ML19320D508
| ML19320D508 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 07/10/1980 |
| From: | Linder F DAIRYLAND POWER COOPERATIVE |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| References | |
| LAC-7022, NUDOCS 8007210447 | |
| Download: ML19320D508 (18) | |
Text
-
3 D ~ DAIRYLAND h
[k COOPERAT/VE
- P.o. BOX 817 2615 EAST AV SOUTH. LA_ CROSSE. WISCONSIN 54601 (608) 768 4 000 July 10, 1980 In reply, please refer to LAC-7022 DOCKET NO. 50-409 Mr. Dennis M. Crutchfield, Chief Operating Reactors Branch #5 Division of Operating Reactors U.
S. Nuclear Regulatory Commission Washington, D. C.
20555
SUBJECT:
DAIRYLAND POWER COOPERATIVE
~
LA CROSSE BOILING WATER REACTOR (LACBWR)
PROVISIONAL OPERATING LICENSE NO. DPR-45 REVIEW OF RCS PRESSURE BOUNDARY STAINLESS STEEL PIPING AND FITTING MATERIAL
REFERENCES:
(1)
NRC Letter, Reid to Madgett, dated September 29, 1977 (2)
Technical Report on Material Selection and Processing Guidelines for BUR Coolant Pressure Boundary Piping (NUREG 0313),
dated July 1977.
(3)
DPC Letter, Madgett to Reid, LAC-5180, dated February 20, 1978.
Dear Mr. Crutchfield:
Reference (1), which transmitted Reference (2), requested the La Crosse Boiling Water R63ctor (LACBWR) to perform certain actions' with regard to reactor. coolant pressure boundary piping.
Reference (3) contained responses to various positions of NUREG 0313.
Attechment C l(a) of Reference (3) referred to NUREG 0313,Section III.2.A. and that LACBWR had completed requirements for accelerated examinations.of non-service sensitive steel lines and that subse-quent inspections of these lines would be in accordance with ASME Section XI schedule as modified by Technical Specifications.
Attachment C.l(b)1. of Reference (3) referred to NUREG 0313 Section-III.2.B(2) and that LACBWR would perform augmented exr.mina-tions of those service sensitive positions of bypass lines of discharge valves in the main circulation loops and reactor core spray system piping.
Table I lists the system, weld number, type.
of examination, and year performed for all the welds in this category of service sensitive lines.
~
, :8.007210 $ f
~..
' 3 7
i 4
b Mr. Dennis M._Crutchfield,-. Chief.
~
' Operating. Reactors Branch 45 LAC-7022 1 Division of< Operating-Reactors July 10, 1980 4
Examinations ' have been conducted at various times during ' the
- 10-year inspection interval and every weld within this service-sensitive : category has been examined at least.once, most more than once.._ The - examinations conducted in 1978 and 1979. cover every Lweld in this category.
October 31, 1979, ended.the 10-year
~ inspection interval without an unacceptable indication being found
- on any-weld..
Attachment _C.l(b)2.- of Reference '(3) referred to NUREG 0313 Section:III.2'B.(3), other service sensitive piping, and that LACBWR would perform augmented examinations on all the welds in those systems becau'se they are not considered to have branch runs to which random ' sampling would be applicable.
Table II lists ~the systems-in this service sensitive category as
^
well as weld numbers, type of examination and year performed.
Examinations have been. conducted at various times during the 10-year inspection interval and every weld in this service-sensitive category has been examined at least once.
Every weld in this
-category was examined in 1979, and none exhibited an unacceptable indication.
LACBWR has completed 10 years of operation without having any of the ' welds inthe RCS piping developing a leak or even finding an unacceptable indication during in-service examination.
All welds 4
in-the-service sensit've' piping have been subjected to 10 years of l
operation, and all w te examined either ~ in 1979 or 1978, all with-out evidence of stress corrosion cracking.
.This 10-year inspection ~
_ period covers a longer period of time than the weld inspection i.
requirements _ of NUREG 0313, which_ requires an augmented inspection
~
frequencyf of once each outage for 3 successive outages in a period of'3. years.
The LACBWR RCS leak detection program is far more restrictive with regard'to allowable leakage limit and' sensitivity'than the Model Technical. Specifications of Reference (1).
If a leak ~did occur, L
.it would be promptly detected. ' Corrective action would be taken sto isolate the leak and place 'the reactor in a shutdown mode to perform 'the. necessary inspections and _ action to repair the
- defective component.
Other considerations, reasons, and programs
-that have contributed"to the1 excellent performance of stainless steel piping in service sensitive lines at.LACBWR are as follows:
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fmri Dennis'M.LCrutchfield,: Chief
- Operating Reactors ~BranchLf5' LAC-7022.
Division of(Operating Reactors July 110, 1980 (1)- Furnace' sensitized-safe-ends:on the reactor vessel and
.~
cprimary piping
- system pressure boundary' piping members e
- andLcomponentstwere replaced as a result of previous 1 programs.
~
(2):.Thereihavelbeen no leaks detected in RCS pressure boundary
_ piping and-fittings since the replacement of the furnace sensitized 14"2feedwater nozzles'in 1969.
'(3)4.There have been no unacceptable indications found in stainless steel welds. during VT, PT, a d UT examinations ~made since the
< furnace sensitized piping components were replaced.
- (4)~ Th'e construction. piping contractor's and LACBWR's welding
-procedures for both shop and field welds provided'for control of current.~and voltage (heat input) and limited the interpass temperature to 2000F for both butt and socket Jelds.
The degree of' sensitization would therefore be minimized-by these.
limitations.
(5)
Catastrophic failure of. austenitic stainless steel without
. prior leakage is, considered to be extremely unlikely.
In
- the ' event-oficracking in the RCS pressure boundary piping, the resulting '(initially small) leaks would be detected by c
the LACBWRileak detection system and plant shutdown would be
. instituted as provided by the Technical Specifications.
.In. combination-with LACBWR Technical Specifications on RCS leakage t
> limits 1and,the above stated-reasons, LACBWR will implement an F(
- augmented -inservice examination ' schedule for service sensitive -
J,
-lines.: The. frequency of examinations will Na conducted within an
.80-monthcinterval.
The!LACBWR second 10-year program began in LNovember 1979?and is being administered in accordance with~
fI r
10 CFR '50. 55a (g). (1).
If you!have any, questions regarding this' subject, please advise.
L
.Very truly yours, DAIRYLAND P GBR COOPERATIVE c
,L kE w
Frank Linder,- General-Manager FL: HAT: abs
- ATTACHMENTS 1
'LCCi "J.fKeppler,) Reg'.EDir.,NRC-DRO;III.
-13f-
TABLE I i.
_1 " HIGH. PRESSURE CORE:' SPRAY - INSIDE BIOLOGICAL' SHIELD
~
Weld No.-
1978-(1 " Socket Welds)
H" VT/PT-I"-
VT/PT
~ J" VT/PT K"
VT/PT L"
VT/PT M"
VT/PT' N"
VT/PT 0"
VT/PT-(Butt Weld)
P" VT/PT 1 " AND 2 " HIGH PRESSURE CORE SPRAY -- DISCHARGE CHECK VALVES TO 2h" HIGH-PRESSURE CORE SPRAY PIPING
- Weld No.
'1972 1975 1979 (1 " Socket Welds)
T'--Outside Pressure Boundary U
VT/PT
.V VT/PT W
VT/PT X
VT/PT Y.
VT/PT X"
VT/PT X '.
VT/PT Y'
VT/PT G - Outside Pressure Boundary H
VT/PT I
VT/PT J
VT/PT K
VT/PT' L
VT/PT (l " Butt)
SS Outside Pressure Boundary
-Z VT/PT M
VT/PT-(2" : Socket) -
A" PT l-PT-c 4-h
- TABLE I~-
(Cont ' d)
- l " AND 2 " HIGli PRESSURE CORE SPRAY - DISCHARGE CHECK VALVES TO 2" HIGH PRESSURE CORE SPRAY PIPING - (Cont ' d)
Weld No.
1972 1975 1979 (2 " Butt)
T" UT.
S"
. U.T C"'
UT U"-
- D" UT B"
UT 2
UT 3
UT 4
4 UT 5
UT 6
UT 7
- (2" Butt) -
E" VT/PT Q"
VT/PT R"
VT/PT F"
VT/PT G"
VT/PT 6" ALTERNATE CORE SPRAY PIPING
- Weld No.
1971 1972 1975 (X1) 1979 75-VT/PT, UT 76 VT/PT, UT 77 VT/PT, UT 78 VT/PT, UT PT/UT 79 VT/PT, UT UT 80=
VT/PT, UT UT 81 VT/PT, UT UT 82 VT/PT, UT UT 83 -
.VT/PT, UT UT 105 VT/PT, UT UT 84 VT/PT, UT '
_VT/PT, UT VT/UT UT 87-VT/PT,' UT VT/UT UT 88' VT/PT, UT VT/UT UT 89 VT/PT, UT VT/UT UT 90~
VT/PT, UT UT 91-VT/PT, UT UT 92 -: Inaccessible - In Pipe Sleeve
TABLE ' I - -(Cont'd)
~
6" ALTERNATE CORE' SPRAY PIPING - (Cont'd)
Weld No.
-1971 1972 19 75 (X1) 1979 93-VT/UT UT
'94 VT/UT UT 95 VT/UT UT 96 VT/UT UT:
-97 VT/UT-UT 98
-VT/UT UT 99-
.VT/UT UT 100 VT/UT UT 101-VT/UT UT 4-102 VT/UT UT 103 VT/UT UT 4" ALTERNATE CORE SPRAY Weld No.
1970 1971 1979 104 VT/UT UT 106 VT/UT VT/UT UT 107 VT/UT VT/UT UT 108 VT/UT UT/PT Nozzle to Head VT/UT 20" Manway-FORCED ~ CIRCULATION SYSTEM 1A DISCHARGE BYPASS
. Weld No.
1975 (X2) 1979 (2" Socket Welds) l
'91A' VT/PT VT/PT 91B VT/PT VT/PT-191D VT/PT VT/PT
-101' VT/PT VT/PT
-100' VT/PT VT/PT 2
95 VT/PT 94 VT/PT VT/PT 98 VT/PT 90D VT/PT 90B VT/PT 90A1-VT/PT o
_.--.--,m, m.
TABLE I - f (Cont'd)
FORCED CIRCULATION - 1B DISCHARGE VALVE BYPASS Weld No.
1975 (X2) 1979 (2" _ Socket Wel'ds) 93A VT/PT VT/PT 93B VT/PT VT/PT 93D VT/PT VT/PT 105 VT/PT VT/PT 104 VT/PT
.VT/PT 97 VT/PT VT/PT 96 VT/PT VT/PT 103 VT/PT VT/PT.
102 VT/PT VT/PT 92D VT/PT VT/PT 92B VT/PT VT/PT 92A VT/PT VT/PT 4-
TABLE II SHUTDOWN CONDEUSER SYSTEM - 4" CONDENSATE RETURN LINE Weld'No.
1972 1979 12' VT/UT' UT
'f These 4 Welds 'Are Upstream of Check Valves.
- 22 'J
-UT 23 VT/UT UT
-24 VT/UT UT 225-
-VT/UT UT 26 VT/UT UT 27 VT/UT UT 28 VT/UT-UT
-29 VT/UT UT 30 VT/UT UT 31 VT/UT UT
- 32 VT/UT UT
.2 AND 21 " BORON INJECT PIPING 5
Weld No.
1972 1975 (X1) 1976 1979 8-VT/UT UT A'
VT/UT UT B'
VT/UT UT C"
VT/UT UT D"
PT E'
PT F '-
UT 9
PT T'
PT 11 UT 12 VT/UT UT 13 VT/UT UT 14 VT/UT VT/UT UT 15 VT/UT VT/UT-UT G'
VT/UT UT 16 VT/UT UT 17 VT/UT UT 18-VT/UT UT 19 VT/UT UT 20 UT 22' UT 23 UT 24
~ TABLE :-II - -(Cont ' d)
- DECAY: HEAT SYSTEM - 6" DISCHARGE PIPING Weld No.
1970 1972 1976 1977 1979 1
PT PT/UT 2
UT 7
UT 8
UT 9
UT 10 UT VT/UT UT 11 UT VT/UT UT
- DCl-2 UT VT/UT, PT PT/UT UT VT/UT, PT PT/UT DCO-2 12 UT VT/UT UT 13' UT VT/UT UT
- 64BC VT/PT PT 14 VT/UT UT 15 VT/UT UT 16 VT/UT UT 17 VT/UT UT 18 VT/UT UT 19 VT/UT
1975 (X1) 1976 1979 22 UT 23 UT 24~
UT 25
'UT
.26 UT
- 27 UT 28 UT 29 UT 30 VT/UT VT/UT UT 41--
- 32 VT/UT VT/UT UT
- 33 UT
- 34-UT
' 3 5' UT UT 51-UT 37-UT 38:
- 38A-150:
-UT m
e-
TABLE II'-
(Cont'd)
DECAY HEAT SYSTEM'- 2" DECAY HEAT PUMP BYPASS PIPING Weld'No.
-56 57 58 59 60 61 62 63 DECAY HEAT SYSTEM - 8" DECAY HEAT SUCTION PIPING Weld No.
18-PT PT/UT 3
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REACION g
VESSEL P-
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- 63 25 003 C"
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h E3 2ts002 2 t/2" X 2" RE DUCE R 4
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63 M 003 g
g.
V 21/2" 3 3/2 X 21/2
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C b3 24 000 ie p.
8 63 24 006 G~
J 2 t/2" X l 1/2" RE DUCE R x y i
k ftOW kkiER LOWEH CAvlIY SOUNOARY
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SS CAtISRATION BLOCKS :
1 1/2" CAPPED CONN 2 I/2" ISO 5 TON INJECTION 2 6 SS ** 21. is teR isEE e. Gun, P. ;3 2 SS 110.218 IS EBR NOTES PtPING IS 304 S S. A 316. Scit too
- BUTT WE t0 j
)SOCKETWitD FIGURE A-18 1-1/2", 2" AND 2-1/2" 11I011 PRESSURE CORE SPRAY SYSTEM PIPING i
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Suo SSA 6* $ Cat 160 A 376 304 5 S 900 A G" Scil 120 A 106 GR B
- UdIIWILU PLANGES g
X HAEER WELDED IS2 S/S 1 r*306 DISSIMILAR METAL WELD gpg
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A 38 2 S/S '
INCONEL *'
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jI G SS 160.71913 LBR NO22LE I
A 106 C/S
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6 CS 120 56214 L 8H 4 IN B0.337 IS L8R 4 sa sui 337 2: 18R q atACron 1
1 FIGURE A-l$
4" AND 6" ALTERNATE CORE SPRAY SYSTEM PIPING 4
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NO1 ES:
PtPtNG IS NO 90A e
92A e
80 SS 304 COUPLING SS IS S WE LDS UCC & 9tc Duo 900 m
920 928 ARE IN9DE 102 l
VALVE 50 30002,
- T WE LDS 92C & 93C ARE gg 103 INSIDE VALVE I
50 30 004
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f e BOT T WE LD g4' 96
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e DISS&MILAR MET AL W D 50 25 002 i
h '96 97 S3A 9A i
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930 s3a ice g
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&OOP A FICURE A-7 j
2" BY-PASS LINES OF 20" FORCED CIRCULATION I
DISCilARGE AT VALVES 50-30-002 AND 50-30-004 4
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ef 22-62 25-012 2,
- 32 25-002 I S' 62-26 006 24 02'2DI HGR. C 114 g
62 24-002 g.
25 0 62 24-002 12' 26 0 1
29 TRANSITION PIECE 27 23 4
0 338C 2La NOTES:
(SEE FIG RE A 16)
ALL PfPING IS TYPE 304 S.S. A.378
- BUTT WELD X HANGER (WELDED)
Call 8R ATION BLOCK-4-SS 80.337 21 L8R FIGURE A-17 O
4" CONDENSER CONDENSATE PIPING A-19
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2 53 NOTES.
ALL DECAY HEAT SUCTION PIPtNG IS:
3 GROUP VI A CLASS 900 SSA 8" SCH.
HGR. 04101 104A376. TYPE 304 S.S.
4 e SUTTWELD X HANGERlWELDEO)
{
g OiSSIMILAR METAL WELO gg, Q HANGERICLAMPE01 CALISRATtON 8 LOCKS.
SSS104.5949 L8R 6G124.5621&L8 R 7
- RADIOGRAPH TAP g
HGR 04104 tt T PUMP 8YPASS 12>
(SEE FIGURE A 101 HGR. 0+1Q d' 558C 3/4" SCRO. BOSS
- 20 8
56 24001 to 14 21<a i S.w. BOSS fy g ii5 OH PUMPf N3 s 18 17 l
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RADIOGRAPH TAP FIGURE A-8 8" DECAY HEAT SUCTION PIPING O
A-10
u
/
Q 20" p c0 (SEE FIGURE A Sel 8 l
-gSNCDNE L 11 g ys ag 4
p C/S S/S 26 W
3I h
0 C llGR.DH 100 HGR. DH 105 ; (
g 2" PUMP %p.,',gN2 F
46aC\\
45 SYPASS ISEE FIGURE x
l* S w. LOSS its 66 24 002
< > 36 3
26 003 2
watt
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I" S W BOSS
< 048 66 24 004 33 HGR. DH 108 49 0 >-l" S W. BOSS 3o g
- 66 24 007 f
44 I"SCHD Boss 32 P
" SCAD. SOSS g, y g g 3
3l 40 lf g
e4fDCI 2 te 06 001 j
I 2"S w. oOSS(CAPPED:
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f LOW ELEMENT b
42 alGR. DH 107 NOTES.
8 At L DECAY HE AT DISCHARGE PLPtNG IS.
O DCO 2e HGR. DH I
% 78 GROUP VI A,8 & C CL ASS 900 SSA 12 4 '91 6" 2
29 6" SCH 120 3FbA. T YPE 304 5 S 1" SCRD. BOSS 83 M
16 658C e BuiT WELD M HANGER (wEtDEDI 1/2" S W. 80SS 43
- % 24 2 e OtSSIMit AH MET AL WELD 648 2" DECAY HEAT TO b HANGER (CLAMPED) 85 p
R. V. HE AD (SE E CALISH AlaON st OCKS.
6 SS 820 662 to tsH 2" 5T ART UP WAT E R 6 IN 820 662 L AX l ItLMOVAL 1 LNE lblE I B60HE A 12)
FIGURE A-9 6" DECAY llEAT DISCilARCE PIPING
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46BC 6" DHD 63 (SEE FIGURE A 9) 6 62 56-24-003 0
59 58 S7
$p NOTE:
1 1/2" FROM CONTROL ROD ORIVE EFFLUENT 58
) SOCKET WELD PUMPS WG IS FAWLESS STEEL y,,o,3 (SEE FIGURE A 8) l n
FIGURZ A-10 1
2" PUMP BY-PASS PIPING i
O A-12
- - - - - - - - - -~ 1