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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
,. - . _ . - _ _ _ _ _ _ - _ _ -_ _ __ _ -- _ _ _ _- _ .
ERGENCYCORECOOLINGSYSTEMS SURVtf LLANCE REDUIRE"ENT5 (Continuedi
, 2) At least once per 18 months:
CCP/SI System $f System Y1 ve Nu*Dir 1 Vaive Nu*ber
$1 881,*T St.8422A St.8616A St.88108 51 88228 51 88168
$1 8810C SI 8822C 51 8816C
$1 88100 $1 88220 51 88160
- h. By performing a flow balance test, during shutdown, following completion of modifications to the ECCS subsystems that alter the subsystem flow characteristics and verifying that:
)
i
- 1) For centrifugal charging pump lir.es, with a single pump running:
- 4) The sum of the injection line flow rates, excluding the hig t flow rate, is greater than or equal to , and i b) The total pump flow rate is less than or ecual to $60 gpe.
- 2) For safety injection pump lines, with a single pump running:
a) The zum of the cold leg injerction line flow '
rates, excluding the htgh flow rate, is greater than or equal to g,and b) The total pump flow rate is less than or equal to 675 gps.
- 3) Eer RHR pump lines, with a single pump running, the stas of the cold leg injection itne flow rates is greater than or equal to 4652. gas.
- 1. Prior to entering M00E 3 and following any maintenance or operations activ' ty which drains port ons of the system by.
venting the ECCS pump casing and acces:ible discharge piping high points.
COMANCHE PEAK . UNIT 1 3/4 5 6
][?*h0b5 P
'[
i - - --. - - .- -.
I .
ENtMfhtY CORJ COOLING $YSTEMS SURVt1LLANtt RE0UIREW[NT5 itentinued)
^2) At least once per 18 months:
CCP/51 Systas SI Svitag DhaNuscar Valve Nweber ll 641M $1.H22A s!.8416T SI M108 11 64218 SI.H168 51 4810C 51 5822C $1 8416C SI H 100 5!.48120 51 84160
- n. By performing a flow balance test, during shutdown, following completion of modiftettions to the (CC$
subsystems that alter the subsystem flow characteristics and verifying that:
- 1) For centrifugal charging pump lines, with a single pump runnings a) The swa of the injection line flow rates, excluding the highest flow rate, is greater than or equal to Q gps, and 243 b)
@ The todt 1 pump flow rats is less t an or equal Spa-
@_ For safety t.EE!3 injection pep lines, with a single pump 1) runnings a) The sus of the cold leg injection line flow rates, excluding the high ow r creat.,tha. .r i s. S f' y , ate, d isu4 b
@ L) 3Thed1 5"' pump f1w rate is less than or equal
- 3) For RHR pump lines, with a sigle pump running, the sus of the cold leg in,)w? en ine flow rates gttater thu or equal ig E45tligpe. 45'2 w
- 1. Prior to enturing MODE 3 and following my maintenuce or operatter.: activity which drains portions of the systes by venting the ECCS pump casing and accessible discharge piping high peints.
l COMANCHE PEAX - UNIT 2 3/4 5 4 MAY 9. 1991
N SE 91-126 ATTAClIMENT 2 WPT-13966 Reduced ECCS Flows - Impact on Containment Mass & Energy
WPT 13966 ET NSL-0$L 11 91 565 Westinghouse Energy Systems $ast!
"" * *" - 8 m ::
Electric Corporation September 27, 1991 Mr. W. J. Cahill, Jr., Executive Vice President S.O. No. TBX-4708 Nuclear Engineering & Operations TU Electric Company P. O. Box 1002 Ref: 1. WPT 13963 Glen Rose, Texas 76043 2. WPT-13927 TU ELECTRIC COMPANY COMANCHE PEAK STEAM ELECTRIC STATION REDUCED ECCS FLOWS - IMPACT ON CONTAINMENT MASS & ENERGY Mr. Cahill:
Per a request of Mr. Ali Tajbakhsh of your organization on September 27, 1991, and in support of Safety Evaluation SECL 91 367 transmitted via the above Reference 1, the following information is provided.
Tne revised minimum ECCS perfonnance data for Comanche Peak Units 1 and 2 was provided via Reference 2 above. This data represents ECCS ,erfonnance with the Centrifugal Charging and Intermediate Head SI pumps throttled to prevent pump runout beyond 560 gpm and 675gpm, respectively, during the cold and hot leg post accident recirculation modes of operation. Maximum ECCS performance data will not be increased as a result of this modification.
Further, there is no impact on the Comanche Peak LOCA Mass & Enargy Release Analysis because the plant is maximum Si flow limited, and therefore the revised minimum SI flows would not affect the limiting transient.
If there are any questions please contact Roy Owoc on 412 374 4037.
Very truly yours, WESTINGHOUSE ELECTRIC CORPORATION R. H. Owoc
{-
S5l J. L. Vota, Manager Comanche Peak Projects w' s- '-"'t '9 =
4 8
ENCLOSURE 3 TO TXX-91369 MARKED UP TECHNICAL SPECIFICATIONS FOR OPERATION OF COMt.NCHE PEAK UNIT 1 Wi1H REVISED ECCS FLOW BALANCE CRITERIA
l l
EMERGENCY CCDE CCOLING Sv5 TEM?
3/4.5.2 ECCS SUB'5YSTEMS - T,y ; 350 F LIMIT]NG C0t4DIT10N FOR OPEDATION 3.5.2 Too indepencent Emergency Core Cooling System (ECCS) subsystems shall be OPERABLE .ith each subsystem comprised of:
- a. One OPERABLE centrifuga'. charging pump,
- b. One OPERABLE safety injection pump,
- c. One OPERABLE RHR heat exchanger,
- d. One OPERABLE RHR pump, and
- e. An OPERABLE flow path capable of taking suction from the refueling water storage tank on a Safety injection signal ano automatically opening the containment sump suction valves during the recirculation phase of operation.
APPLICAB]LITY: MODES 1, 2, and 3*
ACTION:
- a. With one ECCS subsystem inoperable, restore 'he inoperaole subsystem 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 t least HOT STANDBv within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUT 00WN .ithin the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
- b. In the event the ECCS is actuated and inject 2 .ater into tne Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Scecification 6.9.2 ,,itnin 90 days describ-ing the circumstances of the actuation and the total accumulated actuation cycles to date. The current value of the usage factor for each affected Safety Injection no:Zle shall be provided i n this Special Report whenever its value exceeds 0.70.
- The provisions of Specifications 3.0.4 and 4.0.4 are not applicable for entry into MODE 3 for the centrifugal cnarging pumps and the safety injection pumos declared inoperaole pursuant to specification 3.5.3 provided the centrifugal charging pumps and the safety injection pumps are restored to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or prior to the temperature of one or more of the RCS cold legs exceeding 375 F whichever comes first, COMANCHE PEAK - UNIT 1 3/4 5-3
4 e- '" "
- .. 13 ? 5TIMF sb '.. CMENT5 Sb, FC se't-::em shall be cemonstrated OPERABLE:
h30
,J,' ce per 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />so 'y verifying thLt the following valves are
+
^W}fi /-- a poe.'tions with power to the valve operators removeo:
, 3 J W.01 N ot r salve Function Valve Dosition
..r , ?i.
Pi 31.k 4
.s &B 51 Pump to Hot uegs C ' . ;ec 1
B, C, O Accum. Di;; arge Open*
^2)4
~
.- 980. ' & C RHR to Cole Legs Open 6835 51 Pump to Cold Legs Open 8840 RHR to Hot Legs Closed 880G SI Pump Suction from RWST Open 8813 51 Pump Mini-Flow Valve Open
- c. Ac least one.e per 31 days by verifying that each valve (manual, oower-operated, or automatic) in the flow path that is not locked, sealeo, or otherwise secured in position, is in its correct position.
- c. By a visual inspection which verifies that nc loose detris (rags,
' rash, clothing,
, c. ) is present in the containment whicn could De t-ansrcrted to the convainment sun.p and cause restriction of the pump suctions during LOCA conditions. This visual inspection shall be performed:
- 1) For all accessible areas of the contai- ent crior to establish-ing (CNTAINMENT INTEGR:TY, and
- 2) Of the areas offected within containue"; at the comp.et'on of each coritainment entry when CONTAINMENT lNTEGRITY is established.
b d. At 'k2st once per 15 months by: -
- 1) Verifying automatic isolation and interlock action of the RHR system frun the Reactor Coolant 5ystem to ensure that; a) Witn a simulated o actual Reactor Coolant System pre:<.ure tignal greater than or_ec"al to 442 peig the interlockt prevent the valves #ron being opened, e.o t, ) With a simulated or actual Reactor Coolant Sustem pressure signal less than or equal to 750 asig the interlocks will cause the valves to automatical'y close.
" Surveillance Requirements covered in Specification 4.5.1.1.
3 l
COPANCHd ?EAK - UNIT 1 3/45-4 l
. .y Lt
,r' ' Yo , y ',
s
EMERGENCY CORE COOLING SYSTEMS w
SURVEILLANCE REQUIREMENTS (Continuea) _
- 2) A visual insper ... of the containment sump and verifying that the sobsystem suction inlets are nat restricted by debris and that the sump components (trash racks, screens, etc.) show no evidence of structural distress or abnormal corrosion.
- e. At least once per 18 months, during shutdown, by:
, 1) Verifying that each ao+omatic valve in the flow path actuates to its correct position on Safety Injection actuation test signals, and
- 2) Verifying that e- a of the following pumps start automatically upon receipt of a Safety Injection actuation test signal:
- a) Centrifugal charging pumps.
- b) Safety injection pumps, and
- j. c) RHR pumps.
- f. Bv verifyinn that each of the following pumps develops the indicated differentia pressure on recirculation flow when tested pursuant to Specification 4.0.5:
- 1) Centrifugal charging pu:ap > 2370 ps d, i
- 2) Safety injection pump 3 1440 psid, and 3' RiR pump > 170 r J.
- g. Oy verifying the correct position of each mechanical position stop for the following ECCS throttle valves:
- 1) Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following completion cf each valve stroking operation or maintenance on the valve when the ECCS suosystems are t equired to be CPERABLE, and
- 2) At least once per 18 months.
CCP'SI System Va'ive Nuhber 51 System Valve Number SI-8810A SI-8822A SI-8816A SI-8810B SI-8822B SI-6816B SI-8810C SI-8822C SI-8816C SI 88100 51-8822D SI-88160 COMANCHE PEAK - UNIT 1 3/4 5-5 1
o.
EMERGENCV CCRE ".CCLING 3r$' EMS SURVEILLANCE RE(JIREMENTS (Continuen)
- h. 3y performing a flow' balance test, during shutdown. following com-oletian.of mocifications to the ECC5 subsystems that alter tne i sucsjstem flaw characteristics and verifying that:
l .-
- 1) For centrifugal charging pumo lines, with a single pump running:
a) The sum of the injection line flow rates, excluding the righest flow . rate, is greater than or equal to M S gpm, and-gq,g w
b) The total pump flow rate is less than or equal to 560 gpm,
- 2) For safety injection pump lines, with a single pump running:
l- a) The. sum of the cold leg injection line flow rates; excluding
! tt.e nignest flow rate, is gt'*ter than or equal to gpm,
) and g' b) The total pump flow rate is less than or et,Jal to 675 gpm.
- 3) For RHR pump lines, with a single pLep unning, the sum of the colc leg injection line flow rates is - eater than or equal to L 4652 gpm.
- i. Prior to entering MOPE 3 and following a'ny raintenance or operations activity onich drains portions of the system oy unting the ECCS -
pump casing and accessible discharge piping high points.
i o
CCHANCHE PEAK ~~ UNIT 1 3/ 4 5-6
.