ML20081J637
| ML20081J637 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 03/20/1995 |
| From: | Bateman W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20081J640 | List: |
| References | |
| GL-93-05, GL-93-5, NUDOCS 9503280085 | |
| Download: ML20081J637 (18) | |
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k UNITED STATES I'
E NUCLEAR REGULATORY COMMISSION 3'
wasmNGTON. D.C. 20$2-0001 1
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SOUTHERN NUCLEAR OPERATING COMPANY. INC.
DOCKET NO. 50-348 JOSEPH M. FARLEY NUCLEAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE 113 Amendment No.
License No. NPF-2 i
1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Southern Nuclear Operating Company, Inc. (Southern Nuclear), dated January 9, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 (1) 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 Comission's regulations; D.
The issuance of this license amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical i
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:
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i 9503280085 950320 i
PDR ADOCK 05000348 p
PDR l
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.113, 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 C0tMISSION LYle William H. Bateman, Director Project Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 20, 1995
ATTACHMENT TO LICENSE AMENDMENT NO.11,3 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 marginal lines.
Remove Paoes Insert Paaes 3/4 1-15 3/4 1-15 3/4 3-41 3/4 3-41 3/4 5-2 3/4 5-2 3/4 6-11 3/4 6-11 3/4 6-20 3/4 6-20 3/4 10-1 3/4 10-1 l
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i EMERGENCY CORE COOLTNG SYSTEMS st'RVFH f ANCE RFotmtEMWTE (CantinnM) b.
At least once per 31 days and within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> aAer each solution volume increase of grosser than or equal to 1% of tank volume by venfymg the boron concentration of the
@is the RWST and the RWST has not been diluted since a
soures boros concentration is within the accumulator boron ana=* canon limit.
I f
At Isant once per 31 days when the RCS pressure is above the F-11 setpoint by verif/
c.
that power to each isolation valve we-is A--1ed by a locked open disconnect devios.
d.
At least once per 18 months by venfying that each accumulator isolanon valve opens l
auta-hcally under each of the following condinons:
1.
When the RCS pressure (actual or simulated) exceeds the P-11 (Pressuriser Pressure Block of Safety Injecnon) setpoint, 2.
Upon receipt of a safety injection test signal.
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' CONTAINMENT SYSTEMS i
3/4 6 2 DEPRESSL*RIZATION AND COOLING SYSTEMS l
CONTAINMENT SPRAY SYSTEM LIMITING CONDITION FOR OPERATION l
t 3.6.2.1 Two independent containment spray systems shall be OPERABLE with each spray system capable of talung sucten from the RWST and transferring suction to the containment sump.
APPLICABILITY-MODES 1,2,3 and 4.
ACTION:
4 With one contamment spray system inoperable, restore the inoperable sprey system to OPERABLE status i
walun 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore the inoperable spray I
system to OPERABLE status within the next 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in COLD SHUTDOWN wnhin the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REOUIREMENTS f
4.6.2.1 Each containment spray system shall be demonstrated OPERABLE:
At least once per 31 days by verifying that each valve (manual, power operated or a.
automatic) in the flow path that is not locked, scaled, or otherwise secured in position, is in its correct position.
b.
By verifying, that on recirculation flow, each pump develops a discharge pressure ofgreater than or equal to 210 psig when tested pursuant to Specification 4.0.5.
c.
At least once per 18 months during shutdown, by:
1.
Verifying that each automatic valve in the flow path actuates to its correct posmos l
on a Phase B test signal.
l 2.
Venfbag that each spray pump starts automatically on a Phase B test signal.
d.
At least once per 10 years by performing an air or smoke flow test through each spray header and verifying each spray noule is unobstructed.
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113 FARLEY - UNIT 1 3/4 6-11 AMENDMENT NO P
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CONTAIN\\1ENT SYSTE\\f 5 ELECTRIC HYDROGEN RECON 1BTNERS - W LIMITING CONDITION FOR OPERATION 3.6.4.2 Two independent containment hydrogen recombiner systems shall be OPERABLE.
j APPLICABILITY:
MODES I and 2.
ACT10N With orie hydrogen recombiner system inoperable, restore the inoperable system to OPERABLE status within 30 days or be in at least HOT STANDBY within ths next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEIL. LANCE REOUIREMENTS i
4.6.4.2 Each hydrogen recombiner system shall be demonstrated OPERABLE:
At least once each refueling interval by verifying during a recombiner system a.
functional test that the minimum heater sheath temperature increases to greater than or equal to 700'F within 90 minutes. Upon reaching 700*F, increase the power setting to maximum power for two minutes and verify that the power meter ren8s gree.ter than or equal to 60 KW.
b.
At least once each refueling interval by:
l Performmg a CHANNEL CALIBRATION of all recombiner instrumentation and control circuits.
2.
Verifying through a visual exammation that there is no evidence of abnormal i
conditions within the recombiners (i.e., loose wiring or structural connections, deposits of foreign matenals, etc.)
3.
Verifying the integrity of all heater electrical circuits by performmg a resistance to ground test following the above required funcoonal test. The resistance to ground for any heater phase shall be greater than or equal to 10,000 ohms.
FARLEY-UNIT 1 3/4 6-20 AMENDMENT NO,113
l l
3/410 SPECIAL TEST EXCEPTIONS 3/4101 SHLTDOWN MARGIN LIMITTNG CONDITION FOR OPERATION 3.10.1 %s SHUTDOWN MARGIN requirement ofSpecification 3.1.1.1 may be suspended for measurement of cbntrol rod worth and shutdown margin provided the reactivity equivalent to at least the highest estarnated control rod worth is available for tnp insertion from OPERABLE control rod (s).
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APPLICABILITY:
MODE 2.
ACT10N With any full length control rod r.ot fully inserted and with less than the above reactivity a.
equivalent available for trip insertion, immediately i' Sate and continue borata at greater than or equal to 7000 ppm boron or its equivalent until the SHUTDOWN MARGIN required by Specification 3.1.1.1 is restored.
b.
With all full length control rods fully inserted and the reactor suberitical by less than the above reactivity equivalent, immediately initiate and continue boration at greater than or equal to 30 spea of a solution containing greater than or equal to 7000 ppm boron or its equivalent until SHUTDOWN MARGIN required by Specification 3.1.1.1 is restored i
SURVFIT1 ANCE REOUIREMENTS 4.10.1.1 The position of c,f. Tull length rod either partially or fully withdrawn shall be deternuned at least once per 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
4.10.1.2 Each full length rod not fully inserted shall be hmtad capable of fuu insertson when i
tripped from at least the 50% withdrawn position within 7 days prior to reduems the SHIJTDOWN MARGIN to less than the limits of Speci6 cation 3.1.1.1.
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1 FARLEY-UNIT 1 3/4 10-1 AMENDMENTNO 113
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- t UNITED STATES f.
E NUCLEAR REGULATORY COMMISSION 3
f WASHINGTON, D.C. N1
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i SOUTHERN NUCLEAR OPERATING COMPANY. INC.
DOCKET NO. 50-364 JOSEPH M. FARLEY NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.1M License No. NPF-8 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Southern Nuclear Operating Company, Inc. (Southern Nuclear), dated January 9, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 Comission's regulations; D.
The issuance of this license amendment will not be inimical to the comon 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 Comission'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:
A
=
(!)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.104, are hereby incorporated in the license. Southern Nuclear shall cperate the facility in accordance with the Technical Specific.ations.
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 COPMISSION b
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4 o--
William H. Bateman, Director Project Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications l
Date of Issuance:
March 20, 1995 1
1
t ATTACHMENT TO LICENSE AMENDMENT NO. 104 r
TO FACILITY OPERATING LICENSE NO. NPF-8 f
DOCKET NO. 50-364 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 Paaes i
3/4 1-15 3/4 1-15 i
3/4 3-41 3/4 3-41 3/4 5-2 3/4 5-2 3/4 6-11 3/4 6-11 3/4 6-20 3/4 6-20 3/4 10-1 3/4 10-1 i
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REACTIVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION (Continued) b)
ne SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is determined i
at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
c)
A power distribution map is obtained froni the movable incore detectors and F (Z) and FL are verified to be within their limits withia 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and I
Q d)
De THERMAL POWER level is reduced to less than or equal to 75% of RATED THERMAL POWER within one hour and within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the l
high neutron flus trip setpoint is reduced to less than or equal to 85% of RA1ED THERMAL POWER.
SURVEILLANCE REOUIREMENTS 4.1.3.1.1 De position of each full length rod shall be determined to be within the group demand limit by verifying the individual rod positions at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> except during time 'mtervals when the Rod Position Desistion Monitor is inoperable, then verifying the group positions at least once per 4 l
hours.
t 6
i 4.1.3.1.2 Each full length rod not fully inserted in the core shall be determined to be OPERABLE by movement of at least 10 steps in any one directen at least once per 92 days.
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l AMENDMENTNO.104 FARLEY-UNIT 2 3/4115 t
m TABLE 4.3-3 k
RADIATION MONITORING INSTRUMENTATION SURVFII I ANCE REOUIREhENTS CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURYEll1ANCE INSiltVMENT CHECK CALIBRATION TEST RECUIRED u
1.
AREA MONITORS 1
a.
Fuel Searage Pool Ana l
(R-5)
S R
Q h.
Contanameest Ases(R-27A&B)
S R
N/A 1, 2, 3, 4 2.
PROCESS MONITORS a.
Fuel Storage Pool Arca wk Gaseous Activity -
wk Ventilation System l
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isolation (R-25 AAB)
S R
Q I
b.
Containniens i.
r-Activny a) Pwge and Exhaust l
isolation (R-24 AAB)
S R
Q ALL MODES b) RCSleakage Detectson i
(R-12)
S R
Q I,2,3 & 4 l
ii. Paniculaec Actsvity RCS IAakage Desecsson m
(R lI)
S R
Q I. 2,3 & 4 l
5 c.
Control Room Isolation S
R Q
- l. 2,3. 4 rad during l
nuovesment of stradiesed Aselor Z
asevesment ofleads O
overirradiesed Aset
- Wish fuel in the storage pool er besidsag.
- With irradiesed Assi le the storage pool.
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EMERGENCY CORE COOLING SYSTEMS simv; n T AN('F RFOUTREMENTE frontinnad) k b.
At least once per 31 days and within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after each solution volume increase of i
greater than or equal to 1% of tank volurne by verifying the boron concentration of the accumulator solution. This survedlance is not required when the volume increase make i
source is the AWST and the RWST has not been diluted since venfymg that the RWST boros concentration is within the accumulator boron concentration limit.
At least once per 31 days when the RCS pressure is above the P-Il setpoint by venfying c.
that power to each isolation valve operator is disconnected by a locked open discan=a device d.
At least once per 18 months by verdying that each accumulator isolation valve opens automatically under each of the following conditions:
1.
When the RCS pressure (actual or simulated) exceeds the P 11 (Pressurizer
(
Pressure Block of Safety Injection) setpoint, 2.
Upon receipt of a safety injection test signal.
a s
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FARLEY-UNIT 2 3/45-2 AMENDMENT NO.104
1 CONTAWMENT SYSTEMS a
3/4 6 2 DEPRESSURIZATION AND COOLING SYSTEMS CONTAINMENT SPRAY SYSTEM LIMITING CONDITION FOR OPERATION f
3.6.2.1 Two ind6 pendent containment spray systems shall be OPERABLE with each spray system capable of taking soction from the RWST and transferring suction to the containment sump.
APPLICABILITY:
MODES 1,2,3 and 4.
ACTION l
With one containment spray system inoperable, restore the inoperable spray system to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore the inoperable spray system to OPERABLE status within the next 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in COLD SHUTDOWN within the followmg 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
MLLANCE REOUIREMEbrlS l
4.6.2.1 Each containment spray system shall be demonstrated OPERABLE:
At least once per 31 days by verifying that each valve (manual, power operated or m.
automatic) in the flow path that is not locked, scaled, or otherwise secured in position, is in its correct position.
b.
By verifying, that on recirculation flow, each pump develops a discharge pressure of greater than or equal to 210 psig when tested pursuant to Specification 4.0.5.
c.
At least once per 18 months during shutdown, by:
1.
Verifying that each automatic valve in the flow path actuates to its correct position on a Phase B test signal.
2.
Verifying that each spray pump starts automatically on a Phase B test signal.
l d.
At least once per 10 years by performing an air or smoke flow test through each spray header and verifying each spray nozzle is unobstructed.
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FARLEY-UNIT 2 3/46-11 AMENDMENT NO. 104 L
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v.
CONTAINMENT SYSTEMS ~
' ELECTRJC HYDROGEN RECOMBINERS - W 3
LIMITING CONDmON FOR OPERATION
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3.6.4.2 Two independent comainment hydrogen recombiner systems shall be OPERABLE.
l APPLICABILfW:
MODES 1 and 2.-
l ACTION:
i With one hydrogen recombiner system inoperable, restore the inoperable system to OPERABLE status 1
I wnhin 30 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
j SURVEILLANCE REOUIREMENTS 4.6.4.2 Each hydrogen recombiner system shall be demonstrated OPERABLE:
s i
At least once each refbeling interval by verifying during a recombiner syssa a.
fbactional test that the mimmum heater sheath temperature increases to grenser than or equal to 700*F within 90 minutes. Upon reaching 700*F, increase the power
{
setting to maximum power for two minutes and wrify that the power meter supds i
greater than or equal to 60 KW.
b.
At least once each refueling interval by:
l 1.
Performing a CHANNEL CALIBRATION of all recombiner instrumentation and control circuits.
~1 2.
Verifying through a visual examination that there is no evidence of abnormal I
conditions within the recombiners (i.e., loose wiring or structural connections, deposits of foreign matenals, etc.)
j i
3.
Verifying the integrity of all heater electncal circuits by performing a i
resistance to ground test followmg the above required fbactional test.1hs
(
resistance to ground for any heater phase shall be greater than or equoi to 10,000 ohms.
I i
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FARLEY-UNIT 2 3/4 6-20 AMENDMENT NO.104 f
h
t 3/410 SPECfAL TEST EXCEPTIONS 3/4101 SHUTDOWN MARGTN I
LIMITING CONDITION FOR OPERATION i
I 3.10.1 The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 may be suspended for measurement of control rod worth and shutdown margin provided the reactivity equivalent to at least the i
hiehest estanated control rod worth is available for trip insenion from OPERABLE control rod (s).
I APPLICABILITY:
MODE 2.
ACTION:
With any fbit length control rod not blly inserted and with less than the above reactivity m.
equivalent available for trip insertion,immediately initiate and contmue boration at greater than or equal to 7000 ppm boron or its equivalue until the SHUTDOWN MARGIN required by Specification 3.1.1.1 is restored.
l b.
. With all full length control rods fully inserted and the reactor suberitical by less than the above I
reactivity equivalent, immediately inmate and continue boration at greater than or equal to 30 spa i
of a solution containing greater than or equal to 7000 ppm boron or its equivalent until the SHLfrDOWN MARGIN required by Speci6 cation 3.1.1.1 is restored.
i SURVEILLANCE REOUIREMENTS 4.10.1.1 The position of each full length red either pamally or fully withdrawn shall be determined at least once per 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
i
..t 4.10.1.2 Each full length rod not fully insened shall be demonstrated capable of fbil insertion when tripped from at least the 50% withdrawn position within 7 days prior to reducing the SHUTDOWN MARGIN to less than the limits of Specification 3.1.1.1.
F l
FARLEY-UNIT 2 3/4 10-1 AMENDMENT NO.104 l
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