ML20141F239

Amend 128 to License NPF-2,changing TS 3/4.4.9 & Associated Bases to Reduce Limit Associated W/Dose Equivalent I-131

ML20141F239
Person / Time
Site:	Farley
Issue date:	05/19/1997
From:	Berkow H NRC (Affiliation Not Assigned)
To:
Shared Package
ML20141F245	List: ML20141F239 ML20141F252
References
NUDOCS 9705210251
Download: ML20141F239 (8)

Text

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• 4 UNITED STATES j

j NUCLEAR REGULATORY COMMISSION f

WASHINGTON, D.C. 2006MXIO1 1

44.....,o SOUTHERN NUCLEAR OPERATING COMPANY. INC.

l ALABAMA POWER COMPANY

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DQCKET NO. 50-348 JOSEPH M. FARLEY NUCLEAR PLANT. UNIT 1 MiENDMENT TO FACILITY OPERATING LICENSE Amendment No.128 License No. NPF-2 1.

The Nuclear Regulatory Commission (the Commission) has found that A.

The application for amendment by Southern Nuclear Operating Company, Inc. (Southern Nuclear), dated March J5, 1997, complies with the standards and requirements of the Atom:c 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, the provisions of the Act, and the rules and regulations of the Comission; 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; i

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-2 is hereby amended to read as follows:

9705210251 970519 PDR ADOCK 05000348 P

PDR

4 (2)

Technical Snecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.128, are hereby incorporated in the license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.

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'FOR THE NUCLEAR REGULATORY COMNISSION

+(

Herl>}ert N. Berkow, Director y

M./-

(W Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: May 19, 1997 i

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ATTACHMENT TO LICENSE AMENDMENT NO.

128 TO FACILITY OPERATING LICENSE NO. NPF-2

' DOCKET NO. 50-348 i

Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.

Remove Paaes Insert Paoes 3/4 4-23 3/4 4-23 3/4 4-24 3/4 4-24 3/4 4-25 3/4 4-25 3/4 4-26 3/4 4-26 B 3/4 4-5 B 3/4 4-5 1

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i REACTOR COOLANT SYSTEM 3/4.4.9 SPECIFIC ACTIVITY LIMITING CONDITION FOR OPERATION lll 3.4.9 The specific activity of the primary coolant shall be limited tot a.

Less than or equal to 0.3 microcurie per gram DOSE l

EQUIVALENT I-131; b.

Less than or equal to 100/E microcurie per gram.

APPLICABILITY:

MODES 1, 2, 3, 4, and 5 ACTION:

MODES 1, 2, and 3*:

a.

With the specific activity of the primary coolant greater than 0.3 microcurie per gram DOSE EQUIVALENT I-131 for more l

than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous time interval or exceeding the limit line shown on Figure 3.4-1, be in at least HOT STANDBY with Tavg less than 500*F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

b.

With the specific activity of the primary coolant greater than 100/E microcurie per gram, be in at least HOT STANDBY with Tavg less than 500*F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

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E*With Tavg greater than or equal to 500*F.

FARLEY-UNIT 1 3/4 4-23 AMENDMENT NO. 26 6S f66T447,128 !

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REACTOR COOLANT SYSTEN ACTION:-

(Continued)

MODES 1, 2, 3, 4, and 5:

a.

With the specific activity of the primary coolant greater than 0.3 microcurie per gram DOSE EQUIVALENT I-131 or l

greater than 100 /E microcuries per gram, perform the sampling and analysis requirements of item 4a of Table 4.4-4 until the specific activity of the primary coolant is restored to within its limits.

SURVEILLANCE REQUIREMENTS i

I I 4.4.9 The specific activity of the primary coolant shall be determined to be within the limits by performance of the sampling and analysis program of Table 4.4-4.

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FARLEY-UNIT 1 3/4 4-24 AMENDMENT NO. 26 67-f 06 f f 7 el28 T

T es

TABLE 4.4-4 PRIMARY COOLANT SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM 5

TYPE OF MEASUREMENT SAMPLE AND ANALYSIS MCDES IN WHICH SAMPLE

-Q.

AND ANALYSIS FREQUENCY AND ANALYSIS REOUIRED e

3-1.

Gross Activity Determination At least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 1, 2, 3, 4 4

2.

Isotopic Analysis for DOSE 1 per 14 days 1

EQUIVALENT I-131 Concentration 3.

Radiochemical for 5 1 Per 6 monthe*

1 Determination u1 4.

Isotopic Analysis for Iodine a) Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, 1#, 2#, 3#, 4#, 5#

Including I-131, I-133, and I-135 whenever the specific

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activity exceeds 0.3 g

pC1/ gram DOSE EQUIVALENT I-131 or 100/E pCi/ gram, and b) One sample between 2 and y

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> following a 1, 2, 3 g

THERMAL POWER change

[:1 exceeding 15 percent of the RATED THERMAL POWER within a one hour period.

1. Until the specific activity of the primary coolant system is restored within its limits.

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• Sample to be taken after a minimum of 2 EFPD and 20 days of POWER OPERATION have elapsed since reactor was last subcritical for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or longer.

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i 20 30 40 50 60 70 80 90 100 PERCENT OF PATED THERMAL ECWER FIGURE 3. 4-1 DOSE EQUIVALENT I-131 Primary Coolant Specific Activity Limit Versus Percent of RATED THERMAL POWER with the Primary Coolant Specific Activity > 0.3 pCi/ gram Dose Equivalent I-131 l

FARLEY-UNIT 1 3/4 4-26 AMENDMENT NO.26,496r447r128 1

REACTOR COOLANT SYSTEM BASES 3/4.4.8

-CHEMISTRY 1

The limitations on Reactor Coolant System chemistry ensure that corrosion of the Reactor Coolant System is minimized and reduces the potential for Reactor Coolant System leakage or failure due to stress corrosion.

Maintaining the chemistry within the Steady State Limits provides adequate corzvaion protection to ensure the structural integrity of the Reactor coolant System over the life of the plant. The associated effects of e

exceeding the oxygen, chloride, and fluoride limits are time and temperature dependent.

Corrosion studies show that operation may be continued with contaminant concentration levels in excess of the Steady State Limits, up to the Transient Limits, for the specified limited time intervals without having a significant effect on the structural integrity of the Reactor Coolant System. The time interval permitting continued operation within the restrictions of the Transient Limits provides time for taking corrective actions to restore the contaminant concentrations to within the Steady State Limits.

The surveillance requirements provide adequate assurance that concentrations in excess of the limits will be detected in sufficient time to take corrective action.

i 3/4.4.9 SPECIFIC ACTIVITY The limitations on the specific activity of the primary coolant ensure that the resulting 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> doses at the site boundary will not exceed an appropriately small fraction of Part 100 limits in the event of primary-to-secondary leakage as a result of a steamline break.

The ACTION statement permitting POWER OPERATION to continue for limited time periods with the primary coolant's specific activity greater than 0.3 microcuries/ gram DOSE EQUIVALENT I-131, but within the allowable l

limit shown on Figure 3.4-1, accommodates possible iodine spiking phenomenon which may occur following changes in THERMAL POWER.

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FARLEY-UNIT 1 B 3/4 4-5 AMENDMENT NO. 48,26,63,406 447,121 7

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