ML17341A803

Supplement to License Amendment Request for One Cycle Extension of Appendix J Type a Integrated Leakage Rate Test and Drywall Bypass Test Interval

ML17341A803
Person / Time
Site:	Grand Gulf
Issue date:	12/07/2017
From:	Larson E A Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
GNR0-2017 /00079
Download: ML17341A803 (5)

Text

• • *-=-Entergy GNR0-2017

/00079 December 7, 2017 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Entergy Operations, Inc. P.O. Box 756 Port Gibson, Mississippi 39150

• Eric L. Larson Site Vice President Grand Gulf Nuclear Station Tel: 601-437-7500

Subject:

Supplement to License Amendment Request for One Cycle Extension Of Appendix J Type A Integrated Leakage Rate Test and Drywall Bypass Test Interval Grand Gulf Nuclear Station, Unit No. 1 ... , Docket No. 50-416 License No. NPF-29

REFERENCE:

GNR0-2016/00062, License Amendment Request for One Cycle Extension Of Appendix J Type A Integrated Leakage Rate Test and Drywall Bypass Test Interval, dated December 29, 2016

Dear Sir or Madam:

This letter provides a supplemental change to the previously provided Technical Specification Markup, pages 3.6.53 and 5.0-16. Please replace the previously submitted pages with those provided in the attachment.

This letter contains no Regulatory Commitments.

If you have any questions or require add.itional information, please contact Robert Peters at 601-437-2318 or Douglas Neve, Manager Regulatory Assurance at (601)-437-2103.

Sincerely, Eric A. Larson Site Vice President EAL/saw

Attachment:

Revised (Clean) Technical Specification Pages G N R0-2017 /00079 Page 2 of 2 cc: NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150 U.S. Nuclear Regulatory Commission . I ATTN: Mr. Kriss Kennedy Region Administrator, Region IV 1600 East Lamar Blvd, Suite 400 Arlington, TX 76011-4005 Mr. John P. Boska, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 0-8-C2 Washington, DC 20555 Thomas J. Wengert U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Attachment to GNR02017-00079 Revised (CLEAN) Technical Specification Pages '----/

SURVEILLANCE REQUIREMENTS SR 3.6.5.1.1 GRAND GULF SURVEILLANCE Verify bypass leakage is less than or equal to the bypass leakage limit. However, during the first unit startup following drywell bypass leak rate testing performed in accordance with this SR, the acceptance criterion is leakage 5 10% of the bypass leakage limit. 3.6-53 Drywell 3.6.5.1 FREQUENCY 24 months following 2 consecutive tests with bypass leakage greater than the bypass leakage limit until 2 consecutive tests are less than or equal to the bypass leakage limit 48 months following a test with bypass leakage greater than the bypass leakage limit SR 3.0.2 is not applicable for extensions

>. 12 months. 120 months, except that the next drywell bypass leak rate test performed after the October 19, 2008 test shall be performed no later than the plant restart after the End of Cycle 22 Refueling Outage. ( continued)

Amendment No.~' __ _

Programs and Manuals 5. 5. 5.5 Programs and Manuals ( continued)

5. 5 .11 r 5.5.12 GRAND GULF Technical Specificatio~s (TS) Bases Control Program This program provides a means for processing changes to the Bases of these Technical Specifications.

a. Changes to the Bases of the TS shall be made under appropriate administrative controls and reviews. b. Licensees may make changes to Bases without prior NRC apptoval provided the changes do not require either,of the following:

1. A change in the TS incorporated in the license; or 2. A change to the updated FSAR or Bases that requires NRC approval pursuant to 10 CFR 50.59. c. The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the UFSAR. d. Proposed-changes that do not meet the criteria of either Specification 5 .. 5.11.b.l or Specification 5.5.11.b.2 above shall be ~eyie0ed and approved by the NRC prior to implementation.,:

Changes to the Bases implemented without prior NRC approval shall be provided to the NRC on a frequency consi~fent with 10 CFR 50.71(e).

10 CFR 5 0, Appendix -.~J, Testing Program This program establishes the leakage rate testing program of the containment as 'required by 10 CFR 50.54(0) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions.

This program shall be implemented in accordance with the Safety Evaluation issued by the Office of Nuclear Reactor Regulation dated April 26, 1995 (GNRI-95/00087) as modified by the Safety Evaluation issued fqr Amendment No. 135 to the Operating License, except that the next*. Type A test performed after the October 19, 2008 Type A test shall be performed no later than the plant restart after the Er:id of Cycle 22 Refueling Outage. For Type B and Type C local le~kage rate testing, this program shall be in accordanqe with the *guidelines contained in NEI 94-01, Revision 3-A, "Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50r .;.,,ppendix J," dated July 2012. Consistent with standard scheduling practices for Technical Specifications required surveillances, intervals for the recommended surveillance frequency for Type A testing may be extended by up to 25 percent of the test interval, not to exceed 15 months. The calculated peak containment internal pressure for the design basis loss of coolant accident, Pa, is 12.1 psig. _5.0-16 Amendment No. 9-§-, G-9-,