Proposed Tech Specs 3/4.4.3 Re Limiting Conditions for Operation & Surveillance Requirements for RCS Leakage & Leakage Detection SysML20066H095 |
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River Bend ![Entergy icon.png](/w/images/7/79/Entergy_icon.png) |
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Issue date: |
02/13/1991 |
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From: |
GULF STATES UTILITIES CO. |
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To: |
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Shared Package |
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ML20066H094 |
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References |
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NUDOCS 9102200166 |
Download: ML20066H095 (5) |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20210H2901999-07-30030 July 1999 Proposed Tech Specs Pages,Extending Operation of RBS from Current Licensed Power Level of 2894 Mwt to Uprated Power Level 3039 Mwt ML20205P8701999-04-15015 April 1999 Proposed Tech Specs,Implementing Bwrog/Ge Enhanced Option I-A (EI-A) Reactor Stability long-term Solution ML20205L7321999-04-0808 April 1999 Proposed Tech Specs,Removing Notes That Refer to Specific Cycles,Per LAR 1998-15 Re Change to TS 2.1.1.2, Reactor Core Safety Limits ML20206R9351999-01-12012 January 1999 Proposed Tech Specs Re Refueling Equipment Interlocks Required Actions ML20198E8091998-12-16016 December 1998 Proposed Tech Specs Pages Re Change to TS Safety Limit 2.1.1.2,changing Two Recirculation Loop MCPR Limit from 1.13 to 1.12 & Single Recirculation Loop MCPR Limit from 1.14 to 1.13 ML20196A1401998-11-20020 November 1998 Proposed Tech Specs Adding 3.10.9, Control Rod Pattern - Cycle 8, to Support Startup from Outage Planned for Early Dec 1998 ML20154H3691998-10-0808 October 1998 Proposed Tech Specs Implementing BWROG Enhanced Option I-A Reactor Stability Long Term Solution as Documented in NEDO-32339,Rev 1, Reactor Stability Long-Term Solution, Enhanced Option I-A ML20153H0311998-09-23023 September 1998 Proposed Tech Specs Changing Specific Gravity Acceptance Criteria for Div III Battery ML20153E8111998-09-22022 September 1998 Proposed Tech Specs Deleting License Conditions Associated with Transamerica Delaval,Inc EDGs ML20217J0951998-04-21021 April 1998 Proposed Tech Specs Bases Update Package for Revs Implemented Since Last Submittal Through Refuel Outage 7 ML20216F1941998-04-0909 April 1998 Proposed Tech Specs License Condition 2.C(13) Re Partial Feedwater Heating & Final Feedwater Temp Reduction ML20216E4861997-09-0505 September 1997 Proposed Tech Specs Re APRM Setpoints,Reactivity Anomalies & RPS Instrumentation ML20210K2131997-08-15015 August 1997 Proposed Administrative Changes to TS 2.1.1.2 W/Note to Indicate Operating Cycle for Which SLMCPR Value Has Been Approved & TS 5.6.5 W/Note Providing Link to Specific GE Documents Used in Approving SLMCPR Changes for Given Cycle ML20217J0481997-08-0505 August 1997 Proposed Tech Specs 2.1.1.2, Reactor Core (Safety Limits), Increasing Two Recirculation Loop MCPR Limit to 1.13 & Single Recirculation Loop MCPR Limit to 1.14 ML20151L6041997-07-31031 July 1997 Proposed Tech Specs,Requesting Approval of Change to TS 3.6.1.8, Penetration Valve Leakage Control Sys, for Upcoming Outage ML20196J7741997-07-30030 July 1997 Proposed Tech Specs Clarifying Surveillance Requirements 3.6.4.2.1 & 3.6.4.2.2 to Match Corresponding Changes to NUREG-1434 ML20134A7021997-01-20020 January 1997 Proposed Tech Specs to License NPF-47,enhancing Operation of Plant to Allow Operation at 100% Power W/Lower Core Flows & Use of Flow Control Spectral Shift Strategies to Increase Cycle Energy ML20133M0451997-01-10010 January 1997 Proposed Tech Specs 3.4.11 Re RCS Pressure & Temp Limits ML20134M2271996-11-15015 November 1996 Proposed Tech Specs,Changing TS SL 2.1.1.2, Reactor Core (Sl), Which Increases Two Recirculation Loop MCPR Limit from 1.07 to 1.10 & Single Recirculation Loop MCPR from 1.08 to 1.12 ML20134M0151996-11-15015 November 1996 Proposed Tech Specs 3.8.1 Re AC Sources Operating ML20134M2061996-11-0606 November 1996 Proposed Tech Specs,Permitting Increase in Allowable Leak Rate for MSIVs & Deleting Penetration Valve Leakage Control Sys & Ms Positive Leakage Control Sys Requirements ML20129J4231996-10-24024 October 1996 Proposed Tech Specs 3.8.1 Re A.C. 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[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20210H2901999-07-30030 July 1999 Proposed Tech Specs Pages,Extending Operation of RBS from Current Licensed Power Level of 2894 Mwt to Uprated Power Level 3039 Mwt ML20205P8701999-04-15015 April 1999 Proposed Tech Specs,Implementing Bwrog/Ge Enhanced Option I-A (EI-A) Reactor Stability long-term Solution ML20205L7321999-04-0808 April 1999 Proposed Tech Specs,Removing Notes That Refer to Specific Cycles,Per LAR 1998-15 Re Change to TS 2.1.1.2, Reactor Core Safety Limits ML20206R9351999-01-12012 January 1999 Proposed Tech Specs Re Refueling Equipment Interlocks Required Actions ML20199C1881999-01-0808 January 1999 Revised Page 7 to Rev 13 of RBS Security Training & Qualification Plan ML20198E8091998-12-16016 December 1998 Proposed Tech Specs Pages Re Change to TS Safety Limit 2.1.1.2,changing Two Recirculation Loop MCPR Limit from 1.13 to 1.12 & Single Recirculation Loop MCPR Limit from 1.14 to 1.13 ML20196A1401998-11-20020 November 1998 Proposed Tech Specs Adding 3.10.9, Control Rod Pattern - Cycle 8, to Support Startup from Outage Planned for Early Dec 1998 ML20154H3691998-10-0808 October 1998 Proposed Tech Specs Implementing BWROG Enhanced Option I-A Reactor Stability Long Term Solution as Documented in NEDO-32339,Rev 1, Reactor Stability Long-Term Solution, Enhanced Option I-A ML20153H0311998-09-23023 September 1998 Proposed Tech Specs Changing Specific Gravity Acceptance Criteria for Div III Battery ML20153E8111998-09-22022 September 1998 Proposed Tech Specs Deleting License Conditions Associated with Transamerica Delaval,Inc EDGs ML20217J0951998-04-21021 April 1998 Proposed Tech Specs Bases Update Package for Revs Implemented Since Last Submittal Through Refuel Outage 7 ML20216F1941998-04-0909 April 1998 Proposed Tech Specs License Condition 2.C(13) Re Partial Feedwater Heating & Final Feedwater Temp Reduction RBG-44355, Cycle 8 Startup Physics Test Summary1998-01-19019 January 1998 Cycle 8 Startup Physics Test Summary ML20202F0361997-11-26026 November 1997 Rev 0 to IST Plan for Pumps & Valves Second Ten-Yr Interval ML20216E4861997-09-0505 September 1997 Proposed Tech Specs Re APRM Setpoints,Reactivity Anomalies & RPS Instrumentation ML20210K2131997-08-15015 August 1997 Proposed Administrative Changes to TS 2.1.1.2 W/Note to Indicate Operating Cycle for Which SLMCPR Value Has Been Approved & TS 5.6.5 W/Note Providing Link to Specific GE Documents Used in Approving SLMCPR Changes for Given Cycle ML20217J0481997-08-0505 August 1997 Proposed Tech Specs 2.1.1.2, Reactor Core (Safety Limits), Increasing Two Recirculation Loop MCPR Limit to 1.13 & Single Recirculation Loop MCPR Limit to 1.14 ML20151L6041997-07-31031 July 1997 Proposed Tech Specs,Requesting Approval of Change to TS 3.6.1.8, Penetration Valve Leakage Control Sys, for Upcoming Outage ML20196J7741997-07-30030 July 1997 Proposed Tech Specs Clarifying Surveillance Requirements 3.6.4.2.1 & 3.6.4.2.2 to Match Corresponding Changes to NUREG-1434 ML20134A7021997-01-20020 January 1997 Proposed Tech Specs to License NPF-47,enhancing Operation of Plant to Allow Operation at 100% Power W/Lower Core Flows & Use of Flow Control Spectral Shift Strategies to Increase Cycle Energy ML20133M0451997-01-10010 January 1997 Proposed Tech Specs 3.4.11 Re RCS Pressure & Temp Limits ML20140F0151996-12-26026 December 1996 Rev 6 to RSP-0008, ODCM Procedure ML20134M2271996-11-15015 November 1996 Proposed Tech Specs,Changing TS SL 2.1.1.2, Reactor Core (Sl), Which Increases Two Recirculation Loop MCPR Limit from 1.07 to 1.10 & Single Recirculation Loop MCPR from 1.08 to 1.12 ML20134M0151996-11-15015 November 1996 Proposed Tech Specs 3.8.1 Re AC Sources Operating ML20134M2061996-11-0606 November 1996 Proposed Tech Specs,Permitting Increase in Allowable Leak Rate for MSIVs & Deleting Penetration Valve Leakage Control Sys & Ms Positive Leakage Control Sys Requirements ML20129J4231996-10-24024 October 1996 Proposed Tech Specs 3.8.1 Re A.C. Sources - Operating ML20117K1071996-08-29029 August 1996 Proposed Tech Specs Re Reactor Vessel Matl Surveillance Program Capsule Withdrawal Schedule ML20117G7401996-08-29029 August 1996 Proposed Tech Specs 3.1 Re Reactivity Control Systems ML20116P1341996-08-0808 August 1996 Technical Requirements Manual ML20116J3151996-08-0707 August 1996 Proposed Tech Specs,Submitting TS Bases Pages for Revs Performed Since 951001 Approval of TS Bases ML20116L6321996-08-0101 August 1996 Proposed Tech Specs Re Primary Containment/Drywell Hydrogen Mixing Sys & Drywell Isolation Valves ML20113F2271996-06-12012 June 1996 Rev 0 to Calculation PI-0103-00203.002-101, Ampacity Derating Evaluation 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 ML20112E7831996-05-30030 May 1996 Proposed Tech Spec 3.8.3 Re Incorporation of 5-start Air Pressure Design Criterion for Div III DG ML20117H3271996-05-20020 May 1996 Proposed Tech Specs Re Change in Co Name from Gulf States Utils Co to Entergy Gulf States,Inc B130180, Surveillance Specimen Program Evaluation for River Bend Station1996-04-30030 April 1996 Surveillance Specimen Program Evaluation for River Bend Station ML20107E4681996-04-18018 April 1996 Proposed Tech Specs Re Fuel Loading W/Control Rods Withdrawn or Removed from Defueled Core Cells ML20094N7741995-11-22022 November 1995 Proposed Tech Specs,Clarifying Info Contained in License Amend Request (LAR) 95-21 ML20094M8001995-11-20020 November 1995 Proposed Tech Specs Re Drywell Leak Rate Testing Requirements ML20094N0091995-11-20020 November 1995 Proposed Tech Specs Eliminating Selected Response Time Testing Requirements ML20094B0001995-10-26026 October 1995 Proposed Tech Specs,Consisting of Change Request 95-10, Deleting TS 5.5.12, Biofouling Prevention & Detection, & Various Editorial Corrections ML20093L7361995-10-24024 October 1995 Proposed Tech Specs 3.6.1.1 Through 3.6.1.3 Re Containment Sys ML20108B5941995-10-0101 October 1995 Rev 5A to River Bend Station Offsite Dose Calculation Manual Procedure ML20087J5451995-08-17017 August 1995 Proposed Tech Specs Re Engineered Safety Sys Which Responds to Fuel Handling Accident Conditions ML20084L5001995-05-30030 May 1995 Proposed Tech Specs,Allowing TS 3/4.6.2.2, Drywell Bypass Leakage, Tests to Be Performed at Intervals as Long as Five Yrs Based on Demonstrated Performance of Drywell Structure ML20084L4541995-05-30030 May 1995 Proposed Tech Specs Re Request for Exemption from App J, Primary Reactor Containment Leakage Testing for Water- Cooled Power Reactors ML20078M1171995-02-0808 February 1995 Proposed Tech Specs Page Re Secondary Containment Automatic Isolation Dampers ML20077S4401995-01-18018 January 1995 Revised Pages of Proposed Tech Specs Re Conversion to TS Based on NUREG-1434, Improved TS Rev 0 ML20078H0881994-11-10010 November 1994 Proposed Tech Specs Reflecting Clarifications to LAR 91-11 1999-07-30
[Table view] |
Text
.-- --. . , - . - - . . - . - . , . . - . - . . - . -- - . . . . . . ,
REACTOR COOLANT SYSTEM 3/4.a.3 4EACTOR COOLANT _ SYSTEM LEAKAGE 4
, LEAKAGE OETECTION SYSTEMS
- .19!TINGCONDITIONFOROPERAT!0N '
l i
I 3.4.3.1 ee OPERABLE: The follcwing' *eactor coolant system leakage ostection systems sh a.
The drywell atmosohere particulate radioactivity monitoring' syste b.
The drywell systems, and pedestal-floor sump drain flow monitoring c.
Either the drywell air coolers condensate flow rate monitoring system-or the drywell atmosphere gaseous radioactivity monitoring system.
APPLICA8ILITY
(
OPERATIONAL-CON 0!TIONS 1, 2 and 3.
ACTION:
- tion may cotwo of the aboveto -
required leakage detection systems OPERA 8 30 days *provided grab sam gg phere are obtained and ana gaseous and/or particula M aours when the rywell: atmos-required Y wise, be in ve so SHUT 00WH within'the.next 12 hou em i's inoperable; other-LO.SHUTOOWN e following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. .
1,U,RVEILLANCEREQUIREMENTS 4.4.3.1 The reactor coolant sy. stem leakage detection systems shall be demon- :
strated OPERA 8LE by:
a.
Drywell atmosphere particulate and gaseous monitoring systems -
performance of a CHANNEL CHECK at11 east'once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, 4. CHANNEL
- FUNCTIONAL TEST at least once-per 31 days and a CHANNEL CALIBRATION at least once par 18 sonths,
- b. The sump drain flow' monitoring systems performance af a CHANNEL FUNCTIONAL TE51 at least once per 31 days and a . CHANNEL CALIBRATION .
TEST at.least cnce per 18 months,
- c. Orywell air coo er.: candensate -flow rate monitoring system-
' performance of a CHANhel FUNCTIONAL TEST at least once per 31 days and a CHANNEL CAL!BRATION st' least once per 18 montns. -
- d. F1ow testing the drywell floor-drain sump inist piping for blockage at least once per 18 months. " .
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s s q REACTOR COOLANT $YSTEM OPERATIONAL LEAKAGE r .
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LIMITING CONDITION FOR OPERATION ' '
- l 3.4.3.2 Reactor coolant system leakage _ shail be' limited' to:. i
- a. No PRESSURE B0UNDARY LEAKAGE.
- b. 5 gpa UNIDENTIFIED LEAKAGE.
- c. 25gpatotalleakage-(averaged.overfany24-hourperiod$:
- 1 d."' O.5 gpa per nominal inch of valve l size up to' a-maximum of:5 gpa leakage at a reactor: coolant system pressure of 1025 t 15.psig from any reactor coolant: system pressure isolation valve specified'in.
3 Table 3.4.3.2 .1.; *
~
ITY: OPERATIONAL CONDITIONS 1,. 2 and 3.
ACTION:
- . *~
a.
With any PRESSURE 800NDARY LEAKAGE,<be in at least'H0T-SHUTDOWN within.. ,
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTD0WN'withincthe.nexti24" hours.t
- b. With any reactor coolant system'1eakagej greater than the limits in' b ~
~
and/or c above, reduce theileakage' rate'to sithin the limits within--
4' hours o,r be in at least NOT SNUTDOWN within the next?l2~ hours'and in-COLD SHUTDOWN within the following 241 hours0.00279 days <br />0.0669 hours <br />3.984788e-4 weeks <br />9.17005e-5 months <br />'.
' c.
With any reactor coolant system pressurelisciation valve leakage greater ,
than the.above limit . isolate the highipressure: portion of. the Laffacted 1 systes fron' the low' pressure portion within 4(hours by uselof : at least two other closed manual,' deactivated automatic or: check
be.in at ler t HOT' SHUTDOWN within'the nekt 12' hours and in' COLD SHUTDOWN wiu.in-the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.# .
d.
.With one or more of the high/ low pressur'e interface valve leakage L 8 l
pressure monitors. shown in-Table 3;4.3.2-2 inoperable, restore the :
i inoperable monitor (s) to 0PERA8LE status within'7 days'ordvarify the- !
' pressure to be less'than.the alarm point 'at lea' st once per.12: hours; restore the inoperable monitor (s)<to:0PERABLE.. status within 30 days or be in at least-HOT: SHUTDOWN within' the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and COLD : .
SHUTDOWN within the following 24: hours. The-provisions. ^of Specifi-'
NECEiVED cation:3.0.4-are not applicable. <
a RUG 131987 INsr.nr III
.S D C.
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" Which have been verified not to exceed the allowable ' leakage. limit-at the 11ast: refueling outage or after.the-last time the valve was-disturbed.1 a Lwhichever is more recent.
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REACTOR C001. ANT SYSTEM 51)RVillLANCE RIOUIR(MENTS l
4.4.3.2.1 -;
each of: the above'Italts by:The reactor coolant system leakag
- a. !
, Monitoring the drywell atmospheric particulate radioactivity once per ' 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, b.
Monitoring the sung flow rates at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.-
c.
Monitoring per the 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, anddrpell air coolers condensate flow rate at least on ,
d.
Monitoring the 24 least once per reactor hours. vessel head flange leak detection system at 4.4.3.2.2 - fech reactor coolant system pressure isolation valve specified in Table 3.4.3.2 1 shall be demonstrated CPERA8LE b leak testing pursuant to Specification 4.0.5 including paragraph IW 3427 l) of the A5ME Code and verifying the leakage of each valve to be within the specified limit:
- a. LAt least once per 18 monthd and b.
prior to returning the valve to service' following maintenance, l repair or replacement work on the valve which could affect its leakage rate.
. The provisions of- Specification 4.0.4 are not applicable Lfer entry into OPERATIONAL CONDITION 3.
4.4.3.2.3 The high/ low pressure interface valve leakage pressure monitors shall be demonstrated performance of as CPERA8LE with alarm setpoints per Table 3.4.3.2-2 by
- a. CHANNEL FUNCTIONAL TEST at least once per 31 days, and l . b'. CHANNEL CALIBRAT!0N at least once per 18 months.
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s AIVER SEND - 15171 3/4 4 12 Amenenent No.: 7' l RECElYEO t
AUG 131987 l
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1 ENCLOSURE II t
INSERT Basis of Specification 3/4.4.3.1 The drywell and pedestal floor sump drain flow monitoring systems consist of 2 sumps with one level transmitter and two 100% pumps each. The level transmitters feed Main Control Room level indicators as well as various automatic control systems. Each of the automatic systems calculate leakage, control pumps and provide annunciation. The leak rate may be determined by the automatic system or a manual procedure through the use of the -level indication and pump control switches located'in the main control room. The substitution of grab samples for the' drywell particulate and gaseous monitors is to allow for continued monitoring of the function -
while normal components are inoperable.
Basis of Specification 3/4.4.3.2 The use of the drywell= radiation monitors as alternate means to monitor a change in the leakage while the sump f. low monitoring system is inoperable is to continue to provide the-operator with drywell leakage information during system outages. The new LCO. 3.'4.'3.2.0 is intended to address Intergranular Stress Corrosion Cracking- (IGSCC) concerns cf propagating a crack due to these effects. . Leakage whicit continues to increase at a rate of greater than or equal to 2; gpm in a period of.24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> may be' indicative of IGSCC and entry into the appropriate action'is required. Increases in leakage resulting from normal plant activities that stabilize and are no longer increasing at the above rate within the allowed LCO action time (e.g. a packing leak) are not intended-to be addressed by this LCO but continue to be included in the total unidentified leakage limit of 5 gpm.
I 1
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i
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g .3 MEACTOR COOLANT SYSTEN
.V a 3/4.4 ' REACTOR COOLANT SYSTEM L BASES j
SAFETY / RELIEF VALVES (Continued)-
~
Demonstration of the safety-relief valve' lift settirags will occur only during shutdown and willibe-performed in accordance withlthe' provisions of 4
. Specification _4.0.5.- >"
The low-low set system ensures that safety / relief valve 1 discharges are minimized for a second opening of these~ valves, following any overpressure-
' transient.- This. is_ achieved by automatically. lowering thesclosing s'atpoint ofl a 5 valves and lowering the opening setpoint of 2 valves following!the\ initial opening. 'In-this way, the frequency and magnitude of the' containment blowdown a duty cycle is substantially reduced.1 Sufficient redundancy 11s provided_ fori , ;
the low-low set system such that failure of any one valve to;cpen or close at >
its reduced setpoint does:not violate =the design basis.. ;
3/4.4.3 REACTOR C00LANT' SYSTEM LEAKAGE
- a 3/4.4.3.1 LEAKAGE DETECTION-SYSTEMS- "
The RCS lea'kage-detection syptoms; required by'this1 specification;ars s.
provided to monitor and detect leakage from the; reactor < coolant pressure .
J
' boundary. -' These detection syste'es are consistent with-the' recommendations of- '
' Regulatory Guide 1.45,1" Reactor. Coolant Pressure _ Boundary: Leakage: Detection d Systems", May 1973. ;In conformance with; Regulatory Guide 1;45, the atmospheric '
UEEIU seous radioactivity system will:have aisensitivity.of;10 8.pC1/cc.; -t
" 4.4.3.2 OPERATIONAL LEAKAGE E J
The allowable leakage > rates from the-reacto_r coolant' system:have been based- j on the predicted and experimentally 1 observed behavior of cracks .in pipas., Ther l normally-expected background: leakage, due'to: equipment; design and:the c'etection!
. ;e I capability.of the1 instrumentation:for; determining; system;1eakage, wasfalso considered. The evidence 'obtained from- experiments suggests that,lfor leakagen '
a somewhat greater than-thathspecifind for UNIDENTIFIEDJLEAKAGE, the' probability-is small that the imperfection:or crack. associated ~withisuch leakage would growl rapidly.
However, in a11 Leases,11f _the leakage Lrates exceed the1 values Lspecified or t_he leakage'is located and-knowntto be PRESSURE B0UNDARY LEAKAGE,ithe reactor: #
. will be shut down totallow furtheriinvestigationiand: corrective action.
- l. '
l The Surveillance Requirements forJRCS pressure!isoiation valves provide-added assurance of valveEintegrity,1thereby- reducing thenprobability of gross valve failure and consequentiintersystem;LOCA.: Leakage;from the RCS pressure-isolation valves is IDENTIFIED' LEAKAGE and will;be: considered asta portion of :
he allowed limit. "
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