|
---|
Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20211Q4981999-09-10010 September 1999 Proposed Tech Specs Clarifying Conditions of Use Re Analytical Methods Used to Determine Core Operating Limits & Adding Ref to Caldon TR for LEFM ML20211G3221999-08-26026 August 1999 Proposed Tech Specs 4.0.6 Re SG Surveillance Requirements ML20210R7091999-08-13013 August 1999 Revised Proposed Tech Specs for LAR 98-010,proposing Rev to TS Table 3.3.1-1, Rt Sys Instrumentation & TS Table B 3.3.1-1, Rt Sys Setpoints ML20209E1861999-07-0909 July 1999 Proposed Tech Specs,Adding Reactor Core Safety Limit Figures to Section 5.6.5 of Ts,Clarifying That Overpower N-16 Setpoint Remains in TS & Reflecting NRC Approval of TRs Used to Determine Core Operating Limits Presented in COLR ML20212J4251999-06-23023 June 1999 Proposed Tech Specs,Revising EDG Start Be Emergency Start Instead of Normal Start Following Loss of Offsite Power ML20195E5401999-06-0404 June 1999 Proposed Tech Specs Pages 3.2-6,3.4-24,3.4-25,3.7-23,3.7-30, 3.8-25,3.9-9,3.9-10 & 4.0-2,provided as Addl Aditorial Changes Supplementing LAR 99-001 ML20195B6461999-05-27027 May 1999 Marked-up TS Pages Re LAR 99-004,changing Plant Battery Surveillance ML20195B6771999-05-24024 May 1999 Proposed Tech Specs Relocating Parameter Limits Allows for Available Operating & Analytical Margins to Be Used in Most Efficient Manner ML20206G7111999-05-0404 May 1999 Proposed Tech Specs Revising Surveillances Associated with Plant Battery & EDGs & Miscellaneous Editorial Corrections ML20198J3171998-12-21021 December 1998 Proposed Tech Specs,Proposing Changes Administratively for Unit 1 & Increasing Licensed Power for Operation of Unit 2 to 3445 Mwt ML20198J2541998-12-18018 December 1998 Proposed Tech Specs Sections 1.0,3.1,3.3,3.4,3.6,3.7,3.9 & 5.0,converting to ITS ML20198J5211998-12-17017 December 1998 Corrected Tech Specs Pages for Section 3.8 to 971211 Submittal Re TS Conversion Application ML20197K0491998-12-11011 December 1998 Proposed Tech Specs Section 3.8, Electrical Power Systems, Converting to ITS ML20196C5361998-11-20020 November 1998 Proposed TS Converting to ITS Sections 4.0,3.4 & 3.6 ML20195F1751998-11-13013 November 1998 Proposed Tech Specs,Revising Administrative Controls Section to Include Configuration Risk Mgt Program Into CPSES TS ML20195F5291998-11-11011 November 1998 Proposed Tech Specs Revising Core Safety Limit Curves & Overtemperature N-16 Reactor Trip Setpoints for Unit 2 Cycle 5 ML20196B8811998-10-30030 October 1998 Proposed Tech Specs Section 3.3 Re Instrumentation ML20154R7861998-10-21021 October 1998 Proposed Tech Specs Section 3.7, Plant Systems ML20154S2901998-10-14014 October 1998 Proposed Tech Specs Sections 3.1,3.2,3.4,3.5 & 5.0 Re Reactivity Control Sys,Power Distribution Sys,Rcs,Eccs & Administrative Control,Respectively ML20154C9101998-10-0202 October 1998 Proposed Tech Specs 4.0.6, SG SR, Adding Definitions Required for F* Alternate Plugging Criterion & Identifies Portion of Tube Subject to Criteria ML20153E2661998-09-24024 September 1998 Proposed Improved Tech Specs Sections 3.4, RCS & 5.0, Administrative Controls ML20237E8461998-08-28028 August 1998 Proposed Tech Specs Pages Re Sections 1.0,2.0 & 3.0 of Proposed TS Changes in 980707 & s,In Response to NRC RAI ML20236J3131998-07-0101 July 1998 Revised Proposed Tech Specs Pages Re Safety Injection Signal & Blackout Signal ML20249C6101998-06-22022 June 1998 Proposed Tech Specs Section 3.6 Re Conversion Application ML20216E6291998-04-0909 April 1998 Marked-up TS Pages,Reflecting Proposed Changes in Amends to Licenses NPF-87 & NPF-89 ML20216B1471998-04-0606 April 1998 Proposed Tech Specs,Allowing Plant to Continue to Operate W/O Having to Perform Portions of SRs ML20217A3901998-03-18018 March 1998 Proposed Tech Specs Surveillance Requirements 4.8.1.1.2f.4)a) & 4.8.1.1.2f.6)a) at Power Re Enforcement Discretion ML20216H1361998-03-13013 March 1998 Proposed Tech Specs Re Electrical Systems Surveillance Requirements ML20248L3191998-03-12012 March 1998 Proposed Tech Specs TS 4.8.1.1.2f.4)b) & TS 4.8.1.1.2f.6)b) Re Request for Enforcement Discretion ML20216D6021998-03-0909 March 1998 Proposed Tech Specs Temporarily Removing Requirement to Demonstrate Load Shedding Feature of MCC XEB4-3 as Part of SRs 4.8.1.1.2f.4)a) & 4.8.1.1.2f.6)a),for Unit 2 Only ML20203K8621998-02-27027 February 1998 Proposed Tech Specs,Increasing RWST low-low Level Setpoint ML20203J5211998-02-25025 February 1998 Proposed Tech Specs Page to Remove Requirement to Demonstrate Load Shedding Feature of MCC XEB4-3 as Part of Surveillance Requirements 4.8.1.1.2f.4(a) & 4.8.1.1.2f.7(a) Until Plant Startup Subsequent to Next Refueling Outage ML20202B1641998-02-0505 February 1998 Proposed Tech Specs Bases 3/4.7.1.5 Re Main Steam Line Isolation Valves ML20212C3881997-10-24024 October 1997 Proposed Tech Specs Re Revised Core Safety Limit Curves & Revised Overtemperature N-16 Reactor Trip Setpoints ML20141G1941997-05-16016 May 1997 Proposed Tech Specs,Consisting of Change Request 97-002 Re Rev to Unit 2 Rt Setpoint ML20134B9801996-09-19019 September 1996 Proposed Tech Specs Re Inverter/Battery Charger Mod ML20116F0471996-08-0202 August 1996 Proposed Tech Specs Re Increase in Allowed Outage Time for Charging Pump from 72 H to 7 Days ML20116E8651996-07-31031 July 1996 Proposed Tech Specs Modifying Inverter/Battery Chargers by Incorporating Listed Changes Into CPSES Units 1 & 2 TSs ML20116F3711996-07-31031 July 1996 Proposed Tech Specs 6.9.1.6b Including TR, SBLOCA Analysis Methodology, in List of NRC-approved Methodologies & Rev of Unit 1 Rx Trip Setpoints ML20115E8041996-07-10010 July 1996 Proposed TS 3/4.7.11,revising Lco,Actions & SRs to Take Credit for Addition of Train Oriented Fan Coil Units for Each UPS & Distribution Room ML20115C9461996-07-0909 July 1996 Proposed Tech Specs Re Steam Line pressure-low Allowable Value ML20113B5891996-06-21021 June 1996 Proposed Tech Specs,Removing Request to Relocate MSIV Full Closure Time Requirement to Program Administratively Controlled by TS & Revising Associated Bases to Include Info to Clarify Expanded Bases Specific to CPSES ML20106G8231996-03-13013 March 1996 Proposed Tech Specs,Supplementing LAR-95-007,revising TS LCO 3.9.4 to Allow Both Doors of Personnel Airlock to Remain Open as Long as One Pal Door Capable of Being Closed ML20101C5681996-03-12012 March 1996 Proposed Tech Specs 3/4.6.1 & 6.8.3g to Implement New Containment Leakage Rate Testing Program Required by 10CFR50 App J,Option B ML20100J0791996-02-22022 February 1996 Proposed Tech Specs 3/4.9.4,revising Units 1 & 2 TS Bases Allowing Both Doors of Pal to Remain Open as Long One Pal Door Is Capable of Closing ML20096B3281996-01-0505 January 1996 Proposed TS Re Wide Range RCS Temp.-Th Remote Shutdown Indication ML20095E8311995-12-15015 December 1995 Proposed TS Bases 2.2.1,deleting Unnecessary Details Re Time Delay Requirements for Undervoltage & Underfrequency RCP Trip Setpoints ML20094N6201995-11-21021 November 1995 Proposed Tech Specs,Allowing Containment Pal Doors to Remain Open During Movement of Irradiated Fuel & During Core Alterations for Plant ML20094N9011995-11-21021 November 1995 Proposed Tech Specs,Incorporating Revised Core Safety Limit Curves & Revised N-16 Overtemp Reactor Trip Setpoints, Resulting from Reload Analyses for CPSES Unit 2,Cycle 3 ML20087L4581995-08-15015 August 1995 Proposed Tech Specs Removing Several Cycle Specific Parameter Limits & Adding Limits to COLR 1999-09-10
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211Q4981999-09-10010 September 1999 Proposed Tech Specs Clarifying Conditions of Use Re Analytical Methods Used to Determine Core Operating Limits & Adding Ref to Caldon TR for LEFM ML20211G3221999-08-26026 August 1999 Proposed Tech Specs 4.0.6 Re SG Surveillance Requirements ML20212H0771999-08-20020 August 1999 Rev 6 to CPSES Glen Rose,Tx ASME Section XI ISI Program Plan for 1st Interval on 990820. Page 119 in Unit 1 ASME Section XI of Incoming Submittal Not Included ML20212G0821999-08-20020 August 1999 Rev 4 to Augmented Inservice Insp Plan for Cpses,Unit 1 ML20210R7091999-08-13013 August 1999 Revised Proposed Tech Specs for LAR 98-010,proposing Rev to TS Table 3.3.1-1, Rt Sys Instrumentation & TS Table B 3.3.1-1, Rt Sys Setpoints ML20211M0041999-08-0505 August 1999 Rev 31 to Technical Requirements Manual ML20211G7401999-07-27027 July 1999 Revs 29 & 30 to Technical Requirements Manual (TRM) for Cpses,Units 1 & 2 ML20209E1861999-07-0909 July 1999 Proposed Tech Specs,Adding Reactor Core Safety Limit Figures to Section 5.6.5 of Ts,Clarifying That Overpower N-16 Setpoint Remains in TS & Reflecting NRC Approval of TRs Used to Determine Core Operating Limits Presented in COLR ML20212J4251999-06-23023 June 1999 Proposed Tech Specs,Revising EDG Start Be Emergency Start Instead of Normal Start Following Loss of Offsite Power ML20195E5401999-06-0404 June 1999 Proposed Tech Specs Pages 3.2-6,3.4-24,3.4-25,3.7-23,3.7-30, 3.8-25,3.9-9,3.9-10 & 4.0-2,provided as Addl Aditorial Changes Supplementing LAR 99-001 ML20195B6461999-05-27027 May 1999 Marked-up TS Pages Re LAR 99-004,changing Plant Battery Surveillance ML20195B6771999-05-24024 May 1999 Proposed Tech Specs Relocating Parameter Limits Allows for Available Operating & Analytical Margins to Be Used in Most Efficient Manner ML20206G7111999-05-0404 May 1999 Proposed Tech Specs Revising Surveillances Associated with Plant Battery & EDGs & Miscellaneous Editorial Corrections ML20206Q0311999-04-16016 April 1999 Rev 28 to CPSES Technical Requirements Manual ML20205Q1681999-04-14014 April 1999 Rev 27 to CPSES Technical Requirements Manual ML20207F3511999-02-25025 February 1999 Fire Endurance Test to Qualify Protective Envelope for Class IE Electrical Circuits ML20203B0011999-01-25025 January 1999 Rev 10 to Security Training & Qualification Plan ML20211C1071999-01-15015 January 1999 Rev 3 to ASME Section XI ISI Program Plan,Unit 2 - 1st Interval ML20198J3171998-12-21021 December 1998 Proposed Tech Specs,Proposing Changes Administratively for Unit 1 & Increasing Licensed Power for Operation of Unit 2 to 3445 Mwt ML20198J2541998-12-18018 December 1998 Proposed Tech Specs Sections 1.0,3.1,3.3,3.4,3.6,3.7,3.9 & 5.0,converting to ITS ML20198J5211998-12-17017 December 1998 Corrected Tech Specs Pages for Section 3.8 to 971211 Submittal Re TS Conversion Application ML20197K0491998-12-11011 December 1998 Proposed Tech Specs Section 3.8, Electrical Power Systems, Converting to ITS ML20196C5361998-11-20020 November 1998 Proposed TS Converting to ITS Sections 4.0,3.4 & 3.6 ML20195F1751998-11-13013 November 1998 Proposed Tech Specs,Revising Administrative Controls Section to Include Configuration Risk Mgt Program Into CPSES TS ML20195F5291998-11-11011 November 1998 Proposed Tech Specs Revising Core Safety Limit Curves & Overtemperature N-16 Reactor Trip Setpoints for Unit 2 Cycle 5 ML20196B8811998-10-30030 October 1998 Proposed Tech Specs Section 3.3 Re Instrumentation ML20154R7861998-10-21021 October 1998 Proposed Tech Specs Section 3.7, Plant Systems ML20154S2901998-10-14014 October 1998 Proposed Tech Specs Sections 3.1,3.2,3.4,3.5 & 5.0 Re Reactivity Control Sys,Power Distribution Sys,Rcs,Eccs & Administrative Control,Respectively ML20154C9101998-10-0202 October 1998 Proposed Tech Specs 4.0.6, SG SR, Adding Definitions Required for F* Alternate Plugging Criterion & Identifies Portion of Tube Subject to Criteria ML20153E2661998-09-24024 September 1998 Proposed Improved Tech Specs Sections 3.4, RCS & 5.0, Administrative Controls ML20237E8461998-08-28028 August 1998 Proposed Tech Specs Pages Re Sections 1.0,2.0 & 3.0 of Proposed TS Changes in 980707 & s,In Response to NRC RAI ML20154C4511998-07-20020 July 1998 Interim Change Request ISI-1R5-01, Unit 1 ISI Plan,Rev 5 ML20236T9931998-07-20020 July 1998 1RF06 ISI Summary Rept First Interval,Third Period,First Outage for CPSES Unit 1, Commerical Operating Date 900830 ML20236J3131998-07-0101 July 1998 Revised Proposed Tech Specs Pages Re Safety Injection Signal & Blackout Signal ML20249C6101998-06-22022 June 1998 Proposed Tech Specs Section 3.6 Re Conversion Application ML20216B2811998-04-24024 April 1998 Rev 13 to Cpses,Units 1 & 2,IST Plan for Pumps & Valves First Interval ML20216E6291998-04-0909 April 1998 Marked-up TS Pages,Reflecting Proposed Changes in Amends to Licenses NPF-87 & NPF-89 ML20216B1471998-04-0606 April 1998 Proposed Tech Specs,Allowing Plant to Continue to Operate W/O Having to Perform Portions of SRs ML20217A3901998-03-18018 March 1998 Proposed Tech Specs Surveillance Requirements 4.8.1.1.2f.4)a) & 4.8.1.1.2f.6)a) at Power Re Enforcement Discretion ML20216H1361998-03-13013 March 1998 Proposed Tech Specs Re Electrical Systems Surveillance Requirements ML20248L3191998-03-12012 March 1998 Proposed Tech Specs TS 4.8.1.1.2f.4)b) & TS 4.8.1.1.2f.6)b) Re Request for Enforcement Discretion ML20216D6021998-03-0909 March 1998 Proposed Tech Specs Temporarily Removing Requirement to Demonstrate Load Shedding Feature of MCC XEB4-3 as Part of SRs 4.8.1.1.2f.4)a) & 4.8.1.1.2f.6)a),for Unit 2 Only ML20203K8621998-02-27027 February 1998 Proposed Tech Specs,Increasing RWST low-low Level Setpoint ML20203J5211998-02-25025 February 1998 Proposed Tech Specs Page to Remove Requirement to Demonstrate Load Shedding Feature of MCC XEB4-3 as Part of Surveillance Requirements 4.8.1.1.2f.4(a) & 4.8.1.1.2f.7(a) Until Plant Startup Subsequent to Next Refueling Outage ML20203J6151998-02-24024 February 1998 Rev 26 to Technical Requirements Manual ML20217P1531998-02-12012 February 1998 Rev 2 to ISI-2R2-01, Unit 2 ISI Plan ML20202B1641998-02-0505 February 1998 Proposed Tech Specs Bases 3/4.7.1.5 Re Main Steam Line Isolation Valves ML20217P2961998-01-30030 January 1998 Rev 5 to Unit 1 ISI Program Plan ML20202E5981997-11-25025 November 1997 Rev 12 to CPSES Units 1 & 2 IST Testing Plan for Pumps & Valves,First Interval ML20212C3881997-10-24024 October 1997 Proposed Tech Specs Re Revised Core Safety Limit Curves & Revised Overtemperature N-16 Reactor Trip Setpoints 1999-09-10
[Table view] |
Text
_ .-
g.
%C 8
x JAU!I_ 1 3-I a[
oo E
api '
RIACIOR IRIP SY5ilH IN51ROMINIAl10N
[S
~
HINIHOH
- @ i.' 10IAl NO. CilANN[l 5 CilANNLi5 N APPI ICAll! I g ; .'
co j IbNCIlONAL llNil Of CilANNil5 10 l RIP OPl RAlll i HODI S ,_. ACl10N $
@d' c- 1. Hauual Reactor 1 rip 2 1 2 x- n 1, 2 1 g
OtPJ a
e -.
2 1 2 3 , 4 , 5" d d 9
@@ 2. Power Range, Neutron flux
'yorg a. Iligh Setpoint 4 2 3 1, 7 2
- 04.
O'
- b. Iow 5elpoint 4 2 0
3 1 , 2 2
- 3. Power Range, Neutron flux
- 2 3 1, 2 e fligh Positive Rate Y
" 4. Power Range, Neutron flux, 4 2 3 1, 2 2 Y
ro liinh Negative Rate
- 5. Intermediate Range, Neutron Ilux 2 1 2 l', 2 3 6 Source Range, Neutron Ilux
- a. Reactor Trip and Indication
- 1) Startup 2 b 1 2 2
- 2) Shutdom 2 1 2 3, 4 5,1
- b. 11oron Dilution I lux Doublin 2 i 3',4, 1 2 5 5.lg.2.
/. Overtemperature H-16 4 2 3 1, 21 12
- 8. Overpower N-16 4 2 3 t,2 12
- 9. Pressurizer Pressure--low 4 2 1 L 4"
- 10. Pressuriter Pressure- 88igh 4 2 3 1, 2 6 m ~ . ;
- Boron Dilution Flux Doubling requirements become effective for Unit 1 six months after criticality for Cycle 3.
.. u- .n,.- . _ . _ - - ~ w. R a- ~
- ~ -a-.. -
Attachment to TXX;92256' Page 2 of 7 7BLE 3. 3-1 (Continuec)
TA3LE NOTATIONS 3
0nly if the reactor trio creakers haccen to te in tne close: : sit 4:n an: :e Control Rod Drive System is capaele of roo witncrawal.
Below tne :-5 (:nte c eciate Range Neutro : lux :ntericck) Set:oint.
C Below the P-10 (Low 5etcoint Power Range Neutron Flux Interlock) $et:cint.
d Above the P-7 (At Power) Setpoint
'The applicable MODES and ACTION statefrents for these channels noted in Table 3.3-2 are more restrictive and therefort. applicable.
Above the P-8 (3-loop flow permissive) Setpoint.
9Above the P-7 and below the P-B Setpoints.
h The boron dilution flux doucling signals may be blocked during react 0c startu' Above the P-9 (Reactor trip on Turbine trip Interlock) Setpoint.
ACTION STATEMENTS ACTION 1 - Witn ne numcer of OPERABLE channels cre less than tne ui- u-Channels CPERABLE recuirement, restore me inoperable cnaare!
to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or - in HOT STANOBY witnin the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
ACTION 2 - Witn the number of OPERABLE channels or- less than tne Total Numbec of Channels. STARTUP and/or POWER OPERATION may pr ceec prov.ced tne following conditions are satisfied:
e The inoperable channel is placed in the tripped concition witnin 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />,
- b. The Minimum Channels OPERABLE reoutrement is met: no-ever, the inoperable channel may be bypassed for up to a nours for surveillance . testing of other channals per opecification he
. (g-:
4.3.1.1, and Either, THERMAL POWER is restricted to less than or eaual Q'yc.!~ to 75% of RATED THERMAL POWER and the Power Range Neutron Flux Trip 5etpoint is reduced to less than or equal to 85% of RATED THERMAL POWER within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; or, the QUADRANT POWER TILT RATIO is monitored at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> per S' .ci fication 4. 2. 4. 2.
n m ,
- Boron Oilution Flux Ocubling requirements becomc effective for Unit 1 six months after criticality for Cycle 3.
' n_ - _ . _ _ ww COMAhCHE PEAK
.-- Attachment'to TXX-97256 P 3 of.7 = ' I~3'1 ~t"'=}
AC' ION 5'A?i"EN'S (Contiaued)
AC':"N 3 - Wit?
ne nu?cer of cnarnels CPERASLE One less t*an the Miri tum Channels CPERABLE recuirement and ith tse THERMAL cower ievel:
- 3. Belo- ine ^-6 (Intermeciate Range Neutron *' lux [nterlock)
Setpoint, restore tie inoceraole channel to OPERABLE status orier to ;ncreasing THERMAL D0wER acove t~e P-5 3et oint, c.
Above the D-E (Intermediate Range Neutron Flux Interlock)
Setooint but below 10?. of_ RATED THERMAL POWER, restore tne inocersele channel to OPERABLE status prior to increasing THERMAL POWER above 10% of RATED THE" MAL POWER.
ACTION 4 - With the numbe: of OPERABLE channels one less than the Minimum Channels CPERABLE recuirement, suspend all operations insolving
< m -~ % positive , -
reactivity
. - rcnanges.
v - - ~. , W 'M-
,/
ACT!CN 5,1 With the numoer of CPERABLE channels one less than the Minim.m Channels CPERABLE recuirement, restore the inoperable channel
/
cmd'~ tnetoreactor CPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or within the text nour coen trip creakers susoend all coerations involving gj N
_/
positive reactivity cn ces.bnd verify either valve 1C5-3455 or s alves 1C5-6560, FCV-1118,1CS-8439,1CS-8441, and 1CS-8453 are closed and secureo in position, and verify this cositien at.
lav t enea nar la dav< t"araa'tarl Wi;b no enannels OcERABLE M,'
complete M me abo've actions within 4 nours.)snd verify tre I
( Lvwet Pt_
- positions of t.ne aoove valves at least
- nce cer la cays tne ea'te3 p
"'%U -
M f D ER M n lerar" Numcer of Channels, STARTUP and/or POWE; OPERATION may proceec proviced the following conditions are satisfied:
- a. The inoperable enannel is placed in the tripced conoition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and
- b. The Minimum Channels OTERABLE requirement is met, l muever, tne inoperable channel may be bypassed for up to a nours for surveillance testing of other channels per Specification 4.3.1.1.
i ACTION 7 - With less than the Minimum Number of Channels OPERASLE. within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> determive by ceservation of the associated permissive
" annunciator window (s) tnat the interlock is in its reovired state
- g. for the existing plant condition, or apply Specification 3.0.3.
l l NmMO &
\
- Boron Dilution Flux Ooubling requirements become effective for Unit 1 six fronths c#ter criticality for Cycle 3. '
i~
' v COMANCHE PEAK - UNIT 1 3/4 3-6 -
_J i
I
T LAttachment' to TXX-92256
, !Page'4 of?7 INSERT A ACTION 5.2* - With.the number:of OPERABLE channels one less than the-
- Minimum Channels Ol'ERABLE' requirement, restore the inopercble channel. to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or within the next hour verify either valve ICS 8455 or valves 1C5-8560, FCV-111B, 1C5-8439, 105-8441, and 105-8453 are closed and-secured in position, and verify this-position at least once per.14 days thereafter. With no channels OPERABLE, compiete the above actions within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and verify-the positions of- the above valves at least once per 14' days-thereafter.
9 :.
.v,'.' ..,s. - , . , . . , . - . - - . _ _ , __ _m -
Attachment to TXX-92256 .
Page 5 Of 7 Sx 1 AlltI_4.3-1 9
Rt ACIOR .1.R__IP_ _SYSl_l M INSil.dlHI Hl Al10N SURvt 1_1_1 ANCE RI QtilRf MINIS 17 m
- s. IRIP f.
ANALOG AC IllAI I?!G MODES IUR CilANN[ t DEVICE WillCil c CilANNil CllANNI I OPE RAl l0N','
5 OPERAI10NAL ACIUATION SURVI111ANCI
_f_ilNC s l0NAL UNI _T _Cil( CK C AI f il9.._Al lON TEST I LOGIC llSt
. --_E_ SI IS R[QUIRID
~
- 1. Manu?1 Reactor Trip N.A. N A. M. A. d d R(14) N A. 1, 2, 3 , 4 , S
?. Power Rasuge, Neutron I lux
- a. Iligh Setpoint S D(2, 4), 9 N A. NA 1 l' M( 3, 4 ),
Q(4, 6),
R(4, S) m h. low Setpoint R(4) s.
S S/U(l) N. A. P. A. I', 7
.o 3. Power Range, Neutron Ilux, N S. R(4) Q N. A. N A. 1, 2
. 'o liigh Positive Rate
- 4. Power Range, Neutron flux, N.A. R(4) Q N.A. N.A. 1, 2 liigh Negative Rate
- 5. Intermediate Range, 5 R(4, 5) C S/U(1) N.A. N.A. I 2 Neutron flux ,
- 6. Sourte Range, Neutron Ilux 5 R(4, 13) S/U(1), Q(9) R(12 N.A. 2", 3, 4, S
- 7. Overtemperature N-16 S O(2, 4 ) Q N. A. H A. 1, 2
-M(3, 4)
Q(4, 6)
R(4, S)
- 8. Overpower N-16 S D(2, 4) Q N. A. N A. !, ?
R(4, 5)
- 9. Pressurizer l'ressure--l ow S N A.
R Q(8) N. A. I "I. Pre:surizer Pressure--liigh S R Q N A. N.A. !
.u anx c. -v . - , . c -. . ' , -v . ~ , , .,
r
', w w w"',
f
- Boron Dilution Flux Dcubling requirements become effective for Unit 1 's L six months,after criticality for Cycle 3.
t
~ ~ . -
. Attachment to TXX-92256 Page 6 of 7
' ABLE 4. 3 1 (Continuec)
TABLE NOTAT!!N5 a
Oc;j 4' tae rea: tor tri: Crea<ers naccen to De in the closec ;ositi:n aro e Control ::d Drive 3) stem is caca0!e of roc witncrawal.
St ion ;-4 l te-S: r.e Rarge Neutr:n Flux nterlock) 5et:cint.
Below P-10 (LO. 5et:oint D0wer Range Neutron Flux Interlock) Sct;oin .
Above the P-7 ( At Co.er) Set 0cint.
Above the P-9 (Reactor trip on Turbine trip iderlot k) Setpoint.
(1) If not performed in or.,vious 31 days.
(2) Com arison Of calorimetric to excore power and N-16 power indication acove 15% of RATED THERMAL PCWER. Adjust excore channel and/or N-16 channel gains consistent 'ith calorimetric power if absolute difference of the rescectise channel is gr'ater tnan 2%. The provisions of Specification 4.0.4 are not acclicaole 'ci entry into MODE 1 or 2.
(. Single coint cetparison of inc0re to excore AXIAL FLUX OIFFERENCE acowe 15% of RATED THERMAL GOWER. 9ecalibrate if the absolute dif'erence is greater than or equal to 3%. For the purpose of inese surveillance ecui-etents, "M" is defined as at ' east once per 31 E:0
're :*ovisions f 3:ecification 4.0.4 are not ap' icable for entr3 -t:
MODE 1 or 2.
(4) Neutron and N-li cetectors may oe excluced from :-ANNEL CALIBRATICN.
(5) Detecter clateau curves shall be cotained and evaluated. For the
- ntertediate 4arge Neutron Flux, Power Range Neutron Flux and N-16 :narrels the :covisicrs F 3:ecification 4.0.4 are not applicable for entry int MOCE 1 or 2.
! (6) Inc:ee - Er :o e Calioration, acove 75% of RATED Tr4ERMAL POWER. :ce e pur :se of t ese surveillance requirements "Q" is cefined as at least once cer 92 E SC. The provisions of Specification 4.0.4 are not a:clic-acle for entry into MODE 1 ar 2.
(7) Eacn trate shall be tested at least every 62 days on a STAGGERED TEST BASIS.
(3) The MODES speci'iec for tnese channels in Table 4.3-2 are more restrictive ano therefore applicable.
(9) Quarteriy surveillance in MOCES2 3 , a4 , and 85 shall also incluce verifica-tion that permissises P-6 and P-10 are in their required state for exist-ing plant conditions by observation of the permissive annunciator winoow.
Quarterly surveii!ance snall include verification of the Boron Oilution Alarm Setooint of less than or e ual to an increase of twice the C0unt
,s write ithin._a 10-sim te_cet i ggy m memmmm m f
- Baron Oilution Flux Doubling requirements become effective for Unit 1 A<,
s six months after criticality for Cycle 3.
~
CCMANCHE7 fA D T SIi ~1
" A "" - - - ^^
- $tachmenttnTXX-92256 Page 7 of 7
. TsBtg a 3 ' J:or 2uecl TABLE NOTATICNS (Continuec)
( .' 3 ) Setooint verification is not acolicable.
(11) The TRIP ACTUATING DEVICE ODERATICNAL TEST snaliincepencenti f verify : e OPERABILITY trio creakers.
of the uncervoltage ano snunt trir attacnments of ine reactor
('2) at least once per 18 montns curing snutdown, seri'j tha*. on a siTulate:
Boron Dilttion Flux Coubling test signal tre_ normal CVCS discharge valves clos open. 'nc the centrifugal enarging pumos suction valves from tne RW5T (13) With the hign voltage setting varied as recommended by the manufacturer, an initial discriminator bias cueve shall be measurec for eacn cetector.
Sucsecuent ciscriminator bias curves snall De octainec, evaluated anc compared to tne initial curves.
(1A) The TRIP ACTIING OPERABILITY - DEVICE 00ERATIONAL TEST snall independently verify ne the undervoltsge Reactor Trip '~ unction. and shunt trio circui st for the Manual Bypass Breaker trip circuitThe(s).
test snall also verify the OPERABILITf of t~e (15) Ltcal manual snurt tri. prior to placing creaker in service.
(16) Attomatic undervoltage trip.
o b~
W rre
('*BoronDilutionFluxDoublingrequirementsbccomeeffectiveforUnit1 six months after criticality for Cycle 3.
y A AACv COMANCHE PEAK - UNIT 1 3/A 3-12 V