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DOCKET 50-155 - LICENSE DPR BIG ROCK POINT PLANT -
DOCKET 50-155 - LICENSE DPR BIG ROCK POINT PLANT -
GENERIC LETTER 84-11 INTERGRANULAR STRESS CORROSION CRACKING (IGSCC) INSPECTION PROGRAM Nuclear Regulatory Commission Generic Letter 84-11, Inspections of BWR Stainless Steel Piping, dated April 19, 1984 required Consumers Power Company to submit plans relative to inspections for intergranular stress corrosion cracking (IGSCC) of stainless steel piping and to submit plant specific
GENERIC LETTER 84-11 INTERGRANULAR STRESS CORROSION CRACKING (IGSCC) INSPECTION PROGRAM Nuclear Regulatory Commission Generic Letter 84-11, Inspections of BWR Stainless Steel Piping, dated April 19, 1984 required Consumers Power Company to submit plans relative to inspections for intergranular stress corrosion cracking (IGSCC) of stainless steel piping and to submit plant specific
       -leakage detect 1on information. Our response to this request was submitted by letter dated May 25, 1984 and additional clarifying information was provided by letter dated July 2, 1985. The results of the IGSCC weld inspections, which were completed as committed to in our response, were submitted by letter
       -leakage detect 1on information. Our response to this request was submitted by {{letter dated|date=May 25, 1984|text=letter dated May 25, 1984}} and additional clarifying information was provided by {{letter dated|date=July 2, 1985|text=letter dated July 2, 1985}}. The results of the IGSCC weld inspections, which were completed as committed to in our response, were submitted by letter
       ' dated October 31, 1985. By letter dated February 4,'1986, the NRC provided an evaluation of our responses and requested additional information. Our letter dated October 13, 1986 provided the additional information and we committed to perform additional-IGSCC inspections during the 1987 refueling outage. This letter also informed the NFC of our intent to conduct a study to determine the basis for the lack of IGSCC problems and Big Rock Point. By letter dated October 28, 1986, the NRC accepted our inspection sample size cud informed us that the leakage detection concerns remain under NRC technical staff review.
       ' dated October 31, 1985. By letter dated February 4,'1986, the NRC provided an evaluation of our responses and requested additional information. Our {{letter dated|date=October 13, 1986|text=letter dated October 13, 1986}} provided the additional information and we committed to perform additional-IGSCC inspections during the 1987 refueling outage. This letter also informed the NFC of our intent to conduct a study to determine the basis for the lack of IGSCC problems and Big Rock Point. By {{letter dated|date=October 28, 1986|text=letter dated October 28, 1986}}, the NRC accepted our inspection sample size cud informed us that the leakage detection concerns remain under NRC technical staff review.
Having completed our study, we were not able to ascertain why Big Rock Point is unique in that IGSCC is not a problem at our facility. We are, however, submitting an on-going IGSCC Inspection Program to be implemented beginning with the 1988 refueling outage.
Having completed our study, we were not able to ascertain why Big Rock Point is unique in that IGSCC is not a problem at our facility. We are, however, submitting an on-going IGSCC Inspection Program to be implemented beginning with the 1988 refueling outage.
Big Rock Point has sampled IGSCC susceptible welds on three different occasions involving 59 examinations on 41 of the 65 welds that are accessible.
Big Rock Point has sampled IGSCC susceptible welds on three different occasions involving 59 examinations on 41 of the 65 welds that are accessible.

Latest revision as of 16:25, 20 March 2021

Forwards IGSCC Insp Program for Facility.Program Developed from Guidance Offered by IE Bulletin 83-02,Generic Ltr 84-11 & NUREG-0313 as Well as Practical Considerations for Plant
ML20235K009
Person / Time
Site: Big Rock Point File:Consumers Energy icon.png
Issue date: 09/30/1987
From: Frisch R
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
RTR-NUREG-0313, RTR-NUREG-313 GL-84-11, IEB-83-02, IEB-83-2, NUDOCS 8710020198
Download: ML20235K009 (11)
v • d • e


Text

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Consumers l

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@rowsmas mmmemrs passness Power General offices: 1945 West Parnell Road, Jackson, MI 49201 . (517) 788-0550 7 September 30, 1987 _

Nuclear Regulatory Commission Document Control Desk

. Washington, DC -20555

)

DOCKET 50-155 - LICENSE DPR BIG ROCK POINT PLANT -

GENERIC LETTER 84-11 INTERGRANULAR STRESS CORROSION CRACKING (IGSCC) INSPECTION PROGRAM Nuclear Regulatory Commission Generic Letter 84-11, Inspections of BWR Stainless Steel Piping, dated April 19, 1984 required Consumers Power Company to submit plans relative to inspections for intergranular stress corrosion cracking (IGSCC) of stainless steel piping and to submit plant specific

-leakage detect 1on information. Our response to this request was submitted by letter dated May 25, 1984 and additional clarifying information was provided by letter dated July 2, 1985. The results of the IGSCC weld inspections, which were completed as committed to in our response, were submitted by letter

' dated October 31, 1985. By letter dated February 4,'1986, the NRC provided an evaluation of our responses and requested additional information. Our letter dated October 13, 1986 provided the additional information and we committed to perform additional-IGSCC inspections during the 1987 refueling outage. This letter also informed the NFC of our intent to conduct a study to determine the basis for the lack of IGSCC problems and Big Rock Point. By letter dated October 28, 1986, the NRC accepted our inspection sample size cud informed us that the leakage detection concerns remain under NRC technical staff review.

Having completed our study, we were not able to ascertain why Big Rock Point is unique in that IGSCC is not a problem at our facility. We are, however, submitting an on-going IGSCC Inspection Program to be implemented beginning with the 1988 refueling outage.

Big Rock Point has sampled IGSCC susceptible welds on three different occasions involving 59 examinations on 41 of the 65 welds that are accessible.

In all cases, no indication of IGSCC was observed. Big Rock Point has significant design differences from the aewer design BWR's. Industry experience has shown BWR's to develop IGSCC in less than 10 years of operation. The weld sensitization at Big Rock Point is no less than that of other BWR's, and yet, IGSCC has not affected recirculation piping in over 24 years of operation. While it is not fully understood why Big Rock Point does not experience IGSCC, the examination history for IGSCC at Big Rock Point

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'OC0987-0175-NLO2 hdk 8710020198 870930 L1 PR ADOCK 05000155 k PDR

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Nuclear Regulatory Commission 2 j Big Rock Point Plant Generic Letter 84-11 September 30, 1987 lends support to this not being a significant concern. Consumers Power Company's position regarding IGSCC has not changed from earlier submittals.

Attachment 1 contains the IGSCC Inspection Program for Big Rock Point-. This program has been developed from the guidance of fered by IE Bulletin 63-?2, Generic Letter 84-11, and NUREG 0313, as well as practical consideratfor.s for the plant. This program establishes the sample size for Big Rock Poiar such that all accessible welds will have been examined for IGSCC by the end of the next two refueling outages. After all accessible IGSCC susceptible welds have been examined, a re-exam schedule will be established. The number of examinations during any refueling will escalate per the requirement of IWB-2400, if IGSCC is found. In that case, evaluation of the observed IGSCC will be per IWB-3500 and analysis, if required, will be per IWB-3600. Repairs will be by weld overlay reinforcement, partial weld replacement or full weld replacement, depending on the conditions at the time. Flaw repairs will be handled on a case by case basis.

All examinations for IGSCC will utilize qualified examiners and procedures as required by 1E Bulletin 83-02. Documentation of qualifications and procedures will be maintained with the records of the ISI final reports. Pending NRC evaluation and response to our October 13, 1986 submittal, leakage detection measures will not be enhanced.

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k""M A lal h R Ffisch

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Senior Licensing Analyst f l

CC Administrator, Region Ill, NRC NRC Resident Inspector - Big Rock Point Plant 1

Attachment i

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J OC0987-0175-NLO2 l

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ATTACHMENT 1 Consumers Power Company Big Rock Point Plant Docket 50-155 BIG ROCK POINT IGSCC INSPECTION PROGRAM September 30, 1987 8 Pages AT0987-0174-NLO2

'4 BIG ROCK POINT IGSCC INSPECTION PROGRAM I. Scope and Schedule A. Refueling Outage 22 (1988) 12 welds never before examined B. Refueling Outage 23 (1989) 12 welds never before examined NOTE: Upon completion of these examinations, all accessible IGSCC susceptible welds will have been examined at least once.

C. Refueling Outage 24 (1990)

Re-exam schedule to be determined after Refueling Outage 23.

D. Refueling Outage 25 (Approximately 1991)

Re-exam schedule to be determined after Refueling Outage 23.

E. Refueling Outage 26 (approximately 1992)

1) 10 year interval reactor vessel inspection
2) 12 welds never before examined by IGSCC qualified procedure which are only accessible during reactor vessel 1SI.
11. Revision of Scope and Schedule A. If IGSCC is detected during an inspection, the number of welds to be examined will escalate per the requirements of ASME Boiler and Pressure Vessel Code,Section XI, Subsection IWB-2430, 1977 Edition through Summer 1978 Addenda, j B. If IGSCC is detected, indications will be evaluated per ASME Boiler j and Pressure Vessel Code,Section XI, Subsection IWB-3500, 1977 Edition through Summer 1978 Addenda.  ;

C. If an indication is unacceptable, repair will be by weld overlay reinforcement, partial weld replacement or full weld replacement.

Any and/or all flaw repair (s) will be handled on a case by case basis. Other repair methods may be used if appropriate materials and processes are available that offer the repaired weld sufficient resistance to IGSCC.

AT0987-0174-NLO2 l

l L 2 I

I' D. Indications may be analyzed per ASME Boiler and Pressure Vessel Code,Section XI, Subsection IWB-3600, 1977 Edition through Summer 1978 Addenda.

E. Scope and schedule for IGSCC examinations will be amended for refueling outages beyond that of the 23rd cycle, after all accessible welds have been examined at least once.

III. Qualification of Examinations A. All IGSCC examinations will incorporate qualified examiners and procedures in accordance with IE Bulletin 83-02.

IV. Leak Detection Leak detection capability will not be enhanced pending NRC evaluation and response to our October 13, 1986 submittal.

V. Summary To date Big Rock Point has performed 59 examinations for IGSCC on 41 of the 65 accessible welds. For detailed information on these examinations and a history of correspondence on IGSCC at Big Rock Point refer to the Reference section. The program for the inspection of IGSCC is to perform examinations such thet all 65 accessible will have been examined at least once by the end of the 23rd Refueling Outage. In addition, susceptible welds with limited access will be examined during the full reactor vessel examination at the end of the 10 year 1SI interval. It is our intent that after the 23rd Refueling Outage, the scope and schedule of this program will be amended.

V1. References

1. Generic Letter 81-04  ;
2. Responses from Consumers Power Company to Generic Letter 81-04 dated 6-30-81 and 6-22-83
3. IE Bulletin 83-02 j I
4. Consumers Power Company's response to IE Bulletin 85-02 dated 5-4-83 and j 5-12-83 I l

S. NRC Inspection Report 50-155/83010 l l

6. Generic Letter 84-11
7. Consumers Power Company's response to Generic Letter 84-11 dated 5-25-84 and 7-2-85

-AT0987-0174-NLO2

3

8. NRC' Inspection Report 50-155/85018

'9. NRC evaluation of Consumers Power Company's response to Generic Letter 84-11 dated 2-4-86

10. Letter from Consumers Power Company to NRC on additional IGSCC inspections for Generic Letter 84-11 dated 10-13-86
11. Letter from NRC to Consumers Power Company on Generic Letter 84-11 dated 10-28-86
12. NRC Inspection Report 50-155/87003
13. NRC Inspection Report 50-155/87021 1

l 1 j I

I I

AT0987-0174-NLO2

___-_____ _____ _ __ _ _ __ O

4 BIG ROCK POINT IGSCC SUSCEPTIBLE WELD LIST Field Previous IGSCC Comments / Previous Weld ID Weld Exams Routine ISl Exams

1. 4-MRS-141-1 Yes ISI 1-3
2. 4-MRS-141-2 No ISI 2-4 ISI 1-3
3. 4-MRS-141-3 No ISI 2-4 ISI 1-3
4. 4-MRS-141-4 No ISI 2-4 ISI 1-1
5. 4-MRS-141-5 No ---- ISI 1-1
6. 4-MRS-141-6 No ISI 2-3, 2-4 ISI 1-1
7. 4-MRS-141-7 No ISI 2-3,2-4 ISI 1-1
8. 4-MRS-141-8 No ISI 2-4 ISI 1-2
9. 4-MRS-141-9 No ----

No exam due to configuration

10. 4-MRS-141-10 No ISI 2-4 ISI 1-2
11. 4-MRS-141-11 Yes ---- No exam due to configuration
12. 4-RDC-101-l' Yes ----

ISI 1-4

13. 4-RDC-101-2 Yes ---- ISI 1-4
14. 4-RDC-101-3 Yes ISI 1-1, I-2, 1-3, 1-4
15. 4-RDC-101-30 Yes ---- ----
16. 4-RDC-101-31 Yes ----

ISI 1-9 17, 5-MRS-131-1 Yes ---- ---- ,

18. 5-MRS-131-2 No ---- ----
19. 5-MRS-131-3 No ---- ----

20, 5-MRS-131-4 Yes ISI 1-7

21. 5-MRS-131-5 Yes ---- ----
22. 5-MRS-131-6 No ---- ----

l

23. 5-MRS-151-7 No ISI 2-3 ISI 1-7 1

24, 5-MRS-131-8 No ---- ----

5 AT0987-0174-NLO2 l

5 Field Previous IGSCC Comments / Previous Weld ID Weld Exams Routine ISI Exams

25. 5-MRS-131-9 Yes ----
26. 5-MRS-132-1 Yes ---- ----

27, 5-MRS-132-2 No- ISI 2-4 ----

28. 5-MRS-132-3 No ISI 2-3, 2-4 ISI 1-3
29. 5-MRS-132-4 Yes ISI 2-4 ISI 1-3 30, 5-MRS-132-6 Yes ---- ISI 1-3, 1-6
31. 5-MRS-132-7 No ISI 2-3, 2-4 ISI 1-3
32. 5-MRS-132-8 No ISI 2-4 ISI 1-3
33. 5-MRS-132-9 No ----

No UT exam due to configuration

34. 5-MRS-132-10 No ----

No UT exam due to configuration

35. 5-MRS-132-11 Yes ISI 2-4 ISI 2-3
36. 6-SCS-101-2 Yes ----

Inaccessible (RR-A38)

37. 6-SCS-101-3 * ----

Inaccessible (RR-A38)

38. 6-SCS-101-4
  • Inaccessible (RR-A38)
39. 6-SCS-101-5 * ----

Inaccessible (RR-A38)

40. 6-SCS-101-6 * ----

Inaccessible (RR-A38) 41, 6-SCS-101-7 * ----

Inaccessible (RR-A38)

42. 6-SCS-102-22
43. 6-SCS-102-23
44. 6-SCS-102-24
  • ISI 2-4 ISI 1-3, 2-3 45, 6-SCS-102-25
46. 6-SCS-102-25A
  • IS1 2-4 ----
47. 6-SCS-102-26
48. 795-11F No ---- ISI 1-2, 1-9 Mechanized Nozzle-to-Safe End I
  • Currently undetermined AT0987-0174-NLO2

6 Field Previous IGSCC Comments / Previous Weld ID Weld Exams Routine ISI Exams 49, 14-MRS-101-1 Yes ----

ISI 1-9 Mechanized

50. 14-MRS-101-2 No ----

Inaccessible

51. 14-MRS-101-5 Yes Inaccessible
52. 14-MRS-101-4 No ----

Inaccessible

53. 14-MRS-101-5 Yes ISI 2-4 ----
54. 14-MRS-101-6 No ISI 2-4 ISI 1-4
55. 795-11E No ---- ISI 1-2, 1-9 Mechanized Nozzle-to-Safe End
56. 14-MRS-102-1 Yes ----

ISI 1-9 Mechanized

57. 14-MRS-102-2 No ---- Inaccessible
58. 14-MRS-102-3 No ----

Inaccessible

59. 14-MRS-102-4 Yes ----

Inaccessible

60. 14-MRS-102-5 No ---- Inaccessible
61. 14-MRS-102-6 Yes ISI 1-9,2-3,2-4 ISI 1-7
62. 14-MRS-102-7 No ISI 1-9, 2-4 ISI 1-7
63. 795-11D No ---- ISI 1-2, 1-5, 1-9 Mechanized Nozzle-to-Safe End
64. 14-MRS-103-1 Yes ----

ISI 1-9 Mechanized

65. 14-MRS-103-2 No ----

Inaccessible

66. 14-MRS-103-3 No ----

Inaccessible

67. 14-MRS-103-4 Yes ----

Inaccessible

68. 14-MnS-103-5 Yes ISI 2-4 ----

p

69. 14-MRS-103-6 No ISI 2-4 ISI 1-5
70. 795-11C No ----

ISI 1-2, 1-5, 1-9 Mechanized Nozzle-to-Safe End AT0987-0174-NLO2 l

7 Field Previous IGSCC Comments / Previous Weld ID Weld Exams Routine ISI Exams

71. 14-MRS-104-1 Yes ---- ISI 1-9 Mechanized

.72. 14-MRS-104-2 No ----

Inaccessible

73. 14-MRS-104-3 No ---- Inaccessible
74. 14-MRS-104-4 Yes ----

Inaccessibic

75. 14-MRS-104-5 Yes ISI 2-4 ----
76. 14-MRS-104-6 No ---- ISI 1-3, 1-4
77. 795-11B No ---- ISI 1-2, 1-9 Mechanized Nozzle-to-Safe End
78. 14-MRS-105-1 Yes ----

ISI 1-9 Mechanized

79. 14-MRS-105-2 No ---- Inaccessible l
80. 14-MRS-105-3 Yes ----

Inaccessible 1

81. 14-MRS-105-4 No ----

Inaccessible

82. 14-MRS-105-5 Yes ISI 1-9, 2-3 ISI 1-7
83. 14-MRS-105-6 No ISI 2-3 ISI 1-7
84. 795-11A No ---- ISI 1-2, 1-9 Mechanized Nozzle-to-Safe End 85, 14-MRS-106-1 Yes ---- ISI 1-9 Mechanized
86. 14-MRS-106-2 No ---- Inaccessible
87. 14-MRS-106-3 Yes ---- Inaccessible
88. 14-MRS-106-4 No ---- Inaccessible
89. 14-MRS-106-5 Yes ISI 1-9, 2-3 ----

l 90. 14-MRS-106-6 No ISI 1-9 ISI 1-3, 1-4, 1-8, 2-3

91. 17-MRS-111-1 No ----

ISI 1-5

92. 17-MRS-111-2 Yes ---- ----

l AT0987-0174-NLO2

8 l

l I

Field Previous IGSCC Comments / Previous Weld'ID. Weld Exams Routine ISI Exams

93. 17-MRS-111-7 Yes ISI 1-9,2-3,2-4 ISI 1-4
94. 17-MRS-111-7LD-1 No ISI 2-4 ISI 1-4 1
95. 17-MRS-111-7LD-2 No ISI 2-4 ISI 1-4
96. 17-MRS-112-1 No ----

ISI 1-5

97. 17-MRS-112-2 Yes ISI 1-9,2-3 ISI 1-8
98. 17-MRS-113-1 No ----

ISI 1-7

99. 17-MRS-113-2 Yes ---- ----

100. 17-MRS-114-1 No - ISI 1-3, 1-4 101. 17-MRS-114-2 Yes ISI 1-9 ISI 1-8 102. 17-MRS-114-7 Yes ISI 1-9,2-3,2-4 ISI 1-1 103, 17-MRS-114-7LD-1 No ISI 2-4 ISI 1-1 104. 17-MRS-114-7LD-2 No ISI 2-4 ISI 1-1 105. 796-1A No ----

Inaccessible i

106. 20-MRS-121-20 Yes Inaccessible 107. 796-1B No ---- Inaccessible 108. 20-MRS-122-20 Yes ---- Inaccessible 109, 24-MRS-121-1 Yes ISI 1-9,2-3,2-4 ISI 1-4 110. 24-MRS-122 Yes ISI 1-9,2-3,2-4 ISI 1-1 l

AT0987-0174-NLO2 L._

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