ML20080D692: Difference between revisions

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l TRLECOPY TO NRC gggg pg;g j Aug. 22, 1983 Ap a v -
l TRLECOPY TO NRC Aug. 22, 1983     gggg pg;g j Ap a v -     .:n g s t A U. S. Nuclear Regulatory Commission Region II                                     83 AUG25 A 9 : 0 8 101 Marietta Street, NW Suite 3100 Atlanta, Georgia 30303 BFRO-50-259/83049R7 Reported under Technical Specification 6.7 2.a.(3)
.:n g s t A U. S. Nuclear Regulatory Commission Region II 83 AUG25 A 9 : 0 8 101 Marietta Street, NW Suite 3100 Atlanta, Georgia 30303 BFRO-50-259/83049R7 Reported under Technical Specification 6.7 2.a.(3)
Telecony Date   8/22/83 ling 1100 Date of Occurrence: 8/12/83 Time of occurrence:   1400   Unit 1 Technical Specification Involved:   3.6.G Conditions Prior to Occurrence Unit 1 in refueling outage Unit 2 at 3139 MWt Unit 3 at 3081 MWt Identification artd Descriotion of Occurrengg Weld DCS-1-7 (core spray) has an intermittent indication on the pipe side of the weld that is 360-degrees in length and approximately 415 through wall depth. This is a 12-inch, 304 stainless steel, schedule 80 pipe. The cracking is between the manual isolation valve and the testable check valve (inboard containment isolation valve).
Telecony Date 8/22/83 ling 1100 Date of Occurrence: 8/12/83 Time of occurrence:
1400 Unit 1 Technical Specification Involved:
3.6.G Conditions Prior to Occurrence Unit 1 in refueling outage Unit 2 at 3139 MWt Unit 3 at 3081 MWt Identification artd Descriotion of Occurrengg Weld DCS-1-7 (core spray) has an intermittent indication on the pipe side of the weld that is 360-degrees in length and approximately 415 through wall depth. This is a 12-inch, 304 stainless steel, schedule 80 pipe. The cracking is between the manual isolation valve and the testable check valve (inboard containment isolation valve).
Weld DSRWC-1-3 (reactor water cleanup) has two indications that are approx-imately 5" long between 11:30 and 2:30 and 1-1/2" long between 8:30 and 9:30 with a through-wall depth of greater than 80%. This is a 6-inch, 304 stainless steel, schedule 304 pipe. The cracking is between the inboard and outboard containment isolation valves.
Weld DSRWC-1-3 (reactor water cleanup) has two indications that are approx-imately 5" long between 11:30 and 2:30 and 1-1/2" long between 8:30 and 9:30 with a through-wall depth of greater than 80%. This is a 6-inch, 304 stainless steel, schedule 304 pipe. The cracking is between the inboard and outboard containment isolation valves.
Weld DCS-1-8 (core spray) has two indications that are approximately 9" long between 12:30 and 3:30 and 3" long between 9:30 and 10:30 with a through-wall depth of approximately 30%. lais is a 12-inch, 304 stainless steel, schedule 80 pipe. The cracking is on the reactor vessel side of the pipe-to-valve weld on valve HCV-75-27 (manual isolation valve).
Weld DCS-1-8 (core spray) has two indications that are approximately 9" long between 12:30 and 3:30 and 3" long between 9:30 and 10:30 with a through-wall depth of approximately 30%. lais is a 12-inch, 304 stainless steel, schedule 80 pipe. The cracking is on the reactor vessel side of the pipe-to-valve weld on valve HCV-75-27 (manual isolation valve).
Weld DSRWC-1-2 (reactor water cleanup) has a indication that is                     ;
Weld DSRWC-1-2 (reactor water cleanup) has a indication that is approximately 3" long between 12:00 and 1:00 with a through-wall depth of greater than 50%. This is a 6-inch, 304 stainless steel, schedule 80 pipe.
approximately 3" long between 12:00 and 1:00 with a through-wall depth of     '
The cracking is between the inboard and outboard containment isolation
l greater than 50%. This is a 6-inch, 304 stainless steel, schedule 80 pipe.         (
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The cracking is between the inboard and outboard containment isolation             )
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8308300550 830822 PDR ADOCK 05000259 S
8308300550 830822 PDR ADOCK 05000259 S                  PDR y$gM,qd '-
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TRLFCOPY TO NRC Aug. 22, 1983 Corrective Action-Because of the additional weld cracks discovered, an additional 29 welds will be inspected. This will increase the total number of welds to be inspected from 53 to 82 (see attachment for the number of welds per system and the inspection status). This includes all stainless steel welds greater than 1" diameter in all safety-related systems. These 82 welds are composed of Class 1 and 2 stainless steel and dissimiliar metal (carbon steel to stainless steel) circumferential butt welds that fall within the scope of Section II. This will consist of:
TRLFCOPY TO NRC Aug. 22, 1983 Corrective Action-Because of the additional weld cracks discovered, an additional 29 welds will be inspected. This will increase the total number of welds to be inspected from 53 to 82 (see attachment for the number of welds per system and the inspection status). This includes all stainless steel welds greater than 1" diameter in all safety-related systems. These 82 welds are composed of Class 1 and 2 stainless steel and dissimiliar metal (carbon steel to stainless steel) circumferential butt welds that fall within the scope of Section II.
                  . Class 1, stainless steel welds on the CS System, RWCU System and on the RHR head spray line.
This will consist of:
                  . Class 1 and 2, dissimiliar metal (carbon steel to star..less steel) welds.
Class 1, stainless steel welds on the CS System, RWCU System and on the RHR head spray line.
4
Class 1 and 2, dissimiliar metal (carbon steel to star..less steel) welds.
                  . Class 2, stainless steel portion of the HPCI System, CS System and RHR discharge piping.
4 Class 2, stainless steel portion of the HPCI System, CS System and RHR discharge piping.
I                 Uedate Item
I Uedate Item To date the attached are our inspection results.
;              To date the attached are our inspection results.
[h*
[h*
JI.A.Coffey Acting Power Plant Superintendent
JI.A.Coffey
[ Browns Ferry Nuclear Plant i
[ Browns Ferry Nuclear Plant Acting Power Plant Superintendent i
4
4


r ATTACHMENT - BFR0 50-259/8'404cR7 Total Inspection     Inspection     Inspection   Welds with     Under Reauired           Comolete     Satisfactory   Crooks     Evaluation HPCI                   O                   O               O         O                 O C:re Spray           34                   29               24         2                 3 RWCU                 14                   7               5         2                 0 RHR (Class 1)         1                   0               0         0                 0 RHR (Head Spray)     27                   23               23         0                 0 RHR (Discharge)       2                   0               0         0                 0 CRD                   1                   0               0         0                 0 TOTAL                 79                   59               52         4                 3 SATISFACTORY C:re Spray         CS 1-67 DCS 1-6, 9, 14, 15,18, 16, 17, 5, 4 DSCS 1-4, 5, 6, 8, 9, 10, 11, 12, 13, 3, 1, 2, 7, 13 RHR (Head Spray)   DHS 1-2, 3, 4, 5, 6 DSHS 1-1A, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13, 14, 15, 17, 18, 19 TRHR 1-454G RWCU               DRWC 1-4, 1 DSRWC 1-7, 4 TRWC 1-1
r ATTACHMENT - BFR0 50-259/8'404cR7 Total Inspection Inspection Inspection Welds with Under Reauired Comolete Satisfactory Crooks Evaluation HPCI O
O O
O O
C:re Spray 34 29 24 2
3 RWCU 14 7
5 2
0 RHR (Class 1) 1 0
0 0
0 RHR (Head Spray) 27 23 23 0
0 RHR (Discharge) 2 0
0 0
0 CRD 1
0 0
0 0
TOTAL 79 59 52 4
3 SATISFACTORY C:re Spray CS 1-67 DCS 1-6, 9, 14, 15,18, 16, 17, 5, 4 DSCS 1-4, 5, 6, 8, 9, 10, 11, 12, 13, 3, 1, 2, 7, 13 RHR (Head Spray)
DHS 1-2, 3, 4, 5, 6 DSHS 1-1A, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13, 14, 15, 17, 18, 19 TRHR 1-454G RWCU DRWC 1-4, 1 DSRWC 1-7, 4 TRWC 1-1


e i
e i
ATTACHMENT - BFRO 50-254/8'4049R7 UNDER EVALUATION Core Spray           CS 1-69 DCS 1-1A, 2
ATTACHMENT - BFRO 50-254/8'4049R7 UNDER EVALUATION Core Spray CS 1-69 DCS 1-1A, 2 ESTIMATED COMPLETION DATE August 25, 1983 This is an update of the event first reported previously on 8/11/83, and includes all the results through 1330 on 8/19/83 This information was provided verbally to Floyd Cantrell en 8/19/83 r
;        ESTIMATED COMPLETION DATE August 25, 1983 This is an update of the event first reported previously on 8/11/83, and includes all the results through 1330 on 8/19/83     This information was provided verbally to Floyd Cantrell en 8/19/83 r
.}}
_ _ _  _                                                                                  .               _ _ _ _}}

Latest revision as of 22:21, 14 December 2024

Telecopy RO 83049R7:on 830812,indications Discovered on Core Spray Welds DCS-1-7 & DCS-1-8 & Reactor Water Cleanup Welds DSRWC-1-3 & DSRWC-1-2.Addl 29 Welds Will Be Inspected.Insp Results Encl
ML20080D692
Person / Time
Site: Browns Ferry Tennessee Valley Authority icon.png
Issue date: 08/22/1983
From: Coffey J
TENNESSEE VALLEY AUTHORITY
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
RO-83049R7, NUDOCS 8308300550
Download: ML20080D692 (4)
v • d • e


Text

I I

l TRLECOPY TO NRC gggg pg;g j Aug. 22, 1983 Ap a v -

.:n g s t A U. S. Nuclear Regulatory Commission Region II 83 AUG25 A 9 : 0 8 101 Marietta Street, NW Suite 3100 Atlanta, Georgia 30303 BFRO-50-259/83049R7 Reported under Technical Specification 6.7 2.a.(3)

Telecony Date 8/22/83 ling 1100 Date of Occurrence: 8/12/83 Time of occurrence:

1400 Unit 1 Technical Specification Involved:

3.6.G Conditions Prior to Occurrence Unit 1 in refueling outage Unit 2 at 3139 MWt Unit 3 at 3081 MWt Identification artd Descriotion of Occurrengg Weld DCS-1-7 (core spray) has an intermittent indication on the pipe side of the weld that is 360-degrees in length and approximately 415 through wall depth. This is a 12-inch, 304 stainless steel, schedule 80 pipe. The cracking is between the manual isolation valve and the testable check valve (inboard containment isolation valve).

Weld DSRWC-1-3 (reactor water cleanup) has two indications that are approx-imately 5" long between 11:30 and 2:30 and 1-1/2" long between 8:30 and 9:30 with a through-wall depth of greater than 80%. This is a 6-inch, 304 stainless steel, schedule 304 pipe. The cracking is between the inboard and outboard containment isolation valves.

Weld DCS-1-8 (core spray) has two indications that are approximately 9" long between 12:30 and 3:30 and 3" long between 9:30 and 10:30 with a through-wall depth of approximately 30%. lais is a 12-inch, 304 stainless steel, schedule 80 pipe. The cracking is on the reactor vessel side of the pipe-to-valve weld on valve HCV-75-27 (manual isolation valve).

Weld DSRWC-1-2 (reactor water cleanup) has a indication that is approximately 3" long between 12:00 and 1:00 with a through-wall depth of greater than 50%. This is a 6-inch, 304 stainless steel, schedule 80 pipe.

The cracking is between the inboard and outboard containment isolation

valves, j

)

y$gM,qd '-

8308300550 830822 PDR ADOCK 05000259 S

PDR fb

!\\t

\\

TRLFCOPY TO NRC Aug. 22, 1983 Corrective Action-Because of the additional weld cracks discovered, an additional 29 welds will be inspected. This will increase the total number of welds to be inspected from 53 to 82 (see attachment for the number of welds per system and the inspection status). This includes all stainless steel welds greater than 1" diameter in all safety-related systems. These 82 welds are composed of Class 1 and 2 stainless steel and dissimiliar metal (carbon steel to stainless steel) circumferential butt welds that fall within the scope of Section II.

This will consist of:

Class 1, stainless steel welds on the CS System, RWCU System and on the RHR head spray line.

Class 1 and 2, dissimiliar metal (carbon steel to star..less steel) welds.

4 Class 2, stainless steel portion of the HPCI System, CS System and RHR discharge piping.

I Uedate Item To date the attached are our inspection results.

[h*

JI.A.Coffey

[ Browns Ferry Nuclear Plant Acting Power Plant Superintendent i

4

r ATTACHMENT - BFR0 50-259/8'404cR7 Total Inspection Inspection Inspection Welds with Under Reauired Comolete Satisfactory Crooks Evaluation HPCI O

O O

O O

C:re Spray 34 29 24 2

3 RWCU 14 7

5 2

0 RHR (Class 1) 1 0

0 0

0 RHR (Head Spray) 27 23 23 0

0 RHR (Discharge) 2 0

0 0

0 CRD 1

0 0

0 0

TOTAL 79 59 52 4

3 SATISFACTORY C:re Spray CS 1-67 DCS 1-6, 9, 14, 15,18, 16, 17, 5, 4 DSCS 1-4, 5, 6, 8, 9, 10, 11, 12, 13, 3, 1, 2, 7, 13 RHR (Head Spray)

DHS 1-2, 3, 4, 5, 6 DSHS 1-1A, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13, 14, 15, 17, 18, 19 TRHR 1-454G RWCU DRWC 1-4, 1 DSRWC 1-7, 4 TRWC 1-1

e i

ATTACHMENT - BFRO 50-254/8'4049R7 UNDER EVALUATION Core Spray CS 1-69 DCS 1-1A, 2 ESTIMATED COMPLETION DATE August 25, 1983 This is an update of the event first reported previously on 8/11/83, and includes all the results through 1330 on 8/19/83 This information was provided verbally to Floyd Cantrell en 8/19/83 r

.

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