ML062340057

License Amendment, Issuance of Amendments Steam Generator Tube Surveillance Program, MC9498 and MC9499

ML062340057
Person / Time
Site:	Comanche Peak
Issue date:	09/12/2006
From:	Thadani M NRC/NRR/ADRO/DORL/LPLIV
To:	Blevins M TXU Power
Thadani M, NRR/DORL, 415-1476
References
TAC MC9498, TAC MC9499
Download: ML062340057 (12)

Text

September 12, 2006 Mr. M. R. Blevins Senior Vice President

& Chief Nuclear Officer TXU Power ATTN: Regulatory Affairs P. O. Box 1002 Glen Rose, TX 76043

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES), UNITS 1 AND 2 -

ISSUANCE OF AMENDMENTS RE: STEAM GENERATOR TUBE SURVEILLANCE PROGRAM (TAC NOS. MC9498 AND MC9499)

Dear Mr. Blevins:

The Commission has issued the enclosed Amendment No. 128 to Facility Operating License No. NPF-87 and Amendment No. 128 to Facility Operating License No. NPF-89 for CPSES, Units 1 and 2, respectively. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated December 16, 2005, as supplemented by your letter dated June 7, 2006.

The amendments would revise the steam generator (SG) tube surveillance program in a manner consistent with TS Task Force (TSTF) Traveler, TSTF-449, Revision 4, Steam Generator Tube Integrity, and the model safety evaluation prepared by the Nuclear Regulatory Commission, which was published in the Federal Register on March 2, 2005 (70 FR 10298) under the consolidated line item improvement process (CLIIP). In this regards, the scope of the application includes changes to the definition of leakage, changes to the primary-to-secondary leakage requirements, changes to the SG tube surveillance program (SG tube integrity), and changes to the SG reporting requirements.

M.R. Blevins A copy of our related Safety Evaluation is enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.

Sincerely,

/RA/

Mohan C. Thadani, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-445 and 50-446

Enclosures:

1. Amendment No. 128 to NPF-87

2. Amendment No. 128 to NPF-89

3. Safety Evaluation cc w/encls: See next page

M.R. Blevins A copy of our related Safety Evaluation is enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.

Sincerely,

/RA/

Mohan C. Thadani, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-445 and 50-446

Enclosures:

1. Amendment No. 128 to NPF-87

2. Amendment No. 128 to NPF-89

3. Safety Evaluation cc w/encls: See next page DISTRIBUTION:

PUBLIC RidsAcrsAcnwMailCenter LPLIV Reading GHill RidsNrrDorlLpl4 RidsNrrDirsItsb RidsNrrPMMThadani EThomas RidsNrrLALFeizollahi RidsRgn4MailCenter RidsOgcRp RidsNrrDorlDpr Package: ML062340117 TS: ML062580117 Accession No.: ML062340057 *No significant changes to TSB SE input.

OFFICE NRR/LPL4/PM NRR/LPL4/LA NRR/TSB/BC OGC NRR/LPL4/BC NAME MThadani LFeizollahi TKobetz* JRund DTerao DATE 8/30/06 8/29/06 9/11/06 9/12/06 OFFICIAL RECORD COPY

TXU GENERATION COMPANY LP COMANCHE PEAK STEAM ELECTRIC STATION, UNIT NO. 1 DOCKET NO. 50-445 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 128 License No. NPF-87

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

A. The application for amendment by TXU Generation Company LP dated December 16, 2005, as supplemented by letter dated June 7, 2006, 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, as amended, 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 license 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. 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-87.

3. The license amendment is effective as of its date of issuance and shall be implemented within 120 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/

David Terao, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Facility Operating License No. NPF-87 and Technical Specifications Date of Issuance: September 12, 2006

TXU GENERATION COMPANY LP COMANCHE PEAK STEAM ELECTRIC STATION, UNIT NO. 2 DOCKET NO. 50-446 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 128 License No. NPF-89

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

A. The application for amendment by TXU Generation Company LP dated December 16, 2005, as supplemented by letter dated June 7, 2006, 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, as amended, 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 license 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. 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-89.

3. This license amendment is effective as of its date of issuance and shall be implemented within 120 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/

David Terao, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Facility Operating License No. NPF-89 and Technical Specifications Date of Issuance: September 12, 2006

ATTACHMENT TO LICENSE AMENDMENT NO. 128 TO FACILITY OPERATING LICENSE NO. NPF-87 AND AMENDMENT NO. 128 TO FACILITY OPERATING LICENSE NO. NPF-89 DOCKET NOS. 50-445 AND 50-446

. Replace page 3 in each of the Facility Operating Licenses, NPF-87 and NPF-89.

Remove Insert 3 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 areas of change.

Remove Insert ii ii 1.1-4 1.1-4 3.4-33 3.4-33 3.4-34 3.4-34

---

3.4-48

---

3.4-49 5.0-13 5.0-13 5.0-14 5.0-14 5.0-15 5.0-15 5.0-15a 5.0-15a 5.0-16 5.0-16 5.0-16a 5.0-16a 5.0-17 5.0-17 5.0-17a 5.0-17a 5.0-18 5.0-18 5.0-19 5.0-19 5.0-19a 5.0-19a

---

5.0-19b

---

5.0-19c

---

5.0-19d 5.0-36 5.0-36 5.0-36a 5.0-36a

---

5.0-36b

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 128 TO FACILITY OPERATING LICENSE NO. NPF-87 AND AMENDMENT NO. 128 TO FACILITY OPERATING LICENSE NO. NPF-89 TXU GENERATION COMPANY LP COMANCHE PEAK STEAM ELECTRIC STATION, UNITS 1 AND 2 DOCKET NOS. 50-445 AND 50-446

1.0 INTRODUCTION

By application dated December 16, 2005 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML053620367), as supplemented by letter dated June 7, 2006 (ADAMS Accession No. ML061710137), TXU Generation Company LP (the licensee) requested changes to the Technical Specifications (TSs) for Comanche Peak Steam Electric Station (CPSES), Units 1 and 2. The supplement dated June 7, 2006, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the staff's original proposed no significant hazards consideration determination as published in the Federal Register on March 14, 2006 (71 FR 13181).

The proposed changes would revise the existing steam generator (SG) tube surveillance program. The changes are modeled after TS Task Force (TSTF) traveler TSTF-449, Revision 4, Steam Generator Tube Integrity, and the model safety evaluation prepared by the Nuclear Regulatory Commission (NRC) that was published in the Federal Register on March 2, 2005 (70 FR 10298) under the consolidated line item improvement process (CLIIP). In this regard, the scope of the application includes changes to the definition of leakage, changes to the primary-to-secondary leakage requirements, changes to the SG tube surveillance program (SG tube integrity), and changes to the SG reporting requirements.

2.0 REGULATORY EVALUATION

The background, description, and applicability of the proposed changes associated with the SG tube integrity issue and the applicable regulatory requirements were included in the NRC staffs model safety evaluation (SE) published in the Federal Register on March 2, 2005 (70 FR 10298). The Notice of Availability of Model Application Concerning Technical Specification; Improvement To Modify Requirements Regarding Steam Generator Tube Integrity; Using the Consolidated Line Item Improvement Process was published in the Federal Register on May 6, 2005 (70 FR 24126), which made the model SE available to licensees to reference.

3.0 TECHNICAL EVALUATION

In its December 16, 2005, application and June 7, 2006, supplement, the licensee proposed changes to the TSs that are modeled after TSTF-449. There were minor differences between TSTF-449 and the licensee's application. For example, since the licensee plans to replace the Unit 1 SGs at the end of its current operating cycle in the spring of 2007, the licensee is proposing to leave its existing TS 5.5.9 (administratively renamed TS 5.5.9.1, Steam Generator Program) and 5.6.10 (renamed Unit 1 model D4 Steam Generator Tube Inspection Report) in place for the remainder of the current Unit 1 operating cycle to allow the use of the approved alternate repair criteria and tube repair methods. For its current Unit 2 SGs and the replacement Unit 1 SGs, the licensee has developed a new SG program modeled after TSTF-449. Once the current Unit 1 SGs are replaced, the licensee will submit a separate license amendment to administratively remove TS 5.5.9.1 and 5.6.10, making the TS consistent with TSTF-449. In addition, there were minor differences in TS numbering between the licensee's application and TSTF-449. The NRC staff finds that, since these differences in TS numbering are administrative in nature and do not have any safety significance, they are acceptable.

The remainder of the application was generally consistent with TSTF-449. As a result, the staff has determined that the model SE is applicable to this review and finds the proposed changes acceptable.

Consistent with TSTF-449, the proposed TS changes include: (1) a revised definition of LEAKAGE in TS 1.1, (2) a revised TS 3.4.13, "RCS (Reactor Coolant System) Operational LEAKAGE," (3) a new TS 3.4.17, "Steam Generator (SG) Tube Integrity," (4) a revised TS 5.5.9.1, Unit 1 Model D4 Steam Generator (SG) Program, (5) a revised TS 5.5.9.2, "Unit 1 Model D76 and Unit 2 Model D5 Steam Generator (SG) Program," (6) a revised TS 5.6.10, "Unit 1 Model D4 Steam Generator Tube Inspection Report," (7) a new TS 5.6.9, Unit 1 Model D76 and Unit 2 Model D5 Steam Generator Tube Inspection Report, and (8) revised Table of Content pages to reflect the proposed changes.

The proposed TS changes establish a programmatic, largely performance-based regulatory framework for ensuring SG tube integrity is maintained. The NRC staff finds that it addresses key shortcomings of the current framework by ensuring that SG programs are focused on accomplishing the overall objective of maintaining tube integrity. It incorporates performance criteria for evaluating tube integrity that the NRC staff finds consistent with the structural margins and the degree of leak tightness assumed in the current plant licensing basis. The NRC staff finds that maintaining these performance criteria provides reasonable assurance that the SGs can be operated safely, and adequate protection of public health and safety is maintained.

The revised TSs will contain limited specific details concerning how the SG Program is to achieve the required objective of maintaining tube integrity; the intent being that the licensee will have the flexibility to determine the specific strategy for meeting this objective. However, the NRC staff finds that the revised TSs include sufficient regulatory constraints on the establishment and implementation of the SG Program such as to provide reasonable assurance that tube integrity will be maintained.

Failure to meet the performance criteria will be reportable pursuant to the requirements in Sections 50.72 and 50.73 of Title 10 of the Code of Federal Regulations (10 CFR). The NRC reactor oversight process provides a process by which the NRC staff can verify that the licensee has identified any SG program deficiencies that may have contributed to the failure, and that appropriate corrective actions have been implemented.

Based on the above evaluation, the NRC staff finds that the TS changes proposed by the licensee in its December 16, 2005, application and June 7, 2006, letter conform to the requirements of 10 CFR 50.36 and establish a TS framework that will provide reasonable assurance that SG tube integrity is maintained without undue risk to public health and safety.

4.0 STATE CONSULTATION

In accordance with the Commission's regulations, the Texas State official was notified of the proposed issuance of the amendments. The State official had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

The amendments change requirements with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding published on March 14, 2006 (71 FR 13181). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.

6.0 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 the amendments will not be inimical to the common defense and security or to the health and safety of the public.

7.0 REFERENCES

A complete list of references used to complete this review can be found in the NRCs model SE published in the Federal Register on March 2, 2005 (70 FR 10298).

Principal Contributor: Eric Thomas Date: September 12, 2006

Comanche Peak Steam Electric Station cc:

Senior Resident Inspector Mr. Brian Almon U.S. Nuclear Regulatory Commission Public Utility Commission P. O. Box 2159 William B. Travis Building Glen Rose, TX 76403-2159 P. O. Box 13326 1701 North Congress Avenue Regional Administrator, Region IV Austin, TX 78701-3326 U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Ms. Susan M. Jablonski Arlington, TX 76011 Office of Permitting, Remediation and Registration Mr. Fred W. Madden, Director Texas Commission on Environmental Regulatory Affairs Quality TXU Generation Company LP MC-122 P. O. Box 1002 P. O. Box 13087 Glen Rose, TX 76043 Austin, TX 78711-3087 George L. Edgar, Esq. Terry Parks, Chief Inspector Morgan Lewis Texas Department of Licensing 1111 Pennsylvania Avenue, NW and Regulation Washington, DC 20004 Boiler Program P. O. Box 12157 County Judge Austin, TX 78711 P. O. Box 851 Glen Rose, TX 76043 Environmental and Natural Resources Policy Director Office of the Governor P. O. Box 12428 Austin, TX 78711-3189 Mr. Richard A. Ratliff, Chief Bureau of Radiation Control Texas Department of Health 1100 West 49th Street Austin, TX 78756-3189 December 2004