ML16134A070

Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule

ML16134A070
Person / Time
Site:	Millstone
Issue date:	05/09/2016
From:	Mark D. Sartain Dominion Nuclear Connecticut
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
16-199
Download: ML16134A070 (4)

Text

Dominion Nuclear Connecticut, Inc.

5000 Dominion Boulevard, Glen Allen, VA 23060 Web Address: www.dom.com May 9, 2016 U. S. Nuclear Regulatory Commission Serial No.: 16-199 Attention: Document Control Desk NRA/WDC: RO Washington, DC 20555-0001 Docket No.: 50-423 License No.: NPF-49 DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 3 REVISION TO REACTOR VESSEL SURVEILLANCE CAPSULE WITHDRAWAL SCHEDULE This letter is to confirm the subject information sent separately to the NRC in an email dated April 27, 2016 and discussed in a clarification call on April 28, 2016. The April 27, 2016 email is provided as an attachment to this letter.

If you should have any questions regarding this submittal, please contact Wanda Craft at (804) 273-4687.

Sincerely, Mark D. Sartain Vice President - Nuclear Engineering

Attachment:

Email dated April 27, 2016 Commitments contained in this letter: None

Serial No.16-199 Docket No. 50-423 Page 2 of 2 cc: U.S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd Suite 100 King of Prussia, PA 19406-2713 Richard V. Guzman NRC Senior Project Manager U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08 C2 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station

Serial No.16-199 Docket No. 50-423 ATTACHMENT EMAIL DATED APRIL 27, 2016 DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 3

Wanda D Craft (Generation - 6)

From: Wanda D Craft (Generation - 6)

Sent: Wednesday, April 27, 2016 4:08 PM To: Guzman, Richard

Subject:

MPS3 RV Surveillance Capsule Withdrawal Schedule revision Rich, In letters dated July 2, 2015 and January 28, 2016, DNC requested NRC review and approval of a revision to the surveillance capsule withdrawal schedule for MPS3. The NRC approved the revised withdrawal schedule in a letter dated March 15, 2016.

DNC planned to reinstall standby Capsule Y into the reactor vessel from the spent fuel pool during the spring 2016 refueling outage. Capsule Y was scheduled for reinsertion at the 241°location but could not be reinserted there due to the obstruction caused by the lift rig for the upper internals. This obstruction limited travel of the refuel bridge and therefore, restricted access to the 241° specimen guides. DNC proposes to revise the capsule withdrawal schedule for reinsertion of Capsule Y at the 61° location, which has the same lead factor as the 241° location. No other changes are proposed to the withdrawal schedule previously approved in.the March 15, 2016 NRC safety evaluation.

The proposed revision to the reactor vessel surveillance capsule withdrawal schedule is shown below.

Proposed revisions to the capsule withdrawal schedule are shown with additions in bold, italicized text and deletions are shown with strikethrough.

Proposed Millstone Unit 3 Reactor Vessel Surveillance Capsule Withdrawal Schedule REMOVAL/

LEAD FACTOR(al FLU ENCE CAPSULE LOCATION INSTALLATION (n/cm2,E>1.0MeV)(a)

TIME (EFPY)!bl u 58.5° 4.06 1.3 4.00 X 1018(c) x 238.5° 4.35 8.0 1.98 X 1019(c) w 121.5° 4.22 13.8 3.16 X 1019(c. d) y<e)\11 241° 3.98 13.8 P:eetRete ~i) y<tJ 61° 3.98 Footnote (i) v<e> 61° 3.98 Storage z<g> 301.5° 4.22 23.4 5.37x 10 19<hl

a. Updated m Capsule W dosimetry analysis.

b. Effective Full Power Years (EFPY) from plant startup.

c. Plant specific evaluation.

d. This fluence is not less than once or greater than twice the peak end of license fluence, and is approximately equal to the peak vessel fluence at 63 EFPY.

19

e. Capsules Y and V were withdrawn after 13.8 EFPY (EOC 10) and placed into storage after accruing 2.98 x 10 n/cm 2 fluence.

f. Capsule Y was reinserted into its original location ~61°1 at EOC 17 (approximately 23.4 EFPY~.

g. Capsule Z was withdrawn at 23.4 EFPY (EOC 17) after accruing approximately 5.37 x 10 19 n/cm fluence. Dosimetry analysis was performed and the test specimens placed into vendor storage for future testing.

h. This projected fluence is greater than once and less than twice the projected 72 EFPY and 90 EFPY peak vessel fluence.

i. Capsule Y is installed for fluence monitoring during the operating license in accordance with ASTM E 185-82.

Thanks for your review and we are looking forward to discussing this with you in a call tomorrow. We will need NRC approval of the revised capsule withdrawal schedule prior to entering Mode 2, which is currently expected to occur on May 91h. If you have any questions, please let me know. Thanks.

Wanda D. Craft Nuclear Licensing and Operations Support Dominion Resources Services, Inc 1

Dominion Nuclear Connecticut, Inc.

5000 Dominion Boulevard, Glen Allen, VA 23060 Web Address: www.dom.com May 9, 2016 U. S. Nuclear Regulatory Commission Serial No.: 16-199 Attention: Document Control Desk NRA/WDC: RO Washington, DC 20555-0001 Docket No.: 50-423 License No.: NPF-49 DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 3 REVISION TO REACTOR VESSEL SURVEILLANCE CAPSULE WITHDRAWAL SCHEDULE This letter is to confirm the subject information sent separately to the NRC in an email dated April 27, 2016 and discussed in a clarification call on April 28, 2016. The April 27, 2016 email is provided as an attachment to this letter.

If you should have any questions regarding this submittal, please contact Wanda Craft at (804) 273-4687.

Sincerely, Mark D. Sartain Vice President - Nuclear Engineering

Attachment:

Email dated April 27, 2016 Commitments contained in this letter: None

Serial No.16-199 Docket No. 50-423 Page 2 of 2 cc: U.S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd Suite 100 King of Prussia, PA 19406-2713 Richard V. Guzman NRC Senior Project Manager U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08 C2 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station

Serial No.16-199 Docket No. 50-423 ATTACHMENT EMAIL DATED APRIL 27, 2016 DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 3

Wanda D Craft (Generation - 6)

From: Wanda D Craft (Generation - 6)

Sent: Wednesday, April 27, 2016 4:08 PM To: Guzman, Richard

Subject:

MPS3 RV Surveillance Capsule Withdrawal Schedule revision Rich, In letters dated July 2, 2015 and January 28, 2016, DNC requested NRC review and approval of a revision to the surveillance capsule withdrawal schedule for MPS3. The NRC approved the revised withdrawal schedule in a letter dated March 15, 2016.

DNC planned to reinstall standby Capsule Y into the reactor vessel from the spent fuel pool during the spring 2016 refueling outage. Capsule Y was scheduled for reinsertion at the 241°location but could not be reinserted there due to the obstruction caused by the lift rig for the upper internals. This obstruction limited travel of the refuel bridge and therefore, restricted access to the 241° specimen guides. DNC proposes to revise the capsule withdrawal schedule for reinsertion of Capsule Y at the 61° location, which has the same lead factor as the 241° location. No other changes are proposed to the withdrawal schedule previously approved in.the March 15, 2016 NRC safety evaluation.

The proposed revision to the reactor vessel surveillance capsule withdrawal schedule is shown below.

Proposed revisions to the capsule withdrawal schedule are shown with additions in bold, italicized text and deletions are shown with strikethrough.

Proposed Millstone Unit 3 Reactor Vessel Surveillance Capsule Withdrawal Schedule REMOVAL/

LEAD FACTOR(al FLU ENCE CAPSULE LOCATION INSTALLATION (n/cm2,E>1.0MeV)(a)

TIME (EFPY)!bl u 58.5° 4.06 1.3 4.00 X 1018(c) x 238.5° 4.35 8.0 1.98 X 1019(c) w 121.5° 4.22 13.8 3.16 X 1019(c. d) y<e)\11 241° 3.98 13.8 P:eetRete ~i) y<tJ 61° 3.98 Footnote (i) v<e> 61° 3.98 Storage z<g> 301.5° 4.22 23.4 5.37x 10 19<hl

a. Updated m Capsule W dosimetry analysis.

b. Effective Full Power Years (EFPY) from plant startup.

c. Plant specific evaluation.

d. This fluence is not less than once or greater than twice the peak end of license fluence, and is approximately equal to the peak vessel fluence at 63 EFPY.

19

e. Capsules Y and V were withdrawn after 13.8 EFPY (EOC 10) and placed into storage after accruing 2.98 x 10 n/cm 2 fluence.

f. Capsule Y was reinserted into its original location ~61°1 at EOC 17 (approximately 23.4 EFPY~.

g. Capsule Z was withdrawn at 23.4 EFPY (EOC 17) after accruing approximately 5.37 x 10 19 n/cm fluence. Dosimetry analysis was performed and the test specimens placed into vendor storage for future testing.

h. This projected fluence is greater than once and less than twice the projected 72 EFPY and 90 EFPY peak vessel fluence.

i. Capsule Y is installed for fluence monitoring during the operating license in accordance with ASTM E 185-82.

Thanks for your review and we are looking forward to discussing this with you in a call tomorrow. We will need NRC approval of the revised capsule withdrawal schedule prior to entering Mode 2, which is currently expected to occur on May 91h. If you have any questions, please let me know. Thanks.

Wanda D. Craft Nuclear Licensing and Operations Support Dominion Resources Services, Inc 1