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 StructureML20084L500 |
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River Bend ![Entergy icon.png](/w/images/7/79/Entergy_icon.png) |
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Issue date: |
05/30/1995 |
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From: |
ENTERGY OPERATIONS, INC. |
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To: |
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Shared Package |
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ML20084L477 |
List: |
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References |
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NUDOCS 9506070228 |
Download: ML20084L500 (12) |
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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. 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 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 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 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 ML20087J5451995-08-17017 August 1995 Proposed Tech Specs Re Engineered Safety Sys Which Responds to Fuel Handling Accident Conditions 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 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 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 ML20024J3341994-10-0404 October 1994 Proposed Tech Spec Removing one-hour Requirement for Completing Noble Gas & Tritium Sampling & Analysis ML20073B2381994-09-12012 September 1994 Proposed TS 3/4.2.2, APRM Setpoints ML20072U7901994-09-0808 September 1994 Proposed Tech Spec 3.10.2, Special Test Exceptions - Rod Pattern Control Sys ML20064L6481994-03-15015 March 1994 Proposed Tech Specs,Reflecting Removal of Turbine Overspeed Protection Sys Requirements ML20064C0961994-03-0303 March 1994 Proposed Tech Specs,Reflecting Relocation of Response Time Limits to Usar,Per GL 93-08 ML20063K3721994-02-22022 February 1994 Proposed Tech Specs 3.6.1.8 & 3.6.1.9 Re Penetration Valve Leakage Control Sys Air Compressor ML20063A6301994-01-14014 January 1994 Proposed Tech Specs Reflecting Removal of Component Lists ML20059G8181994-01-14014 January 1994 Proposed Tech Specs Re Surveillance Test Interval & Allowed Outage Time Extension Request 1999-07-30
[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
'
Attochment 3 ,
f PROPOSED CURRENT TECHNICAL SPECIFICATION CHANGES (MARK-UPS & REVISIONS) 9506070229 950530 PDR ADOCK 05000458 P PDR
CONTAI N NT SYSTEMS PECEIVEC ,3 DRWELL BYPASS LEAKAGE # I 4 I99I LIMITING CONDITION FOR OPERATION 6CC 3.6.2.2 Orvwell bypus leakage shall de less thanxennal to 10% of the acceptable A/]k design value of 1.0 fta, APPLICA81LITY: When ORWELL INTEGRITY is required per Specification 3.6.2.1.
ACTION:
With the drywell8 bypass leakage greater than 105 of the acceptable A/4 design value of 1.0 ft , restore the drywell bypass leakage to within the limit prior to incre,asing reactor coolant system temperature above 200*F.
i SURVEILLANCE REQUIREMENTS
, ~.
f year,s 4.6.2.2 At least once per the drywell bypass leakage rate test shall be conducted at an in tial erential pressure of 3.0 psid and the A/4 shall be calculated from the measured leakage. Gne drywell air lock door shall remain open during the drywell leakage test such that each drywell door is leak tested during at least every other leakage rate test.
- a. If any drywell bypass leakage test fails to meet the specified limit,
_ thef::h:t!: f:7. :d ;;_;i.; i.uts shall os rn i. .J ei,. .yy. ...J by j
= 0 ziesion. If two consecutive to s fail to meet the limit, a j test shall be performed at least eve until two consecutive l
- tests meet the limit, at which time le n r.tr test schedule may l
be resumed. (ye,v-i 18 wine f em lt fat./
' L ,6 ~ J ndeZAs{'-
I 2A c kwd'
, - ,c/nh Cf , l i.
4 w nnm "Fordha f frstWir ; , Le Ts..,4.4 to-crir,cid: di.h tt- r="tsel4ar-wTagt; -sen.e.l.ii: b;;4HisptemberTW.
l RIVER BEND - UNIT 1 3/4 6-19 Amendment No. 4,'
\
i CONTA!fe8ENT SYSTEMS RECEIVEC DRYWELL BYPASS LEAKAGE # I 4 1991 ;
LIMITING CONDITION FOR OPERATION 3CC 3.6.2.2 Drywell bypass leakage shall be less than or roual to 105 of the acceptable A//k oesign value of 1.0 ft8 -
APPLICA8ILITY:
When ORWELL INTEGRITY is required per Specification 3.6.2.1.
ACTION:
I With the drywell8 bypass leakage greater than 105 of the acceptable A/4 design value of 1.0 ft , restore the drywell bypass leakage to within the limit prior to increasing reactor coolant systes temperature above 200*F.
SURVEILLANCE REQUIREMENTS l
4.6.2.2 At least once per 5 years the drywell bypass leakage rate test shall be conducted at an initial differential pressure of 3.0 psid and the A//E shall be calculated from the sessured leakage. One drywell air lock door shall remain open during the drywell leakage test such that each drywell door is leak tested during at least every other lea uge rate test. l a.
If any drywell bypass leakage test fails to meet the specified limit, ;
the frequency shall be increased to at least once per 36 months, if the subsequent test i
meets the limit, the 5 year test schedule may be resumed. If two consecutive tests fail to !
meet the limit, a test shall be performed at least every 18 months until two consecutive i
test meet the limit, at which time the 5 year test schedule may be resumed. '
l
\
l i
i l
l RIVER BEND - UNIT 1 3/4 6-19 Amendment No. 4.'
l i
b Attachment 4 i
l 1
PROPOSED IMPROVED STANDARD TECHNICAL SPECIFICATION CHANGES (MARK-UPS & REVISIONS) i l
1 l
l 1
i i
Drycell !
B 3.6.5.1 ;
BASES i SURVEILLANCE SR 3.6.5.1.3 REQUIREMENTS -
(continued) The analyses in Reference 1 are based on a maximum drywell bypass leakage. This Surveillance ensures that the actual l drywell bypass leakage is less than or equal to the acceptable AA / li design value of 1.0 ft' assumed in the safety analysis. As left drywell bypass leakage, prior to the first startup after performing a required drywell bypass ,
leakage test, is required to be s 10% of the drywell bypass leakage limit. At all other times between required drywell leakage rate tests, the acceptance criteria is based on design AM. At the design A/Vli the containment p temperature and pressurization response are bounded by the
[ba ' '
pe form ng
, u yo
'T6s , r s of high radiation exposure, and i
the remote possibility that a component failure that is not w@c- identified b some other drywell or primary containment SR might_o u cc5ch r_: u: D)3rltlafli4:ri':n?:7. 5 S f.peifsf th: $;.f:::Ej;>
,w serc tu ~ eel!y p::: the trv:il1;;;; when
%WS r+k c--~ q y. _T W 1the Frequency was t
conclude'dWacce;ptable from a reliability standpoint.
~
)
i SR 3.6.5.1.4 i The exposed accessible drywell interior and exterior ,
surfaces are inspected to ensure there are no apparent physical defects that would prevent the drywell from >
performing its intended function. This SR ensures that !
drywell structural integrity is maintained. The Frequency was chosen so that the interior and exterior surfaces of the drywell can be inspected in conjunction with the inspections of the primary containment required by 10 CFR 50, Appendix J (Ref. 2). Due to the passive nature of the drywell structure, the specified Frequency is sufficient to identify i component degradation that may affect drywell structural i integrity.
REFERENCES 1. USAR, Chapter 6 and Chapter 15. l i
RIVER BEND B 3.6-120 Draft A
une em - '
4
. . Attachment 4 9
INSERT B1.
This Surveillance is performed at least once every 5 years.
If during the performance of this required Surveillance the drywell bypass leakage rate is > 10% of the drywell bypass leakage limit the Surveilience Frequency is increased to every 36 months. If during the performance of the subsequent consecutive Surveillance the drywell bypass leakage rate is s 10% of the drywell bypass leakage limit the 5 year Frequency may be resumed. If during the l
performance of two consecutive Surveillances the drywell bypass leakage is > 10% of the drywell bypass leakage limit the Sutveillance Frequency is increased to at least once every 18 months. The it month Frequency is maintained until during the performance of two consecutive Surveillances the drywell bypass leakage rate is s 10% of the drywell bypass leakage limit, at which time the 5 year Frequency may be resumed. For two Surveillances to be considered consecutive the Surveillances must be performed at least 12 months apart.
Since the Frequency is performance based, l
l t
i i
n 9
Oryue11 !
. . BASES B 3.6.5.1 I i
)
SURVEILLANCE SR 3.6.5.1.3 REQUIREMENTS (continued)
The analyses cypass leakage.in Reference 1 are based on a maximum drywell i drywell bypass leakageThis Surveillance is less thanensures or equalthat the actual to the acceptable A M design value of 1.0 ft 8 safety analysis. As left drywell bypass assumed in the leakage, prior to the first startup after performing a required drywell bypass leakage test, leakage limit. is At required to be s 10% of the drywell bypass i all other times between required drywell leakage rate tests, the acceptanc criteria is based on design A M . At the design A the containment
- temperature and pressurization response are bounded by the assumptions of the safety analysis. The leakage test is l performed.
on a perfonnance based frequency, consistent with the difficulty of performing the test, risk of high radiation exposure, and the remote possibility that a component failure that is not identified by some other drywell or primary containment SR might occur. This Surveillance is performed at least once every 5 years. If during the performance of this required Surveillance the drywell bypass leakage rate is > 10% of the drywell bypass leakage limit the Surveillance Frequency is increased to every 36 months. If during the performance of the subsequent consecutive Surveillance the drywell bypass leakage rate is s 10% of the drywell bypass leakage limit the 5 year Frequency may be resumed. If durin the performance of two consecutive Surveillances the drywell bypass leakage is >
10% of the drywell bypass leakage limit the Surveillance Frequency is increased to at least once every I8 months. The 18 month Frequency is maintained until during the performance of two consecutive Surveillances the drywell bypass leakage rate is 510% of the drywell bypass leakage limit, at which time the 5 year Frequency may be resumed. For two Surveillances to be considered consecutive the Surveillances must be performed at least 12 months apart. The Frequency was concluded to be acceptable from a reliability standpoint since the frequency is performance based.
SR 3.6.5.1.4 The exposed accessibis drywell interior and exterior surfaces are inspected to ensure there are no apparent physical defects that would prevent the drywell from t performing its intended function. This SR ensures that drywell structural integrity is maintained. The Frequency was chosen so that the interior and exterior surfaces of the drywell can be inspected in conjunction with the inspections l of the primary containment required by 10 CFR 50, Appendix J (Ref. 2). Due to the passive nature of the drywell structure, the specified Frequency is sufficient to identify j component degradation that may affect drywell structural l integrity.
~
l REFERENCES 1. USAR, Chapter 6 and Chapter 15.
I RIVER BEND 8 3.6__120 _ _______ _ ______ _ __ ____ __ ___ _ __O r a f t_ A ___
Drywell 3.6.E.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY
( SR 3.6.5.1.3 Verify bypass leakage is less than or i f40 mv .th l equal to the bypass leakage limit. '^* m L
However, during the first unit startup following bypass leakage testing l
performed in accordance with this SR, the I acceptance criterion is s 10% of the drywell bypass leakage limit.
SR 3.6.5.1.4 Visually inspect the exposed accessible Once prior to interior and exterior surfaces of the performance of drywell. each Type A ,
test required by SR 3.6.1.1.1 I
RIVER BEND 3.6-61 Draft A
'... Acccensent 4 INSERT 1 18 months following 2 consecutive tests with bypass leakage
> 10% of the bypass leakage limic until 2 consecutive l tests are s 10%
of the bypass leakage limit ARE2 36 months following a 1 test with {
bypass leakage {
> 10% of the l bypass leakage limit ARE2
- 5 years l
l 4
u
.. Drywell 3.6.5.1 SURVEILLANCE REOUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3,5.5.1.3 18 months Verify bypass leakage is less than or following 2 equal to the bypass leakage limit. consecutive Mowever, during the first unit startup C#8E8 "iCh following bypass leakage testing bypass leakage performed in accordance with this SR, the a 10 of the acceptance criterion is s 10% of the DW8 l' " 9' drywell bypass leakage limit. l
, g ,
tests are 4 10%
of the bypass leakage limit M
36 months following a test with bypass leakage
> 10% of the bypass leakage limit M
5 years SR 3.6.5.1.4 Visually inspect the exposed accessible Once prior to interior and exterior surfaces of the performance of drywell. each Type A test required by SR 3.6.1.1.1 RIVER BEND 3.6-61 Oraft A
Attachment 5 DRYWELL BYPASS LEAK RATE TEST COSTS (TYPICAL)
Amount Sub-Total Amount Equipment $25,000 $25,000 Compressors (2)
Air Dryer (2)
After Coolers (2)
Manifold (1)
Hoses (vary)
Mechanic Estimated Man-Hrs ($50/hr) 1/ 275 $13,750 Test Director / Test (Man /Hr x Rate =)
l Eng/ Tech Procedure Review Tagging Hook-ups Actual Test Walk-Downs Test Review / Approval Critical Path Time 2/ 24 $432,000
($18,000/HR)
Person Rem 3/ Not included 1 person rem x $15,000 TOTAL -1 DBLRT $470,750 t
TOTAL * $6,590,500 (14 DBLRTs)
NOTES:
- Total of 14 1/ including Contract labor DBLRTs eliminated 2/ not available at this time over remaining 3/ replacement power costs licensed life of the plant (30 years) t___ _.__ . . _ _ _ _ . _ _ . . _ _ _ _ . _ _ _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _.
Attachment 6 ,
PREVIOUS RESULTS OF RBS DRYWELL BYPASS LEAKAGE RATE TESTS t
TEST DATE RATIO TO DESIGN LIMIT CALCULATED A/Yk 2
04/85 1.4% 0.01400 ft (PREOP) 2 j 12/87 1.5 % 0.01500 ft (RF-01 )
2 ;
5/89 0.025 % 0.00025 ft (RF02) 2 11/90 0.861 % .00861 ft i
(RF03) 08/92 1.88 % 0.01880 ft 2 l
l (RF04) !
2 06/94 1.05 % 0.01050 ft l
(RF05) l l
l l
1 W-- ~ ,.