ML020310237

License Amendments, Revising the Technical Specifications Requirements, TAC Nos. MB2898 & MB2902

ML020310237
Person / Time
Site:	South Texas
Issue date:	03/19/2002
From:	Thadani M NRC/NRR/DLPM/LPD4
To:	Cottle W South Texas
References
Download: ML020310237 (12)

Text

March 19, 2002 Mr. William T. Cottle President and Chief Executive Officer STP Nuclear Operating Company South Texas Project Electric Generating Station P. O. Box 289 Wadsworth, TX 77483

SUBJECT:

SOUTH TEXAS PROJECT, UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS REVISING THE TECHNICAL SPECIFICATIONS (TAC NOS. MB2898 AND MB2902)

Dear Mr. Cottle:

The Commission has issued the enclosed Amendment No. 137 to Facility Operating License No. NPF-76 and Amendment No. 126 to Facility Operating License No. NPF-80 for the South Texas Project, Units 1 and 2, respectively. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated August 2, 2001.

The amendments revise the TSs requirements by removing the containment post-tensioning system surveillance in TS 3/4.6.1.6, Containment Structural Integrity, and replacing it with TS Section 6.8.3.l which describes and references the Containment Post-Tensioning System Surveillance Program.

A copy of our related Safety Evaluation is also 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, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-498 and 50-499

Enclosures:

1. Amendment No. 137 to NPF-76

2. Amendment No. 126 to NPF-80

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

March 19, 2002 Mr. William T. Cottle President and Chief Executive Officer STP Nuclear Operating Company South Texas Project Electric Generating Station P. O. Box 289 Wadsworth, TX 77483

SUBJECT:

SOUTH TEXAS PROJECT, UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS REVISING THE TECHNICAL SPECIFICATIONS (TAC NOS. MB2898 AND MB2902)

Dear Mr. Cottle:

The Commission has issued the enclosed Amendment No. 137 to Facility Operating License No. NPF-76 and Amendment No. 126 to Facility Operating License No. NPF-80 for the South Texas Project, Units 1 and 2, respectively. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated August 2, 2001.

The amendments revise the TSs requirements by removing the containment post-tensioning system surveillance in TS 3/4.6.1.6, Containment Structural Integrity, and replacing it with TS Section 6.8.3.l which describes and references the Containment Post-Tensioning System Surveillance Program.

A copy of our related Safety Evaluation is also 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, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-498 and 50-499

Enclosures:

1. Amendment No. 137 to NPF-76

2. Amendment No. 126 to NPF-80

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

PUBLIC RidsNrrDlpmLpdiv (SRichards) RidsNrrLAMMcAllister PDIV-1 r/f RidsNrrDlpmLpdiv1 (RGramm) RidsNrrDripRopr (R.Dennig)

GHill (4) RidsNrrPMMThadani RidsAcrsAcnwMailCenter RidsOgcRp RidsRgn4MailCenter (D. Graves, L. Hurley, D. Bujol)

PHearn (PCH) TCheng (TMC)

Tech Spec Pages: ML020790013 Package: ML020910816 ACCESSION NO: ML020310237 *See SE input OFFICE PDIV-1/PM PDIV-1/LA EMEB/BC* TSB/BC* OGC PDIV-1/SC NAME MThadani MMcAllister Tcheng Phern AHodgdon RGramm DATE 2/15/02 2/13/02 10/29/01 11/9/01 3/14/02 3/15/02 OFFICIAL RECORD COPY

South Texas, Units 1 & 2 cc:

A. H. Gutterman, Esq.

Mr. Cornelius F. OKeefe Morgan, Lewis & Bockius Senior Resident Inspector 1111 Pennsylvania Avenue, NW U.S. Nuclear Regulatory Commission Washington, DC 20004 P. O. Box 910 Bay City, TX 77414 Mr. J. J. Sheppard, Vice President Engineering & Technical Services A. Ramirez/C. M. Canady STP Nuclear Operating Company City of Austin P. O. Box 289 Electric Utility Department Wadsworth, TX 77483 721 Barton Springs Road Austin, TX 78704 S. M. Head, Manager, Licensing Nuclear Quality & Licensing Department Mr. M. T. Hardt STP Nuclear Operating Company Mr. W. C. Gunst P. O. Box 289, Mail Code: N5014 City Public Service Board Wadsworth, TX 77483 P. O. Box 1771 San Antonio, TX 78296 Office of the Governor ATTN: John Howard, Director Mr. C. A. Johnson/R. P. Powers Environmental and Natural AEP - Central Power and Light Company Resources Policy P. O. Box 289 P. O. Box 12428 Mail Code: N5022 Austin, TX 78711 Wadsworth, TX 77483 Jon C. Wood INPO Matthews & Branscomb Records Center 112 East Pecan, Suite 1100 700 Galleria Parkway San Antonio, TX 78205 Atlanta, GA 30339-3064 Arthur C. Tate, Director Regional Administrator, Region IV Division of Compliance & Inspection U.S. Nuclear Regulatory Commission Bureau of Radiation Control 611 Ryan Plaza Drive, Suite 400 Texas Department of Health Arlington, TX 76011 1100 West 49th Street Austin, TX 78756 D. G. Tees/R. L. Balcom Houston Lighting & Power Co. Jim Calloway P. O. Box 1700 Public Utility Commission of Texas Houston, TX 77251 Electric Industry Analysis P. O. Box 13326 Judge, Matagorda County Austin, TX 78711-3326 Matagorda County Courthouse 1700 Seventh Street Bay City, TX 77414 February 2002

STP NUCLEAR OPERATING COMPANY DOCKET NO. 50-498 SOUTH TEXAS PROJECT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 137 License No. NPF-76

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

A. The application for amendment by STP Nuclear Operating Company* acting on behalf of itself and for Houston Lighting & Power Company (HL&P), the City Public Service Board of San Antonio (CPS), Central Power and Light Company (CPL), and the City of Austin, Texas (COA) (the licensees), dated August 2, 2001, 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.

STP Nuclear Operating Company is authorized to act for Houston Lighting & Power Company (HL&P), the City Public Service Board of San Antonio, Central Power and Light Company, and the City of Austin, Texas, and has exclusive responsibility and control over the physical construction, operation, and maintenance of the facility.

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-76 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 137, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. The South Texas Project Nuclear Operating Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3. The license amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/

Robert A. Gramm, Chief, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: March 19, 2002

STP NUCLEAR OPERATING COMPANY DOCKET NO. 50-499 SOUTH TEXAS PROJECT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 126 License No. NPF-80

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

A. The application for amendment by STP Nuclear Operating Company* acting on behalf of itself and for Houston Lighting & Power Company (HL&P), the City Public Service Board of San Antonio (CPS), Central Power and Light Company (CPL), and the City of Austin, Texas (COA) (the licensees), dated August 2, 2001, 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.

STP Nuclear Operating Company is authorized to act for Houston Lighting & Power Company (HL&P), the City Public Service Board of San Antonio, Central Power and Light Company, and the City of Austin, Texas, and has exclusive responsibility and control over the physical construction, operation, and maintenance of the facility.

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-80 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 126, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. The South Texas Project Nuclear Operating Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3. The license amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/

Robert A. Gramm, Chief, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: March 19, 2002

ATTACHMENT TO LICENSE AMENDMENT NOS. 137 AND 126 FACILITY OPERATING LICENSE NOS. NPF-76 AND NPF-80 DOCKET NOS. 50-498 AND 50-499 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 3/4 6-9 3/4 6-9 3/4 6-10 3/4 6-10 3/4 6-11 3/4 6-11A 3/4 6-11B 6-18a* 6-18a*

6-18b 6-18b

• Overleaf page provided to maintain document completeness. No changes on this page.

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 137 AND 126 TO FACILITY OPERATING LICENSE NOS. NPF-76 AND NPF-80 STP NUCLEAR OPERATING COMPANY, ET AL.

SOUTH TEXAS PROJECT, UNITS 1 AND 2 DOCKET NOS. 50-498 AND 50-499

1.0 INTRODUCTION

On August 2, 2001, South Texas Project Nuclear Operating Company (STPNOC, licensee),

submitted a license amendment request, pursuant to 10 CFR 50.90, revising the Technical Specifications (TSs) for South Texas Project (STP), Units 1 and 2. The STPNOC proposed to remove the containment post-tensioning system surveillance in TS 3/4.6.1.6, Containment Structural Integrity, and replace it with TS Section 6.8.3.l which describes and references the Containment Post-Tensioning System Surveillance Program (CPTSSP).

The licensee proposed the changes to the TS to conform to the new regulatory requirements.

The major portion of the changes involves replacing the requirements for tendon surveillance with inspection procedures in accordance with the requirements of Subsections IWE and IWL of the American Society of Mechanical Engineers (ASME) Code,Section XI, as supplemented by 10 CFR 50.55a(b)(2)(viii).

Specifically, the licensee proposed the following changes to the current TS:

1. Limiting Condition for Operation 3.6.1.6

a. Replaced the sentence, The structural integrity of the containment(s) shall be maintained at a level consistent with the acceptance criteria in Specification 4.6.1.6, with the sentence, The structural integrity of the containment(s) shall be maintained as required by the Containment Post-Tensioning System Surveillance Program.

b. Deleted the original ACTIONS a. and b. in Section 3.6.1.6 (Sections 3.6.1.6.a and 3.6.1.6.b) and replaced with the words, If the containment is not OPERABLE, restore containment to OPERABLE status in one hour, or be in at least HOT STANDBY in the next 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> and be in COLD SHUTDOWN in the following 30 hours1.25 days <br />0.179 weeks <br />0.0411 months <br />.

2. Surveillance Requirement 4.6.1.6, Containment Prestressing System Deleted Section 4.6.1.6.1 (tendon surveillance inspection procedures and requirements),

Section 4.6.1.6.2, End Anchorages and Adjacent Concrete Surfaces, and Section 4.6.1.6.3, Containment Surfaces, (Pages 3/4 6-9 through 3/4 6-11a), and replaced with the words, Verify containment structural integrity in accordance with the Containment Post-Tensioning System Surveillance Program.

3. Section 6.8, Procedures and Programs, Subsection 6.8.3 The licensee added the following description of Containment Post-Tensioning System Surveillance Program:

This program provides controls for monitoring any tendon degradation in prestressed concrete containments, including effectiveness of its corrosion protection medium, to ensure containment structural integrity. The program shall include baseline measures prior to initial operations. The Containment Post-Tensioning System Surveillance Program shall be in accordance with ASME Code Section XI, Subsection IWL, 1992 Edition with 1992 Addenda, as supplemented by 10 CFR 50.55a(b)(2)(viii).

2.0 BACKGROUND

On January 7, 1994, the Nuclear Regulatory Commission (NRC) published a proposed amendment to the regulations to incorporate by reference the 1992 Edition with the 1992 Addenda of Subsections IWE and IWL of Section XI, Division I of the ASME Boiler and Pressure Vessel Code (the Code). The final rule, Subpart 50.55a(g)(6)(ii)(B) of Title 10 of the Code of Federal Regulations (10 CFR), became effective on September 9, 1996, and requires licensees to implement Subsections IWE and IWL, with specified modifications and limitations, by September 9, 2001.

The limitations on the containment structure internal pressure ensure that: (1) the containment structure is prevented from exceeding its design negative pressure differential with respect to the outside atmosphere, and (2) the containment structure peak pressure does not exceed the design pressure resulting from a steam line break.

The internal pressure limitation ensures that the structural integrity of the containment will be maintained comparable to the original design standards for the life of the facility. Structural integrity is required to ensure that the containment will withstand the maximum pressure in the event of a steam line break.

The post-tensioned tendon system is an integral structural force-resisting component of the containment structure. The post-tensioning system consists of three groups of tendons:

horizontal or hoop, vertical, and dome. The tendon system provides a compressive force in the containment structure concrete, which counteracts the internal pressure inside the structure, postulated to occur during certain accidents such as loss-of-coolant accidents and steam line breaks. The tendons were installed in ducts embedded within the containment structure concrete and tensioned to a prescribed force.

Over time the force in the individual tendons is expected to decrease due to losses caused by phenomena, such as: tendon wire relaxation and concrete creep and shrinkage. The amount of force initially provided by the tendon design and installation accounted for these tendon force losses. The CPTSSP measures the force in a small sample population of tendons from each of the groups at predetermined time intervals. This ensures the rate of tendon force loss is within predicted limits and that the minimum tendon force required to meet the design basis will be available through the time of the next scheduled surveillance.

3.0 EVALUATION As stated above, the Code of Federal Regulations Section 10 CFR 50.55a has been amended to incorporate, by reference, the requirements of the ASME Boiler and Pressure Vessel Code,Section XI, Subsection IWL, 1992 Edition including 1992 Addenda. Additionally, 10 CFR 50.55a contains requirements and limitations that augment the ASME Code. The tendon surveillance requirements currently reflected in the TS and the final safety analysis report (FSAR) comply with the criteria that were applicable when the STP, Units 1 and 2 were licensed. The surveillance requirements in 10 CFR 50.55a and the ASME Code Section XI include requirements beyond those in the current STP, Units 1 and 2 TS and FSAR.

In its submittal, the licensee proposed to delete the details of tendon surveillance inspection procedures and requirements, including requirements for the end anchorages and adjacent concrete surfaces, and containment surfaces, from the current TS, and proposed to demonstrate the containment structural integrity through the implementation of its CPTSSP.

According to the licensee, the CPTSSP has incorporated the requirements for the surveillance of the reactor building post-tensioned tendon system as specified in 10 CFR 50.55a(b)(2)(vi),

Effective Edition and Addenda of Subsection IWE and Subsection IWL,Section XI, and 10 CFR 50.55a(b)(2)(viii), Examination of Concrete Containments. In the Technical Analysis section of the request for amendment, the licensee added that there would be no change in the design basis and in the level of compliance with the General Design Criteria. The licensee further clarified that the proposed TS change only incorporates the tendon surveillance requirements by reference into the CPTSSP and there is no actual change in the requirements.

Consequently, there is no impact on safe operation of the STP, Units 1and 2 as a result of the proposed change. The licensees justification indicates that through the implementation of the CPTSSP (the measurement of tendon lift force, the tensile tests of the tendon wires, the visual examination of tendons, anchorages and exposed interior and exterior surfaces of the containment, and the Type A leakage test), the containment structural integrity can be ensured to withstand a maximum pressure in the event of a steam line break accident.

The NRC staff reviewed the proposed changes to the TS related to containment structural integrity and found that the elements contained in the revised TS are acceptable on the basis of the following requirements: (1) the containment structural integrity will be maintained via the provision of proposed TS 4.6.1.6, (2) the procedures of the CPTSSP are in accordance with the 1992 Addenda of ASME Code,Section XI, Subsection IWL as set forth in 10 CFR 50.55a, and (3) any degradation which exceeds the acceptance criteria detected through the CPTSSP will be reported to the NRC as committed in the unrevised TS reporting requirements.

Approval of the proposed TS changes does not relieve the licensee of its responsibility to report, pursuant to 10 CFR 50.73(a)(2)(ii), any event or condition that results in the condition of the nuclear power plant being seriously degraded. These conditions include serious

degradation of the containment concrete structure, such as de-lamination of the dome concrete, widely spread corrosion of the liner plate, corrosion of prestressing elements (wires, strands, bars) or anchorage components extending more than two tendons, and tendon force trend not meeting the requirement of 10 CFR 50.55a(b)(2)(viii)(B).

The NRC staff has, therefore, determined that the licensee's proposed changes to the TS are acceptable.

4.0 STATE CONSULTATION

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

5.0 ENVIRONMENTAL CONSIDERATION

The amendment permits changes to be made to certain operational limits and surveillance requirements. The NRC staff has determined that the amendment involves 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 amendment involves no significant hazards consideration, and there has been no public comment on such finding (67 FR 2929 dated January 22, 2002). Accordingly, the amendment meets 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 amendment.

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

Principal Contributors: P. Hearn T. Cheng Date: March 19, 2002