ML20127H340
| ML20127H340 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 03/15/1978 |
| From: | NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML20127H318 | List: |
| References | |
| NUDOCS 9211180488 | |
| Download: ML20127H340 (181) | |
Text
{{#Wiki_filter:_ _ _ - _ _ _ _ _ _ _ NORTHERN STATES POWER COMPANY
)ONTICELLO NUCI. EAR GENERATING PLANT DOCKET No. 50-263 LICENSE NOS. DPR ASME CODE SECTION XI INSERVICE INSPECTION AND TESTING PROGRAM -
-AND INFORMATION REQUIRED FOR NRC. REVIEW OF REQUESIS FOR RELIEF FROM ASME CODE SECTION XI REQUIREMENTS
= _ =
SUBMITTED: Harch 15, 1978 REVISED:- Revision 1 August 28, 1978~
-Revision 2 January 5;.1979 Revision 3' February _26, 1979'-
Revision 4-July 27,.1979 Revision 5: March 5, 1980-4
~
9211180488 780315
-PDR ADOCK-05000263-t 4 PDR, a
TABLE OF CONTEh7S SECTION PAGE 1 Nondestructive Examination Program Class I l-1 Class 2 1-37 Class 3 1-50 2 Pressure Testing Program 2-1 3 Inservice Testing of Pumps and Valves 3-1 4 Requests for Relief from ASME Code Section 4-1 XI Requirements Determined to be Impractical d 5 Proposed Technical Specification Changes 5-1 6 Quality Group Classification Drawings 6-1 4 i l l l l 1 l i i l
_R_ECORD 07 REVISIONS
- Page No Revision No Page No Revision No 4
Cover 5 3-8 4 , li original 3-9 Original 5 3-10 4 iii iv 5 3-11 2 Original 3-12 4
! 1-1 1-2 thru l-3 1 3-13 2 1-4 3 3-14 Original 1-5 1 3-15 thru 3-19 2 1-6 thru l-8 3 3-20 thru 3-24 3 1-9 thru l-11 Original 4-1 1
, 1-12 1 4-2 thru 4-4 Original . 1-13 thru l-16 3 4-5 2 1-17 Original 4-6 thru 4-7 Original 4-8 3 i 1-18 1 1-19 thru l-20 Original 4-9 2 1-21 3 4-10 thru 4-11 Original 1-22 thru l-27 1 4-12 1
- 1-28 3 4-13 Original 1-29 5 4-14 1 1-30 5 4-15 Original
. 1-31 5 4-16 2 1-32 3 4-17 thru 4-22 1
- 1-33 5 4-23 thru 4-27 Original l 1-34 3 4-28 1
! 1-35 1 4-29 thru 4-31 Original 1-36 3 4-32 2 1-37 thru l-39 Original 4-33 Original i 1-40 thru l-41 3 4-34 2 1-42 Original 4-35 thru 4-36 Original 1-43 1 4-37 2 l 1-44 Original 4-38 1
- j. 1-45 4-39 3
( 1-45A 1 4-40 1 1-46 thru l-47 3 4-41 thru 4-43 2 l 1-47A 3 4-44 thru 4-45 3 1-48 1 4-46 thru 4-47 5 1-49 1 5-1 thru.5-31 Original 1-50 Original 6-1 3 l 2-1 2 6-2 1 3-1 4 6-3 thru 6-7 Original l i 3-2 1 6-8 2 l 3-3 thru 3-7 2 6-9 thru 6-10 Original 6-11 2 6-12 thru 6-14 Original 6-15 4 6-16 thru 6-20 Original 6-21 3 iii Revision 5' 3/5/80
._ - _ . . _ . _ _ _ . _ _ _ _- _~ - _ _ _ _ . _ _ . _ _ _ _ _ _ _ _ _. . . . _ _ _ _
i l 4 . 1 1 l l This report contains a description of our proposed program of inservice inspection and _ testing of components of the Monticello Nuclear Generating [$ j Plant. This program conforms to the requirements of 10 CFR 50, Section , 50.55a(g). l i i The information presented in this section follows the recommendations I cont ained in a letter dated November 24, 1976 from Mr D L Ziemann, Chief, j ] Operating Reactors Branch #2, Division of Operating Reactors, USNRC, and in a letter dated January 16, 1978 from Mr D K Davis, Act ing Chief, l l Operating Reactors Branch #2. The program is updated as required by changes to Section 50.55a(g) published in the Federal Register on October 7, 1979. Inservice inspection and testing requirements are updated at 120 month ! intervals to conform to the latest edition and addenda of Section XI of
- - the ASME Code referenced in paragraph (b) of 10 CFR 50, Section 50.55a.
l This manual will be updated each time changes are made to the inservice
- inspection and testing program. Deviations from Code requirements are '
also documented for NRC Staff review in this manual.
; The program description is arranged in the following manner:
Nondestructive Examination i Class 1 - Section 1.1 f 4 ! Class 2 - Sect ion 1.2 ' I
- . Class 3 - Section 1.3
!=
- Pressure Testing Program - Section.2 -
l Inservice-Tests of. Pumps and Valves - Section 3 l Deviations _ from Section XI- ' - Section 4 Req uireme nt s l ( . . i Proposed changes to the Technical Specifications which implement this ! program were submitted to the Commission on August- 30, 1977. A summary. I of these proposed changes is contained -in Section. 5 of this report. j -System drawings showing ASME Code classification boundaries are included l-in Section 6 of this report. These drawings are used to define pressure test boundaries and identify those Class 3 components subject to visual-inspect ion as part' of _ the nondestruct ive examination. program. i i-
-iv Revision 5
-3/5/80
.__.u..._..._.?_._.,._-_
- - _ _ _ _ - - - - _ - - - - - - . . - - - _ _ - .-. _ _. ,_ - . . _ - - -.--. - - . - . . - . - . . - - . - ~ . - ... i f I i ASME Section XI Nondestructive Examination program - Class 1 ASME Code Editioa and Addenda: 1974 Edition through and including Sumer 1975 Addenda Program Period: February 28, 1978 to June 30, 1981 (Ihird Inspection Period) NOTES:
- 1. The following tables identify the specific Class I components and parts to be examined. These tables can be directly correlated with Table IWB-2500 and Table IWB-2600 of Section XI identify the examination method for each listed item. The inspections that were completed dur'ng period one and period two are identified in the tables, along with the running percent' completed during each of these periods. No effort was made to retrofit items into the.first two periods that t, era not previously required for examination. The tables show the amount of items required to be examined during period three and the corresponding percentage that will have been com-pleted by the end of this period.
- 2. Repairs will be perfomed in accordance with the applicable requirements of the latest edition and P. addenda of the ASME Code, Section XI.
P However, if railen for a particular repair are not specified in Section XI, the original design specification and Construction Code of the component or system, or later editions of the Construction Code or ASME Code Section III, either in their entirety or portions thereof, may be used. LEGEND Examination method: V - visual U.T. - ultrasonic ; R.T. . radiography S - ettface examination, either liquid penetrant or magnetic pa rticle Inspection Period ONE - June 30, 1971 to October 30, 1974 I
-IWO - October 30, 1974 to february 28, 1978 Tl!REE - February 28, 1978 to June 33, 1981
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a m , . 4 r MVulfAN STATTS POkTR (D. TAMI I.I MhTIQ11D MX1 EAR Q3TRATING PIMF { PN;E 1 OF B .! nN < ras INTERv4L Im pEr_tt w svaawane > MUOR ITU1: R fACTut VESSEL i P191. OMMTAT OR SYS1T}t, 1UTAL, l INSPIE D NNATim I CAlT- - ANTI 143CRITTION OF T.PER g a IIENTIFICATION TION ID MRKS mrN iTi}f 1D PI' l~t?Jt!Nf't) 111}f
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MhT M NT PYRf0D 2 Bl.1 B-A LOP 3GITUDINAL AND CIRCUMFf3rFN- RELIEF PPU"EST NO. 15 ' 4 TLAL WELDS IN LokF. REG 10*4 (Wi1D Lf2ECV4S = 11 FEET) s LONGITUDINAL WELDS '. UT VIAA-1 WELDS ARE NOT - SHELL CtCRSE 1 75' - TUP 27" OF WELD SEAMS VIAA-2 : ACCESSIBLE - SHE1100URSE I 255' - (smell COURSE 1) IN ~3 CORE RECION
.VLEA-1 WELDS ARE NOT -
SHELL COL'RSE 2 45' - BOTTOM 117" OF WELD VLBA-2 ACCESSIBLE - SHELL C03RSE 2 .225' - SEAMS (SHF1L Cot'RSES 2) IN CORE REGION l CIRCUMFERENTIAL WELDS 1 . trr VcnA-2 WF1D IS Nfyf - SHELL cot'RSE 1 TO 2 - (VELD LENCVT
- 37 FEET) ,
' ACCESS 18tLE ELEVATION 19'6" 4 7 Bl.2 B-B LONCITUDINAL AND CIRCt MFFRF14-N TIAL WFt.DS IN SHELL (OTHER THAN THOSE OF (AlfEORY B-A AND B-C) AND MERIDIONAL AND CIR- ] C1'r*.F ERENTIAL 5FAM wilds IN ! BOTTOM HFAD AND CLOSURE HFAD (OTHER THAN THOSE OF CATEGORY B-C) t SHELL. (WELD LENC1HS = 11 FEET) 75' IDNCITUDINAL VELDS 6' tri VIAA-1 WELDS ARE IKTf - SHELL C0t%SE 1' - RELIEF RIMUEST NO. 15 ' VIAA-2 ACCESSIBLE - SHELL COURSE 1 255 VLCB-1 RELIEF RfD'T NO.16 - S!! ELL CW RSE 3' 105' -' RFLIEF RFQUEST NO. 16 VLcB Pf11EF RFW T Ntt 16 - SitELL' COURSE 3 2858' - l VLDB-1 (24" EXAMINED) ONE SMF.LL COURSE 4 130' .(IE%) ONLY $7" (431) OF EACH j (NONE) '1VO (151) VELD SEAM, VLDB-1 AND ' 8 33" 190 1HREE 431 VLDB-2, ARE EXTF.RNALLY ACCESSIBLE mw . . 4 U *e VLDB-2 (NONE) ONE' S1IEll COU!?SE 4 330 0 .(0) ! T7 (57" EXAMINED) 1VO (431) + I
.Moa NONE- THREE 431
!- ~ PELIEF PyrrFST 10, 16 7 VIAA-1 REL1EF Rro*T No.16 - SIIELL COURSE 2 45' - TOP 15" or WEIR SEAMS
- - vLBA-2 uuEr REe'r No. t6 - Suttt CocRsE 2 22so -
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MUOR In}l: REACTOR VESSEL .. INSITC- I UMMIAT OR SYS111f. l linAL Inf TMMTW # AND 11ESCRfrTION Of ML PLR fi3ATIFICATION T1ON RI}nRKS . CATT ; NU M MhI mM iTTM TU RE i'Wf1 NIT) illM f'f E f 0D ltl.2 B-B (CONTINtTD) EttrTOM !!EAD TO COURSE I PF1.IEF REQt?EST NO. 15
- j. CIRCUMFERENTIAL WELDS 3 UT VCBB-1 WELD IS NOT -
E!IVATION 8'7" ACCESSIBLE VCBB-3 WELD IS NOT - SHELL C'AIRSE 2 TO 3 - FritFF pmt'EST No.15 ACCESSIRLE ELEVATION 30*6" 4 g VCBB-4 R ELIEF RFY)'T TML 16 - SHELL COURSE 3 To 4 - PELIEF itFM"EST NO. 16 , i ELEVATION 41'6" CLOSURE HEAD I MERIDIONAL WEtJ)S 6 UT HMCB-1 (lla FEET EXAMINED) ME CTASURE 11EAD 30" (7) (vrLD Liscists - 7 FEET) l IDM31-2 (llJ FERT EXAMINED) ' CLOSUFF ltFAD 90 8 liMCB-1 (7 FEET EXAMINED) TIF) CLOSt'RE HEAD 308 (57) l 0 ! HMCB-3 (7 FEET EXAMINED) CLOSURE ItrAD 150 tiMCB -5 (7 FEET EXAMINED) CLOSITE HEAD 2700 4 g itMCB-4 ItMCB-6 7 FEET 1001 7 FEET 1001 THREE CIDSURE HEAD 210' CIDSt'RE HEAD 330* gy l'
- CIRCUMFERENTIAL WELD 1 t'T 11CCB-2 (NONE) ONE ft1 LIAR PIATE kTLD -
(kTLD LFNCTH = 25 FEET) (25 FEET EXAMINED) 11 # 1 (1001) i'- NONE T11REE 100 l i BOT 1DM ttFAD . Fict'RE 5 :
- MERIDIONAL WELDS 8 UT 11MAB-1 WELDS ARE Nf7T -
ECT1Mt HEAD O* - Rf11FF PPI)fT.ST NO. 16 g HMAs-2 AccEssist.E 45' i itMAB-3 90* I flMAB-4 135' I II:RB-5 150" ; HMAB-6 225 8 EF IIMAa-I 270'
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- 18?MB-10 ACCESSIBLE 195' i
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NOR11113N STATIS PWER (D. TABli 1.t J MMTI& LID NIR11AR GNRATING P1MT I P,$CE 4 Or a '
'EN -ear IN'ERwat t *a s pE r. r t :m s u=w a n < l P1VOR IIIM: REACTOR VESSEt, i
EXAM. (IffMMNT OR SY5 TIN, 1tTTAL i INsPtr- N W. GIT,. AND ITSrRII' TION or m.I1R IDINTIFIGTim EXMIMTim TION 1 Tim M RIM \RKS NOINT AND EXTINT M STIM M NBER NW mW inM 111 RE IMif NTD f1ly p, p m , B1.4 2-D (CorrTINUED) ! VESSEL SifELL' CORE SPRAY A (NSA) .2 IfT CSAD-1 (EXAMINED) TitREE SHELL QURSE 3 90 8 100 l cDRE SPRAY B.(NSB) CSBD-1 (EXAMINED) 1VO SHE!1 COURSE 3 2708 (50) g I Q)NTROL MOD 1 UT CI'AD-1 (EXAMINED) ONEATVO SHELL C0f'RSE 3 ' 65" (100) 'f! HYDRAULIC RETURN (N9) 8 RECIRGIATION 2 UT PCAD-1 (EXAMINED) ONE SHEL1, QX RSE 1 0 (100) DUTLET A (NIA) 8 ] RECIRCtT!.ATION RCBD-1 (EXAMINED) ONE. SHELL COURSE 1 180 (100) , OUTLET B (NIB) 1 W LD 100% THREE 100 RESCHEDt'IID FOR EXAMINA- , TION
',* RECIRGIATION 1NLET FREZLES 10 UT i INLET A (N2A) RRAD-1 (EXAMTNED) Of E SHEll OCRSE 1 30' (10) .
INLET D (M2D) RRDD-1 (EXAMINED) ONE SHrLL COURSE 1 120" (20) ! INLET J (N2J) RRJD-1 (EXAMINED) ONE SHELL COURSE 1 300* (30)' , INLET C (N2C) RFCD-1 (EXAMINED) TWO SHELL OX'RSE 1 90* (40) <
. 1NLET E (N2E) 'RRED-1 (EXAMINED) TWO SHEli QX'RSE 1 ' 150" (50) !
- INLET C.(N2G) RPGD-1 (ERMINED) TWO SHEli ComtSE 1 240' (60)
' I j INLET B (N23) RRBD-1 1 WELD 100% THREE SilE11 QURSE 1 60" 70 1 WELD '100'. SHELL CtURSE 1 2107 80 ~ INLET F (N2F) FRED-1 T11REE INLET H (N2H) i RRHD-1 1 WELD 100% T!!REE SSELL COURSE 1 2700 90 INLET K (N2K) RPKD-1 -1 WELD 100* THREE SHELL COURSE 1 3308 100
- JET PUMP. INSTRUMENT N0ZZLE 2 UT ' +
- N0ZZLE A'(N8A)- JPAD-1 (EXAMINTM ONE SHELL RTRSE 1 60' ~ (50) f
= k ! NOZZLE B (N88) JP!sb-1 1 UEID 1001 THREE SHELL COURSE 1 24L" IX1 ! aw i- gQ B1.5 R-E VESSEL FFNFTRATTONS.'INCLIfD-' I .f* ; ifK: wiTROL ROD DRIVE AN'1 gy' INSTRUMartATI(W FENETRATIONS 1 $ ' "- C(NTROL ROD DRIVE 121 V FICI9E 1 RELIEF Rff}'T NO.17 - t'NDFR REACTOR VESSEL - RFI.1EF pim*FST MO. 17 { PENETRATIONS ' BOTTOM READ i 4 r - s a 4 > y . - -,. .n .,...y , g
. _ _ _ _ _ _ _ _ _ . _ . _ -_ . , _ . - . . . . _ . . - . _ _ _ _ _ _ _ _ . _ . _ . . . . . . . . . . _ . . . . ... .__.-_m.. ._.._,_.__m....m..m. . . . _ m 1M 7 i
MYC1!rRN STATIS IWTR CD. TAPH I.1 MMTIQLID NIKlFAR E'4R-\ TING PIRIT
<F a c gy*tuval f *JSPE r.T ! du ';ceawan e 8 EN MUOR lil?t: J EACTnP VESSEL Elef (M10NILT OR SYSTIM, VMAL IY;PEC MMTM 1 CATION OR RtNNIM.
CATr AND !(3LRIPTifW Or 4).Pf R II(?.TITICh1 UN TUN i fnW ITUf V) 90 iTf6tfNTT) T11N MW AND IET Pf ? f 0D N MN ' Bl.5 H-E (CONTIfmED) INSTRUME!GATION 4 V FICUPE 4 1 WELD 1001 THREE 23 - TENETRATIONS j NO22LE N11A VIAE-1 SHELL COURSE 4 40* ! NOZZLE N11B VLBE-1 SHELL Col lRSE 4 220* l N0ZZLE N12A VICE-1 SHELL COURSE 3 40* i NOZ7LE N128 VIDE-1 SHELL CIURSE 3 220* , RFA' CTOR VESSEL ' ROTTOM HEAD DitAIN (NIS) 1~ V HDAE-1 RI' LIEF RIJ)'T Nil l? - 50T EM HEAD . RELIEF PTTJrEST No. 17 REACTOR VESSEL - CLOSURE HEAD-TIANCE LEAKACE SENSORS 2 .V i NOZ2LE N13 VFAE-1 PELIEF S m'T Nfl 18 - VESSEL FIANGE (DRYWE1L) - RELIEF PMtTST Mn, 13
~ N0Z2LE N14 VFBE-1 VESSEL FLANCE (t*YVELL) i 81.6 B-F N0ZZLE-TO-SAFE END WELDS (19)
CLOSURE HEAD HEAD VENT (N7) 1 PT-UT HVAF-2 (EXAMINED) ONE CI4SUKE PFAD TIC (33) ItEAD SPRAY (NbA) 1 RHDF-2 (EIMtINED) CNE CLOSURE HEAD 90* (67) i HEAD SPARE (N6n) 1 IISBF-2 1 WELD 1007.. THREE CIDSI'RE HEAD 180* 100 BOTTUM HEAD STANDBY LIQUID . 1- PT-UT CPAF-2 PARTIALLY THREE BOTTrPt HEAD 350* 100' FE1.IFF FI'f2 REST No. 19 CONTROL (NIO) .AtTESSIBLE ' l
- VESSEL SHELL 1 um- CORE SPRAY A (NSA) ,2. .PT-UT CSAF-2 ( EXAMINF.D) TWO SHELL C(tPSE 3 90 0 (50)
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'sm (X)RE SPRAY B (NSB) . C56F-2 (EXAMINED) ,
TWO SHELL (XWRSE 3 270* (100) 4 U$ " CONTROL ROD 1 PT-irT CRAF-2 . (EXAMINED) TWO BASELINE (100). PEPIACLD Wim CAF I**7 HYDRAULIC REll;RN (N9) . { 1 WEA D 100* THREE SHELL CorPFE 3 65* 10 7. +- i
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NETillTN STATTS I%TR 00. TABff^ 1*1 , htNTIRLID MICITAR GNERATING Pl#fr l PM 6 or s
*n <cai retstvat inspEtr w i+-as, PtVOR IIT}1: RfACTOR VEs5Et IMf. M10NINT OR SYSIUf.- 1UIAL f INSPI:C- NV Tim OR AND I43CRIITION Or ?O.PIR IIU TIN CATION IMIINATIM TION 1 . pyygggg N CATE WNT AND IIITNT ny,gg SYSTD1 m R PTM mW f1T?f m Pr rWffNTD fTT?f Mt.6 -B-F (CONTINUED)
VESSEL SHELL RECIRCU!ATION . 2 FT-UT RCAF-2 (EXAMINED) ONE SHELL O TRSE 1 0" (50) Bom SAFE C D WELDS OtTIT ET A (NIA) 8 (A&B) k'EFE EXMIENED pg RECIRCUIATION RCBF-2 (EXAMINED) ONE S1tELL COURSE 1 180 (100) DURING PERIOD WE PER 1 WELD 1007. THPEE 100 PIANT TECH. SPEC. OUTLET B (N1B)
. RECIRCU1ATION INLET (10) TT-trr 8
INLET A (N2A) RRAF-2 '(EXAMINED) ONE SHELL COURSE 1 30 (10) l
' INLET D (N2D) RRDF-2 (EXAMINED) UNE SMELL O('RSE 1 1208 (20) l 1NLET J (N2J) PRJF-2 (EXAMINED) UNE SHELL cot'RSE 1 300* (30)
INLET C (N2C) RFCF-2 (EXAMINED) TWO S11 ELL COURSE 1 908 (40) 7 INLET E (N2E) RREF-2 (EXAMINED) WO ~ SHELL CtVRSE 1 1500 . (50) i I
' INLET C (N20) PRGF-2 (EXAMINED) .. WO SHELL COURSE 1 240" (60)
INLET B (N28) 'RREF-2 1 WELD.'100* THREE SHELL CWRSE 1 608 70 INLET F (N2F) RRFF-2 1 WELD 1001 - THREE SHELL COURSE 1 2108 80 8 INLET H (N2H) RIGIF-2 1 WELD 1001' THREE SHELL COURSE 1. 270 90 RRKF-2 1 WELD 100%. TitREE SHELL Cot *RSE 1 330* 100 INLET K (N2K) JET PLHP INSTRUMENTATION 2 PT-UT N0ZZLE A (NBA) ' JPAT-2 (EXAMINED) ONE SME11 COURSE 1 608 (50) N0Z2LE B (N88) JPBF-2 1 WELD 1007. THREE SHELL CtMRSE.1 240* 100 ; INSTRUMENTATION LINES 4 PT-LT
~
N0ZZLE A (NilA) VIAF-Z 1 kT1D 100%' TifREE SHELL QWESE 4 40* 25 N0ZZLE B (N118) VIBF-2 1 WELD 100% THEEE SHELL col'RSE '4 220* 50 VICT-2 1 WELD 1007.' MIKEE SHELL Cot'RSE 3 408 73 N0ZZLE C (N12A) NOZZLE D (N128) VI DF-2 -1 WFLD 100% THREE SHELL COURSE 3 220* 100
*p Rt.7 01DS1*RE' STUDS AND NtlTS 64 FICURE 3 M. 6
' UT (23 EXAMINED) . o*IE -
(36) O* Bl.8 4-C-1 INPTACE '
- g .. or (2) EXAMINED) . 'WO' -
(72) l
'WHEN REMOVED SURFACF 23 STUDS 1007.~ THi'EE. - 100 u ,pc.2 6 UT
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i MA'T101tD ME'tIAR GNRATDC PIMT i PAGE 11 OF 17 i n r ac s u Esevat insecrr g m sts-ag e j ) * ? MUDR IlUt: PIPING PRESSURE BOUhTARY ' I ! i 4 1 wt OMYADrr OR SYS11M, 1UIA1. Iff0C- N T- t l AND ICRCRIITI(N OF *a).PI R IIn TTI'ICATi m NNATim Tim TW M pyygggg i CA1Y SYSTUIhu eJR P!3CDTf ! qN YUN in RF f twf%TTb YTIM AMilNT AND ITffNT p pynn p ' i B4.11 B-J (CONTINt'ED)
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MEDIDN STATIS IOUt (D. TABE 1.6 MWilfTifo MIQIAR (EUATDC PIMT PAGE 1 OF 6 3
*Es <Ema 1%*Envak 1*asPE CT 10% s u==a a r MtKR ITD(: VALVE PRESSURE BacNrmaY
!IAM. (IMuirAT OR SYSTD4, 1UTAL Igrgs CATT. AND DEsatIITim OF MLPDL .
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. 2" x 15.5" (1-12 EKAMINED) WO (50)
.- 151-1.3a 12 BOLTS (13-24) THREE 100 24 V-ti CATE N02-438 (NONE) ONE DRWE11 REW135-28" -
2" I 15.5" (1-12 EXAMINED) Wo (50) 151-13B 12 BOL N (13-24) THREE 100 Be.2 E-G-1 P*NSWE-PFTAINTNG BM,TS AND AND SD:DS WEN kDSWED j e6.3 B-G-1 (2 13K3R AND 1ARCER DIA.) RECIRTIATION CATE TALVES 24 V-S CATE VALVES (NONE) ONE W 2-53A ITT 2" I 15.5" (NONE) WO 100 WlH2s VALVES DISASSEM , M02-41A ISI-13A /138 24 BOLTS (1-24) 1HREE RECTRCLUTION LOOP A & fi Mn2-538 NOTE B6.7 BllD (RELIEF REQ NO. 42) ! :o 2-438 RDtARKS - - SUPPORTS ARE LISTED R6.4 3-E-1 Th"rECRAl1Y LT1DFD SUPPORTS - - UNDS B4.9 OF TABLE 1.6 yy ti stTPOPT O ri?' er m s RDnRKS - - SUPPORTS ARE LISTED g; B6.5 3-K-2 - - UNDER B4.10 OF TABLE 1.4 o B6.6 S-M-1 VALVE BODY bTLDS IKh1 f 4 r . , . , . - - . . . - , . _- .,,p -
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.. f MuiR I11M: VALVE PRESStTRE BOUNDARY '
EIAM. meGENT OR SYSTIM, 'IUtAL pgy. lit 30GNf gjg EXAMINATIN 10CATIN OR j y CATE- A2 IESGIFTIN OF M).MR IDDrTIRCAUm TIN SYSTIM MBEER PEIG N1 N t N TT9610 F EXAMI6 TTIM APONT AT) EXIINT mm 4 1 l 1 B6.7 B-M-2 (CourTINCED) 15 Y F05-1758 EIAMINE W E INTER- THREE CORE SPRAY A 100 .( j ANCHOR # ho-1754 NALS OF ONE VALVE TW7-8"EF ' ! CATE VALVE t POS-1757 G RE SFRAY B ' MD-1753 TW11-8"EF ' t f, 10-2034 HPCI - STM. ' MD-2035 PS18-8"ED = 4 MO-2029 ,RHR - REW10 > j { MO-2030 . REW10-18"ED ' } P05-2028 ; ' I l p
** FW-95-2 . FEEDWATER A i .FW25-14"ED O :
i - j FW-98-1 FEEDWATER B { FW2A-14"ED 4 POS-2019 RHR - TV20 TW20-16"DB j 70-2015 FOS-201B RHR - TV30 m-2014 tv30-16"DB 6 V 102-65A EIAMINE THE INTER- " THREE RECIRCLTATION 100. *klHEN VALVES ARE f CRANE CHAPMAN DISASSDGLLED F NO2-65B NALS OF ONE VALVE. REW32-22" ! CATE VALVE (REL1EF REQUGT WO. 42) I { M02-53A RECIRC1'LATION A i t M02-43A .REV13A-28" l RECIRCULATION B i 902-535 f REV135-28" , MD2-435 i f t ** -
- INCL 1!DED IN B4.11 ,
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ASME Section XI Nondestructive Examination Program - Class 2 ASME Code Edition and Addenda: 1974 Edition through and including Summer 1975 Addenda Program Teriod: Februa ry 28, 1978 to June 30,1981 (Third Inspection Period) WTTES :
- 1. W e following tables identify the specific Class 2 components and parts to be examined. These tables can be directly correlated with Table IWC-2520 and Table IWC-2600 of Section XI and identify the examination method for each listed item. In period one and two, Class 2 components and parts were not required to be examined; because of this, the Class 2 inspection program will begin with period three ne tables identify the number of items required to be examined over a forty (40) year service lifetime, and the amount required for a ten (10) year inspection interval. He tables also show the amount of items required to be ' examined during period three (which is approximately 1/3 of that required for an inspection interval), nd the percentage that will have been cogicted by the end of that period based on the 40 year requirements.
- 2. We scope of the inspection program for Class 2 components was based on the exemption criteria of IWC-1220.
- 3. In accordance with the requirements of IWC 2411 the nondestructive examinations were selected so that the total examinations completed over forty (40) years will be 1007. of the required examinations of the system or portions of the systems with a single stream or he equivalent to having performed 1007. of the required
- examinations in one of the streams of a multiple stream systan. H e only exception is that the selection of de " pressure retaining bolting for valves was based on the type, manufacturer, and design of valve and not on the total number of certain size valve bonnet bolts per system.
- 4. Repairs will be performed in accordance with the applicable requirements of the latest edition and addenda of the ASE Code, Section XI. However, if rules for a particular repair are not specified in Section XI, the original design specification and Construction Code of the component or system, or later editions of the Construction Code or ASME Code Section III, either in their entirety or portions thereof, may be used.
IIGEND: Examination method: V - visual U.T. - ultrasonic R.T. - raddography S - surface examination, either liquid penetrant or magentic particle Inspection Period ONE - June 30, 1971 to October 30, 1974 IWO - October 30, 1974 to February 28, 1978 T!!REI; - Februa ry 28, 1978 to June 30, 1981
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- P4 W Tl GLIJ1 ESi!T I 7,y[I ny,y -
I
!LN iLW IVI1FY1L INTCTION SIPStWy PEE 2 or 3 I
l l K UOR ITIM: P1 PING - 01RmfFEFFNTIAf. Bt?TT kTLDS 4AVI 4 D GSSWXI @ M SlDt, A A.15^ l IDI CAIT - AND ltSCRil710N g W M AL If21 M R. 10 YR.. Tit !RD Tti LRD i 6 7 MT ITIM 10 PE 13,WINII) UN WU ^*CNT PERI @ PERIOD _ LOCATION RT}tWKS ' 2 tmE AP'* NT mm Pnt m I f (2.1 L-s; (owt!NLTD) . j C0RE SPRAY A & 5 10" . j 151-34 & I51-35 TW7-10"CE A UT 14 la 4 PWlLTIPLE STREAM 1 1 17 } TWi l -10"r. E B EL 976' REACTOR s tT 10 10 2 - -- -CS PD1P M-I r1971' BUC CORE SPRAY A 5 5 h%4 1 C2.1 C-C CONTAINMurf PtfRGE Cf.HSINF D CP!-18"ttE A ITT 1 3 1 ISI-3fa ! j - - - EL 925' @ PENET.1-26 ' MULT!FII STREAM
- i l CPI-15"HE R TORUS O! AMBER ftRGE LINE UT 3 3 1 - '~
I - - EL 976* <? PEhTT. X-25 A & a CoMnINED ' R'JCU R0(H t ISI-388 *
. C2.1 C-C R!tR SERVICE WATER MULTIPIL STREAM t
i 4 SW9-8TE LTT 47 47 24 6 2 REACTOR ISI-39 { 8 EL933' BLDG C2.1 S INGLI ST RE AM C-F CIPr1MFFRfNTIAL WTT bTibs j 9FT.f FF PNUEST NO. 21 j C-T MAIN STEAM A I 151-26 i l t PSI-18"ED UT 16 16 4 M11TIPLE STREAM i
' 1 1 6 EL 936' STEAM CHASE
{ C-F ( ',) - (1978 BA5!LINE) MAIN STEAM R 151-27 PS2-18"LD UT 15 15 4 MULTIPLE STREAM i 1 I 13 FL 940' STEAM CHASE (2) f = l C-F !%IN STEAM c (1978 BASELINE) l ! 15!-28 I PS3-18"ED UT 16 16 4 MULTIPLE STREAM 1 - - i EL 942' MOISTURE SEPR1R r . C-F M IN STEAM D (') - (1978 BASFLI5E) . l i 151-29 i ! PS4-18"ED UT 16 16 4 M.1TIPLE STREAM 1 - -
- EL 942' NOISTURE SEPRTR j t-F SUPPLY Yn STrn (2) -
'1978 BASELINE) ,
l ** 7 SEAL SYSTEM W ISI-30 47 PS11-6"ED UT 8 '8 2 1 - - ] *4 EL 940' Pt)ISTURE SEPRTR : ML1TIPLE STRFNth l 1 (. PS12-6"ED UT 5 5 (j) - (1978 BASELINE) l 2 .! l PS13-6"ED UT 5 5 I 1 1 17 TL 940' MotSTURE SEf'RTR MTIPLE STRFAtts } PS] 4-6"ED UT 5 5 M1TIPLE STREMIS 1 -
;f i (Str 1401 LINFS Cftm!NTD) 'TLTIFI E STREA"5
; i
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~ - - - - - - - ~ ~ - - - -~~--- ~ '
i
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i i 1
'dWT15 FN STATTS PWIR (D. TAPII 7.2.1 ML718111A 131T 1 PACE" 1 DI~ )
'fT.N U.G IY!1M*d, INSPtCTION S7f t4Y i
- %UOR ITDf
- PIPIE - CIRrt' 78TdNTIAI P.itTT VFLDS :
4 I i tivt (3 H t P.tN!' s H SbIlN, AA35- t i W CA IT. - A*a f( N I!!i10N (p ME TUTAL y gty 40 Ut. 10 YR. TH1RD THIKO IIDI tiGY MDM IN g,fRIOD PERIOD 10 CATION RDtW3 , ITUt TO PE EXMtIN!? ITUG Amin:T Areths Ann 7 rrR(rNT j t.2.1 C-F (UINT int f.D)
- SUPPLY 70 STEAM
- SEAL SYSTt?t IS T-30 ' '
1 t!T t PstG-5" - 18 18 Is 5 2 11 EL 940' Pv)1STURE SEPRTR SitELE STREAPI #-% Ps7-10"ED UT 1* lb 16 4 1 ,6 EL 940' Pv11 STORE SEPRTR S!? ELE STPEAM PS7-8"ED UT 7 7 7 2 ~- - EL 940' Pt01ST1"PE SEPRTR SIFCLE STFEAM }, C-F HIQI PRESSUPI CotitJLNT IM.3fCTION - WATER SIDE 151-31 -otsCHAPGE- ) i T'43-12"ED UT 6 6 6 2 - - EL 933' STEAM CHASE SINGLE STREAM (TO) FW28-II."ED j ,. C-F FEEJEATER 5 ISI-37 i :
~ r F% 28-14*F D UT -3 3 1 - - -
EL 940' STEAM 01A5E MULTIPLE STREAM j FEEWATER A 151-37 4 ! Ed2A-14"ED IfT 3 2 33 3 1 1 EL %O' STEAM CIIASE MULTIPLE STREAM f fT EICTE R A & 5 CON 3INED , I l C-F REACTOIt EATLR FPOSt .k SKD?iR SYSTEM 151-36 .
! BEW11-8"HE UT 29 29 29 8 2 7 EL 1037' REACTOR SIDG SINCLE STREAM l 3 $WIP1MER TANK i
- C-F MAIN STEAM EQUAL 121Nr E1.APf R g$1 40 l C-F PS 30-18"ED R UT 2' 21 21 6 2 10 I AL 940' P90!STURE SE"RTR SI'WLE STEEAM (21) -
(1978 BASELINE) u2 j L* 10" IRYP LEC IT 2 2 2 2 - - 4 (2) - (1978 EASFLINE) . . i 'l I q .. i
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ll h., e i t Nnirff!ERN STAILS IWTR (D. TABLE, 2.2.5 l rewrricE1.f>1 tTNIT 1 3 PAGE 1 0F 7 l TIN YEAR INITTNAL IN9TLTION SMuRY ' f i NUOR ITfM: PIPINt: - INTECRA1,LY WFIJ1FD SITPPORTS f* LXNI . OMUaNr OR SYSTIN, AL11.S. M CATE- AND DE50tIITION 01: NDE W TAL ggty; 40 YR. 10 YR. THIRD TH I RI) ID PERIOD m M TION ' RIMVtKS GnRY ITIN M PE EXAMINill UN IN ITDE AMJNT AMfE , AWN eft f I. C2.5 C-E-1 I?TTTCRALLY WEIDED SUPPORTS I i l C-E-1 MAIN STEAM A POISTURE SEPERATOR RfMM ISI-26 4 PSI-18"ED S I I 100% PER I i 100 EL 938 @ MS STOP val,VE INTERVAL MAIN STEAM B ISI-27 e PS2-18"ED S 1 1 100% PER - - - EL 938' M MS STOP VALVE ' *. + l INTERVAL
- MAIN S1 TAM C '
ISI-28' PS3-18"ED S I ! 100% PER - - - EL 936' @ MS STOP VALVE ItTIT RVAL MAIN STEAM D 151-29 ' 4' PS4-1R"ED [ S 1 1 1001 PER - - - EL 938' @ MS STOP VALVE MULTIPlz STREAMS [NTERVAL 18" LINES C(EBINED 4 C-E-1 SUPPLY TO STEAM SEAL SYSTEM 151-30 ! PS14-6"ED 5 I I 1001 PER I - EL 940" (8 PS 4-18"ED MULTIPIE STREAM INTERVAL (SINCtz ITEM) C-E-1 HICH PRESSURE COOLANT ; INJECTION - WATER SII1E TW3-12"ED S 4 4 1001 ITR INTE!! VAL 4 1 25 EL 915' HPCI PLMP ROOM 151-31 EL 926' TORUS CHAMMER SINGli STREAM I C-E-l HfCH PRESSURE Coot. ANT INJECTION - STEAM SIfE PS18-8"ED S 2 2 1001 PER 2 - - EL 045' STEAM OfASE 151-32 ( INTE RVAL EL 906" TORUS CHAMBER S!!Cl2 STREAM r f e. g C-E-l Hf'CI - STEAM DISCMAPLE ^ 4 .. .: NS2-16"IfE 2 1001 PER
]{
,o S 2 INTE RVAL 2 1 50 EL 920' HPCI PtMP RonM 151-33
' " 5I! ELE STEAM a C-E-l CORE JPRAY A TW7- 8"E D $ 2 2 1 - - EL 978 RWCif POOM ISI-34 TW7-10"CE S 3 3 1001 PER 2 1 50 EL 927 TogUS C!lAMRER MrTSTIFIE STREAM INTE. AL 4 7 i
. , _ . _ . - . . _ , . - - _ . _ , . . _ _ _ _ _ _. . . _ . , . , . . , . _ . _ . _ . . , . . _ , . . - . _ , , _ . . . _ . _ , . . , - _ _ _. _a.,_,_.._
s Nrgr!11ERN STATES PtwER (D. TABLE- 2.2.5 nviticEup imtT I PN2i 2 OF 7
, T13 iTAR I?ilTEVAL INSPFLTION SMt\RY 2
4t10R TIIM: PIPING - INTECRAlfX WEIMf' SUPPORTS 1 L1.Vt O M Us1AT OR SYSR N N1L5- Tit!RD THIRD SIIB ('ATli- AND !)LeculTION CF i E MAL IBII. 40 YR. 10 YR. In!OD PERion IDCATICN - RIMtRKS UTM m gnM m g wh73 E!1tI6 ITDts gnx; AMotwr AMotnrr Anwr er r>rtm ' C2,5 C-E-1 (CONTINIED) l CORE SPRAY B Twit-a sn s norm - TW11-10*tE 5 1 1 100% PER - - - EL 950 REACTOR BUG - ISI-35 IfirERVAL MUI.TIPIE STREAM CORE SPRAY A & B CtMBINED' C-E-1 REACrOR WATER FRDffr - SKIMMER SYSTEM ) j . REW ll-8"lE S 5 5 100% PER S 2 40 EL 1005' O SKIMMER TANK 151-36 i I!trERVAL EL 998' REACTOR BUG SINCII STREAM i
- C-E-1 PHR SERVICE WATER 'r b
W SW9-8T,E S 2 2 1007. PER 2 - - EL 928 AUX BU C 151-39 i m RvAt EL 920 Aux suc siscts STREAM 4 4 7 1 i i i )
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i s I MWl1ERN ST1TTS TW1:R (I). ' TAB 11- 2.2.6 I MWTICELLO 131T 1 ilN Y1M IN111TAL 1NSP!CI!(W S1f f t%T i 4 I
. MUCR IlT}f: PIPINC - SLTPORT COMPONENTS I i
i IMI (19541A1 (E .Shll}i, M Ls- THIP.D MIG QE- AND I4KRIlil(W OF hTE WAL IBin 40 YR. 10 YR. pgpgm PERIOD G%T Ill}f TD PE l'XAMINT31 6 516 ITi}M A M;NT IMTICN RII M Ill}ti AMOUtTT AMOL'NT PERCINT I < a C2.6 C-E-2 HICH PRESSURE C001 ANT h INJECTION - WATER SIDE 1 151-31 SINGLE STREAM i tv3-12"ED V 9 9 100% PER 9 3 33 EL 926' TORUS CHAMBER INTERVAL #% C-F-2 HICH PRESSUM COOLANT EL 915'TORL'S . ROOM .i' INJECTION - STEAM SIDE 151 INLET- l , PS18-8"ED V 13 13 100% PER 11 4 31 EL 943' STEAM CHASE INTERVAL EL 949' EL 906' HFCI P GP FOOM EL 905' HPCI PUMP IELET 4 i C-E-2 HIGH PRESSITRE COOLANT
~ ISI DISCHARCE l INJECTION - STEAM DISCH.
SINCLE STREAM i j RS2-16"HE V 6 6 100% PFH 6 2 33 EL 905' HPCI P mP ROOM INTIFVAL @ DISCHARGE C-E-2 CORE SPRAY A & B 151-34 & 151-35
" MULTIPLE STREAM ; TW7-10"CE A V 3 3 100t PER 2 25 1 EL 955' REACTOR BLDG TW11-8"GE B V 4 4 INTERVAL I 2 - -
1 CORE SPRAY A & B i 151-34 & 1S1-35 MULTIPLE S1 REAM - TW 7- 8"ED A V 1 1 100% FER 2 - - CCRE St We I TW 1-8"ED B V 2 2 INTERVAL 50 EL 971' REACTOR BLDG 1 A & B COMBINED
! C-E-2 REACTOR WATER TROM SI-36 .
SKI?979 SYSTTM a SIW LE STF.EAM
, RTV11-8"HE V 4 4 100*5 PFR 4 25 1 FL 998' EEACTOR BLDC i 1NTEPVAL :! SRIMMER. TANK uy C-E-2 CONTAINMENT PUFCE A ISt-3M 4 4 "E
T CPI-18"EF V 2 2 100I PER I 100 FL 925' TORR 5 CHAMBER STLTIFIE 'IRf AM 2E INTERVAL 1 { (ATOP) I CONTAlf: MENT Pt:kCE B ISI-3fB
' TIT IPLE S T FE AM CP2-18"HE V N' WE -
100* PFR - - - EL 9 76' RWCit @ PENET.25 l'tECT LINE8 i'ri'wr % tN = I'
I
.- ~.. ,
5 4 l I I i NnR11!!KN STATTS 1%1R (T). TABtE 2.2.6 Mr*T: Cell 0 UNIT 1 '
.I i
11N ri.W INlllML INSPIITION Siff th :
- PN:E 3 0F 3 MMOR ITI)t: PIPINC - SITPPORT COMPONENTS -i 11V1 )
Of-StNNI Olt SYS11}f, NOA- THIRD ! CATE- ME IUTAL' THIRD AND ff5CRIPTitN G. ypg 40 YR. 10 YR. ' IIDI CORY ITT}t 1Y) BE 11V4fNT'D ntCIllTE IIDS AMrtNT Amt:NT Pf3tIO() PERLnD LOCATION RDt\RKS ITT16 Amt:NT PERCENT C2.6 C-E-2 (CONTINLTD) 5 C-E-2 RHR SERVICE VATER 4 SW9-8"CE V 15 15 1001 PER 4 15 26 EL 920 REACTOR BLDG ISI-39 INTERVAL EL 9 31 SINCLE STFEAM .i
- C-E-2 MAIN STEAM EQUALIZING
, HEADER '
. [,
P510-18"EDB V 3 3 100% PER l 3 1 33 EL 940' MOISTERE 151-40 i INTERVAL SEPARATOR FOOM SINCLE STEEAM
' I, I
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- 2. .!
)
NnF".11IM STATIS in1R (1). TABLE 2.3 6
?ONT f rELIJ) t'MIT 1
' PVT 1 OF I - U7. YFAH INTFHVAL INSITCTION S79tEY j MMOR I1TM: PtHPS I - i a va mamm (v sysnu, .v u.s- Turun une s M GTE- M N- 40 YR. 10 YR. 4 AND DISCRIPTION OF IBII PERIOD PERion li n TION RIMGKS I i ITIM g; $'Y IllM 10 BE EXAMINED UN ITI M A'KUtn APRONT ITi m AnuwT Prream . i -- t i C3.1 C-C PtHPS - RDtARKS - - - - - -' THERE ARE NO ITEMS WITH SEAMED CASINGS, C 3.1 C-F PtMP CASING WLDS - R C1 ARKS - - - - - - C3.2 C-D PRESSYTRF PETAINTNr: BOLTING , t !. HIGH PRES $URE COOLANT 151-32 ' AND ISI-33 I INJECTION RELIFF REQt'EST No. 24 i I. C-D HPCI PLMP TURBINE V REMARKS - 100% PER 20 20 106 EL 906' HPCI PLHP Ro0M BOLTINC/ STUDS EK-
- CASING INTERVAL CEEDING l" DIAMETER
, UT - - 107, PER 2 (MIN) - - -TtrTALS- AS REyJ1 RED 1 INTERVAL ON PLMP DJRBINE ! CASING - l 03.3 C-E-1 idTFCRAIJ.Y WELDED StrPPORTS - REMAPJC5 -. - - - - - DIERE ARE NO ITEMS ) [ TINDER C3.3 - ALL WELDED SUFPORTS AT C2.5 *
. c 1.4 C-f'-2 SUPPORT CfMPf*FNTS -
P D1%K5 - - - - - - SUPPORT COMPONENTS LINDER C2.6 1 I 1 I l
<m r el I
'M n;.
e. I 4
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f l t .I t i t l NORTIERN STATES PNFR (D. TABtf 2.4 I nurICELIA 1 HIT I i PAGE 1 0F 1 1TN YEAR INTIlTAL INSPFCTION SIM1ARY MUOR ITIN: V AI.VE S DM OMWlAT OR SYSIIN, KLM-M CATE- AND DESCRIITION OF E IUTAI- 40 YR. 10 YR. 'I l 23rgan ITTM IPIE PERIOD ImTim MEYS ' t GWY ITIN 10 BE 13AMINED EN NU ITT75 ^!9N ANUW '*8CEff! mm l C4.1 C-G VALVE S - REMAggs - - - THERE ARE NO ITEMS i C4.1 WITH SEAN D r . C-F VAI.VE MODY WfES - REMARK! - - - - - - 1 e I I C4.2 C-D~ PRESSURE-RETAINING BOLTTNG i RELIFF REQtTST NO.24
- VAIVE BOLTING '
, SCHEDUIED BY VALVE : RAlltER titan BOLT l AMOUNT. MAIN STEAM - REMARK!; - - - - - - OUT OF CIASS 2 STOP VALVF. A V 1 1007. PE R 1 INTERVAL i i 100 MOISTITRE SEPERATOR ROOM MULTIPIE STREAM + PSI-18"ED UT - - - - EL 938' SV-1 151-26 t _ STOP VALVE B V I I - - - - EL 938' SV-2 151-27 j,. PS2-18"ED UT 10 7 FER 1 1 10 Irr!ERVAL STOP VALVE C ~V 1 EL 938' SV-3 1 - - - ISI-28
, PSI-18"ED ITT STOP VALVE D V i 1 - - - -
E L 9 38' SV-4 ISI-29 Ps4-18"ED UT BTPASS 1007.ITE l CottrROL VALVE - 1I V 1 1 INTE RV AL 1 1 100 EL 940' No.Il 151-30 5 OWrROL VALVE - 12 UT 1 1 10 7. PE R - - EL 940' NO.12 INTERVAL C4.3 C-E-1 INTFCRAI.f Y WIJWD SUPPORT 9 - FEMAPV: - - - - - - ALL WELDED SUFFORTS l AT C2.5 C4.4 C-F-? 51'PIORT cmHPretjr_rS, - REMARF' - - - - - -- SUPPORTS AT C2.5 l f .- 1 i ' I i l I i ! ,, - . . . - . .,.--._.-..--.- -.. - .-----.~ --. -.-,- - -.- _ - - -. --. --. - - . - - - . _ . - - - . . - - - - - . . . . --- . . . . .
ASPE Section XI Nondestructive Examination Program - Class 3 ASME Code Edition and Addenda: 1974 Edition through and including Summer 1975 Addenda Program Period: February 28, 1978 to June 30, 1981 (Third Inspection Period)- NOTES:
- 1. The classificationdiagrams* identify the systera that are required' for examination in' accordance with IWD-2000, i During period one and period two, these examinations ware not required, and no effort will be made to retrofit these examinations.
- 2. The scope of the inspection program for C1sss 3 components is based on the classification of the plant's inspection boundaries and exemptions as allowed for in IWD-2600 and IWD-5200. The inspection progr am will conforr to IWD-2400 (Inspection Schedule), and will begin with period three of the first inspection interval.
- 3. Visual examination will be conducted for evidence of camp ment leakage, structural distress, or corrosion when the system is undergoing either a system inservice test, component functional test, or a system pressure test.
- 4. Supports and hangers for camponents will be visually examined to detect any loss of support capability or
- y evidence of inadequate restraint.
i io 5, Repairs will be performed in accordance with the applicable requirements of the latest edition and addenda of the ASME Code, Section XI. Ilowever, if rules for a particular repair are not specified in Section XI, the original design specification and Construction Code of the component or system, or later editions of the Construction Code or ASME Code Section III, either in their encirety or portions thereof, may be used. LEGEND Inspection Period ONE - June 30, 1971 to October 30, 1974 TWO - October 30, 1974 to February 28, 1978 TIIREE - February 28, 1978 to June 30, 1981
- Classification' diagrams are included in Section 6 of this report.
g - M N v * + - - - r v ,v p.,., y ..,we. . _ -i , , , , , , , . ___,, , , _ . . ,_,,_,,__u _g , ,s. , _ _ , , _, _ _ _______,____,,,,_, _ _ _ , _ _ , , _ , _ __ ____ _
m ARIE Section XI Pressure Testing Program ASME Code Edition and Addenda: 1974 Edition through and including Summer 1975 Addenda, y Program Period: February 28, 1978 to June 30, 1981 4 g
- a The system Quality Group boundaries are shown on the rigures in Section 6.
- These figures do not include small instrument, leak test, vent and drain lines. *o r*
h m APPLICABLE A9fE TLST TEST CODE CLASS TYPE RTOJFST FOR RELIEF h FPIQIIENCY g M Leakage Refueling 30 d 7
" 5 1
Ilydrostatic 10 years 30,36,38 s 8 2 Pressure 10 years E 30,31,36, 37,38 3 Pressure 10 years 30,36,37
.g.3 2 ,2 ,
a% 8 m
l SECTION 3 INSERVICE TESTING OF PUMPS AND VALVES A. Applicable ASME Code Edition and Addenda: 1974 Edition through and including Summer 1975 Addenda B. Program Period: October 28, 1979 to June 30, 1981 r. t Key for 3.C Pump Testing Table M = Monthly NR = Not required (constant speed drive or fixed resistance system) NA = Not applicable (sealed bearings) RR = See request for relief
, Key for 3.D Valve Testing Table Q = Quarterly NR = Not Required RR = See request for relief CSIQ = Cold Shutdown, not more often than quarterly.
IWV-3510 = In accordance with the requiretaents of paragraph IWV-3510. IWV-3610 - In accordance with the requirements of paragraph IWV-3610. Revision 4 3-1 7/27/79
-r t
i T k n C. Pump Testirg Applicable i ASE Code Pur:p Description Class Test Parameter Requests 'for Relief N Pi AP Q V b/. Tb 3 11 Emergency Service Water 3 NR RR RR RR M NA RR 2, 3 , 27 12 Emergency Service Water 3 NR RR RR RR M IM RR 2, 3 , 27
- 11 Standby Liquid Control 2 hR M M M M h TlUT 2, 3
~
12 Standby Liquid Control- 2 hR M M M M bi~ RR 2, 3 11 Core Spray 2 NR M M M M NA RR 2, 3 r 12 Core Spray 2 hR M M M M NA RR 2, 3 ; 11 Residual IIcat Removal 2 NR M M M M NA RR 2, 3 12 Residual lleat Removal 2 NR ll M M M NA RR Z, 3 13 Residual licat Removal 2 hR M M M M NA RR - 2, 3 14 Residual lleat Removal 2 hR Af M M M NA RR 2, 3 tf w 11 RIR Service Water 3 hR ETi RR M M NA RR 1,2,3 12 RIR Service Water 3 NR RR RR M M NA I:R 1, 2, 3 13 ElR Service Water 3 NR RR RR M M NA RR 1, 2, 3 14 RIR Service Water 3 NR RR RR M M NA RR 1, 2, 3 Iligh Pressure Coolant Injection 2 M M M M M M RR 2, 3 Reactor Core Isolation Cooling 2 M M M M M M RR 2, 3 fD "1 s O o _,---___-_m___-.__m -_- - _ _ - -___
D. Vrilve Terting 1 FSAPs Valve Valve Applicable ASMF Valve Test Request System Number No. Description Code Class Category Frequency Test For Relief Fhin Seenm A0 2-80A 80-A thin Steam Isolation 1 A Q Full Strcke-Time 28 Main Sten AD 2-80B 80-B Shin Steam isolation 1 A Q Full Stroke-Time 28 l Shin Seeam A0 2-80C 80-C Main Steam Isolation 1 A Q Full Stroke-Time 28 Main '" stenn A0 2-30D 80-D thin Steam Isolation 1 A Q Pull Stroke-Time 28 hhin Stean A0 2-86A 86-A __ thin Steam Isolation 1 A Q Full Stroke-Time 28 Fhin Steam A0 2-86B 86-B thin Steam Isolation 1 A Q Full Stroke-Time 28 bhin Steam A0 2-86C 86-C Shin Stean Isolation 1 - A Q Full Stroke-Time 26
' Shin Steam A0 2-86D 86-D bbin Steam Isolation 1 A Q Full Stroke-Time 28 T
Phin Steam 50-2373 74 Steamline Drain Isolatiori 1 A Q Full Stroke-Time 28 hhin Steam M0-2374 77 Steamline Drain Isolatior 1 A Q Full Stroke-lime 28 bhin Steam RV-2-71A RV-71-A Main Steam Safety Relief I C IhV-3510 Setpoint Bhin Steam RV-2-71B RV-71-B Main Steam Safety Relief 1 C IhV-3510 Setpoint -~ thin Steam RV 71C RV-71-C Main Steam Safety Relief 1 C IhV-3510 Setpoint Shin Steam RV-2-71D RV-71-D hhin Steam Safety Relief 1 C IhV-3510 Setpoint Fbin Steam RV-2-71E None Main Steam Safety Relief 1 C IhV-3510 Setpoint bb in ~ . , Steam RV-2-71F None Main Steam Safety Relief 1 C IhV-3510 Setpoint G* thin C( Steam RV-2-71G None Main Steam Safety Relief 1 C IhV-3510 Setpoint
- EP thin Steam FV-2-71II None Main Steam Safety Relief I C IhV-3510 Setpoint
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i i: % , i i I FSAR Valve Valve . Applicable ASME Valve. Test _ Request , System Number No. Description Code Class Category Frequency Test' For Relief i' FW FW 91-1 27B FW Inlet Check Valve 2 C RR RR' 7 1- 'i i 1 FW FW 91-2 27A FW Inlet Check Valve 2 C RR RR 7' i, . FW FW 94-1 96B Outboard Isolation 1 A, C RR RR 8 y :y
'FW FW 94-2 96A Ontboard Isolation 1 A, C RR RR 8 FW FW 97-1 28B Inboard Isolation 1 A, C 'RR RR 8-FN FW 97-2 28A~ Inboard Isolation 1 A, C RR RR 8
) FW FW 98-1 29B 'Feedwater Block Valve 1 E NR. Valve Lineup
'j_ FW FW 98-2 29A Feedwater Block Valve 1 E NR Valve' Lineup Recirc CV-2790 39 Rx Water Sample Isolaticn 2 A Q Full Stroke-Tine 10, 28 i .
j Recirc CV-2791 40 Rx Nater Sample Isolatico 2 A Q Full Stroke-Tine' 10, 28 Recirc FO-2-43/ 43A Recirc Suction 1 B CSIQ. Full Stroke-Tine 28 4 Recirc 50-2-431 , 43B Recirc Suction 1 B CSIQ Full Stroke-Tine 28 9-' 4 Recirc 50-2-53/. 53A Recirc Discharge 1 B CSIQ Full' Stroke-Tin e 28
.Recirc BO-2-53I 53B Recirc Discharge 1 B CSIQ Full Stroke-Tine. 2S
,_., Recirc 30-2-54/. 54A Recirc Disch. Bypass 1 is Q Full Stroke-Tine 28 ;
-D 7
' .3 ; Recirc FO-2 -54I 54B Recirc Disch. Bypass 1 B Q Full Stroke-Tine 28
'" E r Recirc PO-2-65/ 65B Recirc Loop Crosstic 1 B CSIQ Full Stroke-Tine '28-n
- j. Recirc 3D-2-651 . 65A Recirc Loop Crosstie 1 In CSIQ Full Stroke-Ti9 28.
1 i
i
),
L l 9
\
FSAR Valve Valve Applicable ASME Valve Test Request ' System Number No. Description Code Class Category Frequency Test For Relief i I' Recirc MO-2-66A 66B Recirc Crosstie Bypass 1 B 'CSIQ Full Stroke Tire 28- .! Recirc MO-2-660 66A Recirc Crosstie Bypass 1 B CSIQ Full Stroke-Tire 28 , Block Valve on [
- Recirc None Unner Seal Leakoff 2 B RR Full Stroke-Tine 5,28 l l Block Valve on t-g l Recirc Unper Seal Leakoff 2 -B RR Full Stroke-Tine 5,28 None i
i PJ R RV-1990 72A Pump Suction Relief 2 C IhV-3510 Setpoint i i- Rf R RV-1991 72B Ptznp Suction Relief 2 C IhV-3510 Setpoint RV-1992 72C Pump Suction Relief 2 C IhV-3510 Setpoint } PJ R to RV-1993 72D Pump Suction Relief 2 C IhV-3510 Setpoint
,4 _p lR I
RV-2004 35A Pump Discl Relief 2 C IhV-3510 Setpoint
- JJR .
pjR RV-2005 35B Pump Disch Relief 2 C IhV-3510 Setpoint None !!x Shell Side Relief 2 C IhV-3510 Setpoint JJR , PJ R None !!x Shell Side Relief 2 C IhV-3510 Setpoint i pj a AO-10-4M AO-46A LPCI loop Check 1 A, C CSIQ ' Exercise plR A0-10-40B AO-46B LPCI Loop Check 1 A, C CSIQ Exercise 4 _ pj m RIR-2-1 48A RiR Pump Discharge Check 2 C Q Exercise 33 RIR Ptunp Discharge Chect 2. C Q Exercise q; pj R RIR 2 48B ' o Exercise o PJ R RI R L ' 4EC PJR Pump Discharge Check 2 C Q w pjp RIR-2-4 48D RIR Pump Discharge Check 2 C Q Exercise
. _ . _ . . _ _ - _ _ _ . , _ . . . _ _ . . - _ . _ _ _ _ . _ , _ . , . . . ___ _ _ . _ . _ _ _ _ _ _ . _ . _ . _ - _ _ _ . _ _ _ . . . _ . , . _ _ . . . ~ . _ _ . ~ - -
- 4. &
! l
- i i -
FSAR Valve Valve Applicable ASME Valve Test Request .;
- System Number No. Description Code Class Category Frequency -Test For Relief' l PJ llead C1g Check 1 C RR RR 7 I IU R RIR-21 29 i- PJR Min Flow Check 2 C RR RR 7 RIR RIR-8-1 19A
?
- i l RIR 50-1986 30-13A Torus Suction 2 E NR Valve Lineup RIR 50-1987 FO-13B Torus Suction 2 E NR Valve Lineup ,e*
i RIR 50-1988 30-15A Shutdown C1g Suction 2- B CSIQ Full Stroke-Time 28 j RIR 50-1989 50-15B Shutdown C1g Suction 2 B CSIQ Full Stroke-Tima 28 , 9 IU R 50-2002 50-65A lix Bypass 2 E NR Valve Lineup ; l _ RIR 50-2003 50-65B !!x Bypass 2 E NR Valve Li . j u, , os 4 i RIR 50-2006 50-39A Disch to Torus 2 A Q Full Stafe-Time 28. : Disch to Torus 2 A Q Full Stron Lma 28 a i RIR 50-2007 FO-39B \ . i , RIR h0-2008 FO-34A Torus C1g Inlet 2 A Q Full Stroke-Time 28 t 1 i RIR h0-2009 FD-34B Torus C1g Inlet 2 A Q Full Stroke-Tima 28 ?
~
i RIR 50-2010 FO-38A Torus Spray 2 A Q Full Stroke-Tima 28 50-2011 FO-38B Torus Spray 2 A Q- Full Stroke-Tima 28 j l R!!R 4 R1m 50-2012 FO-27A LPCI Injection 2 B Q Full Stroke-Tim 3 28
~ 5' Full Stroke-Tim 28 31 RIR 3D-2013 }D-27B LPCI Injection' 2 B Q 3
- O" RIR 50-2014 FD-25A LPCI Injection 1 A -Q Full Stroke-Tim .
28 !*8 . ' u RIR 50-2015 FO-25B .LPCI Injection 1 A Q Full Stroke-Time 28 _ _ , . _ , _ , , _ . . , _ _ . , _ _ . . ,, . ~ , . , . _ _ . _ , . . _ , _ , - _ - . . - - - . , . . . _ . _ . _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ . _ _ _ _ . _ _ - _ _ - _ - _ . _ _ _ . _ _ . _ _ _ - _ _ _ . - . _
I
+
f a FSAR i Valve Valve Applicable ASME Valve Test Request ! j- System Ntznber No. Description Code Class Category Frequency Test For Relief ! t Cont Spray .i RI R ' KO-2020 FO-26A Outboard Isolation 2 A 0- Full Stroke-Tin e 28 Cont Spray i j R!R FO-2021 FO-26B Outboard Isolation- 2 A 0 Full Stroke-Tine 28- .[ j Cont Spray ; RIR 50-2022 hD-31A Inner Isolation 2 A 'O Full Stroke-Tine 28 % ! Cont Spray RIR 50-2023 50-31B Inner Isolation 2 A 0 Full Stroke-Tire 28 Full Stroke-Tire 28 i RIR FO-2026 50-33 Ilead Sprav Isolation 1 A CSIQ .! RIR CSIQ Full Stroke-Tire 28 j 4 hn-2027 B0-32 Head Sprav Isolation 1 A , RIR 50-2029 FO-18 Shutdown C1n Isolation 1 A CSIQ Full Stroke-Tire 28 , I ' RIR h0-17 Full Stroke-Tire 28 K0-2030 Shutdown C1n Isolation 1 A CS1Q RIR 50-2033 50-20 RIR Loop Crosstie 2 E NR Valve Lineup' Full Stroke-Tine i RIR 50-2032 50-57 Disch to Waste Surne 2 B Q 28 RIR CV-1994 CV-153A RIR hann ? tin Flow 2 B Q Full Stroke-Tire 28 28 Full Stroke-Tire ! RIR CV-1995 CV-153B RIR Ptsto Min Flow 2 B Q RJR CV-1996 CV-153C RIR hmm flin Flow 2 B Q Full Stroke-Tire 28 RIR CV-1997 CV-153D PJR Punn hiin Flow 2 B Q Full Stroke-Tire 28 > RIR RV-2025 44 licad Spray Line Relief 2 C 1hV-351r Setpoint RIR 19B RIR Blin Flow Check 2 C RR RR 7
}[ RI R- R- 2 RIR RI R-SW- 1 7 182- SW imerc Supply to RIR 2 C' RR RR 11 PIR RV-2031 40 RIR Shutdmm Clg Relief 2 C IhV-351'. Setpoint
4 l 6
- F i }
i i lFSAR Request . -i Vals. j Valve Applicable A9tE Valve Test Description Code Class Category Frequency Test For Reiicf System Ntaber ijlo. RIR RIR 1 81A R!R Imop Block 1 E NR Valve Lineup l 3 RIR RlR- 6-2 81B RIR Loop Block 1 E NR Valve Lineup l RIR RIR-1-1 152A RIR Ptnp Suction Block 2 E NR Valve Lineup MR RIR-1-2 152B RIR Pump Suction Block 2 E NR Valve Lineup i, RIR RIR-1-3 152C RIR Ptup Suction Block 2 E AR Valve Lineup RIR PJ R- 1-4 152D RlR Ptup Suction Block 2 E AR Valve Lineup I' PJR RIR-3-1 47A RIR P'mp Disch Block 2 E NR Valve Lineup RIR RIR- 3-2 47B RIR Pump Disch Block 2 E NR Valve Lineup l u i in NR Valve Lineup RIR RIR- 3-3 47C RIR Ptnp Disch Block 2 E
- RIR RIR-3-4 47D RIR Ptsp Disch Block 2 E NR Valve Lineup MR RIR- 18-1 30A CST to FJR Block 2 E NR Valve Lineup RIR RIR 2 30B CST to RIR Block 2 E NR Valve Lineup Core Exercise
- Jgay A0- 1.t - 13l A0 13A loop Inj . Check I A, C CSIQ Core AC CSIQ E.xercise Jpray AO-14-13H AO-13B Loop Ini. Check 1 _
u :o Core Ful1 St roke- Tim N n$ J gay 50-1753 BD- 12A __ Core Spray Inject ion 1 A Q
%C Core A Ful? St roke- Time 29 i.
Snrav T-1754 MO-12H Core Spray Injection 1 Q
.'$ E
" Corc
~
3 28 j
- Snrav 50-1751 FO-11A Core Spray Injection 2 11 O Full Strake- Timp I
~
Core Full Stroke-Time 28 I _Sprav !O-1752 ?U IIB Core Spray Inp etion 2_ B Q
4 ..
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i FSAR Valve Valve Applicable ASME Valve Test Request' ! j System Number No. Description Code Class Category Frequency Test For Relief . l [*, RV-1745 20A Disch Line Relief 2 C IhV-3510 Setpoint j Core ' i RV-1746 20B Disch Line Relief -2 C :IhV-3510 Setpoint 4 %. m. ! k ((. CS-9-1 10A Pump Disch' Check- 2 'C Q Exercise j ((1 CS-9-2 10B Pump Disch Check 2 C Q Exercise' a - t ! k[* , 50-1741 7A Core Spray Suction 2 B Q Full. Stroke-Tim: 28 Core , %y 50-1742 - 7B Core spray Suction 2 B Q Full Stroke-Tim: 28' [ E# CS-10-1 18A Min Flow Block 2 , E NR Valve Lineup. Y h((y CS-10-2 18B Min Flow Block 2 E NR Valve Lineup , ((y 50-1749 f.0-26A Test Line to Torus 2 B Q Full Stroke-Tim: 28 I h((y 50-1750 !O-26B Test Line to Torus 2 B Q Full Stroke-Tim 3 r 28 h((y ' CS-1-1 32A - Torus Suction Block 2 E NR Valve Lineup ! h((y CS-1-2 32B ' ' Torus Suction Block 2 E NR Valve Lineup [ h((y CS-13-1 14A Core Spray Block 1 E NR . Valve Lineup h((y CS-13 14B Core Spray Block 1 E NR Valve Lineup l hre , CS-3-1 8A CST Suction Block 2 E NR- Valve Lineup ((y CS-3-2. 8B CST Suction Block 2 E NR Valve Lineup ! ppm RV-205(- 66 Rel'icf Valve 3 C IhV-3510 Setpoint i HPCI HPCI-1E. 130 C1g Water Return Check 3 C Q Exercise I ' t
-- -i m n -wy..,-,-, ----..,a u,.mm..,-3y.,- ,,2 - w e ,.r.m ..w.--. .m..- .,-,.--e....-..*,-.: - . - - - . , - ..--m....sm_--U-__-___---___-------_ - --+-e---Eem - _--_ _ _- s - - > - +-
a FSAR Applicable AS!Ii Valve Test Request Valve Valve Systen FAnber No. Description Code Class _ Cyg Frequency Test FogRelief Q Full Stroke-1irr 28 IIPCI 50-2068 50-19 Pump Discharge Isol 2 11 A0-18 C1g Wtr Disch Check 2 C CSIQ Ilxercise
!KI A0-23-1F Full Stroke-Timc 28 IEI 50-2071 10-21 Test return to CST 2 11 Q It r, Fu11 Stroke- fin- 28 liPCI KO-2067 FO-20 Coolant Ptep Disch. 2 l'PCI CV-2065 41 Flin Flow Bypass 2 B Q Full Stinke-Tirx 28 RR RR 7 IIPCI IIPCI-42 62 blin Flow flypass Check 2 C ,
ID'CI RV-2064 34 Felief Valve 2 C IhV-3510 Setroint IIPCI-32 32 CST Suctiert Check 2 C Q lixercise [a llPCI B Q Full Stroke-Tire 28 IIPCI ?O-2063 FO-17 CST Suction 2 P, Full Stroke-Tire 28 ffPCI B0-2062 50-57 Torus Suction 2 Q C RR RR 7 HPCI liPCI-31 61 Tonts Suction Check 2 H Full Strole-Tine 28 _IU CI 50-2061 5 0 -58 Torus Suction 2 Q 33 Ptep Suctica Block 2 1: NR Valve Lineup I liPCI 15'CI - 33 Ful1 Stroke-Tit 'e 28 3[ me
!!NI 30-2034 50-15 Stcam Supplv Isolation i A Q DE IJ CI 30-2035 BO-16 Ste:un 01thoard Isolatiorl 1 1 o-Ftrll Stroko-Tine 28 i
,o p '
Full 4t role-Tine <8 r fiPCI 50-2036 50-14 Turbine Stean Supply 2 1; Q 10 Titrbine ! top Valve 2 B Q Full Strole 10
!!PCI 1D-7
!!PCI 10 8 fin Turbinet'ontrol Valve 2 B Q Full Stroke-Tine 28 y ,
& n ?q FSAR Valve Valve Applicable ASME Valve Test Request System Number No. Description Code Class Category Frequency Test For Relief Cooling Water
- IIPCI PCV-3492 PCV-50 Supply Cont. 2 B RR RR Cooling Water IIPCI IIPCI-20 131 , Return Oteck 2 C Q Exercise
!!PCI IIPCI-14 56 Ex. Line Drain Pot Check 2 A, C RR RR 7 f.h IIPCI IIPCI-15 45 Ex. Line Drain Pot Check 2- C RR RR 7' ilPCI IIPCI-9 65 Turbine Ex. Line Check 2 A, C Q Exercise.
IIPCI IE I-10 12 Ex. I,ine Stop Check 2 C Q Exercise ; IIPCI IIPCI- 65 None Vac. Ekr Check 2 C RR RR 7' T I!PCI LEI- 71 None Vac. Bkr Check 2 C RR RR 7 U llPCI PSD-2038 None Ex. Line Rupture Disc 2 D NR Full Stmke-Timc 28 RCIC MO-2096 MO-2096 Cooling Plater to Cond. 2 B Q RCIC- RV-2097 RV-2097 Relief Valve 3 C IhV-351C Setpoint- - RCIC RCIC-14 None Condenser Cond Pump Disc 1 2 C. Q Exercisc , Vac Pump Disch Check 2 C RR -RR 7 Og' RCIC RCIC-17 None w< A,C Exercise 3 RCIC RCIC-9 None Turbine Exhaust Check 2 Q S Exercise y RCIC RCIC-10 None- Steam Exh Stop Check 2 C Q-Vac Brkr Oteck 2 C RR RR 7 RCIC RCIC-57 None RCIC RCIC-59 None Vac Brkr Check 2 C RR RR 7' Pf!C PSD-2089 PSD-2089 Rupture Disc 2 D NR
i I FSAR Valve Valve Applicable A.9fE Valve Test Request Sntem N' ster ?b. Descriptio_n Cckle Class Ca t er.o=& rv,.. Frequency Test For Relief PCIC 50-2075 50-2075 Stean Simply isolation 1 A Q full sticle-Tim, 28-PCIC 50-2076 50-2076 Steam SurP l y Isolatic,n i A Q rull Stroke-Tint 28-PCIC h0-2078 FO-2078 Stean Supply to Turbine 2 B Q Full Stroke-Tim- ?8 TEIC RCIC-7 None Throttle Trip Valve 2 R Q Full Stroke 10 t Ef:IC 10 None RCIC Goveming 2 - B RR RR "CIC PCV-2092 ICV- 2092 Condenser Press Cont 2 It RR RR RCIC RCIC-16 None Vac hrtp Disch Check 2 A, C RR RR 7
; IPCIC 50-2100 FD-2100 Inboard Torus Suction 2 B Q Full St roke-Tirr 28 ,. I I
PCIC RCIC-31 None Check Valve to Torus 2 C RR RR 7 PCIC B0-2101 FD-2101 Outboard Tonis Suction 2 B Q Full Stroke-Tirr 28 PCIE RCIC-41 tione Check Valve to CST 2 C Q Exercise FCIC 50-2102 50-2102 CST Suction 2 B Q Full Stroke-Tirr 28
!CIC RV-2103 RV-2103 RCIC Suction I.ine Relict 2 C ThV-351f 9etpoint v nye _ _ _ _ . .___ __
PCIC CV-2104 CV-2104 h!in Flow iMuss 2 1: O Full Stroisc-Timt ?
".I UCIC RCIC-37 None !!in Flow Pvrass Check 2 C RPs RR "g _ .. _. . _ _
21 3 FCIC ?O-2106 50-2106 Pictp Discharyc 2 It Q Full St r ole-Tint 9 mg .
& RCIC FO-2107 FD-2107 Pump Discinrge 2 U Q Iull Stroke-Timr 28 RCIC A0-13 22 VL 13- 22 Pump Disci, Check 2 C CSIQ Exercise
.w w - - -
FSAR Valve Valve Applicable ASME Valve Test Request System Number No. Description Code Class Category Frequency Test For Relief Full Stroke-Time 28 PfIC B0-2110 50-2110 Test Retum to Cond Stor 2 B Q Pump Suction Block 2 E NR Valve Lineup RCIC PCIC-32 None Pump Disch Check 2 C Q Exercise SBIf XP-3-1 43A <8 Bxercise SBIf XP-3-2 43B Pump Disch Check 2 C Q A, C RR R 13 SELC XP-6 16 Outboard Isclation Check 1 A, C RR R 13 SELC XP-7 17 Inboard Isolation Check 1 SBIf RV-11-39A 39A Relief Valve 2 'C IhV-35103etpoint SBIf RV-11-39 'i 39B Relief Valve 2 C IhV-35105etpoint
'f U Explosive Actuated Valve 2 D IhV-3610\ctuation SELC 11-14A 14A SBlf 11-14B 14B Explosive Actuated Valve 2 D IhV-3610 Actuation SBlf XP-17 41 Suction from Test Tank 2 E NR /alve Lineup XP-20 None Suction licader Drain 2 E NR /alve Lineup SBLC _
I SBIf Rf- 56 None Demin Water to Suction 2 E NR /alve Lineco Test Line Retum 2 E NR /alve Lineup l SBIf XP-13 26 XP-11-1 Pump Discharge Drain 2 E NR /alve Lineup l SBif 34 l XP-38 None Poison Tank Drain 2 E NR Valve Lineup SRLC S SBIf XP-1 11 Poison Tank Outlet 2 E NR i. 'n Lineup ( SBIf XP-2-1 12A Pump Suction Block 2 E NR Valve Lineup
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FSAR Valve Valve Applicable ASME Valve Test Request System Number No. Description Code Class Category Frequency Test For Relief SELC XP-2-2 12B Pump Suction Block 2 E hR Valve Lineup SBLC XP-4-1 13A Pump Disch Block 2 E hR Valve Lineup SDLC XP-4-2 13B Pump Disch Block 2 E hR Valve Lineup Snif XP-5 15 Injection IIcader Block 2 E hR Valve Lineup SElf XP-8 18 Injection lleader Block 1 E hR Valve Lineup CRD CV-3-32A CV-32A Scram Disch Volume Vent 1 B Q Full Stroke-Time 28 CRD CV-3-32B CV-32B Scram Disch Volume Vent 1 B Q Full Stroke-Time 28 Y CRD CV-3-33 CV-33 Scram Disch Volume Drain 1 B Q Full Stroke-Time 28 l 7 scram Disch volume CRD RV-3-34 34 Relief Valve 2 C IhV-3510 Setpoint CRD CRD-114 114 Scram Riser Check 2 C RR RR 9 Accumulator Charging CRD CRD-115 115 Water Check 2 C RR RR 9 CRD CRD-138 138 Cooling Water Check 2 C RR RR 9 CRD CV-126 CV-126 Inlet Scram Valve 1 B RR RR 9 CRD CV-127 CV-127 Outlet Scram Valve 2 B RR RR 9 RIR SW CV-1728 CV-1728 R!lR SN Control Valve 3 3 B Q Full Stroke-Time 28 RIIR SW CV-1729 CV-1729 RIR SW Control Valve 3 B Q Full Stroke-Time' 28 RIIR-SW i RiiR-SW RIIR SW Pump EliR SW 1-1 1-1 Disch Check 3 C Q Exercise Rl[R-SW HliR-SW RIIR SW Pump RIIR SW 1-2 1-2 Disch Check 3 C Q Exercise
RHR-SU-4-2 RilR-SW-12 RHR-SW-14 h-, *[2 r, To RHR-SW-3-2 x"" A
\x RHR-SV-2-2 RilR -SW-1-2 '
y h 1
-RHR-SW-4-1 r
l d N 'N~ ~ 1 RHR-SW-1-4 4 RiiR-SW-8-1 +RIIR-SW-8-2 l RHR-SW-2-4 ; p 9_ D M -2 m f 4HR-SW-2-3 \ DemineralizedWater\- l.6 X jX X'X+ RnR-SW-2-1
-RIIR-SW-1-3 f
5 i ~
& xv;3203 I
+-- RH R-SW-1-1 C lC G-f -
[ _ a ___ g __ O O O BH-316-1 RHR Bil-316-2 RIIR Demineralized Water HX IIX CV-1728 CV-1729 up ( __ \ -- 3E:s _ci <3-D~
.C M s- RifR SERVICE WATER PUMPS To Circ Water Discharge Rl!R SERVICE WATER
.~
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FSAR I' Valve Valve Applicable ASME Valve' Test .. Request System Number No. ' Description Code Class Category Frequency- Test For Relief Emerg 7 Serv Wtr SW-103 None E.S.W..rheck Valve 3 C RR RR Energ Serv Ntr SW-104 None E.S.W. Check Valve 3 C RR RR 7 Emerg Serv Wtr ESW-1-1 ESW-1-1 Pumn Check Valve 3 C 0- Frercise Faerg. . .. Serv Wtr ESW-1-2 ESW-1-2 Pumn Check Valve 3 C. O Exercise Faerg , Serv Wtr SW-16 SW- 16 E.S.W. Check Valve 3 C RR- RR' 7 Emerg. Serv Wtr SW-18 SW-18 E.S.W. Check Valve 3 C RR RR' 7 Emerg Serv Wtr AV-3155 AV-3155 Pump Disch Air Vent 3 - C 0 Exercise
.- Emerg 1 lY Serv Wtr AV-3156 AV-3156 Pump Disch Air Vent 3 C 0 Exercise-K. Emerg-Serv Wtr ESW 1 ESW-3-1 Easket Strainer Bvpass 3 E NR Valve Lineun Fxterg Sertr Wtr .ESW-3-2 ESW-3-2 Easket Strainer Evpass 3 E NR Valve Lineup Primary Containm. A0-2377 None Cont. Purge Isolation 2 'A 0- Full Stroke-Tim y ,j Primry .
intainm. A0-2378 None Toms Purne Isolation 2 A 0 Full Stroke-Tim? '78 _ .~w Primary .M intainm. A0-2379 None Torus Vac Ekr Isolation 2 A 0 Full' Stroke-Tim y 28
- 3g Primary
*p lontainm. A0-2330 None- Torus Vac Ekr Isolation 2 A 0 Full Stroke-Time 28 3 Primary .
N :ontainm. A0-2381 'None Drywell Purge Isolation 2 A 0 Full Stroke-Time 28 Primary intainm. A0-2333 None Torus Vent Isolation 2 A 0 Full Stroke-Time 28
'rimarv ontaint. A0-2386 None Drvwell Vent Isolation 2 A 0 Full Stroke-Time 28 Trimary
- ontainm. A0-2387 None Drywell Vent Isolation 2 A O Full' Stroke-Timo 28
_ = _ .
.! FSAR Valve Valve Applicable ASME Valve Test Request For Relief System Number No. Description Code Class Category Frequency Test l Prima y Containm. AO-2896 None Torus Vent Isolation 2 A 0 Full Stroke-Time 28 Primary Sec Cont to Containm. DhV-8-1 None Torus Vac Ekr 2 A. C Q lxercise 33.
Prima y Sec Cont to Containm. DhV-8-2 None Torus Vac Tkr 2 A. ' C Q 1xercise' 33
#~'
Primary Centainm. CV-7436 None N, Ptsnpback Isolation 2 A RR m 12, 28 Primary Containm. CV-7437 None N,Pumpback Isolation 2 A RR m 12, 28 Primary Contaifim. CV-2384 None Torus Vent Isolation 2 A Q Full Stroke-Tim 28 Primary Containm. CV-2385 None Drywell Vent Isolation 2 A Q Full Stroke-Tim 28 I
.. Primarv
'Y' Contaiftm. CV-3267 None Torus N, Makeup Iso. 2 A Q Full Stroke-Tim 28 4 Primary Containm. CV-3268 None Drywell N2' Makeup Iso. 2 A Q Full Stroke-Tim 28 Primary Containm. CV-3269 None Cont N., Makcun Iso 2 A Q Full Stroke-Timr 28
~
Primary Containm. CV-3305 None Drywell 02 Analy Iso 2 A Q Full Stroke-Timc 28 Primary. Containm. CV-3306 None Drywell 07 Analy Iso 2 A Q Full Stroke-Timt 28 Primary , Containn. CV-3307 None Drywell 02 Analy Iso 2 A Q Full Stroke-Tint 28 l l Primary Containm. CV-3308 None Drvwell 02 Analy Iso 2 A Q Full Stroke-Time 28 C( Primary T0 Containm. CV-3309 None Drywell 03 Analy Iso 2 A Q Full Stroke-Timt 28
'%l Primary E Containn. CV- 3310 .None Drywell 02 Analy Iso 2 A Q Full Stroke-Time 28
, , Primary Containm. CV-3311 None Drywell 02 Analy Iso 2 A Q Full' St roke-Time 28 Primary Containn. CV-3312 None Drywell 02 Analy Iso 2 A Q Full Stroke-Time 28
t. FSAR Valve Valve Applicable ASME Valve Tet t Request System Number No. Description Code Class Categone Frequencf Test For Relief Primary
~
nntninn_ CV-3313 None Drvwell 0, Analv Iso 2 A 0 Full Stroke-Time 28
~
f'rimary
-nntainn CV-3314 None Dnvell 0, Analy Iso 2 A 0 Full Stroke-Time 28 Primary
~
nntninn_ CV-7440 None Torus to Drvwell N? Iso 2 A 0 Full Stroke-Time 28 j ,
- ond Serv lystem IN-58 None Drwell Demin Ktr Iso 2 A RR RR 12 1PCOV 50-1426 PD-1426 Drywell RFCCW 1 solation 2 A CSIC Full Stroke-Tim 3 28 1FCCW RPCC-15 None Drwell RPCCW Isolation 2 A. C RR RR 6 Thul !D-2397 50-2397 Pump Suction Isolation 1 A 0 Full Stroke-Time 28
[ 1hal 3D-2398 50-2393 Pump Suction Isolation 1 A 0 Full Stroke-Tiny 28 m .iquid Radwaste AD-2541A sone Drvwell Floor Drn Smp Iso 2 A O Full Stroke-Tim y 28
.iquid ladwaste A0-2541B None Drwell Floor Drn Smp Iso 2 A O Full Stroke-Tina 28
.iquid Radwaste A0-2561A None Drvwell Fauip Sump Iso 2 A Q Full Stroke-Time 28
.iquid bdwaste A0-2561B None Drywell Equip Sump Iso 2 A O Full Stroke-Time 28
~
Tuel Pool l
- In F. C1p PC-20-1 None Fuel Storage Pool Check 3 C RR RR 7 uel Pool
,3 ::In 5 C1p PC-20-2 None Fuel Storage Pool Check 3 C PR PR 7 3$ 'F1p C; (ir CV-1478 CV-1478 Dnvell Comp Air Iso 2 A CSIQ Full Stroke-Time 28
- EP
- omp (ir CV-7956 None Torus Inst Air Iso 2 A Q Full Stroke-Time 28
" :onp Tir AS-39 None Scrvice Air Iso 2 A PR RR 12
FSAR Valve Valve Applicable A9fE- Valve Test Request System Ninnber Ninnber Description Code Class Category Frequency Test- For Relief 71 11P isolation Full Stroke
'A Time 28,'10 TIP TIP 1-1 None Ball Valve 2 Q
#2 TIP Isolation Full Stroke A Time 28, 10 TIP' TIP 1-2 None Ball Valve 2 Q
#3 ~1iP Isolation Full StroKc.
Time 28, 10 TIP TIP 1-3 None Ball Valve' 2 A Q ..
#1 TIP Isolation IW (N TIP- TIP 2-1 None Shear Valve 2 D 3610 Actuation
#2 IIP Isolation IhV TIP TIP'2-2 None Shear Valvc 2 D 3610' Actuation
[ #3 IIP Isolatt T IW Actuation TIP TIP 2-3 None Shee- Valve 2" D 3610 llP System Y TIP- TIP 3 None Purge Check 2 A, C RR RR 26 5 Main Full Stroke Time 28 - Steam FCV-7682 FCV 27 Recombiner Steam Supply 2 B CS1Q Main Reactor IIcad Seal Full Stroke Steam CV-2369 17 Leak-Off Valve 2 B Q' Time 28 Main Reactor IIcad Seal Full Stroke Steam CV-2370 18 Leak-Off Valve 2 B Q Time 28 Main Reactor IIcad Full Stroke Steam CV-2371 20 Vent Valve 2 B Q Time- 28 Main Reactor IIcad Full Stroke Steam CV-2372 21 Vent Valve 2 B -Q Time 28
]s. '
RIIR RIIR-7 16 Crosstic Block 2 E NR Valve Lineup Pump Cooling IIPCI IIPCI-7 None Water Block 2 E NR Valve Lineup
~x
'Q$ Turbine Ishaust 2 C RR RR 7
'3O IIPCI !!PCI-60 ~None Vacinea Breaker
*Ew p-
FSAR Valve Valve Applicable AS3E Valve Test Request System Ntrber No. Description Code Class Category Frequency Test For Relief RX INST. X-27A None Excess Flow Geck- Valve 1 A, C RR RR 39 X-27B Excess Flow Check Valve A, C RR I RR 39 RX INST. None 1 A,C RR RR 39 RX INST. X-27C None Excess Flow Check Valve 1 RX INST. X-28A None Excess Flow Geck Valve 1 A, C l RR' 'RR 39 F*- RX INST. X-28B None' Excess Flow Geck Valve 1 A, C RR- RR 39 RX. INST. X-28C None Excess Flow Jieck Valve 1 A, C RR- RR 39 RX INST. X-28D None Excess Flow Check Valve 1 A, C RR RR 39 RX INST. X-28E None Excess Flow Geck Valve 1 A ,C RR RR 39 < IRX. INST. X-29A- None Excess Flow Geck Valve 1 A, C RR RR 39 RX INST. X-29B None Excess Flow Check Valve 1 A, C RR RR 39 - RX INST. X-29C None Excess Flow Check Valve 1 A,'C RR RR 39 RX. INST. X-29D None Excess Flow Check Valve 1 A, C RR RR 39
,RX INST. X-31A Mone Excess Flow Check Valve 1 A, C RR FR 39 >
RX INST. X-31B None Excess Flow' Check Valve 1 A, C ~ RR ' RR 39 RX INST. X-31D None Excess Flow Check Valve 1 A, C RR RR 39. RX INST. X-31E None Excess Flow Check Valve 1 A, C RR . RR 39 l
., y M;i RX INST. X- 31 F None Excess Flow Check Valve' 1 A, C RR RR 39 u l1 '
eg u
Valve Valve Applicable ASME Valve Test Request System Nwi>er 'No. Description Code Class Category Frequency Test For Relief Excess Flow Check Valve A, C RR RR 39 RX INST. X-32A None 1 A, C 39 RXINST.lX-32B None Excess Flow Check Valve 1 RR RR ; 1 RX INST. ;l X-32D None Excess Flow Check Valve l' A, C RR RR 39 t- RX INST. X-32E None Excess Flow Check Valve 1 A, C RR RR 39 RX INST. X-32F None Excess Flow Check Valve 1 A, C RR RR 39 RX INST. X 33A None Excess Flow Check Valve 1 A, . C RR RR 39 1 1 RX INST. X-33B None Excess Flow Check Valve 1 A, C RR RR 39 Y Z RX INST. X-33C None Excess Flow Check Valve 1 A, C RR RR- 39 RX INST. X-33D None Excess Flow Check Valve 1 A, C RR RR 39 RX INST. X-33E None Excess' Flow Check Valve 1 A, C RR . RR 39 RX INST. X-33F None Excess Flow Check Valve I A, C RR RR 39 RX INST. X-40A-it None Excess Flow Gleck Valve 1 A, C RR RR 39 RX INST. X-40A-I. None- Excess Flow Check Valve 1 A, C RR RR 39 _ RX INST. X-40A-C None Excess Flow' Check Valce 1 A, C- RR ER' 39 RX INST. X-40A-D None Excess Flow Check Valve 1 A, C RR -RR 39 RX INST. X-40A-li None Excess Flow Check Valve 1 A, C RR RR 39
- n RX INST. X-40A- : None Excess Flow Check Valve- 1 A,C- RR RR 39 nn-RX INST. X-40B-A None Excess Flow Check Valve 1 A,.C RR RR 39 0$
m
1
+
FSAR I Valve. Valve Applicable ASME Valve Test Request System Nurber No. Description Code Class Category Frequency Test For Relief A, C RR RR 39 RX INST. X-40B-B None Excess Flow Check Valve 1 A, C RR I RR- 39 RX INST. X-40B-C None Excess Flow Check Valve 1 i 1 A, C RR RR '39 RX INST. X-40B-D None i Excess Flow Check Valve 1 A, C RR RR 39 r 9-I RX INST. X-40B-E None Excess Flow Check Valve A, C RR RR 39 RX INST. X-40B-F None Excess Flow Check Valve 1 1 A, C RR RR 39 RX DST. X-40C-A None Excess Flow Check Valve 1 A, C RR RR 39 RX INST. X-40C-B None 1 Excess Flow Check Valve A, C RR- DR- 39 X-40C-C None Excess Flow Check Valve 1 - y RX INST. A, C RR RR 39 RX INST. X-40C-D None Excess Flow Check Valve 1 1 A, C RR RR 39 RX INST. X-40C-E ~.Jone._lExcessFlowCheckValve A, C -RR RR 39 PX INST. X-40C-F None Excess Flow Check Valve 1 1 A, C RR RR 39 RX INST. X-40D-A None Excess Flow Check Valve i A, C RR .RR 39 .._ RX INST. X-40D-B None Excess Flow Check Valve 1 A, C- RR RR 39 RX INST. X-40D-C None Excess Flow Check Valve I A, C RR RR. 39 RY IET. X-40D-D None Excess Flow Check Valve 1 A, C RR- ".R 39 ! RX INST. X-40D-E None Excess Flow Check Valve 1 1 A, C RR RR 39 RX INST. X-40D-F None Excess Flow Check Valve-ea :c t: 3ia LJ
. m ._-, -- . . - , , . , , . _ , - , - - . _ . . . . , - - . , , . - - - ... _ . , - . - , . , . - - -
- .m FSAR !
Valve Valve Applicable ASME Valve Test Request ! System Nurber No. Description Code Class Category frequency Test For Relief , RX INST. X-49A None Excess Flow Geck Valve 1 A, C RR RR 39 RX INST. X-49B None Excess Flow Check Valve 1 A, C RR l RR 39 RX INST. X-49C None Excess Flow Geck Valve 1 A, C RR- RR 39 RX INST. X-49D None Excess Flow Check Valve 1 A, C RR RR 39 (% RX INST. X-49E None Excess Flow Check Valve 1 A, C RR- RR 39 RX INST. X-49F None Excess Flow Check Valve 1 A, C RR- - RR' 39 RX INST. X-50A None Excess Flow Check Valve 1 A, C RR RR 39 RX INST. X-503 None Excess Flow Geck Valve 1 A, C RR- RR- 39 ' l RX INST. X-50C None Excess Flow Check Valve 1 A, C RR RR 39 RX INST. X-50D None lExcessFlowGeckValve 1 A, C RR RR 39 RX INST. X-51A None Excess Flow Check Valve 1 A, C RR RR 39 RX INST. ~X_51B None Excess Flow Check Valve 1 A, C RR RR 39 RX INST. X-51C Mone Excess Flow Check Valve 1 A, C RR RR 39 RX INST. X-51D None Excess Flow Check Valve 1 A, C - RR RR 39 RX INST. X-51E- None Excess Flow Check Valve 1 A, C RR RR 39 RX INST. X-51F None Excess Flow Check Valve 1 A, C RR RR 39 RX INST. X-52A None Excess Flow Check Valve- 1 A, C RR PR 39 2? - s . *? 3 l".
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M'bu , I . i [ I FSAR Valve Valve Applica' ale AS'E Valve Test Request i System Ntst,- No. Ikscription Code Class Category Frequency Test For Relief 4 RX INST. X-52B None Excess Flow Check Valve 1 A, C RR RR 39 RX INST. X-52C None Excess Flow Check Valve 1 A, C RR RR 39 i RX INST. X-52D None Excess Flow Check Valve 1 A, C RR 39 _RR RX INST. X-52E None Excess Flow Check Valve 1 A, C RR RR '39 85 RX INST. X-52F- None Excess Flow Check Valve 1 A, C RR Rr. 39 RX INST. X-28F None Excess Flow Check Valve 2 A, C RR RR 40 i i 9 . tl (-s w 4 i 1 %
- 90 *
- m<
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.. . . . . . . . . . -, , ,-. ..- . . - . . -.,-- _.... ,-.~~. ,-, -.
- 1. E REGJEST FOR RELIEF h
a v QNPCNDir IU CTION APPLICABLE A9fE CODE CLASS h<= 4 d
~g cw 11, 12, 13, 14 RIR es w Provide cooling water to the RIR 3 $ @
Service Water Ptunps heat exchangers, j r Code Requirement pE 8g 5 Inlet pressure and differential pressure will not be measured directly as required by IWP-3100 Mi5 and IWP-4213. Q8 Basis s-gg HQ There is no installed instnanentation for directly measuring the inlet pressure and differential 9 P1 pressure of these pumps These pumps are submerged and take suction several feet below the river level. "8 R C' U g< Alternate Testing s. M ,E The river level elevation will be measured to detemine the inlet pressure for these punps. _ Differential pressure will be detemined by taking the difference between the discharge pressure and calculated inlet pressure. Scheduled for Implementation February 28, 1978
h
- 2. Request for Relief 00Meir FUNCTION ;
APPLICABLE ASME CODE CLASS
- 11, 12 Emergency Provide cooling water to the emergency Service Water 3 diesel generators and critical reactor building equipment.
t 11, 12 Standby Provide a redundant means of reactor Liquid Control 2 shutdown as a backup to the Control ; Rod Drive System. 11, 12 Core Spray Provide cooling water to the reactor 2
- under emergency conditions.
i 11, 12, 13, 14 Provide cooling water to the reactor 2 f Residual ifeat and to containment under accident to Removal conditions. 11, 12, 13, 14 Provide cooling water to the RIR heat 3 RIR Service Water exchangers, Iligh Pressure Provide cooling water to the reactor 2 Coolant Injection under emergency conditions. Reactor Core Provide cooling water to the reactor 2 Isolation Cooling under emergency conditions. Code Requirement Pump bearing temperature will not be measured as required by IhP-3100 and IM'-4310. Basis
'Ihere is no instrumentation installed to measure lube oil or bearing temperature. The use of external temperature measuring devices is not considered meaningful because of the environmental influence on these parameters.
h
. 2.
RFUEST FOR RELIEF (Cont'd.) Altemate Testing
- The mechanical condition of the pump will be assessed by using vibration data.
Schedule for Implementation . Febmary 28, 1978 i e B
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_m _ . . . _ , . , _ . . . , _ . _ . _ . , . .. . . . _ . . - . . . . , _ . , . , . . . -
- 3. RTGJEST FOR RELIEF C04POWNr RRCfl0N APPLICABLE CODE CLASS 11, 12 Emergency Provide cooling water to the emergency 3 Service Water diesel generators and critical reactor Ptrips building equipment.
11, 12 Standby Provide a redundant means of reactor 2 Liquid Control shutdown as a backup to the Control Pumps Rod Drive System. 11, 12 Core Provide cooling water to the reactor - 2 Spray Pumps under emergency conditions. ' 11, 12, 13, 14 Provide cooling water to the reactor 2 Residual IIeat and to containment under accident Removal Punps conditions. c- 11, 12, 13, 14 Provide cooling water to the RIR heat 3 1- PJR Service exchangers. . Water Punps Ifigh Pressure Provide cooling water to the reactor 2 Cooling Injection under emergency conditions. Reactor Core Provide cooling water to the reactor 2 Isolation Cooling under emergency conditions.
- Code Requirement 4
Displacement vibration amplitude will not be used to evaluate the condition of the pump as required by Ih'P-3110, 3210, 4500, 4510. Basis We prefer to measure vibration velocity due to its superiority in detecting wear and interior machine failure. Existing instrumentation reads out in velocity units. Alternate Testing Vibration velocity measurements will be used to evaluate the condition of the punp. Schedule for Implementation February 28, 1978
- c. . t 64/5/1 g uois}Aa3 ,
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- 5. REQlEST FOR RELIEF Applicable Valve Component Function __
ASE Code Class ' Category Shutoff Recirc Ptrnp #11 Upper Seal 2 B Flow hhen Pump is Shutdown Chutoff Recirc Pump #12 Upper Seal Flow 2 P hhe Ptunp is Shutdown Code Requirement These valves cannot be tested at the frequency i m uired by IhV-3410 Basis
- - 'Ihese valves are located inside primary containment which has an inerted atmosphere. The only way to In verify valve stroke and measure stroke time is by direct observation of the valve ste.m.
Alternate Testing These valves will be full stroked and timed during each refueling outage when the Containment is de-inerted- , and open for general access. Schedule for Implementation February 28, 1978
t
- 6. Request for Relief Applicable Valve ,
Component Function ASE Code Class Category i RBCC-15 To provide containment isolation for the 2 A, C , React or Ikzilding Closed Cooling water drywell inlet line. Code Requirement This valve will not be exercised as required by IhV-3520. Basis There are no means provided for determining that the disc travels to the seat promptly on cessation c, - or reversal of flow. y Alternate Testing This line will be modified upon concurrence of the NRC to allow leak testing of this valve (see letter from L. O. Mayer to Victor Stello, subject, " Planned Modifications to Permit Testing to be Conducted in.Accordance with 10CFR50, Appendix J", dated May 5, 1976). Proper seating of the valve disc will be verified during the leak rate test. Schedule for Implementation See Alternate Testing. E a.m -, _ 3 , -, ,--,.- - ---. . , . - - - - + - , , _
- 7. RI1QIEST FOR RELIEF Applicable A9fE Valve .
Component Function Code Class Category w i
- SW-101 Prevent flow of emergency service water 3 C SW-102 int the nonnal service water systm 3 C when the emergency service water system -
SW-103 is operating. 3 C SW-104 3 C 1 ESW-4-1 Prevent reversal of flow into redundant 3 C ESW-4-2 mergency service water line. 3 C FW-91-1 Prevent reversal of flow into the 2 C FW-91-2 feedwater system. 2 C R!R 8-1 Prevent reversal of flow into PJR 2 C p;g g_y Pump Discharge Line. 2 C IufR-21 Prevent reversal of flow into IIend 1 C (boling line IIPCI-14 Prevent reversal of flow from 2 C IIPCI-15 Torus into IIPCI System. 2 C IIPCI-42 2 C IIPCI-31 Prevent reversal of flow from IIPCI Systen 2 C into Torus. l IIPCI-65 Prevent IIPCI Exhaust Steam flow to 2 C ggy_y Torus Air Space. 2 C u :n RCIC-57 Prevent RCIC exhaust steam flow to 2 C h RCIC-59 Torus Air Space. 2 C s. OE RCIC.37 Prevent Reversal of Flow from the 2 C u RCIC-16 Torus Into the RCIC System. ~ 2 C RCIC-17 2 C RCIC-31 Prevent Reversal Flow of'PCIC Flow 2 C to Torus.
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- 7. RIRUEST IUR RELIEF (Cont'd.)
Applicable ASME Valve Component Function Code Class Category SW-21-1 Prevent Reversal of Nomal Cooling 3 C SW-21-2 Flow Into the Service Water System. 3 C SW-16 Prevent Reversal of Flow From 3 C SW-18 FNgency Mce Water Systm 3 C Into Service Water System.
-w PC-20-1 Prevent siphoning of Water From 3 C PC-20-2 Fuel Storage Pool Into Fuel Pool 3 C Cleanup System.
HPCI-60 Turbine Steam Exhaust Vac Brkr 2 C Code Requirement y These valves will not be tested as required by IhV-3520. Basis There is no means available to verify that the disc travels promptly to the seat on cessation or reversal of flow for normally open valves or that the disc raoves promptly away from the seat when the closing differential is removed and flow through the valve is initiated for nomally closed valves. Alternate Testing -- l The systems in which these valves are located will be functionally tested on a periodic basis to demonstrate proper operation. C g' Schedule For Implementation 25 0E NA 8 m b
- 8. REQUEST IUR RELIEF Applicable ASME Valve Component Function Code Class Category W 94-1 1 A, C W 94-2 To pmvide containment isolation for 1 A, C the feedwater injection lines.
W 97-1 1 A, C W 97-2 1 A, C Code Requirement These valves will not be exercised as required by IhV-3520. R1 sis [ o There are three check valves in series in each of the feedwater injection lines. Verification that each valve disc travels to the seat promptly on cessation of flow cannot be completed by observing pressure indications. The valves cannot be directly observed and there is no instrumentation installed to monitor disc position. Alternate Testing Proper seating of the valve disc will be verified during the valve leak rate testing. 1 Schedule for Impicmentation February 28, 1978
- 9. PIQUEST IUR RELIEF Applicable ASE Valve-
_ Component Function Code Class Category-CRD-114 Prevent scram discharge flow frm '2 -C-flowing back.into.the CRD during a scram. CRD-115 Prevent scram accunulator pressure 2 C from discharging into CRD accumulator charging water circuit during a scram. CRD-138- Prevent scram accumulator pressure from 2 C discharging into CRD cooling water circuit during a scram. CV-126 Provide scram accumulator pressure 1 B to the bottom of the control rod . i drive piston during a-scram. ! Exhaust scram discharge water from CV-127 -2 B f- the top of the control rod drive I y piston during.a scram. Code Requirement These valves will not be tested as required by IhV-3410 and IhV-3520. Basis
.The above listed valves are located on each of the 121 hydraulic control units', 'Ihere is no practical method of testing these valves. in accordance with Section XI requirements. .There-is no instrumentation installed to verify proper seating of the check valves and the control valves operate too rapidly to measure stroke time. Technical Specifications require all control rods to be scram tested once per operating cycle. These valves are all exercised one full cycle during a scram. Proper operation of these valves and the safety function of the control rod drive system are verified by the scram testing.
Alternate Testing See Basis Schedule For Impicmentation-February 28, 1978
- 10. Rrf3IEST FOR RELIEF Applicable ASME Valve Comnonent Function Code Class- ,
Category , 10-7 Imediately stop the steam flow to the 2- B IIPCI Turbine. RCIC-7 Immediately stop the steam flow to the 2 B t PLIC Turbine. Drywell Isolation for reactor water sample 2 A CV-2790 line from recirculation Loop B. 2 A CV-2791 , 2 A TIP 1-1 Drywell isolation for_ TIP System. 2 A TIP 1-2
.2 A C TIP 1-3 Code Requirment These valves will not be stroke timed as required by IhV-3410.
Basis "Ihese valves operate too fest to obtain meaningful stroke time. Alternate Testing R 5' These valves will be full stroked as required by IhV-3410 and proper operation will be verified.
$1 Schedule for Imp 1 mentation
- February 28, 1978
i l- - . r 4 - i
- 11. REQLIFSr FOR RELIEF !
s } I t
-Y h
! Component
' Applicable ASME Valve }
Function Code Class Category ; 1
- RIR SW-17 Prevent reversal of flow of RIR water 2- C' -l
- - Into RIR Service Water' System. I i .l I
Code Requirement This valve cannot be exercised as required by IW-3520 .: Basis i Exercising of this valve would require ptsaping river water into the RIR System. ' l' - 7' ' Alternate Testing I W 1, . ' None ; i Schedule for Implementation- - ; .1 f NA .!
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l ' F t 1 r ! [
- .i 6
.. i 4
I f
, , , , , . _ . , . ...-_,.r,,-,-..--_,., e_,--,..,_ , ~ ,- - .,. , . :..-.---.,..~.,,-....,-,._..vs,.m.,-__,.-..__e,-m- . . . . , -,,;.,.. , , . - - ,,.. -... , - ,... -,m,.-,-m..-,_.- .---i-
- 12. REQUEST FOR RELIEF T
Applicable ASIE Valve Component Function Code Class Category Rf-58 Shutoff demineralized water to drywell. 2 A AS-39 Shutoff service air to drywell. 2 A CV-7436 2 A Drywell Isolation for N2 pmpback CV-7437 system. 2 A Code Requirement
? These valves will not be tested as required by IhV-3410.
5 Basis These valves are located in systems or portions of systems that are presently out of. service. They will be tested as required by IhV-3410(f). Alternate Testing See Basis Schedule For Imp 1 mentation May 31, 1978
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- 13. REQUEST IOR RELIEF Applicable it9fE Valve Component Function Code Class Category XP-6 Prevent reversal of flow of reactor 1 A, C p,7 water into SBLC System.
1 A, C Code Requirement These valves will not be exercised at the frequency required by IhV-3520. Basis Exercising of these valves can only be accomplished by initiation of the SML System, including actuation of an explosive valve, and pumping to the reactor vessel. Alternate Testing [ m These valves will be exercised by initiation of the SNL System, actuating an explosive valve and pumping demineralized water to the reactor vessel during each refueling outage. Schedule For Implementation February 28, 1978
d 64/s/1 91 - t' i g uo} sir.3 N k 1 . W M 4 O c c+ ~1 Q' / i m '" T M 0 X i . ! t~ m m i 1 e i e Y d o 1 0 l 1 1 1 l J i j 8 l
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- 4 .
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- 15. REQUEST FOR RELIEF CONPONENT CODE EIAM CIASS TABLE ITEM CATEGORY REACTOR VESSEL
- 1) Longitudinal and Circumferential Welds in Core Region 1 1.1 Bl.1 B-A
- 2) Zengitudinal and Circumferential Welds in Shell (other than 1 1.1 Bl.2 B-B B-A and B-C) and Meridinal Welds in Bottom Head: l VIAA-1 &-2, VCBB-1 6-3, and IDRB-1 through -10
- 3) Nozzle-to-Vessel Welds and Inside Radius: Standby Liquid 1 1.1 Bl.4 B-D Control CPAD-1 CODE REQUIREMENTS 7
- 1) and 2) Volumetric examination of 107. of each longitudinal weld and 57. of each circumferential weld
- will not be performed as required by Exam Category B-A and B-B.
N
- 3) Volumetric examination of nozzle-to-vessel weld and inside radius will not be performed as required by Exam Category B-D, however, an attempt will be made to volu:netrically examine this weld and the inside radius to the extent possible.
BASIS The design of the reactor internals and the external biological shield and vessel insulatio a prevents both internal and external access to these welds. It should be noted that the Monticello reactor vessel was fabricated and subjected to as-built inspection under very demanding specifications. Because the site was inaccessible to a' river barge of the capacity necessary to transport a fully assembled vessel, the vessel was ) assembled at the site from shop-fabricated subassemblies. All requirements of Section III of the ASME Boiler and Pressure Vessel Code, 1965 Edition, including Addenda through Summer 1966, were satisfied just as if the vessel were shop fabricated. In addition, additional requirenents more stringent than those required by the ay Code were applied by General Electric due to the unique circumstances surrounding the vessel fabrication. u< Refer to Volume VII of the Monticello Final Safety Analysis Report, " Reactor Pressure Vessel Desigu kport," 33 for details concerning vessel fabrication and inspection. In addition, it should be noted that base" on mo analysis of the dosimeter removed from the reactor vessel, the maxinrm neutron fluence level at T/4 of the reactor vessel wall will be only 1.23 x 1018nyt at the end of designed life (40 years). Based on the high quality level established for vessel fabrication and the relative low neutron fluence level at the vess " 'l vall, the inability to examine these welds is not considered to have any significant decrease in safety.
-~
15 Pr'ET FOR PILIPS (continued) , ALTERNAIT As the result of their inaccessibility, no examinations will be performed on these welds, other than the vessel pressure tests, and in the case of CPAD-1, examination will be to the extent possible. l SCHEDULE FOR IMPID9NTATION February 28, 1978 ~? ,2 < a TA C o e
, . . ..- ~-,, - - - , , -. . , . . - - --
- 16. RH)UEST FOR RELIEF ,
COMPONENT CODE EXAM CIASS TABLE ITEM CATECORY . REACTOR VESSEL
- 1) Iongitudinal and Circumferential Welds in Shell: VLCB-1, 1 1.1 Bl.2 B-B VIEB-2, VLBA-1, VLBA-2, and VCBB-4 l
- 2) Integrally Welded vessel Stabilizer Lugs 1 1.1 Bl.12 B-H CODE RIT)UIREEhr
- 1) Volumetric examination of 107, of each longitudinal veld and 57 of each circumferential weld will not be performed as required by Exam Category B-B.
y
- 2) Volumetric examination of the vessel stabilizer lugs will not be performed as required by Exam Category B-H.
BASIS The design of the biological shield and vessel insulation prevents external access to these welds. Internal access is available but surface preparation of the vessel cladding would be required to provide dependable ultrasonic results. Approximately 20 ft of2 cladding would need to be ground to pennit the above examinations. Our experience indicates that even after hydro lancing the vessel wall, and the use of a concrete plug over the core and lead blankets on the wall for shielding, we could still expect personnel exposure to be in the 600-700 mr/hr range. Based on the high quality level of the Monticello vessel and the relatively low neutron fluence level that the vessel wall will see during its service life (refer to Request for Relief No. 15), we do not believe that exposure to personnel is warranted for the preparation and the performance of these examinations. Especially, i since there are vessel velds at much higher stress levels (such as the vessel and head flange welds, nozzle ~RE welds, and head welds) that are being examined at greater frequencg and, thus, their examination results should previde a sufficient means to measure the maintenance of vdshel integrity. 'E$
,DE It should also be noted that for the integrally welded stabilizer lugs (Item 2), they are part of a mechanical *$ snubber system for seismic loading and have no support function. Therefore, the examination of these lug welds is probably not within the scope of Section XI inservice inspection requirements. - - . - __. - - . - ~
1 1 . V:, j
~
- 16. PMUECT FOR RELIEF (continued) .
ALTDtNATE As the result of their inaccessibility, no exactinations will be performed on these welds, other than the
- vessel pressure tests. However, an attempt will be made to examine the lug welds to the extent 'possible i
4 with a surface method.
- SCHEDULE FOR IMPLDfENTATION
.i l February 28, 1978- , 4 h i k 9 t.- 10 l l t
+
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j ! I j . 1 .i I 17. RIKlUE3T FOIt RELTU k 1
.I
- i CODE EXAM -
- COMPONENT CIASS . TABLE ITEM CATECORY i
1 j VESSEL PENE'11tATIONS i
'f
, Control Rod Drive and Bott e Head Drain 1 1.1 -31.5 B-E I i i i i y CODE RIK)UIREBENT The area surrounding each penetration cannot be visually exmined for evidence of leakage during' the vessel j pressure test as required by Exam Category B-E. l BASIS '
- r lh j
The design of :he vessel, the biological shield, and vessel insulation prevents access to' these areas that are directly adjacent to the vessel penetrations. l j AIMMAR 1 - l The areas below these penetrations will be visually examined for evidence' of leakage during' the vessel ) pressure test.which will have a hold time of 4 hours. l i SCHEDUIE FOR IWIDE!NTATION 1 i February 28, 1978 4 ! i i i i sca*,c . 1
- u<
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*hJ P CD O U .f t #
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i .
- 18. PlDUEST EDR RELIEF CODE EXAM COMPCNET CIASS TABIE ITEM CATECORY REACTOR VESSEL Closure Head Flange Leakage Sensors (Nozzle N-13 and N-14) 1 1.1 Bl.5 B-E l
CODE REQUIRDENT The area surrounding these two penetrations will not be visually exmined for evidence of leakage during the vessel pressure test as required by Exm Category B-E. . BASIS fj These penetrations never see pressure during etcher operation or vessel preesure test, unless the vessel flange o-rings leak. Inspection during pressure testing therefore serves no purpose. In addition, the nozzle area la not accessible without dam ging insulation. ALTERNATE The nozzles will be hydrostatically tested to insure seal integrity at or near the end of the inspection interval. l SCHEDUIE FOR IMPLEMENTATIN February 28, 1978
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25 s. a e- _w.. _m-
1
- 19. REQUEST FOR RELIEF 1
CODE EXAM COMPONENT ) CIASS TABLE ITEM CATECORY REACTOR VESSEL Standby I.iquid Control Nozzle-to-SLfe End Welds 1 1.1 Bl.6 B-F. t CODE R@UTREME!TT The ultrasonic exa:2ination, and possibly the liquid penetrant examination, cannot be performed for the total weld as required by Exam Category B-E. , PASIS The design of the biological shield prevents access to the bottoci portion of this weld for ultrasonic
,_ examination.
[a u ALTERNATE l Effort will be made to ultrasonically examine as much of the weld as physically possible and to liquid penetrant examine the total weld, provided undue radiation exposure will not result to personnel. SCHEDULE FOR IMPIDfE!TTATION February 28, 1978 s ) 'i 4
- 20. RTUEST FOR RELIEF CODE EXAM COMPONENT s CIASS TABLE ITEM CATECORY REACTOR VESSEL Closure Head Cladding 1 1.1 Bl.13 B-I-1 CODE REQUIRDIE!Tr The liquid penetrant examination of the closure head cladding wil'1 not be scheduled as required by Exam Category B-I-1.
BASIS From our past experience in liquid penetrant examining the Monticello vessel cladding, we have discovered that I the roughness of the closure head cladding results in considerable number of nonrelevant indications that
'e required grinding to eliminate any possible masking effects. In addition, to assure success in the detection of tight cracks, the cladding has a need to be ground to eliminate the oxides and crud that develop during service.
The design stress analysis for the Monticello vessel did not take any credit for cladding thickness. The purpose of the cladding was to maintain water quality. It should be noted that many of the new IL'R vessel designs have eliminated this cladding, and later editions of ASME Section XI Code has eliminated all requirements for the inspection of the closure head cladding. AlfrERNATE Visual examination will be performed on the cicsure head cladding. SCHEDULE FOR IMPLEMENTATION
- February 28, 1978
. ., . . . . - ,, - - - , , - - . . ~ - - -., - --- - - -- - -- -. ------
- 21. PlDUEST FOR RELIEF CODE EXAM COMPONENT CIASS TABLE ITEM CATEGORY Reactor Vessel Safe-end Welds 1 1.1 Bl.6 B-F Pipe Weld Inspection 1 1.4 B4.5 B-J 1 1.4 B4.6 B-J 1 1.4 B4.9 B-K 1 1.4 IW.1 B-F 2 2.2.1 C2.1 C-F l 2 2.2.1 C2.1 C-G j CODE REQUIREMENT e
h The ultrasonic examination method requirements (Appendix I of Section XI and Article 5 of Section V) of the l Code Addenda in effect will not be used to govern the ultrasonic examination procedures for the inspection of pipe welds and welds of ccanponents fabricated from pipe cocponents. BASIS "Ihe use of side drill holes (instead of slots) to establish a distance amplitude correction curve (DAC) for pipe veld inspections, as required by Appendix I of Section XI and Article 5 of Section V, results in an , excessive instrument gain setting which greatly impairs the inspector's ability to detect and to interprete indications by producing a lower signal-to-noise ratio and reducing the range of useable DAC. ALTERNATE The rules of Appendix III, including Supplement 7, of the 1975 Winter and 1976 Sumer Addenda to ASME Section XI Code will govern the ultrasonic examination method for the inspection of pipe welds and welds of components fabricated from pipe components. SCHEDULE FOR IMPEMENTATION February 28, 1978
---- -. - _ - =-. -- - - . . -. - . . - . -. . .
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- 22. Rmur.Sr roR REuEr I t
CODE EXAM .i
- COMPONENT CIASS TABLE ' ITEM ' CATEGORY b i
; Piping Socket Welds - Drain lines (REW28-2"-EF and REW29-2"-EF) of 1- 1.4 B4.8 B-J recirculation system A E, B I
)
! Valve Bonnet Briting - Valves IR-6-1, IR-7-1. IR-6-2, and IR-7-2 l' l.6 B6.9 B-C-2 :
i !
- CODE RfDUIREPE!rr i
Ihe surface examination of the 2" socket velds and the visual examination of the valve bonnet bolting. .; of these two drain lines were not scheduled for examination as required by Exam Category B-J and B-G-2, e 4 respecti-cly. l t E BASIS n> - i
- i These two, 2-inch drain lines are reading in excess of 2R/hr. The location of these lines prevent's the use
~
i ' of shiniding or distance to provide any significant reduction in radiation exposure to personnel. We have ; estimated that exposure to inspection and insulating personnel would be in access of 1 man-rem for the - i er oination of approximately four socket velds and the bolting of four valves. f l ALTERNATE These lines would be examined in accordance with the requirements of' Exam Category B-P, upstream from and ; including their first isolation valve. " i l SCHEDULE FOR IMPLENEh"TATION ' i ! February 23, 1978 't i
! I l
l i
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. . - , . . - - - - , , . - - , --y,-, . .-,
- 23. REQUEST FOR RELIEF CODE EXAM COMPONENT CIASS TABLE ITEM CATEGORY ,
B Non-Welded Piping and Valve Supports 1 1.4 B4.10 B-K-2 2 2.2 C2.6 C-E-2 2 2.3 C3.4 C-E-2 2 2.4 C4.4 C-E-2 3 - - IWD-2600(c) CODE REQUIREMENT Examination Category B-K-2 and C-E-2 requires all areas of the support component from the piping, valve, and pu=p attachment to and including the attachment to the supporting structure. Insulation will not be removed
,_ for visual examination of these support cocponents.
MSIS The general radiation background field for the inspection of Class I systems located within containment ranges from 30 to 400 mR and the Class 2 systems have permanent type of insulation (insulation not designed for removal and replacement). It has been our experience that any loss of support capability or inadequate restraint can usually be detected through the inspection of the uninsulated portion of the support and the surrounding insulation. It is our contention that the removal and replacement of insulation for the sole purpose of inspecting Class I supports would result in undue radiation exposure to personnel without providing significant increase in safety. The governing Codes and Regulations used in the design and construction of those systems that are now ' classified as Class 2 and 3 did not require provisions for inspection access for these systems. Thus, it would be an undue burden without compensating increase in safety to require insulation removal for support inspection. ~ ALTERNATIVE The insulation will be removed from a supported component for further inspections whenever an abnormality is detected that may have been a result of a loss of support capability or inadequate restraint. SCIEDULE FOR IMPIEJfENTATION February 28, 1977
a . i } 2 '. . REQl'EST FOR RELIEF I 1
- CODE EXXI q COMP 02!.T CLASS TABLE ITEM CATECORY Pressure Boundary Bolts and Studs 1 1.5 B5.1 B-G-1 1 1.5 B5.2 B-G-1 2 2.3 C3.2 C-D i
2 2.4 C4.2 C-D 1 i CODE REOUIPEME!Tr ~ 1 Volumetric examination of bolts / studs will not have a DAC constructed (distance amplitude curve) as described in Article 5, section V. ~
- BASIS n
co l The technique described in section V is not as sensitive to detect surface defects as the presently , applied technique using the basic back reflection method correlated with "as built /as installed" > bolting sketch of the particular item being examined. 1 ALTERNATE The items will be ultrasonically examined by longitudinal straight beam, utilizing the response from the back reflection of the bolt or stud being examined, evalustion criteria shall be per section XI, IWB-3000. .i SCHEDUlf FOR IMPIEMEffrATION i co :o j 3$ Feb ru ary 28, 1978 R. On O 1 o e-* r l
- - - - ,, ,-~,.,, - , , , - , , . . - , , - - - - . . - - , - - - , . , , - - - - . ~ , , , , - . - - - - - . -. , , - - - . - -
l ! 4
- 25. IGQUEST FOR RELIEF i
ASME e ) Cm!PONENT FUNCTION lade Viv Class Cat 2 All Class 2 Caponents pressure retaining 1 2 - 2 i CODE REQUIRDtEhT The system pressure tests will not be distributed as required by IWC-2412. RASIS ' Scheduling system pressure tests in this manner is not practical as mechanisms are not available for isolation of l 7 the piping systems at the various boundaries created by the NDE exenption criteria. Consequently numerous redun-
, fj dant pressure tests will be performed whichare not warranted considering the operational problems (system valve j
1 lineups, leak of f or over-pressure protection, radiation exposure, generation of waste, etc.) involved. Addition-11y the majority of these systems are either normally pressurized or pressurized during the performance of a pu:np or valve functional test 1 such that any system degradation would be 1:nmediately known. 1 ALTERNATE INSPECTION (TESTING) 4 All ca ponents will be pressure tested at or near the end of each inspection interval. This is consistant with prepose.1 revisions (Winter 1976 Addenda) to ASME-XI Subsection IWC and Section XI Subcomunf ttee interpretation of Class 2 Pressure Test Requirements (attached). , SCHEDULE FOR 3(PLINENTATION i Febmary 26> 1978 * ) i l
I i 25 Request for Relief (continued) ' { i Y4 The A.mericetn Society of Mechanical Engineers . E -S . United Engineering Chnter / 34!i E,47th St., New York, N.Y. 10017 / 212 M4 7015 g i 3 TH4 DolltR AND } *tilitune. vtt*.t L . j rmies i e i I cs,e/,m,,e ; t
., 3 l6
? L P. Zo i v co cwomen i W L HAf40 LNG The llartford Steam Boiler Inspection and j Insurance Company ' ' i 7,',*y g y $6 Prospect Street , i llartford, Connecticut 06102 : C W At tlSoN j e W.s&ct Att F. T. Duba . 2 m o p:)NNtn ! I 8,Uis"TYn n
Subject:
AS!E File #BC-76-418 ! HV CANAVAfJ Section X1, Division 1. System l'ressure Tests
- R.J Lle*LUCH '
5 t.J CHOCkit F ' w r. coorrH
Dear tir. Doba:
W D. o0TY c t. rHAtcHtH J
" Your inquiry of February 24, 1976 has been considered by the
",CiaYn'/5oy cognitant committee. We are responding to the following question; i E.J HE MZY w.P. JoH NsoN t L r.tuuitti.
OtfES T10N: I t.L.
- evt i
J t- LAT TAN 1. Arc system 1cakage tests required for Class 2 and Class 3 systems? ' y',Cj((,,, *
- 2. Arc system hydrostatic tests required for Class 2 and 3 systems?
n H t. intl u H i T i Notitwur' FIPLY: l C t RAWLINS ,
% H TVITH, sn.
nt sc,utus 1. Systrm lege tests are not required for Class Land 3 components. ,
- 2. System hvetrostatic tests are required for Class 2'and 3 components j ai or near- the end o,f each inspection interval. In addition, a .'
systen hydrostatic test is required on components which have been repaired by velding prior to returning the plant to service. T Very truly y'o. irs, , A F ce n t- '"r June Ling Nuclear Engine ing Administrator JL:1c
- R E C E I V E DL
' CNGINURING re. A 9 ufIb E. L KlMMtt.7
" era Dr v.f...
Memtwr of Eng.neris Council for Professional Development and Engineeri Joint Counest 4-30
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- 26. REQUEST FOR RELIEF APPLICABLE AS4E VALVE j CWPCNENT FUNCTION CODE CLASS CATEGORY,*
TIP 3 Prevent reversal of flav 2 A, C in TIP purge line. Code Requirement This valve cannot be exercised as required by IW-3520. Basis "Ihis is a nomally open check valve that is in sen-ice during all modes of operation. In addition, there is no means available to 7- verify that the disc travels promptly to the seat on cessation or y reversal of flow. Alternate Testing. Proper seating of the valve disc will be verified during the valve Icak rate testing. Schedule for Implementation February 28, 1978
- 27. REQUEST FOR RELIEF APPLICNILE ASLIE l QNPONL7r IUNCTION CODE CIASS i 11,12 Emergency Service Provide cooling water to the emergency 3 Nater Pumps diesel generators and critical reactor building equipment.
P^ Code Requirement Punp f1wrate will not be measured to determine pmp performnce as required by 1hT-3100. Basis here is no installed instrumentation for measuring the flowrate of these pumps. Flowrate varies due to the seasonal variations in cooling requirments er king it impractical to 4 to establish a reference value and acceptance criteria for this parameter. Alternate Testing He Emergency Service Water pumps will be tested to shutoff pressure. Pump differential pressure will be measured under these conditions. Schedule for Implementation January 1, 1979 _ C ?,' 21 aa 8 m
i i i l l
-l l' ! ! I
- 28. PRNEST FOR RELIEF t
. t l I' _00MIMENT APPLICABLE ASTE VALVE FUICTION CODE CLASS CATEGORY {: } All power operated 3 valves. 1, 2, 3 A, B 1' l j Code Requirement i / ' .; t
- i. The acceptance criteria for valve-stroke time as stated. in IhV-3410c)(3) P 1-will not be used. !
I
- l. Pasis- S t-
-O*'
Stroke' time acceptance criteria outlined in IhV-3410 is general and i g j e
.is not based on system functional requirements and nonnal valve variability.
j Alternate ,
- Acceptance criteria lfor valve stroke times will be based on nor: sal.
' valve variability and on system functional' requirements.
- . Schedule for Imp 1 mentation i
j Febniary L28,.1978: , I
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e
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t b a E e 2 W t c-5 E R Revision 2 4-34' 1/5/79
- 30. RFQEST FOR REMEF MTLICABLE AS4i COGUiINT RRCTION CODE CLASS All Class 1, 2 and Pressure Retaining 1, 2, 3 3 Components Code Requirements The test pressure requirements of IhA-5000, IhB-5000, INC-5000 and IhD-5000 will not be met on certain components.
Basis The code does not recognize that non-isolable junctions of cc.npenents c d, with different design pressures or different ASME Classes exist (i.e.,
- pump suction and discharge lines, piping upstream and downstream of restricting orifices, etc.). Pressurizing components to the require-ments of the code may result in overpressurizing the non-isolable components.
Altemate Testing hhere these junctions exist, test pressure will be based on the component with the lowest test pressure requirement. Schedule for Implerentation February 28, 1978
_m_ . _ . - _ . - _ . t i 1 T
'31. REQUEST FOR RELIEF i i :
t APPLIOHLE ASE i ONPONENT FUTTION CODE CLASS 1 i Head vent and leak- Provide connection for 2 test connections on Icak testing and for Class'.1 piping. venting the reactor head.
, Code Requirement
,. These lines will not be pressure tested in acconlance with IhC-5210.
.e i 3- Basis-
'Ihese . lines are connected to Class 1 piping and are classified as Quality Group B lines (applicable ASE Code Class 2) due to line !
size only. These lines will be tested in accordance with Class 1 requirements' (IhB-5000). Altemate Testing i
- See Basis i
Schedule for Inplanentation i February.28,.1978 c : $ r 4 k 4 !
s N i lh U 5 3 2 8 d 4-37 Revi81on 2 1/5/79
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'8
-h 2 E t e-U S m
m l l Revision 2 l 4-37 1/5/79
i i
- 33. REQUEST FOR RELIEF Applicable ASTE Valve i
Cotponent Function Code Class Category DhV-8-1 Secondary containment to toms 2 A, C vacuin breaker. ~ DhV-8-2 2 A, C Code Requirement . These valves will not be exercised as required by ThV-3520(b)(2). Basis Paragraph IhV-3520 of Section XI,1974 Edition with Addenda through and including Struer,1975, does not recognize that the mechanical exerciser torque requirements do not apply to vacuun breakers, whereas the 1977 Edition Sumer 1977 Addenda does recognize this fact. u J. Alternate Testing en These valves will be tested in accordance with Paragraph IhV-3520 of Section XI,1977 Edition Sumer 1977 Addenda. Schedule For Imp 1cmentation May 31, 1978 U S.
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J I a r i l l a ; 4 2 i + l i l .I i i t l i b A w M d w 2 o 4
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0 rA Y n 4-39 Revision 3 2/26/79
- 35. REQUEST FOR RELIEF wDt. EXAM COMPONENT CLASS TABLE ITEM CATEGORY Reporting Requirements for Class I and Class 2 Cmponents 1&2 ____ ____ ____ f CODE REQl'IREMENT The filing of the Inservice inspection reports for Class I and 2 components within ninety (90) days after '
completion by Ik'A-6220. of the inservice inspection with the regulatory authority ( USNRC ) vill not be done as required BASIS Submital of the inservice inspection rtports vould be an addition to the already heavy reporting burden and ! would require positive reporting of success ful completion of the hundreds of tests and examinations that are required every year on a nuclear plant. ALTER!' ATE w E All inspectio and test records are available at the facility for inspection by the 1 & E regional inspectors. In addition, the inservice inspection examination surrmary report will be submitted following each outage in which inspections are conducted. Four copies 'will be sent to the Director, NRR, and two copies will be sent to the Region III office of Inspection and Enforcement. SCHEDULE FOR IMPLEMENTATION February 28, 1978
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- 36. REQUEST FOR RELIEF APPLICABLE AS1E C0fPONENT FUNCTION CODE CIISS All Class 1, 2 and 3 Pressure Retaining 1, 2, 3 Convonents Code Requirement The hydrostatic test pressure and temperature will not be held for four (4) hours for exposed components, as required by IEl-5210.
Basis u f h It is unnecessary to maintain the pressure and tercerature for four hours for areas of " exposed pipe and components. Ten minutes is a sufficient period of time to detemine if leaks are present in exposed areas. Alternate Testing , The test pressure and temperature will be held for ten minutes for exposed areas and four hours for unexposed areas. Schedule For Imp 1cmentation , , January 1,1979 C E' R1 ! aa 3 90 l IJ
i !
- 37. REQUEST FOR RELIEF MTLICABLE ASti CON 1PONENT- FUNCTION CODE CLASS i All Class'2 and 3 Air and Pressure Retaining 2, 3 -
Nitrogen Systems f Code Requirement /% l The hydrostatic tests required by Ih*A-5000, IhE-5000 and IhD-5000 will not be performed using water as the test medium for certain systems. Basis I u I- %c air and nitrogen systems were not designed for water service. Therefore, a hydrostatic r test would be ' inappropriate. Alternate Testing These systems wi11' undergo pneumatic. tests. r Schedule For Implementation January 1, 1979 , , 4 w l
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- 3 M
9 i s . + i
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- 38. REQJIST FOR RELIIT APPLICABLE AS4E COMPONENT IUNCTION CODE CIASS All Class 1 and 2 Pressure Retaining 1, 2 Components-Code Requirement The hydrostatic test temperature will not be greater than or equal to 100*F for austenitic stainless steel components as required by ThT>-5222 and Iht-5220.
Basis u Austenitic stainless steels do not exhibit or undergo ductile-to-brittle transitions and the h toughness remins essentially constant regardless of tlc temperature of the material. There-fore, heating the test meditm to above 100*F for these components is unnecessary. Alternate Testing Austenitic stainless steci portions of lines will be tested at anbient temperature. Schedule for Implerrentation Janua y 1, 1979 - CilE R;1 8 w
- 39. REQUEST FOR RELIEF APPLICABLE ASBE VALVE NON M ION ODIE CLASS CATEGORY Excess Flow Check blinimize the blowdown to the Secondary Valves, Typical of Containnent in the event of an instrinnent 1 A, C X-27A through X-52F sensing line break.
Except X-28F. 001E RrdJTRBENT These valves will not be tested as required by IhV-3410 or Ih'V-3520. BASIS I ? The Excess Flow Check Valves are located in sensing lines for the Plant Protection System and ECCS l a Instruments. Testing the check valves during operation is not practical since it would make the-vital instrumentation inoperable. Cold shutdown tesfing is also impractical since it would require pressurizing
^
l ! the reactor vessel to operating pressure. l l
' ALTERNATE TESTING The Excess Flow Check Valves are tested each refueling outage when the vessel is pressurized to 1000 l
psig during the Reactor Vessel Ifydro Test. l SOIEIULE TUR IMPLDIENTATION . This testing was implemented since initial plant startup as required by the original Technical Specifications. l$l1 3 ;"
*8 v
- ~ -
' ' -= -
- = - -
~
- 40. REQUEST FOR RELIEF -
APPLICABLE ASME VALVE LYMUNL'Nr Fi1\'CTION WDE CIE - GMW Excess Flow Check Minimize the Blowdown to the secondary Valve X-28F containment in the event of an instru- 2 A, C ment line break and vessel head seal failure. vu ; CODE ICQUIPBINT This valve will not be tested as required by IhY-3410 or IhY-3520 BASIS
?
O There is no way to test this valve except to remove it from the line since there is nonna11y no pressure between the vessel head seals. Removal of the valve is extremely difficult because the piping is rigid and thread damage has resulted from previous atterpts to remove the valve. A sensing line break would result in blowdoim to the secondary containment only if the vessel head seal was leaking. The blowdown would be limited by the seal leak which would, in all probability, be less than the leakage allowed by the check valve. The probability of a line break and seal leak occuring to cause a significant blowdoim is extremely small, therefore it is felt this valve should not be tested to avoid further thread damage to the piping. . ALTERNATE TESTING , None SOIEIULE IUR IMPIBBTTATICN N/A h.k Pa= eg w a
- 41. REQUEST FOR RELIEF Code Exam Compone nt Class Table Item Category PUMP CASINGS-RECIRCULATION PUMPS "A" AND "B" 1 1.5 B5.7 B-L-2 Code Requirement The visual examination of the Recirculation Pumps internal pressure surfaces will not be scheduled as required'by Exam Category B-L-2.
Basis Disassembly of the recirculation pumps for the sole purpose of visual examination of the casing internal pressure surfaces requires many manhours from skilled maintenance personnel. Increased 7 radiation exposures result from this act ivity. The probability of pump failure is increased by
$ unnecessarily disassembling'the units. Deferring the examination has no af fect on integrity of the pumps.
Alternate Recirculation Pump internal pressure surfaces will be visually examined when the pumps are disassembled for maintenance. Schedule ' for Implementation March 5, 1980 J R%' . C.i. m Or w 11
- .. .. - .... ....~. _ - . . . . - . . - _ . _ . . - . . - . . . . . . . . . . . - ~ . - . . - _ - . _ . . _ . . _ _ _ _ - . - _ . . . - . . _ _ _ _ _ - . . .
- sg.- ;
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[
- f. 42. REQUEST. FOR RELIEF l i Code Exam Component Class Table- Item Category VALVE BODIES 1 1.6 B6.7 B-M-2
~
. CRANE CHAPMAN CATE VALVES i RECIRCULATION VALVES. ;.Jl2-65A,.MO 2-65B
! MO 2-53A, MO 2-4 3A 'j MD 2-53B, MO 2-43B t i
Code Requirement 1 1 .
- . The visual examination of_the Recirculation Valves internal pressure surfaces will not be !
I ,- scheduled as required by l Exam Category B-M-2. i i ! . Basis I ! s. I
$. Disassembly 'of the recirculation valves for the sole purpose of visual examination of the internal
" Increased radiation 3
pressure surf aces requires many manhours from skilled maintenance personnel. } exposures result from this activity. - 'Ihe probability of valve failure -is increased by . l unnecessarily disassembling the units. Deferring the examination has no af fect 'on the integrity of the valves. ; i ,' ~ Alternate ,l Recirculation Valve' internal pressure. surface will be visually. examined when the pumps are
. disassembled l for maintenance. !
1 [ Schedule for -Implement ation
- March 5, ' 1980.l .
8
+
H . i I" , N fD .1 Ls< 1 I 03 as u r
, C> W 1 0
- 3 ,
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1 i ( SECTION 5 PEPOSED TECHNICAL SPECIFICATION CHANGES i I Reproduced in this section are the proposed Technical Specification = changes included in Northern States Power Company's License Amendment Eequest dated August 30, 1977. These changes revise the surveillance i requirements in the Technical Specifications to confom to 10 CFR 50, l Section 50 55a(g). . Changes proposed in Northern Stateo Power Company's License Amendment I Bequest dated January 18, 1978 also appear here. These changes vere submitted to incorporste a progma of sugmented inservice inspection for piping susceptible to stress corrosion cracking. t 1 5 l 1 l t 5-1
- - ~ . .. . - . ._ .-- . ~ - . _ . - .
t
, 4 i-t I
3 l 3.0 LIMITING' CONDITIONS FOR OPERATION h.O SURVEILIANCE REQUIRD4ENTS 4 34 STANDBY LIQUID CONTROL' SYSTEM h.h STANDBY LIQUID CONTROL SYST&! . l ' Applicability: i Applicability: l. Applies to the operating status of the Applies to the periodic testin6 require-
- standby liquid control system. i ments for' the standby liquid control system. i
!- Objective: Objective:
^
.l i To assure the. availability of an Independent reactivity control mechanism. To verify the operability of the standby !
4 liquid control system. ! 4 SPECIFICATION: SPECIFICATION: i A. . Normal' Operation A. i The operability of. the standby liquid a . control systen shall be verified by l 1. The steadby liquid control system performance of the following tests: i shall be operable at all times when
- s. ' fuel is in the reactor.and the reactor'is not shutdown by control 1. . At least once each opersting .' cycle
}- L2 nds, except as specified in 3.h.B. manuall y initiate one' of: the two standby liquid control systemsiand
- 2. Ehch standby liquid control; system pump Pump demineralized water.into the ;
shall be capable of delivering 24 gym reactor vessel.~ Both systems shall. 1 ; } . against ,a reactor. pressure of 1275 psig. be tested arvi inspected in the l course of two operating cycles. ! ! 3 The" system pressure relier' valves shall be opersble with a setpoint .between 1350 and 1450 psig. l
.7 1
- . l 3.h/4. A hav -
1 ,
, n I
'3 0 LIMITInc compITrous Fat OPERATION 1.0 6
SLEVEIILUICE REQUIRENDrfs
- 2. Inservice inspection and testing of components shall be conducted in accordance with Specification 4.13 1
Y
' u B. Operation with . Inoperable Components B. Surveillance with Inoperable Components From and after the date that a mdundant component is.mde or found to be inoperable, When a component becomes inopemble, its Specification 3 4.A shall be considered redundant component shall be demonstmted fulfilled, provided that the component is to be operable immediately and daily returned to an operable condition within thereafter.
seven days. ls
.( .i 1
c + - 3.u/4.4 89 REV
_ . _ _ . . . _ . _ . _ . _ _ _ . _ _ _ _ . - . _ . . _ . _ _ . _ _ . _ _ . . _ _ _ . _ _ _ _ = . _ . _ . . . . _ m , l
)
I i i 30 LIMITING CONDITIONS FOR OPERREION 4.0 SURVEILIANCE REQUIREMDFfS ' C. Vo1Moncentration Requireunents C. %e availability of the proper boron h e liquid poison tank shall'contain bearing solution shall be verified by a boron bearing solution-that satisfies perforsence of-the fol4owing tests
- i the voltane-concentration requirements 1. At least once per month -
of.. Figure . 3 4.1' and at all times when the' standby liquid poison system .is re- j quired to be operable the temperature Boron concentration shall be t shall not be less than the solution temp-determined.' In addition, ' the boron '
+
ersture presented in Figure 3 4.2. In concentration shall be deter 1 mined ! any time water or boron are added ! addition, the heat tracing on the pump suction lines shall be operable whenever - or'if the solution temperature drops y- the' room temperature is less than the below the limits specified by Figure 3.4.2. e- solution temperature presented in Figure , 3.4.2. . i f t t 4
'I i
?
i h 3.4/h.4 9o- ; [ t PM f'
en 4 Rases 3.4 and 4.4-A. The design objective of the standby liquid control system is to provide the capability of bringing the reactor from full power to a cold, xenon-free shutdown assuming that none of the withdrawn con-trol rods can be inserted. To meet this objective, the liquid control system is designed to inject a quantity of boron which produces a concentration of 900 ppm of boron in the reactor core in less than 125 minutes. 900 ppm boron concentration in the reactor core is required to bring the reactor from full power to a 37. o k subcritical condition considering the hot to cold reactivity swing. xenon poisoning and an additional 257. boron concentration margin for possible imperfect mixing of the chesnical solution in the reactor water and dilution from the water in the cooldown circuit. A minimum net quantity of 1400 gallons of solution having a 21.47. sodium pentaborate concentration is required to meet this shut-down requirement. he time requirement (125 minutes) for insertion of the boron solution was selected to override the rate of reactivity insertion due to cooldown of the reactor followirg the xenon poison peak. The 2 anxistse net storage volume of the boron solution is 2095 gallons. (256 gallons are contained below Y the pump suction and,. therefore, have not been used in the net quantities above.) Boron concentration, solution temperature, and volume (including check of tank heater and pipe heat tracing system) are checked on a frequency to assure a high reliability of operation of the system should it ever be required. , Experience with pump operability demonstrutes that testing at a three-month interval is adequate to detect if failures have occurred. s Standby liquid contml system ecerponents are inspacted and tested in acconiance with the requirements of 10 CFR 50, Section 50 55a(g). These mquirements are delineated in Specification 4.13 his ' inspection and testing pmgram, combined with the additional surveillance requirements contained in this section, pmvide a high degree of assurance that the standby liquid contml system will perform as mquired when needed. The relief valves in the standby 11guld control system protect the system piping and positive dis-placement pumps which are nominally designed for 1500 psi from overpressure. The pressure relief ' valves discharge back to the standby liquid control solution tank. ! 34/4.4 ansm g RW F
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8 3.0 LIMITING CONDITIONS FOR OPERATION h.0 SURVEIIJEICE REQUIRDelTS ' 35 CORE AND CONTAIMMEfrP COOLING SYSTDG ! 4.5 CORE AND CONTAINMErr COOLING SYSTEMS
, Applicability:
Applicability: Applies to the operational status of the emergency cooling systems. Applies to periodic testing of the emergency cooling systems. Objective: , Objective: To insure adequate cooling capability for heat removal in the event of a loss of coolant To verify the operability of the emergency cooling systems. a accident or isolation from the nomal reactor os heat-sink. Specifica tion: Specification: Iow Pressure Core Cooling Capability Low Pressure Core Coolig Casability I A. Core Spray System A. Surveillance of the core sprsy system shall ' be performed as follows: 1.- Except as specified in 3.5.A.2., 3 5.A.3., and 3 5.A.S. below, both core 1. Routine Testing spray subsystems shall be operable when-ever irradiated fuel is in the reactor a. A simulated automatic actuation test vessel and reactor coolant water tempern-ture is greater than 212 F. shall'be conducted each refueling outage.
- b. Core spray headerap instrumentation
- shall be checked once each day, tested
- once each month, and calibrated once cach 3-month period.
3 5/4.5 96 PJLv
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3.0 LIMITING CONDITIONS FOR OPERATION h.0 SURVEILIANCE REQUIRDfMfS '
- c. Inservice inspection and testing of components shall be conducted in accordance with Specification h.13 a
'T N
2. From and after the date that one of the 2. core spray, systems is made or found to be When it is detemined that one core inoperable for any reason, reactor opera- spray system is inoperable, the operu , tion is permissible only durirv5 the suc-able core spray system and the LPCI - ceeding fifteen days unless such system ' mode of the RER systs and the diesel is sooner made operable, provided that genem tors required for opem tion of j during such fifteen ' days all active compo- such components (if no external source nents of the other core spruy system and of power were available) shall be the LPCI mode of the RHR system and the demonstrsted to be operable issuedia-diesel generators required for operation tely. 'Ihe operable core spray system , of such components (if no external source shall be demonstrated to be operable daily thereafter. of power were available) shall be operable.
- 3. From and after the date that both core ~
spray systems are. made or found to be 3. - When it is determined that both core
' inoperable for any reason, reactor spray systems are inoperable, the LPCI mode of _ the RHR system and the.
35/4.5 2 97 REv
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l I
.y
. 3.0 LIMITING CONDITIONS FOR OPERATION h.O SURVEILIANCE REQUIRD(DfTS
~
operation is pennissible only during diesel generators required for the succeeding- seven days unless.at operation of such components (if least one of such systems is sooner no external source of power were aride operable, provided that during such seven days all active-components available) shall be demonstruted of the LPCI mode of RHR system and the to be operable immediately and daily ' thereafter. diesel generators required for operation of such components (if.no external source of power were available) shall be opera-ble.
- 4. ' Each core spray system shall be. capable .
of. delivering -3,020 gpm against a reactor Y
- pressure of 130 psis. . If this rate of delivery requirement cannot be met, the system shall be considered inoperable.
5 If the requirements of 3 5. A.1 .-3 cannot
- be met, an ortlerl,y shutdown of the reactor will be initiated and the reactor water
- temperature ahall be reduced to less than 212 0F vithin :~h' hours.
i . i 1 4 4 35/4.5
. mzy 4
1
3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILIANCE REQUIRIMDITS B. Iov Pressure Coolant Injection (IPCI) Subsystem B. Surveillance of the Iow Pressure Coolant (IPCI mode of PJIR system) Injection (LPCI) Subsystem (IPCI mode of RIIR system) shall be perfomed as follows:
- 1. Facept as specified in 3.5.B.2 and 3 5.B.3 below, the LPCI shall be operable 1. Routine Testing whenever irradiated fuel is in the reactor vessel and reactor coolant temperature is a. A simulated autmatic actuation test greater than 212 F. shall be conducted each refueling cutage.
- b. Inservice inspection and testing of components shall be conducted in accordance with Specification 4.13 y c. During each five year period, an air
'o test shall be performed on the dryvell spray headers and nozzles.
- 2. Freen and after the date that one of the 2. When it is determined that one of the LPCI pumps or admission valves is mde or found to be inoperable for any reason, LPCI pumps is inoperable, the renn.tning active components of the LPCI and con-reactor operation is pemissible only tainment cooling subsystem, both core during the succeeding thirty days unless- spray systems and the diesel generators such pump or admission valve is sooner made operable, provided that during such required for operntion of such components thirty days the remining active components (if no external source of power were of the LPCI and containment cooling sub- available) shall be demonstrnted to be system and all active components of both operable imediately and the operable LPCI ptr.ps daily thereafter.
core spray systems and the diesel genera-tors required for operation of such com-ponents (if no external source of power were available) shall be operable. 35/h.5 99 REV
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+
gy 3 t I t 30 LIMITING. CONDITIONS FOR OPERATION h.0 SURVEILIANCE REQUIRMSTS 3 From and after the date that two of the 3 When it is detemined that the IPCI L LPCI peps or admission valves are made subsysten is inoperable, both core , or found to be inoperable for any reason, spray systems, . the contaitument cooling reactor operation is pemissible only subsystem, and the diesel generators during the succeeding seven days unless required for operation of such com-such pumps or admission valves are made ponents (if no external source of operable sooner, provided that during such power were available) shall be seven days all active components of both demonstrated to be operable immedi-core spray systems, the containment ately and. daily thereafter. , cooling subsystem (including 2 LPCI . pumps) w and the diesel generators required for 4 4 operation of such components (if no o external source of power were available) shall be demonstrated to be operable at least once each day. i
- 4. : A'maxistan of one drywell spray loop i ' (containment cooling mode of RHR) may bs
' inoperable for'30. days when the reactor water. temperature is greater than 212 F.
- If the loop is .not retumed to service t
within 30 days, the orderly shutdown of i the reactor will be initiated and the reactor. water temperature chall be f reduced to less than 212 0F, 5 Each' LPCI subsystem (RHR) pump 'shall be 4 capable of' delivering h,000 gpm against t a reactor pressure of'20 psig. If'this 1 35/4.5 100 REV
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I t i t i l i l 3 0 ' LIMITING CONDITIONS' FOR OPERATION k.O SURVEILIANCE REQUIRDHTS. ; i' rate of delivery requirement cannot be met, the pump shall be considered inoper-able.
- 6. If the requirements of 3.5.B.1-4 cannot ,
be met, an orderly shutdown of the reactor l will be initiated and the reactor water > j" ' teyrstureshallbe. reduced-tolessthan' 212 F within.2h hours, j i j r Containment Cooling Capability. Containment Cooling Capability
- V .
P i C. Residual Heat Removal (RHR) Service Water C.. Surveillance of. the RHR service water i -System system shall be performed as follows: ! 1.- Except as specified in 3 5.C.2 and 3 5.C.3
.below, both RHR service water system loops
- 1. Ineervice inspection and testing of components shall be conducted in.
shall be opernble whenever irradiated fuel accordance with' Specification k.13 is in the reactor vessel and reactor coolant ; ! temperature .is greater than 2120F. l F < i
- 2. ' From and af ter..the date that 'one of 'the 2.. .
When it is determined that one~BHR 'i RHR service water system pumps is ade or service water pump is inoperable, . [ found .to. be inoperable for any reason, the redundant' components of the ; I }1 t f ! 101 1
'REV .
[ 35/h.5
1 . 30 LIMITING CONDITIONS FUR OPERATION 4.0 SURVETTJANCE RBEJIREBENTS reactor operation is-pemissible only remaining subsystem shall be during the succeeding thirty days unless demonstrated to be opemble 1:msedi-such pump is sooner made operable, pro- ately and daily thereafter.
, vided that during such thirty days all other active ' components of the RHR service water system are opemble.
3 From and after the date that one of the 3 When one RHR service water system RHR service water systems is made or .found becomes inopemble, the opemble to be inoperable for any reason, reactor system shall be demonstrated to be opemtion is pemissible only during the opemble inanediately and daily succeeding seven days unless such cystem thereafter. is sooner made ope mble, provided that during such seven days all active compo-y nents of the operable RHR service water y system shall be demonstrated to be opera-ble at least once each day.
- h. 'Ib be considered operable, a RHR service d
vnter pump shall be capable of delivering 3500 gpm against a head of 500 feet. 5 If the requirements of 3 5.c.1-3 cannot be met, an orderly shutdown of the reactor vill be initiated and the reactor water temperature shall be reduced to less than 2120F vithin 24 hours. 3 5/4 5 im REV
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L 3.0 LIMITING CONDITIONS FOR OPERATION h.0 SURVEILIAICE REQUIREIEffS j Ifigh Pressure Core Cooling Capability High' Pressure Core Cooling Capability ] D. High Pressure Coolant Injection (HPCI) System D. Surveillance of HPCI System shall be i performed as follows:
- 1. Except as specified in 3.5.D.2 below, 1. Routine Testing the HPCI system shall be operable when-ever the reactor pressure is greater than .
150 psig and irradiated fuel is in the a. A si -lated automatic actuation test reactor vessel. - shall be conducted each refueling outage.
- b. Inservice inspection and testing of components shall be conducted
\"
s in accordance with Specification h.13 w
- 2. From and after the date that the HPCI 2. When it is determined that HPCI system is made or found to be. inoperable system is inoperable, the RCIC system, for. any' reason, reactor operation is per- the LPCI subsystem, and both of the core'
.missible only during the succeeding seven spray systems shall be demonstrated days unless'such system is sooner made to be operable immediately.
operable, provided that during such seven
-days all of the Automatic Pressure Relief system, the RCIC ~ cystem, both of the core spray Lsystems, and the LPCI subsystem and containment cooling mode of the FJIR system are operable.
i 3.5/4.5 103 i REV
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m_, ; s . t'
- 3.0 LIMITING CONDITIONS FOR OPERATION h.O St RVEILIANCE REQUIRDH2rfS 3 To be considered opernble, the HPCI system shall meet the following conditions:
- a. H e HPCI shall be capable of delivering 3,000 gpm into the reactor vessel for the reactor pressure range of 1120 psig to 150 peig.
- b. -- he condensate storage tanks shall !
contain at' least 75,000 gallons of condensate water.
*~
- c. he controls for automatic transfer of the HPCI pump suction from the corulensate storage tank to the suppression chamber shall be operable.
- 4. If the . requirements of. 3 5.D 1-2 cannot be met, an orderly reactor shutdown 'shall be initiated 1smeediately and the reactor.
pressure shall be reduced to 150 psig t
. within 24 hours thereafter.
104
'35/h.5. m
- p,. .
i 30 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILIAr:CE REQUIRDfEITS E. Automatic Pressure Relief System 'E. Surveillance of the Autosumtic Pressure - Relief Systest shall be perforised as follows:
- 1. Except as specified in 3 5.E.2 and 3 5.E.3 below, the. entire auto.mtic 1. Routine Testing pressure relief system shall be operable a. A simulated automatic actuation at any time the reactor pressure is above test shall be conducted each oper-150 psig and. irradiated fuel is in the ating cycle. !
reactor vessel.-
- b. Once each operating cycle. valve oper-
- 2. ability shall be verified by cycling From and after the date that one of the the valves and observing a compensating automatic pressure relief system valves is y cede or fo nd to be inoperable for any change in turbine bypass valve position.
u 4 reason, reactor operation is pemissible
- c. Inservice inspection and testing of '
'only durire the succeeding seven days components shall be conducted in .
unless such valve is sooner made operable, accordance with Specification 4.13. i
- provided that during such seven .inyt '
both remaining automatic relief systm
- j. valves and the HPCI system are operable.
i 3 . From and after the date that more than
^ one of the automatic pressure relief
! valves are made or found to be inoperable I i for any reason, reactor operation is 2. pemissible only during the succeeding 14:en it is determined that one or ! 24 hours unless repairs.are made and more automatic pressure relief valves ! i- provided that'during such time the HPCI of the Automatic Pressure Relief I system is crerable, system is inoperable, the HPCI systems
- shall be demonstrated to be operable j k. If the requirements of 3 5.E.1-3 cannot immediately and weekly thereafter.
- be met, an orderly reacter shutdown shall j l be initiated immediately and the reactor shall be reduced to 150 psig within 24
} .
hours thereafter. :
! 35/4.5
- 105 E
REV
* , .m...
m . 3.0 LIMITIEC CGtDITIONS FOR OFERATION h.0 SURVEILIATE REQUIREMBff3 F. Reactor Core Isolation Cooling System (RCIC) F. Surveillance of Reactor Core Isolation Cooling System -(RCIC) Surveillance of the ICIC System shall be performed as follows:
- l. Except as specified in 3.5.F.2 below, the 1. Routine Testing RCIC system shall be operable whenever the reactor pressure is greater than 150 a. A sf =ilated autourttic actuation test psig and irradiated fuel is 'in the reactor .shall be conducted each zvfueling outage.
vessel.
- b. Inservice inspectic antl testing
- a. To be considered operable, the RCIC of components shall be conducted
- system shall be capable of delivering in accordance with Epecification 4.13
[ LOO gpm into the reactor vessel. ch
- 2. From and after the date that the RCIC sys-
- 2. Vnen it is determined that the RCIC sys-tem is cade or found to be inoperable for l any reason, reactor operation is permissible tem is inoperable, the HPCI systes2 shall I
only during the succeedint.15 days unless be demonstrated to be operable in::tediately and daily thereafter. such system is sooner cade opeiable, provided that during such 15 days all active compo-r nents of the HPCI system are operable. 3 If the requirements of 3 5.F.1 - 2 cannot 4 be met, an orderly shutdown of the reactor } ehall be initiated innediately .and the i reactor pressure shall be reduced to 150 psig within 24 hours thereafter. g 35/h.5 m
3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILIANCE REQUIRDENTS - I. Racirculation Systen I. Recirculation System
- 1. Except as specified in 3.5.1.2 below, whenever 1. Once per month, when irristed fuel is in the irradiated fuel is in the reactor, with reactor reactor with reactor coolant temperature greater coolant temperature greater than 2120 F and both then 2120 F and both reactor recirculation reactor recirculation pumps operating, the pumps operating, the recirculation systse cross recirculation system cross tie valve interlocks tie valve interlocks shall be demonstrated to shall be operable. be operable by verifying that the cros tie valves cannot be opened using the normal control
- 2. The recirculation system creas tie valve inter- switch.
locks may be inoperable if at least one cross
, tie valve is maintained fully closed. 2. When a recirculation system cross tie valve L
~4
*nterlock is inoperable, the position of at
, least one fully closed cross tie valve shall
- 3. Valves in the equalizer piping between the be recorded daily.
recirculation loops shall be closed. Reactor , operation with one loop shall be limited to 24 hours. 3 Inservice inspection and testing or
' components shall be conducted in accordance with Specification 4.13
- 3.5/4.5 lOBA REV
. . .. - ~-. - .. , _
Bases b.5: The testing interval for the core and containment cooling systems is based on a quantitative reliability analysis,' judgment, and practicality. The core cooling systems have not been designed to be fully testable during operation. For example, the core spray final admission valves do not open until reactor pressure has fallen to 450 psig; thus, during operation even if high drywell pressure were simulated, the final valves would not open. In the case of the HPCI, automatic initiation during power operation would result in pumping cold water into the reactor vessel, which is not desirable. The systems can be automatically actuated during a refueling outage and this will be done. To increase
' the availability of the individual components of the core and containment cooling systens, the components which make up the system, i.e.,, instrumentation, pumps, valve operators, etc.4 are tested more frequently.
The instrumentation will initially be functionally tested once per month umil a trend is established and thereafter according to Figure 4.1 (see Section 3.1/4.1) with an interval not greater than three months. ' Core and containment cooling system components are inspected and tested in accordance with Y the requirements of lo CFR 50, section 50 55a(g). These requirements are delineated in specification
$ h.13 This inspection and testing progrrun, combined with the additional surveillance mquirements contained in this section, provide a high degree of assumnce that the core and containnent cooling systems will perfom as requimd when needed.
With components or subsystems out-of-service, overall core and contairunent cooling reliability is main-talned by demonstrating the operability of the remaining cooling equipment. The degree of operability to be demonstrated depends on the nature of the reason for the out-of-service equipment. Pbr routine out-of-service periods caused by preventative maintenance, etc., the pump and valve operability checks will be performed to demonstrate operability of the remaining components. However,,if a failure, design
. deficiency, etc. , caused the out-of-service period, then the demonstration of operability should be thorough enough to assure that a similar problem does not exist on the remaining ccanponents. Far exagle, if an out-of-service period were caused by failure of a pump to deliver rated capacity due to a design deficiency, the other pumps of this type might be subjected to a flow rate test in addition to the operability checks.
4.5 BASES 114 1 REV (
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3.0 LIMITING CONDITIONS FDR. OPERATION 4.0 SURVEILIANCE REQUIREMENTS - ' t E. Safety / Relief Valves E. Safety / Relief Valves
.1 During power operating conditions and whenever 1. The integrity of the safety / relief. '
reactor coolant pressure is greater'than 110'psig valve bellows shall be continuously and temperature is' greater than 345 F : monitored.
- m. The safety valve function (self-actuation) of 2. Le operability of the bellows seven safety / relief; valves'shall be operable. monitoring system shall be demonstrated at least once every three months.
- b. Ibe solenoid activated reller function '3. Inservice inspection aal testing of
( Automatic. Pressure Relief) shall be . components shall be conducted in 1 operable as required by Specification Ys ' 3 5. E. accordance with Specification 4.13.' ' to 4 f I > t i i i 1 7 l3.6/4.6 119 { , , . . .
i
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30 LD4ITII G CONDITIONS FOR OPEPATION h.O SURVEILIANCE RBlUIRDENTS F. deleted F. deleted [0. Jet Pumps G. Jet Puaps Whenever the reactor is in the Startup Whenever there is recirculation flow with the or Run modes, all jet pumps shall be oper- reactor.in the Startup or Run modes, jet pump 4 able. If it is determined that a jet pump is operability shall be checked daily by verify-inoperable,.the plant shall be placed in a ing that all-the following conditions do not
- l. cold shutdown condition within 24 hours. occur sic:uitaneously:
- 1. The two recirculation loop flows are unbalanced by 15% or more when the recirculation pumps are operating at the same speed.
' 2. The indicated value of core flow rate is 10% or more less than the value de-rived from loop flow measurements. 36/4.6 120 REV
. _ .. _ _. ._ _ _ . _ . _ -_ . . _ . . . . _ __. m _ . _ . . _ . ___ .._ __. _.. _ .. _ . - _ .. _ _ . _ _ . _ . . _ _ _
2 Bases Continued 3.6 'and h.6: i he safety /relier valves have two functions; i.e. power relief or self-actuated by high pressure. ; he solenoid. actuated function' (Automatic Pressure Relief) in which external instrumentation s6gnals of coincident high dryvell pressure and low-low water level initiate opening of the valves. This function is discussed in Specification 3 5.E. . In addition,' the valves con be operated manually. i he safety. function'is perfomed by the name safety / relief valve with self-actuated integral i bellows and pilot valve causing main volve operation. Article 9 of the AS4E Pressure Vessel Code Section III ? Nuclear Vessels requires that these bellows be monitored for failure since this vould defeat the safety ! function of the safety / relief valve. It is realized that there is no'vay to repair or replace the bellows during operation and the. plant must be. shut down to do this. The thirty-day period to do this allows the operator flexibility to choose his time -for shutdown; meanwhile, because of- the redundancy present in the. design and the continuing { j monitoring of the integrity of.the.other valves, the overpressure pressure protection has not been , compranised. De auto-relief function vould not be"dmpaired by a failure of the bellows. However, the
- , self-actuated overpressure safety function vould be impaired by such a failure.
4 ro . . , P -t
' Provision nlso has been made to detect failure of the bellows monitoring system. Testing of this system quarterly provides assurance of bellows integrity.
r l ' When the setpoint is being bench checked, it is pntdent to disassemb1'e one of the safety / relief valves to axamine for: crud buildup,. bending of certain actuator members or other signs of.possible deterioration. 1 1 j. he program of ' safety /relier valve testing conforms to the requirements of 10 CFR 50, Section 50 55a(g). 1
% eseirequirements are delineated in Specification 4.13 This inspection and testing program, combined
- with the additional surveillance requirements contained in this section, provide a high degree of assurance j- that the safety /relier valves will perfonn as required when needed.
i: . t
; i j
3.6/h.6 EASES 135 i
me a e r f i b J s e 4
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4
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4 J 4 o J e k 4 S4 1
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4 e g; m* m -4 N
& Q en 5-22
f .g Bases Continued 3.6 ani 4.6: G. Jet pumps Failure of a jet pump nozzle assembly hold down schanism, nozzle assembly and/or riser, would increase the cross-sectional flow area for blowdown Ellowing the design basis double-ended line break. h erefore, if a failure occurred, repairs must be made. he detection technique is as follows. With the two recirculation pumps balanced in speed to within
+ 5%, the flow rates in both recircula' tion loops will be verified by Control Rocan monitoring instruments.
If the two flow rate values do not differ by more than 10%, riser and nozzle assembly integrity has been verified. If they do differ by 10% or more, the core flow rate measured by the jet pump diffuser differential pressure system must be. checked against the core flow rate derived from the measured values of loop flow to core flow correlation. If the difference between measured and derived core flow rate is 10% or more (with the deri' red value higher) diffuser measurements vill be taken to define the location within the vessel of failed jet pump nozzle (or riser) and the plant shut down for repairs. If the potential u blevdown fJov area. is increased, the system resistance to the recirculation pump is also reduced; hence, "lo - the affected drive pump vill "run out" to a substantially higher flow rate (approximately 115% to 120% for i a sin 81 e nc,zzle failure). If .the two loops are balanced in flow at the same pump speed, the resistance characteristics cannot have changed. Any imbalance between drive loop flow rates vould be indicated by the plant process instrumentation. In: addition, the affected jet pump would provide a leakage path past the core thus reducing the core flow rate. E'e reverse flow through the inactive jet pump would still be indicated by a positive differential pressure but the net effect would be a slight decrease (3% to 6%) in the total core flow measured. his decrease, together with.the loop flow increase, vould result in a
~
lack of correlation between measured and derived core flow rate. Finally, the affected jet pump diffuser differential pressure siEnal vould be reduced because the backflow would.be 'less than the normal forward flow. A nottle-riser system failure could sloo generate the coincident failure of a Jet . pump body; hei tver, the . converse is not true. He lack of any substantial stress in the jet pump body raskes failure imp ;ssible without an initial nozzle-riser system fatture. , 137 3.6/4.6 BASES REV 4
. . . . ._. ._ ___ _ _ . ._ .._ _ ._._ . _ . _ _ . . . _ _ _ _ . _ . _ _ _ _ _ . _ _ . _ . . _ _ _ . . - _ . _ . . _ .. ._.m
<s ,
I 3 0 LIMITING CONDITIOfG }VR OpDATION h.O SURVEILIANCE REQUIREMENTS
'3 Pressure Suppression Chamber - 3 Pressure Suppression Chamber -
' Reactor Building Vacuum Breakers Reactor Building vacuum Breakers a.- Except as.specified in 3.7.A.3.b
- a. The pressure suppression chamber-reactor below, two pressure suppression building vacuum breakers and associated.in-chamber-reactor building vacuum strumentation including set point shall be breakers shall be operable at all checked for proper operation every three . .
times when the primary. containment months. ' integrity is required. The set point of the differential pressure
- < ~ instrumentation which actuates the b'. Inservice inspection and testing of
- w components shall be conducted'in !
. pressure suppression chamber-reactor
/o' accordance with Specification 4.13.
" building vacuum breakers shall.be O.5 psi.
i F b. From and after the date that one of l 1 the-pressure suppression chamber-reactor building vacuum breakers is * } .made'or-found to.be inoperable for i any. reason,' reactor. operation is I ' permissible only during.the suceed-ing seven. days unless such vacuum t 1 breaker.lis' sooner made operable, provided that the repair procedure -
.:does not violate primary containment integrity.
,. t i' ! lh6
- REV, 3 7/4.7 d
3.0 LIMITING CONDITIOIIS FOR OPEPATION h.O GURVEILLAI;CE PJRJIRE4 Errs 1
- d. The fbcl cask or irradiated fuel is not being moved within the reactor building.
D. Primary Contalment Isolation Valves D. Primar/- Contalment Isolation valves
- 1. During reactor power operating conditions, 1. The primary containment isolation valves all isolation valves listed in Table 3.7.1 surveillance shall be pcrformed as follows:
m and all primary system instrument line 4 w flow check valves shall be operable except a. At least once per operating cycle the as specified in 3.7.D.2. operable isolation valves that are powar operated a:xi automatically initiated shall be tested for sicrulated automatic initiation and closure times,
- b. Inservice inspection and testing of components shall be conducted in accordance with Specification 4.13.
3 7/h.7 151 PSV
c. 3.0 LIMITING CONDITICIC FOR CPEFATIO;i 4 1.0 SURVETTTATE RRUIRDG2C3 Y M
- 2. In the event any isolation valve specified 2.
in Table 3.7.1 becoines inoperable, reactor L'henever an isolation valve listed in operation in the run mode may continue Table 3.7.1 is inoperable, the position of provided at least one valve in each line at least one iblly closeti valve in each line having an inoperable valve is closed. having an inoperable valve shall be .ecorded daily.
.3.. If Specification 3.7.D.1 and 3.7.D.2 cannot be met, initiate normal orderly shutdown
- and have~ reactor in the cold shutdown condition within 24 hours.
a b 3.7A.7 lW au
30 LIMITim CONDITIo:C FVR OPERATION h.O SUF/ETTJANCE REQUIRDENTS 3 13 IIf5ERIICE IIGPECTION AND TESTIM h.13 INSEFIICE IICPECTION AND TECTIM App:Leab11ity: Applicability: Applies to carponents which am part of Applies to the periodic inspection and the reactor coolant pressure boundary and testin6 of coc:ponents which am part of , their supports and other safety-related the reactor coolant pressum boundag pressure vessels, piping, pu=ps, and and their suppo cs and other safety-valves. related pressur- vessels, piping, pumps, and valves. Objective: Objective: I To assure the integrity of the reactor To verify the integrity of the reactor coolant pressure bounday arri the coolant pressum boundary and the opemtional readiness of safety-related operational readiness of safety-y pressure vessels, piping, pu=ps, and m lated pressure vessels, piping, pu=ps, to valves, and valves.
-a Spacification: Soacification:
A. Inservice Inspection A. Inservice Inspection
- 1. 1. Inservice inspection of Quality To be considered operable, Quality Group A, B, and C components shall Group A, B, and C components shall be perfor=ad in accordance with satisfy the requiremnts contained the requiren?nts for ASME Code Class in rection XI of tha ACiG Boller 1, 2, arxi 3 hvorents, respectively, i and Pressure Vessel Code and appli-contained in rection XI of the AS;E enble Addenda for continuad service Boller and Pr?asure Vessel Code arri of ACME Code Class 1, 2, and 3 cc=po-applicable Addernia as required by nents, respectively, except where relief has baan requested f rom the 10 CFR 50, Section SO.55a(g), except where relief has been requested from Cor: mission pursuant to 10 CFR 50, Section 50 55a(g)(6)(i). the Comission pursuant to 10 CFR 50, Section 50 55a(g)(6)(i),
4 i 313/h.13 189R
30 LU4ITING COriDITIO?U FOR OFEFATION h.O SUF/ETT.TANCE REQUIBDEITES
- 2. For Non-Conforcini- Iines which ara not Service Gensitive, inspections raquirad by h.13. A.1 during the first lO-year inspection interml shall be completed by the end of the 1978 refueling outage. If these examimtions reveal no incidence of stress corrosion crnektrg, the examinntion schedule =ay revert to that specified in h.13.A.l.
- 3. For Non-Confornirg Lines which am Sarvice fansittve:
- a. The velds and adjoinirg amns of bypass y piping of the discharge valves in the main to 03 meirculation loops, and of the austenitic st tinless steel ranctor core spray piping up to end includirc the sewnd irolation v'lve, shall be examined at each rasctor mfuelirg outve or at other schadulad or unschaduled plant cold shutdowns. Successive examinations need not be closer thrtn six mnths spa d. In the event thrra successive e7aminations fird the piping fme of unacceptable indications, the exeelnettion
=ny be extendad to each 36 mnth interval, plus or minur 12 nonths, vinriding with a refuelirs outage, and any be limited to one bypass pipa run aid one rasctor core epmy pLpe run.
313/h.13 1893 PZi
LIMITIrn cOreITIOrG FOR OPERATION h.0 SUR7EILIANCE RBif1IRD(EN15 30
- b. If Service Sansitive Lines other than those listed in L.13.B.3.a above are identitled, the velds and ad. Joining areas of this piping chall h subjected to examination at cach reactor rafueling outage or at other schaduled or unschadaled plant cold shutdowns on a sa=pling basis. Successive examinations naed not be closer than six months apart. If unaccaptable flav indications are detectad in any bmnch run, the remining branch runs with similar functions and configumtions shall be examined. In the event three suc-cessive examinations find the piping free of unacceptable indications, the examination schedule may revert to that specified in Y
n> 4.13.A.1 vith the exception that all examina-w tions nomally con:pleted over a ten-year interval shall be co=pleted each 80-month period. Bo Inservice Testing of Pumps and Valves B. Inservice Testing of Ptanps ard Valves
- 1. To be considered opemble, Quality 1. Inservice testing of Quality Group Group A, B, and C pumps and valves A, B, and C ms and valves shd1 be shall satisfy the mquirements con- performed in ecconiance with the tained in Section XI of the ASME Doller requiremants for ASME Cole Class 1, and Pressure Vessel Code and appli- 2, and 3 pu=ps and valvac, respectively, cable Addenda for operability of contained in Section Xi of the ASME ASME Code Class 1, 2, and 3 pumps Boiler and Pressure Vessel Code and and valves, respectively, except applicable Addenda as required by where relief has been requasted from 10 CFR 50, Section 50 55afg), axcept the "ocnission pursuant to 10 CFR 50, whem relief has been reo&2ted from Sect *on SO.55a(g)(6)(i). the Cotnission pursuart '.010 CFR 50, Section 50 55a(gX6'.1).
313/h.13 189T _m _
. -. _ _ . .. .-.._-. . . .- - . . . ~ - _ = _ . . _ _ - . -- . ..
r Bar;es 313 and h.13: he inservice inspection ermi testing pmgran confoms to the requiments of 10 CFR 50, Section 50 55a(g). Where pmetical, the inspection sad testing of components classified into NRC Quality Gmups A, B, and C vill confom to the requirements for ASME Code Class 1, 2, and 3 cocponents contained in Section XI of the ASME Doller and Pressure Vessel Code. Using Pegulatory Guide 1.26, Revision 3, " Quality Gmup Classifications and Standards for Water, Steam, and Padioactive-Vaste-Containing Components of Nuclear Power Plants," as a Eulde, all Monticello components have been classified into Quality Gmups. Bis classification serves as the basis for detemining which ASME Code Class inspection and testing requirements are applicable to a given coc:ponent. 10 CFR 50, Section 50 55a(g) requires components which are part of the reactor , coolant pressure boundary and their supports to meet the inservice inspection and testing requirements ' applicable to components classified as ASME Code Class 1. Other safety-related ccmponents must meet the inservice inspection and testing requirements applicable to components classified as ASME Code Class 2 or 3 He inservice inspection pmgmm must be updated at 40 month intervals. The pmgram for testing w pu=ps and valves for opemtional readiness must be updated every 20 months. A description of the OO updated progreme should be submitted to the IGC for review at least 90 days before the start or each period. A suggested romat for this description is contained in Appendix A to reference (1).
- The inservice inspection and testing program must, to the extent prsetical, comply with the l mquirements in editions and addenda to the AEME Code that are "in effect" no mor= than six months before the start of the period covered by the updated pro 6rs=. The term "in effect" means both having been publiehed by the ASME, and having been referened in parsgraph (b) of 10 CFR 50, Section 50 55a. If a code mquired inspection or test is impractical, requests for deviations are submitted to the Commission in accordance with 10 CFR 50, Section 50 55a(g)(6)(1). ,
;- he infomation specified in Appendix B to refemnce (1) should be submitted for each deviation
- requested. Deviation requests should, if possible, be submitted to the NRC f ar revia at 1-ast 90 days tefore the stort of each period. Deviations identified during an inspection reriod may be gmuped and requested at the end of each calendar quarter. It is expected thm- a san 11 number of deviations vill be identified during the inspection period, particularily th" first period when new inspection and testing techniques vill be utill:ed. A requested devietion request may be considered acceptable to the Co=aission until a romal disapproval has been received.
I \ 313A.13 PASES 189U REv
s Pares 313 and 14.13 (continued): Small, hairline cracks in austenitic stainless steel piping in BWR racilities has been observed on several occasions. Data indicates that Typa 304 sustenttic stainless steel piping in 1 the reactor coolant pressum boundary or the boiling vater reactor is suscaptible to s+.cass corrosion c racking. Such cracking is caused by a combination of significant amounts or oxygen in tha coolant, hirh stresses, and some sensitization or metal adjacent to walds. Cracks have occurred in the heat affected zones adjacent to welds, but are not expected to occur outside these amas, provided the pipe material is properly annealed. Pipe runs containing stagnant or low velocity fluids have been observed to be mom susceptible to stress corrosion cracking than pipes containing a continuously riovin6 fluid during plant operation. Historically, these cracks have been identified either by volumatric examination, by lesk detection systems, or by visual ingection. Because of the inherent high material toughness or austenttic n'ainless steel piping, stress corrosion cracking is unlikely to cause a rapidly propagating railure resulting in a loss of coolant accident. Although the probability that stress corrosion cracks will propagate far enough to create a significant safety hazani is slight, the pmsence or such cracks is undesirable. The following steps hav- been taken-to minimize this problem:
- 1. Where practical, pipe runs constructed or mterial susceptable to stmss corrosion erneking and Y vhich contained stagnant or lov velocity fluid have D been replaced with mterials not susceptable to cracking or they have been eliminated.
- 2. She reactor coolant laakage detection tecimical specifications have been amended to enhance the ability to detect unidentified leakage that may include through-wall cracks.
- 3. The program of inservice inspection has baan aur;nented to increase the probability or emek detection in lines susceptable to stress corrosion crnekirg.
This progmm conforms to the Coc:=ission?s guidelines for plants with operating licenses i: Jemnce 2). Rere mnces:
- 1. letter from D. L. Ziemann, Qiter, Operating Reactors Branch f2, USNRC, to L. O. thyer, ESP, dated November 214, 1976.
- 2. NURE-0313, " Technical Beport on ihterial Selection and Prucessirs Guidelines for BWR Coolant Pressure Boundary Piping," July,197T.
3 13/14.13 . BASES 169v t_ -.
SECTION 6 QUALITY GROUP C1/SSIFICATION DRAWINGS System __ Faf'e
-)
hin Steam byctem 6-2 feedvater System 6-3 heactor Recirculation System 6-L Core Spray System 6-5 hesidual Heat Eemoval Syste loop A 66 hesiduni Heat Eemoval System loop B 6-7 High Pressure Coolant Injection System (steam side) 6-8 High Pressure Coolant Injection System (vater side) 6-9 RCIC (steam side} 6-10 RCIC (Water side) 6-11 Standby Liquid Control System (-12 Primary Containment System 6-13 Ibergency Service Water 6 14 RHR Service Water 6-15 CRD Hydraulie Control Unit 6-16 Control Rod Drive Syst6m 6-17 Fuel Pool Cooling & Clean-up System 6-18 Compressed Air System 6-18 Condensate Service System 6-18 Reactor Building Cooling Water Syctem 6-19 heactor Vater Clean-up System 6 19 Liquid Fadvaste System 6-19 Traversing In-core Probe System 6-20 Excess Flow Check Valves 6-21 l Key IndicatesQuality Indicates Quality
*- Group B Group A i
b Indicates Quality nmnp r >- l Revision 3 6-1 2/26 m
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\ Recombiner System g MS-24-1 _
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. [ CV-1243 N { t_ a T4_ Line A & B Only k XD 1 l
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