ML19254E799
| ML19254E799 | |
| Person / Time | |
|---|---|
| Site: | Three Mile Island  |
| Issue date: | 10/26/1979 |
| From: | METROPOLITAN EDISON CO. |
| To: | |
| Shared Package | |
| ML19254E796 | List: |
| References | |
| PROC-791026, NUDOCS 7911020335 | |
| Download: ML19254E799 (41) | |
Text
{{#Wiki_filter:, = CLASS 1 INSPECTION PLAN INSERVICE INSPECTION OF TMI-1 CLASS 1 COMPONENT PRE 3st'RE BOUNDARY I. Scope and Objectives This attachment describes the Inservice Inspection Progrs= for Class 1 (reactor coolant system) pressure boundary components of TMI-1. II. Identification of Class 1 Boundary The Class i boundary was established in accordance with 10 CFR 50, Paragraph 50.2(v) and footnote 2 to paragraph 50 55a(g)(1). The Class 1 boundary is shown in the attached dravings, Drawing Nos. C-300-00h "nd 5-GN1, C30N015 to 017-GN1, and C-300-019 and 020-GN1. III. Applicable Code Edition and Addenda In accordance with 10 CFR 50, Paragraph 50.55a(b), the applicable ASME Code Edition and Addenda are the 197h Edition with Addenda through Su=mer 1975 IV. Period of Applicability In accordance with 10 CFR 50, Paragraph 50.55a(g)(h)(ii), this progrsm is applicable from January 1978 to May 1981. Unless an extension is permitted per paragraph IWA-2400(a). However, the program is written in ter=s of the ASME Code required ten-year inspection interval, which started September 197h. V. Inspection Program As shovn in Table A-1, inservice inspections will be carried out in accordance with the ASME Code, Section XI, 197h Edition with Addenda through Su=ser 1975, except that alternate inspection techniques vill be used for items 34.1 and 35.h in Table A-1, because the inspection techniques required by the Code are impractical due to plaat design features. In addition, some inspections of reactor vessel nozzles (Item 31.h) vill be deferred to the end of the inspection interval since they cannot be performed until the core barrel is re=oved. Any repairs found to be necessary as a result of inservice inspections vill be performed in accordance with the ASME Code, Section XI, 1974 Edition with Addenda through Sunmer 1975 VI. Excettions Specific exceptions to the ASLE Code, Section XI requirements are identified in Table A-1, together with the basis for each exception ret,uested. (See Itens 31.b Eh.1 and 35.k). [260 243 7911020 3b 4
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TABLE A-1 . CLASS 1 INSER7th 1:ISPECT1015 Page 3 of 8 f b. AMIP4A I 40N
'" II## INSPEC f lON SCHCOt1E AND EXTE NT EXCEPTIONS TO CODE REOulREFEr4TS CATEGW) F'C R ARL AS TO t3L i X ANINCO df8 '# Mi TOK)O T atsi t: t ut t3 -2 W O.E Viu.at 25". of these ( aww(t6aris will t,e inspetted durissa IC . ) lle ater penetrateons.
the ps emee e te .t a tanka ted awar ll.c er=1 of ttw 10-year innwtteon intersal. 112 . 4 U-F Nonte-to-safe-eswi nelds These dissimilar metal w id. are (overed in f tem (dissimilar awtal). 01.1. U-G-1 Pressur e retainirvt teolterw3 Visual, volu- The t.oltiews for the manway asui the three heater D 2 . 'i . H .' . e . tasidies will te in:. pes ted dur6r.g the 10-year e 4 0.' .7 2 6ns.hes and greater in diam- metric , and eter , sus f.sa e 6n . pet tient intes val pitt. urw or t wo c.f these sets nf L,oltiv=3being thet ked about every 3-1/3 year 3.
- In-place misual arul volumett is inspe(tions will be pee for med uni. ss etwa tsuiteng 6s renwaved for other te,asons in which case sus fate inspections will also be per fue med.
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13-H Integrally welded vessel Volums t r ic The eight suptwirts will be in pec ted each IC-year IC.8 in . pet teon entee val, noth at,out 1/ 3 of them beirvj suppor t s. inspes ted each 3 1/3 years. Vessel cladding. Visual A 36 6n. patch will be inspected once daring the 10 tC .9 U-t-2 year inspection interval. Visual these crunpi wnts will t inspe< led for leakage 01.13 D-P E nempted enamonents. due i<w3 the pr essue e test curujur.ted near the end of the ]Q-year inspectson intersal. Visual T his bolting will be viwaally in:. petted at least 112.11 U-G-2 Pressure retaining boltirw; one e dur irup she 10-pec interval. T he inspettions less th.en 2 irw hes on diameter. % well t,e owne isa plan e asiless breaking the conrieg tion is e egast ed for uttwr rcasons. 1/ 3 of these inspet tions will tw demie about evee y 3 8/3 years. G.. . t or ,
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e'.) Lewigitudinal or circumferential Volumetric S.G. - T he onl y melds in this <.ategory are the 43 t.1 (3-13 four tubesheet-to-twed welds. Five percent of welds in primary side shell, each of Ilw se melds mill be inspetted dirir g the a 10-year interval, with one or two welds being inspected each 3-l/3 year s. N
@ L.C. - A r,ortion of the longiludinal seem weld on ech of four primary manifvids is eccessible C at the mJnifold-to-pipt- M, int . IIW at Lessible portions of cat h m.wufuld will be inspetle j daring the 10-year ingwe lion inter val wnh one or tau being N inspec ted eat h 3-1/ 5 years.
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TABLE A-1 (LASS 1 Page 4 of 8 . INSER'llCE liiS?ECT10.15 t % Aust44i nord 8 ILM M PEN INSPtCTION INSPECllOr4 SCHEOtiLE AND EMIENT HEMANKS C A T E Gtwt Y PE H ARE AS TO BE [ X AMINED I at$t E lat$ OrN T Aas t lat).2*o) ti l . .' ts - D Pe im.se y notile-to-he.ad welds Volunwtret S.G. -- Iber e er e sin (e,) seisles in this t elegury. assi ewiele inskje e adeused All sit thesc will be ine.pec ted diria.9 tie 10-year sers a son, hispct tion interval. with Inu (2) tseing isv.gns ted eac h 3-l/.$ year s. L . C. -- i hee e are tw L .C. =cids in this a ategur y D l.1 ts-F Primary eessie-to-safe-eswi S.G. es=1 L .C. -- T here are re me lds in this welds (dassimilar metal), c ate.jur y. is t . 4 til.5 and U-G-1 Pressure retainirwa bultie*J 2 Visual, volu- S.G. -- Ibe teoit e=3 fur the four ni.anways will tae t4 5.e iru hem ar'd over in dianwter. mete ic .umf in . petted da n=3 the 10-year interv.R , with one or sue f ate tau marieays treing inspe t ted e.es h 3-1/3 years. in-plate vi auel arst solurnetr ic ina. pet tions will tie pcs f or me d utiless the imeltienj is a cenvved for other reewns. in wh.th (ase sue f ace in pr(teori mill also be per fue seied. t .C. -- T here is re t,olting in this c.tegory. El ' . " U.H integrally welded vessel Volunwtric S.G. - Ten percent of the length of ihis weld on st44ee ts. each steam generator will be ina petted during the 10-year inspection interval with cee weld being inspected durir*J each of the first two 3-l/3 -pear per iods . L.C. -- There are rm supports in thes category. O l.ti 15-5-2 Vessel cladfing. Visual S.G. -- A 36 in.2 4tch will be seispected in each steam generator during the 10. year interval. t .C. -- l here is no (i.edduwj in the t .C. 11 5. 9 B-P E nempted c omponents. Visuet t hese s.ong,uncrees will t,e inspet ned for leak.ge during the pe essur e test a vidated near the essi of ste IO-year enspec e6cn inter vet. t13.10 U-G-2 Pressure retaining botting less Visual S.G. -- All of this tx>lting will be visually inspetted than 2 lewhes in diameter. dit ing the 10-ye c inspec ti.wi inter vel. T he in-ge< tions mill be demie in pl.ac e unless la eahiews the coewies Linn es s c< paired fur other reasons. 1/3of steme theths will te one .itsuut every 3-l/3 years.
.- e L .C. -- Itwre is no bohiew; in this c ategrery.
N Lis=.t CB CD S4fe-end wcfds (dissimilar Vohienetric 28" pipe -- lhe esaiht beenetalik welds at the HC U 4.1 0 -F enetal). aeul surf 4(e guirnps will tse iet pc< ted ire the IO-year irispec t.on iniers.t . wish .t> oui I/3 of these t>cing inspetted N eac h 3-1/3-year per lud. N s
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TABLE A-1 Cl. ASS 1 ' INSER'litt INSPECT 101S Page 6 of 8 [ MAutr4411(te FE" IN ITCTION INSPEC I10t4 SOtEDtF E AND Ex1ENT E XCEPT IOt45 TO CODE HEQUIRE'eLN15
' I f ' '4 C Air GJHY PER ARE AS TO BL L N AMINED utTHOD i et t' l a B W f A ba t' 1 AB-25aC U4.11 OP 0 meneted cong>,nents. Visu.st lhese (ueepoewns s mill be inspec ted for leakage de ie na tiw pr. . sue e test cosalua ted ricar the end of the 10-year inspe( teon inter sal.
Oa.12 D-G-2 Pressue e retaining bullirs leos Ttese juent* an e cosered in the pe essurlier ar.d valve set tions e,f this opnifecation. than 2 irw ties todiarewtc r . Q.e. t. e t%14nt t .r. V6 ual, volu- Ine hcaliery for the lour RC pumps will t>e inspetted D5.1. 85.2 D-G-l Pressure retaining taolting dureng the 10-yi:ae inspection inserval. with one or
,4 05.3 2 inches and over in dienieter. metric and surf ac e twe pumps beiswa inspetled ea(h 3-1/3 years. In-plac e visual and volumetric inspe(t ons will be per-forn ed unless the tioltiema is remosed for eller reasons, en which case sus f ace irspection will also t,e performed.
One pump will be inspected each 10-year interval. Lug welds on the pump casings cannot be meaningfully B5.4 B-K-1 Integeally welded st4 ports. Surface R.T. or U.T. Inspe ted because of their geome try aN since the casings are cast austenitic stainless steel. Therefore. LP will t>e used. S(pport components. Visual All the sagspori toreponents mill be visually in-H 5. 5 D-K -2 spe(ted durary the IO-year inspettion inter val. Pune casing seam welds. Thee e are no casiry team welds on Class 1 pumps. 16.e U-L ~1 f3 -L - 2 Internal ina.pection of pun, Visual This inspection will tse done to the entee t prac-tn.7 Ricabic for one purep casirw3 (asiruJs. B -P E sempied congx2nents. Visual Thest congxinents will t>e inspected for leakage 65.8 during the pressure test (oswiucted near tie end of the 10-year inspection inter val. Pressure retaining teolting Visual this tsuiterwa mill tie visu, illy inspet ted at least once O'. . a U-G-2 less than 2 in(bes in diameter, dur iey the IO-year leiserval. The inspections will t,e dme in pl.ece unless tarcakiry the e orwm tiorr is required for other reasons. 1/3 of tha se inspections
- nill be dune about every 3-1/3 years.
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TIIREE MII2 ISLAND - UNIT NO.1 INSERVICE INSPECTION PROGRAM - CLASS 1 COMPONENT PRESSURE BOUNDARIES TABI2 A-1 Page 8 of 8 AREAS TO INSPECTION SCIIEDULE BE EXAMINED INSPECTION METIIOD AND EXTENT REMARKS All Class 1 Systems System Leakttge and Cystem leakage test prior as in dirited on ISI IIydrostatic Pressure to startup following each Drawings C300-001 Test per Ih'A 5000 and refueling outage and a through C300-005 and IWB 5000 system hydrostatic C300-008 through pressure test at/or near C300-023 the end of the inspection interval Ch CD N LM a w
INSERVICE I::SPECTICN OF TMI-l CLASS 2 CCMPCEiT PRESSURE ECUNDIRIES I. Score and Objectives This attach =ent describes the Inservice Inspection Program for Class 2 pressure boundary components of TMI-1. The objective of the inservice inspection program is to provide assurance of the continuing integrity of the Class 2 system while at the same time minimizing radiation exposure to personnel and plant down time in the performance of the inspections. II. Identification of Class 2 Boundaries The Class 2 boundaries were established in accordance with the NRC Standard Review Plan Section 3.2.2 (ll-2h-75), ANSI N18.2A (1975) and Regulatory Guide 1.26 Revision 3, Quality Group B. The Class 2 systems and boundaries are shown in ISI Drawings C300-001 through C300-005 and C300-008 through C300-023 III. Apelicable Code Edition and Addenda In accordance vith 10 CFR 50 Paragraph 50 55a(b), the applicable Code Edition and Addenda are the 197h Edition with Addenda through Sunmer 1975 IY. Period of Atelicability In accordance with 10 CFR 50, Paragraph 50 55a(g)(h)(ii), this program is applicable from January 1978 to May 1981, unless an extension is pernitted per paragraph IWA-2k00(a). However,the program is written in terms of the Code required ten year inspection interval which started in September 197h. In addition, the inspection program is based upon a forty year service lifetime of the unit which ends in September, 201h. V. Inspection Procram Inservice Inspections vill te carried out in accordsace with ASME Section XI, 197h Edition with Addenda through Sunmer 1975 and specific i- actions for this applicability vill be perfor=ed as shown on Table 3-14 ached. Any repairs found to be necessary as a result of inservice inspections vill be performed in accordance with Section XI,197h Edition with Addenda through Su==er 1975. VI. Excettions Specific exceptions to the ASME Section XI requirements are identified in the attached Table 3-2 along with the basis for each exception requested. 1260 252
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THREE MILE ISLAND - UNIT NO-.1 j INSERVICE INSPECTICN PROGRAM - CLASS 2 COMPONENT PRESSURE BOUNDARIES -
. i.
TABLE B-1 Page 1 of 7 ' I e I i EL_U4INATION l ITEM NO. PER CA TGORY AREAS TO BE EXAMINED INSPECTION INSPECTION SCHEEULE AND TABLE IWC 2600 T.G2 IWC 2520 METHOD EXTENT REMARKS i C1.1 C-A Pressure vessels Volumetric 8 welds will be inspect-circumferential butt welds ed during the service life of the unit: Decay lleat System - 2 welds Steam Generator - 6 welds ! C1.2 C-B Pressure vessel Volumetric 14 welds will be inspect-Nozzle-to-vessel welds ed during the service life of the unit: ~ Decay Heat System - 2 welds Steam Generator - 2 welds Integrally welded C1. 3 C-C Pressure vessel - N/A steam generator Integrally - Welded Supporte supIorts are covered by Class 1 inspection program. N There are no other Ch integrally velded CD supports in Class 2 systems N LJi U
. . _ . _ _ _ _ _ __ - - _ _ _ _ , _- _ _ _ _ _ . - . . . _ _ .__ . _ _ ..._.._.mm. - -
I - THREE MILE ISLAND - UNIT NO. 1 I:;. ERVICE INSPECTION PROGRAM - CLASS 2 COMPONENT PRESSURE BOUNDARIES - TABLE B-1 Page 2 of 7 ICAMINATION ITEM NO. PER 0.CEGORY AREAS TO BE EXAMINED INSPECTION INSPECTION SCHEDULE AND TABLE IWC 2600 2A3LE Ii4C 2520 :!ETHOD EXTENT REMARKS i 8 Cl.h C-D Pressure vessel Visual & The pressure retaining ' Pressure-Retaining Bolting either sur- bottling of 3 flanges face or will be inspected during See Table B-2 Volumetric the 10-year interval: Main Steam System - 2 flanges Decay Heat System - 1 flange , C2.1 C-P, C-G Piping Volumetric 17h welds will be Circumferential butt velds inspected during the service life of the unit Main Steam Systems - 28 welds Decay Heat System - 113 welds Feedwater System - 18 welds Reactor Eldg. Emerg. Clg 2 welds r Ilydrogen Purge System - 5 welds Intermediate Cooling N System - h velds . Cs Steam Generator - 4 CD welds. - N . LD b . i
s
) -
TliREE MILE ISLAND - IJlIT NO. 1 j IIISERVICE IllSPECTION PROGRAM - CLASS 2 COMPCNENT PRESSURE B003 .1 RIES TABLE B-1 Page 3 o r "( l t D_A'IIN ATION ITEM !!0. FER CA TGORY AREAS TO BE EXAMIllED IIISPECTION IllSPECTI:I SCllEDULE AND TABLE IWC 2600 TA3LE IWC 2520 :'ET110D .XTENT EEMARKS C2.2 C-F, C-G Longitudinal weld Volumetric 91 welds will be
.jeints in fittings insI>ected during the service life of the unit Main Steam System - S welds 11ecay lleat System - 66 welds C2.3 C-F, C-G Branch welds in piping Volumetric 6 welds will be inspect-ed during the service li fe of the unit.
Main Steam System 14 Ik cay lleat System - 2 C' . h . C-D Piping pressure retaining Visual & The pressure retaining bolting either sur- bolt Ing or 810 flange:, face or vi11 he inspected Volumetric ' luring the 10-year i n t,e rval : Plain Steam System - h rIanges N 1)ecay llent System - h m flanges C Air llandling -P Syst.em flanges N Ln LD
_ . . . . _ - . . . . . . . . . . ~ . . . _. . . . . . . w e.. .- s m . e ._ . .: _ .- . . . .u T11REE MILE ISLAND - UNIT fl0. 1 i ~ IIISE9VICE INSPECTIOri PROGRAM - CIs' dis 2 col &ONENT PRESSURE BOUNDARIES TABLE B-1 PnfM h "I' 7 I I i 17_*241 NATION ITE!f NO. PER CA_ EGORY AREAS TO BE EXAMIllED INSPECTION INSPECTI0ti SCIIEDULE AND l TABLE :NC 2600 T.0 LE T4C 2520 ItETIIOD EXTENT RE!! ARKS C2.5 C-E-1 Piping integrally welded Sur t' ace 86 integrally velded supports. (Included in this pipe supports will be category are the welds ""'"" " " inspected during the attaching the process pip "' IO-year interval. to the Reactor Building Con-tainment Wall Penetrations Assembly outside ol' cont. tin-ment.) ' ca.6 C-E-2 Piping support components Visual '/3 pipe hangers will be inapected during each inspection interval g (10 years). Main Sterun System - 32 l'ecay llent System - 33 Feedwater System - 16 Slezun Generator - 8 , Ilydrogen Purge - 2 Syctem In t.ermediate - 2 N t'ooting ON CD N
- Ln ON
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INSERVICE INSPECTION PROGRAM - CLASS 2 COMPONENT PRESSURE BOUNDARIES TABLE B-1 Page 5 of 7
. j r EO24INATION ITEM NO. PER CA_IGORY AREAS TO BE EXAMINED INSPECTION INSPECTION SCHEDULE AND TABLE IWC 2600 l'A33 IWC 2520 :2THOD EXTENT REMARKS l
l C3 1 C-G Pump casing velds - - There are no welded pump casings in Class 2. systems C3.2 C-D Pump pressure retaining Volumetric The pressure retaining bolting bolting of 1 decay heat system flange will be inspected during the 10-year inspection interval. C3. 3 C-E-1 Pump integrally welded - - There are no inte-supports grally welded supports on Class 2 pumps C3. 4 C-E-2 Pump support components Visual The pump support com-ponent of 1 decay heat system pump will be inspected during the ' g 10-year inspection g interval. , CD N W s N
_ _ _ _ . _ _ m., m - m._~~ m ... _.mm_ ._m ...m., ... a . % . . _-- . gm I k . l, THREE MILE ISLAND - U'iIT NO.1 l INSERVICE INSPECTION PROGRM4 - CLASS 2 COMPONENT PRESSURE BOUNDARIES TABLE B-1 Page 6 of 7 EU.MINATION ITEM NO. PER C/C TCORY AREAS TO BE EXN4INED INSPECTION INSPECTION SCHEDULE MID TABLE IWC 2600 TA3LE IWC 2520 :.2THOD EXTENT REMARKS Ch.1 C-G Valve body welds Volumetric Four welds in AH-VlA or AH-VID.will be inspect-ed during the service life of the unit. Ch.2 C-D Valve pressure retaining Volumetric The pressure retaining bolting bolting of 3 valves will be inspected during the 10-year inspection interval. Main Steam System .1 ' Decay Heat System - 2 Ch.3 C-E-1 Valve integrally welded - - There are no inte-supports grally welded sup-ports in Class 2 systems. , Ch.h C-E-2 Valve support components - - There are no valve support components N in Class 2 systems. Ch CD N en - CO
THREE MILE ISLAND - UNIT NO. 1 INSERVICE INSPECTION PROGBAM - CLASS 2 COMPONENT PRESSURE BOUNDARIES TABLE B-1 Page 7 of 7 Areas to be Inspection Schedule Examined Inspection Method and Extent Remarks ' All Class 2 systems Hydrostatic pressure test 100% inspection every See fxceptions as indicated on ISI (Visual) per IWA 5000, 10 year inspection (Table B-2). Drawings C300-001 IWC 5000 and IWC 2412 interval. through C300-005 and at 1.25 times decign C-30 -008 through pressure. C300-023. ON CD r\) Ln W
THREE MILE ISLAND - UNIT NO. 1 INSERVICE INSPECTION PROGRAM - CLASS 2 EXCEPTIONS TABLE B-2 Page 1 of 5 ASME III l TESTING PE3 FORMED IN COMPONENT CODE CLASS ASME XI EXCEPTION REQUESTED JUSTIFICATION LIEU OF CODE REQUIREMENT Penetration Pres- NON-NUCLEAR IWC 2412 and IWC 2500 This system is an This system is leak tested surization System air system for con- quarterly during normal opera-See ISI Dwg. tainment integrity. tion utilizing permanently 300-015 The introduction of installed flow instrumentation. water into it for pressure testing will be narmful to it and associated components and will impair and degrade its sub-sequent operation. OTSG reedwater NON-NUCLEAR Table IWC-2600, Iter C2.5 Clearance between Welds will be visually header support and Table IWC-2520, Catagory shell and FW inspected for soundness when attachment velds C-E-1. header does not support is examined, permit preparation of weld for surface examination. C) ' O N O
THREE MILE ISLAND - UNIT NO. 1 INSERVICE INSPECTION PROGRAM - CLASS 2 EXCEPTIONS TABLE B-2 Page 2 of 5 ASME III TESTING PERFORMED IN COMPONENT CODE CLASS ASME XI EXCEPTION REQUESTED JUSTIFICATION LIEU OF CODE REQUIREMENT Waste Gas Disposal N-3 These are systems These systems vill he System from WDG-V4 which contain gas. pneumatically preenure to Penet. #330 The introduction tested to Reactor See ISI Dwg. 300-023 of water into containment calculated them for pressure accident pressure testing vill be during Local Leak Nitrogen Supply Non- IWC 2hl2 and IWC 2500 harmful to them Rate Testing and leak System from NI-V26 Nuclear and ass lated checked (i.e. soap to Penet. #307 "P " " * "" " 1 * ** db See ISI Dwg. 300-023 will impair and degrade their Hydrogen Purge Non- subsequent System from HP-V1 Nuclear operation. to Penet. #240 See ISI Dwg. 300-023 Service Air System Non-from SA-V2 to Penet. Nuclear
- 109 See ISI Dwg. 300-023 __.
N Containment Monitoring Non- o System from CM-V1 to huclear Penet. #108 and CM-V4 rs) to Penet. #108 @
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See ISI Dwg. 300-023
Y!ll(1:E Mll.i: 1:sIAllD - (Hl LT I!O.1 I!!SEf(VICE IllSPIr]'IGH PIOCRA!4 - CI ASS 2 EXCEPCIOIIS
'I A!il,E R-2 Page 3 of 5 ASt4C III TESTitiG PEl&Cli!4ED Ill C0f fPON1lT Col'E CIASS AS!4t: XI 1:XCEPTLOli REQUESTED JUSTIFICATIO!! LIEU CP CCDE El'QUIRI.MCIIT 1h inen leeny IIcat Tatle 1UC 2601, Item 2.1 and Table This piping is en-pipiUC fruu Dil-V6 ,VC 2520 Catecon C-F caued in concrete I, and b to HeacLor Il-2 turder the Heuct.or bailding Sump. See Building floor and In f Drawing 300-005 therefore cannot be innpected volwae-trically. The butt Hone vejdu on DR-V6A and g
g ti cannot be inspec-ted since thece o valves are located N in a velded valve l
@ containee and are N not accessible.
10 inch Decay IIcat Table IWC 2600, Item 2.1 and Table This cection of Pressure test per IWC-5000 piping elbov immedia
- IWC 2520, Category C-F decay heat. Pi pe is taly upstream of DII- contained within a
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', ld and two longi -
and in not accen-t'tlinal ve]ds on sible for inspec-oach elbow tion. 02e ISI Dug. 300-005 - - >-- - - - - - - - - - - - - - --- - s -
TIIREE MILE ISLAND - UNIT NO.1 . INSERVICE INSPECTION PROGRAM - CLASS 2 EXCEPTIONS TABLE B-2 Page 14 of 5 ASME III TESTING PERFORMED IN COMPONENT CODE CLASS ASME XI EXCEPTION REQUESTED JUSTIFICATION LIEU OF CODE REQUIREMENT 6 inch "Y" N-2 Table IWC 2600, Item 2.1 and These strainers are Pressure test per IWf-5000 pattern strainer Table IWC 2520, Category C-F located in 14 inch upatream of piping exempted by DII-VTA and B in IWC 1220 (d) Makeup Pump suction line. See ISI INg. 300-005 M Os CD N Os u
THREE MILE ISLAND - UNIT NO. 1. INSERVICE INSPECTION PROGRAM - CLASS 2 EXCEPTIONS TABLE B-2 Page 5 of 5 ASME III TESTING PERFORMED IN LIEU COMPONENT CODE CLASS ASME XI EXCEPTION REQUESTED JUSTIFICATION OF CODE REQUIRBIENT Makeup System N-2 IWC 2112 and IWC 2500 4 In order to hydro The se.ctions of piping piping frcat the piping between between the pumps and pump to first the MU pumps and discharge valves vill downstream stop the first down- be examined for leakage valves stream valves it with the suction side would be necessary piping and pump hydros. to install a blank In addition, the subject in the pump dis- piping vill be examined charge flanges and for lea'; age during the remove the discharge first ISI pump test check valve internals. subsequent to the hydro. To install a blank would require springing back relatively short lengths of thick wall pipe and/or disturbing pump alignrent. Ch CD N cts 4
TAllLE B-3 Cl!ANGES TO TABLE B-1 0F Tile ORIGIflAl, SilBMITTAL (INilEliVICE Ill ll'Irl' ION pHOGilAM - CLAS3 2 CoffPONFNT PRESSURE BOUflDARIES - tifilT 1) lu rl'E: CilAllGl?i AHL UNDEHLIllED p , 3 g ,. 7 ITEM NO. CIIANGE JUSTIFICATION C1.2 Under Inspection Schedule and Extent There are only tvo pressure-retaining nozzles in each column: I welds will be inspected steam generator that are over 1 6 inches in dimneter. P.e r during the service life of the unit: ASME Section XI, IWC-1220 (d) only components connections Decay lleat System - 2 welds greater than is inches are to be examined and per IWC-2):11 Steam Generator - 2_ welds (Multiple St; eam Analysis) only two ateam generat or nozzh welds are to be examined during the service life of the unit. C l . la Under Inspection Schedule and Extent The original submittal had inadvertently included C61umn: The pressure retaining several bolted piping connections. 'lliis Item Ilo. should bolting of J flanges will be inspected include the pressure retaining bolting of pressure during 10-year inspection interval: vessels only. Main Steam System: 2 flanges Decay lleat System: I flange ON CD N Os LJ1
TAbl.E IL3 CIIANGES TO TABLE B-10F Tile ORIGIllAL SUBt4I'!"fAL (INSFl(VICE IllSPEL"fION PROGilAll - ~ CLASS 2 C0f4P0llENT PRESSURE BOUNDARIES - Il!!IT 1) NOTE: CliANGES Al(E IINDElt!.INEli Page 2 of Y IT'e21 NO. CilANGE .lUSTIFICATION C2.1 Under Inspection Schedule and Extent The original submittal had mistakenly included four Air column: llandling System valve bady welds in this item. 'ihere four Air llandling System valve body welds have been Q Welds will be inspected during the transferred to Item fio. Cls . l . In addit. ion, an arithmetic service life of the unit: error was made in the original submittal. blain Steam Systems - 28 welds IMcay Heat System - 113 welds Feddwater System - 18 welds Reactor Bldg. Emerg. C1g. - 2 welds flydrogen Purge System - S welds Intermediate Cooling System la welds Steam Generator la welds C2.2 Change total number of welda from 178 to A tabulation error was made when the original submi t tal 9J. Also change number of decay h.at was drafted. system welds from 171 to 86. Os CD N Ch CN
TADI.E D-3 CilANGES TO TABIE B-1 0F Tile ORIGINAL SUBMITTAL (INSEliVICE IllSPECTION P110GilAM - . CLASS 2 COMPONENT I aiutiltE BOUNDAltIES - lifilT 1) N(frE: CllANGES ARE !'NDElli,INEli Page 3 o f 7 IT141 NO. CIIANGE JUSTIFICATION C2.3 (a) Under inspection schedule and ex- (a) See Table B Class 2 exceptions. tent change total number of welds from 15 +.o 5 and main steam system (b) The original submittal erroneously specified that, a welds from 11 to 3. given number of areas would be examined during the service life of the unit. ASIlE Section XI, however, specifies (b) Alco, change the words " Service those areas t.o be examined during the 10-year 'insteet, ion life of the unit" to "10-year interval and that, change is therefore made. Inspection int.erval". C2. la Chrz.ge the words " Service life of the The original submittal erroneously specified that a unit" to "10-year inspection given number of areas would be examined during the service i n te rval" . life of the unit. ASME Section XI, however, speci rien those areas to be examined during the 10-year inspection interval and that change is therefore made. Os _ _ _ _ . _, CD Os N
TABLE B-3 CHANGES TO TABLE B-10F TIIE ORIGINAL SilBMITTAL (INSEltVICE INSPECTION P110 GRAM - - CLASS 2 COMPONENT PRESOUltE BOUNDARIES - UNIT 1 NOTEt Cl!ANGES AltE UNDElli,1NEls Page 's of 7 1
] TIN NO. CitANGE JUSTIFICATION C2, S Change inspection schedule and extent i 67 welds attachir 3 the penetration to process pipe (Inside c'olumn to read: containment) are added to the program.
81L integrally welded pipe supports will be inspected during t.he 10-year inspec- 8 welds on the steam gencrator feedwater header are delet-
- t. i on interval. e See Table B-2 for request for relief.
Main Steam System - 3 welds Decay llent System - 8 welds 'lhe original submittal erroneously specified that a Feedwater System -- 1 welds given number of areas would be examined during the service Intermediate Closed life of the unit. ASME Sect,lon XI, however, speci fies Cooling System - 1 weld those areas to be examined during the 10-year inspect. ion Penetration welds - Q welds interval and that change is therefore trade. C2.6 Change the words " Service life of the 'lhe original submittal erroneously specified that a unit" to'10-year inspection interval". given number of areas would be examined during the service life of the unit. ASME Section XI, however, speel fies those areas to be exulned during the 10-year inspection interval and that chanfe in therefore made. e CD rN) CB CD
TABLE B-3 - CilANGES TO TA141.E B-1 OF Tile ORIGINAL SU13MITTAL (INSEHVICE INSPECTION PROGRAM - CLASS 2 COMPONENT PRESSURE BOUNDARIF11 - UNIT 1) - NOTE: CilANGES AftE UNDElthTHEli Page 5 of '( ITFN NO. CllANG E EuSTIFICATION C3 2 Change the words " Service life of the The original submitt il erroneously specified that a unit" to "10-year inspection interval". given number of areas would be examined durin6 the service life of the unit. ASME Section XI, however, speci fles those areas to be examir.ed during the 10-year inspection interval and that change is therefore made. l C 3.14 Change tije words " Service life of the The original submittal erroneously specified that a uni t'!' to 10-year inspection interval". g*ven number of areas would be examined during the service i li fe of the unit. ASME Section XI, however, speci rles those areas to be examined during the 10-year inspection interval and that change is therefore made. I l. S k N W CD N l w W
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TAllLE 11-3 CllANGES TO TABLB B-1 OF TIIE ORIGIHAL SUBf4ITTAL (IllSEHVICE INSP 7?fl0N PROGRAff - CLASS 2 CO!4 PONE,fff PRESSilRE llnUNDAHIFil - UIIIT 1) NOTE: Cl!ANGIII AltE IINDElthillED Page 6 or '( ITF24 NO. CIIANGE .!USTIFICATION Cla .1 Under Inspection idet. hod coltunn: Statement of inspection method per Table IWC-2600. Volumet rie e .1 Cls. I Under Inspect,lon Schedule and Extent, These are the four Air IIandling valve body welgia tivit, were column: mistakenly included in Item No. C2.1.
, Four welds in All-VI A or AH-VID will be inspected during the 10-year inspection int,erval.
Q N wa O
TABI.E B-3 CilANGES TO TABLE H-1 OF Ti!E OltIGINAL SULMI' ITAL (INSERVICE INSPECTION pit 0GilAM - . Cl. ASS 2 CollP0HENT PRESSlfftE B0lHIDAftIES - UNIT 1) NOTE: CHANGidi AltE IJHDFHLINEl' Page 7 of 7 ITill NO. CilANG E JUSTIFICATION "I Change the words " Service 1i fe of t.he
" " " P E * """ *# "#""" "" * **"" "" " "E """"#"
unit " to "10-year inain etion interval"* life of the unit. ASME Section XI, however, specifies those areas to be examined during the 10-year inspection interval and th..t change is therefore made. Ch.? The pressure ret.nining lolting of 3 The original submittal erroneously specified that a valves will be inapected during the given number of areas would be examined during the service 10-year inspection interval. l i re of the unit. ASME Section XI, however, speci fies those areas to be examined during the 10-year inspection Main Steam System - 1
. interval and that change is therefore made.
Decay ! eat System - 2 Os CD N N
INSERVICE INSPECTICH CF TMI-1 CLASS 3 CCMPONE'iT PRESSURE BOUNDARY I. Scope and Obiectives This attachment describes the Inservice Inspection Program for Class 3 pressure boundary co=ponents of TMI-1. The objective of the inservice inspection program is to provide assurance of the continuing integrity of the Class 3 system while at the same time mini =ising radiation exposure to personnel and plant downtime in the performance of the inspections. II. Identification of Class 3 Boundaries The Class 3 boundaries were established in accordance with the NRC Standard Reviev Plan Section 3.2.2 (11-2h-75), ANSI N18.2A (1975) and Regulatory Guide 1.26 Revision 3 Cuality Group C. The Class 3 systems and boundaries are shown in ISI Drawin6s C300-001 through C300-005 and C300-008 through C300-023 III. Atelicable Code Edition and Addenda In accordance with 10 CFR 50 Paragraph 50 55a(b), the applicable Code Edition and Addenda are the 197h Edition with Addenda through Sun =er 1975 IV. Period of Atelicability In accordance with 10 CFR 50, Paragraph. 50.55a(gl(bl(lil this progrea is applicable from January 1978 to May 1981, unless an extension is permitted per Paragraph IWA 2h00(al. However, the program is written in ter=s of the Code required ten year inspection interval which. started Septe ber 1974. V. Instection Proeram Inservice inspections vill be carried out in accordance with.Section XI, 1974 Edition with Addenda through Ss-r 1975, and the specific inspections vill be performed in accordar.:e with Tab 2e C-1 attached. Any repairs found to be necessary as a result of inservice inspections vill be performed in accordance with. Section XI,197h Edition with. Addenda through Su==er 1975. VI. Excettions Specific exceptions to the ASME Section XI requirements are identified in the attached Table C-2 along with the basis for each. exception requested. 1260 272
I i I A. i Ill!1ER f tTI# ISIJtND - II!!1T 110. 1 CD i inn:kVICI' IIIfiPECTTOli Pp.0CP/hl - CIX;0 3 C0!!!'0!11 GIT PRFTGlillF IGl!IIDApTIT. c page 1 of 1 N
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TABLE C --I Areas To be Innpection Dehedule Inspection Method And Extent fremarks Examined Vinual per IWA 5000, 1001, inrpection every Testing of buried piping per All Clans 3 systems IWD 5000 (except buried 10 year inspect. ion IWD 2600 (b) will not be per-as indicated on piping) and IUD 2600 Interval formed. See exception request ISI DWFu. C300-001 at 1.1 times design Table A-2 thru C300-005 and C300-008 thru C300- pressure 023 Visual per IWA 5240 1 100"., innpection Testing of buried piping per All Class 3 systems as indicated on ISI and DTD 2600 (except every Ino month IWD 2600 (b) will not be per-buried piping) while inspectior, interval formed. See exception requent thrgs. C300-001 thru C300-005 and C-300- at normal operating Table A-2 008 thru C300-023 pressure
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THREE MILE ISLAND - UNIT NO. 1 INSERVICE INSPECTION PROGRAM - CLASS 3 EXCEPTIONS TABLE C-2 Page 1 of 1 ASME III ASME XI EXCEPTION TESTING PERF0Pd4ED COMPONENT CODE CLASS REQUESTED JUSTIFICATION IN LIFll OF CODE REQUIREMENT Nuclear Service River Non-Nuclear IWS 21400(b) These sections of piping are under- None Water-underground ground and therefore cannot be piping between valves visually inspected. They also can-NR-V3 and NR-VlB and 4 not be isolated with tight closing , NR-V5 shown on valves as required by IWD 2600(b). N Drawing C300-002 Therefore, during a pressure test, CNJ leakage through installed valves would invalidate the results of C"3 Decay Heat River Water Non-Nuclear underground - piping ~ between valves These systems are low pressure /high DR-VlA(B), DR-V2A(B) & v lume systems (i.e.: Nuclear Service River Water System - 20 to DR-V1 & A(B) shown on I40 psig, Decay Heat River Water Drawing C300-002. System 20-30 psig and Reactor Building Emergency Cooling Reactor Building Non-Nuclear System 60 psig). This piping was not designed to be inspected or Emergency Cooling - tested in this manner and therefore underground piping this testing is not required by between valves 10 CFR 50 50.55a(g)(I). 4 RR-V1A (B) and RR-V3A (B) (C) and In addition, the Decay Heat River NS-V8 and NS-V85 Water Syster and the Reactor and EF-Vl4 shown on Building Emergency Cooling System Drawings C300-002 are each a 100% redundant system and C300-010 and loss of one underground line would only result in loss of system redundancy. In emergency situations the Nuclear Services Closed Cooling System can be cross connected with the secondary.
INSERVICE INSPECTICN CF DtI-l PUIGS PROVIDED WITH EfEF0ENCY POWER SCLPCES I. Score and Objectives The attachment describes the Inservice Inspection Program for all Class 1, 2, and 3 pu=ps which are provided with an emergency power source. The objective of this program is to provide assurance of the operational readiness of these pu=ps during their service life. II. Identification of Class Boundaries Class 1, 2, and 3 boundaries were established in accordance with the NRC Standard Review Plan Section 3.2.2 (ll-2h-75), ANEI N18.2A (1975), and Regulatory Guide 1.26 Revision 3 III. Attlicable Code Edition and Addenda In accordance with 10 CFR 50, Paragraph 50.55a(b), the applicable Code Edition and Addenda are the 1974 Edition with Addenda through Su=mer 1975 IV. Period of Attlicability In accordance with 10 CFR 50, Paragraph 50 55a(g)(.h)(iv), this program is applicable from September 1979 to the expiration of the second h0 month period. V. Insteetion Proerim The inspection program, which is detailed in the attached Table D-1, vill be carried out in accordance with ASME Section XI, 1974 Edition with Addenda through Su=mer 1975 S? ecific exceptions to the ASME XI Code requirements for each component are identified in attached Table D-2 along with the basis for each exception request 3d. 12?60 275
O N THREE MILE ISLAND UNIT NO.1 N INSERVICE INSPECTION PROGRAM - PUMPS o TABLE D-1 Pac 1 of 2, FLOW .ISI TEST QUANTITIES MEASURED
- TEST PUMP NAME PUMP NUMBER (S) DIAGRAM DRAWING N Pi AP Q V f',hf, Tb
^'
SPENT FUEL GF-PIA C-302-630 300-018-GN1 X X X Monthly During SF-P2A Operation D4ERGENCY FEED- EF-P2A C-302-081 300-009-GN1 X X X X X X Quarterly During WATER (MOTOR EF-F2B Operation DRIVE) EMERGENCY FEED- EF-P1 C-302-081 300-009-GN1 X X X X X X X quarterly Durin6 WATER (TURBINE Operation DRIVE) MAKE-UP AND MU-PIA C-302-661 300-017-GN1 X X X X X Monthly During PURIFICATION MU-P1B Operation MU-Plc NUCLEAR SERVICE NR-P1A C-302-202 300-002-GN1 X X Monthly During HIVER WATER NH-PIB Operation NR-Plc NUCLEAR SERVICE NS-P1A C-302-610 300-010-GN1 X- X X X X Monthly During CLOSED COOLING NS-PIB Operation WATER NS-Plc RFACTOR BUILDING RR-P1A C-302-202 300-002-GN1 X X X Quarterly During EMERG.ENCY RR-PlB COOLING
- SEE ASME SECTIi )N XI FOR DEFINITI( tN OF TEST QUANTITIES
N t% TilREE MII.E IGLAND UNIT NO. 1 N INGERVICE INSPECTION P110 GRAM - PUMIY; o TARLE D-1 C Page 1 or'd N
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FLOW ISI TEST QUANTITIEG IIEASURED " TE::T PUMP NAffE PUMP NUMBER (S) DIAGilAM DRAWING H PI AP V fj.!(, Tg, I II'I l' IIYSI' Q __. SCREEN WAGli GW-PlA C-302-203 300-01h-Gril X x thnttily I'urinn GW-PlB Operation SCREEN II0tIGE SW-P2A C-302-203 300-0116-GN1 X X Mont.hly 1)nring VENTILATION SW-P2B Opernt. ion EQUIIMENT CONTROL All-P3A C- 302 81:7 300-011-Grli X X X X f1ontiily I'nri nc BUILDING AII-P3B Ogerntion CilILLED WATER BORIC ACID CA-PIA C-302-670 300-021-Gril X X PInnt R, rueling CA-P1B Outncer, BUILDING GPilAY BG-PIA C-302-712 300-012-GNI X X X X X X Quar te r l y l>uring BS-PIB Operat i on L)ECAY llEAT Dil-PIA C-302-67:0 300-005-GN1 X X X X X X Quartorly In ring REMOVAL DII-PIB Oporntion DECAY llEAT DC-PIA C-302-6h5 30e-003-GN1 X X X X X quarterly Durinn CLOGED COOLING DC-PIB opernt,lon WATER ' DECAY llEAT DR-PlA C-302-202 300-002-Grli X X X tionthly Iturl un . RIVER WATER DR-PIB O t ernt.lon
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- AUME GECTION I F0ll DEFINITION OF TIclT (31 ANTI'l lICI
CX") N N Tl!REE MILE ISLAND - UNIT NO.1 INSERVICE INS'r'ECTION PROGRAM - PUltPS CD EXCEPTIONS TO ASME XI REQUIREMENTS NO N TABLE D-2 - Page 1 of 3 ASME XI ASME III ASME XI EXCEPTION TESTING PERFORMED IN PUMP NN4E PUMP NO. CODE CLASS. CODE CLASS REQUESTFD
- JUSTIFICATION LIEU OF CODE REQUIRFifENT REACTOR BUILDING RR-PlA 3 Non-Nuclear V See Note 1 Motor Vibration will be D4ERGENCY COOLING mansured RR-PlB Tb See Note 2 None Lubr. Level See Note 2 None Monthly Testing Gee Note 10 Quarterly Testing SCREEN WASil SW-P1A 3 Hon-Nucler.r Q See Note T Visual Observation of Flow SW-?1B V See Note 1 Motor Vibration vill be mean.
Tb See Note 2 None Lub- . Level See Note 2 Hone SCREDI HOUSE SW-P2A 3 Non-Huclear Q See Note 3 None VDITILATION SW-P2B V See Note 1 Motor Vibration will be mens. EQUIPMENT Th See Note 2 None Lubr. level See Note 2 None CONTROL BUILDING All-P3A 3 Won-Nuclear Q. See Note 3 None CIIILLED WATER AH-P3B Tb See Note 5 None DECAY IIEAT DR-PlA 3 Non-Nuclear V See Note 1 flotor Vibration will be meas RIVER WATER DR-PlB Tb See Note 2 None Lubr. Level See Note 2 None SPENT FUEL GF-P1A 3 N-3 Pi See Note h Pi vill be calculated SF-PIB AP See Note h None Tb See Note 5 None
*See ASME Section XI for Definition of Test Quantities
- i N THREE MILE ISLAND - UNIT NO.1 N INUEltVIUM Inut'ECTIOrl l'ItOClit.M - l'UMl'8 EXCEPTION 3 TO ACME XI HFQUIREMEN'IU C3 TABLE D-2 N Page 2 of 3 ASME XI ASME III ASME XI EXCEPTION TESTING PERFORME0 IN PUMP NAME PUMP NO. CODE CT'SS. CODE CLASS REQUESTED # JUSTIFICATION LIEU OF CODE REQUIRI2-fENT MAKEUP AND MU-P1A 2 N-2 Q See Note 8 None PURIFICATION MU-PIB MU-PIC NUCLE /R SERVICE NR-P1A 3 Non-Nuclear Q See Note 6 Will be measured during RIVER WATER NR-P1B Plant Shutdown V See Note 1 Motor Vibration vill be mean.
NR-Plc Tb See Note 2 None Lubr. Level See Note 2 None NUCLEAR SERVICE NS-P1A 3 Non-Nuclear Q See Note 9 None CLOSED COOLING NS-PIB NS-PIC EMERGENCY FEEINATEIl EF-P2A 2 Mon-Nuclear Monthly Testing See Note 10 Quarterly Testing (MOTOR DRIVE) EF-P2B EMERGENCY FEEDWATEF EF-P1 2 Non-Nuclear Monthly Testing See Note 10 Quarterly Testing (TURBINE DRIVE) s BUILDING SPRAY BS-P1A 2 N-2 Monthly Testing See Ncte 10 Quarterly Testing BS-P1B .
- *See ASME Section XI for Definition of Test Quantitico (
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. JUSTIFICATIOU NOTES FOR TABLE D-2 -Note 1 a This is a vertical deep well type pump with the purp submerged under water at all times. It is not practical to measure pump vibration in this type of installation. Past operating experience has shown that notor vibration is indicative of pump mechanical problens in this type of installation. Therefore, motor vibration vill be measured in lieu of pump vibration.
Note 2 This is a vertical deep well type pump with the pump submerged under water at all times. Pump bearings are lubricated by the fluid being pumped. There are no installed means of measuring bearing temperature and the pu=p design and installation makes it impractical to measure in any other manner. Hote 3 There are no flow meters installed in the flow path of this pump there-fore test quantity "Q" cannot bc reasured. An exception is requested per 10 CPR 50, 50 55 a (g) (4) since ceasurement of system flow vaald require a design change to this systen and therefore not be within the limits of the current design. Note h Since there is no pump inlet pressure gauge installed, test quantities Pi and 0? cannot be directly ceasured. An exception is requested per 10 CFR 50, 50.55 a (g) (h) since neasurement of purp inlet pressure vould require a design change to this systen and therefore not be with-in the limits of the current design. However, pump inlet static pres-sure vill be calculated based upon the difference in elevation between pump suction and the source of pump suction fluid. Note 5 Pump bearing temperature cannot be reasured on this pump since the bearings are located deep inside the pump casing and are currounded by an oil reservoir. An exception is requested per 10 CFR 50, 50.55 a (g) (h) in that measurement of parameter Tb is n t practical within the limits of design of this purp. Note G Flow metering for this systen is located in the co==on discharge lines from all three pucpc. Plant operating requirements dictate the operation of at least two Huclear Service River Uater pumps during plant operations, thereby making it impossible to measure flov for a single pump. Pump flow vill be measured for each pump during plant shutdown when operation of cnly one pung is required. 1260 281
During accident conditions flov to a significant portion of the Nuclear Services Closed Cooling System is shut off, thereby reducing the heat load on the Nuclear Service River Water System. Therefore, if the Nuclear - Service River Water System is adequate during normal operation it vill be more than adequate at accident conditions when the heat load is reduced. Note 7 There are no flov instru=ents in the flow path of these pu=ps and therefore, test quantity "Q" cannot be measured. As an alternative, the discharge at the spray nozzles vill be observed during each test to determine if sufficient flow is available to wash the screens. Note 8 There are no flow meters installed in the flow path of this pu=pytherefore test quantity "Q" cannot be measured. An exception is requested per 10 CFR 50, 50.55a(g)(h) since measurement of system flow would require a design change to this system and therefore not be within the li=its of the current design. The high pressure injection system is however) y tested during cooltawn/ heatup between 275 F and 380 F at cold shutdown head. Note 9 Flow metering for this system is located in the conmon discharge lines from all three pumps. Plant operating requirements dictate the operction of at least two Nuclear Service Closed Cooling Water pumps during plant operations, thereby making it impossible to measure flow for a single pump. Pump flow vill be measured for each pump during plant shutdown when operation of only one pump is required. During accident conditions flow to a significant porti'on of. this system is-shut off, thereby reducing the heat load. Therefore, if the system is-adequate during normal operation it vill Be more than adequate at accident conditions when the heat load is reduceds Note 10 During nor=al operation there are several pumps that are lined up for ,. e=ergency standby and only operate during surveillance tests. For those pu=ps relief is requested from monthly ISI testing since operating experience has demonstrated that degradation of a non-operating pump is improbable. Quarterly testing vill be substituted in order to ensure the operational readiness of the pumps and to obtain data for evaluation of pu=p degradation. In addition, quarterly testing vill enhance nuclear safety in that it - reduces the number of times an emergency standby system loop is re=oved from service for testing. 1260 282
Note 11 The Boric Acid Pu=ps vill be tested only during refueling outages since the only meth,od of testing there pumps is to inject concentrated boric acid into the Reactor Coolant Makeup System. This would adversely affect plant operations and result in additional significant volumes of radioactive vaste. 1260 283}}