Text

Amends 132 & 124 to Licenses NPF-02 & NPF-08,respectively, Changing TS 3/4.4.9, Specific Activity & Associated Bases to Reduce Limit Associated W/Dose Equivalent iodine-131
	ML20198R518
Person / Time
Site:	Farley
Issue date:	10/29/1997
From:	Berkow H; NRC (Affiliation Not Assigned)
To:	;
Shared Package
ML20198R489	List: ML20198R483; ML20198R518; ML20198R522;
References
	NUDOCS 9711130301
	Download: ML20198R518 (16)
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' O ttoy g i UNITED STATES

, .g ,} NUCLEAR REGULATORY COMMISSION g '! WASHINGTON, D.c. 30ee6-0001 4 -

EOUTHERN NUCLEAR OPERATING COMPANY. INC.

ALABAMA POWER COMPANY DOCKET NO. 50 348 i

JOSEPH M. FARLEY NUCLEAR PLANT UNIT 1 AM2NDMENT TO FACIL!TY OPERATING LICENSE Amendment No.130 Lic.ense No. NPF-2

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

A. The application for amendment by Southern Nuclear Operating Company, Inc.

(Southern Nuclear), dated September 17,1997, 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; i

B. The facility will operate in conformity with the application, the provisions of the Act, and tha rules and regulations of the Commission; C. There is reasonable assurance (i) that the a:tivities authorized by this

amendment can be cor, duct *: 1 without endangering the health and safety of the 4

public, and (ii) that s,uch activities will be conducted in compliance with the t

Commission'; regulations; I

D. The issuance of this license amendment will not be inimical to the common defense and security or to tne health and safety of the public; and E. The issuance of this amendment is in w cordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2. Accordir. gly, 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:

9711130301 971029 PDR P

ADOCK 05000348 PDR

i 2

4 i (2) Technical Snecifications The Technical Specifications contained in Appendices A snd B, as revised

, through Amendment No, 132 , are hereby incorporated in the license.

I 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 ofissuance.

i 9

FOR THE NUCLEAR RFnULATORY COMMISSION

. l i /p 46W He rt N. Berkow, Director ,

Project Directorate Il 2 Division of Reactor Projects - 1/11 i Office of Nuclear Reactor Regulation

Attachment:

! Changes to the Technical Specifications l

l Date of lasuance: October 29, 1997 4

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6ITACHMr.NT TO LICENSE AMENDMENT NO 132 TO FACllITY OPERATING LICENSE NO. NPF-2 ,

QQCKET NO. 50-348 Replace the following oages of the Appendix A Technical Specifications with the enclosed

pages. The revised areas are indicated by marginallines.

I i .

i' Remove r-aoes insert Paoes

! 3/4423 3/4 4-23 i 3/4 4-24 3/4424 i 3/4 4-25 3/4 4-25 3/4 4-26 3/4426 -

i B 3/4 4-5 B 3/4 4 5

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i e REACTOR COOLANT SYSTEM 3/4.4.9 SPECIFIC ACTIVITY LIMITING CONDITION FOR OPERATION-3.4.9 The specific activity of the primary coolant shall be_?.imited tot

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a. Less than or equal to 0.3 5 microcurie per gram DOSE l EQUIVALENT I-1313

b. Less than or equal to 100/E microcurie per gram. I 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 0.15 microcurie per gram DOSE E(,UIVALENT I-131 for more l than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months during one continuous time interval or wxceeding 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 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ,

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 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

With Tavg greater tTan or equal to 500*F.

FARLEY-UNIT 1 3/4 4-23 AMENDMENT NO. 26. I3, IO6, if7, 128, 132

i a REACTOR COOLANT SYSTEM ACTION: (Continued)

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

a. With the specific activity of the primary coolant greater than 0.15 microcurie per gram DOSE EQUIVALENT I-131 or l greater than- 10 0 / E microcuries per gram, perform the sampling i

and analysis requirements of item da of Table 4.4-4 until the

specific activity of the primary coolant is restored to within-its limits.

, SURVEILIXICE REQUIREMENTS

. 4.4.9 The specific activity of the primary coolant shall be determined to

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.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. 2$, 67, f@$,

ff 7, 128, 132

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3 4 TABLE 4.4-4

, PRIMARY COOLANT SPTCIFIC ACTIVITY SAMPLE i AND ANALYSIS PROGRAM t

I

' M

$ . TYPE OF MEASUREMENT SAMPLE AND ANALYSIS MODES IN WHICH SAMPLE

, AND ANALYSIS FREQUENCY AND ANALYSIS REQUIRED 1

i C 3 1. Gross Activity Determination At least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 1, 2, 3, 4 9

w 2. Isotopic Analysis for DOSE 1 per 14 days 1 EQUIVALENT I-131 Concentration

3. Radiochemical for i 1 Per 6 months

1 Determination

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

Including I-131, I-133, and I-135 wht.never the specific i activity exceeds 0.15- p

$ pC1/ gram DOSE EQUIVALENT-

} I-131 or 100/E pC1/ gram, l and

! E b) One sample between.2 and 1, 2, 3

' 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months following a Q

g THERMAL POWER change R exceeding 15 percent of

$ the RATED THEPJtAL POWER j z within a one hour period.

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, w # Until the specific activity of the primary coolant system is restored within ita 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 !

M was last suberitical for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or longer.

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8 20 30 40 50 60 70 80 90 100 PERCENT OF RATED THERMAL POWER FIGURE 3.4-1 DOSE EQUIVALENT 1-131 Primary Coolant Specific Activity Limit Versus Percent of RATED THERMAL POWER with the Primary Coolant Specific Activity > 0.15 pCi/ gram Dose Equivalent I-131 l FARLEY-UNIT 1 3/4 4-26 AMENDMENT NO. 26, f@$, 177, 128, 132

_ REACTOR COOLANT SYSTEM RASES 3/4.4.8 CHEMISTRY The limitations on Reactor Coolant System chemistry ensure that cerrosion of the Reactor Coelant System is minimized and reduces the potential for i

d Reactor Coolant System leakage or failure due to stress corrosion.

Maintaining the chemistry within the Steady State Lindts provides adequate corrosion protection to ensure the structural integrity of the Reactor Coolant System over the life of the plant. The associated effects of eFF , ding the oxygen, Chloride, and fluoride limits are tiF9 and temperature dependent. Corrosion studies show that operat.on 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 8teady State Limits.

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

3/4.4.9 SPECIFIC ACTIVITY The lindtations on the specific activity of the primary coolant ensure that the resulting 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 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 lindted time periods with the primary coolant's specific activity greater than 0.15 microcuries/ gram DOSE EQUIVALENT I-131,-but within tne allowable l lindt shown on Figure 3.4-1, accommodates possible iodine spiking 1 phenomenon which may occur following changes in THERMAL POWER.

l

-l FARLEY-UNIT 1 B 3/4 4-5 AMENDMENT No. IS, 26, Ei, 106, if7, 128, 132 l

_ _ _ _ _ _ _ _ _ _ . ~ . - -

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\ UNITED STATES '

NUCLEAR REGULATORY COMMISSION :

WA4MINGToN, D.C. seseHem !

...*. 4 SOUTHERN NUCl EAR OPERATING COMPANY. INC. ,

ALABAMA POWER COMPANY DOCKET NO. 50-364 JOSEPH M. FARLEY NUCLEAR PL. ANT. UNIT 2 )

AMENDMENT TO FACILITY OPERATING LICENSE

. Amendment No.124 License No. NPF-8

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

A. The application for amendment by Southem Nuclear Operating Company, Inc.

(Southem Nuciaar), dated September 17,1997, 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, 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 !ssuance 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 wi'h 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 attarb 1ent to this license amendment; and paragraph 2.C.(2) of Facility Operating License No. NPF-8 is bereby amended to read as follows:

(2) Technical Soecifications

The Technical Specifications contained in Appendices A and B, as revised through Amendmont No.124. are hereby incorporated in the license. Southem Nuclear shall operate the facility in accordance with the Technical Specifications.

1

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

4 FOR THE NUCLEAR REG _ULATORY COMMISSION

- p .

1p -

e i

Herbert N. Berkow, Director Project Directorate ll 2 Division of Reactor Projects - 1/11

Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of issuance: October 29, 1997 4

-y, -.,.-p .,,,ce -

ATTACHMENT TO LICENSE AMENDMENT NO.124 TO FACILITY OPERATING LICENSE NO. NPF-8 DOCKE1 NO. 50-384 Replace the following pages of the Appendix A Technical Spt Wications with the enclosed pages. The revised areas are Indicated by marginallines.

[tamove lated 3/4 4 23 3/4423 3/4424 3/4424

, 3/4425 3/4425 3'4426 3/4426 83/445 B 3/4 4 5

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! REACTok COOLANT SYSTEM J

3/4.4.9 SPECIFIC ACTIVITY-LIMITING CONDITION FOR OPERATION i,

.S.4.9 The specific activity of -the primary coolant shall be limited tot i

j a. Less than or equal to 0.15 microcurit per gram DOSE l 1 EQV1 VALENT 1-131;

b. Less than or equal to 100/E microsNrie per gram.

i APPLICABILITY: MODES 1, 2, 3, 4 and 5 f'

ACTION:

i l MODES 1, 2 and 3*:

V l a. With the specific activity of .the primary coolant greater ;

j than0.15microcuriepergramDOSEEQUIVALENTI-131formore'l t than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months during one continuous time interval or

j exceeding the limit shown on Figure 3.4-1,' be in at least HOT ;

}

' STANDBY with Tavg less tnan 500'r within . 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

j -_. b. With the specif1c ativity of the primary coolant greater

] than 200/E microcurie per gram, be in at least HOT STANDBY j with Tavg less than 500'r within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . I T

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With T avg greater than or equal to 500*F.

, FARLEY-UNIT 2 3/4 4-23 AMENDMENT No. 54, 94, 196, p 124 1

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REACTOR C001 ANT SYSTEM ACTION (Continued)

H0 DES 1, 2, 3, 4 and 5:

a. With the specific activity of the primary coolant greater than 0.15 microcurie per gram DOSE EQUIVALENT 1-131 or greater thanl 200/I 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 wit hin its limits.

SUR',IILIANCE REQUIREMENTS 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.

FARLEY-UNIT 2 3/4 4-24 AMENDMENT No.(9, 9#, !Of, 124

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l TABLE 4.4-4 FRIMARY COOLANT SPECIFIC ACTIVITY SAMPLE q AND ANALYSIS FROGRAM _

n t*

t9 TYPE OF MEASURD4ENT SAMPLE AND ANALYSIS MODES IN WHICH SAMFLE t

7 AND ANALYSIS FREQUENCY. AND ANALYSIS REQUIRED C

h 1. Gross Activity Determ* nation At least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 1, 2, 3, 4 8

N 2. Isotopic Analysis for DOSE 1 per 14 days 1 EQUAVALDfT I-131 Concentration

3. Radiochemical for j 1 per 6 months

1 Determination s

4. Isotopic Analysis for Iodine a) Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , 18,25,35,4#,55 Including 1-131, 1-133, and 1-135 whenever the specific activity exceeds 0.15 .g PCi/ gram DOSE EQUIVALENT

'1-131 or 100/E pCi/ gram, and w

1, 2, 3 1 b) One sample between 2 and 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months following a f THERMAL FOWER change N exceeding 15 percene of

" the RATED THERMAL FOWER within a one hour period.

E a

2 S # Until the specific activity of the primary coolant system is restored within its limits.

z

sat e lto be taken after a minimum of 2 EFFD and 20 days of FOWER OPERATION have elapsed since

. reactor was last suberitical for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or longer.

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m 8 20 30 40 50 60 70 80 90 100 PERCENT OF RATED THERMAL POWER 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 > 0.15 pci/ gram Dose Equivalent I-131 l FARLEY-UNIT 2 3/4 4-26 AMENDMENT No. H , 106, 124

. e.

REACTOR C >y23 SYSTEM l

BASES e

3/4.4.8 CHEMISTRY 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 corrosion protection to ensure the structural integrity of the Reactor Coolant System over the life of the plant. The essociated effects of axceeding the oxygen, chloride and fluoride limits are time and temperature dependent. Corrosion st>Ues show that operation may be continued with containment concentrasc a lf.41m in excess of the Steady State Limits, up to the Transient Limitt, c4 thu specified limited time intervals without having a significant effect er, the structural integrity of the Reactor Coolant System. The time interval permitting continued operation within the restrictions of the Transisnt Limits provides time for taking corrective actions to restore the containment concentrations to within the Steady State Limits.

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

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

The ACTION statement perndtting POWER OPERATION to continue for limited time periods with the primary coolant's specific activity greater than 0.15 l microcuries/ gram DOSE EQUIVALENT I-131, but within the allowable limit shown on Figure 3.4-1, accommodates possible iodine spiking phenomenon which may occur following changes in THERMAL POWER.

t 4

EARLEY-UNIT 2 B 3/4 4-5 AMENDMENT No. II, 94, 106 124

ML20198R518

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