ML072130052

Revised License Pages of Facility Operating License No. NPF-90

ML072130052
Person / Time
Site:	Watts Bar
Issue date:	08/09/2007
From:	Moroney B T NRC/NRR/ADRO/DORL/LPLII-2
To:
Moroney B T, NRR/DORL, 415-3974
Shared Package
ML072200032	List: ML072130052 ML072200034
References
TAC MD4621
Download: ML072130052 (4)

Text

REVISED LICENSE PAGESFACILITY OPERATING LICENSE NO. NPF-90DOCKET NO. 50-390REMOVEINSERT 4 4 5 5

- - 5a Revised by letter dated August 9, 2007 4(5) Reactor Vessel Fracture Toughness TestingSupplemental fracture toughness testing (J-R) will be performed inaccordance with a testing procedure that has been previously reviewed and approved by the NRC staff on Surveillance Capsule W specimens (removed from Cycle 3 Refueling Outage) and Capsule X specimens (to be removed from Cycle 5 Refueling Outage). The supplemental test results will be included in the report to be submitted in accordance with 10 CFR 50, Appendix H requirements for each Capsule specimen and will include an evaluation of the effects on TVA's equivalent margins analysis which was submitted October 15, 1993 and approved by NRC in Supplemental Safety Evaluation Report (SSER) 14.(6)Mitigation Strategy License ConditionDevelop and maintain strategies for addressing large fires and explosionsand that include the following key areas:(a)Fire fighting response strategy with the following elements:1. Pre-defined coordinated fire response strategy and guidance

2. Assessment of mutual aid fire fighting assets

3. Designated staging areas for equipment and materials

4. Command and control

5. Training of response personnel(b) Operations to mitigate fuel damage considering the following:1. Protection and use of personnel assets

2. Communications

3. Minimizing fire spread

4. Procedures for implementing integrated fire response strategy

5. Identification of readily-available pre-staged equipment

6. Training on integrated fire response strategy

7. Spent fuel pool mitigation measures(c) Actions to minimize release to include consideration of:1. Water spray scrubbing

2. Dose to onsite responders(7)The licensee shall implement and maintain all Actions required byAttachment 2 to NRC Order EA-06-137, issued June 20, 2006, except the last action that requires incorporation of the strategies into the site security plan, contingency plan, emergency plan and/or guard training and qualification plan, as appropriate.D.The following exemptions are authorized by law, will not present an undue risk to the public health and safety, and are consistent with the common defense and security. Therefore, these exemptions are granted pursuant to 10 CFR 50.12.(1) Deleted Revised by letter dated August 9, 2007 5(2) The facility was previously granted an exemption from the criticalitymonitoring requirements of 10 CFR 70.24 (see Special Nuclear Material License No. SNM-1861 dated September 5, 1979). The technical justification is contained in Section 9.1 of Supplement 5 to the Safety Evaluation Report, and the staff's environmental assessment was published on April 18, 1985 (50 FR 15516). The facility is hereby exempted from the criticality alarm system provisions of 10 CFR 70.24 so far as this section applies to the storage of fuel assemblies held under this license.(3) The facility requires an exemption from 10 CFR 73.55(c)(10). Thejustification for this exemption is contained in Section 13.6.9 of Supplement 15 and 20 to the Safety Evaluation Report. The staff's environmental assessment was published on April 25, 1995 (60 FR 20291). Pursuant to 10 CFR 73.5, the facility is exempted from the stated implementation schedule of the surface vehicle bomb rule, and may implement the same as late as February 17, 1996. (4) The facility was previously granted an exemption from certainrequirements of 10 CFR 73.55(d)(5) relating to the returning of picture badges upon exit from the protected areas, such that individuals not employed by TVA who are authorized unescorted access into protected areas can take their badges offsite (see 59 FR 66061, December 22, 1994). The granting of this exemption is hereby affirmed.(5) The facility was previously granted an exemption from certainrequirements of 10 CFR 50, Appendix E, such that the State of Tennessee, which is within the ingestion exposure pathway emergency planning zone, need not participate in the November 1995 full-participation exercise (see 60 FR 54526, October 24, 1995). The granting of this exemption is hereby affirmed.E. TVA shall fully implement and maintain in effect all provisions of theCommission-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 50.54(p). The combined set of plans, which contains Safeguards Information protected under 10 CFR 73.21, is entitled: "Watts Bar Nuclear Plant Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 0," submitted by letter dated September 9, 2004, and supplemented on October 6, October 12, 2004, and October 22, 2004. F. TVA shall implement and maintain in effect all provisions of the approved fireprotection program as described in the Fire Protection Report for the facility, as approved in Supplements 18 and 19 of the SER (NUREG-0847) subject to the following provision:TVA may make changes to the approved fire protection programwithout prior approval of the Commission, only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

Revised by letter dated August 9, 2007 5aG. Except as otherwise provided in the Technical Specifications (Appendix A to thislicense) or Environmental Protection Plan (Appendix B to this license), TVA shall report any violations of the requirements contained in Section 2.C of this license in the following manner: initial notification shall be made within twenty-four (24) hours to the NRC Operations Center via the Emergency Notification System with written follow-up within 30 days in accordance with the procedures described in 10 CFR 50.73 (b), (c), and (e).H. The licensee shall have and maintain financial protection of such types and insuch amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.