling Return Provement to inhibit propagation of 10-IA-9 X X 0 0 0 0 0 Loop "A" I.D. defects 10-IA-11 X X X 0 0 0 0 Inservice inspect to ASME Section XI criteria in accordance with 10 CFR 50.55a RHR Shutdown 10-IB-8 X 0 0 - - - -
Conduct induction heating stress im-Coeling Return pr vesent to inhibit propagation of 10-IB-9 X 0 0 -- - - -
Lool "B" I.D. defects 10-IB-11 0 0 0 -
Inservice inspect to ASME Section XI criteria in accordance with 10 CFR 50.55a T3
i .-
UNIT 2 NON-COXFORMINO. SERVICE SENSITIVE VELDS (SRI E1.2)
NUREO Recuirerent: 3 18 Month, %36 Month. 1-80 Month Examinations "X" Denotes Exandnation Perfereed to Date "0" Denotes Examinations to be Perfomed Weld 18 Kenths 36 Months 80 Months System Identificatien 1 2 3 1 2 3 1 Planned Long-Tem Prorram R: actor Water 12-0-1 0 0 0 0 0 0 0 Replace these welds with the installa-Olean-Up Pump
. Suction 12-0-7 0 0 0 0 0 0 0 t n f3 stainless steel pipe during the next refuel outage 12-0-8 0 0 0 0 0 0 0 j 12-0-9 0 0 0 0 0 0 0 12-0-10 X 0 0 0 0 0 0 12-0-11 0 0 0 0 0 0 0 ,
12-0-12 0 0 0 0 0 0 0 12-0-13 0 0 0 0 0 0 0 12-0-1h x0 0 0 0 0 0 12-0-15 0 0 0 0 0 0 0 S
e Th -
m
UNIT 2 NON-CONFORMING. SERVICE LUISITIVE WELDS (SRI <1.2)
NUREG Recuirement: 1-80 Month Examination "X" Denotes Examinations Performed to Date "O" Denotes Examinations to be Performed Weld 80 Months System Identification 1 Planned LoneTerm Program Reactor Recirculation- 2-AHF-1 X Inservice inspect to ASME Section XI Loop "A" c e a in a c rdance w m 10 m 2-AHG-1 O 50 55a 2-AHJ-1 X l
2-AHK-1 0 1
2- h 1/AHK X 2- h 1/AHJ X i
2- E h/AHG O 2- E h/AHF 0 1
Reactor Recirculation 2-BHA-1 0 Inservice inspect to ASME Section XI Loop "B" criteria in accordance with 10 CFR p,3 y 50.55a 2-BHD-1 X 2-BHE-1 0 2-BM-1/ BHA X 2-BM-1/BHB. O 2-BM-h/BHD X 2-BM-h/BHE O -
RHR Shutdown 10-0-3 X Inservice inspect to ASME Section XI Cooling Suction riteria in a rdan e with 10 CE 10-o-5 X 50.55a T5 a
! UNIT 2 NON-CONFORMING, SERVICE SENSITIVE VELDS iSRI <1.2)
NUREG Recuirerent: 1-80 Month Eranination "X" Denotes Ernminations Perfermed to Date "O" Denotes Examinations to be Performed Weld 80 Months System Identificatien 1 Plan.ed Long-Term Program l
l RHR Shutdown Cooling 10-IA-10 X Inservice inspect to ASME Section XI Return Loop "A" criteria in accordance with 10 CFR 50.55a
- RER Shutdown Cooling 10-IB-10 0 Inservice inspect to ASME Section XI l Return Loop "B" criteria in accordance with 10 CFR 50 55a l
l Reactor Water Clean-Up 12-0-2 X Replace these velds with the installa-Pump Suction 12-0-3 0 tion of 316L stainless steel pipe during the next refuel outage 12-%h O 12-o-5 0 12-0-6 X 12-0-16 o
! T6 E__
i e UNIT 2 NON-CONFORMING. SERVICE SENSITIVE VELDS (N0_ SRI VALUE)
NUREG Recuirement: 3-18 Month, 3-36 Month 1-80 Month Examinations "X" Denotes Examination Perforced +.o Date "O" Denotes Examinations to be Performed
" " Denotes Exception to Examination Requirements -
Weld 18 Months 36 Konths 80 Months System Identification 1 2 3 1 2 3 1 Planned Long-Tem Program i
RHR Shutdown 10-IA-1h* X X 0 0 0 0 0 Inservice inspect to ASME Section XI Cooling Return criteria in accordance with 10 CFR Leop "A" 50.55a RHR Shutdown 10-IB-1h* X 0 0 - - - -
Inservice inspect to ASME Section XI Cooling Return criteria in accordance with 10 CFR Loop "B" 50.55a
! RER Heed Spray 10-HS-19 X X X 0 0 0 0 Replace these welds with the installa-10-HS-20 X X 0 0 0 0 0 tion of 316L stainless steel pipe during the next refuel outage 10-HS-21 X X 0 0 0 0 0 10-ES-22 X X 0 0 0 0 0 10-HS-23 X X O. O O O O 10-HS-2h X X X 0 0 0 0 10-HS-25 xX X 0 0 0 0 10-HS-25A 0 0 0 0 0 0 0 10-HS-26R 0 0 0 0 0 0 0 10-HS-27R O O O O O O O
l T7 a _ _ _
l UNIT 2 NON-CONFORMING. NON-SERVICE SENSIfIVE WELDS (SRI E1.2)
NUREG Reouirement: 1-80 Month Examination "X" Denotes Examinations Perfomed to Date "0" Denotes Examinations to be Perfomed Weld 80 Months
' System Identification 1 Planned Leng-Term Progra=
Reactor Recirculation 2-AS-2 X Conduct induction heating stress im-Loop "A" PM Ve:ent t h PmpagaMon of 2-AS-3 0 I.D. defects 2-AS-L X 2-AS-7 0 2-AS-10 0 2-AS-11 0 2-AD-1h 0 2-AN15 0 2-AN15 O l Reactor Recirculation 2-BS-3 O Conduct induction heating stress im-Loop "B" Provement to inhibit propagation of l 2-BS-h O I.D. defects
! 2-B %6 X
, 2-B b9 0 2-BS-10 0 RHR Shutdown 10-0-10 0 Inservice inspect to ASME Section XI l Cooling Suction I criteria in a e rdan e with 10 CFR 10-0-15* 50.55a
~
T8 m ---
UNIm 2 NON-CCNFORMING. NON-SERVICE SENSITIVE WELDS (SRI 21.2)
NUREG Recuire=ent: 1-80 Month Examination "X" Denotes Examinations Performed to Date "O" Denotes Examinations to be Perfomed Weld 80 Months System Identification 1 Planned Long-Tem Prorrem RER Shutdown 10-IA-h Cooling Return O Conduct induction heating stress in-Loop "A" 10-IA-5 0 provement to inhibit propagation of I.D. defects 10-IA-6 0 l RHR Shutdown 10-IB-b X Cooling Return Conduct induction heating stress im-Loop "B" 10-IB-5 o P" ****"*
- I"hiDi* P" P*8 ** " #
I.D. defects 10-IB-6 0 l
i
NUREG Requirement: 1-120 Month Examination "X" Denotes Examinations Performed to Date "O" Denotes Examinations to be Perfomed Weld 120 Months System Identification 1 Planned Long-Tem Program Reactor Recirculation 2-AS-5 0 Inservice inspect to ASME Section XI Loop "A" criteria in accordance with 10 CFR 2- h 6 X 50 55a 2-AS-8 0 2-AS-9 0 2-AN12 0 2-AN13 X 2-AD-16 X 2-AN17 0 2- h 1 0 2- E 2 X 2- h 3 0 2- E h O Reactor Recirculation 2-BS-2 0 Inservice inspect to ASME Section II Loop "B" p_33_7 y criteria in accordan.:e with 10 CFR 50.55a 2-BS-8 o 2-P N11 0 2-B N12 X 2-BD-13 0 2-BD-1h X 2-BD-15 o
^
T10 m
l l
UNIT 2 NON-CONFOPHING. KON-SERVICE SENSITIVE WELDS l' SRI <1.2)
NUREG Recuire:ent: 1-120 F.onth Eranination "X" Denotes Eraninntions Perfor=ed to Date "0" Denotes Eraninations to be Perfomed l
l Weld 120 Ebnths l Systen Identification 1 Planned Lone-Tem Progra=
Reactor Recirculation 2-BD-16 0 Inservice inspect to ASE Section II
. Loop "3" (Continued) criteria n acc rdance with 10 M 2- h 17 0 50 55a 2- h 1 0 2- h 2 X l
2- h 3 0 2- E h X l RHR Shutdown 10-0-11 X Inservice inspec't to ASE Section II Cooling Suction criteria in accordance with 10 CFR 10-0-16 X 50.55a RHR Shutdown Cooling 10-IA-3 X Inservice inspect to ASME Section XI l
Return Loop "A" criteria in accordance with 10 CFR 10-IA-7 0 i
, 50.55a RHR Shutdown Cooling 10-IB-3 0 Inservice inspect to ASE Section Il Return Loop "B" criteria in accordance with 10 CFR 10-IB-7 0 50.55a
?
[ T11 A
. o UNIT 2 NON-CONFORMING NON-SERVICE SENSITIVE WELDS (NO SRI VALVE)
NUREG Reauirement: 1-80 Month Examination "X" Denotes Exaninations Perfomed to Date "O" Denotes Examinations to be Performed Weld 80 Months System Identification 1 Planned LoneTem Progra_m Core Spray Loop "A" 1h-A-12* X Inservice inspect to ASME Section XI criteria in accordance with 10 CFR 50.55a Core Spray Loop "B" 1h-B-11* X Inservice inspect to ASME Section II criteria in accordance with 10 CFR .
50.55a RHR Shutdown Cooling 10-IA-1* O Inservice inspect to ASME Section II Return Loop "A" criteria in accordance with 10 CFR 50.55a RHR Shutdown Cooling 10-IB-1* I Inservice inspect to ASME Section XI Return Loop "B" criteria in accordance with 10 CFR 50.55a RER Head Spray 10-HS- 3* X Inservice inspect to ASME Section XI 10-HS-6* X cr eria in ac ce v m 10 m 50.55a l 10-HS-9* X RHR Shutdown Cooling 10-0-12* X Inservice inspect to ASME Section XI Suction criteria in accordance with 10 CFR 10-0-17* I 50.55a
- Dissimilar Metal Weld T12 m
e <
UNIT 3 NCN-COIFORMING. SERVTCE SEN3ITIVE WELDS (SRI E1.2)
NUREO Renuirerent: 3 18 Month. 3-36 Month.1-80 Month Examinations "X" Denotes Examinatien Perforced to Date "O" Der.otes Eraninatiens to be Perfomed
"" Denotes Exception to Eranination Requirecents-Weld 18 Months 36 Months 80 Months Systen Identification 1 2 3 1 2 3 1 Planned Long-Ter:n Prosrram Reactor 2-AHF-2 Recirculation Conduct induction heating stress in-
.Lo0P A 2- M -3 - - - - - - -
pr vecent to inhibit propagation of I.D. defects 2-ABF-b - - - - - - -
2-AHa-2 - - - - - - -
2-AHG-3 - - - - - - -
2-AHa-k - - - - - - -
2-AHH-2 - - - - - - . -
2-AHH-3 - - - - - - -
2-AHH_h - - - - - - -
2-AHJ-2 X 0 0 0 0 0 0 2-AHJ-3 0 0 0 0 0 0 0 2-AHJ-h X X 0 0 0 0 0 2-AE-2 - - - - - - -
2-AHK-3 - - - - - - -
2-AR-b - - - - - - -
T13 O
UNIT 3 NON-CO'iFOR IING, SERVICE SENSITIVE WELDS (SRI k1.2)
NUREG Reauirement: 3 18 Month. 3-36 Month. 1-80 Month Examinations "X" Denotes Examination Perforced to Date "0" Denotes Examinations to be Performed
"" Denotes Exception to Examination Require =ents Weld 18 Months 36 Months 80 Months system Identification 1 2 3 1 2 3 1 Planned Long-Term Pro. g i' Reactor 2-BHA-2 X 0 0 0 0 0 0 Conduct induction heating stress im-Recirculation Provement to inhibit propagation of
. Loop "B 2-BHA-3 X 0 0 0 0 0 0 I.D. defects 2-BHA-h X0 0 0 0 0 0 4
2_BHs_2 - - _ - - - -
1 2-BHB-3 - - - - - - -
2-BHB-h - - - - - - -
2-BBC-2 - - - - - - -
2-BHC-3 - - - - - - -
2-BHo-h - - - - - - -
2-ben-2 - - - - - - -
2-BHD-3 - - - - - - -
1 2-BHD-h - - - - - - -
2-BHs-2 - - - _ - - -
2-BHE-3 - - - - - - -
2-BEE-h J
T1h i
1 .
n
4 ,
UNIT 3 NON-CONFORMING, SERVICE SENSITIVE WELDS (SRI U1.2)
NUREG Recuirement: 3-18 Month, 3-36 Month. 1-80 Mon _th Examinations "X" Denotes Examination Performed to Date "O" Denotes Examinations to be Performed
" " Denotes Exception to Examination Requirements Weld 18 Months 36 Months 80 Months System Identification 1 2 3 1 2 3 1 Planned Long-Term Program RHR Shutdown 10-0-1 X X X 0 0 0 0 Conduct induction heating stress im-j Cooling Suction pr vement to inhibit propagation of 10-0-2 X X X 0 0 0 0 I.D. defects 1%%h 0 0 0 0 0 0 0 10-0-6 X X X 0 0 0 0 10-0-7 X X X 0 0 0 0 Inservice inspect to ASME Section XI criteria in accordance with 10 CFR SC.55a.
RHR Shutdown 10-IA-8 X 0 0 - - - -
Conduct induction heating stress ir.
e Cooling Return provement to inhibit propagation of Loop "A" 10-IA-9 0 0 0 - - - -
I.D. defects i
10-IA-11 X 0 C - - - -
Inservice Jnspect to ASE Section XI
- criteria in accordance with 10 CFR 50.55a RER Shutdown 10-IB-8 X X X 0 0 0 0 Conduct induction heating stress it-Cooling Return pr vement te inhibit propagation of Loop "E" 10-IB-9 X X X 0 0 0 0 I.D. defects 10-IB-U X X X 0 0 0 0 Inservice inspect to ASE Section XI criteria in accordance with 10 CFR 50.55a T15
UNIT 3 NON-CONFOPlGNG. SERVICE SENSITIVE WELDS (SRI <1.2)
NUREG Recuirerent: 1-60 Month Examination "X" Denotes Examinations Perforced to Date "O" Denotes Exa=inatican to be Performed Weld 80 Fanths j Systen Identification 1 Planned Long-Term Program Reactor Recirculation 2-ABF-1 0 Inservien inspect to ASME Section XI Loop "A" A riteric in accordance with 10 CFR 2-AHG-1 50.55a 2-AHJ-1 0 l
2-AHK-1 0 '
2- h 1/AHK 0 2- 5 1/ARJ 0 2- w h/AHG 0 2- w h/AHF 0 Reactor Recirculation 2-BHA-1 0 Innervice inspect to ASME Section XI Loop "B criteria in accordance with 10 CFR 2-BHB-1 0 50.5%
2-BHD-1 0 2-BHE-1 0 2- % 1/ BHA 0 l 2-%1/BBB 0 2- w h/BHD 0 2- w h/BHE O RHR Shutdown 10-0-3 X Inservice inspect to ASME Section XI Cooling Suction 0 r eria in accordance w m 10 C E 10-0-5 50.55a
. T16 O. _ _ _ _ _ _ _ _ _ _ _
s e UNIT 3 NON-CONFORMING, SERVICE SENSITIVE WELDS (SRI <1.2)
NUREG Recuirement: 1-80 Month Examination "X" Denotes Examinations Perferred to Date "O" Denotes Examinations to be Performed Weld' 80 Months Systen Identification 1 Plaa.ned Lond-Term Program
- RHR Shutdown Cooling 10-IA-10 0 Inservice inspect to ASME Section XI Return Loop "A" criteria in accordance with 10 CFR 50 55a RHR Shutdown Cooling 10-IB-10 X Inservice inspect to ASME Section XI Return Loop "B" criteria in accordance with 10 CFR '
50.55a
< b i
I O
e i
T17 4 Y
-O
UNIT 3 NON-CONFORMING, SERVICE SENSITIVE VELDS (NO SRI VALUE)
NUREG Requirement: 3-18 Month, 3-36 Month, 1-80 Month Examinations "X" Denotes Examination Performed to Date "O" Denotes Examinations to 'ce P- forced i " " Denotes Exception to Examination Requirements Weld 18 Months 36 Months 80 Months Syste: Identification 1 2 3 1 2 3 1 Planned Long-Term Program ,
RHR Snutdown 10-IA-1h* X 0 0 - - - -
Inservice inspect to ASMS Section XI Cooling Return criterie in accordance with 10 CFR 1
Loop "A" 50.55a i 4
RHR Shutdown 10-IB.-1h* X X 0 0 0 0 0 Inservice inspect to ASMB Section XI
. Cooling Return criteria in accordance with 10 CFR Loop "B" $0 55a i RHR Head Spray 10-HS-19 X .i X 0 0 0 0 RerInce these welds with the installa-10-HS-20 X X X 0 0 0 0 tion of 316L stainless steel pipe during the next refuel outage j 10-HS-21 X X X 0 0 0 0 i 10-HS-22 X X X 0 0 0 0 10-HS-23 X X X 0 0 0 0 10-HS-2h X X X 0 0 0 0
) 10-HS-25 X X X 0 0 0 0 10-HS-26 X X X 0 0 0 0 10-HS-27 X X X 0 0 0 0
Y T18 1
.c .
. a UNIT 3 NON-CONF 0P. MING, NON-SERVICE SENSITIVE WELDS (SRI 21.2)
NUREG Reauirement: 1-80 Month Examination "X" Denotes Examinations Performed to Date "0" Denotes Examinations to be Perforced Weld 80 Months 4 System Identification 1 Planned Long-Term Progrer Reactor Recirculation 2-AS-2 O Conduct induction heating stress im-Loop "A" pmvemen i p mpagaMon of 2-AS-3 0 I.D. defects 2-AS-h 0 2-AS-7 X 2-AS-10 0 2-AS-11 0 2-AD-1h 0 2-AD-15 X 2-AD-18 0 3 Reactor Recirculation 2-BS-3 0 Conduct induction heating stress im-Loop "B" pr vament to inhibit propagation of 2-B M 0 1.D. lefects 2-BS-6 0 2-BS-9 0 2-BS-10 0 RHR Shutdown 10-0 10 0 Inservice inspect to ASME Section XI Cooling Suction riteria in a rdan e with 1 CFR 10-0-15 0 50.55a T19
_. e
~
1 UNIT 3 NON-CONFORMP'% NON-SERVICE SENSITIVE VELDS (SRI E1.2)
NUREG Reanire=ent: 1-80 Month Examination "X" Denotes Examinations ?erformed to Date "O" Denotes Examinations to be Performed Weld 80 Yonths 4 System Identification 1 Planned Lons-Term Program RHR Shutdown 10-IA-14 0 Conduct induction heating stress in-Cooling Return Provement to inhibit propagation of Loop "A" 10-IA-5 0 I.D. defects 10-IA-6 0 l
) RHR Shutdown 10-IB-14 0 Conduct induction heating stress im--
Cooling Return provement to inhibit propagation of Loop "B" 10-IB-5 0 I.D. defects 10-IB-6 0 l l
4 T20 A
a .
UNIT 3 NON-CONFORMING, NON-SERVICE SENSITIVE VELDS (SFl 41.2)
NUREG Recuire:ent: 1-120 Month Examination "X" ~; notes Examinations Perforced to Date "O" Lenotes Examinations to be,Perforced Yeld 120 Konths System Identification 1 Planned Long-Term Program Reactor Recirculation 2-AS-5 0 Inservice inspect to ASME Section XI Loop "A" criteria in accordance with 10 CFR 2- 6 6 X 50.55a j 2-AS-8 X 2-AS-9 0 2-AD-12 0 2-AD-13 X 2-AD-16 0 ,
2-AD-17 0 '
2-AM-1 0 2-AM-2 X 2-AM-3 X 2-AM-h 0 Reactor Recirculation 2-BS-2 O Inservice inspect to ASME Section XI Loop "B" criteria in accordance with 10 CFR 2-B M X 50 55a 2-BS-8 X 2-BD-11 0 2-BD-12 X l 2-BD-13 0 2-BD-1h 0 1
2-BD-15 0 m
. T21
. . . . . . . . . ..m._.. ..
UNIT 3 NON-CONFORMING, NON-SERVICE SENSITIVE WELDS (SU <1.2)
~
NUREG Requirement: 1-120 Month Examinatiot.
"X" Denotes Examinatb ns Perforced to Date "O" Denotes Examinations to be Perforand .
I Weld 120 Months System Identification i_ Planned Long-Term Program Reactor Recirculation 2-BD-16 0 Inservice inspect to ASME Section XI Loop "B" (Continued) riteria in accordance with 10 CFR i 2-BD-17 0 50.55a 2-B W1 0 2-35 2 X 2-BW3 0 2-BWl4 0 RHR Shutdown Cooling 10-0-11 0 Inservice inspect to ASME Sect'.e. 7
" *I " criteria in accordance with 10 CFR 10-0-16 0 50.55a RHR Shutocen Cooling 10-IA-3 X Inservice inspect to ASME Section XI Rettrn i,oop "A" X criteria in acc e dance with 10 M 10-IA-7 50 55a RdR Shutdown Cooling 10-IB-3 0 Inservice inspect to ASME Section XI Return Loop "B" riteria in accordance with 10 CFR 10.IB-7 0 l 50.55a
'T22
s .
UNIT 3 NON-CONFORMING, NON-SERVICE SENSITIVE WELDS (NO SRI VALTE)
NUREG Recuirement: 1-80 Month Examination "X" Denotes Examinations Perforced to Date "0" Denotes Examinations to be Perfomed 4
Weld 80 Months System Identification 1 Planned Lone-Term Program Core Spray Loop "A" 1h-A-12* X Inservice inspect to ASE Section XI criteria in accordance wit.h 10 CFR 50.55a l Core Spray Loop "B" 1h-B-11* X Inservice inspect to ASME Section XI j criteria in accordance with 10 CFR 50.55a RHR Shutdown Cooling 10-IA-1* O Inservice inspect to ASME Section XI Return Loop "A" criteria in accordance with 10 CFR 50.55a
, RHR Shutdown Cooling 10-IB-1* O Inservice inspect to ASME Section XI Return Loop "B" criteria in accordance with 10 CFR 50.55a I
RHR Head Spray 10-HS-3* O Inservice inspect to ASME Section XI 10-HS-6* X criteria in accordance with 10 CFR 50 55a 10-HS-9* X l 4
RHR Shutdown Cooling 10-0-12* X Inservice inspect to ASME Section XI Suetien .
10-0-17* O criteria in accordance with 10 CFR 50.55a
,
- Dissimilar Metal Welds T23 ,
WELD IDENTIFICATION FIGURES Peach Bottom Unit 2 Table of Contento Finuro Ti t1e Paco A-11 hin Rocirculation - Loop "A" Suction F-1 A-12 hin Rocirculation - Loop "A" Discharge and 2 Bypass b13 h in Rocirculation - Loop "A" Nanifold 3 A-14 hin Rocirculat, ion - Loop "A" Risers k A-1$ hin Rocirculation - Loop "B" Sue'.on $
A-16 h in Rocirculation - Loop "B" Discharge and 6 Bypass b17 hin Recirculation - Loop "B" Manifold */
b18 Main Recirculation - Loop "B" Risers 8 A-26 Residual Heat Removal Road Gpray ~9 b27 Residual Heat Removal (in) Loop "A" 10 A-28 ResidualHeatRemoval(in) Loop"B" 11 b29 Residual Heat Removal (out) 12 A-31 Reactor Water Clean-Up (ottt) 13 A-33 Coro Spray Loop "A" 1h A-3h Core Spray Loop "B" 15 Peach httom Unit 3 Tablo of Contento s
Figuro Title Patm A-11 Min Recirculation - Loop "A" Suction 16 612 h in Recirculation - Loop "A" Discharge and 17 Bypass b13 Main Rocirculation - Loop "A" Manifold 18 A-14 Main Recirculation - Loop "A" Risers 19 A-15 hin Recirculation - Loop "B" Suction 20 A-16 hin Recirculation - Loop "B" Dischargo and 21 Bypass A-17 Main Rocirculation - Loop "B" Manifold 22 i
Finiro Titic Pam_
A-18 Main Recirculation - Loop "B" Risers F-23 A-26 Rosidual Heat Removal Head Spray - 2h A-27 ResidualHeatRemoval(in) Loop"A" 25 l A-28 ResidualHeatRemoval(in) Loop"B" 26 A-29 Rosidual Hoat Removal (out) 27 J
A-33 Coro Spray Loop "A" 28 A-314 Core Spray Loop "B" 29 1
4 l
l I
I 1
11 1
.ca p , --..am .,--- --gy9 p-, ,,ye.,p,,+y p y - - ,-.v.,.gw.p-.w- g p "'"" * " *-" " "
9TT""*'W'T**W"*"7*HT**'"t*""'T & " ' ' ' '"*'""**F"--'*"FT*"' f'"P-" C t~'#T'** T#""'F
- 1 Legend of Symbols PS Pipe Support I
h RL Rostraint Lugs llL Hunger Lugs k Direction of Flow
{y- DC I3'"".ch Connections 4 or Smaller Dronch Connections A .4 Larger Than 4"
--->- General Information
, Wold identification Containment Penetration l
111
Peach Bottom Unit 2 M AIN RECIRCUL ATION - 1.00P "A" SUCTIOrl N1A Uf
@ 2 AS 1 2AS2
! r,', h NOTE: 2 AS 1,2-AllF 5.2 AttC 5 f 2 AHH 5.2 AHJ 5. sad 2 AliK 5 2 AS 28 0 AHE 0 SStu LArt METAL S 2 AS-3LU l.k.hh2-A03 -
MAtN RECIRC-LOOP "A"
- ~ --2-AS4 MATERIAL-STAINLESS STEEL 2-AS4LUt 1 P1PE DATA-SUCTION (AS) 2-AS4 LUOE 2 AS4LD 1
[
NOM 00-20*
2 AS SLO MIN WT-1 G38" 2 AS 6 NOM CIRC-89" C AL. S L K. 28 3 3 *X*l.3 22
- S A
- PES
.a TO niiR (OUT)" " 2 A-PUMP RL 1 2 AS G '
2-AS GLD -- 2 A-PUMP HL 2A-aj 2 AS4tiL 1 THHU 4 , f
/s 2 APUMP HL 1A C
-4 2-AS9LO j 2 AS 9 2 AS 93C C
, ( -2AS0 2 AS DSC-A 2 S 6 0C A Q ," PUMPtA 2 AS-7LU j
',-[
q 2 AS 7 -
- {. 4 I h ,,, .
-2 A PUvP ttL 2 2 As-7: 00 2 AS 7LDI
/' d /*
-2 A PUvP HL 3A 3
/ b 0 43A
. . 2 AS 11 2 AS B UC u 2 AS 0!tt 2 A PUMP RL 3 2 AS S DC C 2 AS att; -2 AS lO 2-AS 7HL 2 AS-Dec S
- 2 AS tO Lu l-2 AS s80 0 2 AS.:stuO
{2 AS 11LUI
{2-AS 2 AS10LDI 10LDO
,I 4
FIGURE A-Il 1
l 1
Peach Bottom Unit 2 DISCHAliGE AND BYPASS 2AD17 f FROM RHR (int LOOP"A" i 2-AD 15LD .
2 AD 15 2AD16 2- AD 15LU l b 2-AD 16L1J
~^
2 AD 12LD s'*
2 A414LDI
'F2 AD lb/DPAN -AD 16HL 1 THrtU 4
2 AD 135C B 2 AD 13 [2 BPA 10. A 2 AD-130C Cj 2 AD 13L j
' hPE DATA-DISCt4ARGd (AD) q g J
' NOM 03-28" MIN WT-1.272"
' 2 AD 13P5JJ U' 14P5 NOM CIRC-80" MOL3Ag AD IJrS 2 C AL. 9 LE.2 8 S S *X l.3 2 2 -9 A-PE8 P PE O/.TA-0YPASS (BPA)
NOM OD-4.5" FOM WT- 0 337 isch. 80s NOM CIRC 14" C AL. BLK.4-SS 80 .337 80A PE8 2 BPA 1- A
)
^
NOTE: 28" 22".& 12"P;?i tS SEAM WELCED I
4 FIGURE A-12 i
l j
Peach Bottom Unit 2 MO*SSA3 2 AM 2 BC-C g 2*AM 2BC.O 2- AM-28C.A 2*AM. \ ]
/ 2.AM.2 i !
d
<g s 2 AM*2M \ 2*AM*2A "N 2-AM-28 2*AM 2C 2 AM-2L ,
2*AM*2D
- AM MANIFOLD 2.AM*2K ,
2-AM 2J
- 4/ 2 - AM AGF1 A6G-LU 2.AM-28CC 24HK.1 W 24HH.1LD 2AHK1 2 AN'IW 2 ANO ILO I'AHE*I bO 2-AM-28CB 2.AHH l 28 A 1/AHJ Mo GSAg 2A *
/ ,
2 4sA AM4/AMF
- a ,. ~2 . n , ? )
LCOP \ 2-AM 2AM3 24M4LD 2.AM 3LD 2MIRt. 2-AM lLD 2 AM 1HL-2 \
1 2M2 ~2'#U'I HI SEE DETAIL Aeovg 2- AM-4 /AHy i,C -
PtPE D/Y,%UANIFOLD (AM: 2- AM + ML F:0!J OC -2t* A M -l / A HJ - LD
?.'iN WT-GJ. 7 2- AW'4 H L kG?a ctRC~u S*
CAL. ELK. 22 ss-X s.030 14-Pts ,
2-AM AGF-LO FIGU.9E ,,A-13 F-3
4 4
Peach Bottom Unit 2 Risers 300*
2-AHG-5 h 2 AHF 6 l h 2-AHH $ 2l
- 2AHG4 2-AHF4 Q 2AHKS 330*h 2y_,g,4 AHJ 5 3 2-AHH4 e N 2F y_gg o 2-AH K4 g gg , N 2J ,-
/N'20 % wpy, 2.AHH4 LU 2AHG4LU 2-AllF 3LD 2 AHK4LU- 2-AHJ4LU 2AHG3LD e 2 Al*-3 .AHF.3LU 2
2 AHK 3tD ,r 2 AHJ 3LD 2 AHH 3LO -g,ggg.3 '- 2 AHF-2LD 2 AHK 3 2 O3'U m 1 2 AHJ-3 2 AlH'8 324HH.3LU . 2.AH3 3LU %2 AHF.2 4
y f ,
-L 2 AHJ 3LU .
- 2. AHH-2 LD "E- ,
2 AleG 2LD 2 AHF-2LU q
4 2 AHK 2LD
- 2 AHJ-2LD 2 AHH 2 2 AltG 2 ,
g,Agr.g Lg AHK2 2-AHJ 2 g,A3,4ggy ; L g.A gg.gty Ji, 7 Ag7,9 J L .y Aug.2LU j $ 2' At.tJ 21 U 1 .
2 AHH no f2 AIG1LD 2 / 2 AHG 1 p'2;'" _
f'W;' d -AHit-1 . / -
tit *C OAT A Iif AcrR::{Al11 Nou OD- 12.75 kliN WT-0 5091VE RTI
. 0 7L"J (tlon173 Nun 4 C1RC-40 5" C AL. 8 L K, it - 5 S - N *.6 2 5- II A
- P E S h NOTE. 2- ANK- S . 2- AHJ-S . 2-AllH-5, 2.AHG-3, AND 2-A'tF-5 ARE DISSIMILAR LCTALS -
I' FIGURE A-14 4
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Peach Bottom Unit 2 4
DISCHARGE AND BYPASS 2 0F 15tu 28016 2 BD-14 LD f j - FROM RHR (IN)-LOOP"B" 2 0 0614 - -
28015 2-B0-14).8J0 j g 2 BD-14Lui e 2 BD-13LDI p 2 I:D-13LDO l )( 2 BD-14HL 1 THRU 4 2 6014/8P3 2 SD-11LD \- 2 t!P&l0- A 2-6 0-11 2 B0-13 O P&PE DATA-DISCHARGE (803 NOa,100- 28" MCL538 f ~ 9IN nT-1.272" m
2 ED-12
( Nou 00 89*
{ 2 0012L f ) f C AL.BLE.28 SS-X-8.322*S A* PES
' P&PE DATA BYPASS (SPU 2 DD-II/UPg 2-SPU-t A
[
200123 1 2-eD-tM NOM 00--4 5" NOM WT-0.337 M M 00-121$2 Nota CIRC-14" C A L.6 L K.4-S $* S O ".3 3 7*lO A* PE S i
i i
?
i FIG 9RI A"16 i
4 1
1 I
h Peach Bottom Unit 2 i
1 2*BM-20 2*5M-2E i:i":li \\ // i:i":i; 2* SM-2H i \
i
, % (( p t-SM-2K 2 8M-2J 2 gu-2A ,, r t-BM-2L 2 -BM - 2M MO 8 5 5 2-Bu- 3 1 I 2-eu-2
- VALVE SY* PASS I 2 8M 2BC 2 tM 2BC 8 2-eM-asc-c [
MANIFOLD 2-BM l/3H3 Lu 2 BM l/8HA-2 *SM*l/SH A-LU SEE DETAIL A00VE tr 28017 2 SM 1/Eria 2 eu 31tt.21 Nlj 2 BM-4/BHE J aM.4/gHo l j
./ 2 CM 3r1L 22 gy A ;*/ . . . , ;*] ... . .
TO LOOP A
- b? ' ' ** bM 3HL 2 3 2 DM S
> /2.M4h 2- M-SHO *L D
/
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2-DM 4HS p
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2 8M-1LD UU'I 72SMIPL2 BM lilL.3 v' '- n2 2nt.,
2 su 3tD 2 BM 3 2 - DM -l/ O NS-L O 2 DM 20C-C
'/BM 41fL 1 2 0M 4t D MO CSS 2 CM 4HL 2 2DM4 2-au-4/enn Lu 28Mtuco 2 0M lHL 2 0'A 2JC-A 2-BM 4/ SHE
- LD 2 UM.2 PIPE DAM-MANIFOLD (BMI 2*8 M l/8H A- LD -
, NOM OD-22"
} MIN VIT-0.000*
a NOM CHtC-GS 5" CAL .8L K. 22 - SS -X 8.030 14-PES l
4 FIGURE A-17 i I 1
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Peach Bottom Unit a ions 2s 14HS27 RESIDUAL HEAT REMOVAL 10025 HEAD SPRAY t14HSs HEAO SPRAY st.ANGE MATERIAL: '
- D CARDON STEEL-10 HS1 TO toHS 3 ISHS6TOl@HS9 STAirdLESS STEE t.+10HS3 TO I4HS8 ISHS 9 TO 10+sS27 GHS23 k.s H 22 h NOTE: 14HS-3.14HSS. ANO 14HS9 ARE OtSSIMILAR METALS 1 HS21 PlPE DATA-HEAO SPRAY (10 HS)
NOM 00-6.625* IGHS20 NOM WT-0.432 isch, aos CS de SS h0M CIRC-38" 34HS 39 CAL. SLK.6*CS -80*.4 32 -4 PE0
~ OHraELL FLANGE 6* S S '80*.432
- S A* PES i>HSie 14a*HS 17HL*1 THAu 4%
4-
)L o-a3 ar i.HS.,, ,S. ,
14HS16 14HSI4 = 14HS15
)( 10 HS12HL 1 THRU 4
/ 14HS 2 D
@ 10-HS3 @
r ' -- 10-HS 12 i+HSi f- i>HS.ii
- o 10 HS10 o i 14HS4 IOM h ,
ISHS5 14HS8 a
MO 1033-4 21032 HIGHS 4
-i m FIGURE A-26 il F-9 l
Peach Bottom Unit 2 141A 14 141A10 h 14IA 10LUI / POS-GI A 28"LtAIN RECIRC LOOP "A" 141A10 LOO l DISCHARGE IC IA9LD -'
144A 9LDO p
IGlA 9LU 10 IA 12 gggg,g g 141ASLD gggg
\ go.lA IILUO m.eA.It L ul g 141A-8LUS I A 0 143A 8LUO gggA.$
144A 7LDI I4*IM '\
/ 148A 5LU 141A 7 LOO < 143A 4LO 141A7 - 148A 4 E2 14tA-4tuO 141A7LU TJ 10-lA.4Lus 144A3LDO 141A4FS 541A 3Los RESIDUAL HEAT REMOVAL (IN) gggg LOOP "A" hd A (141Al gggA.3(y q
- ATERIAL 10 -14*2 #,
STAINLESS STEEL-14tA 1 TO 10 IA Il ,D CARSON STEEL-14tA 1 AND 141A ll TO +
143A 14
/
/
P6PE DATA-RHR llNI LOOP"A"(144Al g :48A.2LO NOP.100-24" "'
i tilN wT-1.072 STAtNLESS STEEL NOH wT-1.531 (Sch.1003 CARBON STEEL
, k NOfl CIRC-76* gggg ,
l I j L
h NOTE: 148At.14tA 11. AND 148A 14 b ARE DISSIMil.AR METALS f NOTE: STAINLESS STEEL IS SEAMED CARBON STEEL IS SEAMLESS C AL. 8Lat. 2 4*CS* LOO *l.531*2 A* PEG 24 *J5 *tOO *l.331- 32
- PES FIGURE A-27 F-10
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