GNRO-2011/00092, Supplemental Information Pertaining to Extended Power Uprate

Supplemental Information Pertaining to Extended Power Uprate

ML112980113
Person / Time
Site:	Grand Gulf
Issue date:	10/24/2011
From:	Krupa M Entergy Operations
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
GNRO-2011/00092
Download: ML112980113 (4)

Text

Entergy Operations, Inc.

P. O. Box 756 Port Gibson, MS 39150 Michael A. Krupa Director, Extended Power Uprate Grand Gulf Nuclear Station Tel. (601) 437-6694 GNRO-2011/00092 October 24, 2011 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

SUBJECT:

Supplemental Information Pertaining to Extended Power Uprate Grand Gulf Nuclear Station, Unit 1 Docket No. 50-416 License No. NPF-29

REFERENCE:

Entergy Operations, Inc. letter to the NRC (GNRO-2010/00056),

License Amendment Request - Extended Power Uprate, September 8, 2010 (ADAMS Accession No. ML102660403)

Dear Sir or Madam:

In the referenced letter, Entergy Operations, Inc. (Entergy) submitted to the NRC a license amendment request (LAR), which proposes to revise the Grand Gulf Nuclear Station (GGNS)

Operating License (OL) and Technical Specifications (TS) to increase the maximum reactor core power operating limit from 3898 megawatts thermal (MWt) to 4408 MWt.

Based on a telephone call with the NRC staff on October 18, 2011, Entergy is providing supplemental information to address a staff question pertaining to 10 CFR 50, Appendix J testing and bypass leakage testing. This information is provided in the attachment to this letter.

The No Significance Hazards Determination and the Environmental Consideration provided in Reference 1 are not impacted by this response.

This letter contains no new commitments.

If you have any questions or require additional information, please contact Mr. Guy Davant at (601) 368-5756.

GNRO-2011/00092 Page 2 of 2 I declare under penalty of perjury that the foregoing is true and correct; executed on October 24, 2011.

Sincerely, MAK/ghd

Attachment:

Supplemental Information Pertaining to Extended Power Uprate cc: Mr. Elmo E. Collins, Jr.

Regional Administrator, Region IV U. S. Nuclear Regulatory Commission 612 East Lamar Blvd., Suite 400 Arlington, TX 76011-4005 U. S. Nuclear Regulatory Commission ATTN: Mr. A. B. Wang, NRR/DORL (w/2)

ATTN: ADDRESSEE ONLY ATTN: Courier Delivery Only Mail Stop OWFN/8 B1 11555 Rockville Pike Rockville, MD 20852-2378 State Health Officer Mississippi Department of Health P. O. Box 1700 Jackson, MS 39215-1700 NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150

ATTACHMENT GRAND GULF NUCLEAR STATION GNRO-2011/00092 SUPPLEMENTAL INFORMATION PERTAINING TO EXTENDED POWER UPRATE

Attachment to GNRO-2011/00092 Page 1 of 1 SUPPLEMENTAL INFORMATION PERTAINING TO EXTENDED POWER UPRATE By application dated September 8, 2010, Entergy Operations, Inc. (Entergy) submitted to the NRC a license amendment request (LAR), which proposes to revise the Grand Gulf Nuclear Station (GGNS) Operating License (OL) and Technical Specifications (TS) to increase the maximum reactor core power operating limit from 3898 megawatts thermal (MWt) to 4408 MWt.

Based on a telephone call with the NRC staff on October 18, 2011, Entergy is providing supplemental information to address a staff question pertaining to 10 CFR 50, Appendix J testing and bypass leakage testing.

Request for Additional Information Provide: a) justification why it is appropriate to have the five Technical Specification Surveillance Requirements (3.6.1.1.1, 3.6.1.3.5, 3.6.1.3.9, 3.6.5.1.1 and 3.6.5.1.2) in a single license condition rather than separating them out by test purpose; and b) confirmation the new EPU bypass leakage effective area capability A/K limit of < 0.8 sq. ft. will be met upon implementation.

Response

a) Three of the surveillance requirements (SRs) relate to Appendix J containment leakage testing requirements (3.6.1.1.1, 3.6.1.3.5 and 3.6.1.3.9). Two of the SRs implement drywell bypass leakage testing and examination requirements (3.6.5.1.1 and 3.6.5.1.2).

SR 3.6.1.1.1 is for the containment integrated leakage rate test (App J Type A test); this test is typically performed every ten years (120 months) and involves the use of large air compressors to support the pressurization of the building. Similarly, the drywell bypass leakage test of SR 3.6.5.1.1 is typically performed every 120 months and also involves the use of large compressors. The frequency of the visual examination requirement of SR 3.6.5.1.2 is clearly tied to the performance of the Appendix J Type A test of SR 3.6.1.1.1.

Entergy believes this scheduling relationship among the SRs justifies maintaining a single license condition rather than splitting it into forming two conditions. Therefore, Entergy requests the proposed license condition be retained as written.

b) As stated above, the drywell bypass leakage test specified in SR 3.6.5.1.1 is performed once every 120 months. The Technical Specification imposes an acceptance criterion of 10% of the bypass leakage limit. The most recent test was completed on October 20, 2008. The result from that test indicated an actual A/K value of 0.019 sq. ft. This result meets the new A/K criterion of 0.8 sq. ft. with ample margin. Therefore, Entergy confirms the EPU bypass leakage effective area capability A/K limit is met at implementation of the EPU and can be next performed at its established frequency.