|
---|
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
. . - . - . . . - . . .. . .. - . . - . - .-. . - - . . - . . . _ . . .-. . . - . .
6 ATTACHMENT 2 TO TXX 96384 AFFECTED TECHNICAL SPECIFICATION PAGES (NUREG 1468)
" Technical Specification, CPSES Units 1 and 2" i
[Pages 3/4 7-8, Insert A Pages 1, 4, and 5,]
and Insart B Page 1]
i I
i l
l 1
l l
9606270223 960621 PDR ADOCK 05000445 P PDR
Attachment 2 to TXX-96384 Page 1 of 5 PLANT SYSTDt3 MAIN STEAM LIMF ISOLATION VAtVES LIMITING crumtTION FOR OPERATION y Fea Mssvs 3.7.1.5 Rach main steam line isolation valve (MSIVD shall be OPERA APPLICAaILITY: MODES 1. 2, and 3 EllM:
MODE 't:
STAW UD *e. next 6 h=rs ,
With one M51V i wperable but spes POWER OPERAT!0N may con nue provided 6 the inoperable talve is restored ,to 0 PEP!"f status within ours:
his mise theberoiiovins iMMUT IThy within the next 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ane in MUT SHUTnrum]r' a hoursJ ,
~
M 3 m 94_
i s With one provided"M5tVfinoperable, the nsavanan vaivants sudeeu,ent eseraties MBE 2 or 3 may in proceed 113adFclosed , otherwise, he in HOT STAM BY within the next 4 hou'rs '
a NIFI' SWTOC 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Al within the following l suavEItimeer araut_ m
- 4. 7.1.5n Each witmin ==-- ,IF M shall be demonstrated OPEMBLE by verifyt
! fu 1 losu s'vr ubestested.pursuanttoSpecification4.0.5. provis i
of spectficatten 4.8.4 are met applicable for entry inte MODE 3.
d I
I
- h bh ( OO O k%% $ $
for8cd M5tV. h i
i COMMCHE PEM - WITS 1 AM 2 3/4 T-8 i
j
~
Attachment 2 to TXX-96384 r Pdge 2 of 5' 8
-s -
aswh h fB '3.7 PLANTSYSTDtS\
( B 3.1.2 MainSteamIsolationvalves(M51Vs)]
e.
QASE5]~
A K ROUND The MSIVs isolate steam flow from the secondary side of the Ea&, pseg 3 o
Q steam generators following a high energy line break (HEL8). I
+breQ fnount Iej.,t,$n fnh' p M51V closure terminates flow from the unaffected (intact) steam generators.
,(e gegey
,g 4gg y, r a+mesekerie.
'" ' Ee dc.h hos %ce e.
M 'o^5 Wp'c.h cre. dcse,; One MSIV is located in each asin steam line outside, but close to, containment. The M51Vs are downstream from the g>ute ord epen, wfL '
pemc3 re. turn to aato pe5rhen. in steam safety valves (M55Vs) and auxiliary feedwater 6e Tro,n A w Tecon 3 -
AFW) pump turbine steam supply, to prevent M55V,[ane AFw A" solation from the steam generators by M51V closure.
cor.ke t s are c@in e d m losing the M5!Vs isolates each steam generator.from the Pac,6 hc nd 3g,j.c h others, and isolates the turhine,/ team stem, and pI other auxiliary steam supp11es from the steam rators.
., 3% g,. The MSIVs close on a main steam isolation ignal generated Pre ssum ca,,0c, p by either low steam generator pressure ich containment ro+t eW.gh pressue one ws mi casas an aan a, -nm as A rac= nan TJg L.g d' E ^'"r' jJbr'e 9m Each M51V has an M5!V bypass valvd "AliDeegh these oypass S r vai ves are rue. -s iy c ieuse, s. , . w ri ve the ng e- c' osure sianal as de their associated MEIVs. i Vs may' l vaWes em h* . ,4 u g % j dosed tr.wn 8 a'se be actuated manually. w Mor% .e,n,e eh Ne .
A description of the MEIVs is found in**#*** the 4'*F5An,~
- ',e Section 10.3] (Ref. 1). *'* g5 l er s.z,..u APPLIr.AeL E The easign easts of the MEIVs is established by the g
SAFETY ANALYSES containment analysis for the large steam line break ($LB) inside containment discussedintheFSAR,Section(5.2]
(Ref.2). It is aIse affected by the accident analysis of theSLSeventspresentedintheF54R.Section(15.1.5)
(Asf.3). The design precludes the bloudeus of more than one steam generater, assuming a single active component i failure (e.g., the fallers of one M5tv to close on demand).
The Ilmiting case for the containment analysis is the SLS inside containment, with a less of effsite peser following turhine trip, and failure of the M5IV em the effected steamj (continued) a - o diOG STX) ' (T3.7 D Gav. O, og/28/g2)
Attachment 2 to TXX-96384 Page 4 of E g gy, 3J.2 APPLICABILITY In MODE 4, nomally most of the MSIVs are closed, and the (continued) steam generator energy is low.
In MODE 5 or 6, the steam generators do not contain much energy because their temperature is below the boiling point of water; therefore, the M5!Vs are not required for isolation of potential high energy secondary system pipe i breaks in these MODES.
s ACTION ricof. I :
With one MSIV inoperable in action must be taken to restore OPERA 8tE status within rs. 5 airs to tJeMSIVcanbemadewiththeun hot. The ur !
acompletiongfies is reasonable, considering th ou probability of an accident occurring during this time period that would require a closure of the MSIVs.
The hourgospletion/les is greater than that nornelly all for containment isolation valves because the M5IVs are valves that isolate a closed system penetrating Tc g , gw3-fWs Achon containment. These valves differ from other conta<nment
""j yd isolation valves in that the closed system d e b e- additional means for containment isolation.provides an
, 4 and cwp ehen i hines Me b-es ge hd ,,g 4,e Adam M M McDES lod 3 MCM comp I eMe O' dess,ysW "hN '
to be.bodeg on a P vave u M51V cannot be restored to status within basis. When dve 15 cjecjyre,) L iours, the unit must be placed in M in which the imp e ,$M ^ " does not apply. To achieve this tus . the unit must I enFe and 6 mwfjeh h entered. 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> mewould be tirn e_ dMS - M beplacedinMODE2witkifleesareroe The M letion e, based on operating experience, to reach IWDE 2 and to close the MSIVs fs each vaWe. and sep
!5 0,.
Mgg
> la as orderly meaner and without challenging unit systems.
g[ .1 qad C y -MonEs Z M
'5
- h s i b IIste ingthatsepGatef Since the M51Vs are required to be OPERABLE in MODES 2 and 3, the inoperable M51Vs any either be restored to (continued) o a tai sis ) Cs 3.7-10 y diipv. o09/28/92h p w+ k , Pafe (4) %: 5)[
--w -- w- ,s - w ,-a- y w-r7 e1--wrw- - = w - - ee -ir-- vrw - = ew--'
Attachment 2 to TXX-96384
/~M51VsT L8 3.7.21
.o W
Me5 *1 *0 A ACTIONS (C.1 and C.ff (continued)
OPERA 8LE status or closed. When closed, the MSIVs are already in the position required by the assumptions in the safety analysis.
The Mourjompletiongime is consistent with that allowed in n-m- o.se i 4cruw .
For inoperable MSIVs that cannot be rest,ored to OPERA 8tE status within the specified gospletionJime, but are closed, the inoperable MSIVs must barverified on a periodic basis to be closed. This is necessary to ensure that the assumptions in the safety analysis remain valid. The 7 daygompletion
/Ime is reasonable, based on engineering judgmeft, in view of M51V status indications avai'able in the control room, and other administrative controls, to ensure that these ,
i valves are in the closed position. -
(b.1 w 0.27 If the M51Vs cannot be restored t OptRA8LE status or are not closed within the associated lationgime,theunit must be placed in a MODE in whi the LCO does not apply.
To achieve this status, the unit must be placed at least in MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and in MODE 4 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. The allowed gompletion /imes are reasonable, based on operating experience, to reach the required unit conditions from MODE 2 conditions in an orderly manner and without challenging unit systems. '
l 4.1.C.K , i e~.:...s.1 .. i R E 5 This SR verifies that MSIV closure infThe hueconds)
__o.+ .
on an actual or simulated actuation signal. MSEt . MT, i u n-' '~. closure n eJis assumed in the accident and containment gg- analyser. Inis Surveillance is nones 11y performed upon returning the unit to operation following a refueling outage. The M51Vs should not be tested at power, since even a part stroke exercise increases the risk of a valve closure when the unit is generating power. As the MSIVs are not tested at power, they are exempt from the ASIE Code, (continued) w srs; _ a 2.7.10 e_
a.v . o, o,ns/90
. Jh u > , kelnagtf
Attachment 2 to .TXX-96384
- , Page 3 of S
1 APPLICABLE SAFETY ANALYSES:
! The basis for the MSIV operability is derived from their assumed operation in the accident analyses of the breaks in the secondary system (principally, steamline l break). The design of the secondary system precludes the uncontrolled blowdown
- of more than one steam generator, assuming a single active component failure (e.
j g., the failure of one MSIV to close on demand). In addition, the MSIVs are credited in the analyses of the steam generator tube rupture accidents.
I in the safety analyses, several different SLB events are compared against different event acceptance limits. A double-onded guillotine SL8 at hot zero power is the limiting case with respect to the com response. The double ended guillotine SLB outside containment upstream of the MSIV is limiting for offsite dose "N" consequences, although a break in this short section of gping has a very low
=;n.. of the MSIVs in the i probability.
steam tunnels from A 1.0 ft' non-mechanistic at-power conditions is limit breakp;ing with respect to
}
j qualification in the steam tunnels. A large SLS st higher power levels is limiting with respect to maximum containment temperature used for equipment j
qualification. In the analyses of the feedwster line break and steam generator tube i
rupture accidents, the MSIVs are credited for steam generator isoletion. A i
significant failure considered for all cases is the fadure of a MSIV to close. -
^
(emd hew kWs im#m 4 te clue, on b.C The MSIVs :: :: : '; ::"z; t :"- :
- remain open during power operation [
These valves are assumed to operste under the following situatione:
4 l a.
A HEL8 (SL8 or FL8) inside containment. In order to maximize the mass and i
energy release into containment, the analyses assumes that the MSIV on the affected steam generator fails to close. For this scenario, steam is discharged into containment from all steam generators until the remaining ,
MSIVs close. After MSIV closure, steem is discharged into containment only {
from the affected steam generator and from the residual steam in the main l steam piping downstream of the closed MSIVs in the unaffected loops.
Closure of the MSIVs isolates the break from the unaffected steam generatore.
.