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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20211E7151999-08-20020 August 1999 Proposed Tech Specs,Incorporating Many Generic Improvements Agreed Upon Between Industry & NRC Since GGNS Conversion to ITS ML20196K0831999-06-29029 June 1999 Proposed Tech Specs Page 3.4-3,reflecting Implementation of BWROG Enhanced Option I-A,reactor Stability long-term Solution ML20196G7131999-06-23023 June 1999 Proposed Tech Specs Revising TS Associated with Various Esfss Which Need No Longer Be Credited Following Design Basis Fuel Handling Accident ML20206K5361999-05-0606 May 1999 Proposed Tech Specs Pages,Changing SLMCPR ML20206R9351999-01-12012 January 1999 Proposed Tech Specs Re Refueling Equipment Interlocks Required Actions ML20154Q4511998-10-16016 October 1998 TS Bases Update for Period of 970410 Through 981015 ML20236T1661998-07-20020 July 1998 Proposed Tech Specs 3.2.4,3.3.1.1,3.3.1.3,3.4.1,5.6.5, B 3.2.4,B 3.3.1.1,B 3.3.1.3 & B 3.4.1,enabling Full Implementation of Enhanced Option I-A Long Term Solution to Address Neutronic/Thermal Hydraulic Instability Issue ML20198J3581998-01-0909 January 1998 Proposed Tech Specs,Providing Certain Clarifications to Amend & Adding Restriction to Allowed Interval Extensoions ML20198N3941997-10-28028 October 1997 Proposed Tech Specs Implementing Option B & Ref SE Issued by NRR for Ggns'S App J Exemption as Implementing Document for performance-based Leakage Testing Program ML20211M8481997-10-0606 October 1997 Proposed Tech Specs Replacement Bases Pages Associated W/Proposed Amend to License Re Response Time Testing ML20210V5581997-09-18018 September 1997 Proposed Tech Specs Reflecting Decrease of Two Recirculation Loop SLMCPR Limit to 1.11 & Single Recirculation Loop SLMCPR Limit to 1.12 ML20210H0871997-08-0606 August 1997 Proposed Tech Specs Changing TS 3.8.1, AC Sources Operating. Removal of Accelerated Testing Requirements for Standby DGs as Advised by GL 94-01 ML20141A1681997-05-0707 May 1997 Proposed Tech Specs Re Eliminating Selected Response Time Testing Requirements ML20140E3211997-04-18018 April 1997 Proposed Tech Specs,Revising TS Bases to Include Changes Made Since Rev 1 Was Sent to NRC 960201 ML20134N7841996-11-21021 November 1996 Proposed Tech Specs Pp 5.0-20 & 5.0-21,revised by Adding Footnote Indicating Proposed Change Applicable Only for Cycle 9 ML20134N7611996-11-20020 November 1996 Proposed Tech Specs Re MCPR Limits for Two Recirculation Loop Operation ML20134E1261996-10-22022 October 1996 Proposed Tech Specs Revising TS Figure 3.4.11-1, Minimum Reactor Vessel Metal Temperature Vs Reactor Vessel Procedure, Curves Using Methodology of NRC Reg Guide 1.99, Rev 2, Radiation Embrittlement of Reactor Vessel Matls ML20128M5681996-10-0909 October 1996 Proposed Tech Specs 3.8.1.14 Re Surveillance Requirements ML20117P4461996-09-19019 September 1996 Proposed Tech Specs Re Containment Purge Valves W/Resilient Seals on Performance Based Leakage Testing Frequency ML20117M7021996-09-0505 September 1996 Proposed Tech Specs Re Min Critical Power Safety Limit ML20117G6781996-08-27027 August 1996 Proposed Tech Specs Re Surveillance Requirements for Safety/Relief Valves ML20116F0211996-07-31031 July 1996 Proposed Tech Specs Required to Support Cycle 9,reload 8 ML20113B7381996-06-20020 June 1996 Proposed Tech Specs,Redefining Secondary Containment Boundary to Allow Encl Bldg to Be Inoperable During Upcoming Refueling Outage ML20117L2581996-06-0404 June 1996 Proposed Tech Specs Re Replacement Page for Ltr RBG-42764, Proposed Tech Specs 3.9.1 Re Refueling Equipment Interlocks1996-05-31031 May 1996 Proposed Tech Specs 3.9.1 Re Refueling Equipment Interlocks ML20117F4661996-05-0909 May 1996 Proposed Tech Specs,Modifying SRV Surveillance Test for Relief Mode of Operation ML20117D6941996-05-0909 May 1996 Proposed Tech Specs Required to Support Unit 1 Cycle 9, Including Changes to SLMCPR & Ref for Analytical Methods Used to Determine Core Operating Limits.Addl Methodology Ref in Various TS Bases Revised to Reflect GE Methodologies ML20111B2701996-05-0808 May 1996 Proposed Tech Specs,Placing Containment Purge Valves W/ Resilient Seals on Performance Based Leakage Testing Frequency ML20108E3591996-05-0606 May 1996 Proposed Tech Specs Re Change in Co Name from Mississipi Power & Light to Entergy Mississippi,Inc ML20107E4681996-04-18018 April 1996 Proposed Tech Specs Re Fuel Loading W/Control Rods Withdrawn or Removed from Defueled Core Cells ML20100J8391996-02-22022 February 1996 Proposed Tech Specs Re Safety Setpoint Tolerance Requirements for Safety/Relief Valves ML20097C3541996-02-0101 February 1996 Proposed Tech Specs,Revising TS Bases to Include Changes Since 950221 Approval of TS Bases ML20094M8001995-11-20020 November 1995 Proposed Tech Specs Re Drywell Leak Rate Testing Requirements ML20087B5061995-08-0404 August 1995 Proposed Tech Specs Assoc W/Various ESF Sys Following Design Basis Fuel Handling Accident ML20082K3451995-04-13013 April 1995 Proposed Tech Specs Re Change to Be Reduced to Leave in TS Requirement to Test Outboard MSIV LCS Blowers ML20078S5141995-02-14014 February 1995 Proposed TS Consisting of Changes to SR 4.4.1.4.a.1 & 4.6.1.4.a.2 ML20078N6611995-02-10010 February 1995 Proposed Tech Specs Supporting Performance of Drywell Bypass Leakage Rate Surveillance on Performance Based Interval ML20079B4501994-11-0909 November 1994 Proposed Tech Specs Associated W/Various ESF Systems Following Design Basis Fuel Handling Accident ML20070C9751994-06-24024 June 1994 Proposed TS Pages 3/4 6-4 & 3/4 6-6 Associated W/Proposed Exemption to 10CFR50,App J ML20065L4971994-04-15015 April 1994 Proposed Tech Specs Re Administrative Controls ML20059H6061994-01-13013 January 1994 Proposed Tech Specs,Removing 2,324 Spent Fuel Pool Storage Limit ML20058D3911993-11-23023 November 1993 Proposed Tech Specs Bases Pages Re Cycle 7 Reload ML20059A4871993-10-22022 October 1993 Proposed Tech Specs Modifying Testing Frequencies for Drywell Test & Airlock Tests ML20059B0351993-10-15015 October 1993 Proposed Tech Specs Converting Current GGNS TS to TS Based Largely on NUREG-1434,Rev 0 ML20057C7281993-09-23023 September 1993 Proposed Tech Specs Removing Surveillance Requirement 4.4.1.2.2 Due to Problems Encountered W/Jet Pump Differential Pressure Instrumentation Measurements ML20056E4511993-08-12012 August 1993 Proposed Tech Specs 3/4 6-3,6-4,6-4a,6-6,6-12 Re Exemption to 10CFR50,App J, Primary Reactor Containment..., for Local Leak Rate ML20056D5621993-08-11011 August 1993 Proposed Tech Specs Section 3/4.3.7.5 Reflecting Relocation of Certain Accident Monitoring Instrumentation to Administrative Control ML20046D2081993-08-11011 August 1993 Proposed Tech Specs Section 3/4.3.7.10, Loose Part Detection Sys, Relocating Loose Part Detection Instrumentation from TS to Administrative Control ML20046D1961993-08-11011 August 1993 Proposed Tech Specs Supporting Compliance W/New Requirements of 10CFR20 & 10CFR50.36a ML20056C7141993-07-15015 July 1993 Proposed Tech Specs Removing Operability Requirements for auto-test Feature of Load Shedding & Sequencing Sys & Increase AOT for Inoperable Load Shedding & Sequencing Sys from Eight to Twelve 1999-08-20
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211E7151999-08-20020 August 1999 Proposed Tech Specs,Incorporating Many Generic Improvements Agreed Upon Between Industry & NRC Since GGNS Conversion to ITS ML20196K0831999-06-29029 June 1999 Proposed Tech Specs Page 3.4-3,reflecting Implementation of BWROG Enhanced Option I-A,reactor Stability long-term Solution ML20196G7131999-06-23023 June 1999 Proposed Tech Specs Revising TS Associated with Various Esfss Which Need No Longer Be Credited Following Design Basis Fuel Handling Accident ML20206K5361999-05-0606 May 1999 Proposed Tech Specs Pages,Changing SLMCPR ML20206R9351999-01-12012 January 1999 Proposed Tech Specs Re Refueling Equipment Interlocks Required Actions ML20154Q4511998-10-16016 October 1998 TS Bases Update for Period of 970410 Through 981015 ML20236T1661998-07-20020 July 1998 Proposed Tech Specs 3.2.4,3.3.1.1,3.3.1.3,3.4.1,5.6.5, B 3.2.4,B 3.3.1.1,B 3.3.1.3 & B 3.4.1,enabling Full Implementation of Enhanced Option I-A Long Term Solution to Address Neutronic/Thermal Hydraulic Instability Issue ML20198J3581998-01-0909 January 1998 Proposed Tech Specs,Providing Certain Clarifications to Amend & Adding Restriction to Allowed Interval Extensoions ML20210F6651997-12-22022 December 1997 Redeacted Version of Test Rept M-J5.08-Q1-45161-0-8.0-1-0, Pressure Locking & Thermal Binding Test Program on Two Gate Valves with Limitorque Actuators for Entergy Operations ML20217H6211997-12-15015 December 1997 Rev 21 to Odcm ML20199L5711997-11-26026 November 1997 Rev 8 to Program Plan GGNS-M-189.1, Grand Gulf Nuclear Station Pump & Valve IST Program - Safety Related ML20198N3231997-11-0606 November 1997 Rev 11 to GGNS-M-489.1, Program Plan for ASME Section XI ISI Plan ML20198N3941997-10-28028 October 1997 Proposed Tech Specs Implementing Option B & Ref SE Issued by NRR for Ggns'S App J Exemption as Implementing Document for performance-based Leakage Testing Program ML20211M8481997-10-0606 October 1997 Proposed Tech Specs Replacement Bases Pages Associated W/Proposed Amend to License Re Response Time Testing ML20210V5581997-09-18018 September 1997 Proposed Tech Specs Reflecting Decrease of Two Recirculation Loop SLMCPR Limit to 1.11 & Single Recirculation Loop SLMCPR Limit to 1.12 ML20210H0871997-08-0606 August 1997 Proposed Tech Specs Changing TS 3.8.1, AC Sources Operating. Removal of Accelerated Testing Requirements for Standby DGs as Advised by GL 94-01 ML20141A1681997-05-0707 May 1997 Proposed Tech Specs Re Eliminating Selected Response Time Testing Requirements ML20140E3211997-04-18018 April 1997 Proposed Tech Specs,Revising TS Bases to Include Changes Made Since Rev 1 Was Sent to NRC 960201 ML20134N7841996-11-21021 November 1996 Proposed Tech Specs Pp 5.0-20 & 5.0-21,revised by Adding Footnote Indicating Proposed Change Applicable Only for Cycle 9 ML20134N7611996-11-20020 November 1996 Proposed Tech Specs Re MCPR Limits for Two Recirculation Loop Operation ML20134E1261996-10-22022 October 1996 Proposed Tech Specs Revising TS Figure 3.4.11-1, Minimum Reactor Vessel Metal Temperature Vs Reactor Vessel Procedure, Curves Using Methodology of NRC Reg Guide 1.99, Rev 2, Radiation Embrittlement of Reactor Vessel Matls ML20128M5681996-10-0909 October 1996 Proposed Tech Specs 3.8.1.14 Re Surveillance Requirements ML20117P4461996-09-19019 September 1996 Proposed Tech Specs Re Containment Purge Valves W/Resilient Seals on Performance Based Leakage Testing Frequency ML20117M7021996-09-0505 September 1996 Proposed Tech Specs Re Min Critical Power Safety Limit ML20117G6781996-08-27027 August 1996 Proposed Tech Specs Re Surveillance Requirements for Safety/Relief Valves ML20116F0211996-07-31031 July 1996 Proposed Tech Specs Required to Support Cycle 9,reload 8 ML20113B7381996-06-20020 June 1996 Proposed Tech Specs,Redefining Secondary Containment Boundary to Allow Encl Bldg to Be Inoperable During Upcoming Refueling Outage ML20117L2581996-06-0404 June 1996 Proposed Tech Specs Re Replacement Page for Ltr RBG-42764, Proposed Tech Specs 3.9.1 Re Refueling Equipment Interlocks1996-05-31031 May 1996 Proposed Tech Specs 3.9.1 Re Refueling Equipment Interlocks ML20117D6941996-05-0909 May 1996 Proposed Tech Specs Required to Support Unit 1 Cycle 9, Including Changes to SLMCPR & Ref for Analytical Methods Used to Determine Core Operating Limits.Addl Methodology Ref in Various TS Bases Revised to Reflect GE Methodologies ML20117F4661996-05-0909 May 1996 Proposed Tech Specs,Modifying SRV Surveillance Test for Relief Mode of Operation ML20111B2701996-05-0808 May 1996 Proposed Tech Specs,Placing Containment Purge Valves W/ Resilient Seals on Performance Based Leakage Testing Frequency ML20108E3591996-05-0606 May 1996 Proposed Tech Specs Re Change in Co Name from Mississipi Power & Light to Entergy Mississippi,Inc ML20107E4681996-04-18018 April 1996 Proposed Tech Specs Re Fuel Loading W/Control Rods Withdrawn or Removed from Defueled Core Cells ML20100J8391996-02-22022 February 1996 Proposed Tech Specs Re Safety Setpoint Tolerance Requirements for Safety/Relief Valves ML20097C3541996-02-0101 February 1996 Proposed Tech Specs,Revising TS Bases to Include Changes Since 950221 Approval of TS Bases ML20094M8001995-11-20020 November 1995 Proposed Tech Specs Re Drywell Leak Rate Testing Requirements ML20087B5061995-08-0404 August 1995 Proposed Tech Specs Assoc W/Various ESF Sys Following Design Basis Fuel Handling Accident ML20082K3451995-04-13013 April 1995 Proposed Tech Specs Re Change to Be Reduced to Leave in TS Requirement to Test Outboard MSIV LCS Blowers ML20108A2691995-03-10010 March 1995 Rev 17 to ODCM ML20078S5141995-02-14014 February 1995 Proposed TS Consisting of Changes to SR 4.4.1.4.a.1 & 4.6.1.4.a.2 ML20078N6611995-02-10010 February 1995 Proposed Tech Specs Supporting Performance of Drywell Bypass Leakage Rate Surveillance on Performance Based Interval ML20079B4501994-11-0909 November 1994 Proposed Tech Specs Associated W/Various ESF Systems Following Design Basis Fuel Handling Accident ML20070C9751994-06-24024 June 1994 Proposed TS Pages 3/4 6-4 & 3/4 6-6 Associated W/Proposed Exemption to 10CFR50,App J ML20065L4971994-04-15015 April 1994 Proposed Tech Specs Re Administrative Controls ML20059H6101994-01-14014 January 1994 Cycle 7 Startup Physics Test Summary Rept for Physics Testing Completed on 931220 ML20059H6061994-01-13013 January 1994 Proposed Tech Specs,Removing 2,324 Spent Fuel Pool Storage Limit ML20029D6451993-11-30030 November 1993 Reactor Containment Bldg 1993 Integrated Leakage Rate Test. ML20058D3911993-11-23023 November 1993 Proposed Tech Specs Bases Pages Re Cycle 7 Reload ML20059A4871993-10-22022 October 1993 Proposed Tech Specs Modifying Testing Frequencies for Drywell Test & Airlock Tests 1999-08-20
[Table view] |
Text
. ._
a .
. GNRo 96/00096 Attachment 2 page 1 of 9 i
)
4 PROPOSED CHANGE TO THE OPERATING LICENSE i
- Revised Technical Specification and
, Technical Specification Bases pages ;
l I
l
)
i
! Cross reference of attached pages to pages originally submitted via GNRO-96/00037
] Attachment 4.
I This submittal Attachment 2 Replaces GNRO-96/00037 Attachment 4 page1 Not Applicable page 2 page1 page 3 page 3 page 4 Not Applicable - New Insert page 5 page 5 page 6 page 7 page 7 Not Applicable - New insert page 8 page 9 page 9 page 12 9609050200 960827 PDR ADOCK 05000416 p PDR
.- _- . .. . . . .. .. _ . - . . = -. _. . _ . _
l I
GNRO-96/0oO96 S/RVs Attachment 2 3.4.4
,page 2 of 9
!' SURVEILLANCE REQUIREMENTS (continued) 1 SURVEILLANCE FREQUENCY 5
i SR 3.4.4.2 -------------------NOTE-------------------- ,
Valve actuation may be excluded. '
i Verify each required relief function S/RV 18 months i actuates on an actual or simulated 4
automatic initiation signal. Shbn 1 k
! SR 3.4.4.3 ---------------- --NOTE-------------------- ^Aw bou i
Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor- steam pressure and flow are W4 %.
adequate to perform the test. ' Tnse v'c.a Te.dh
........................................... p* SN" l I
Verify each required S/R a ch d v O M manually actuated.
when k M Z'on S' TEST a
b- '
BASIS for each valve solenoid GRAND GULF 3.4-11 Amendment No. 120
h S/RVs GNRO 96/ooo96 '
Attachment 2 j p
, age 3 gfg SURVEILLANCE SR 3.4.4.3 (continued)
- REQUIREMENTS
'a gamagingth valve, Also, ade ate steam flow must e assing thro h the main turbine r turbine bypass va es to ntinue to co trol reactor pressu when the S/RVs di t j i'
I s am flow upon pening. Sufficien time is therefore al wed after th required pressure a flow are achieved pe 'orm this test. Adequate pressure a which this test is to e performed is nsistent with the p ssure recommended by le valve manufac rer. Plant startup allowed prior to pjrforming this te because valve OPERA LITY and the I setpgints for overpress re protection are ver ied, per ASME requiPements,priortoylveinstallation. Th efore, this )
SR is modified by a Note at states the Surveil nce is not requi ed to be performed u il 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after rea or steam pressu e and flow are adequ e to perform the test. The 12 hou allowed for manual a tuation after the requ ed pressur is reached is suffici t to achieve stable h(shn \
conditio s for testing and prov es a reasonable time complete he SR. If the valve f 1s to actuate due only to ,
i the failu of the solenoid but i capable of opening on
\
4 l overpressu e, the safety function o_ the S/RV is y nsider
\ Q BEJ -
- g7,,g ,,,,4,g pg, g. n A< ThE""" STAGGERED TESTL BASIS Frequency ensures AA.c Mg_ d h_ach solenoid for each S/RV*is alternately tested.
that e The l
Frequency 4was developed based on the S/RV tests requirea Dy the ASME Boiler and Pressure Vessel Code.
g 15'N Section XI (Ref. 1)f" Op ing exper e has s tha 1
ghe omponents u lly pass Sur e when 6 3,4-9/ A 3 yarfnema + tha in mon _ eauenc Therefore, e L
Frequency was concluded to be acceptable from a reliability standpoint.
REFERENCES 1. ASME, Boiler and Pressure Vessel Code, Sections III and XI.
- 2. UFSAR, Section 5.2.2.2.3.
- 3. UFSAR, Section 15.
j l
GRAND GULF B 3.4-21 Revision No. O I
I GNRO-96/00096 l Attachment 2 page 4 of 9 l
l INSERT B 3.4-21 A as implemented by the Inservice Testing Program of Specification 5.5.6. The testing Frequency required by the Inservice Testing Program is based on operating experience and valve performance.
ke_MI3lon 1 1
I l
1 I
l l
l I 1 l
L .
j . GNRO-96/00096 ECCS-Operating
= Attachment 2 4 page 5 of 9 3.5.1 i
i SURVEILLANCE REQUIREMENTS (continued) j SURVEILLANCE FREQUENCY t
SR 3.5.1.5 -------------------NOTE--------------------
4 Vessel injection / spray may be excluded.
- Verify each ECCS injection / spray subr/ stem 18 months >
i actuates on an actual or simulated l automatic initiation signal.
- SR 3.5.1.6 -------------------NOTE--------------------
l Valve actuation may be excluded.
j Verify the ADS actuates on an actual or 18 months simulated automatic initiation signal.
Re,s te%
3 i
I
! SR 3.5.1.7 -------------------NOTE--------------------
Tn er:ccebNou QAgg Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are gg l l 4
. adequate to perform the test. 1^*fM " M ,^3j j -..........................................
gr%g
[ Verify eahADS valve when manually M on a
- . y } j A X, actuated. K a STAGGERED TEST ,
4 ,
BASIS for each
':T'M *M / !
l valve solenoid i I l SR 3.5.1.8 Verify the ECCS RESPrASE TIME for the HPCS 18 months i System is within linits.
i l
9 GRAND GULF 2.5-5 Amendment No. 120
i .
ECCS-Operating i - B 3.5.1
, GNHO-96/00096
- Attachment
- page 6 of 9 SURVEILLANCE SR 3.5.1.7 (continued) <
i REQUIREMENTS -
4 i
OPERABILI and the setpoin for overpressure pr action er ASNE requir i i
k q are verifie , erefore, this S ts,s modified
) installation.
prior to valve by a N e that tes the Surve ance is not requ to be performe i
! unt 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> afte *eactor steam pre ure and flow ar adequate o perfone tl test. SR 3.5 1. and the LOGIC !
, _ SYSTEM F ONAL TEST formed in LCO 3. 5.1 overlap th's i
t j gg ,A provide e late testing of e assumed A c.%< hic [safety Surveillance functio -
I The W A t ab M , STAGGERED TEST BASI 3 ensures that both solenoids for each ADS valvegre alternately _
sted.
he r . -- = m.y i; L- ;6 on we
" Surve a to pe re this l nee unde the condit ns that ap y just p or to r8'3,% 7*A }% r durin startup t
a plan outage a he pote al
! f unplann transion Operat experien l
has sh i e
)3A tha these c onents us lly pass SR when rformed j i a the month F auenev. wh h it hu
- ,i ~ aa tha re 11 ;
uc ycle.1 Therefore, the Frequency was concluded to be 4
g .
accepfable from a reliability standpoint. l Rw Mo n 1
l SR 3.5.1.8 -
This SR ensures that the HPCS System response time is less than or equal to the maximum value assumed in the accident analysis. Specifte testing of the ECCS actuation j instrumentation inputs into the HPCS System ECCS SYSTEM RESPONSE TIME is noi required by this SR. Specific response
- time testing of thh instrumentation is not required since 1 these actuation channels are only assumed to respond within the diesel generator start time; therefore, sufficient margin exists in the diesel generator 10 second start time when compared to the typical channel response time (milliseconds) so as to assure adequate response without a specific measurement test. The diesel generator starting and any sequence loading delays must be added to the HPCS System equipment response times to obtain the HPCS System
. ECCS SYSTEM RESPONSE TIME. The acceptance criterion for the
.HPCS System ECCS SYSTEM RESPONSE TIME is s 27 seconds.
(continued)
GRAND GULF B 3.5-13 Revision No. 1
(> 0
. GNRO-96/00096 Attachment 2 page 7 o,f 9 INSERT B 3.5-13A The Frequency of the required relief-mode actuator testing was developed based on the tests required by the ASME Boiler and Pressure ;
Vessel Code,Section XI as implemented by the Inservice Testing '
Program of Specification 5.5.6. The testing Frequency required by the ;
7nservice Testing Program is based on operating experience and valve j performance.
St>b$\on S l
l l
i l
l
[ l l l l llS Values
. GNRo-96/00096 3.6.1.6 Attachment 2 pago 8 of 9 NON I f ' SURVEILLANCE REQUIREMENTS s SURVEILLANCE
\
FREQUENCY I
I I
SR 3.6.1.6.1 ------------------NOTE------------------- i bis.'nl
, Not required to be performed until 6^*
M cNet.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and wA h flow are adequate to perform the test. TMe.r vi <5t.
.m ga !,3 er p m 5' Qrc' ^^-O i
Verify each* LLS valve - = when manually m th on a actuated. STAGGERED TEST eg.\it:Q- mh BASIS for each g 4 A c- p eokt.s valve solenoid l
SR 3.6.1.6.2 ------------------NOTE--------- ^^--------
! Valve actuation may be excluded.
j .........................................
Verify the LLS System actuates on an 18 months i actual or simulated automatic initiation l signal.
J 1
a l
I 1
i i i
f 1
l GRAND GULF 3.6-21
. Amendment No. 120
I ~l i
k' l
. GNRO-96/OOO96 .i Anschmern 2 1 page 9 of 9
. w !
l SR 3.6.1.6.1.a BASES Insert i 1
1 A manual actuation of each required LLS valve (those valves removed and replaced to satisfy SR 3.4.4.1.) is performed to verify that the I valve is functioning properly. This SR can be demonstrated by one of ;
two methods. If performed by method 1), plant startup is allowed
- prior to performing this test because valve OPERABILITY and the setpoints for overpressure protection are verified, per ASME l requirements, prior to valve installation. Therefore, this SR is [
modified by a Note that states the Surveillance is not required to be l performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are !
adequate to perform the test. The 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> allowed for manual ;
actuation after the required pressure is reached is sufficient to achieve stable conditions for testing and provides a reasonable time to complete the SR. If performed by method'2), valve OPERABILITY has been demonstrated for all installed LLS valves based upon the i successful operation of a test sample of S/RVs.
- 1) Manual actuation of the LLS valve, with verification of the response of the turbine control valves or bypass valves, by a change in the measured steam flow, or any other method suitable !
to verify. steam flow (e.g. , tailpipe temperature or pressure). r Adequate reactor steam pressure must be available to perform this test to avoid damaging the valve. Also,' adequate steam flow must be passing through the main turbine or turbine bypass valves to continue to' control reactor pressure when the LLS valves divert steam flow upon opening. Sufficient time is therefore allowed !
after the required pressure and flow are achieved to perform this test. Adequate pressure at which this test is to be performed is consistent with the pressure recommended by the valve j manufacturer.
i
- 2) The sample population of S/RVs tested each refueling outage to !
satisfy SR 3.4.4.1'will be stroked in the relief mode during "as- '
found" testing to verify proper operation of the S/RV. The successful performance of the test sample of S/RVs provides :
reasonable assurance that all LLS valves will perform in a !
similar fashion. After the S/RVs are replaced, the relief-mode actuator of the newly-installed S/RVs will be uncoupled from the J S/RV stem, and cycled to ensure that no damage has occurred to
" the S/RV'during transportation and installation. This verifies kSN that each replaced S/RV will properly perform its intended
% function.
D
- N, The STAGGERED TEST BASIS Frequency ensures that both solenoids for
! each LLS valve relief-mode actuator are alternately tested. The
. Frequency of the required relief-mode actuator testing was developed l based on the tests required by the ASME Boiler and Pressure Vessel
' Code,Section XI as implemented by the Inservice Testing Program of
- Specification 5.5.6. The testing Frequency required by the' Inservice i Testing. Program is based on operating experience and-valve
- performance. Therefore, the Frequency was concluded to be acceptable
- from a reliability standpoint.
i i
1 i . _ - - . _
_ _ . , ,