ML20076J073
| ML20076J073 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 06/14/1983 |
| From: | Bradley E PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8306200317 | |
| Download: ML20076J073 (31) | |
Text
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PHILADELPHIA ELECTRIC COMPANY 2301 M ARKET STREET P.O. BOX 8699 PHILADELPHI A. PA.19101 EDW ARD G. B AU ER, J R.
a osans a6 counssk EUGENE J. BR ADLEY a as...ea.......a ....s..
DON ALD BLANKEN 9 /_
KUDOLPH A. CHILLEMI E. C. KIR K H A LL T. H. M AMER CORNELL PAUL AUERB ACH assistant osmenaL counsak June 14 8 1983 2DW ARD J. CULLEN J R.
THOM AS H. MILLER. JR.
G R ENE A. McKEN N A assesvant cousesst Mr. A. Schuencer, Chief Licensing Branch No. 2 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
Limerick Generating Station, Units l&2 Re ference : NRC Letter from A. Schwencer toe. G.
Bauer, Jr., dated June 3, 1983 File: GOVT l-l (NRC)
Dear Mr. Schwencer:
l l Attached are draft responses to NRC Questions 250.1, 250.2, 250.3, 250.4 and 250.5 of the referenced letter.
The information contained on these draft page changes will be incorporated into the FSAR, exactly as it appears on the attachments, in the revision scheduled for July, 1983.
Sincerely, 8306200317 830614 PDR ADOCK 05000352 l E PDR Eug ,e J. B adley SAJ/gra/22 Copy to: See Attached Service List l l i i
l
cc: Judge Lawrence Brenner (w/o enclosure)
Judge Richard F. Cole (w/o enclosure)
Judge Peter A. Morris (w/o enclosure)
Troy B. Conner, Jr., Esq. (w/o enclosure)
Ann P. Hodgdon (w/o enclosure)
Mr. Frank R. Romano (w/o enclosure)
Mr. Robert L. Anthony (w/o enclosure)
Mr. Marvin I. Lewis (w/o enclosure)
Judith A. Dorsey, Esq. (w/o enclosure)
Charles W. Elliott, Esq. (w/o enclosure)
Jacqueline I. Ruttenberg (w/o enclosure)
Thomas Y. Au, Esq. (w/o enclosure)
Mr. Thomas Gerusky (w/o enclosure)
Director, Pennsylvania Emergency Management Agency (w/o enclosure)
Mr. Steven P. Hershey (w/o enclosure)
Donald S. Bronstein, Esq. (w/o enclosure)
Mr. Joseph H. White, III (w/o enclosure)
David Wersan Esq. (w/o enclosure)
Robert J. Sugarman, Esq. (w/o enclosure)
Martha W. Bush, Esq. (w/o enclosure)
Atomic Safety and Licensing Appeal Board (w/o enclosure)
Atomic Safety and Licensing Board Panel (w/o enclosure)
Docket and Service Seccion (w/o enclosure)
LGS FSAR 8 OUESTION 250.1 11 Clarify the inconsis,tency between FSAR Tables 5.2-10 " Inservice 13 Testing and Inspection - Class 1 Component" 1 Sections A, C, and 14 D) and Table 6.6-1 " Inservice Testing and Inspection - Class 2 14 Components" 1 pressure vessel, pumps, and valve sections) and 15 Sections 5.2.4 and 6.6 of the May 21, 1982 letter from 16 John S. Kemper, Philadelphia Electric Company to 16 Harold R. Denton, NRC which states that the preservice inspection 17 for reactor pressure vessels, pumps, and valves will meet the 18 requirements of the 1980 ASME Code Section XI including the 19 Winter 1980 Addenda. 19 RESPONSE 21 Eections 5.2.4 and 6.6 have been changed to indicate that only 23 the PSI /ISI of the reactor pressure vessel and the operational 24 readiness testing of pumps and valves use ASME Section XI (IWP 25 and IWV) 1980 code, including the Winter 1980 Addenda. All other 27 PSI /ISI testing is performed under the codes discussed in revised 27 Eections 5.2.4, 5.2.4.5, and 6.6. The PSI /ISI information on the 29 RPV has been deleted from Table 5.2-10 and placed in 29 Table 5.2-11. 29 i
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1 5.2.4 INSERVICE INSPECTION AND TESTING OF THE REACTOR COOLANT PRESSURE BOUNDARY (RCPB). , ..
3 The construction permits for the Limerick Generating Station Units 1 and 2 were issued in June 1974 and the inservice inspection program was required to meet the 1971 ASME B&PV Code, (hereinaf ter referred to as "the Code"),Section XI, through the Winter 1972 Addenda. .
i YcNda e ith the provisio of 10 CFR 50.55a(g) which allows for the use of subsequent eff tive editions and ad nda'of the L Code, the inservice inspec n program for Class 1 iping systems meets the requirements of he 177 fode,Section I through the Summer 1975 Addenda wi Appendsi . t of the W ter 1975 Addend ..
l and paragraph IWA-22 of the b e[r ] 1 9 7 6 nda, A d to the est
- practicable. The ctor pr de vessels d Class 1 pump d valve testing wi be in ce rdan with e ASME 1980 cod
! including the te 5$ dd Thr ghout the servi life, components e si JdSI B , Clas I will meet th requiremen exc or and cess provisions nd preservi i on ements t forth in the dition and Addend ft de XI th is effective later than 6 mo s pri o the month p iod during whi the inservice ins etion is conduct , to th extent practic within the 1 iltations of design, geome , and material of construction.
Should certain Code Section XI requirements be determined to be impractical in the course of inspecting the components, PECo will .
submit a request for relief from the requirements to the NRC in-accordance with the provisions of 10 CFR 50.55a(c)(5).
h inse vice inspe ion program descri is for the fir 40-month period lowing start of e .iercial operatio If later editions and enda of the Code b ome effective pr to six months bef this interval, t Finspection progr will be revised cecordi y. The type and accor . ce with the requi .ents of the Code
. er of examinatio will be in per the first 40-month
. The program i onsistent with an inservice inspection i erval of 10 years.
5.2.4.1 System Boundarv -
Limerick piping was originally designed to ANSI B31.7. For the purpose of inservice inspection, ANSI B31.7 C? +s I is considered
' cquivalent to ASME Code Section III Class 1. Figures 5.2-14 through'5.2-29 show the systems or portions of systems included in l the inservice inspection program.
5.2.4.2 Accessibility -
Th'e access'provided for the various components and parts is in accordance with Subarticle IWA-1500 of Section XI of the Code.
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DRAF L gso INSERT A Yw /d'A-In accordance with the provisions of 10 CFR 50.55a(g), which allows for the use of subsequent effective editions and addenda of the Code, the inservice inspection program (with the exception of the reactor pressure vessel and the operability testing of pumps and valves programs) meets the requirements of the 1974 Code,Section XI through the Summer 1975 Addenda with Appendix III of the Winter 1975 Addenda and paragraph IRA-2232 of the Summer 1976 Addenda, to the extent practicabic. The reactor pressure vessel testing will be in accordance with the ASME 1980 Code including the Winter 1980 Addenda. The inservice testing of the operability of pumps and valves are in accordance with the requirements of ASME Section XI, IWP and IWV of the 1980 Code including the Winter 1980 Addenda. Throughout the service life, components classified ANSI B317, Class I will meet the requirements, except for design and access provisions and preservice inspection require-ments3 set forth in the edition and Addenda of the Code Section XI that is effective not later than 12 months prior to the initial 120 month inspection interval (which commences with c68ercial 4
operation) or 12 months prior to any subsequent 120 month inspection interval.
l Insert B l
The inservice inspection program described is for the first 120 monthperiodfollowingstartof.ck2ercialoperation. If later editions and Addenda of the Code become effective prior to 12 months before this interval, the inspection program will be revised accordingly.
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- c. Holstsandotherhandlingmachineryneces,sarytosuphet - .
inservice inspection are provided.
- d. Equipment, personnel, and procedures for alternative examinations that may be required will be provided.
- s i ~ e. Repair and replacement procedures"are provided for
',' system components and parts, when necessary.
Examination Techniques and Procedures 5.2.4.3 s.
The techniques and procedures for surface, visual, and volumetric examinations are in compliance with ;
Subarticle IWA-2200 of Section XI of the Code.
b.
Alternate examination methods are acceptable provided the results are equal or Thesuperior to the criteria acceptance methods forof Subarticle IWA-2220.
alternate examination methods shall be in accordance with Sebarticle IUS-3100.
5.2.4.4 Inspection Intervals Inservice inspection is performed according to the schedule : ,T outlined in Subarticle IWB-2400; all required examinations being _/
completed inspection interval. within a 10-year period, hereafter referred to as theInsp with normal plant outages.
5.2.4.5 Examination'Catecortes and Requirements *[pidMr. erce/,w gg Table .2-10 provides a listing of the Class 1 components,or h,ptj y,
parts the corresponding Table IWB-2600 item number, the Table IWB-25 0 examination category, the required method of examination, and the extent and frequency of examination.
Components exempted asTaprovided f b2. - t/ pvbyr.'/a/
Subarticle a.
IWB-1220 ar Category BP of Table IWB-2600. i !s wvMr 4, se reputermee.h of &< / qfs Roos 9w fnerere ntret cenyremo fts ba& h Cd /s es tW. M.c 8*s> 8'r it#u Mhwk.
5.2.4.6 Evaluation of Examination Results
- a. The standards for evaluation of examination results are in accordance with Subarticle IWB-3100.
The repair procedures are in agreement with Subarticle
.b.
IWB-4000. -
- c. Flaw analysis is in accordance with the requirements of Table IWB-3410.
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6.6 INSERVICE INSPECTION OF CLASS 2 AND 3 COMPONENTS ..
TheconstructionpermitsfortheLimerickGeneratinghtstion Units 1 and 2 were issued in June, 1974, and the inservice inspection program was required to meet the 1971 ASME B&PV Code .
(hereafter referred to as "the Code"),Section XI through the Winter 1972 Addenda.
In accordance with the provisions of 10 CFR Part 50.55a(g), which allows for the use of subsequent effective editions and addenda of the Code, the inservice inspection program for Class 2 and 3 f.A */ r*gA'- ' ";rt r meet XI through the Summ/ er the 1975requirements Addenda, with of the 1974 Code, Appendix III ofSection the .
Winter the gm,,er./;L976 AddendaJS75 to the Addenda extent and paragraph IWA-2232 practicable. Pump and ofvalv LesEs wT11 be in accordance with the 1980 code,Section XI inc1 ing the Winter l 1980 Addenda. Throughout the service life, components classified as ANSI B31.7 Classes 2 and'3 will meet the requirements, except .
I for design and access provisions and preservice inspection requirements, set forthJn th dition of the Code Section XI thatiseffectiveTbMordthe inservice inspection is conducted to the extent practicable month period during which the within the limitations of design eometry, and construction materials. e r. rs e rwk prok h * *y ed uje **Y s, .
no on es *A is sp es1%e. imhrn/
(-) If certain Code Section XI requirements are determined to be ,
impracticable in the course of inspecting components, PECo will submit a request to the NRC for relief from the requirements, in accordance with the provisions of 10 CFR Part 50.55a(g)(5).
The inservice inspection program described is for the first 9 0 = @ month period following the start of commercial operation. If subsequent editions of the Code become effective earlier than e4m- #2 months before the start of this interval,.the inspection program will be revised accordingly. S: i-l;- - ' -"^ ^- M
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I Z-6.6.1 COMPONENTS SUBJECT TO EXAMINATION Limerick piping was originally designed to ANSI B31.7. For
. .. inservice inspection, ANSI B31.7 Classes II and III are considered equivalent to ASME Code Section III Classes 2 and 3.
Examination of welds (Class 2 components) and system pressure tests (Class 2 and '3'~ systems) will be conducted on the basis of a 40-month examination period. Performance examinations of pumps and valves will be conducted on the basis of a 20-month examination period. The piping and instrument diagrams for each system, located in the sections describing each system, show the components or parts considered to be Class 2 and 3.
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. '6.6.4 INSPECTION INTERVALS ' . .
The examinations required by IWC-2400 for Class 2 system components and by IWD-2400 for Class 3 system components will be i performed on the basis of a 10-year interval, hereafter known as
- the inspection interval. ,
6 3 6.5 EXAMINATION CATEGORIES AND REQUIREMENTS .
Table 6.6-1 is a listing of the Class 2 components or parts including the Table IWC-2600 item number, the Table IWC-2520 examination category, the required method of examination, and the extent and frequency of examination. Where multiple streams .
exist in one system, the distribution procedure of IWC-2411 will be used to determine the examinations required for each stream.
. Components exempted (as provided by IWC-1220) from the examinations required by IWC-2411 will be tested in accordance with IWC-2412 and IWC-251.0. All Class 3 components will be examined in accordance with the requirements of IWD-2600.
6.6.6 EVALUATION OF EXAMINATION RESULTS Articles IWC-3000, IWC-4000, IWD-3000, and IWD-4000 are still in preparation. The standards for the evaluation of results and repair procedures are in accordance with Article IWA-3000, and
(.) Article IWA-4000. Articles IWC-3000, IWC-4000, IWD-3000, and IWD-4000 will be incorporated into the program to the extent ;
practicable during the first ^^ - inspection per'^d during '
which they become effective. 44ftewel 6.6.7 SYSTEM PRESSURE TESTS
~
The system pressure tests will be performed in accordance with the general requirements of IWA-5000 and the specific requirements of IWC-5000 and IWD-5000 for Class 2 and 3 components, respectively.
l 6.6.8 AUGMENTED INSERVICE INSPECTION TO PROTECT AGAINST J POSTULATED PIPING FAILURES High-energy fluid system piping between containment isolation f _
j valves will receive an augmented ISI to the extent that:
~*
- a. Protective measures, structures, and guard pipes do not
.1 in general prevent the access required to conduct the
! examinations specified in the Code Section XI, Division 1. Exceptions will be identified in the detailed program. .
The examination completed during each inspection O b.
interval will include 100% volumetric examination of all l n .: . -
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t.E IwB-2500 7 IwR-2600 .rA41NATI3n 4ETW30 DF E95P,QNENTS_OR PRRFS BE ERAMINE9 1 MU1stR CJTE30RY .
EX AMI M4 TION _ EXTErr AND _OF_EN MATION A. Reactor vesse M bb bI t Longitudina and circumfere 1 B1 B- V31u .tric At least - 01 of each 1 itedinal we I shell wel in core regions , and 51 . each circum rential weld (mini equivalent og one weld thi -
ness),<at or near thefend of each <
. inspection interval /. When the we has . received an esposure to nest fle* in excess of,)Cl* net (E21 ),
at/ least 501 of tp weld is
, examined. ,
At least 50% o the repaired.dreas
/ are examined when the repaired ',
area has received a neutron, fluz in excess oft 105' nyt, but/in any
/ / case no later than at the/end of the
,, second inspection intervel.
Longitudinal a circumferent B f2 B* V21ame ic 101 of the length of every lon-wel$s in shel (other than t se j gitudinal weld and SE of the leng of Category B and B-C) and /
! of every circumferential weld, meridional a circumf erentid' 'i / / during'each inspection interval seam welds the bottom he&S anS / / For welds in the reactor vessel closure ha (other than those of / examinations may be performed at oc
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near the end of every inspectice inthrval ./ ./
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's Vessel- flange anS S-to- B1.3 B-C V31ametric tdot of each circumferentia'l weld flange ircumferentia welds / / / uring each inspa tion interval Prima nortle-to-v sel welSe B1. 4 i B-D V31usetric 100% of volume shown in,Tigure and ztle inside r tuseS IWB-2500 D, or each nostle. All see Sn / < nozzles in ach inspection interval v el penetrati , incluSi 5 B- E Visual 25% of groep penetrat3ons W
y and instrume ation (Iwk-5 ) of e able size no function netrations during each inspec ion intervat,
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1.@4 13 FSAR
- j Tn ' 5. 2- 10 (Cont' (Pege 2 o 6)
TABLE IND-250 TRBLE IwR-26 ERAMINATION 4ETNDD 3P COMPONENTS _PRRTS.73 BE __INED ITEM NUMBER CATE33RY EX AMI NATION ENT AND FRFUU. _OF EXAMIlm .ON ,
' /
Nousle o-safe end welds B1. B- F Volumetric 100% of all de during each 7
/ and surfa inspection i erval .
T Clos.'e stads in place .7 B- 1 Valemetr c 100% of all stede during the I inspection interval '
closure stads and nu a when Bl.8 3-1 Val ric 100% of p 1 stodo and nuts faring /
v4 moved and a rface each insipection interval t.igaments between readeS B1.9 B-G-1 Val 'etric 1001 all ligaments 'ing stud holes ,
each / Inspection interval' 6 Closure washers a bushings B1.10 / B-G-1 seal 100T of all washers an boshinge ,
i /
during each inspection interval
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.'l ;r Pressure-retain ng bolting les than 2 inches B1.11 3-3-2 / Visual 001 of all bolts, stude, and a to diameter / uring each inspection intervat
, j of l-Integrally we ed vessel Bl.12,' B-B / V31emetric For vessel supporf skirts, 10f
supports / f of the circumferential welds /to
- f , the vessel during each inspection i j / intervat. For,wsoel support lug
' / attachments, 1901 of the weld to the
/ i /
vessel during/ench inspection intervel t / / / /
', closure h ad cladding 1.13 9- A1 -
Not applicable. I.inerief, closers i i heads ar= not clad.
/ j f Vessel adding f/ B1.14 I-1 Vis 1 100% of e6c' h patch ared (6* x 6' areas) ddring each inspection interval /.
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i Yesse interior B1.15 B-N-1 seal Areas $bove and below the reactor I core made accessible by removal of components. First refueling ostage and pubsequent refdeling outages at apptoximately 3-yWar intervals i Interior attachment and core Bl.16 3-N-2 Visual 1 of the vi 11y accessible I support structures integrally -
attachment weldsland surfaces of the CJ1 welded core support ettuctures during each inspection intetval A
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TnBLs 5.2-10 (cant'St (Page i
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4 YnBLE IWB-2500 TLBLE I42600 EtnMInnTIon METW30 or l N OR PSRTs.?:';_gg_!t_gleIngo ITEM winsg L CnTE,oRY EtnMINATION _EITENT AND ptBDITEIOC{_9F_rxAR1mTI99 -
Removab cors suppo ,37 -3 - applicable. r PWRs 17 -
, struct e '
l Con 1 rod del housi Bl.1g B-0 Valemetric 100% of welds i 105 of t peripher CRD hoe. ngs der /
each i tion tervat mempted snent B1.1 B-P Vis All ouposEm are esse ed l
IW 5000 in ecorda with Iun 900 during the syste hydrostati pressere test requi by IWB-5000 ering each
- A. geuk- Vers. / (w,de= b Are* F E We ces* 4***i=9ee = i=terv=1 '
- 8. Pipine Presse_re _ Bound _ art sea n. uv r.s -n) '* * * ' ** "'" h -
- safe end-to-branch piping we1Ss and surface inspection interval i
i Pressure-retaining bolts anS B4. 2 B-G-1 Tsimmetric 100% of bolts, stede, and nets i stude, in place, 2 inches in during each inspection interval l diasieter and greater
- Pressure-retaining bolts and B4.3 3-G-1 Volumetric 100% of bolts, stede, and nets studs, when removed, 2 inches and surface during each inspection interval l in diameter and greater
- l Pressure-retaining bolting, B4.4 B-G-1 Visual 100% of the botting during each l
4 2 inches in diameter and inspection intervai greater l Circumferentist and longitesinal B4. 5 B-J Valemetric 255 of circonferential joints,
{ pipe welds including the adjoining 1-foot 1 sections of longitodinal joint, j during each inspection intervat 1
l Branch connection welds B4.6 B-J Walemetrie 255 of all welds during each I exceeding 6 inches in diameter inspection interval i
i Branch connection welds B4.7 D-J surface 255 of all welds during each 3 6 inches in diameter and smaller inspection interval 9
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TABLE 5.2-10 (Cont'ol (rege f ,
TABLE IWB-2500 TABLE Iwn-2600 EXAMINATI3N METB30 3P M EN?s_OR PARFS TO_9E Et,M M ED { TEM NLMBER _ CATE30RY EX AMINATION __ EXTENT kND FRbw OF EEANIIWtTION Socket welds 34.3 B-J Surface 255 of all welde during each inspection interval Integrally welded espports 34 g B-K-1 Ts1stetrie 255 of all welds during each inspection interval. The weld to the pressure-retaining boundary and the base metal beneath the weld zone and along the support attach-ment me,6er for a distance of two support thicknesses support cosuponents I4.10 B-K-2 Visent All support components during each Inspection interval. support cettir,ge of constant and variable spring type hangers, snobbers, anS shenck adsorbers are verifies.
Exempted components B4.11 9-P Visual All components are' examined in IW4-5000 accordance with IWh-5000 during the system hydrostatic test required by fue-5000
(
, Pressure-retaining bolting, B4.12 B-0-2 Visual 1995 of all botting during each smaller than 2 inches in inspection interval diameter C. Pump Pressure Boundag P Pressure-retaining bolts and B5.1 B 1 vslumetric 1005 of bolts, stede, and nets studs 2 inches in diameter or during each inspection interval I greater, in place ,
Pressure-retaining bolts sna B5. 2 B-3-1 vslumetric 1001 of bolts, stede, and nets stuis, 2 inches in diameter and surface during each inspection interval or greater, when removed Pressure-retaining bolting B5. 3 B-G- f ' visual 1005 of bolting during each 2 inches in diameter or inspection interval greater g H
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- TtBLE 5.2-10 (Cont'dl trage o ,
TABLE IwB-2500 T4BLE litR-2600 Etat:NATI3N METW30 3F Cv,iegr5 OnyRis 70 PE_Et_Mt1ED IFEM NtNBER Q3FE* ORT ER APEIN4 TION _ EITENT AND_ PREQUMCT_OF_ ERAN115tTf0N '
+
Integrally welded supports 95.4 B K-1 Vstesetrie 25% of all integrally welded ,
survorte dering each inspection interval. The weld to the pressete-
' retaining honndary anS the base metal beneath the we15 sone and along the support attactument mester for a distance of two c support thicknesses support components B5.5 B-K-2 Visual All support components during each inspection interval. Support settings of constant and variable spring type hangers, snubbers, and shock absorbers are verified.
Pump casing welds B5.6 B-L-1 Valemetric 1005 of the pressere-retaining welds in at least one pump in each group of pumps performing similar functions in the system, during each inspection intervel Pomp casings B5.7 B-L-2 Visual one pomp in each group of pumpe performing similar functions in the system during each inspection interval (snay be same pump as _
chosen for B-L-1 esaminations)
Eweapted components B5.8 B-P Visual 411 components are esamined in IW4-5000 accordance with Iwn-5000 during l
the system hydrostatic test requi by Iws-5000 I Pressure-retaining bolting B5.9 B-G-2 visual 100% of all botting dering each
- less than 2 inches in dieseter inspection interval I
D. valve Pressurs_ Boundary Pressure-retaining bolts and' B6.1 B-3-1 Volueetric 1005 of all bolts, stede, and studs in place, 2 inches in during each inspection inteeval diameter or greater g
i Pressure-retaining bolts snS studs when removes, 2 inches in B6.2 B-G-1 vslumetric 1005 6f all bolts, stede, and nets M diameter or greater and surface during each inspection interval O CO l
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TABLE 5.2-10 (cont'd) (pagefor l TABLE Iws-2500 i TABLE Iwn-2600 EtMINATION METR 3D OF go!!Po!!E!!TS OR P4RTS TO BE RIBMMED ITEM NUgsen CgTE3ORY ERAMINATION EXTENT AND PREQUENCY OF EIAfEINATICII Pressure-retaining botting, B6.3 B-G-1 Visual 1005 of botting daring each -
2 inches in diameter or greater inspection interval Integrally welded supports 96.4 B K-1 V31asetrie 255 of all integrally welded supports in each inspection interval. The weld to the pressure-retaining boundary and the base metal beneath the weld tone and along the sepport a
attachment mester for a distance '
of two support thicknesses
- Support componente B6.5 B-K-2 Visual All support cosponents during *
! i each inepection interval.
Support settings of constant fi i
x and variable spring type hangers, ,
snobbers, and shock r.bsorbers are @
verified.
,g Valve - body welds 86.6 ' B-M- 1 V31unetric At least one valve in each groep of valves of t5e same constructional .
design, manufacturing method, and manuf acturer that performs a similar function in the system is examined in 1005 of its pressere- ,
', retaining welds, during each inspection interval.
Valve bodies B6.7 B-M-2 Visual one valve in each groep of valves of the same constructional desiga, manufacturing method, and manufacturer that performs sintler femtions in the system is examinei in each inspection interval.
Exempted comp 3nents 96.8 B-P visual All components are examined in (IWA-5000) accordance with IWA-5000 during the system hydrostatic test required by IWB-5000.
Pressure-retaining bolting less B6.9 B-G-2 Visual 1005 of botting during each t than 2 inches in diameter inspection interval
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TABLE 5.2-11 -
I '
INSERVICE TESTING AND INSPECTION OF THE REACTOR PRESSURE VESSEL AND COMPONENTS .
OUT TO AND INCLUDING SAFE END TO PIPE WELDS
- s. 4 ,
ITEM
- PARTS EXAMINATION EXAMINATION EXTENT AND FREQUENCY OF EXAMS.
NO. EXAMINED CATEGORY METHOD lat. Interval Successive Intervals #
Su. .a = 8-A * * '
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Cirosdesung One huishes regime estgs.s SL11 - '
the bs00he regles seldH.s sua LanWedhial ,
But' llend Weeds VehmumMc .
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" "88' d ** *'8d' out Clrandwesed .
M lueg81d am W i
towidlensi
. aN 4 .f 91.22 .
t-
.u. . sus.n.i Vues.u. wr -!' wr -
.*- r, . .
SEAS , 90mm M > R eige Wied + Valenstric W'Id' ' .. Willed' ,
mW sudese .
. P *
- I BLN Reser Wules' Asesti
. eneneedsaymerses -
sut. asasheeegime Vetensete supsir auss -
l .. __
IIBMS: *
(U Matarted these suuts0 meld sugstre stesse *eepair daySe entseds 10% seeminal d Sie escal mall. SeInha seglen esteds for See lengen d Se ~,
oreset Wisistel sNeid, er he Wie absener of a therwiel shield, the effective length of reacter furt elovnents,if Wie location of Wie espair ts met ' I poothety mul accuroesty W Wiesi alie Indevtihaaf shool plate, forging, er sheH course contabibig Wie repelr slull be battuted.
itt sachsdro esernelatly 100% et the weed ionssi. g 09 Se4ect mead locsted at a destyi serwctural d6scentinuity,If may.
4 (48 The beuany ce ected a weeds are to be evenamined during esccessive hussesien bestein. , .
! (d The emarninellen of she#4s flange weeds may he performed shring sie first and Gerd W perteds he centsicNee alue se aseste enamensues of Enam. Cat. 8-D ( Progrant Bl. At least 50% of ster #4e flange weeds shall he en.wsikied by tie med of sie first hupscuen pertog, 3 and sie remainder by Wie end of Wie tiled inspection perled. , -k A
.,' 7 4N-CO Nb C'
. M.
y .
1 *
. -~
i TABLE 5.2-11 INSERVICE TESTING AND INSPECTION OF THE REACTOR PRESSURE VESSEL AND CONPONENTS .
i OUT TO AND INCLUDING SAFE END TO PIPE WELDS i ITEM , PARTS EXAMINATION EXAMINATION EXTENT AND FREQUENCY OF EXAMS.
NO. EXAMINED CATEGORY METHOD lat. Interval Successive Intervals S-D I n=en won '
aus mve,ess wim wa='iata = ==*sd -
auce messes m asas samme . v emmate - = w 'G m .mssise r ,
m suustes' 6
'metu: \
, s
( M Met- M SdS $ mitas e ,W aussisad W e .
e m .. .
M
- e 94.1R vegese meentes 25% Isosites same as terla henrumf
- Be.32 Cesarei pas Optse Itsestas 25 % leas m s Sese as forlet hused l 9423 bueruumiession Wassess Q
I 2
i
\ ben j, ..
s s .. o co
. 1 00 Vc I
j
\ C
\
8 .
\
\
. i
\ .
\ .
\
\
- TABLE 5.2-11 's '
. \ -
INSERVICE TESTING AND INSPECTION OF THE ,
\ ,
REACTOR PRESSURE VESSEL AND COMPONENTS i
OUT TO AND INCLUDING SAFE END TO PIPE WELDS
\ .
ITEM PARTS EXAMINATION EXAMINATION EXTENT AND FREQUENCY OF EXAMS.
NO. EXAMINED CATEGORY METHOD 1st , IntervalI7 Successive Intervale M i ,
- i n, ,ve.d B-F .,
I'" C;5* **
- y a .d. FA. ..e y r,1 : " ; ; }
' aue ween t
j g
,I
- Sitt
, i modnd Ptse she < 4 ti.
n.,, w s.g g ,g Sedece m eeies ?,9 -
m g, @ ,T .:.'
e = wde . ,
- !gg33 mges, g,g W M usedras F,$ , M sth Y pI I '
. _ . - - *o
. Sodut weeds -
. I 4
Fw. vet I,,,
I SSS) , Nom 8'ul Pipe Slee >4 kl. Serface -
M M 'el M useh A4 4 F' 7 . ' - '
cheimnar andas amt wdh .
3131,' Nameuf Pipe Sage <4 In. g ,,gg,me F,I g ' F,7 , , g o , mad === =de . . . _ _ _ _ . . .
~ ..
N0ftS: , ,
't es) Esenensuens are eveulred of each safe end weld in each leap ad connectens trendus of the vescoor cessem syneen, ,
g(t) For the reactor veswl norzie sale ends, the esaminstlens may be performed coincident alte Wie westet nearte seanimettens esgsIred by : ,
1 Esamination Category 8-D. .
$tM includes dissimilar metal odds tutween continstlens of:
tal cartan or leur alloy steek to high alloy steels; ,
(b) carbon er low alloy strek to high nickel alloys; ; g (c) hlWe alloy steth to high picket alleys. I I ~ ,
. H
- CJ1 4
- CI) 9V g-o 1
- y. ,- . -
. . . , 1.*'
1s. .r.;, . . ,
.,.; ;f- -
. n. .;, n . .
, . ,e . ,
~,<:
'i . . ' ' .o .
- q. .
- 7 i 1.['.. .' ; * '
- '(? -
i TABLE 5.2-11 '
.f . -
. ,4.! 6 !
. . 6 , 4 y. . : .*'. . , . .. -
!. i..*
INSERVICE TESTING AND INSPECTION OF TNE *
- * ..i l -
, REACTOR PRESSURE VESSEL AND COMPONENTS
,, OUT TO AND INCLUDING SAFE END TO PIPE WELDS -
i -
.= ,-.
i l** .
ITEM PARTS EXAMINATION EXAMINATION NO. EXTEffT AND FREQUENCY OF EXAMS.
EXAMINED CATEGORY METHOD ..
l.
lat. Interval Successive Intervals -
l 6
.eue*
maarwous Ouese tened see8s !
3.$.1 yM w AA heng, ands,me,but.
but,#* mash Ase.
Seeaty N+MthItt se[ *
- , eue osene semes,h sense . ..--
eue p .g , ou8Intus . '
, osaseseme,esimo W f h aved , aise M e '
- i. ,. .i I
..S u e Ttweeds b Flags w .
..- e..
,3053 _Osmse Wesers, - ^^ _ T- Setsies,47$ -
yg,,g,yy.g .. . , - *i
}.
l I h asfe< Wstel 1 i- '
ro,ferwI 5-r, -2i.
} -
~wa r n _--
i d er.se - - . aa hai. 'a ai. . === a= a >= : -
&o rs, s+ ss % w. me.wm .j .
1
- <g spuk* .
g gl-c a? asm, in.di, .e
.-_m_>',fr I - : s . Er asaamins.
! #3a ,, _ -
veutvt 1 == mcoo
{ 0,//r,5VuJs * ** j g" f.y - houshe uses
- j
. .. eism ease .
e- .
- t. .
I. . , .
i e i .
t.
8 l .. . -
CJ1 i
4 g
1 co <
C ..
x
TABLE 5.2-11 INSERVICE TESTING AND INSPECTION OF Tile - e" REACTOR PRESSURE VESSEL AND COMPONENTS -
OUT TO AND INCLUDING SAFE END TO PIPE WELDS ITEM PARTS EXAMINATION EXAMINATION EXTENT AND FREQUENCY OF EXAMS.
NO. EXAMINED CATEGORY METl!OD lst Interval Successive Intervals 98.10 Reactee Vessel Integrath Welded Attachmeets g Volumetric or surface, as W o
s '
applicable e ~
e
(<o) weswl, as applicable."100% of the welding of exh 8w3 on it* veswl is included in the cuamenation.
n "U
s
~
W D l CJ1 i
o '
CD 00 O
TABLE 5.2-11 INSERVICE TESTING AND INSPECTION OF TIIE REACTOR PRESSURE VESSEL AND COMPONENTS -
l OUT TO AND INCLUDING SAFE END TO PIPE WELDS ITEM PARTS EXAMINATION EXAMINATION EXTENT AND FREQUENCY OP EXAMS.
NO. EXAMINED CATEGORY MET 110D lst Interval Successive Intervals
<' ,e .' @$ g.y.2.
..). a -
.iu. v,
- 4.:p
,*.-.- .m .
R. . , % ,
- r. . ;.p. .
I * '
g3 Reart.r Vent 4 (SWR) * ' I- 'E -
Sene de f.r tot heaveII i,k *I' '"
lat.rter Amactmmes
- j l ~ .
Olue.'. .,.
M. "*I weegs
- 4
,..r.!**,i,-[ 9 .g *
.. .s 8
. .s y
t Y
- wa Q ,
4 x C.O GO O
j TABLE 5.2-11
, INSERVICE TESTING AND INSPECTION OF THE c
, REACTOR PRESSURE VESSEL AND COMPONENTS -
! . OUT TO AND INCLUDING SAFE END TO PIPE WELDS -
, i . .
1 ?
l f.
4 l ITEM PARTS EXAMINATION EXAMINATION EXTENT AND FREQUENCY OF EXAMS. ,
j NO. EXAMINED CATEGORY METHOD lst, Interval Successive Intervals l y)y AeoeW*I $& $oehee /09* !*f $1mone e as 6ir 6 inhomef i .
mus . . co .
as w.f Hosiny .
4 i . . .-
! l
, {
(
e n.' .
l i . . q 1 <
M
. CJ1 g;:n t to CD
, - CD a*
2;
.}
TABLE 5.2-11 l
INSERVICE TESTING AND INSPECTION OF THE - ** - L REACTOR PRESSURE VESSEL AND COMPONENTS .;-
OUT TO AND INCLUDING SAFE END TO PIPE WELDS l,
-[
ITEM PARTS EXAMINATION EXAMINATION EXTENT AND FREQUENCY OF EXAMS. !
NO. EXAMINED CATEGORY METHOD lst Interval Successive Intervals .;
I i
815.10 neoctor Veswa Pressure Retaining soundary 3.p Visual, VT.2 Ed Wing outage Ed refue81ng !
B15.11 Pressure Retaining soundary Visual, VT.2 one test 0,e w pee .
(38) The system leakage test flWB-52211 shall be conducted prior to plant startup folle=6ne each reactor refueling outave.
(s1J The system hydrmtatic flWB-52221 shaft be conducted at or near the end of each impection interval.
O.!
.3
~
M
, s
.. a H Q
. O P L c.o 00 CD
j)
OUESTION 250.2 l
l Plans for preservice examination of the reactor pressure vessel 13 1
welds should address the degree of compliance with Regulatory 14
! Guide 1.150 in accordance with NRC Generic Letter No. 83-15 dated 15
( March 23, 1983. 15 l
RESPONSE ,
37 Limerick will comply with Regulatory Guide 1.150 Rev. 1 in 19 accordance with NRC Generic Letter No. 83-15 dated' March 23, 20 1983. 20 l
I l
1 1
250.2-1 Rev. 21, 06/83 3
^
LGS FSAR 8 OUESTION 250.3 11 1 Sections 5.2.4 and 6.6 of the Limerick Generating Station 13 FSAR and the partial PSI Program (Rev. 5), submitted with a 14 letter dated September 24, 1982, reference ASME Code 15 Section XI, Appendix III of the Winter 1975 Addenda and 16 )
Paragraph IWA-2232 to the Summer 1976 Addenda which has not 17 been referenced in 10CFR50.55a(b). Note that 18
' 10CFR50.55a(b) states that when applying the 1974 ASME 18 j Section XI Code Edition, only the Addenda through Summer 19 1975 may be used.
If Appendix III is used it must be used 20 l in conjunction with Summer 1978 Addenda or later Addenda as 21 i
1 referenced by 10CFR50.55a(b).
Plant specific approval has 22 been granted to use Appendix III of the Winter 1975 Addenda 23 I if the Applicant demonstrates that the provisions used are 23 equivalent or superior to the requirements of referenced 24
- - editions of Section XI Code. 24 l
- 11. In later editions of the ASME. Code, Appendix III of 26 Section XI, is specified for ferritic piping welds. If 28 this requirement is not applicable (for example, for 28 austenitic piping welds), ultrasonic examination is 29 required to be conducted in accordance with the applicable 29 requirements of Article 5 of Section V, as amended by 30 l IWA-2232.
l Discuss the criteria for applying Article 5 of 31 Section V, as amended by IWA-2232. Provide a technical 32 justification for any alternatives used such asSection XI, 32 Appendix III, Supplement 7, for austenitic piping welds and 33 discuss the following: 33 A. All modifications permitted by Supplement 7. 35 B. Methods of ensuring adequate examination sensitivity 37 over the required examination volume. 38 C. Methods of qualifying the procedure for examination 40 through the weld (if complete examination is to be 41 l
considered for examinations conducted with only one 42 side access).
42 III. When using Appendix III of Section XI for preservice or 44 inservice examination of either ferritic or austenitic 45 piping welds the following should be incorporated: 45 A. Any crack-like indication, 20% of DAC or greater, 47 1 discovered during examination of piping welds or 48 adjacent base metal materials should be recorded and 49 '
investigated by a Level II or Level III examiner to 49 the extent necessary to determine the shape, identify, 50 and location of the reflector.
50 i !
l
[
t 250.3-1 Rev. 21, 06/83 3 l
- -- _ _ _ _ _ _ i ]
- The Owner should evaluate and take corrective action 52 for the disposition of any indication investigated and 53 found to be other than geometrical or metallurgical in 54 nature. 54 RESPONSE 56
$>sser"l k -pl,uc r rartare 1 Althoughtthe AC.": Secti:n XI, ?.ppendi; III of the '> inter SS
???: Addend: ;nd P : gr:ph I'c?A 2222 Of th: Currer 1975 59 Add:nd; :::: not specifically referenced by 10CFR50.55a(b), 60 they are equivalent to the comparable portions of the nhefwnf/ 7 61
- approved *; ASME Section XI of Summer 1978 Adden'da as long 61
$}#crgsp.sntpJhsSectionXIA_ppendixIIIindicationsgreaterthan50%DAC 62 are recorded.TA41merick ISI sube:ntr: ter' (MES) 63
'j uith " 63 procedures do ye:r 2sucl, n,AiNfor,:s:, requirement,s.
eee5 II. ASME S : tion XI is ine:ncirtent := to th " T. re ;uirc nts
. 65 for custenitic E i ping u Ids. O_c c t ion XI Pereg regh I'.?A 2 2 3 2 67 r quires ferritic piping to be exei-inud to 6ppendi- III (at 68 50t DAS rc Ording), but : nd t:ry Supplement of 7 68 Appendix IIIg ercrr:nd the use of Appendix III for 69 p e,.,,,g austenitic piping welds with certain mpdifications,J/Isarns8/469 consistent with the PSI /ISI industryfyAppendix III (at 50% 70 DAC recording)x is more appropriate for austenitic piping 71 weld examination than -th; cther interpretatier cf ACMS 72 S : tion XI, which w;uld pply Article 5 of ASME Section V. 72 r
The NRC has previously accepted the&tre positiong for 74 Susquehanna,- Diablo Canyon a_nd other nuclear power plants. 75 Thus for austenitic piping welds: 76 A. upplement 7 modifications are being -eee4.uMce 78 B. Examination sensitivity is assured thru the 80 calibration process. 81 C. Where onesided-access only occur and penetrations 83 cannot be confirmed,%n one-sided-access limitation is 85 iioted in the data package for that weld. ,
85 III. ^
When using Section XI, Appendix III for either ferritic or 87 88 austenitic piping welds, the following applies:lteoe epa A. All indications showing signal amplitudesAin excess of 90 20% of the reference response are evaluated to the 91 extent that the level II or III examiner can determine 92 their true nature. 92 i B. Errult: cf ICI c--i --* i aa -"-lusti:n: er: :: m wed by. 94 j IS! iubtentrecter tc the plant Owner er it: : gent, 95
+
14HefE),
Rev. 21, 06/83 250.3-2 6 )
~
250,'S z-A
( DRAFT s.. a n . e-. a . u-. u a , ,- - . - .. n e laterad 71~ fn, c.4,,,;ahln/a -oxe s-e-ms-AY* Ir *k e$W ?b Yob -l row y
/S a r&vproreffr7
~eLA s,,,,,4 x -fne sed mrs#4 /
p <7n/t zws-22z2 fne .ranna- mt J4dnere x1Slcd 8 ne na, esa6L anhhi c,,-<d;< -d,~ fn rsa 4;& afan, A<& art;,A/-/6 h,je-7%
76., ye did,--7iAsiaLane.
i I
1 1
i :
i
_ h. -
b ms ,s. DRAFT 8
_.. . _ . . _ . . _ . _ . , ... ._. .-.4.m.., 4_ e 4mn,1...n W ;.a the :at, ject
~
214 96 96
,,.....z.-.
+
250.3-3 Rev. 21, 06/83
, __ J
OUESTION 250.4 11 l 1. Clarify the discrepancy between Limerick FSAR Section 3.6.2.6 13 l which states that " guard pipe assemblies are not used in this 14 plant" and Section 6.6.8 Augmented Inservice Inspection to 15 l Protect Against Postulated Piping Failures, paragraph (c) 16 which states " Inspection ports are provided in guard pipes to 17 permit examination of circumferential pipe welds." 17 1
i High energy lines within the " break exclusion" of the 19
- containment penetration area, whether encased in guard pipes 20 l or not, must receive augmented preservice/ inservice 21 examination regardless of the requirements of Section XI of 22 the ASME Code as discussed in SRP 3.6.1 and 3.6.2. However, 23 high energy lines meeting the " modified break exclusion 23 region" criteria need not be subjected to augmented 24 l preservice/ inservice examination. The " modified break 25 l exclusion region" criteria may be applied in those special 26 l cases in which guard pipes are necessary, and it has been 26 demonstrated to the satisfaction of the NRC that access to 27 l perform an examination is extremely difficult to achieve. In 29 l such areas the examination requirements may be eliminated 29 l provided the guard pipe is designed for the full dynamic 30 l
effects of a longitudinal or circumferential break of the 31 enclosed process pipe including jet impingement, pipe whip 31 impact and environmental effects. 32 r If the high energy fluid system piping does not meet the 34
- modified break exclusion region" criteria, submit the 35 required augmented preservice/ inservice examination program 35 for this piping. 35
- 2. Confirm that high energy fluid system piping between 37 containment isolation valves will receive an augmented 38 examination as follows: 38 A. Protective measures, structures, and guard pipes should 40 not prevent the access required to conduct the inservice- 41 examination specified in the ASME Code,Section XI. 42 i
B. For those portions of high energy fluid system piping 44 l between containment isolation valves, the extent of 45 i inservice examination completed during each inspection 46 interval (ASME Code Section XI) should provide 100% 47 volumetric examination of circumferential and 47 l
longitudinal pipe welds within the boundary of these 48 portions of piping. 48 l C. For those portions of high energy fluid system piping 50 l
enclosed in guard pipes, inspection ports should be 51 provided in the guard pipes to permit the required 52 250.4-1 Rev. 21, 06/83 3
LGS FSAR DRA.V ' 8 53 examination of circumferential pipe welds. Inspection 53
' ports should not be located in the portion of the guard 54 pipe passing through the annulus of dual. barrier 54 containment structures.
56 D. For those items requiring ISI, a baseline or preservice 57 examination for establishing the integrity of the 58 original condition is also required by the ASME Code.
60
- 3. Confirm that the augmented examination for high energy system 61 piping is maintained throughout the entire piping system up 62 to the outboard restraint. If the restraint is located at 63 teh isolation valve, a classification change at the valve 63 interface is acceptable.
65
- 4. Confirm that welds between outboard containment isolation 66 valves and piping restraints are included in the PSI and ISI 66 program plan required.
68
RESPONSE
70
- 1. Limerick does not have guard pipes on piping requiring ISI. 71 Section 6.6.8 has been changed to delete references to guard 71 pipes.
73
- 2. A. Protective measures and structures are located, to the 74 greatest extent possible, so as not to prevent access 74 for in-service inspectiegens.
76 B. High energy fluid system piping between containment 77 isolation valves are required to be 100% volumetrically 78 examined (both circumferential and longitudinal welds) 78 during each examination interval.
80 C. L' erick high energy fluid system piping does not use 80 (guard pipe _
82 D. High energy piping requiring examination to ISI receives establish a integrity the baselineof 83 (preservice) 83 the original condition of the welds.
85 3 X.
Augmented examination for high energy piping is maintained 86 out to outboard restrain em2B above).
88 41 Welds between outboard containment included in theisolation PSI planvalves and as required 89 90 piping restraints _and will be included in the ISI grogram plan as required.
uN//be 6
Rev. 21, 06/83 250.4-2
1 11 OUESTION 250.5 FSAR Sections 5.2.4 and 6.6 state that "preservice/ inservice 13 14 inspections will be conducted, to the extent pr4ctical within the limitations of design, geometry, and materials of construction.
~
14 15 Should certain Code Section XI requirements be determined to be 16 impractical in the course of inspecting the components, PECo will 17 submit a request for relief from the requirements to the NRC in 17 accordance with the provisions of 10CFR50.55a(g)(5)."
Indicate the anticipated date for submittal of this information 19 and all requests for relief from impractical examinations. The 21 I
Preservice Inspection Program should include the following 21 21 information:
For ASME Code Class 1 and 2 components, provide a table 23 l A.
similar to IWB-2600 and IWC-2600 confirming that either the - 24 entire Section XI preservice examination was performed on the 25 component or relief is requested with a technical 26 26 justification supporting the request.
B. Where relief is requested for pressure retaining welds in the 28 reactor vessel, identify the specific welds that did not 29 30 receive a 100% preservice ultrasonic examination and estimate the extent of, the examination that was performed. 30 C. Where relief is requested for piping system welds 32 (Examination Category B-J, C-F, and C-G), provide a list of 33 the specific welds that did not receive a completion 33 Section XI preservice examination including drawing or 34 l isometric identification number, system, weld number, and 35 physical configuration; e.g., pipe-to-nozzle weld, etc. 36 Estimate the extent of the preservice examination that was 37 performed. Wnen the volumetric examination was perofrmed 38 from one side of the weld, discuss whether the entire weld 39 39 volume and the heat affected zone (HAZ) and base metal on the 41 far side of the weld were examined. State the primary reason 42 that a specific examination is impractical; e.g., support or 42 component restricts access, fitting prevents adequate 43 ultrasonic coupling on one side, component-to-component weld prevents ultiasonic examination, etc. Indicate any 45 alternative or supplemental examinations performed and 45 46 method (s) of fabrication examination.
l Detailed guidelines for the preparation and content of relief 48 requests are attached as Appendix A to these questions. 49 1
I Rev. 21, 06/83 3 I 250.5-1 l
1
- 8 LGS FSAR RESPONSE 51 The results of the preservice inspection' of th,e RPV will be 53 submitted by June 1984. The piping PSI results will be submitted 54 in April 1984. If,.in the course of conducting the inspections, 55 it is found that ad_ditional relief requests are required, they 56 will be 6dd^d t: t_h^? final reports. The PSI Examination Reports 57 58 will contain the\information in Sections A, B, C, and Appendix A, 58 referred to aboveh.
meIdedk14ese 1
l l
Rev. 21, 06/83 250.5-2 6 l
e- - - - - - - -- _ , . . . - , .
-