ML20206L445
| ML20206L445 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 05/10/1999 |
| From: | Emch R NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20206L451 | List: |
| References | |
| NUDOCS 9905140028 | |
| Download: ML20206L445 (16) | |
Text
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UNITED STATES eo NUCLEAR REGULATORY COMMISSION f.
WASHINGTON, D.C. 20555-0001
\\...../
SOUTHERN NUCLEAR OPERATING COMPANY. INC.
ALABAMA POWER COMPANY
- DOCKET NO. 50-348 JOSEPH M. FARLEY NUCLEAR PLANT. UNIT 1 LMENDMENT TO FACILITY OPERATING LICENSE Amendment No.142 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 April 2,1999, 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; l
4 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 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:
O 9905140028 990510 PDR ADOCK 05000348 P
q l
i l (2)
Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.142, 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.
FOR THE NUCLEAR REGULATORY COMMISSION O
Richard L. Emch, Jr., Chief, Section 1 Project Directorate 11 Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: May 10, 1999 i
IL I
ATTACHMENT TO LICENSE AMENDMENT NO.142 TO FACILITY OPERATING LICENSE NO. NPF-2 DOCKET NO. 50-348 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginallines.
Remove Paaes insert Paaes
~ 3/4 4 23 3/4 4-23
~ /4 4-24~
3/4 4-24 3
l 3/4 4-25 3/4425 3/4 4-26 3/4 4-26 B 3/4 4-5 B 3/4 4-5 i
5 i
U 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 limited to:
a.
Less than or equal to 0.30 microcurie per gram DOSE l
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*:
With the specific activity of the primary coolant greater than a.
0.30 microcurie per gram DOSE EQUIVALENT I-131 for more than 48 l hours during one continuous time interval or exceeding the limit line shown on Figure 3.4-1, be in at least HOT STANDBY with T.ve 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 Tav, 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 />.
- With Tevo greater than or equal to 500*F.
FARLEY-UNIT 1 3/4 4-23 AMENDMENT NO. 26/67/IN6/II7, I28,I32,142 f
I
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l REACTOR COOLANT SYSTEM ACTION:
(Continued)
MODES 1, 2, 3,
4, and 5:
a.
With the specific activity of the pritnary coolant greater than 0.30 microcurie per gram DOSE EQUIVALENT I-131 or greater than l
10 0 / 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 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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1 PERCENT OF PATED THEPMAL POWER
[
FIGURE 3.4-1 i
l 7
DOSE EQUIVALENT I-131 Primary Coolant Specific Activity Limit Versus l
Percent of RATED THERMAL POWER with the Primary Coolant Specific l
Activity > 0.30 Ci/ gram Dose Equivalent I-131 l
FARLEY-UNIT 1 3/4 4-26 AMENDMENT NO. 26/106/ff N f28, 132,142 i
p
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^ REACTOR COOLANT SYSTEM-BASES 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 Steacy State Limits provides adequate corrosion protection to ensure the structural integrity of the Reactor Coolant System over the life of the plant. The associated effects of 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.
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 0.30 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.
EARLEY-UNIT 1 B 3/4 4-5 AMENDMENT NO. IS/26/$3/f06/ff/,
128/132, 142 t -.,. -
stou y*
4 UNITED STATES l
g
,j NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 20555 6 1 1
SOUTHERN NUCLEAR OPERATING COMPANY. INC.
ALABAMA POWER COMPANY DOCKET NO. 50-364 JOSEPH M. FARLEY NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.134 License No. NPF-8 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Southern Nuclear Operating Company, Inc.
(Southern Nuclear), dated April 2,1999, complies with the standards and i
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 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 8 is hereby amended to read as follows:
p l
2 l
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.134, are hereby incorporated in the license. Southern l
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.
FOR THE NUCLEAR REGULATORY COMMISSION
^
/
Richard L. Emch, Jr., Chief, Section 1 Project Directorate !!
Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications i
Date of issuance:
May 10, 1999 I
l l
ATTACHMENT TO LICENSE AMENDMENT NO.134 l
l TO FACILITY OPERATING LICENSE NO. NPF 8 1-l DOCKET NO. 50-364 l
l Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
l Remove Insert 3/4423.
3/4 4-23 3/4424 3/4 4-24 3/4425 3/4 4-25 3/4426 3/4 4-26 B 3/4 4-5 B 3/4 4 5
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 limited to:
a.
Less than or equal to 0.30 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 0.30 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 shown on Figure 3.4-1, be in at least HOT STANDBY with T 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 />.
avg 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 />.
t
- With T greater than or equal to '500'F.
avg FARLEY-UNIT 2 3/4 4-23 AMENDMENT NO. 5d/9#ff06/f24,134
REACTOR COOLANT SYSTEM ACTION:
(Continued)
. MODES 1, 2, 3,
4 and 5:
With the specific activity of the primary coolant greater than a.
0.30 microcurie per gram DOSE EQUIVALENT I-131 or greater than l
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 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.
.EARLEY-UNIT 2 3/4 4-24 AMENDMENT NO. 49/94/106/124,134
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PERCENT OF iGTED THERMAL POWER FIGURE 3.4-1 l
DOSE EQUIVALENT I-131 Primary Coolant Specific Activity Limit Versus Percent of RATED THERMAL POWER with the Primary Coolant Specific Activity > 0.30 C1/ gram Dose Equivalent I-131 l
FARLEY-UNIT 2 3/4 4-26 AMENDMENT No. M/106/f8,134
r~.
r REACTOR COOLANT SYSTEM BASES 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 associated effects of exceeding the oxygen, chloride and fluoride limits are time and temperature dependent.
Corrosion studies show that operation may be continued with containment 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 containment 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.
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 steam line break.
The ACTION statement permitting POWER OPERATION to continue for limited time periods with the primary coolant's specific activity greater than 0.30 l
)
microcuries/ gram DOSE EQUIVALENT I-131, but within the allowable limit l
shown on Figure 3.4-1, accommodates possible iodine spiking phenomenon which may occur following changes in THERMAL POWER.
l AMENDMENT NO.$((f4/f@$
EARLEY-UNIT 2-B 3/4 4-5 l
i-