NOC-AE-02001442, Corrections to Proposed Amendment to Operating License and Technical Specifications Regarding Steam Generators

Corrections to Proposed Amendment to Operating License and Technical Specifications Regarding Steam Generators

ML030210106
Person / Time
Site:	South Texas
Issue date:	01/07/2003
From:	Jordan T South Texas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NOC-AE-02001442
Download: ML030210106 (6)

Text

Nuclear Operating Company South T7s Prodje Elctrlc GeneaghgStation S PO. Box 28,9 kdsavIth, Terns 77483 _ _ _ _ _ _

January 7, 2003 NOC-AE-02001442 10CFR50.90 U. S. Nuclear Regulatory Commission Attention: Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852 South Texas Project Units 1 and 2 Docket Nos. STN 50-498 and STN 50-499 Corrections to Proposed Amendment to Operating License and Technical Specifications Regarding Steam Generators

Reference:

Letter, J. J. Sheppard to NRC Document Control Desk, "License Amendment Request - Proposed Amendment to Operating License and Technical Specifications Regarding Steam Generators," dated May 23, 2002 (NOC-AE-02001272)

The referenced letter requested an amendment to several sections of the Technical Specifications and to the Unit 2 Operating License to delete information specific to Model E steam generators (SGs).

The Model E SGs in both units have been replaced with Delta 94 SGs. Therefore, differentiation between SG models is no longer required. Specific references to Delta 94 SGs are also removed.

The proposed amendment included retyped Technical Specification pages with the proposed changes incorporated. There were minor typographical errors (incorrect paragraph number, missing parenthesis, capital letter) on the retyped pages. Those errors have been corrected and replacement pages are attached with this letter. Additionally, the retyped Unit 2 Operating License page has been updated to reflect the approved ownership change from HL&P to Texas Genco, LP.

If there are any questions regarding this matter, please contact Mr. Scott Head at (361) 972-7136 or me at (361) 972-7902.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on January 7, 2003 T. . ordan Vice President Engineering & Technical Services

/ 6 jtc Attachments: Retyped Technical Specification Pages 3/4 4-12, 3/4 4-13, and 3/4 4-18 Updated Unit 2 Operating License Page 3 STI: 31534447

NOC-AE-02001442 Page 2 of 2 cc:

(paper copy) (electronic copy)

Ellis W. Merschoff A. H. Gutterman, Esquire Regional Administrator, Region IV Morgan, Lewis & Bockius LLP U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 L. D. BlaylockIW. C. Gunst Arlington, Texas 76011-8064 City Public Service U. S. Nuclear Regulatory Commission Mohan C. Thadani Attention: Document Control Desk U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike R. L. Balcom Rockville, MD 20852 Texas Genco, LP Richard A. Ratliff A. Ramirez Bureau of Radiation Control City of Austin Texas Department of Health 1100 West 49th Street C. A. Johnson Austin, TX 78756-3189 AEP Texas Central Company Cornelius F. O'Keefe Jon C. Wood U. S. Nuclear Regulatory Commission Matthews & Branscomb P. 0. Box 289, Mail Code: MN116 Wadsworth, TX 77483 C. M. Canady City of Austin Electric Utility Department 721 Barton Springs Road Austin, TX 78704

REACTOR COOLANT SYSTEM 3/4.4.5 STEAM GENERATOR LIMITING CONDITION FOR OPERATION 3.4.5 Each steam generator shall be OPERABLE.

APPLICABILITY: MODES 1,2, 3, and 4.

ACTION:

With one or more steam generators inoperable, restore the inoperable generator(s) to OPERABLE status prior to increasing T"avg above 200'F.

SURVEILLANCE REQUIREMENTS 4.4.5.0 Each steam generator shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.5.

4.4.5.1 Steam Generator Sample Selection and Inspection - Each steam generator shall be determined OPERABLE during shutdown by selecting and inspecting at least the minimum number of steam generators specified in Table 4.4-1.

4.4.5.2 Steam Generator Tube Sample Selection and Inspection - The steam generator tube minimum sample size, inspection result classification, and the corresponding action required shall be as specified in Table 4.4-2. The inservice inspection of steam generator tubes shall be I performed at the frequencies specified in Specification 4.4.5.3 and the inspected tubes shall be verified acceptable per the acceptance criteria of Specification 4.4.5.4. The tubes selected for each inservice inspection shall include at least 3% of the total number of nonplugged tubes in all steam generators; the tubes selected for these inspections shall be selected on a random basis except:

a. Where experience in similar plants with similar water chemistry indicates critical areas to be inspected, then at least 50% of the tubes inspected shall be from these critical areas;

b. The first sample of tubes selected for each inservice inspection (subsequent to the preservice inspection) of each steam generator shall include:

1) All nonplugged tubes that previously had detectable wall penetrations (greater than 20%),

2) Tubes in those areas where experience has indicated potential problems, and SOUTH TEXAS - UNITS 1 & 2 3/4 4-12 Unit 1 - Amendment No.

Unit 2 - Amendment No.

REACTOR COOLANT SYSTEM STEAM GENERATORS SURVEILLANCE REQUIREMENTS (Continued)

3) A tube Inspection (pursuant to Specification 4.4.5.4a.9) shall be performed on each selected tube. If any selected tube does not permit the passage of the eddy current probe for a tube inspection, this shall be recorded and an adjacent tube shall be selected and subjected to a tube inspection.

c. The tubes selected as the second and third samples (if required by Table 4.4-2) during each inservice inspection may be subjected to a partial tube inspection provided:

1) The tubes selected for these samples include the tubes from those areas of the tube sheet array where tubes with imperfections were previously found, and

2) The inspections include those portions of the tubes where imperfections were previously found.

The results of each sample inspection shall be classified into one of the following three categories.

Cateqory Inspection Results C-1 Less than 5% of the total tubes inspected are degraded tubes and none of the inspected tubes are defective.

C-2 One or more tubes, but not more than 1% of the total tubes inspected are defective, or between 5% and 10% of the total tubes inspected are degraded tubes.

C-3 More than 10% of the total tubes inspected are degraded tubes or more than 1% of the inspected tubes are defective.

Note: In all inspections, previously degraded tubes must exhibit significant (greater than 10%) further wall penetrations to be included in the above percentage calculations.

SOUTH TEXAS - UNITS 1 & 2 3/4 4-13 Unit 1 - Amendment No.

Unit 2 - Amendment No.

Table 4.4-2 STEAM GENERATOR TUBE INSPECTION 1st SAMPLE INSPECTION 2nd SAMPLE INSPECTION 3rd SAMPLE INSPECTION Sample Size Result Action Required Result Action Required Result Action Required N.A. N.A. N.A. N.A.

A minimum of S C-1 None Tubes per SG. C-2 Plug defective tubes C-1 None N.A. N.A.

and inspect additional 2S tubes in this SG. C-2 Plug defective tubes C-1 None and inspect additional 4S tubes in this SG C-2 Plug defective tubes C-3 Perform action for C 3 result of first sample C-3 Perform action for N.A. N.A.

C-3 result of first sample.

C-3 Inspect all tubes in this All other N.A. N.A.

None SG, plug defective tubes and inspect 2S SGs are C-1 I

tubes in each other Some SGs Perform action for C-2 N.A. N.A.

SG. C-2 but no result of second additional sample Notify NRC pursuant to SG are C-3 10CFR50.72(b)(3)(ii)

Additional Inspect all tubes in N.A. N.A.

SG is C-3 each SG and plug defective tubes.

Notify NRC pursuant to 10CFR50.72(b)(3)(ii) where N is the number of steam generators in the unit, and n is the number of steam generators inspected during an 11 inspection.

SOUTH TEXAS - UNITS 1 & 2 3/4 4-18 Unit 1 - Amendment No.

Unit 2 - Amendment No.

(1) STPNOC pursuant to Section 103 of the Act and 10 CFR Part 50, to possess, use and operate the facility at the designated location in Matagorda County, Texas, in accordance with the procedures and limitations set forth in this license; (2) Texas Genco, LP, the City Public Service Board of San Antonio (CPS), Central Power and Light Company (CPL), and the City of Austin, Texas (COA), pursuant to the Act and 10 CFR Part 50, to possess the facility at the designated location in Matagorda County, Texas, in accordance with the procedures and limitations set forth in this license; (3) STPNOC, pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; (4) STPNOC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5) STPNOC, 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 or instrument calibration or associated with radioactive apparatus or components; and (6) STPNOC, 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 authorized herein.

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 STPNOC is authorized to operate the facility at reactor core power levels not in excess of 3853 megawatts thermal (100% power) in accordance with the conditions specified herein.

Amendment No.