Marked-up Revised Tech Spec 3/4 8-4 for Electrical Power SysML20126K080 |
Person / Time |
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Site: |
Farley ![Southern Nuclear icon.png](/w/images/1/14/Southern_Nuclear_icon.png) |
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Issue date: |
05/05/1981 |
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From: |
ALABAMA POWER CO. |
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To: |
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Shared Package |
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ML20126K072 |
List: |
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References |
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NUDOCS 8105110208 |
Download: ML20126K080 (6) |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217B1791999-10-0404 October 1999 Revised TS Re Control Room,Penetration Room & Containment Purge Filtration Sys & Radiation Monitoring Instrumentation, Reflecting Agreements Reached in 990909 & 16 Discussions ML20209B8161999-06-30030 June 1999 Proposed Tech Specs Chapters 3.4,3.5,3.6,3.7,4.0 & 5.0, Converting to ITS ML20196J8731999-06-30030 June 1999 Proposed Tech Specs Correcting Errors,Per 990222 TS Amend Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation ML20207D6421999-05-31031 May 1999 Proposed Conversion to ITSs for Chapter 3.3 ML20206H0001999-04-30030 April 1999 Proposed Revs to Previously Submitted Tech Specs with LAR Related to RAI on Conversion to ITS ML20206F4421999-04-30030 April 1999 Proposed Revs to Previously Submitted Tech Specs with LAR Related to RAI Re Conversion to Its,Chapter 3.8 ML20206B4721999-04-21021 April 1999 Corrected Proposed TS Pages 5.5-6,5.5-7,5.5-8 & 5.5-9, Replacing Current W Model 51 SGs with W Model 54F ML20205G8571999-04-0202 April 1999 Proposed Ts,Increasing Dei Limit from 0.15 to Uci/Gram IAW 10CFR50.90 ML20205A2401999-03-19019 March 1999 Proposed Tech Specs Table 3.3-6,re Cr,Penetration Room & Containment Purge Filtration Sys & Radiation Monitoring Instrumentation ML20207C2451999-02-22022 February 1999 Proposed TS Amends to Clarify SR Refs to ANSI N510 Sections 10,12 & 13 to ASME N510-1989,with Errata Dtd Jan 1991 & to Add Footnote Which Refs FNP FSAR for Relevant Testing of Details ML20203A7711999-02-0303 February 1999 Proposed Tech Specs Pages Re Conversion to Its,Chapter 3.4 ML20196B6241998-11-20020 November 1998 Proposed Tech Specs Pages Re Conversion to Improved TS, Chapters 3.6.& 5.0 ML20155J4561998-11-0606 November 1998 Proposed Tech Specs Re Nuclear Instrumentation Sys Power Range Daily Surveillance Requirement ML20154K2521998-10-12012 October 1998 Proposed Tech Specs Section 6,providing Recognition of Addl Mgt Positions Associated with SG Replacement Project & Providing Ability to Approve Procedures Re Project Which May Affect Nuclear Safety ML20237D4111998-08-20020 August 1998 Proposed Tech Specs Reflecting Conversion to Improved TS Re Discussion of Changes & Significant Hazards Evaluations ML20217N4801998-05-0101 May 1998 Proposed Tech Specs Bases Pages Re Safety Limits,Reactivity Control Systems & Afs ML20217Q7261998-03-20020 March 1998 Proposed Tech Specs Re Power Update Implementation,Replacing Page 6-19a ML20202G1311998-02-12012 February 1998 Proposed Tech Specs Re Pressure Temp Limits Rept ML20202F1121998-02-12012 February 1998 Revised Proposed Changes to TS Page 6-19a for Power Uprate ML20198H3661998-01-0707 January 1998 Proposed Tech Specs Pages,Adding Note to Specifically Indicate Normal or Emergency Power Supply May Be Inoperable in Modes 5 or 6 Provided That Requirements of TS 3.8.1.2 Are Satisfied ML20198E6621997-12-31031 December 1997 Proposed Tech Specs Changing Nis IR Neutron Flux Reactor Trip Setpoint & Allowable Value ML20198E3141997-12-30030 December 1997 Proposed Tech Specs Re Auxiliary Bldg & Svc Water Bldg Battery Surveillances ML20197B6691997-12-18018 December 1997 Proposed Tech Specs Pages Re 970723 TS Amend Request Associated W/Pressure Temperature Limits Rept ML20211P5861997-10-16016 October 1997 Proposed Tech Specs Pages,Revising Number of Allowable Charging Pumps Capable of Injecting in RCS When Temperature of One or More of RCS Cold Leg Temperatures Is Less than 180 F ML20211J1501997-09-30030 September 1997 Proposed Tech Specs,Correcting Page 20 of 970723 TS Amend Request to Relocate RCS Pressure & Temperature Limits from TS to Pressure & Temperature Limit Rept ML20217C0341997-09-25025 September 1997 Revised Proposed Ts,Providing Addl Info Re 970630 Submittal, Titled, Jfnp TS Change Request - Credit for B for Spent Fuel Storage ML20211A6891997-09-17017 September 1997 Proposed Tech Specs Re Primary Coolant Specific Activity ML20216D0031997-09-0303 September 1997 Proposed Tech Specs Re Moveable Incore Detector Sys ML20149K1001997-07-23023 July 1997 Proposed Tech Specs,Relocating RCS P/T Limits from TS to Proposed P/T Limits Rept IAW Guidance Provided by GL 96-03, Relocation of P/T Limit Curves & LTOP Sys Limits ML20148R7521997-06-30030 June 1997 Proposed Tech Specs,Incorporating Requirements Necessary to Change Basis for Prevention of Criticality in Fuel Storage Pool.Change Eliminates Credit for Boraflex as Neutron Absorbing Matl in Fuel Storage Pool Criticality Analysis ML20148Q1041997-06-30030 June 1997 Proposed Tech Specs,Revising & Clarifying Requirements for CR Emergency & Penetration Room Filtration Sys,Required Number of Radiation Monitoring Instrumentation Channels & Deleting Containment Purge Exhaust Filter Spec ML20148K7501997-06-13013 June 1997 Proposed Tech Specs Changing TS 3/4.9.13, Storage Pool Ventilation (Fuel Movement) ML20140A3931997-05-28028 May 1997 Proposed Tech Specs,Clarifying That Testing of Each Shared EDG to Comply W/Sr 4.8.1.1.2.e Is Only Required Once Per Five Years on a Per EDG Basis,Not on Per Unit Basis ML20148E5921997-05-27027 May 1997 Proposed Tech Specs Pages Revising Applicable Modes for Source Range Nuclear Instrumentation & Providing Allowances for an Exception to Requirements for State of Power Supplies for RHR Discharge to Charging Pump Suction Valves ML20148F2381997-05-27027 May 1997 Corrected TS Bases Page B 3/4 1-3 That Incorporates Changes from COLR & Elimination of Containment Spary Additive Sys TS Amends ML20138B9251997-04-23023 April 1997 Proposed Tech Specs,Revising TS Pages to Include Footnote Concerning Filter Pressure Drop Testing & Mechanical Heater Testing ML20137H6091997-03-25025 March 1997 Proposed Tech Specs Re Primary Coolant Specific Activity ML20136F8231997-03-0707 March 1997 Proposed Tech Specs 3/4.6.3 Re Containment Isolation Valves Surveillance Requirements ML20135C6731997-02-24024 February 1997 Proposed Tech Specs Re Surveillance Requirements of Control Room,Penetration Room & Containment Purge Filtration Systems ML20135C4941997-02-24024 February 1997 Proposed Tech Specs Re SG Tube Laser Welded Sleeves.Voltage Based Alternate Repair Criteria Is Approved Prior to Laser Welded Sleeve Amend ML20135C8641997-02-14014 February 1997 Proposed Tech Specs Revising Specified Max Power Level & Definition of Rated Thermal Power ML20134J4051997-02-0606 February 1997 Proposed Tech Specs,Providing Addl Info Re voltage-based Repair Criteria for SG Tubing ML20133G5801997-01-10010 January 1997 Proposed Tech Specs Re Generic Laser Weld Sleeving & Deleting One Cycle Implementation of L* Which Expired at Last Unit 2 Outage ML20138G9581996-12-26026 December 1996 Proposed Tech Specs Reflecting Guidance Contained in GL 95-05, SG Tube Support Plate Voltage-Based Repair Criteria, Using Revised Accident Leakage Limit of 20 Gpm & Using Probability of Detection That Is Voltage Dependent ML20134N9211996-11-18018 November 1996 Proposed Tech Specs Bases B 3/4 2-5 Re RCS Total Flow Rate Surveillance ML20134K5551996-11-15015 November 1996 Proposed Tech Specs 3.6.2.2 Re Spray Additive Sys ML20134G9601996-11-11011 November 1996 Proposed Tech Specs Amending License NPF-8 to Replace Farley Specific Laser Welded Sleeve Requirements Currently in TS W/Generic Laser Welded Sleeve Process ML20149L8991996-11-0606 November 1996 Revised Technical Specification Pages for Plant Units 1 & 2 ML20128M4821996-10-0808 October 1996 Proposed Tech Specs Reflecting Deletion of Cycle Specific L* Repair Criteria Which Expires at Start of Next Unit 2 Refueling Outage ML20128F8821996-09-30030 September 1996 Proposed Tech Specs Change Request Relocating cycle-specific Core Operating Parameter Limits to Colr.Proposed Changes Based on Guidance Found in NRC GL 88-16,WOG-90-016, NUREG-1431 & COLR Approved by NRC 1999-06-30
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217B1791999-10-0404 October 1999 Revised TS Re Control Room,Penetration Room & Containment Purge Filtration Sys & Radiation Monitoring Instrumentation, Reflecting Agreements Reached in 990909 & 16 Discussions ML20209B8161999-06-30030 June 1999 Proposed Tech Specs Chapters 3.4,3.5,3.6,3.7,4.0 & 5.0, Converting to ITS ML20196J8731999-06-30030 June 1999 Proposed Tech Specs Correcting Errors,Per 990222 TS Amend Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation ML20207D6421999-05-31031 May 1999 Proposed Conversion to ITSs for Chapter 3.3 ML20206H0001999-04-30030 April 1999 Proposed Revs to Previously Submitted Tech Specs with LAR Related to RAI on Conversion to ITS ML20206F4421999-04-30030 April 1999 Proposed Revs to Previously Submitted Tech Specs with LAR Related to RAI Re Conversion to Its,Chapter 3.8 ML20206B4721999-04-21021 April 1999 Corrected Proposed TS Pages 5.5-6,5.5-7,5.5-8 & 5.5-9, Replacing Current W Model 51 SGs with W Model 54F L-99-170, Snoc Jfnp Startup Test Rept Unit 1 Cycle 16. with1999-04-20020 April 1999 Snoc Jfnp Startup Test Rept Unit 1 Cycle 16. with ML20205S9641999-04-20020 April 1999 Snoc Jfnp Startup Test Rept Unit 1 Cycle 16. with ML20205G8571999-04-0202 April 1999 Proposed Ts,Increasing Dei Limit from 0.15 to Uci/Gram IAW 10CFR50.90 ML20205A2401999-03-19019 March 1999 Proposed Tech Specs Table 3.3-6,re Cr,Penetration Room & Containment Purge Filtration Sys & Radiation Monitoring Instrumentation ML20205A3101999-02-28028 February 1999 Analysis of Capsule Z from Alabama Power Co Jm Farley Unit 2 Reactor Vessel Radiation Surveillance Program ML20207C2451999-02-22022 February 1999 Proposed TS Amends to Clarify SR Refs to ANSI N510 Sections 10,12 & 13 to ASME N510-1989,with Errata Dtd Jan 1991 & to Add Footnote Which Refs FNP FSAR for Relevant Testing of Details ML20203A7711999-02-0303 February 1999 Proposed Tech Specs Pages Re Conversion to Its,Chapter 3.4 ML20205T0011998-12-23023 December 1998 Rev 17 to FNP-0-M-011, Odcm ML20205T0081998-12-23023 December 1998 Rev 18 to FNP-0-M-011, Odcm ML20196B6241998-11-20020 November 1998 Proposed Tech Specs Pages Re Conversion to Improved TS, Chapters 3.6.& 5.0 ML20155J4561998-11-0606 November 1998 Proposed Tech Specs Re Nuclear Instrumentation Sys Power Range Daily Surveillance Requirement ML20154K2521998-10-12012 October 1998 Proposed Tech Specs Section 6,providing Recognition of Addl Mgt Positions Associated with SG Replacement Project & Providing Ability to Approve Procedures Re Project Which May Affect Nuclear Safety ML20151V6991998-09-11011 September 1998 Snoc Jm Farley Nuclear Plant Startup Test Rept Unit 2 Cycle 13. with ML20237D4111998-08-20020 August 1998 Proposed Tech Specs Reflecting Conversion to Improved TS Re Discussion of Changes & Significant Hazards Evaluations ML20217N4801998-05-0101 May 1998 Proposed Tech Specs Bases Pages Re Safety Limits,Reactivity Control Systems & Afs ML20205S9971998-04-19019 April 1998 Rev 16 to FNP-0-M-011, Odcm ML20217Q7261998-03-20020 March 1998 Proposed Tech Specs Re Power Update Implementation,Replacing Page 6-19a ML20202G1311998-02-12012 February 1998 Proposed Tech Specs Re Pressure Temp Limits Rept ML20202F1121998-02-12012 February 1998 Revised Proposed Changes to TS Page 6-19a for Power Uprate ML20198H3661998-01-0707 January 1998 Proposed Tech Specs Pages,Adding Note to Specifically Indicate Normal or Emergency Power Supply May Be Inoperable in Modes 5 or 6 Provided That Requirements of TS 3.8.1.2 Are Satisfied ML20198E6621997-12-31031 December 1997 Proposed Tech Specs Changing Nis IR Neutron Flux Reactor Trip Setpoint & Allowable Value ML20198E3141997-12-30030 December 1997 Proposed Tech Specs Re Auxiliary Bldg & Svc Water Bldg Battery Surveillances ML20197B6691997-12-18018 December 1997 Proposed Tech Specs Pages Re 970723 TS Amend Request Associated W/Pressure Temperature Limits Rept ML20212B1791997-10-31031 October 1997 1 SG ARC Analyses in Support of Full Cycle Operation ML20211P5861997-10-16016 October 1997 Proposed Tech Specs Pages,Revising Number of Allowable Charging Pumps Capable of Injecting in RCS When Temperature of One or More of RCS Cold Leg Temperatures Is Less than 180 F ML20211J1501997-09-30030 September 1997 Proposed Tech Specs,Correcting Page 20 of 970723 TS Amend Request to Relocate RCS Pressure & Temperature Limits from TS to Pressure & Temperature Limit Rept ML20217C0341997-09-25025 September 1997 Revised Proposed Ts,Providing Addl Info Re 970630 Submittal, Titled, Jfnp TS Change Request - Credit for B for Spent Fuel Storage ML20211A6891997-09-17017 September 1997 Proposed Tech Specs Re Primary Coolant Specific Activity ML20216D0031997-09-0303 September 1997 Proposed Tech Specs Re Moveable Incore Detector Sys ML20149K1001997-07-23023 July 1997 Proposed Tech Specs,Relocating RCS P/T Limits from TS to Proposed P/T Limits Rept IAW Guidance Provided by GL 96-03, Relocation of P/T Limit Curves & LTOP Sys Limits ML20148Q1041997-06-30030 June 1997 Proposed Tech Specs,Revising & Clarifying Requirements for CR Emergency & Penetration Room Filtration Sys,Required Number of Radiation Monitoring Instrumentation Channels & Deleting Containment Purge Exhaust Filter Spec ML20148R7521997-06-30030 June 1997 Proposed Tech Specs,Incorporating Requirements Necessary to Change Basis for Prevention of Criticality in Fuel Storage Pool.Change Eliminates Credit for Boraflex as Neutron Absorbing Matl in Fuel Storage Pool Criticality Analysis ML20148K7501997-06-13013 June 1997 Proposed Tech Specs Changing TS 3/4.9.13, Storage Pool Ventilation (Fuel Movement) ML20140A3931997-05-28028 May 1997 Proposed Tech Specs,Clarifying That Testing of Each Shared EDG to Comply W/Sr 4.8.1.1.2.e Is Only Required Once Per Five Years on a Per EDG Basis,Not on Per Unit Basis ML20148F2381997-05-27027 May 1997 Corrected TS Bases Page B 3/4 1-3 That Incorporates Changes from COLR & Elimination of Containment Spary Additive Sys TS Amends ML20148E5921997-05-27027 May 1997 Proposed Tech Specs Pages Revising Applicable Modes for Source Range Nuclear Instrumentation & Providing Allowances for an Exception to Requirements for State of Power Supplies for RHR Discharge to Charging Pump Suction Valves ML20138B9251997-04-23023 April 1997 Proposed Tech Specs,Revising TS Pages to Include Footnote Concerning Filter Pressure Drop Testing & Mechanical Heater Testing ML20198T4921997-03-31031 March 1997 Small Bobbin Probe (0.640) Qualification Test Rept ML20137H6091997-03-25025 March 1997 Proposed Tech Specs Re Primary Coolant Specific Activity ML20136F8231997-03-0707 March 1997 Proposed Tech Specs 3/4.6.3 Re Containment Isolation Valves Surveillance Requirements ML20135C4941997-02-24024 February 1997 Proposed Tech Specs Re SG Tube Laser Welded Sleeves.Voltage Based Alternate Repair Criteria Is Approved Prior to Laser Welded Sleeve Amend ML20135C6731997-02-24024 February 1997 Proposed Tech Specs Re Surveillance Requirements of Control Room,Penetration Room & Containment Purge Filtration Systems ML20135C8641997-02-14014 February 1997 Proposed Tech Specs Revising Specified Max Power Level & Definition of Rated Thermal Power 1999-06-30
[Table view] |
Text
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'..x' ELECTRICAL POWER SYSTEMS ....'._,_..,__,,, 5
@) tag l , SURVElLLANCE REQUIREMENTS (Continued') ~
~
- ~ ' G. Verifying the diesel generator is aligned to provide standby
.m.
. ;'l ' power to the associated emergency busses.
- 7. . .m , .
f . J. b. At 'least once per 92 days by verifying that a sample of diesel fuel
- f. -
' :~ .._.,...._. '.. ;_ from the fuel storage tank obtained in accordance with ASTH-D270-65,.
is within the acceptable limits spec .in Table 1 of AS111 D975-74
.. wnen enecked for viscosity, water anhfiec seticent.
. ec .. . . . . . . .
G , ./ ,;.C- LAt least once per 18 months by: -
ww.e 9F ~ '
UM . : .m
- l. Subjecting the diesel to an inspection in accordance with procedures prepared in conjunction with its manufacturer's
%v Gj. , .
reccomendations for this class of standby service,
$.y 2 ~
~
- 2. Verifying the capability to reject a load of greater than or 2WP">~ ..
. equal to the largest single load associated.with that diesel Q.t ~ . l. ,.;
generator, while maintainAng voltage between 3120 and 4910 volts and speed less than or equal to 75/, of the dif ference between J '
nominal spee'd and the overspeed trip setpoint and verifying 4': ," recovery to.4160 i 420 volts and 60 i 1.2 Hz within 2 seconds. . 'l,
~
Verifying the generator capability to reject a load equal to
.. . .h_ . . ; ._ _ _ __. 3. .
ns conunuous raung vnnout tripp1ng. lne generator voltage -
s; shall not exceed 120% during and folleving the load rejection.
~
- 4. - Simulating a loss of offsite power by itself, and:
~
a) Verifying de energi2ation of the emergency u ses and load -
pp* _
[l shedding from the emerDency busses.
-- e -e ' - 'b) ' Verifying the diesel starts
"' e auto-start signal, . .
energizes the emeroency bus es with permanent 1v connected to a#
~
77..
loads withiD C 0 second's EFiergizes the auto-connected W/;
shutdown greater loads than through or equal to the load sequencer 5 minutes and operates while its generator is ' for% d,/
g
- loaded with the shutdown leeds. After energi2ation of all p,
" r!c
' ' . loads, the steady state volta 0e and frequency of the emer-gency busses shall be maintained at 4160 + 420 volts and CO a-1.D We duri ny +.h 4 :s h a s. ,
- 5. Verifying that on an Safety Injection test signal (without loss of offsite power) the diesel generator starts on the auto-start signal and operates on standby for greater than or equal to 5 minutes. The generator voltage and frequency shall be .,.
2 3952 volts and 1 57 Hz within 10 seconds after the auto start -
signal; the steady state penerator voltage and frequency shall
( ). be maintained between 4160 1 420 volts and 60 1 1.2 Hz during this test. g.,
yn,.$. _Auewridafunrwoy FM '
g rgusnao ne vasn. 2 c ic se,werp p 24.stawM,
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eg, FARLEY-UNIT 2 3/4 a-4
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8105110908
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..;b@SURVIILLANCE REQUIREHERTS ~ (Continued) !
q$m.4 ? f ". ,
>' 9.. '
. / 6.
Simulating a loss of offsite power in conjunction w th a Safety l
'.PM.3K w ((.[
Jnjection test signal, and Mry . ..EE % a)
Verifying de energization' of the emergency b sses and load ;
.S. -M.. D. . ;,. (' h.. . . . >
shedding front the emergency busses.
M.
7 ,
Am . .
W. ..R . .. . y.
- a. 4' b) . Verifying the diesel starts from ambient c dition on th ur q l euro starr. signal, energ12es the emergency busses with hE5i . I " 'w" ' . .
permanently connected loads within 10 seconds energizes ,y
< m., /
[i b'W??.U7 G the auto-connected emergency accioent) 7$$$.?4.77"T mg:n % E ,( '
load sequencer and operates for greater than or equal tothrough the M,N 5 minutes while its generator is loaded with the e:tergency y.s29
$ ,i'W?f Y,: ' ' 'I, .~ $. _ '
loads. After energization, the steady state voltage and frequency of the emergency busses shall be maintained at y N' f.c F F .,c ~ >'
Mem.tW W , a a -
. j 4160 + 420 volts and 60 + 1.2 Hz during this test.
/.
l W W .. c) Verifying that all automatic diesel generator trips, .
j
! j
.gw ~ t, except engine overspeep and generator differential and low 1hfl.b..g, .
s .
Tube oil pressure, art. automatically bypassed upon loss of Qb-W. .
O voltage on the emergency bus and/or a safety injection test signal. )
e:
W M G' . ~. ~- ,,. .
c'*:' 7. \
Im V '. '"~ '! *^sO ' Verifying the diesel generator operates for at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- During the first 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of this tent. the diesel- de norator shall
' ~~ De loaded to greater than or equal to 4474 kw for the 4075 kw
.W diesels and 3250 for the 2850 diesels and during the remaining '
MqC, 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> of this test, the diesel generator shall be loaded to QQ "s ' greater than or equal to 4075 kw for the 4075 kw diesels and l
' y '- 2850 kw for the 2850 kw diesels. Immediately after completing this 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test, perform Specification 4.8.1.1.2.c.4. The j;Q .
'g generator voltage and frequency shall be 13952 volts and 157 H2 !
within 10 seconds after the start signal; the generator voltage t.pM,' p' and frequency shall be maintained between 3120 and *1E volts hM . , . and'57 and 61.2 Hz during this test.* 4mo
- ri . . ,
" 7,:g., V. 8. Verifying that the auto-connected loads to each diesel generator T." .-
do not exceed the 2000 hour0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> rating of 4353 kw for the 4075 kw generator and 3100 kw for the 2850 kw gem rator. .
@MM -.
J.'.).
p:. v ... . 9. Verifying the diesel generator's capability to: !
gT.577~
Y:JS,-
l..~ a) Synchronize with the of fsite power source while the generator is loaded with its emergency loads upon a W+ c @.; ..'N;g... t simulated restoration of offsite power,
- '. r . , ,-.n . b) Transfer its loads to the offsite power source, and q'- ),.Q .
c) Ba restored to its standby status.
.o ,
n.. ?- - - . i.,
..g /. ~ This surveillance is not required for HODE 3 or 4.
time chanDe to plant operations prior to This is a ono initial criticality.
7l I
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M EweTyh ificm*yeuy body fe De. tut te- i>ched b 2A' ' S
.,JARLEY-UNIT '
3/4 8-5 Amendment No. 1
_ . . . - . - - l
g,g ,g Page3of$g$
These draft Technical Specification pages provide limits for -
energizing all Unit 2 related diesels. The 24 second limit for diesel 2C is based on the following:
- 1. I second delay for intermediate relay actuation and breaker (DG-13) -
trip.
- 2. Up to 1 second delay for closing of the output breaker DJ06.
- 3. 20 second time delay for bus 2J + 2 second tolerance for time relay ,
actuation.
Total : 24 Seconds r
m I
t L
A
PC4 tio. M!A Rev.-
FAR12Y lluCLEAR PLANT CN I?o. N/A Rev.
HUCLEAR SAFETY EVALUhTION CHECK LIST FSAR ChAnga N
)} ff, z,_ PDFe 4 of Mhb No . _,_ N/otice A
oo (if applicable)
(1) UNIT
' -(2) CHECK LIST APPLICANT.E TO: W4d . d C6L 2.2C2 v/c.,f 1-
..(3) SAFETY EVA10ATION - PART A * - I M_b _bd
.; . The procedure, design change or modification to which this evaluntion is n applicable represents:
,w;. (3.13 Yes A chanze to the plant as described in the FSAR?
.(3.2) Yes No . /
No A change to procedures as described in the FSAR?
(3.3) Yes No / A test or experiment not described in the FSAR?
t
- J ' (3.4) Yes g/
No A change to the plant technical specifications -
(Appendix A to the Operating License)?
. If1 t.he answer to any of the above questions is "Yes," cornplete Itum (4) and an FSAR
- . . Chonge Noti _ce_. If the answer to all_ of the nbove is "No_," omit Iten (4)and PSAR CN.
w.
i~ (4) . SAFETY EVALUATION - PART B (Justification for Part B answers cust be included on Page 2)
'2 (4.1) Yes No M '
Will the probability of an accident previously cvaluated in the FSAR be increased?
.(4.2) Yen , No' d Will the consequences of an accident previously evaluated in the PSAR be increased?
i=1 s. (4.3) Yes No _ d May the possibility of an accident which is different
.,i than any already evaluated in the FSAR be created?
-(4.4) Yes No _d Will the probability of a malfunction of equipc> ant
., _ important to safety previously e. valuated. in the YSAR-be increased?
(4.5) Yes__ no d vill the consequences of a malfunction of equipment.
important to safety previously evaluated in the FSAR be inerensed?
i; (4,6) Yes _ No liay the possibility of a malfunction of equipment
, , , important to nafety different than any already cvaluated in the FSAR be created?
(4.7) Yes tio [ Will the margin of safety as defined in the bases to
- any Technien) Specification be reduced?
~
- If the cuswer to any of the above questions is "Yes," an unreviewed safety question is involved.
r..<r) remnuc. 4Ast. k .aalimonoi pa na . r vs.concory.)
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.(7) CROUP SUP: DATE: 5"" bh __
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Au DATE: __ k l (9). FROJ REVIEW: .
{ [ f f. DATE _ ("b (10) PORC REVIDJ: DATE:
(11) 140k8 Ut:v)on _ _ _
DATE , , , , _ _
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i N11 CLEAR SAFETY EVALUATI0h! CHECK LIST 'I
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The following provides justification for answers given in Part B of the safety ,
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