ML030360135

Correction to License Amendment Request 02-10, Administrative Changes to TS Section 6.

ML030360135
Person / Time
Site:	Seabrook
Issue date:	01/24/2003
From:	Warner M Florida Power & Light Energy Seabrook
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NYN-03009
Download: ML030360135 (6)

Text

0 FPL Energy FPL Energy Seabrook Station Seabrook Station P.O. Box 300 Seabrook, NH 03874 (603) 773-7000 January 24, 2003 Docket No. 50-443 NYN-03009 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555-0001 Seabrook Station Correction to License Amendment Request 02-10 "Administrative Changes To Technical Specification Section 6" FPL Energy Seabrook, LLC (FPLE Seabrook) has enclosed herein a correction to License Amendment Request (LAR) 02-10. The correction changes the paragraph reference in the double asterisk footnote on Technical Specification page 6-15 from 10 CFR Part 20.220b to 10 CFR Part 20.2206. The number "6" was mistakenly written as "b" on the markup and retyped pages of the original LAR submittal.

10 CFR Part 20 was revised several years ago with new paragraph numbers starting with paragraph 1001. Thus 10 CFR Part 20 paragraph 220b does not exist. 10 CFR Part 20.2206 is the correct paragraph of reference for submitting reports of individual monitoring. The corrected markup and retype pages are enclosed.

The correction does not change the conclusion of the original LAR 02-10 that the proposed change does not involve a significant hazards consideration pursuant to the requirements of 10 CFR 50.92 and continues to meet the criteria of 10CFR 51.22(c)10 for a categorical exclusion from the requirements for an Environmental Impact Statement. Therefore, this correction to LAR 02-10 will not adversely affect or endanger the health and safety of the general public.

A-601

U.S. Nuclear Regulatory Commission NYN-03009/Page 2 Should you have any questions regarding this letter, please contact Mr. James M. Peschel, Regulatory Programs Manager, at (603) 773-7194.

Very truly yours, FPL Energy Seabrook, LLC.

Mark E. Warner Site Vice President Seabrook Station cc:

H. J. Miller, NRC Region 1 Administrator R. D. Starkey, NRC Project Manager, Project Directorate 1-2 G. T. Dentel, NRC Senior Resident Inspector Mr. Donald Bliss, Director New Hampshire Office of Emergency Management State Office Park South 107 Pleasant Street Concord, NH 03301

FPL Energy Seabrook Station SEABROOK STATION UNIT 1 FPL Energy Seabrook, LLC submits this correction to License Amendment Request 02-10 pursuant to 10CFRS0.90. The following information is enclosed in support of this License Amendment Request:

• Markup and Retype of the Proposed Change I, Mark E. Warner, Site Vice President of FPL Energy Seabrook, LLC hereby affirm that the information and statements contained within this License Amendment Request are based on facts and circumstances which are true and accurate to the best of my knowledge and belief.

Mark E. Warner Sworn and Subscribed Site Vice President before me this f day of January, 2003 S)#Notau**blic

MARKUP AND RETYPE PAGES ADMINISTRATIVE CONTROLS The Startup Report shall address each of the tests identified in the Final Safety Analysis Report and, hall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specificationc.

Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required In license condi tions based on other commitments shall be included in this report.

Startup Reports shall be submitted within: (1) 90 days following completion of the Startup Test Program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e., initial criticality, completion of Startup Test Program, and resumption or commencement of commercial operation), supplementary reports shall be submitted at least every 3 months until all three events have been completed.

ANNUAL REPORTS*

6.8.1.2 Annual Reports covering the activities of the station as described below for the previous calendar year shall be submitted prior to March 1 of each year. The initial report shall be submitted prior to March 1 of the year following initial criticality.

Reports required on an annual basis shall include:

a. A tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures greater than 100 mrem/yr and their associated man-rem exposure according to work and job functions** (e.g., reactor operations and surveillance, inservJce inspection, routine maintenance, special maintenance [describe maintenance], waste processing, and refueling).

The dose assignments to various duty functions may be estimated based on pocket dosimeter, thermoluminescent dosimeter (TLD), or film badge measurements. Small exposures totalling less than 20% of the tidividual total dose need not be accounted for. In the aggregate, at least 80% of the total whole-body dose received from external sources should be assigned to specific major work functions;

b. The results of specific activity analyses in which the primary coolant exceeded the limits of Specification.3.4.8. The following information shall be included: (1) Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded (in graphic and tabular format); (2) Results of the last isotopic analysis for radiciodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radioiodine activity was reduced to less than limit. Each result should include date and time of sampling and the radioiodine concentrations; (3) Clean-up flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (4) Graph of the 1-131 concentration (pCi/gm) and one other radio iodine isotope concentration (pCi/gm) as a function of time for the

• A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units att the station.

"**This tabulation supplements the requirements of -* 10SCFR!

SEABROOK - UNIT 1 6-15 A,1E-,JbA'e&or

ADMINISTRATIVE CONTROLS a," 7, The Startup Report shall address each of the tests identified in the Final Safety Analysis Report and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions-bnd specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report.

Startup Reports shall be submitted within: (1) 90 days following completion of the Startup Test Program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. Ifthe Startup Report does not cover all three events (i.e., initial criticality, completion of Startup Test Program, and resumption or commencement of commercial operation), supplementary reports shall be submitted at least every 3 months until all three events have been completed.

ANNUAL REPORTS*

6.8.1.2 Annual Reports covering the activities of the station as described below for the previous calendar year shall be submitted prior to March 1 of each year. The initial report shall be submitted prior to March 1 of the year following initial criticality.

Reports required on an annual basis shall include:

a. A tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures greater than 100 mrem/yr and their associated man-rem exposure according to work and job functions" (e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance [describe maintenance], waste processing, and refueling). The dose assignments to various duty functions may be estimated based on pocket dosimeter, thermoluminescent dosimeter (TLD), or film badge measurements. Small exposures totaling less than 20% of the individual total dose need not be accounted for. In the aggregate, at least 80%

of the total whole-body dose received from external sources should be assigned to specific major work functions;

b. The results of specific activity analyses in which the primary coolant exceeded the limits of Specification 3.4.8. The following information shall be included: (1)

Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded (in graphic and tabular format); (2) Results of the last isotopic analysis for radioiodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radioiodine activity was reduced to less than limit. Each result should include date and time of sampling and the radioiodine concentrations; (3) Clean-up flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (4) Graph of the 1-131 concentration (IiCilgm) and one other radio-iodine isotope concentration (pCi/gm) as a function of time for the

• A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station.

"**This tabulation supplements the requirements of 10 CFR 20.2206.

SEABROOK - UNIT I 6-15 Amendment No.