ML083010065

Correction to Amendment No. 70 Regarding Control Room Envelope Habitability

ML083010065
Person / Time
Site:	Watts Bar
Issue date:	10/28/2008
From:	John Lamb Watts Bar Special Projects Branch
To:	Campbell W Tennessee Valley Authority
Lamb John G./NRR/DORL, 415-3100
References
TAC MD7474
Download: ML083010065 (9)

Text

October 28, 2008 Mr. William R. Campbell, Jr.

Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801

SUBJECT:

WATTS BAR NUCLEAR PLANT, UNIT 1 C CORRECTION TO AMENDMENT NO. 70 REGARDING CONTROL ROOM ENVELOPE HABITABILITY (TAC NO. MD7474)

Dear Mr. Campbell:

The U.S. Nuclear Regulatory Commission (NRC) issued the Amendment No. 70 to Facility Operating License No. NPF-90 for Watts Bar Nuclear Plant, Unit 1 on October 8, 2008 (Agencywide Document Access and Management System Accession No. ML082730231). This amendment was in response to your application dated October 26, 2007 (ML073380948).

Amendment No. 70 revised the Technical Specifications (TS) to adopt TS Task Force (TSTF)

Change Traveler TSTF-448, Revision 3, Control Room Envelope Habitability.

Subsequent to issuance, it was discovered that pages 4 and 4a of the License, which contain license conditions, were inadvertently omitted. Enclosed are the corrected pages containing the license condition for Amendment No. 70. Please replace the authorization pages and insert the license pages in Amendment No. 70 issued on October 8, 2008. This corrects an administrative error and does not affect the technical content of Amendment No. 70 and its associated safety evaluation.

We regret any inconvenience this may have caused. If you have any questions, please contact me at (301) 415-3100.

Sincerely,

/RA/

John G. Lamb, Senior Project Manager Watts Bar Special Projects Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-390

Enclosure:

License pages 4 and 4a cc w/enclosure: See next page

ML083010065 OFFICE LPWB/PM LPWB/LA LPWB/BC NAME JLamb BClayton LRagahavan DATE 10 / 28 / 08 10 / 28 /08 10 / 28 /08 William R. Campbell, Jr.

Tennessee Valley Authority WATTS BAR NUCLEAR PLANT cc:

Mr. Gordon P. Arent Site Vice President New Generation Licensing Manager Watts Bar Nuclear Plant Tennessee Valley Authority Tennessee Valley Authority 5A Lookout Place P. O. Box 2000 1101 Market Street Spring City, TN 37381 Chattanooga, TN 37402-2801 Mr. Michael A. Purcell Mr. Ashok S. Bhatnagar Senior Licensing Manager Senior Vice President Nuclear Power Group Nuclear Generation Development Tennessee Valley Authority and Construction 4X Blue Ridge Tennessee Valley Authority 1101 Market Street 6A Lookout Place Chattanooga, TN 37402-2801 1101 Market Street Chattanooga, TN 37402-2801 Ms. Beth A. Wetzel, Manager Corporate Nuclear Licensing and Vice President Industry Affairs Nuclear Support Tennessee Valley Authority Tennessee Valley Authority 4X Blue Ridge 3R Lookout Place 1101 Market Street 1101 Market Street Chattanooga, TN 37402-2801 Chattanooga, TN 37402-2801 Mr. Masoud Bajestani, Vice President Mr. H. Rick Rogers Watts Bar Unit 2 Vice President Watts Bar Nuclear Plant Nuclear Engineering & Technical Services Tennessee Valley Authority Tennessee Valley Authority P.O. Box 2000 3R Lookout Place Spring City, TN 37381 1101 Market Street Chattanooga, TN 37402-2801 Mr. Michael K. Brandon, Manager Licensing and Industry Affairs General Counsel Watts Bar Nuclear Plant Tennessee Valley Authority Tennessee Valley Authority 6A West Tower P.O. Box 2000 400 West Summit Hill Drive Spring City, TN 37381 Knoxville, TN 37902 Mr. Michael J. Lorek, Plant Manager Mr. John C. Fornicola, Manager Watts Bar Nuclear Plant Nuclear Assurance Tennessee Valley Authority Tennessee Valley Authority P.O. Box 2000 3R Lookout Place Spring City, TN 37381 1101 Market Street Chattanooga, TN 37402-2801 Senior Resident Inspector Watts Bar Nuclear Plant Mr. Larry E. Nicholson, General Manager U.S. Nuclear Regulatory Commission Performance Improvement 1260 Nuclear Plant Road Tennessee Valley Authority Spring City, TN 37381 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Mr. Michael D. Skaggs

County Executive 375 Church Street Suite 215 Dayton, TN 37321 County Mayor P. O. Box 156 Decatur, TN 37322 Mr. Lawrence E. Nanney, Director Division of Radiological Health Dept. of Environment & Conservation Third Floor, L and C Annex 401 Church Street Nashville, TN 37243-1532

TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-390 WATTS BAR NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 70 License No. NPF-90

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Tennessee Valley Authority (the licensee) dated October 26, 2007, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2

2. Accordingly, the license is amended by changes to the Operating License and Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-90 is hereby amended to read as follows:

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 70, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. TVA shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3. This license amendment is effective as of the date of its issuance, and shall be implemented no later than 60 days from the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/

L. Raghavan, Chief Watts Bar Special Projects Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Operating License and Technical Specifications Date of Issuance: October 8, 2008

CORRECTION TO AMENDMENT NO. 70 FACILITY OPERATING LICENSE NO. NPF-90 DOCKET NO. 50-390 Replace Page 4 of Operating License NPF-90 with the attached Page 4.

Insert Page 4a of Operating License NPF-90 with the attached Page 4a.

The revised pages are identified by the captioned amendment number and contain marginal lines indicating the areas of change.

(5) Reactor Vessel Fracture Toughness Testing Supplemental fracture toughness testing (J-R) will be performed in accordance 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 Condition Develop and maintain strategies for addressing large fires and explosions and 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 by Attachment 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.

Amendment No. 70

- 4a -

(8) Upon implementation of Amendment No. 70 adopting TSTF-448, Revision 3, the determination of control room envelope (CRE) unfiltered air inleakage as required by SR 3.7.10.4, in accordance with TS .7.2.20.c.(i), the assessment of CRE habitability as required by Specification 5.7.2.20.c.(ii), and the measurement of CRE pressure as required by Specification 5.7.2.20.d, shall be considered met following implementation:

(a) The first performance of SR 3.7.10.4, in accordance with Specification 5.7.2.20.c.(i), shall be within the specified Frequency of 6 years, plus the 18-month allowance of SR 3.0.2, as measured from April 5, 2004, the date of the most recent successful tracer gas test, as stated in the August 4, 2004, letter response to Generic Letter 2003-01, or within the next 18 months if the time period since the most recent successful tracer gas test is greater than 6 years.

(b) The first performance of the periodic assessment of CRE habitability, Specification 5.7.2.20.c.(ii), shall be within 3 years, plus the 9-month allowance of SR 3.0.2, as measured from April 5, 2004, the date of the most recent successful tracer gas test, as stated in the August 4, 2004 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 measurement of CRE pressure, Specification 5.7.2.20.d, shall be within 18 months, plus the 138 days allowed by SR 3.0.2, as measured from May 10, 2007, the date of the most recent successful pressure measurement test, or within 138 days if not performed previously.

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 Amendment No. 70