|
---|
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
[-( TM w .[d.: ; - ( k,dkQ .;M. qi .f.j.,7g.gr -
_., g .
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,, , z ).;
Attachment 1 O
?
Mf ' Proposed Administrative Technical Specification Change; *
- /* .X ,
e..
" " us. c
, (; 1) Change to Hote 3 of Table 4.3-1 (Both Units 1 & 2) 49
.. N. The existing note requires that the monthly time clock for the g!
a l d: -
~t~. comparison of incore to excore axial flux differences begin when is This requirement J*
,?
Q the reactor is above 15% RATED THERMAL POWER.
not consistent with the surveillance requirements of Technical
?J ~ [5 l.' f. Specification sections 4.2.2.2.d.l(b) and 4.2.3.1.b Since which require flux mapping ;h that flux mapping be performed every 31 EFPD.
is required in order to verify incore to excore axial flux {
I( 3, differences, it is requested that all tb ;se Technical Specification g;2 p$ . ; requirements be performed every 31 EFPO. h -
This change will alleviate the administrative burden of maintaining gy jf separate schedules and the potential for duplicate flux mappino ?p solely for incore to excore axial flux difference comparisions.
]@ Reduction of this duplication of operator ef fort will allow more ,'
time and attention for more significant issues of plant operation p?
.3
'9 i and reduce wear on the movable incore detector system components. x i
3,.y a) Change to Table 3.6-1 Section A, Items 42, 43, 44 and 45 (Both N
C.
i
.+ 2) J Units 1 and 2) p[?
. e.~ ?
,.,. Recent plant modifications to implement license comitments Q f
/0' related to containment purge have been completed. As part of pi these modifications the Containment Mini-purge Isolation Valves f4 +
have been replaced with 8 inch diameter valves. The valve K .,
-1 V y
identification numbers have been changed as a result. This
$ .S. renumbering requ1res these Technical Specification Tables to be f7 revised.
M y'
gg
- . ,& .D b) Change to Table 3.6-1, Section D, 'tems 1,2,5,6 .nd 17 (Unit 1 ')
V?h only)
. ~ U. ' )
./ %.4 -l This change simply corrects the valve numbers so that the ,s.
~ J. ( proper Unit 1 prefix number is reflectad in the tables. . g.
..1y m
Change to Figure 6.2-2 (Both Units 1 & 2)
~y 3) 19 a.2 The Chemistry Supervisor Position title has 'oeen changed to d
Chemistry and Environmental Supervisor. There have not been i{ The i g.i significant responsibility changes as a result of this change. M change in title simply reflects more closely the responsibilities 7 7
i i 6
d$
onL of this position.
e
. . . . no In addition, the new position of Computer Services Supervisor has A f og been added to Figure 6.2-2. This change reflects the importance of P
, f4 ho the Computer Services function in supporting the operation of the f.l i~
' n 4x Farley Nuclear Plant. .,"
av 40 oJ i 6'~
'g.- 4) Change to Technical Specification 3.7.ll.l.c (Unit 1 only) Q MJ
- r. n ;.$
A recent review of this Technical Specification section identified D' O$
mat that the cross-references to other fire protection specifications
.1
'-N 6:- were in error. The proper cross-references are to Sections d" 3.7.11.2, 3.7.11.4 and 3.7.11.5. This corrects an administrative :i error that has existed since License Amendment 26 was issued. ;
4 [D n
%. ...,., w ,.c n A
s , ' ., _ . .
- 5. . c m. 3. . . c eg.' . $ bq.cvy 3 33 ;;:-e m j.
.g , . , , . .
V ,. .
, , , . , 7 e -
2 . . . . .q.,
. . . - .g . ,
t \
' Attachment 2
/
Praposed Changes to Technical Specification Pages Unit 1 Page 3/4 3-14 Page 3/4 6-17 Page 3/4 6-18 Page 6-3 Page 3/4 7-82 Unit 2 Page 3/4 3-14 Page 3/4 6-17 ,
Page 6-3 s
u TABLE 4.3-1 (Continued)
TABLE NOTATION With the reactor trip system breakers closed and the control rod drive system capable of rod withdr:dal.
(1). - If not performed in previous 7 days.
(2) -
Heat balance only, above 15% of RATED THERMAL POWER. Adjust channel if absolute difference greater than 2 percent.
(3) -
Compare incore to excore axial flux difference every 31 EFPD.
Recalibrate if the absolute difference is greater than or equal to 3 percent.
(4) -
Manual ESF functional input check every 18 months.
(5) -
Each train or logic channel shall be tected at least every 62 days on a STAGGERED TEST BASIS.
(6) -
Neutron detectors may be excluded from CHANNEL CALIBRATION.
(7) -
Below the P-6 (Block of Source Range Reactor Trip) setpoint.
t (8) . - Logic only,'if not performed in previous 92 days.
(9) - CHANNEL FUNCTIONAL TEST will consist of verifying that each channel indicates a turbine trip prior to latching the turbine and indicates no turbine trip after latching the turbine.
(10) - If not performed in the previous 31 days.
FARLEY-UNIT 1 3/4 3-14 AMEllDMENT N0.
l
^
TABLE 3.5-1 (Continued) ,
i is0tarianitiin E
(SEC) 5 enASE a" 150taTion FUNCTION g (Continued _
4 <10 l CCW from exc. letdoun itCOT lets
" 710 l 32. CCWW-3067 '
Accumulators fill line isolation i i 33. CVC-HV-8860 Accumulator tanks sample isolation valve 310
- 34. SS-HV-3766 Accumulator tanks sample isolation valve $10 i <10
! 35. SS- N-3334 RCOT vent line isolation valve
- 36. LWP-HV-7126 310
! RCDT vent line isolation valve $10 j 37. LWP-HV-7150 Containment sump recirculation valve -
- 38. LWP-HV-3380 .Demineralizer water to reactor W storage $10 1 <5
- 39. CTS-HV-3659 Containment purge exhaust isolation valve i _5
- 40. C8V-HV-3196 Containment purge supply isolation valve 1 41. C8V-HV-3197 Containment mini purge e.*aust isolation valve $5
- 42. C8V-HV-2867 C Containment mini purge eAhaust isolation valve $5 l w $5 l ) 43. C8V-HV-2867 D Containment mini-prge supply isolation valve
- 44. CBV-HV-2866 C Containment mini purge supply isolation valve $5
- e. .
3
.t. 45. C8V-HV-2866 D l
i w '
- 8. PHASE "B" ISOLATION
- <15 .
CCW to RCP coolers <15 1.
CCW-MOV-3052
- 2. CCW-MOV-3046
.. CCW from RCP oil coolars <10 l 3. CCW-MOV-3182 CCW from RCP THRM BARR <10
- 4. CCW-HV-3184 CCW froc RCP THRM BARR <10 .
i E 5. CCW-HV-3045 Containment instrument air supply valve 1 E 6. IA- W-3611 o '
2 C. SAFETY INJECTION SIG8pl -
[
o Charging pumps to regenerative HX
<10
<10
- 1. CVC-MDV-8107 Charging pumps to regenerative HX
- 2. CVC-MOV-8108 <15 4
SW to RCP motor air coolers <15
- 3. SW-MOV-3135 SW from RCP motor air coolers l 4. SW-MOV-3131 <15 i SW from 3CP motor air coolers
- 5. SW-MOV-3134 l
4 1 .
g a
- s TABLE 3.6-1 (Continued)
'{
f
- n
- E r- ISOLATION TIME ' h-
!Q FUNCTION (SEC) ly. 3.- MANUAL NA IQ Refueling Cavity Supply
! 1. Q1G31V012 NA
- 2. Q1G21V005*
Reactor Coolant drain tank <120 f" 3. RHR-MOV-8701A**
Reactor cootant LP IC to RHR pump 1A Reactor coolant LP 1A to RHR pump 18 <120
! 4. RHR-MOV-8702A** MA i 5. Q1P18V001" Service Air NA
- 6. Q1P18V002" Service Air NA l Containment leak rate test valve l 7. CdV-MOV-3238 7
11 A o RH RHR <17 Containment sump to RHR pump 18
- 10. RHR-MOV-8811 8 <17 Containment sump to RHR pump 1A
- 11. RHR-MOV-8812 A <17 l Containment sump to RHR pump 18 ,
'w 12. RHR-MOV-8812 8 <17 ,
CS-MOV-8826 A CS pump 1A containment sump suction isolation <17
') 13. CS pump 18 containment sump suction isolation si 14. CS-MOV-8826 8 -
<17 4
CS pump 1A containment sump suction isolation 0
- 15. CS-MOV-8827 A CS pump 18 containment sump suction isolation
<17
- 16. CS-MOV-8827 8 NA l Pressurizer pressure generator l 17. Qt813V0268* Containment post-LOCA sampling valve 1 NA
- 18. C8V-MOV-3528 A* NA l Contaiswaent post-LOCA sampling valve 2
- 19. C8V-MOV-3528 8* NA C8V-MOV-3528 C*
Conainment post-LOCA sampling valve 3
- 20. Containment post-LOCA sampling valve 4 NA
- 21. CBV-MOV-3528 D* NA a
08V-MOV-3739 A*
Containment post-LOCA sampling isolation valve
)
- 22. Containment post-LOCA sampling isolation valve NA
- 23. C8V-MOV-3739 B" NA C8V-MOV-3745 A*
Containment post-LOCA sampling return valve J
- 24. Containment post-LOCA sampling return valve NA
- 25. CBV-MOV-3745 88 NA
{k jg 26.
27.
C8V-MOV-3835 A*
C8V-MOV-3835 B*
- Containment post-LOCA sampling return valve Containment post-LOCA sampling return valve Containment post-LOCA vent isolation valve NA NA
- 28. C8V-MOV-3740" NA l ,o C8V-MOV-3530*
Containment post-LOCA vent isolation valve
! $ 29.
, E.
' ~*May be opened on an intermittent basis under administrative controls
- May be opened and power removed under administrative controls when the plant is in MODE 4 (for ensuring overpressure protection system operability).
9
___m _ _ _
Plant
% nager let Asistant 1 - Staff - Staff Plant & nager Assistant l I I I i i g I l I Operations SL mintenance Technical Adninistrative Training Sys. Perf, and l
Superintendent Superintendent Superintendent Superintendent Director Planning Super.
l I
I l l - L_T -l l I I Operations SL Supervisor lac Supervisor Nintenance Supervisor l Computer Serv.
Supervisor Technical Supervisor ll Nterials Supenisor Security Supervisor Dorasent (bn.
SupPrvisor Staff Plaming Sys. Perf.
SupPrvisor Supervisor l
lI Il
_ _ _ _ _ _J '
l.. _ I I !
Shift SL lac Nintenance l Reactor Fire Staff Searity Staff Staff Staff l Supenisor Forven Forwen Engineer Nrshall** Forsen l
g i I l Staff
- Staff Staff Staff Ojartis Plant %d. (bality (bntrol Supervisor Supervisor l
I l _
l I i l l Health Phy. Chenistry & Envirornental Staff Staff
- Shift Tectrifcal Supervisor *** Supervisor Advisor I I 1 - Senior Operator's License Staff Staff * - Reactor Operators will have Operator's License
- - Onsite Apibility for Fire Protection Progrsa Fipre 6.2-2 Facility Organization
- In rustine netters, the Health Physics Supervisor reports directly to the Technical Superintendent, in netter of radiatim policy & termination, interpretatim or iglenentation (Based toon the Health Physic Supervisor's judgnent) the Health Ptysics Supervisor rey report directly to the Assistant Plant %napr.
FARLEY - lMT 1 6-3 M O D O E 10.
s
o 1 ,, .
l PLANT SYSTEMS 1
3ftd.11FIRESUPPRESSIONSYSTEMS
-' FIRE SUPPRESSION WATER SYSTEM LIMITING CONDITION FOR OPERATION 4
I3.7.11.1 : The fire suppression . water system shall be OPERABLE with:
- a. Two' high pressure pumps, each with a capacity of 2500 gpm, with their discharge aligned .to the fire suppression header, ib. . Separate water supplies, each with_ a minimum contained volume of 250,000 gallons, and
~
- c. An OPERABLE ~ flow path capable of'taking suction from each tank and transferring the water through distribution piping with OPERABLE sectionalizing control or isolation valves to the yard hydrant curb valves, -the last valve ahead of the water flow alarm device on each sprinkler or hose standpipe, and the last valve ahead of the deluge valve on each deluge or spray system required to be OPERABLE per Specification 3.7.11.2, 3.7.11.4 and 3.7.11.5.
APPLICABILITY: At-all times.
ACTION:-
- a. With one of the above required pumps and/or water supplies inoperable, restore the inoperable equipment to OPERABLE status within 7 days or,
-in lieu of any other report required by Specification 6,9.1, prepare and submit a-Special Report to the Co;amission pursuant to Specification 6.9.2 within the next 30 days outlining the plans and
. procedures to be used to provida for the loss of redundancy _in this system. The pro' visions of Specifications 3.0.3 and 3.0.4 are not applicable. '
- b. With the fire suppression water systed otherwise inoperable:
-1. Establish a backup fire suppression water system within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and
- 2. 'In lieu of any other report required by Specification 6.9.1, submit a SpecialL Report in accordance with Specification 6.9.2:
a)~ By telephone.within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, m b)~ - Confirmed by telegraph, mailgram or facsimile transmission no 11ater than:the first working day following the event, and
-c) In writing within 14 days following the event, outlining the action taken, the cause of the inoperability and the ' plans and schedule .for restoring the system to OPERABLE status.
FARLEY-UNIT l' 3/4 7-82 AMENDMENT NO.
.e-
h t
T,ABLE 4.3-1 (Continued)
TABLE NOTATION ~~
(1). - If not performed in previous 7 days.
(2) - Heat balance only, above 15% of RATED THERMAL POWER. Adjust channel if absolute ~ difference greater than 2 percent.
(3) - Compare incore to excore axial flux difference every 31 EFPD.
Recalibrate if the absolute difference is greater than or equal to 3 percent.
(4) - - Manual ESF functional-input check every 18 months.
(5) - Each train or logic channel shall be tested at least every 62 days an a STAGGERED TEST BASIS.
(6) . Neutron detectors may be excluded from CHANNEL CALIBRATION.
(7) - Below the P-6 (Block of Source Range !;ac; tor Trip) setpoint.
(8). - Logic only, if not performed in. previous 92 days.
(9) - CHANNEL FUNCTIONAL lEST will consist of verifying that each channel indicates a turbine trip prior to latching the turbine and indicates no turbine trip after latching the turbine.
(10) If not performed in the previous 31 days.
1
'l . FARLEY-UNIT 2 3/4 3-14 AMENDMENT N0.
y '
j . .
TABLE 3.6-1 (Continued) .
m ISOLATION TIME R FUNCTION _
(SEC)
- PHASE "A" ISOLATION 1 (Continued E $10
% CCW from exc. letdown RCOT ifMS <10 u 32. CCW-HV-3067 Accumulators fill line isolation 310
- 33. CVC-HV-8860 Accumulator tanks sample isolation valve Accumulator tanks sample isolation valve 510
- 34. SS-HV-3766 <10
- 35. SS-HV-3334 RCDT vent line isolation valve 310
- 36. LWP-HV-7126 RCDT vent line isolation valve j Containment sump recirculation valve- $10 l
- 37. LWP-HV-7150 $10 1
- 38. LWP-HV-3380 Demineralizer water to reactor HD storage l Containment purge exhaust isolation valve $5
- 39. OsS-HV-3659 $5
- 40. C8V-HV-31% Containment purge supply isolation valve ' ,
Containment mini purge exhaust isolation valve $5 /
- 41. C8V-HV-3197 l
Containment mini purge exhaust isolation valve 55
- 42. CBV-HV-2867 'C $5 R 43. CBV-HV-2867 0 Containment mini purge supply isolation valve 15
^ 44. CBV-HV-2866 C Containment mini-purge supply isolation valve ,
? 45. CBV-HV-2866 0 i 0
- 8. PHASE "8" ISOLATION <15 CCW to RCP coolers <15
- 1. CCW-MOV-3052 CCW from RCP oil coolers <15
- 2. CCW-MOV-3046 CCW from RCP oil coolers <10
- 3. CCW-MOV-3182 CCW from RCP THRM BARR <10
- 4. CCW-HV-3184 CCW from RCP THRM BARR <10
- 5. CCW-HV-3045 Containment instrument air supply valve E 6. IA-HV-3611 9
9 C. SAFETY INJECTION SIGNAL
<10 w Charging pumps to regenerative HX <10 5 1. CVC-MOV-8107 Charging pumps to regenerative HX <15
- 2. CVC-MOV-8108 SW to RCP motor air coolers <15
- 3. SW-MOV-3135 SW from RCP motor air coolers <15
- 4. SW-MOV-3131 SW from RCP motor air coolers
- 5. SW-MOV-3134
r- ,y a
e Plant IUC Assistant 1 - Staff - Staff Plant knager Assistant i I I I 1 1 I
'I f I l l Assinistrative Training Sys. Perf. and Operations SL mintenance Tecmical l Superintendent Superintendent Director Planning Super.
Superintendent Superintendent l 1
l i i i- L_: -l i i i ll l Gruputer Serv. Technical mterials Security Document (bn. Staff Planning Sys. Perf.
Operations SL UC mintenance Su,e,wsor S - g{ 5 - s- l Superus- Su,erw-ll Su,erus- Su-s- Superws- Superus- Su,erus-l _____ _ _ _ _ _ _J l
i l i II mintenance Reactor Fire Staff Security Staff Staff Staff Sift i 180 l Mrshall** Forwen Supervisor Tcus
l I i i l Staff (hants Plant m d. Quality Control l Staff
- Staff Staff l Supervis- Supervisor .
~
l I I 11 1 Health Pty. Chenistry & Envirornental Staff Staff l Shift Technical-
- Supervisor *** Supervisor Advisor I I SL - Senior Operator's License Staff Staff * - React- Operators #11 have Operator's -
- -(hsite Responsibiitty for Fire IN' Figne 6.2-2 Facility Organization
- In ruutire asttm, the Health Ptysics Supervisor reports directly to the Technical Swerintendent, in retter of radiation policy determination, interpretation or t-ga'ntation (Based upon the Health Phyfc Supervisor's judpent) the Health Ptysics Supervisor ney report directly to the Assistant Plant knager.
Farley - thit 2 6-3 MlOUT M).
,.