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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] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20199C1881999-01-0808 January 1999 Revised Page 7 to Rev 13 of RBS Security Training & Qualification Plan ML20202F0361997-11-26026 November 1997 Rev 0 to IST Plan for Pumps & Valves Second Ten-Yr Interval ML20140F0151996-12-26026 December 1996 Rev 6 to RSP-0008, ODCM Procedure ML20116P1341996-08-0808 August 1996 Technical Requirements Manual ML20113F2271996-06-12012 June 1996 Rev 0 to Calculation PI-0103-00203.002-101, Ampacity Derating Evaluation B130180, Surveillance Specimen Program Evaluation for River Bend Station1996-04-30030 April 1996 Surveillance Specimen Program Evaluation for River Bend Station ML20108B5941995-10-0101 October 1995 Rev 5A to River Bend Station Offsite Dose Calculation Manual Procedure ML20076K9161994-10-27027 October 1994 Updates to IST Pump & Valve Program Manual ML20059A8501993-12-23023 December 1993 Near-Term Performance Improvement Plan ML20128D9221993-01-29029 January 1993 Rev 6 to Pump & Valve Inservice Testing Plan for River Bend Station First 10-Yr Insp Interval ML20045E0311992-08-19019 August 1992 Change 92-01 to Rev 3 to RSP-0008, Odcm. ML20114D0711992-08-19019 August 1992 Rev 3 to Odcm ML20086G8411991-10-0202 October 1991 Rev 5 to Inservice Insp Plan for River Bend Station - Unit 1 ML20082M0061991-08-0909 August 1991 Rev 4 to RWS-0204, Radwaste Processing Control Program RBG-35-380, Rev 5B to River Bend Station Pump & Valve Inservice Testing Program Plan. Relief Requests Encl1991-07-26026 July 1991 Rev 5B to River Bend Station Pump & Valve Inservice Testing Program Plan. Relief Requests Encl ML20029B7841991-03-0606 March 1991 Station,Inservice Insp Plan,Summary Rept Refuel Outage RF-3 Second Period,First Interval, Vols 1 & 2 ML20070U7721991-02-26026 February 1991 Rev 4 to River Bend Station Inservice Insp Plan (First Interval) ML20245F0101989-04-24024 April 1989 Rev 2 to Offsite Dose Calculation Manual ML20114B7411989-03-0808 March 1989 Rev 5 to Procedure RWS-0304, Radwaste Handling & Control ML20245F0041989-02-14014 February 1989 Rev 3 to Offsite Dose Calculation Manual Procedure ML20154C9851988-08-16016 August 1988 Rev 3 to Inservice Insp-First Interval ML18053A7101988-03-22022 March 1988 Rev 5 to Pump & Valve Inservice Testing Plan,First 10 Yr Insp Interval. W/880422 Ltr ML20238C3651987-08-13013 August 1987 Rev 1 to Station Operating Procedure RSP-0008, Offsite Dose Calculation Manual Procedure RBG-26506, Rev 4 to Pump & Valve Inservice Testing Plan River Bend Station First 10-Yr Insp Interval. Fee Paid1987-07-29029 July 1987 Rev 4 to Pump & Valve Inservice Testing Plan River Bend Station First 10-Yr Insp Interval. Fee Paid ML20235Y0591987-07-16016 July 1987 Rev 2 to Radwaste Processing Control Program RBG-26044, Rev 2 to Inservice Insp Plan - First Interval1987-06-0202 June 1987 Rev 2 to Inservice Insp Plan - First Interval ML20114B7281987-05-14014 May 1987 Rev 3 to Procedure RWS-0307, Radwaste Segregation RBG-25841, Rev 0 to Procedure RSP-0008, River Bend Station,Offsite Dose Calculation Manual1987-04-30030 April 1987 Rev 0 to Procedure RSP-0008, River Bend Station,Offsite Dose Calculation Manual ML20114B7311987-03-16016 March 1987 Rev 2 to Procedure RWS-0207, Radwaste Shipping Criteria ML20209G3121987-01-0202 January 1987 Rev 3 to Pump & Valve Inservice Testing Plan,River Bend Station,First 10-Yr Insp Interval ML20214T6231986-09-11011 September 1986 Revised Emergency Plan Implementing Procedures,Including Rev 5 to EIP-2-007, Protective Action Recommendation Guidelines & Rev 4 to EIP-2-024, Offsite Dose Calculations Manual Method ML20214N6811986-08-0606 August 1986 Rev 2 to Pump & Valve Inservice Testing Plan,First 10-Yr Insp Interval ML20207E8711986-07-0202 July 1986 Vol 1 to Rev 1 to Pump & Valve Inservice Testing Plan,River Bend Station,First 10-Yr Insp Interval ML20206J1501986-06-20020 June 1986 Rev 4 to River Bend Station Unit 1,Preservice Insp Plan, Final Update ML20238C4141986-05-18018 May 1986 Rev to Nonradioactive Oil/Hazardous Matl Spill Prevention, Control & Countermeasure Plan ML20155G5391986-02-26026 February 1986 Station,Emergency Response Exercise Manual, Evaluated Exercise RBG-22-117, Rev 3 to Offsite Dose Calculation Manual1985-09-16016 September 1985 Rev 3 to Offsite Dose Calculation Manual ML20135A6331985-06-27027 June 1985 Revs to Nuclear Plant Engineering Preservice Insp/Pump & Valve Testing Plan, Replacing Pages 4 & 5 & App F RBG-21363, Rev 0 to Station Operating Procedure ADM-0053, Asiatic Clam Control Program1985-06-21021 June 1985 Rev 0 to Station Operating Procedure ADM-0053, Asiatic Clam Control Program ML20135A9211985-06-17017 June 1985 Rev 1 to OSP-0007, Preparation of Operations Sections Procedures ML20125D2751985-06-10010 June 1985 Updated Rev 1 to Nuclear Plant Engineering Preservice Insp/Pump & Valve Testing Plan ML20129E9531985-06-0606 June 1985 Rev 2 to Station Operating Procedure ADM-0022, Conduct of Operations ML20117P4831985-05-30030 May 1985 Rev 1 to Pump & Valve Inservice Testing Plan,River Bend Station,First 10-Yr Insp Interval RBG-21545, Rev 2 to River Bend Station Offsite Dose Calculation Manual1985-05-27027 May 1985 Rev 2 to River Bend Station Offsite Dose Calculation Manual ML20128E8881985-05-17017 May 1985 Revised Program Plan for Tdi Standby Diesel Generators ML20117P1431985-05-13013 May 1985 Rev 2 to Procedure COP-1050, Post-Accident Estimation of Fuel Core Damage RBG-21-165, Rev 1 to, River Bend Station Offsite Dose Calculation Manual1985-04-24024 April 1985 Rev 1 to, River Bend Station Offsite Dose Calculation Manual ML20129E9591985-03-27027 March 1985 Rev 1 to Station Operating Procedure AOP-0001, Reactor Scram ML20112G4641985-01-0707 January 1985 Offsite Dose Calculation Manual ML20112G4491985-01-0707 January 1985 Rev 0 to Procedure RWS-0204, Process Control Program 1999-01-08
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[ 1.0 INrRODUCTION k '1he Inservice Inspection Plan for -River Bend Station punps and valves -is developed in empliance with 10CFR50.55a and Section XI of _the ASME Boiler and Pressure Vessel Code,1980 Edition, Winter 1981 Addenda. Where conpliance is determined to be inpractical,-
specific relief has been requested.
Section 2.0 discusses the Inservice Testing Plan for applicable Class 1, 2, and 3 pu ps. Section 3.0 discusses the Inservice Testing Program for applicable Class 1, 2, and 3 valves. Note that all information provided should be considered final and may require
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INSERVICE TESTING PLAN
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ISI CLASS 1,2 & 3 VALVES RIVER BEND STATION SYSTEM: Service Water (ISWP*) FSK HO. 9 -1011 SIIEET 1 0F 1 PACE 1250F 140 N $ g$ Q% k VALVE NUMBER x k h REMARKS
/, / a f i M ee # rr p V172 3 B-8 C 30 CK SA. O FSE Q V173 3 B-9 C 30 CK SA 0 FSE Q MOV 501A 3 D-4 B 18 BF M0 O FSE 10 Sec. Stroke Time Q
PI RF MOV 501B 3 D-6 B 18 BF MO O FSE 10 Q Sec. Stroke Time PI 1;F g MOV SilA 3 N-4 B 18 BF MO O FSE 10 Q Sec. Stroke Time, PI RF MOV SilB 3 N-6 B 18 BF M0 O FSE 10 Q Sec. Stroke Time PI RF l
INSERVICE TESTING PLAN ISI CIASS 1,2 & 3 VALVES e :
RIVER BEND STATION SYSTEM: Service Water (ISWP*) FSK NO. 9-10K SHEET 1 0F 1 PAGE 12 60F 14 0 VALVE NUMBER N '
REMARKS MOV 68A 3 H-7 B 18 BF M0 C FSE 10 Q -Sec Stroke Time PI RF MOU 68B 3 N-7 B 18 BF M0 C FSE 10 Q -Sec Stroke Time PI RF vl99 3 H-6 C 18 CK SA C FSE Q 00, 3 N -- 6 C 18 CK SA C FSE Q RV F100 A 3 G-5 C 3/4 RV SA C SP RF 150 psig 4 R 00B 3 M-5 C 3/4 RV SA C SP RF 150 psig I e
INSERVICE TEdnriC PLAN -
ISI CLASS 1.2 & 3 VALVES RIVER BEND STATION SYSTEM: Service Water System (ISWP*) FSK NO. 9-10R SilEET 10F 4 PAGE 130 0F 140
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VALVE NUMBER REMARl(S .
/ / / / i 12 t'Rsht FSE
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-Sec Stroke Time MOV 510A 3- B-8 B CA M0 C 10.11 RF PI RF MOV 510B 3 B-6 B 12 CA M0 C FSE 1 0.11 RF -Sec Stroke Time PI RF I MOV 504A 3 B-4 B 12 GA M0 C FSE 10.11 RF -Sec Stroke Time PI RF MOV 504B 3 B-2 B 12 CA MO C' FSE 1 0.11 RF -Sec Stroke Time PI RF MOV 507A 3 F-10 A 12 CA MO O FSE 10 Q 58 Sec Stroke Time LR RF 10CFR50 App J PI RF MOV 507B 3 F-8 A 12 CA MO O FSE 10 Q 58 Sec Stroke Time LR RF 10CRF50 App J
) PI RF
INSERVICE TESTING PLAN
- ISI CLASS I,2 & 3 VALVES
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RIVER BEND STATION SYSTEM: Service Water (ISWP*) FSK NO. 9-10R SilEET 3 0F 4 PAGE 1320F 140 VALVE NUMBER
/ A. 9 h REMA'RKS MOV 4A 3 J-10 B 12 GA MO O FSE 10 Q -Sec Stroke Time PI RF MOV 4B 3 J-S B 12 GA MO 0 FSE<, 10 Q -Sec Stroke Time PI RF MOV 502A 3 11 - 1 0 B 8 GA M0 C FSE 1 0,11 RF -Sec Stroke Time PI RF l MOV 502B 3 11 - 7 B 8 GA MO C FSE 1 0,11 RF -Sec Stroke Time PI RF MOV SA 3 J-l A 10 GA MO O FSE 10 Q 49 Sec Stroke Time LR RF 10CFR50 App J PI RF MOV SB 3 J-3 A 10 GA M0 O FSE 10 Q 49 Sec Stroke Time LR RF 10CFR50 App J 3
PI RF
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INSERVICE TESTINC PLAN ISI CLASS 1,2 & 3 VALVES RIVER BEND STATION SYSTEM: Service Water (ISWP*) FSK NO. 9-10R . SIIEET 4 0F 4 PAGE 1330F 140
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/ a f e ~9r["/ f MOV 503A 3 11 - 2 A 6 CA M0 C FSE 10,11 RF 30 Sec Stroke Time LR RF 10CFR50 App J PI RF l MOV 503B 3 C-4 A 6 GA M0 C FSE 1 0,11 RF 30 Sec Stroke Time LR RF 10CFR50 App J PI RF l _ _ . _ _ _ _ _____ _ _ . _ _ _ . _ _ _
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INSERVICE TESTING PLAN ISI CIASS 1,2 & 3 VALVES RIVER BEND STATION SYSTEM: Service Water (ISWP*) FSK No. 9-100 SilEET 1 0F - 1 PACE 135A of 140 l: .
VALVE NUMBER h g h h Y
REMARKS N N d b 4 N 8 l*a c $ y *Nf 4 4 g$
MOV 27B 3 B-2 B 6 BF M0 C FSE 10 Q -Sec Stroke Time PI RF MOV 27D 3 C-4 B 6 BF MO C FSE 10 Q -Sec Stroke Time PI RF V79 3 E-2 C 6 CK SA C FSE Q V80 3 E-6 C 6 CK SA C FSE Q V155 3 F-2 C 6 CK SA C FSE Q V156 3 F-5 C 6 CK SA C FSE Q RV 91B 3 H-2 C 1 RV SA C SP RF 150 psig RV 91D 3 11 - 5 C 1 RV SA C SP RF 150 psig
INSERVICE TESTIT4C PLAN ISI CIASS 1,2 & 3 VALVES RIVER BEND STATION SYSTEM: Service Water (ISWP) FSK No. 9-10V SilEET 1 0F 2 PACE 135BOF 140 l4
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VALVE NUMBER -
REMARKS
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Q Sec. Stroke Time LR RF 10 CFR 50 App. J PI RF SOV 522B 2 A GL SO C 10 1 FSE Q Sec. Stroke Time LR RF 10 CFR 50 App. J PI RF SOV 522C 2 A GL SO C 1 FSE 10 Q Sec. Stroke Time LR RF 10 CFR 50 App. J PI R?
SOV 522D 2 A CL SO C 1 FSE 10 Q Sec. Stroke Time LR R? 10 CFR 50 App. J PI R?
SOV 523A 3 B 3/4 GA So C FSE 10 Q Sec. Stroke Time i PI R?
SOV 523B 3 B 3/4 GA SO C FSE 10 4 Sec. Stroke Time PI RF SOV 523C 3 B 3/4 GA SO C FSE 10 Q Sec. Stroke Time PI RF SOV 523D 3 B 3/4 CA SO C FSE 10 Q -
.Sec. Stroke Time PI Rl' SOV 552A 3 B 3/4 GL SO O FSE 10 Q Sec. Stroke Time PI R1' SOV 552B 3 B 3/4 GL SO O FSE 10 Q Sec. Stroke Time PI RI'
INSERVICE TESTTUG PLAN ISI CLASS 1,2 & 3 VALVES RIVER BEND STATION SYSTEM: Service Water (ldWP) FSK No. 9-10V SilEET 2 0F 2 PACE 135COF 140 l8 .
ff VALVE NUMBER g
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REMARKS
/ / ; s V1087 3 C 3/4 CK SA C FSE (!
V1086 3 C 3/4 CK SA C FSE
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I V1091 2 C 1 CK SA C FSE (!
V1092 2 C 1 CK SA C FSE O g V1095 2 C 1 CK SA C FSE (!
V1098 2 C 1 CK SA C FSE Q V1102 3 C lh CK SA C FSE Q v1103 3 C 1 CK SA C FSE C'
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- ISWP*MOV 502A..Bl ' Transfer normal cooling water from Ventillation .3 lB-
' ISWP*HOV 504A, B Chilled Water System or Reactor Plant Component .,
,' ISWP*MOV 510A, B Cooling Water System to._ Standby Service Water ,
' System for Containment Unit Cooler, RHR Pumps,
. and Fhel Pool' Cooling' Heat Exchangers. I
' ISWP*MOV 503A, B Transfer normal cooling water return from 2 A
- Ventillation Chilled Water System to Standby Service Water System for Containment Unit ,
Coolers, i e
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I TEST REQUIREMENT: Valves shall be exercised at least once every 3 months.
l i BASIS FOR RELIEF: Exercising these valves.during normal plant operations will result-in impurities -
i- in the Standby Service' Water System being introduced into the. essentially pure i Reactor Plant Component Cooling Water System and Ventillation Chilled Water System.
Testing during refueling will allow sufficient time to establish provisions to i
prevent cross contamination and/or sufficient time to restore normal. water purity i
- if cross contamination occurs.
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i ALTERNATE TESTING: Full stroke exercise during refueling when provisions can be.taken to prevent j impurities being introduced- into the Reactor Plant Component . Cooling Water System ,
j and Ventillation Chilled Water System.
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