ML20196A930

From kanterella
Jump to navigation Jump to search
Rev 3 to 80A8616, Inservice Insp Program Plan,Rcic Sys,Shoreham Nuclear Power Plant Unit 1. W/Two Oversize Drawings
ML20196A930
Person / Time
Site: Shoreham File:Long Island Lighting Company icon.png
Issue date: 01/25/1988
From:
NUCLEAR ENERGY SERVICES, INC.
To:
Shared Package
ML20196A839 List:
References
80A8616, NUDOCS 8802050211
Download: ML20196A930 (27)
v • d • e


Text

_ _ - _ _ _ _ _ _ _ . _ _ _ _ _ _ . _ _ _ _ _

M NUCLEAR ENERGY SERVCES DOCUMENT NO. ROARAIA REV.3 1 PAGE I OF 8 i

'w.J INSERVICE INSPECTION PROGRAM PLAN REA", TOR CORE ISOLATION COOLING SYSTEM SHOREHAM NUCLEAR POWER PLANT UNIT 1 Prepared For LONG ISLAND LIGHTING COMPANY c/

^

l 1

ProKt Application Copy No Assigned To 5536 APPROVALS j TITLE / DEPT. SIGN ATURE - D ATE l

REV NO PREP ARED BY Proj. Dept.

u,nn one m n,ane OA 3(n nn on e _

~ ~

o 1

w

. 'I >

3 as,de.sLM %,.%%i" M67j* a9256$"

4 5

6

_,, ,,r ,, , pn ppgTJ 7

{$i Va {dldu uus a

_ _ _ ,, men 8

r

ws U k[QM hf Eb N IN b to B00129

?$R*S0$&050003p G

PD l I FIRM ONES204 t/84

a e ggg REVISION LOG NUCLEAR ENERGY SERVICES, INC. PAGE

- 8 ^86

2 OF 8 l [- DATE "^[

y DESCRIPTION APP ROV A L 1 7/10/84 -

See CRA 4453 Revision includes hM6, h editorial changes and the addition of new information ,

2 5/8/85 Fig. 8616-2. See CRA 5295 [/)hj 3 1/25/88 4,7. 0 See CRA 6725 [h I >

l l

4 l

FORM *Nti 206 ? 810

DOCUMENT NO. ROAR 616 PAGE ? OF R

"" NUCLEAR ENERGY SERVICES TABLE OF CONTENTS PAGE 4

1. INTRODUCTION 4
2. CLASSIFICATION 4
3. EXEMPTIONS 5
4. EXCEPTIONS 5
5. CALIBRATION STANDARDS PROGRAM PLAN AND SCHEDULE 6 6.

PRESSURE TESTS 7 7.

ISOMETRIC FIGURES AND SKETCHES 7 8.

S

9. AUGMENTED REQUIREMENTS Tables 4

3-1 Exemptions 4-1 Exceptions 5 5-1 Calibration Standards 6 6-1 Section XI Examination Schedule 7 Isometric Figures 8 8-1 Appendix A 1

l 1

O FOAM e NES 205 2/80

any DOCUMENT NO. Stn A R A f A PAGE i, y 3 NUCLEAR ENERGY SERV)CES 1

i l

1. INTRODUCTION )

This document presents the Inservice Inspection Requirements for the Reactor Core Isolation Cooling System of the Shoreham Nuclear Power Plant.

The General Text, NES Document Number 80A8608 presents the basis for the Inservice inspection Program and a more detailed descr.iption of the Inservice Inspection Program Plan than is contained in this document.

2. CLASSIFICATION l

l The Reactor Core Isolation Cooling System piping and instrumentation diagrams have l been reviewed and Quality Group A and B boundaries have been established in accordance with Regulatory Guide 1.26 Rev 3. These boundaries are shown on Figures 1 FM-22A-ISI and FM-22B-ISI.

rm

3. EXEMPTIONS The portions of the Reactor Core Isolation Cooling System that are exempted from the volumetric and surf ace examinations of Section XI are listed in Table 3-1.

TABLE 3-1 i EXEMPTIONS f

i Quality Component Basis for Boundary Group Description Exemption Diagram A All piping 1 inch IWB-1220(b) FM-22A-ISI nominal pipe size and smaller B All Piping 4 inches Code Case FM-22A-ISI nominal pipe size N-408 (a) (1) and and smaller FM-22B-ISI pony EMS 205 2/60

DOCUMENT NO. 3;g;;;;

g 1 NUCLEAR ENERGY SERV)CES PAGE

- OF -

o l

s

4. EXCEPTIONS For those examinations in the Reactor Core Isolation Cooling System that cannot be completed in accordance with the Section XI requirements a relief request will be prepared and submitted to the NRC. Those areas for which a relief request has been prepared are listed in Table 4-1.

TABLE 4-1 EXCEPTIONS Component Component Fig. Relief Identification Description N o. Request Rem arks l None G

5. CALIBRATION STANDARDS Table 5-1 lists the Calibration Standards for ultrasonic examinations scheduled for the Reactor Core Isolation Cooling System.

TABLE 5-1 Calibration Standards Title Size Material Drawing 03-080-CS 3" SCH. 80 SA-106, GR. B NES 80C0513 06-120-CS 6" SCH.120 SA-106, GR. B NES 80C0519 l

l l

9 FORM s NES 205 2/80

DOCUMENT NO. goggc!c .

my PAGE g 05 3 NUCt. EAR ENERGY SERVICES l l

6. PROGRAM PLAN AND SCHEDULE The specific Reactor Core Isolation Cooling ISI examination requirements are defined by the Program Plan and Schedule Tables. This Program Plan lists all the required examinations for a 10 year interval of 3 periods of 40 months each. Table 6-1 presents a summary of these Section XI required examinations scheduled by different Code categories applicable to this system.

Each weld and component is aesignated by a unique identification riumber, and then described. Also identified is the applicable examination procedure number, Code category and number, examination method, and the calibration block, if required. Any comments specific to a component are noted in the remarks column.

Examination items are divided according to the Isometric figure on which they appear O and are listed following the direction of flow in the pipe. Multiple examination requirements of the same component are listed together in the schedule tables.

Augmented examinations are listed af ter the Section XI examinations for each period.

Where the augmented requirements overlap the Section XI requirements the component is listed in both places, however, a note is added in the augmented section stating that the augmented requirements are met or exceeded by the Section XI requirements.

O FORM e NES 205 2/80

DOCUMENT HO. gnaget MGE 7 OF g NUCLEAR ENEPGY SERVlCES F TABLE 6-1 SECTION XI EXAMINATION SCHEDULE REACTOR CORE ISOLATION COOLING SYSTEM Component Code Examinations by Total In Period Description Category Pg P 2

P Total System 3

Bolting < 2" B-G-2 1 1 1 3 3 g

Piping welds (circumferential) B-3 2 3 3 8 31 Valve Bodies B-M-2 1*

  • 0 0 1 1 System Leakage Test B-P * * * - -

System Hydro Test B-P 0 0 1 1 -

Integral A:tachments C-C 1 0 0 1 1 l Piping Welds (circumferential)* *

  • C-F-2 1 2 2 5 83(7)@ I

)

System Leakage Test C-H I i 1 3 -

System Hydro Test C-H 0 0 1 1 -

l Leakage Test is required at each ref ueling outage.

    • Deferral of these examinations to the end of the interval is permissible.

I I *** Weld selection in accordance with Code Case N-408.

@ Only 7 welds require any nondestructive examination in accordance with Code Case N-408.

l

7. PRESSURE TESTS In accordance with Section XI all Quality Group A pressure retaining components are to receive a leakage test in accordance with IWB-5221 every refueling outage, all Quality Group B pressure retairting components are to receive a leakage test in accordance with IWC-5221 every period (40 months), and both Quality Group A & B pressure retaining components are to receive a hydrostatic test in accordance with IWB-5222 and IWC-5222 respectively at or near the end of the interval. The portions of the Reactor Core Isolation Cooling System requiring these pressure tests are those marked Quality Group A & B including lines 1 inch and less on boundary diagram FM-22A-ISI and FM-22B-ISI.

8.150 METRIC FIGURES AND SKETCHES The piping isometric figures listed in Table 8-1 show the identification and location of areas for :he Reactor Core Isolation Cooling System requiring examination. Sketches FOW s NES 205 2/00

DOCUMENT NO. AnARAf 6 r m  !

11 NUCt. EAR ENERGY SERVICES MGE  ? OF R I

may also be included that illustrate or locate areas of components requiring  ;

identification for examination. Boundary Diagrams are provided to show the Quality l Group boundaries and also to define those areas requiring pressure testing under Code Category B-P and C-H.

TABLE 8-1 ]

Isometric Figures l 1

8616-1 Rev.1 8616-2 Rev.3 d l

l Boundary Diagrams l

FM-22A-ISI Rev.I l i

FM-22B-ISI Rev.1 CN 9. AUGMENTED REQUIREMENTS V

l Following are the augmented requirements that apply to the Reactor Core Isolation Cooling System. i 9.1 NUREG-0800 (Break Exclut. ion Piping)

All welds that fall between the "Break Exclusion Boundary" and the penetration have been scheduled evenly among the 3 periods. These welds appear under the headings. period 1 A, 2A, and 3A. Where a weld has already been scheduled for examination because of Section XI requirements, the weld is listed again with a reference to the Section XI listing.

O FOAM eNES 205 2/00

O l

l APPENDIX A O .

1 4

O e

  • r- - , ---- - _ __ _ ___ __

DOCUMENT NO. SOAS616 0 ' 0' NUCLEAR ENERGY SERVICES APPENDIX A Table of Contents Number of Pages

1. Program Plan Work Schedule Tables 1

Period 1 1

Period 1 A (Break Exclusion) 1 Period 2 1

Period 2A (Break Exclusion)

Period 3 i 1

Period 3A (Break Exclusion)

2. Isometric Figures 8616-1 8616-2
3. Boundary Diagrams F M-22A-ISI FM-22B-ISI The following notes apply to the Program Plan and Schedule Tables.

Note 1 - The valve internal surface examination (B-M-2) has been scheduled for the first period, however the examination may be performed at any time during the interval when the valve interior is accessible.

Note 2 - This weld is scheduled for a Section XI examination which meets or exceeds the agumented requirement and is !!sted here only for continuity.

O l

FOAM s NES 2M 2/80

\

5 O

PERIOD.

1 O

O 4

O O O

~

SHOREHAM NUCLEAR POWER STATION SYSTEM: REACTOR CORE ISOLATION COOLING ISI PROGRAM PLAN AND SCHEDULE PERIOD 1 NES ISO NUISER 8616-1 80A8616 REV. 3 PAGE 1 OF 1 I l l I l 1 l l CODE I l l COMPONENT I SIZE I COMPONENT  ! PROC. I CAL. l 00DE I 00DE lEXAM i REMARKS I I IDENTIFICATION l (IN) l DESCRIPTION 1 NO. I BIDCK  ! CAT. I NO. IMETH !  !

I I I I I I I I I I T T E51-MOV-035-b <2 VALVE MOV-035-BOLTING 80A3133 N/A B-G-2 B7.70 VT-1 E51-1676-4E 6 PIPE 10 ELBOW 80A3131 06-120-CS B-J B9.11 Ur 80A3132 PT E51-1676-5A 6 ELBOW 10 PIPE 80A3131 06-120-CS B-J B9.11 Ur 80A3132 PT E51-Mov-035 6 VALVE-INTERNAL SURFACES 80A3133 N/A B-M-2 B12.50 Vr-3 SEE NOTE 1 E51-PSA-014 6 INTEGRALLY WELDED ATTACHMENT 80A3132 N/A C-C C3.20 PT E51-IC-68-FW10 6 PIPE TO VALVE E51-MOV-035 80A3131 06-120-CS 80A3132 C-F-2 C5.51 Ur PT g

e t

t 4

l i

I 1

. PERIOD 1A l (BREAK EXCLUSION) ,

I i

l 4

i l

1

! l i

i l

1 l

l l .

l l_._. .., . - _ . ~ - _ __ . . , _ . . . _ _ _ _ , , _ . _ . - _ . _ _ . . . . . _ . _ _ _ _ _ _ _ _ _ _ . _ _ , _ , _ ,

O O O

~

SHOREHAM NUCLEAR POWER STATION SYSTEM: REACTOR CORE ISOLATION COOLING ISI PROGRAM PLAN AND SCHEDULE PERIOD 1A NES ISO NUMBER 8616-1 80A8616 REV. 3 PAGE 1 OF 1 1 I I I I I I [ CODE I I

! COMPONENT I SIZE I COMPONENT I PROC. I CAL. I CODE 1 00DE IEXAM I REMARKS I l IDENTIFICATION l (IN) I DESCRIPTION I NO. I BLOCK l CAT. I NO. IME111 1 I I I I I I I I I I I E51-1676-4E 6 PIPE TO ELBOW 80A3131 06-120-CS B-J B9.11 Ur SEE NOTE 2 E51-1676-4F 6 ELBOW 10 PIPE 80A3131 06-120-CS B-J B9.11 Ur E51-IC-68-FW14 6 PIPE TO ELBOW 80A3131 06-120-CS B-J B9.11 Ur E51-1676-5A 6 ELBOW 10 PIPE 80A3131 06-120-CS B-J B9.11 UT SEE NOTE 2 E51-IC-68-FW13 6 PIPE 10 ELBOW 80A3131 06-120-CS B-J B9.11 UT T

m __ _ _ _ _ _. _ _ -_ _ _ _ _ . - - _ _ _ _ . - _ _ . - _ _ _ _ - _ _ _ _ - -- - - - n -

-e. e - * - - - -. m w e

\

l I

O

- PERIOD 2 O ,

i 1

i l

i i

r l

l l

I I

w y y _ _ ,,__.m--_ . - - _ - , .-.- ,. ,___ .___,,_

O O O

~

SHORDIAM NUCLEAR POWER STATION SYSTEM: REACTOR CORE ISCt.ATION (I)0 LING ISI PROGRAM PLAN AND SCHEDULE PERIOD 2 i NES ISO NUMBER 8616-1 80A8616 REV. 3 PAGE 1 0F 1

, w w w {

l i I I I I I ICODE l l l COMPONENT I SIZE I COMPONENT I PROC. I CAL. I CODE I CODE IEXAM I REMARKS I I IDENTIFICATION l (IN) I DESCRIPTION l NO. I BLOCK I CAT. I NO. IMETH I l 1 1 I I I I I I I I E51-MOV-041-b <2 VALVE lOV-041-BOLTING 80A3133 N/A B-G-2 B7.70 VT-1 E51-IC-60-W3 3 PIPE 10 VALVE E51-MOV-041 80A3132 N/A B-J B9.21 PT E51-261-F 3 ELBOW 10 PIPE 80A3132 N/A B-J B9.21 PT E51-IC-68-W11 6 VALVE E51-MOV-03510 PIPE 80A3131 06-120-CS B-J B9.11 Ur 80A3132 PT E51-1675-A 6 PIPE TO H. BOW 80A3131 06-120-CS C-F-2 C5.51 Ur 80A3132 PT E51-1675-C 6 ELBOW 10 PIPE 80A3131 06-120-CS C-F-2 C5.51 Ur 80A3132 PT w

4e..- a - - 4 e,JL .--- .4 -- 2---e a-s,,+---a-4..msa - s-.- _a_-,-2.a---em -.~nAa . a k a s %

O f

1

) i I

I l

I 1

4 l

l v

PERIOD 2A .

i (BREAK EXCLUSION) i l

4 i

I l

.I I

i

)

j d

i 4

I f

1 1

l 3

i

O O O SHOREHAM NUCLEAR POWER STATION SYSTEM: REACTOR CORE ISOLATION COOLING ISI PROGRAM PLAN AND SCHEDULE PERIOD 2A NES ISO NUMBER 8616-1 80A8616 REV. 3 PAGE 1 OF 1 I I I I I I I l CODE ! l l COMPONENT I SIZE I COMPONENT I PROC. I CAL. l 00DE l 00DE lEXAM ! REMARKS I I IDENTIFICATION I (IN) i DESCRIPTION I NO. I BIDCK 1 CAT. I NO. IMEIII I I 1 I I l l l 1 I l l E51-IC-68-FW11 6 VALVE E51-MOV-035 TO PIPE 80A3131 06-120-CS B-J B9.11 W SEE NOTE 2 E51-1676-4G 6 PIPE TO ELBOW 80A3131 06-120-CS B-J B9.11 W E51-1676-4H 6 ELBOW ID PIPE 80A3131 06-120-CS B-J B9.11 W E51-1676-4C 6 PIPE TO ELBOW 80A3131 06-120-CS B-J B9.11 W E51-1676-4D 6 ELBOW 70 PIPE 80A3131 06-120-CS B-J B9.11 W

4-.->w-, a m A m -.~a - a a-- - a _ ,_- ., _ ,, . n.. - - - , - - - - , - -

.- ___ y O

e i

l 4

i

. PERIOD 3 I

d e

4 l

l l

l l

l

- _ _ . . .- .l

O O O

~

SHOREHAM NUCLEAR POWER STATION SYSTEM: REACTOR CORE ISOLATION COOLING ISI PROGRAM PLAN AND SCHEDULE PERIOD 3 NES ISO NUPEER 8616-1 80A8616 REV. 3 PAGE 1 OF 1 I i i i l I i ICODE!  !

I COMPONENT l SIZE I COMPONENT I PROC. I CAL. I CODE l 00DE lEXAM I REMARKS 1 1 IDENTIFICATION I (IN) I DESCRIPTION  ! NO. l BIDCK I CAT. I NO. IMETH I I I I I I I i 1 I I I E51-MOV-042-b <2 VALVE MOV-042-BOLTING 80A3133 N/A B-G-2 BT.70 VT-1 B21-NS001-BW12 3 W-0-L 10 PIPE 80A3132 N/A B-J E9.21 PT E51-259-E 3 ELBOW TO PIPE 80A3132 N/A B-J B9.21 PT E51-IC-60-FW2 3 PIPE TO ELBOW 80A3132 N/A B-J B9.21 PT E51-1686-A 6 6X4 REDUCER TO PIPE 80A3131 06-120-CS 80A3132 C-F-2 C5.51 Ur PT g

E51-1675-B 6 ELBOW TO ELBOW 80A3131 06-120-CS C-F-2 C5.51 Ur 80A3132 PT

__._._ __ __ __ _ . - _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ , - - ~ _ ---

e

  • O l l 1

PERIOD 3A (BREAK EXCLUSION) _

i 4

l i

l i

)O 1

1 1

l 9 I

O O O

~

SHOREHAM NUCLEAR POWER STATION SYSTEM: REACTOR (X)RE ISOLATION 000 LING ISI PROGRAM PLAN AND SCHEDULE PERIOD 3A

. NES ISO NUMBER 8616-1 80A8616 REV. 3 PAGE 1 0F 1

! l l 1 1 I I ICODE I l l COMPONENT I SIZE I COMPONENT I PROC. I CAL. I CODE I CODE lEXAM i REMARKS I I IDENTIFICATION 1 (IN) l DESCRIPTION  ! NO. I BLOCK I CAT. I NO. IMEIH !  !

I I I I I I l 1 I I E51-IC W1 3 PIPE 10 PIPE 80A3131 03-080-CS B-J B9.21 Ur l

E51-IC-61-W2 3 PIPE 10 VALVE E51-MOV-042 80A3131 03-080-CS B-J B9.21 Ur E51-IC-61-W3 3 VALVE E51-MOV-042 TO PIPE 80A3131 03-080-CS C-F-2 C5.51 Ur 3

E51-263-B 3 PIPE TO ELBOW 80A3131 03-080-CS C-F-2 C5.51 Ur E51-263-C 3 ELBOW 10 PIPE 80A3131 03-080-CS C-F-2 C5.51 Ur 1

1

O SYSTEM

,O ISOMETRIC F/GURES a

1 1

2

. O 1

l 1

L___--__-.__-._--__._.._..___-_..._-_-___-.--.....--_--__--,

i O E61-210-9 O O ~

ESt-2eO-C Es t-eC-SO4W2 ES t-2SS-64 I

" Est-2SO4 m ,

C' \ _ n. '5:'* .

~E 81-2004

f. gyp-g-eOth*1 h

fESt-203-3 e-E s t HC-e t-F W 3 Est e $,4-oS. o 5 ** '

5 0* CO.NTEIG 2 'MADe STEAM se to-t (A) M St-2Se-C 1 .' s 04g a:.;;::o t E51 ....e o'4 , 82 0-es4001-8W 12H ' S1-260-0 E s t-eC-S t -f w2 9 gg,_2See

> Est-2eo-M ,

E S ,-tC_ .1-,W t s *

<. Ess-2eo-t Est-x-te

    • _c- N E5 t-tC-004W3 E S t-sC-co4We esO CossT. Foo. E s t-EC-oo-fWS E S t-20 t 4 E S t-2814 eESt-tete-SA E S t-4C-se-f W le - 1 , 47, b 'S

$ *- WR 8018 - 9 _ ,g Op ES9-,.r.- - . ,8 , -te.es.,, , ,

ES ,-,e re-4E - J -

Es t-ier -.o ,

Esi-tere-4C e0 -xCO,n.Fis.

ESt-14Te-4H 7 8e18-4 ES t- te FG-40 E41Me784 ES,-,C.08-,W,, /  % rESi-serS-a ES9 e"we 8

  1. 3; Mov g-03s ES t-4C-es-fw l0 E S t - t e TS-C * >

ESt-teTS-f E S t-tC-4.-FWG .g E' #^4 '*

enEF. OWGS .

sC-ooseas IC-estsAS SC-81#12AS ES t-tese-A Saw PsPE STRESS WORK 4"M4" RED. e=e== ***

SKETCH AM-30AS AM2M

  • RCsC -STEAnd SUPPLY AtsO PUMP OtSCMARGE 900 COstT. Pet. ., ,e.e se10-9 se PSS ==e sja6fay
    • $ E *"*. l[d
  • SHOREMA04 arma

_ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -.-______.__ _ - _ _ _m___ ___m____ __ _

O O '

es fS9-2..-N r E . 9 -8C- F t -F.3 g _, g,,

e s ggi I /

R o.D.

../

E . t *' .. -G w g Est-2 6-at 8 9-3..-9 " >

IE S S-2 5-ed A - ...-,..-.

I F e s e +..*-o3 e tes-se.-w "

r e s-eC-r :44

....c., . . . -.C- r . 4 3 a.i-e..-as on ,

  • =
e. .-e. -an 1 " ' +"* ' ] ao co r =

?

, e s e - s..-t e. -s.r-c ,,,

ESt-9..-Cd asOW .g*3 #,,

E S t -4C- F 9 -F .. 002 q*

e..-e.. . 6

.**E 3"ftto. " ' '

. . . e,.

seO COneT. fse.

Q #C.aC.T.um . U ,sef

...-.e.,,-..

E 6 s -2..-F *

<p,,- +

\ .# y

. "E 31sT E E w o .* ... T ...

< +'

..-e.. 3 7 e . . c - r . -,. . . - 1 ,s g

e..->..-L. . . . . . .

seO COesT. Fse.

...-... .. A p7 m.......

< o.

.C-.., ..

h I

RCaC-.TE AM .UPPLY III Ass 0.TEmes ExnaveT es. 3 == me n.-2 e

th esse W%

-e 4 4 m eow l

=

.seontmans e

_.e_

-s-,a--Me&- m.*-r wA=m n-aAM-m --4AA-JA " ^ --m- --~ .m---w anm &-A--*' su*em+ A mom-A--.s-,,s .-ma--uw- -_u->,,m3, a-..b- - _ - - 4= -=-a_.-,,.AAa_ --- ----AA--- --

o .

(

t O

)

i i

SYSTEM O BOUNDARY DIAGRAMS j

'l 1

l 4

1 s

l

!, O -

1 i

OVERSIZE DOCUMENT
PAGE PULLED 4

l SEE APERTURE CARDS NUMBER OF OVERSIZE PAGES FILMED ON APERTURE CARDS l

I APERTURE CARD /HARD COPY AVAILABLE FROM RECORD SERVICES BRANCH j FT5 492-8989 l

1 1 1 1

1 I

l

. _ - _ _ - - - , _

Retrieved from "https://kanterella.com/w/index.php?title=ML20196A930&oldid=2987647"