ML022740492

Revised Technical Specifications Pages for Post Accident Sampling System Submittal

ML022740492
Person / Time
Site:	Hatch
Issue date:	09/24/2002
From:	Sumner H Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
HL-6294
Download: ML022740492 (7)

Text

Lewis Sumner Southern Nuclear Vice President Operating Company, Inc.

Hatch Project Support 40 Inverness Parkway Post Office Box 1295 Birmingham. Alabama 35201 Tel 205 992.7279 Fax 205 992 0341 S Wk SOUTHERN N September 24, 2002 COMPANY Docket Nos. 50-321 50-366 Energy to Serve Your World*

HL-6294 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Edwin I. Hatch Nuclear Plant Revised Technical Specifications Pages for Post Accident Sampling System Submittal Ladies and Gentlemen:

On June 24, 2002, we submitted a request to change the Hatch Unit 1 and 2 Technical Specifications (TS) regarding elimination of the Post Accident Sampling system. Following discussions with your staff it was decided to change the mark-up of Unit 1 and 2 TS page 5.0-8 we originally submitted to you on June 24. The enclosure contains the revised pages and page change instructions.

The TS change request was based on Standard Technical Specification Change Traveler, TSTF-413, "Elimination of Requirements for a Post Accident Sampling System (PASS)." The availability of this Technical Specification improvement was announced in the Federal Register on March 20, 2002, as part of the consolidated line item improvement process (CLIIP).

The justification, 10 CFR 50.92 evaluation and environmental assessment provided in the original submittal still apply.

In accordance with the requirements of 10 CFR 50.91, a copy of this letter and all applicable enclosures will be sent to the designated state official of the Environmental Protection Division of the Georgia Department of Natural Resources.

Mr. H. L. Sumner, Jr. states he is Vice President of Southern Nuclear Operating Company and is authorized to execute this oath on behalf of Southern Nuclear Operating Company, and to the best of his knowledge and belief, the facts set forth in this letter are true.

Respectfully submitted, H. L. Sumner, Jr.

Sworn to and subscribedbefore me this L day of _t 2002.

Commission ExpirationDate: 0, - -

U. S. Nuclear Regulatory Commission Page 2 September 24, 2002

Enclosure:

Revised Technical Specification Pages eb/OCV cc: Southern Nuclear Operating Company Mr. P. H. Wells, Nuclear Plant General Manager SNC Document Management (R-Type A02.001)

U.S. Nuclear Rewulatory Commission, Washington, D.C.

Mr. Joseph Colaccino, Project Manager - Hatch U.S. Nuclear Regulatory Commission, Region II Mr. L. A. Reyes, Regional Administrator Mr. J. T. Munday, Senior Resident Inspector - Hatch State of George Mr. L. C. Barrett, Commissioner - Department of Natural Resources HL-6294

Enclosure Edwin I. Hatch Nuclear Plant Revised Technical Specifications Pages for Post Accident Sampling Submittal Proposed Technical Specification Pages Page Change Instructions Unit 1 Paage Replace 5.0-8 5.0-8 Unit 2 Paae Replace 5.0-8 5.0-8 HL-6294

Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.2 Primary Coolant Sources Outside Containment This program provides controls to minimize leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to levels as low as practicable. The systems include the Core Spray, High Pressure Coolant Injection, Residual Heat Removal, Reactor Core Isolation Cooling, and Reactor Water Cleanup. The program shall include the following:

a. Preventive maintenance and periodic visual inspection requirements; and

b. System leak test requirements'for each system, to the extent permitted by system design and radiological conditions, at refueling cycle intervals or less.

5.5.3 Post Accident Samplincq (Deleted) 5.5.4 Radioactive Effluent Controls Program This program conforms to 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as reasonably achievable. The program shall be contained in the ODCM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:

a. Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation, including surveillance tests and setpoint determination, in accordance with the methodology in the ODCM;

b. Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areas, conforming to 10 times the concentrations stated in 10 CFR 20, Appendix B (to paragraphs 20.1001 - 20.2401),

Table 2, Column 2; (continued)

HATCH UNIT 1 5.0-8

and Manuals Programs Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.2 Primary Coolant Sources Outside Containment This program provides controls to minimize leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to levels as low as practicable. The systems include the Core Spray, High Pressure Coolant Injection, Residual Heat Removal, Reactor Core Isolation Cooling, and Reactor Water Cleanup. The program shall include the following:

a. Preventive maintenance and periodic visual inspection requirements; and

b. System leak test requirements for each system, to the extent permitted by system design and radiological conditions, at refueling cycle intervals or less.

5.5.3 Post Accident Sampling (Deleted) 5.5.4 Radioactive Effluent Controls Program This program conforms to 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as reasonably achievable. The program shall be contained in the ODCM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:

a. Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation, including surveillance tests and setpoint determination, in accordance with the methodology in the ODCM;

b. Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areas, conforming to 10 times the concentrations stated in 10 CFR 20, Appendix B (to paragraphs 20.1001 - 20.2401),

Table 2, Column 2; (continued)

HATCH UNIT 2 5.0-8

Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.2 Primary Coolant Sources Outside Containment This program provides controls to minimize leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to levels as low as practicable. The systems include the Core Spray, High Pressure Coolant Injection, Residual Heat Removal, Reactor Core Isolation Cooling, and Reactor Water Cleanup. The program shall include the following:

a. Preventive maintenance and periodic visual inspection requirements; and

b. System leak test requirements for each system, to the extent permitted by system design and radiological conditions, at refueling cycle intervals or less.

5.5.3 Post Accident Samplinq program provides contro s that ensure te capa to reacto lant; radioactive gases and particulates in plant gaseouents; and contain tmosphere samples under accident cond"r. The prograr shall include the fo

a. Training of personnel;

b. Procedures for pling and analysis; an c' -. isions for maintenance of sampling and analysis eq nt.

5.5.4 Radioactive Effluent Controls Proaram This program conforms to 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as reasonably achievable. The program shall be contained in the ODCM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:

a. Limitations on the functional capability of radioactive liquid and gaseous monitoring instru6,entation, including surveillance tests and setpoint determination, in accordance with the methodology in the ODCM;

b. Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areas, conforming to 10 times the concentrations stated in 10 CFR 20, Appendix B (to paragraphs 20.1001 - 20.2401),

Table 2, Column 2; (continued)

HATCH UNIT 1 5.0-8 Amendment No. 195

Programs and Manuals

• 5.5 5.5 Programs and Manuals (continued) 5.5.2 Primary Coolant Sources Outside Containment This program provides controls to minimize leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to levels as low as practicable. The systems include the Core Spray, High Pressure Coolant Injection, Residual Heat Removal, Reactor Core Isolation Cooling, and Reactor Water Cleanup. The program shall include the following:

a. Preventive maintenance and periodic visual inspection requirements; and

b. System leak test requirements for each system, to the extent permitted by system design and radiological conditions, at refueling cycle intervals or less.

5.5.3 Post Accident Samplinq Thi ram provides controls that ensure the capabihty to obtain and anal reactor co radioactive gases and particulates in plant gaseous ents; and containment s here samples under accident condiV . The program shall include the following.

a. Training of personnel;

b. Procedures mpling and analysis; and

c. rovisions for maintenance of sampling and analysis equipme 5.5.4 Radioactive Effluent Controls Program This program conforms to 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as reasonably achievable. The program shall be contained in the ODCM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:

a. Limitations on the functional capability of radioactive liquid and gaseous monitoring instru~nentation, including surveillance tests and setpoint determination, in accordance with the methodology in the ODCM;

b. Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areas, conforming to 10 times the concentrations stated in 10 CFR 20, Appendix B (to paragraphs 20.1001 - 20.2401),

Table 2, Column 2; (continued)

HATCH UNIT 2 5.0-8 Amendment No. 135