NL-15-010, Response to Request for Additional Information Regarding Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule Indian Point Nuclear Generating Unit Number 3: Difference between revisions
StriderTol (talk | contribs) Created page by program invented by StriderTol |
StriderTol (talk | contribs) StriderTol Bot change |
||
| Line 18: | Line 18: | ||
=Text= | =Text= | ||
{{#Wiki_filter:Enterciv Nuclear Northeast Indian Point Energy Center 450 Broadway, GSB | {{#Wiki_filter:wEntergy Enterciv Nuclear Northeast Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 Tel (914) 254-6700 Lawrence Coyle Site Vice President NL-15-010 January 26, 2015 U.S. Nuclear Regulatory Commission Document Control Desk 11545 Rockville Pike, TWFN-2 F1 Rockville, MD 20852-2738 | ||
==SUBJECT:== | ==SUBJECT:== | ||
==REFERENCES:== | |||
1. | |||
Response to Request for Additional Information Regarding Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule Indian Point Nuclear Generating Unit Number 3 (TAC No. MF5148) | Response to Request for Additional Information Regarding Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule Indian Point Nuclear Generating Unit Number 3 (TAC No. MF5148) | ||
Docket No. 50-286 License No. DPR-64 | Docket No. 50-286 License No. DPR-64 NRC Letter to Entergy Regarding Request for Additional Information Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule (TAC No. MF5148), Dated January 14, 2015 | ||
: 2. | |||
Entergy Letter (NL-14-129) to NRC Regarding Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule Per 10 CFR 50 Appendix H, dated November 5, 2014 | |||
: 2. Entergy Letter (NL-14-129) to NRC Regarding Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule Per 10 CFR 50 Appendix H, dated November 5, 2014 | |||
==Dear Sir or Madam:== | ==Dear Sir or Madam:== | ||
The Nuclear Regulatory Commission (NRC) requested additional information (Reference 1) regarding the Entergy Nuclear Operations Inc. (Entergy) request for a change to the Reactor Vessel surveillance capsule withdrawal schedule (Reference 2). The response to the requested information is attached. | The Nuclear Regulatory Commission (NRC) requested additional information (Reference 1) regarding the Entergy Nuclear Operations Inc. (Entergy) request for a change to the Reactor Vessel surveillance capsule withdrawal schedule (Reference 2). The response to the requested information is attached. | ||
There are no new commitments in this letter. | There are no new commitments in this letter. | ||
| Line 35: | Line 34: | ||
NL-15-010 Docket No. 50-286 Page 2 of 2 1d~clare under penalty of perjury that the foregoing is true and correct. Executed on January | NL-15-010 Docket No. 50-286 Page 2 of 2 1d~clare under penalty of perjury that the foregoing is true and correct. Executed on January | ||
.. =L(=, 2015 Sincerely, | .. =L(=, | ||
2015 Sincerely, | |||
==Attachment:== | ==Attachment:== | ||
Response to Request for Additional Information Regarding Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule cc: | Response to Request for Additional Information Regarding Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule cc: | ||
Mr. Douglas Pickett, Senior Project Manager, NRC NRR DORL Mr. Daniel H. Dorman, Regional Administrator, NRC Region 1 NRC Resident Inspector Mr. John B. Rhodes, President and CEO, NYSERDA w/o Enclosure 2 Ms. Bridget Frymire, New York State Dept. of Public Service w/o Enclosure 2 | |||
ATTACHMENT TO NL-15-010 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED REVISION TO REACTOR VESSEL SURVEILLANCE CAPSULE WITHDRAWAL SCHEDULE ENTERGY NUCLEAR OPERATIONS, INC. | ATTACHMENT TO NL-15-010 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED REVISION TO REACTOR VESSEL SURVEILLANCE CAPSULE WITHDRAWAL SCHEDULE ENTERGY NUCLEAR OPERATIONS, INC. | ||
INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 DOCKET NO. 50-286 | INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 DOCKET NO. 50-286 | ||
NL-15-010 Docket No. 50-286 | NL-15-010 Docket No. 50-286 Page 1 of 2 REQUEST FOR ADDITIONAL INFORMATION PROPOSED REVISION TO REACTOR VESSEL SURVEILLANCE CAPSULE WITHDRAWAL SCHEDULE By {{letter dated|date=November 5, 2014|text=letter dated November 5, 2014}} (Accession No. ML14323A729), Entergy Nuclear Operations, Inc. (Entergy, the licensee) requested approval from the Nuclear Regulatory Commission (NRC) regarding a revision to the reactor vessel surveillance capsule withdrawal schedule pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix H, Section III.B.3. | ||
The NRC staff has reviewed the proposal and determined that additional information is needed. | The NRC staff has reviewed the proposal and determined that additional information is needed. | ||
The NRC staff, Vessels and Internals Integrity Branch (EVIB), requested a response to the following request for additional information. | The NRC staff, Vessels and Internals Integrity Branch (EVIB), requested a response to the following request for additional information. | ||
BACKGROUND 10 CFR Part 50, Appendix H, states that the purpose of the material surveillance program is to monitor changes in the fracture toughness properties of ferritic materials in the reactor vessel beltline region of light water nuclear power reactors which result from exposure of these materials to neutron irradiation and thermal environment. Under the program, fracture toughness test data are obtained from material specimens exposed in surveillance capsules, which are withdrawn periodically from the reactor vessel. | BACKGROUND 10 CFR Part 50, Appendix H, states that the purpose of the material surveillance program is to monitor changes in the fracture toughness properties of ferritic materials in the reactor vessel beltline region of light water nuclear power reactors which result from exposure of these materials to neutron irradiation and thermal environment. Under the program, fracture toughness test data are obtained from material specimens exposed in surveillance capsules, which are withdrawn periodically from the reactor vessel. | ||
ISSUE Out of the capsules that have been removed and tested, capsule Z had the highest fluence value at 1.04 x 1019 n/cm 2 with a lead factor of 3.48. The most recent capsule tested, which was removed in 2003, had a capsule fluence of 8.74 x 1018 n/cm 2 with a lead factor of 1.49. The proposed schedule would postpone the withdrawal and testing of the next capsule until refueling outage 23 (currently scheduled for March 2025) which would have a capsule fluence of approximately 1.85 x 1019 n/ | ISSUE Out of the capsules that have been removed and tested, capsule Z had the highest fluence value at 1.04 x 1019 n/cm 2 with a lead factor of 3.48. The most recent capsule tested, which was removed in 2003, had a capsule fluence of 8.74 x 1018 n/cm 2 with a lead factor of 1.49. The proposed schedule would postpone the withdrawal and testing of the next capsule until refueling outage 23 (currently scheduled for March 2025) which would have a capsule fluence of approximately 1.85 x 1019 n/cm2 with a lead factor of 1.52. This fluence would correspond to a reactor vessel peak fluence of 1.22 x 1019 n/cm 2. | ||
REQUEST Estimate when the vessel peak fluence is expected to exceed the fluence of capsule Z. Further, describe how the fluence of the reactor vessel beltline materials will be monitored once the reactor vessel peak fluence surpasses that of capsule Z. | REQUEST Estimate when the vessel peak fluence is expected to exceed the fluence of capsule Z. Further, describe how the fluence of the reactor vessel beltline materials will be monitored once the reactor vessel peak fluence surpasses that of capsule Z. | ||
| Line 53: | Line 54: | ||
Based on current core burnup estimates and the most recent fluence evaluation, Entergy estimates that the peak vessel clad/base metal interface will be subjected to a neutron fluence of approximately 1.04 x 1019 n/cm 2 (i.e. Capsule Z equivalent neutron fluence) at approximately 31 Effective Full Power Years (EFPY). Indian Point 3 is currently projected to reach 31 EFPY approximately in October 2019. | Based on current core burnup estimates and the most recent fluence evaluation, Entergy estimates that the peak vessel clad/base metal interface will be subjected to a neutron fluence of approximately 1.04 x 1019 n/cm 2 (i.e. Capsule Z equivalent neutron fluence) at approximately 31 Effective Full Power Years (EFPY). Indian Point 3 is currently projected to reach 31 EFPY approximately in October 2019. | ||
NL-15-010 Docket No. 50-286 Page 2 of 2 After the peak vessel fluence exceeds the fluence of Capsule Z, it will be monitored in accordance with the requirements of 10CFR50 Appendix H. Appendix H requires that a surveillance capsule withdrawal schedule be established based on the requirements of paragraph 7.6.2 and Table 1 from ASTM E-185-82. The Indian Point 3 surveillance capsule withdrawal schedule proposed in the November 5, 2014 letter implements the requirements of ASTM E-185-82 for a 60 calendar year (48 EFPY) operating term. It should also be noted that although the peak vessel clad/base metal fluence is expected to exceed the fluence of Capsule Z prior to the withdrawal of the next surveillance capsule, the 1/4 thickness (i.e. the location used to establish the normal operating heatup and cooldown limits) fluence is not expected to exceed the Capsule Z fluence prior to the end of the period of extended operation (60 calendar year).}} | NL-15-010 Docket No. 50-286 Page 2 of 2 After the peak vessel fluence exceeds the fluence of Capsule Z, it will be monitored in accordance with the requirements of 10CFR50 Appendix H. Appendix H requires that a surveillance capsule withdrawal schedule be established based on the requirements of paragraph 7.6.2 and Table 1 from ASTM E-185-82. The Indian Point 3 surveillance capsule withdrawal schedule proposed in the {{letter dated|date=November 5, 2014|text=November 5, 2014 letter}} implements the requirements of ASTM E-185-82 for a 60 calendar year (48 EFPY) operating term. It should also be noted that although the peak vessel clad/base metal fluence is expected to exceed the fluence of Capsule Z prior to the withdrawal of the next surveillance capsule, the 1/4 thickness (i.e. the location used to establish the normal operating heatup and cooldown limits) fluence is not expected to exceed the Capsule Z fluence prior to the end of the period of extended operation (60 calendar year).}} | ||
Latest revision as of 14:39, 10 January 2025
| ML15034A507 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 01/26/2015 |
| From: | Coyle L Entergy Nuclear Northeast, Entergy Nuclear Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NL-15-010, TAC MF5148 | |
| Download: ML15034A507 (5) | |
Text
wEntergy Enterciv Nuclear Northeast Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 Tel (914) 254-6700 Lawrence Coyle Site Vice President NL-15-010 January 26, 2015 U.S. Nuclear Regulatory Commission Document Control Desk 11545 Rockville Pike, TWFN-2 F1 Rockville, MD 20852-2738
SUBJECT:
REFERENCES:
1.
Response to Request for Additional Information Regarding Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule Indian Point Nuclear Generating Unit Number 3 (TAC No. MF5148)
Docket No. 50-286 License No. DPR-64 NRC Letter to Entergy Regarding Request for Additional Information Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule (TAC No. MF5148), Dated January 14, 2015
- 2.
Entergy Letter (NL-14-129) to NRC Regarding Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule Per 10 CFR 50 Appendix H, dated November 5, 2014
Dear Sir or Madam:
The Nuclear Regulatory Commission (NRC) requested additional information (Reference 1) regarding the Entergy Nuclear Operations Inc. (Entergy) request for a change to the Reactor Vessel surveillance capsule withdrawal schedule (Reference 2). The response to the requested information is attached.
There are no new commitments in this letter.
If you have any questions, or require additional information, please contact Mr. Robert Walpole, Regulatory Assurance Manager, at [914] 254-6710.
NL-15-010 Docket No. 50-286 Page 2 of 2 1d~clare under penalty of perjury that the foregoing is true and correct. Executed on January
.. =L(=,
2015 Sincerely,
Attachment:
Response to Request for Additional Information Regarding Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule cc:
Mr. Douglas Pickett, Senior Project Manager, NRC NRR DORL Mr. Daniel H. Dorman, Regional Administrator, NRC Region 1 NRC Resident Inspector Mr. John B. Rhodes, President and CEO, NYSERDA w/o Enclosure 2 Ms. Bridget Frymire, New York State Dept. of Public Service w/o Enclosure 2
ATTACHMENT TO NL-15-010 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED REVISION TO REACTOR VESSEL SURVEILLANCE CAPSULE WITHDRAWAL SCHEDULE ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 DOCKET NO. 50-286
NL-15-010 Docket No. 50-286 Page 1 of 2 REQUEST FOR ADDITIONAL INFORMATION PROPOSED REVISION TO REACTOR VESSEL SURVEILLANCE CAPSULE WITHDRAWAL SCHEDULE By letter dated November 5, 2014 (Accession No. ML14323A729), Entergy Nuclear Operations, Inc. (Entergy, the licensee) requested approval from the Nuclear Regulatory Commission (NRC) regarding a revision to the reactor vessel surveillance capsule withdrawal schedule pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix H,Section III.B.3.
The NRC staff has reviewed the proposal and determined that additional information is needed.
The NRC staff, Vessels and Internals Integrity Branch (EVIB), requested a response to the following request for additional information.
BACKGROUND 10 CFR Part 50, Appendix H, states that the purpose of the material surveillance program is to monitor changes in the fracture toughness properties of ferritic materials in the reactor vessel beltline region of light water nuclear power reactors which result from exposure of these materials to neutron irradiation and thermal environment. Under the program, fracture toughness test data are obtained from material specimens exposed in surveillance capsules, which are withdrawn periodically from the reactor vessel.
ISSUE Out of the capsules that have been removed and tested, capsule Z had the highest fluence value at 1.04 x 1019 n/cm 2 with a lead factor of 3.48. The most recent capsule tested, which was removed in 2003, had a capsule fluence of 8.74 x 1018 n/cm 2 with a lead factor of 1.49. The proposed schedule would postpone the withdrawal and testing of the next capsule until refueling outage 23 (currently scheduled for March 2025) which would have a capsule fluence of approximately 1.85 x 1019 n/cm2 with a lead factor of 1.52. This fluence would correspond to a reactor vessel peak fluence of 1.22 x 1019 n/cm 2.
REQUEST Estimate when the vessel peak fluence is expected to exceed the fluence of capsule Z. Further, describe how the fluence of the reactor vessel beltline materials will be monitored once the reactor vessel peak fluence surpasses that of capsule Z.
RESPONSE
Based on current core burnup estimates and the most recent fluence evaluation, Entergy estimates that the peak vessel clad/base metal interface will be subjected to a neutron fluence of approximately 1.04 x 1019 n/cm 2 (i.e. Capsule Z equivalent neutron fluence) at approximately 31 Effective Full Power Years (EFPY). Indian Point 3 is currently projected to reach 31 EFPY approximately in October 2019.
NL-15-010 Docket No. 50-286 Page 2 of 2 After the peak vessel fluence exceeds the fluence of Capsule Z, it will be monitored in accordance with the requirements of 10CFR50 Appendix H. Appendix H requires that a surveillance capsule withdrawal schedule be established based on the requirements of paragraph 7.6.2 and Table 1 from ASTM E-185-82. The Indian Point 3 surveillance capsule withdrawal schedule proposed in the November 5, 2014 letter implements the requirements of ASTM E-185-82 for a 60 calendar year (48 EFPY) operating term. It should also be noted that although the peak vessel clad/base metal fluence is expected to exceed the fluence of Capsule Z prior to the withdrawal of the next surveillance capsule, the 1/4 thickness (i.e. the location used to establish the normal operating heatup and cooldown limits) fluence is not expected to exceed the Capsule Z fluence prior to the end of the period of extended operation (60 calendar year).