ML091320179
| ML091320179 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 07/21/2009 |
| From: | John Lamb Watts Bar Special Projects Branch |
| To: | Swafford P Tennessee Valley Authority |
| Lamb J, 415-1727 | |
| References | |
| TAC ME1192 | |
| Download: ML091320179 (10) | |
Text
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~O July 21, 2009 Mr. Preston D. Swafford Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 SUB..IECT:
WATTS BAR NUCLEAR PLANT, UNIT 1 - ISSUANCE OF AMENDMENT REGARDING THE APPLICATION FOR TECHNICAL SPECIFICATION (TS)
CHANGE TO CORRECT MINOR ERROR IN AMENDMENT 70 (TAC NO.
ME1192)
Dear Mr. Swafford:
The Commission has issued the enclosed Amendment No. 78 to Facility Operating License No. NPF-90 for Watts Bar Nuclear Plant, Unit 1. This amendment is in response to your application dated April 30, 2009.
The amendment revises Technical Specification (TS) 5.7, "Procedures, Programs, and Manuals," to correct a typographical error in the TS section from 5.2.7.20 to 5.7.2.20.
A copy of the safety evaluation is also enclosed. Notice of issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely, G. Lamb, Seni roject Manager ts Bar Special Projects Branch ision of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-390
Enclosures:
- 1. Amendment No. 78 to NPF-90
- 2. Safety Evaluation cc w/enclosures: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-390 WATTS BAR NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 78 License No. NPF-90
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Tennessee Valley Authority (the licensee) dated April 30, 2009, 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 Title 10 Code of Federal Regulations (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 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. 78 and the Environmental Protection Plan contained I
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 30 days from the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
~efL Watts Bar Special Projects Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to License and Technical Specifications Date of Issuance: July 21, 2009
ATTACHMENT TO LICENSE AMENDMENT NO.78 FACILITY OPERATING LICENSE NO. NPF-90 DOCKET NO. 50-390 Replace page 3 of Operating License No. NPF-90 with the attached page 3.
Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT 5.0-25 5.0-25 5.0-25a 5.0-25a
- 3 (4)
TVA, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required, any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis, instrument calibration, or other activity associated with radioactive apparatus or components; and (5)
TVA, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C.
This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect, and is sUbject to the additional conditions specified or incorporated below.
(1)
Maximum Power Level TVA is authorized to operate the facility at reactor core power levels not in excess of 3459 megawatts thermal.
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 78
,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)
Safety Parameter Display System (SPDS) (Section 18.2 of SER Supplements 5 and 15)
Prior to startup following the first refueling outage, TVA shall accomplish the necessary activities, provide acceptable responses, and implement all proposed corrective actions related to having the Watts Bar Unit 1 SPDS operational.
(4)
Vehicle Bomb Control Program (Section 13.6.9 of SSER 20)
During the period of the exemption granted in paragraph 2.D.(3) of this license, in implementing the power ascension phase of the approved initial test program, TVA shall not exceed 50% power until the requirements of 10 CFR 73.55(c)(7) and (8) are fully implemented. TVA shall submit a letter under oath or affirmation when the requirements of 73.55(c)(7) and (8) have been fully implemented.
Amendment No. 78
Procedures, Programs, and Manuals 5.7 5.7 Procedures, Programs, and Manuals 5.7.2.19 Containment Leakage Rate Testing Program (continued)
Leakage rate acceptance criteria are:
- a.
Containment overall leakage rate acceptance criterion is ~ 1.0 La. Durin9 the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are < 0.60 La for the combined Type B and Type C tests, and
~ 0.75 La for Type A tests.
- b.
Air lock testing acceptance criteria are:
- 1)
Overall air lock leakage rate is ~ 0.05 La when tested at ~ Pa.
- 2)
For each door, leakage rate is ~ 0.01 La when pressurized to ~ 6 psig.
The provisions of SR 3.0.2 do not apply to the test frequencies specified in the Containment Leakage Rate Testing Program.
The provisions of SR 3.0.3 are applicable to the Containment Leakage Rate Testing Program.
5.7.2.20 Control Room Envelope Habitability Program A Control Room Envelope (CRE) Habitability Program shall be established and implemented to ensure that CRE habitability is maintained such that, with an OPERABLE Control Room Emergency Ventilation System (CREVS), CRE occupants can control the reactor safely under normal conditions and maintain it in a safe condition following a radiological event, hazardous chemical release, or a smoke challenge. The program shall ensure that adequate radiation protection is proVided to permit access and occupancy of the CRE under design basis accident (DBA) conditions without personnel receiving radiation exposures in excess of 5 rem whole body or its equivalent to any part of the body for the duration of the accident. The program shall include the following elements:
- a.
The definition of the CRE and the CRE boundary.
- b.
Requirements for maintaining the CRE boundary in its design condition including configuration control and preventive maintenance.
- c.
Requirements for (i) determining the unfiltered air inleakage past the CRE boundary into the CRE in accordance with the testing methods and at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, "Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors,"
Revision 0, May 2003, and (ii) assessing CRE habitpbility at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, Revision O.
(continued)
Watts Bar-Unit 1 5.0-25 Amendment 5, 70,78
Procedures, Programs, and Manuals 5.7 5.7 Procedures, Programs, and Manuals 5.7.2.20 Control Room Envelope Habitability Program (continued)
- d.
Measurement, at designated locations, of the CRE pressure relative to all external areas adjacent to the CRE boundary during the pressurization mode of operation by one train of the CREVS, operating at the flow rate defined in the Ventilation Filter Testing Program (VFTP), at a Frequency of 18 months on a STAGGERED TEST BASIS. The results shall be trended and used as part of the 18 month assessment of the CRE boundary.
- e.
The quantitative limits on unfiltered air inleakage into the CRE. These limits shall be stated in a manner to allow direct comparison to the unfiltered air inleakage measured by the testing described in paragraph c. The unfiltered air inleakage limit for radiological challenges is the inleakage flow rate assumed in the licensing basis analyses of DBA consequences. Unfiltered air inleakage limits for' hazardous chemicals must ensure that exposure of CRE occupants to these hazards will be within the assumptions in the licensing basis.
- f.
The provisions of SR 3.0.2 are applicable to the frequencies for assessing CRE habitability, determining CRE unfiltered inleakage, and measuring CRE pressure and assessing the CRE boundary as required by paragraphs c and d, respectively.
Watts Bar-Unit 1 5.0-25a Amendment 70, 78
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 78 TO FACILITY OPERATING LICENSE NO. NPF-90 TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT, UNIT 1 DOCKET NO. 50-390
1.0 INTRODUCTION
By letter dated April 30, 2009 (Agencywide Document and Management System Accession No. ML091320562), the Tennessee Valley Authority (TVA, licensee) submitted a request for changes to the Technical Specifications (TSs) for Watts Bar Nuclear Plant (WBN), Unit 1.
The proposed amendment revises TS 5.7, "Procedures, Programs, and Manuals," to correct a typographical error in the TS section from 5.2.7.20 to 5.7.2.20.
Notice of this amendment was given in the Federal Register on May 19, 2008 (74 FR 23449).
2.0 BACKGROUND
In a TVA letter to the U.S. Nuclear Regulatory Commission (NRC) titled, "Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with Technical Specification Task Force (TSTF)-448, Revision 3. Using the Consolidated Line Item Improvement Process," dated October 26,2007 (ML073380948), TVA sent to the NRC typographical errors contained on TS pages 5.0-25 and 5.0-25a. The typographical error is located in the TS section; the TS section is listed as 5.2.7.20 and it should be 5.7.2.20.
This typographical error was carried forward in the NRC Amendment No. 70, dated October 8,2008 (ML082730261).
3.0 REGULATORY EVALUATION
The provisions of Title 10, Code of Federal Regulations (10 CFR) 50.36, "Technical Specifications," include requirements for the contents of TSs. These shall include Surveillance Requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met.
- 2
4.0 TECHNICAL EVALUATION
The NRC staff reviewed the TVA letter, dated October 26,2007 (ML073380948). On page A2-5 of the application dated October 26,2007, Insert 6 states the following: "5.2.7.20 Control Room Envelope Habitability Program." On page A2-9 of the application, dated October 26,2007, the TS section is 5.7, "Procedures, Programs, and Manuals," and the subsection prior to Insert 6 is "5.7.2.19 Containment Leakage Rate Testing Program (continued)." The NRC staff finds that a typographical error was introduced in the application dated October 26,2007. The NRC staff carried this typographical error along in Amendment No. 70, dated October 8, 2008.
The NRC staff finds that correcting the typographical error in the TS Section numbering on pages 5.0-25 and 5.0-25a in TS 5.7 has no adverse impact on safety, and therefore, is acceptable.
5.0 STATE CONSULTATION
In accordance with the Commission's regulations, an official of the Tennessee Bureau of Radiological Health was notified of the proposed issuance of the amendment. The State official had no comments.
6.0 ENVIRONMENTAL CONSIDERATION
The amendment relates to changes in recordkeeping, reporting, or administrative procedures or requirements. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(1 0). Pursuant to 10 CFR 51.22(b), no environmental impact statement need be prepared in connection with the issuance of the amendment.
7.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principle Contributor: John G. Lamb Date: July 21, 2009
Mr. Preston D. Swafford Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
SUBJECT:
WATTS BAR NUCLEAR PLANT, UNIT 1 - ISSUANCE OF AMENDMENT REGARDING THE APPLICATION FOR TECHNICAL SPECIFICATION (TS)
CHANGE TO CORRECT MINOR ERROR IN AMENDMENT 70 (TAC NO.
ME1192)
Dear Mr. Swafford:
The Commission has issued the enclosed Amendment No. 78 to Facility Operating License No. NPF-90 for Watts Bar Nuclear Plant, Unit 1. This amendment is in response to your application dated April 30, 2009.
The amendment revises Technical Specification (TS) 5.7, "Procedures, Programs, and Manuals," to correct a typographical error in the TS section from 5.2.7.20 to 5.7.2.20.
A copy of the safety evaluation is also enclosed. Notice of issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely, IRAI 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
Enclosures:
- 1. Amendment No. 78 to NPF-90
- 2. Safety Evaluation cc w/enclosures: Distribution via Listserv DISTRIBUTION:
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