ML113320423

Correction of Facility Operating License Page in Amendment No. 186 Issued 7/27/2011 Revise License Condition and Approval of Cyber Security Plan and Associated Implementation Schedule

ML113320423
Person / Time
Site:	Grand Gulf
Issue date:	12/05/2011
From:	Wang A Plant Licensing Branch IV
To:	Entergy Operations
Wang, A B, NRR/DORL/LPLIV, 415-1445
References
TAC ME4379
Download: ML113320423 (5)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 5, 2011 Vice President, Operations Entergy Operations, Inc.

Grand Gulf Nuclear Station P.O. Box 756 Port Gibson, MS 39150

SUBJECT:

GRAND GULF NUCLEAR STATION, UNIT 1 - CORRECTION OF FACILITY OPERATING LICENSE PAGE IN AMENDMENT NO. 186 (TAC NO. ME4379)

Dear Sir or Madam:

By letter dated July 27, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML111940165), the U.S. Nuclear Regulatory Commission (NRC) staff issued Amendment No. 186 to Facility Operating License (FOL) No. NPF-29 for the Grand Gulf Nuclear Station, Unit 1 (GGNS). The amendment was in response to your license amendment request dated July 22, 2010 (ADAMS Accession No. ML102070558), as supplemented by letters dated September 23 and November 30, 2010, and February 15 and April 4, 2011 (ADAMS Accession Nos. ML102670030, ML103350161, ML11158A071, and ML11103A042, respectively), in which Entergy Operations, Inc. (the licensee) requested approval of the Cyber Security Plan (CSP) and Implementation Schedule for the GGNS, as required by Section 73.54, "Protection of Digital Computer and Communication Systems and Networks," of Title 10 of the Code of Federal Regulations.

On November 28, 2011, the licensee notified the NRC staff of an error in FOL page 16a issued by Amendment No. 186. Specifically, FOL page 16a was issued with the footer incorrectly marked. The error was introduced inadvertently by the NRC staff during its processing of the amendment. Thus, according to the NRC's policy established by SECY-96-238 (ADAMS Legacy Library Accession No. 9611250030), this error can be corrected by a letter. Enclosed please find the replacement FOL page 16a.

- 2 This error, on the part of the NRC, was administrative in nature and does not change any of the NRC staff's conclusions in the safety evaluation associated with the amendment. We apologize for any inconvenience caused by this error.

Sincerely, Olcu/L ~)alv(~

Alan B. Wang, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-416

Enclosure:

As stated cc w/encl: Distribution via Listserv

ENCLOSURE REPLACEMENT FACILITY OPERATING LICENSE NO. NPF-29 PAGE 16A GRAND GULF NUCLEAR STATION, UNIT 1 DOCKET NO. 50-416

(b) The first performance of the periodic assessment of CRE habitability, Specification 5.5.13.c.(ii), shall be within 3 years, plus the 9-month allowance of SR 3.0.2, as measured from March 2005, the date of the most recent successful tracer gas test, as stated in the June 30, 2005 letter response to Generic Letter 2003-01, or within the next 9 months if the time period since the most recent successful tracer gas test is greater than 3 years.

(c) The first performance of the periodic assessment of the CRE boundary, Specification 5.5.13.d, shall be within the next 18 months, plus the 136 days allowed by SR 3.0.2, as measured from the date of issuance of this amendment.

D. The facility required exemptions from certain requirements of Appendices A and J to 10 CFR Part 50 and from certain requirements of 10 CFR Part 100. These include: (a) exemption from General Design Criterion 17 of Appendix A until startup following the first refueling outage, for (1) the emergency override of the test mode for the Division 3 diesel engine, (2) the second level undervoltage protection for the Division 3 diesel engine, and (3) the generator ground over current trip function for the Division 1 and 2 diesel generators (Section 8.3.1 of SSER #7) and (b) exemption from the requirements of Paragraph III.D.2(b)(ii) of Appendix J for the containment airlock testing following normal door opening when containment integrity is not required (Section 6.2.6 of SSER #7). These exemptions are authorized by law and will not endanger life or property or the common defense and security and are otherwise in the public interest. In addition, by exemption dated December 20, 1986, the Commission exempted licensees from 10 CFR 100.I1(a)(l), insofar as it incorporates the definition of exclusion area in 10 CFR 100.3(a), until April 30, 1987 regarding demonstration of authority to control all activities within the exclusion area (safety evaluation accompanying Amendment No. 27 to License (NPF-29). This exemption is authorized by law, and will not present an undue risk to the public health and safety, and is consistent with the common defense and security. In addition, special circumstances have been found justifying the exemption.

Therefore, these exemptions are hereby granted pursuant to 10 CFR 50.12.

with the granting of these exemptions, the facility will operate, to the extent authorized herein, in conformity with the application, as amended, the provisions of the Act and the rules and regulations of the Commission.

E. The licensee shall fully implement and maintain in effect all provision of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: "Physical Security, Safeguards Contingency and Training and Qualification Plan," and were submitted to the NRC on May 18, 2006.

The licensee shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The licensee's CSP was approved by License Amendment No. 186.

16a Amendment No. +/-7G, ~ 186 Revised ~y Letter dated J~ly 18, 2007

-2 This error, on the part of the NRC, was administrative in nature and does not change any of the NRC staff's conclusions in the safety evaluation associated with the amendment. We apologize for any inconvenience caused by this error.

Sincerely.

IRA!

Alan B. Wang, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-416

Enclosure:

As stated cc w/encl: Distribution via Listserv DISTRIBUTION:

PUBLIC LPLIV r/f RecordsAmend Resource RidsAcrsAcnw_MailCTR Resource RidsNrrDorlLpl4 Resource RidsNrrLAJBurkhardt Resource RidsNrrPMGrandGulf Resource RidsOgcRp Resource RidsRgn4MailCenter Resource ADAMS Accession No ML113320423 OFFICE NRR/LPL4/PM NRR/LPL4/LA N RRlLPL4/BC NRRlLPL4/PM NAME ABWang JBurkhardt MMarkley ABWang DATE 12/5/11 1211111 1215/11 12/5/11 OFFICIAL AGENCY RECORD