ML20041C404
| ML20041C404 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 02/23/1982 |
| From: | Fay C WISCONSIN ELECTRIC POWER CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20041C405 | List: |
| References | |
| NUDOCS 8203010283 | |
| Download: ML20041C404 (29) | |
Text
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Wisconsin Electnc eaara couraur 231 W. MICHIGAN, P.O. BOX 2046 MILWAUKEE, WI 53201 February 23, 1982 I
Mr. H.
R.
Denton, Director Office of Nuclear Reactor Regulation p
U.
S.
NUCLEAR REGULATORY COMMISSION NUE Washington, D. C.
20555 MAR 011M2a 5
Dear Mr. Denton:
DOCKET NO. 50-266 Bet COMPLETION OF FIRST TEN-YEAR INSERVICE INSPECTION INTERVAL
/
POINT BEACH NUCLEAR PLANT, UNIT 1 On December 20, 1981, the first inservice inspection interval for Point Beach Nuclear Plant Unit 1 was completed.
The Unit 1 first ten-year interval was extended from December 20, 1980 to December 20, 1981 to permit inspections to be concurrent with plant outages as allowed in Article IWA 2400 of the 1974 Edition up to and including the Summer 1975 Addenda of Section XI of the ASME Boiler & Pressure Vessel Code.
Enclosures 1 and 2 are a summary of the examinations performed during the first ten-year interval for Unit 1.
Upon review of the summary of examinations performed, it is apparent that some deviations from the ASME Section XI Code occurred.
Prior to the third period, inservice inspection was performed in accordance with Technical Specification 15.4.2.B, included in for your reference.
Third period inservice inspection work was performed at the direction of the NRC in accordance with the most restrictive provisions of either Specification 15.4.2.B or the inservice inspection plan Wisconsin Electric submitted to the NRC on May 20, 1977.
The inservice inspection plan submitted to the NRC was written to the 1974 Edition (Summer 1975 Addenda) of ASME Section XI.
All of the Technical Specification and ASME Section XI inservice inspection interval requirements were met with only a few exceptions.
Those exceptions are noted and explained in.
The first ten-year inservice inspection interval require-ments for Unit 1, within the limits of practicality, were completed during the fall 1981 refueling outage.
Wisconsin Electric's future intention is to perform the second interval inservice inspection 8 8203010283 820223 PDR ADOCK 05000266 b I O
s Mr.
H.
R.
Denton February 23, 1982 work in accordance with a ten-year plan currently being developed.
However, as noted in the following paragraphs, Wisconsin Electric has yet to receive final NRC approval to implement the inservice inspection requirements of ASME Section XI.
On February 17, 1977, Wisconsin Electric submitted Technical Specification Change Request No. 42 for Unit 1 to the NRC for review and approval.
This Technical Specification change replaced Technical Specification 15.4.2.B in its entirety with revised language which followed NRC guidelines.
- Briefly, this change directs the licensee to perform inservice inspection and inservice testing of ASME Code Class 1, 2, and 3 components in accordance with ASME Section XI as required by 10 CFR 50.55a.
In addition, it directs that containment isolation valves be tested in accordance with Technical Specification 15.4.4 vice ASME Section XI, which fulfills 10 CFR 50 Appendix J requirements.
For your convenience, Enclosure 5 is a copy of Technical Specifica-tion Change Request No. 42 for your review.
Reactor vessel material surveillance shall be performed in accordance with Technical Specification Table 15.3.1 and is not addressed in ASME Section XI.
Reactor coolant pump flywheel inspections shall be conducted in accordance with the inservice inspection plan as follows:
1.
100% visual exam overy period.
2.
Surface exam of the bore and keyway every period.
3.
100% volumetric every interval.
The reactor coolant pump flywheel exam requirements are not addressed in ASME Section XI.
Snubber surveillance shall be conducted in accordance with Technical Specification 15.4.13 vice ASME Section XI, Article IWF-5000.
As Wisconsin Electric informed NRC on October 6,
- 1981, the Unit 1 second ten-year interval plan is being written to the 1977 Edition (Summer 1979 Addenda) of ASME Section XI.
The scope of examination of Class 1 and 2 pipe welds shall be in accordance with the 1974 Edition (Summer 1975 Addenda) of ASME Section XI as allowed by 10 CFR 50.55 a(b) (2) (ii) and (b) (2) (iv).
Until Technical Specification Change Request No. 42 is approved, Point Beach Nuclear Plant Unit 1 will again be governed by two sets of conflicting inservice inspection requirements, namely, ASME Section XI and Technical Specification 15.4.2.B.
I s
4 Mr. H.
R.
Denton February 23, 1982 In order to effectively develop and implement the second ten-year inservice inspection interval plan it is imperative that Technical Specification Change Request No. 42 be approved by the Commission.
In light of the five years that this change has been outstanding, we would expect that final approval should be expected in the very near future.
If this is not true, Wisconsin Electric requests at least interim approval of Technical Specification 15.4.2.B.1 of Technical Specification Change Request No. 42.
With this interim approval, we will be able to implement in a timely fashion the inservice inspection plan for the Unit 1 second ten-year interval.
Very truly yours,
/
/'
/
/
Assistant Vid President C. W.
Fay Enclosures Copy to NRC Resident Inspector
1 s
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ENCLOSURE 1 10-YEAR ISI
SUMMARY
TABLES The ISI summary tables provided herin are a listing by component, category and item number of the_ Technical Specifi-cation and Code examination requirements as well as the status of the examinations.
The following is a key to the summary tables:
Block Description (1)
Component Component noun name (2)
Exam area Area to be examined (3)
Cat ASME Section XI category (4)
Item No ASME Section XI item number (5)
Meth NDE method UT Ultrasonic test PT Dye penetrant test VT Visual test MT Magnetic particle. test RT Radiographic test (6)
Reg Exam requirement a.
TS Technical Specification b.
C ASME Section XI Code (7)
Comp Percent of exam area complete (8)
Period 40-month period (9) 10-Yrs 10-year interval Abbre /iations NA Not applicable REM Remainder
o SK RA M
E R
4 TSR I
F O
7 S
C RA L
E A
Y VR 0
E 1
Q S
C a
b T
E T
6 6
N R
I M
7 D
O O
I C
R E
P D
R I
Q S
C a
b I
E T
6 6
I T
R 1
T M
I D
N O
O 7
U I
C R
E P
D N
Q S
C a
b O M T
6 6
CE S
M DO O
7 I
C R
E P
TS 0
R S
C a
b I
T 6
6 F
y$
5 ysH 4
1 g<o 3
T NE N
O P
M O
A E
R 2
A MAXE
]
1 4
t l
l
e COMPONENT - REAC'IOR VESSEL UNIT 1 INTERVAL - FIRST FIRST PERIOD SECOND PERIOD TIIIRD PERIOD 10 YEARS RM COM REQ COMP W
COM RQ COM EXAM AREA E
- n REMARKS TS TS TS TS c
c c
c Lower !!ead to Lower NA
"^
"^
(1 of Weld un #
0%
100%
0%
100%
1 Ring Circumferential g) g)
g g
Weld BA Bl.1 UT NA NA NA 5% (1)
"^
Lower Ring to Lower 0%
100%
0%
100%
(1) Of Weld Length Shell Circ Held BA Bl.1 UT (1)
NA NA 5% (1) i 1
NA NA NA 5% (1) 100%
(1) Of Weld Length Lower Shell to 0%
100%
og fliddle Shell Cire (1)
(1)
(1)
(1)
Weld BA Bl.1 UT NA NA NA 5% (1) y NA NA NA 10% (1) 100%
(1) Of Weld Length Lower Longitudinal 0%
100%
0%
(1)
(1)
(1)
NA NA NA 10% (1)
Middle Shell to NA NA NA 5% (1)
(1) Of Weld Length Upper Shell Circ 0%
100%
0%
100%
(1)
(1) g 5% (1)
Upper Longitudinal NA NA NA 10% (1)
(1) Of Weld Length 0%
100%
0%
100%
(1)
(1)
(1)
NA NA NA 10% (1) 25%
25%
33-REfi 33-100%
166-Closure liead to Plange Weld BC Bl.3 UT 100%
1/3%
1/3%
2/3%
25 -
25 -
REM 100%
i 33-1/3%
33-1/3%
Plange to Shell 25%
25%
EM 0%
133-333-
{
25 -
25 -
1/3%
1/3%
33-1/3%
33-1/3%
2 2
2 6
(1) 100% = 6 Nozzles 33-33-Notzles 66-Nozzles Nozzles 133-Nozzle to Vessel Nozzles (2) 100% of each weld Welds BD Bl.4 UT 25 -
1/3%
25 -
2/3%
1/3%
1/3%
examined 33-1/3%
33-1/3%
i t
1 j
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i COMPONENT - REACTOR VESSEL UNIT 1 INTERVAL - FIRST e
FIRST PERIOD SECOND PERIOD THIRD PERIOD 10 YEARS
]
EXAM AREA E
- G REMARKS j
y y
g TS Ts TS Ts c
c c
c I
2 2
2 6
(1) 100% = 6 Nozzles Nozzle Inside Nozzles Nozzles 66-Nozzles 33-Nozzles Radius Section BD Bl.4 UT 25 -
25 -
2/3%
1/3%
100%
33-1/3%
33-1/3%
a (1) Of Each Group of NA NA NA NA Penetrations of 4
Vessel 100%
100%
l 6-1/4 -
6-1/4 -
REM 25%
Comparable Size and Penetrations BE Bl.5 VT g)
B-1/3 % (J) 3-1/3%(1)
(1)
(1)
Function.
(1) 100% ='6 Nozzles Nozzle to Safe-25%
33-33-166-(2) 100% of Weld Examined 6 No s)
BP Bl.6 UT 3 1/3%
3 -1/3%
i (1) 100% - 6 Nozzles 25%
100%
133-(2) 100% of Weld Examined 33-66-33-
^5-1/3%
25 -
2/3%
1/3%
1/3%
(3) PT Could not be Per-
^
formed on both SI Nozzles i
33-1/31 33-1/3%
due to Inaccessibilitv.
(1) 100% - 6 Nozzles 25%
33-66-
.5 3-133-(2) 100% of Weld Examined VT 1/3%
2/3%
1/3%
1/3%
(3) VT Could not be Per-formed on both SI Nozzles NA NA NA NA Due to Inaccessibility.
1 (1) 100% = 48 Studs 25%
100%
(2) Bl.7 Applies to Closure 33-33-33-Bl.7 100%
Studs in Place.
sur s
BGl
~
(3) Bl.8 Applies to Closure B1*8 REM 100%
33-1/3%
33-1/3%
Studs Removed.
i NA NA NA NA (1) 100% = 48 Studs Bl.8 MT' 0
0 25 -
25 -
3%
1 3%
REM 100%
33-1/3%
33-1/3%
25%
25%
REM 100%
(1) 100% = 48 Studs 33-33-33-j 100%
i l/3' 1/3%
1/3%
NA NA NA l
NA i
25%
33-33-33-l Closure Nuts BGl Bl.8 UT 100%
25 -
1/3%
25 -
1/3%
REM 1/3%
100%
33-1/3%
33-1/3%
i
e o
COMPONENT - REACTOR VESSEL UNIT 1 INTERVAL - FIRST PIRST PERIOD SECOND PERIOD THIRD PERIOD 10 YEARS EXAM AREA
- C
- c REMARl(S TS TS TS TS C
C C
C NA NA NA NA (1) 100% - 48 Nuts 33-33-Bl.8 MT 25 -
0 25 -
0 REM 1/3%
loog 1/3%
33-1/3%
33-1/3%
25%
33-33-33-100%
VT 1/3%
1/3%
1/3%
NA NA NA NA NA
"^
"^
"^
(1) Examine When Connection 33-33-166-100%
sassedled Ligaments BG1 Bl.9 UT 1/3%
1/3%
2/3%
NA NA NA (1) 25%
25%
( )
Was rs
=
33-33-33-Washers BG1 Bl.10 VT 25 -
1/3%
25 -
1/3%
1/3%
100%
33-1/3%
33-1/3%
NA NA NA NA Not Applicable. All Pressure Retaining Bolting Greater Than Bolting BG2 Bl.11 VT 2" Diameter.
NA NA E
E
"^
PP 9
Integrally Welded Support BH Bl.12 UT 25 -
0 25-100%
0 100%
REM 19%
33-1/3%
33-1/3%
2 2
2 6
(1) 6" x 6" Patch
^
C d ng BIl Bl.13 PT O
(1) 2 (1) 2 Patches (1) 2 Patches (1) 6 Patches Patches Patches (1)
Patches (1)
Patches (1) l 2
2 2
6 (1) 6" x 6" Patches Patches Patches 4
Patches 2
Patches 6
Bl.13 VT 0
Patches Patchee g
W 2
(1) 6 (1)
II)
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Patches Patches Patches Patches 6
(1) Gen Area Inspection NA NA MA Patches Patches (2) 6" x 6" Patch Vessel Cladding BIl Bl.14 VT (2) 2 (2) 2 (2) (3)
(2) 2 (2) 6 (3) Be t "
O 0
Patches Patches Patches Patches ac s I
o COMPONENT -
REACTOR VESSEL UNIT 1 INTERVAL - PIRST o
PIRST PERIOD SECOND PERIOD THIRD PERIOD 10 YEARS REO COMP REQ COMP REO COMP REQ COMP p
EXAM AREA g
g g
TS TS TS TS g
g g
c c
c c
NA NA NA NA (1) All Interior Surfaces Vessel Interior Bril Bl.15 VT 0%
0%
0%
'0%
yesselMadeAccessble "9
"9*
(1)
(1)
(1)
NA i
NA NA NA NA Not Applicable to PWR.
Interior Attachments BN2 Bl.10.VT NA NA NA NA NA NA NA (1) When Core Barrel Core Support Removed.
Structures BN3 Bl.li VT 100%
93A gg NA 100%
(1) 10% of Peripheral CRDM NA NA NA NA flousings.
45%
45%
(2) 20 Peripheral CRDM Welds BO Bl.10 UT 0
Ilousin s ofPer$,phe3c NA NA (3)
NA (1)
(3)
(3) ud 1 CRDM nniic i m (1) Inspect as Accessible NA NA NA (1)
(2) 20 Peripheral CRDM 45%
45%
Housings VT (3) of Peripheral CRDM NA NA (3)
NA NA (3) llousing Welds NA NA NA NA (1) During System Hy r stade hessure Exempted Components BP Bl.10 VT 100%
100%
100%
Test NA B
n (1)
A
e a
COMPONENT - REACTOR VESSEL UNIT 1 IHTERVAL - FIRST FIRST PERIOD SECOND PERIOD THIRD PERIOD 10 YEARS REO COMP REQ COMP REQ COMP REQ COMP p
pg EXAM AREA
- C g
g r,
TS TS TS TS g
g g
C c
c c
NA NA NA NA (1) All Interior Surfaces f Vessel Made Accessible Vessel Interior BN1 Bl.15 VT 0%
0%
0%
0%
During Normal Refueling.
(1)
(1)
Q)
NA NA NA NA NA Not Applicable to PWR.
Interior Attachments BN2 Bl.10.VT NA NA NA NA NA NA NA (1) When Core Barrel Core Suplert Removed.
Structures BN3 Bl.11 VT NA NA NA 100%
(1) 10% of Peripheral CRDM NA NA NA NA Housings.
CRDM Housing 45%
45%
(2) 20 Peripheral CRDM Housings Welds BO Bl.10 UT O
NA NA (3)
NA (1)
(3)
(3) Of PQriphe Me1 CRDM wd nniic,nn (1) Inspect! as Accessible NA NA NA (1)
(2) 20 Peripheral CRDM 45%
45%
Housings VT (3) of Peripheral CRDM NA NA (3)
NA NA (3)
Housing Welds NA NA NA NA (1) During System Hy r stade Pressure Exempted Components BP Bl. l(J VT 100%
100%
NA NA NA (1) i
COMPONENT - PRESSURIZER UNIT 1 INTERVAL - FIRST PIRST PERIOD SECOND PERIOD TlilRD PERIOD 10 YEARS M
Q MP Q
COMP REQ COMP EXAM AREA y
y REMARKS g
TS TS TS TS g
g g
c c
c c
(1) Of Weld Length NA NA NA Upper Nead to 13.7%
5% (1) 13.7%
(2) 25 1/3% of all Upper Shell Circ (1)
(1)
Shell Welds (5 Total)
Welds (2)
(2)
(3) 5% - (1)
(3) ggnderofShell l
(1) Of Weld Length NA NA NA 5% (1) 13.7%
13.7%
NA NA NA NA (1) Of Weld Length Upper Shell to NA NA NA 5% (1) 13.7%
(2) 25 1/3% of all 13.7%
Lower Shell Circ Remainder of(Shell5 Total)
Shell Welds (1)
(1)
(2)
(2)
(3) 5% (1)
Welds NA NA
"^
( '
13.7%
13.7%
NA NA NA NA (1) Of Weld Length NA NA NA 5% (1)
(2) 25 1/3% of all Lower Shell to 1.7%
13.7%
Shell Welds (5 Total)
Lower IIead Circ I'
(2)
(3) 5% (1) e NA NA NA 5% (1)
(1) of Weld Length 13.7%
13.7%
g NA (1)
NA NA NA (1)
(1) Of Weld Length NA NA NA 10% (1)
(2) 25-33-1/3% of all Upper Shell 12.1%
12.1%
Shell Welds Longitudinal Remainder of (Shell5 Total)
(2)
(3)
-(1 (1)
(3) 10% (1)
Welds NA NA NA 10% (1)
12.1%
NA NA NA (1)
NA (1)
- 9 Lower Shell NA NA NA 10% (1) 18.2%
18.2%
(2) 25 1/3% of all Shell Welds 5 To Longitudinal BB B2.1 UT (2)
(1)
(2)
(3) 10g (1)
(1) g g nder of(Shelgal)
(3)
COMPONENT - PRESSURIZER UNIT 1 INTERVAL - FIRST PIRST PERIOD SECOND PERIOD THIRD PERIOD 10 YEARS REO COMP REQ COMP REQ COMP REQ COMP EXAM AREA y
y REMARKS g
TS TS TS TS g
g g
C C
C C
NA NA NA 10% (1)
(1) Of Weld Length 18.2%
18.2%
VT III III NA NA NA NA NA NA NA NA Not Applicable. All N zz e essel e s BD B2.2 N Nozzles are Integrally NA NA NA NA Cast Into the Vessel lleads.
NA NA NA NA Nozz es
=
Nozzle Inside Radius Section BD B2.2 UT 25 -
25 -
33-1/3**
33-1/3%
NA NA NA NA (1) Performed During IIeater 100%
100%
liydrostatic Pressure Penetrations BE B2.3 VT NA NA NA 25% (1)
Test.
25%
25%
REM 100%
(1) 100% = 5 Nozzles Nozzle to Safe End Welds BP B2.4 UT 25 -
0%
25 -
100%
40%
140%
33-1/3%
33-1/3%
25%
25%
REM 100%
(1) 100% = 5 Nozzles PT 0%
100%
40%
140%
25 -
25 -
33-1/3%
33-1/3%
25%
25%
REM 100%
(1) 100% = 5 Nozzles 0%
100%
0%
100%
VT NA NA NA NA Pressure Retaining NA NA NA NA Not Applicable.
Bolts and Studs In Bolting is Less Than Place BG1 B2.5 UT NA NA NA NA 2" Diameter.
Pressure Retaining NA NA NA NA Not Applicable.
Bolts and Studs'When UT Bolting is Less Than Removed BG1 B2.6 MT NA NA NA NA 2" Diameter.
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COMPONENT - STEAM GENERATOR "A" UNIT 1 INTERVAL - FIRST PIRST PERIOD SECOND, PERIOD TIIIRD PERIOD 10 YEARS M
MP REQ COMP EQ COM EXAM AREA E
Z REMARKS TS TS TS TS C
C C
C Primary Head to NA NA NA 5% (1)
(1) Of Weld Length Tubesheet Weld BB B3.1 UT 8.9%
5.2%
14.1%
0%
(1) 1-2 l-2/g 5% (1)
^
"A of Weld Lenge 8.9%
Os 5.2%
14.1%
0T (1)
(1)
(1)
(1)
NA NA NA NA Longitudinal and NA NA NA NA Not Applicable.
Circumferential No Primary Shell Welds.
Welds BB B3.1 UT NA NA NA NA NA NA NA NA Not Applicable. All Nozzle to Shell N zz s are Integrally Helds BD B3.2 UT NA NA NA NA Cast Into Primary Head.
"^
"^
"^
"^
~
Nozzle Inside Radius Section BD B3.2 UT 25 -
0%
25 -
0%
100%
100%
EM 100%
33-1/3%
33-1/3%
Nozzle to Safe 25%
25%
REM 100%
(1) 100% = 2 Nozzles End Weld BF B3.3 UT 25 -
25 -
33-1/3%
33-1/3%
25%
25%
REM 100%
(1) 100% = 2 Nozzles B3.3 M 50%
0%
100%
150%
25 -
25 _
REM 100%
33-1/3%
33-1/3%
25%
25%
REM 100%
(1) 100% = 2 Nozzles VT 50%
0%
100%
150%
NA NA NA NA Pressure Retaining NA NA NA NA Not Applicable.
All Bolts and Studs in Bolting is Less Than BG1 B3.4 UT 2" Diameter.
Place NA NA NA NA
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A A
A A
A A
0
)
)
E 1
O s
C T
E T
N N
N N
N 1
2 N
0 0
0 1
(
(
N R
1 I
P 0
)
D M
2 0
O O
(
1 I
C R
E P
D M
R A
A A
A' A
A A
A A
E I
Q S
C l
E T
N N
N N
N N
N N
N iT R
1 T
P I
D M
N O
O U
I C
R E
P 3
D
/
N Q
A A
A A
A A
A A
A 1
O E
S C
N N
N N
N N
N N
N 5
C R
T 2
E 3
S 3
P D
M O
O I
C R
E P
1 3
"A T
/
S O
A A
A A
A A
A A
A 1
R E
S C
N N
N N
N N
N N
N 5 -
I R
T 23 R
F O
3 TAR TT T
T T
T T
gg UM V
U V
V V
E N
E 5
6 7
8 9
0 G
1 yg 3
3 3
3 3
3 M
B B
B B
B B
A T
i 2
2 E
1 1
I P
G gg G
G l
B B
B S
B B
B s
o t
g T
n d
n n
N i
e e
i E
ns d
g n
n N
id l
n o
i O
au e
i p
a P
t td W
d m
t M
O A
eS e d
o e
C E
R v
y a
C R
R d o g
l l
A enm en l s C
d e
rae rig at e
rg M
u R
unn rr l
t un A
ss sii go e
n si X
st n sat ep s
m st E
el e etl t p s
e el roh r eo nu e
x ro PBW PRB I S V
E PB
COMPONENT - STEAM GENERATOR "B" UNIT 1 INTERVAL - FIRST FIRST PERIOD SECOND PERIOD TilIRD PERIOD 10 YEARS REQ COMP REQ COMP REO COMP REQ COMP EXAM AREA g
g p.
pg g
TS TS TS TS g
g g
~
C C
C C
Primary Head to NA NA NA 5% (1)
(1) Of Weld Length Tubesheet Weld BB B3.1 UT 0%
9% (1)
_ j4 _
g_174 _
REM of 1-2/3%
l-2/3%
5% (1) 5% (1)
(1)
(1)
NA NA NA 5% (1)
(1) Of Weld Length 0%
9% (1) 0%
9% (1) dT NA
.NA NA NA Longitudinal and NA NA NA NA Not Applicable.
Circumferential No Primary Shell Welds.
"^
"^
"^
"^
^EE
^ ** ^
Nozzle to Shell
NA NA NA NA
(
N zz es Nozzle Inside Radius Section BD B3.2 UT 25 -
0%
25 -
100%
Os 100%
EM 100%
33-1/3%
33-1/3%
Nozzle to Safo 25%
25%
REM 100%
(1) 100% = 2 Nozzles End Weld BP B3.3 UT 25 -
25 -
EM 100%
33-1/3%
33-1/3%
25%
25%
REM 100%
(1) 100% = 2 Nozzles B3.3 PT 50%
0%
100%
150%
25 -
25 -
REM 100%
33-1/3%
33-1/3%
25%
25%
REM 100%
(1) 100% = 2 Nozzles VT 50%
0%
100%
150%
NA NA NA NA Pressure Retaining NA NA NA NA Not Applicable.
All Bolts and Studs in Bolting is Less Than BGl E3.4 UT 2" Diameter.
Place NA NA NA NA
r e
t h
r e
t o
r O
p u
s r
p r
h l n l n u
o cy gs o
l a l a oS f
t a ne f
s Ah Ah N
b w i r t
T T
d e
P n rP e
l a
u l
o e
M"M D c b
B S
.s
.s
.d K
es es el i
i R
l e l e l e s
h dt s
2 A
bL bW s
xc ea s
3 M
bL E
a r
a r
a e
a mt es R
cse cse cy c
" E rs cn=
iit iit il c
6 oo co l
e l
e l l A
r f rt A s%
pgm pgm pa h-a rd s a0 pna pna pr s
e eye se0 Aii Aii A g A
N pit AR1 l
tD tD e
tl tl t t
)
)
)
)
oo on 2
1 1
2 oo" N B "2 NI
(
(
(
(
NB2 TS R
P 0
3
)
I M
2 0
/
P O
(
1 1
S C
RA L
E
)
A Y
1 V
(
R 0
A A
A A
A A
A
)
0
)
E 1
Q S
c T
E T
N N
N N
N N
1 N
0 1
0
(
0
(
1 N
R 1
I P
0 D
M 0
O O
1 C
I R
E P
D M
R A
A A
A A'
A A
A A
A E
O S
c l
E T
N N
N N
N N
N N
N N
R l
i T
R 1
T P
)
I D
M 2
N O
O
(
U I
C R
E P
3 D
/
N Q
A A
A A
A A
A A
A 1
O E
S c
N N
N N
N N
N N
N 5
C R
T 2
E 3
S 3
P 3
D M
/
O O
1 I
C R
E P
3 B
T
/
S O
A A
A A
A A
A A
A 1
R E
S c
N N
N N
N N
N N
N 5 -
I R
T 23 R
F O
3 TA E
gg TT T
T T
T T
R UM V
U V
V V
N 5
6 7
8 9
'u E
i.
G gg 3
3 3
3 3
3 M
B B
B B
B B
AE J
1 2
2 G
G I
P G
I T
gg S
B B
IB B
B B
s o
t g
T n
d n
n N
i e
e i
E ns d
g n
n N
id l
n o
i O
au e
i p
a P
t td W
d m
t MO A
eS e d
o e
C E
R v
y a
C R
R d o g
l l
A enm en l s C
d e
rae rig at e
r9 M
u R
unn rr l
t u"
A ss sii go e
p s1 XE st n sat ep s
m st el e etl t p s
e el roh reo nu e
x ro PBW PRB I S V
E PB
COMPONENT -
REGENERATIVE IIEAT EXCHANGER UNIT 1 INTERVAL - FIRST FIRST PERIOD SECOND PERIOD THIRD PERIOD 10 YEARS OW W
GW RM COM EXAM AREA E
m REMARKS TS TS TS TS C
C C
C
^
NA NA 66-NA 33-NA Circumferential
=
e s 0%
2/3%
1/3%
100%
Welds BB B3.1 UT (1) 25-(1) 25-REM 100%(1)
(3) 5% of Each Circ Weld g
33-1/3%
33-1/3%
(1)
(3) is examined
^
"A NA (1) 00% = 12 Nozzles Nozzle to Shell 66-33-Welds BB B3.2 6T 25 -
25 -
2/3%
1/3%
M 100%
33-1/3%
33-1/3%
Not Applicable.
NA NA NA NA Nozzle Inside No Inside Radius Sectior.
Radius Section BB B3.2 UT NA NA NA NA NA NA NA NA Not Applicable.
Nozzle to Safe UT No Safe Ends.
End Welds BF B3.3 PT Pressure Retaining NA NA NA NA Not Applicable.
Bolts and Studs in 9*
BG1 B3.4 UT Place NA NA NA NA Pressure Retaining NA NA NA NA Not Applicable.
Bolts and Studs UT No Bolting.
When Removed BG1 B3.5 MT NA NA NA NA Pressure NA NA NA NA Not Applicable.
Retaining No Bolting.
Bolting BGl B3.6 VT NA NA NA NA NA NA NA NA (1) 100% = 3 Supports.
Integrally Welded 0%
0%
0%
0%
Supports 3 1/3%
33 /3%
NA NA NA NA (1) 100% = 3 Supports 0%
0%
(
VT NA NA NA NA
+-
t S
e e
e K
l l
l R
b b
A b
M ag a
a.
E cn c
cg R
ii i
i n ld l
l i pd p
pt pa p
pl Al A
A o C
B t
t t
oo o
oo NN N
NN TSR P
I M
F O
S C
RA L
E A
Y VR 0
E 1
O S
C A
A A
A A
A T
E T
N N
N N
N N
N R
I P
D M
O O
I C
R E
P
~
D R
I O
S C
A A
A A
A A
l E
T N
N N
N N
N iT R
1 T
P I
D M
N O
O U
I C
R E
P D
N Q
A A
A A
A A
O E
S C
C R
T N
N N
N N
N E
S R
EG P
D M
N O
O A
I C
H R
C E
X P
E T
T S
Q A
A A
A A
A R
E S
C A
N N
N N
N N
I R
T E
F H
E V
T T
T g
V
.V V
I T
C A
8 9
1 R
E g$
3 3
3 N
B B
B E
G 2
2 E
N I
P G
R B
B B
TN E
NO P
t00 C
s t
g g
d n en n
ee rig l i t n unn ed po sii sd mp sat sa em etl el xo reo VC EC P RB
-o.
s r
i dt r
ys e
e 1
1 g
T n
g a. ne htir cpru hmus S
eDs K
R x
e A
tEdr M
a eP E
e1 m R
i rc l
s oi ssft ara l et cps
)
2
(
TS R
W 0)
I F
O 02 6
S C
1(
RA L
E A
Y V
R 0
0)
E 1
O S c A
02 T
E T
N 1
N R
I M
0)
D O
O 02 I
C 1(
R E
P D
R I
Q S c A
A i
E T
N N
l T
R 1
T M
I D
N O
O U
I C
R E
P D
M N
S c A
A O
T N
N C
E R
S EGN A
D f
O O
i C
I X
R E
E P
TA TS 0
E R
S c
A A
I I
I T
N N
F NWOD T
T V
EL 9
S E
3 S
B EC X
P E
B T
N E
NO P
M O
A C
ER A
M s
A e
X l
E eez bd z uio TSN
n COMPONENT -
CLASS 1 PIPING UNIT 1 INTERVAL - PIRST FIRST PERIOD SECOND PERIOD THIRD PERIOD 10 YEARS EXAM AREA
]
g REMARKS g
TS TS TS TS g
c c
c c
pp c M e.
Safe NA NA NA NA
~ Safe End Welds BP B4.1 PT Under Each Separate g
g g
Component.
Pressure Retaining NA NA NA NA Not Applicable. All Bolts and Studs in n
ss h an 2" BG1 B4.2 dT Place NA NA NA NA Diameter.
Pressure Retaining NA NA NA NA Not Applicable. All Bolts and Studs UT Bolting Less Than 2" Removed BG1 B4.3 MT Diameter.
M NA NA Pressure NA NA NA NA Not Applicable.
Retaining All Bolting Less Than Bolting BGl B4.4 VT 2" Diameter.
NA NA NA NA Circumferential 6%
6%
13%
25%
(1) 100% = 294 Welds Pipe Welds BJ B4.5 UT 8%
6-1/4 -
6-1/4 -
REM of 8-1/3%
8-1/3%
25%
6%
6%
13%
25%
9%
8%
25%
~
NA NA NA NA NA NA NA NA Not Applicable.
9. " ""
No Longitudinal Pipe Pipe Welds BJ B4.5 UT gg Branch Pipe NA NA NA NA (1) 100% - 4 Welds Connections Greater 0%
0%
0%-
50%
Than 6" Diameter BJ B4.6 UT 6-1/4-6-1/4-REM 25%
8-1/3%
8-1/3%
25%
..-.;,,..~~,-
.. -...~. -. _.
/
s s
/
COMPONENT -
CLASS 1 PIPING UNIP 1 i
INTERVAL - FIRST
~~
FIRST PERIOD SECOND PERIOD THIPD PERIOD 10 YEARS EXAM AREA g
g REMARKS g
TS TS TS TS p
g C
C C
C Branch Pipe Connec-(
NA NA NA NA tions Less Than or 0%
23%
6%
29%
Equal to 6" BJ B4.7 PT 6-1/4 -
6-l/4 -
REM,/
25%
Diameter 8-1/3%
8-1/3%
25%
NA NA tQ NA (1) 100% = 430 Welds 4
Socket Welds BJ B4.8
.PT 0%
15%
10%
25%
l 6-1/4 -
6-1/4 -
pgg y
25%y 1
B-1/3%
8-1/3%
25%
+
)
NA NA NA NA (1) 100% - 18 Supports i
Integrally Welded Sockets BK1 B4.9 UT 11%
l' 11%
39%
/
6-1/4 -
6-1/4 -
REM of 8-1/3%
8-1/3%
25%
/
//
NA NA NA NA (1) 100k = 94 Supports i
Support Components BK2 B4.10 VT 25 -
1%
25 -
6%
93%
100%
100%
33-1/3%
33-1/3%
,f, REM e
/
r
"^
"^
"^
"^
"9 "Y Exempted 100%
100%
essure h st j
Components BP B4.ll VT 0%
0%
(1) 100%
(1)
NA NA NA (1)
NA NA NA NA (1) 100% = 13 Sets of Pressure 0%
69%
31%
1001 Flange Bolting Retaining-25 -
25 -
Boltin9 33-1/3%
33-1/3%
I F
f
[
l i
COMPONENT - REACTOR COOLANT PUMP "A" UNIT 1 INTERVAL - FIRST FIRST PERIOD SECOND PERIOD THIRD PERIOD 10 YEARS OMP A
I N EQ N
m REMARKS TS TS TS TS c
c c
c NA NA NA NA (1) 100% = 24 Studs (2) B5.1 Applies to Studs Pressure Retaining b5.1 0%
66-33-100%
Studs BGl B5*2 UT 25 -
25 -
in Place.
/
1/3%
100%
(3) g vg@s to Ms 33-1/3%
33-1/3%
(1) 100% - 24 Studs NA NA NA NA (2) If Bolting Removed.
B5.2 MT 01h 0%
0%
0%
(3) Bolting Not Removed NA NA NA (2)
(3)
During This Interval.
NA NA NA (2)
(1) 100% - 24 Studs 33-133-(2) As Accessible for 100%
0%
B5.3 VT 5
1/3%
Other Reasons.
REM 100%
33 1/3%
33 /3%
NA NA NA NA (1) If Bolting Removed.
(2) 100% - 24 Nuts Pressure Retaining 0%
0%
0%
0% (3)
Nuts BG1 B5.2 MT (3) Bolting Not Removed NA NA NA (1)
Durino This Interval.
(1) As Accessible for NA NA NA (1)
Other Reasons.
100%
0%
33-133-B5.3 VT 25 -
25 -
(2) 100% = 24 Nuts REM 1/3L 100%
1/3%
33-1/3%
33-1/3%
NA NA NA NA (1) If Disassembled Ligaments BG1 B5.3 VT 0%
01, 0%
0% (2)
(2) Pump Was Not Disassem-NA NA NA 100%(1) bled This Interval.
A t rally Integrally Welded NA NA NA NA W Id support Lugs BK1 B5.4 UT 0%
0%
0%
0%
(2) 100% = 3 Support Lugs NA NA NA 25% (1)
(3) Exam Not Practical (1) Of All Integrally NA NA NA NA Welded Supports.
33-33-(2) VT Performed Vice UT VT 0%
1/3%
P NA NA (1)
NA NA (y
NA NA (1) 100% - 3 Support Leos NA NA 66-33-100%
Support Legs BK2 B5.5 VT 25 -
25 -
2/3%
1/3%
REM 100%
33-1/31 33-1/3%
_ -.. -..~-
]
COMPONENT -
REACTOR COOLANT PUMP "A" UNIT 1 INTERVAL - FIRST FIRST PERIOD SECOND PERIOD THIRD PERIOD 10 YEARS REO COMP REQ COMP REO COMP REQ COMP EXAM AREA E
REMARKS TS TS TS TS C
C C
C (1) 100% of all Casing
"^
"^
"A "A
Welds in One RCP Punp Casing Welds BL1 B5.6 RT 0%
0%
0%
0%
(2) IB RCP Examined
)
NA NA NA 100%(1)
NA NA NA 100%(1)
(1) 100% of All Casing VT 0%
0%
0%
0%
NA NA NA NA (2) IB RCP Examined.
(1) 100% of the Internal NA NA NA NA Pump Casing PressureRetaininbP.
Surfaces of One R 0%
0%
0%
0%
n em s BR B5.7 W NA NA NA 100%(1)
(2) IB RCP Examined.
l NA NA NA NA (1) Performed During j
Exempted 100%
100%
Hydrostatic Pressure Components BP B5.'8 VT (l)
(1)
Test NA NA E
100%(1) l (1) Inplace UT i
NA (1)
(2)
NA (2) 100% UT (3)
III (2)
(3) Bore & Keyway Flvwheel UT (4)
(3)
(4) Top Surface pg NA NA NA NA NA NA NA (1) Bore & Keyway PT (1)
(1}
NA NA NA NA i
(1) Inplace VT (1)
NA NA NA (2) 100% VT fVT (3)
(1)
(2)
(3) VT of Top, Periphery, NA NA NA NA and Bore Surfaces g
e I
h 1
i 4
E f,
e-m
COMPONENT - REACTOR COOLANT PUMP "B" UNIT 1 INTERVAL - FIRST FIRST PERIOD SECOND PERIOD THIRD PERIOD 10 YEARS REO COMP REQ COMP REO COMP REQ COMP EXAM AREA 2:
c h
TS TS TS TS
~
c c
c c
NA NA NA NA (1) 100% = 24 Studs
.(2) B5.1 Applies to Studs Pressure Retaining B5.1 66-33-100%
in Place.
Studs BG1 B5*2 UT 25 -
25 -
2/3%
REM 1/3%
100%
.(3) B5.2 Applies to Studh 33-1/3%
33-1/3%
Removed.
(1) 100% - 24 Studs NA NA NA NA (2) If Bolting Removed.
B5.2 MT 0%.
0%
100%
100%
NA NA NA (2)
NA NA NA (2)
(1) 100% - 24 Studs 33-133-(2) As Accessible for B5.3 VT 100%
Og W
M er Reasons, RM 100g 33 /3%
33 /3%
flA NA NA NA (1) If Bclting Removed.
Pressure Retaining 0%
0%
100%
100%
(2) 100% - 24 Nuts Nuts BG1 B5.2 MT g
g g
(1) As Accessible for NA NA NA (1)
Other Reasons.
100%
0%
33-133-B5.3 VT 25 -
25 -
(2) 100% = 24 Nuts REM 1/3%
100%
1/3%
33-1/3%
33-1/3%
NA NA NA NA (1) If Disassembled Ligaments BG1 B5.3 VT 0%
0%
100%
100%
NA NA NA 100%(1)
(1) Of All Integrally Integrally Welded NA NA NA NA Welded Supports Support Lugs BKl B5.4 UT 0%
0%
0%
0%
(2) 100% = 3 Support Lugs HA NA NA 25% (1)
(3) Exam Not Practical NA NA NA NA (1) VT Performed Vice UT.
(2) 100% = 3 Support Lugs VT Og 0%
100%
100%
(3) of all Integrally NA NA NA (3)
NA (3)
Welded Lugs NA (1) 100% - 3 Support Legs NA NA 66-NA 33-100%
Support Legri BK2 B5.5 VT 25 -
25 -
2/3%
1/3%
REM 100%
33-1/31 33-1/3%
l
I COMPONENT -
REACTOR COOLANT PUMP "B" UNIT 1 INTERVAL - FIRST
=
PIRST PERIOD SECOND PERIOD TilIRD PERIOD 10 YEARS i
3 REO COMP REQ COMP REO COMP REQ COMP EXAM AREA y
y REMARKS g
Ts Ts Ts Ts g
g g
l C
C C
C (1) 100% of All Casing Welds NA NA NA NA in one RCP.
(2) Exam Done in Accordance Pump Casing Welds BL1 B5.6 RT 0%
0%
100%
100%
with 1977 Ed. Summer of NA NA NA 100%(1) 1979 Addenda of Sec. XI.
(Ltr. of 10-6-B1 to Denton)
NA NA NA 100%(1)
(1) 100% of All Casing Welds in one RCP.
0%
0%
100%
100%
NA NA NA NA NA NA NA NA (1) 100% of the Internal Pump Casing Internals BL2 B5.7 VT 0%
0%
100%
100%
Pressure Retaining surfaces of One RCP.
NA NA NA 100%(1) l NA NA NA NA
- E Hydrostatic Pressure 100%
100%
Components BP B5.8 VT st A
NA NA 100%(1)
Not Applicable, Pressure NA NA NA NA All Bolting is Greater pggg an am er.
Bolting BG2 B5.9 VT NA NA NA NA (1) In Place UT NA III (2)
NA (2) 100% UT (3)
(1)
(2)
Flywheel (3) Bore & Keyway UT NA (4)
NA (3)
NA NA (4) Top Surface NA NA NA NA (1) Bore & Keyway (1)
(1)
(1)
PT NA NA NA NA (1) In Place VT (1)
NA NA NA (2) 100% VT (3)
(2)
(2)
(3) VT of Top, Periphery &
VT NA NA NA NA Bore & Keyway Surfaces 2
COMPONENT - CLASS 1 VALVES UNIT 1 INTERVAL - FIRST PIRST PERIOD SECOND PERIOD THIRD PERIOD 10 YEARS REO COMP REQ COf f P REQ COMP REQ COMP EXAM AREA y
y R
RKS g
TS TS TS TS g
g g
C C
C C
Pressure Retaining NA NA NA NA Not Applicable. All Bolts and Studs Bolting less than 2" in Place BG1 B6.1 UT NA NA NA NA Pressure Retaining UT NA NA NA NA Not Applicable. All Bolts and Studs Bolting less than 2" When Removed BG1 B6.2 MT NA NA NA NA Diameter.
Pressure Retaining NA NA NA NA Not Applicable. All Bolting BG1 B6.3 VT Bolting less than 2" Diameter.
UA NA NA NA Integrally NA NA NA NA Not Applicable.
Welded No Valve Supports.
Supports BK1 B6.4 UT NA NA NA NA NA NA NA NA Not Applicable.
Support Components BK2 B6.5 VT No Valve Supports.
NA NA NA NA ne Large Gate Va he NA NA NA (1)
- 9#
Valve Body Welds BM1 B6.6 UT "E
V#l#
NA NA (2)
(3) of Valves of the Same Constructional Design, Manufacturing Method and Manufacturer that Perform Similar Functions.
(3) Only the 10" Velan Gate Valves Have Body Welds.
COMPONENT - CLASS 1 VALVES UNIT 1 INTERVAL - FIRST FIRST PERIOD SECOND PERIOD TillRD PERIOD 10 YEARS Op W
COM M
COM EO COW EXAM AREA E
,m pggggg3 e
TS TS TS TS c
c c
c (1) VT of one Large Check IJA
!!A IJA (1) 2 1
4 7
Valve and One Large Gate Valve Bodies BM2 B6.7 VT Valves Valve Valves.
Valves Valve.
11A NA NA (2)
(2) VT of one Valve in each Group of Valves of the Same Constructional Desion, Manufacturing Methods and
. Manufacturer That Performs Similar Functions.
(3) Valves Examined -
10" Darling Gate Valve 10" Darling Check Valve 10" Velan Gate Valve 4" Velan Gate Valve 3" Velan Gate Valve 6" Velan Check Valve 3" Co es Vulcan Globe va ve NA NA NA NA (1) During Hydrostatic Exempt Components BP B6.2 VT 100%
100%
Pressure Test (1) 100%
(1)
NA NA NA (1) 11A NA NA (1)
(1) As Accessible for Pressure Retaining Bolting BG2 B6.9 VT 25 -
25 -
100%
33-1/3%
33-1/3%
ENCLOSURE 2
SUMMARY
OF ASME SECTION XI PRESSURE TESTS ASME Sect XI Class Reference Type of Test Frequency Status 1
IWB' 5210 (a)
Hydrostatic pressure test 100% every 10 years 100% complete IWB 5210 (b)
Leakage test 100% overy 100% complete refueling outage 2
IWC-2412 (a)
Pressure test of exempt 100% each interval 100% complete components l
( }
IWC-2412(b)
Not applicable III 3
IWD-2410 (b)
Hydrostatic pressure test 100% every 10 years 75% complete IWD-2410 (c)
Inservice pressure test 100% every period 100% complete II This requirement was adopted during the third period.
WE committed to the performance of 33-1/3% of the required Class 3 hydrostatic pressure tests for the first 10-year l
interval in our inservice inspection plan submitted May 20. 1977.
l
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As stated in our inservice inspection plan, all Class 2 systems are exempt in accor-dance with IWC-1220