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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 REPORT
MONTHYEARRBG-44355, Cycle 8 Startup Physics Test Summary1998-01-19019 January 1998 Cycle 8 Startup Physics Test Summary ML20116M8051992-08-31031 August 1992 Reactor Containment Building Integrated Leak Rate Test for River Bend Station ML20043D4611990-05-30030 May 1990 Suppl 16 to Startup Test Rept, for Period Through 900530. W/900601 Ltr ML20042E9891990-04-27027 April 1990 Suppl 15 to Startup Test Rept. W/900430 Ltr ML20006C5581990-01-27027 January 1990 Unit 1 Startup Test Rept (Suppl 14). W/900131 Ltr ML19354D4471989-10-31031 October 1989 Startup Test Rept (Suppl 13), for Period Through 891027. W/891031 Ltr RBG-31323, Unit 1 Startup Test Rept (Suppl 12), Covering Period Through 8907271989-08-0404 August 1989 Unit 1 Startup Test Rept (Suppl 12), Covering Period Through 890727 ML20246M6951989-05-31031 May 1989 Reactor Containment Bldg Integrated Leakage Rate Test Types A,B & C Periodic Test RBG-30602, Unit 1 Startup Test Rept (Suppl 11)1989-04-27027 April 1989 Unit 1 Startup Test Rept (Suppl 11) RBG-29153, Suppl 9 to River Bend Station Unit 1 Startup Test Rept1988-10-13013 October 1988 Suppl 9 to River Bend Station Unit 1 Startup Test Rept RBG-28346, Startup Test Rept (Suppl 8) for Unit 11988-07-18018 July 1988 Startup Test Rept (Suppl 8) for Unit 1 ML20043A9081988-05-25025 May 1988 Determination of Fast Neutron Flux Density & Fluence:River Bend Station. RBG-27778, Suppl 7 to River Bend Station Unit 1 Startup Test Rept1988-04-15015 April 1988 Suppl 7 to River Bend Station Unit 1 Startup Test Rept RBG-27434, Suppl 6 to River Bend Station-Unit 1 Startup Test Rept1988-01-27027 January 1988 Suppl 6 to River Bend Station-Unit 1 Startup Test Rept RBG-26875, Gulf States Utils Co,River Bend Station-Unit 1 Startup Test Rept (Suppl 5)1987-10-27027 October 1987 Gulf States Utils Co,River Bend Station-Unit 1 Startup Test Rept (Suppl 5) RBG-26366, Suppl 4 to Gulf States Utils Co River Bend Station Unit 1 Startup Test Rept1987-07-28028 July 1987 Suppl 4 to Gulf States Utils Co River Bend Station Unit 1 Startup Test Rept ML20210B2831987-04-23023 April 1987 Suppl 3 to Startup Test Rept ML20212C8861987-01-30030 January 1987 Suppl 2 to Startup Test Rept ML20214P2001986-11-18018 November 1986 Suppl 1 to Startup Test Rept RBG-24132, Startup Test Rept,River Bend Unit 11986-07-31031 July 1986 Startup Test Rept,River Bend Unit 1 ML20132B2801985-08-31031 August 1985 Evaluation of CLASIX-3 Conservatisms & Quarter-Scale Tests ML20134H2151985-06-30030 June 1985 Ani/Maerp Std Method of Fire Tests of Cable & Pipe Penetration Fire Stops:Internal & External Seal of Aluminum Conduits,B&B/Promatec CTP-1092,A Issue & CTP-1093,A Issue, Final Rept ML20134G8601985-04-30030 April 1985 Reactor Containment Bldg Integrated Leakage Rate Test, Types A,B & C,Preoperational Test ML20094N7891984-01-13013 January 1984 GE Plant Piping Analysis Ii,Design Memo 150-96 ML19305E7131980-03-20020 March 1980 Rept of Potential Alkali Reactivity ASTM C227. ML19305E6841980-03-11011 March 1980 Rept on Potential Alkali Reactivity ASTM C227 & C-289. ML19322E9601980-02-20020 February 1980 Rept of Potential Alkali:Reactivity,Astm C227. ML19322E9631980-02-20020 February 1980 Rept of Potential Alkali:Reactivity,Astm C227. ML19322E9521980-02-12012 February 1980 Rept of Potential Alkali:Reactivity,Astm C227 & C289. ML19322E9531980-02-12012 February 1980 Rept of Potential Alkali:Reactivity,Astm C227 & C289. ML19322E9471980-01-23023 January 1980 Rept of Potential Alkali:Reactivity,Astm C227. ML19322E9461980-01-23023 January 1980 Rept of Potential Alkali:Reactivity,Astm C227. ML19322E9341980-01-15015 January 1980 Rept of Potential Alkali:Reactivity,Astm C227 & C-289. ML19322E9381980-01-15015 January 1980 Rept of Potential Alkai:Reactivity,Astm C227 & C-289. ML19294B2821979-12-20020 December 1979 Rept of Potential Alkali Reactivity ASTM C-227 & C-289 for Gulf States Utils Co - S&W Agent, for Fine Aggregate ML19294B2871979-12-20020 December 1979 Rept of Potential Alkali Reactivity ASTM C-227 & C-289 for Gulf States Utils Co - S&W,Agent for Number 57 Coarse Aggregate 1998-01-19
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.e GULF STATES UTILITIES COMPANY fWIR MND STAnDN POST OFTbCi SOk 270 bl FFtANCbSVRtl LOUl$1AhA 7017%
AREA CODE 604 M5 6M*4 $46 BCE) t April 30, 1990 RBG- 327 56 File Nos. G9.5, G9.25.1.5 U. S. Naclear Regulatory Cmmission Document Control Desk -
Washington, D.C. 20555 Gentlemen
. 1 River Bend Station - Unit 1' !
b Docket No.>50-458 f Enclosed -is Supplement 15 to the Startup Test Report for River Bend Station - Unit 1. This report covers the period through April 27, 1990.
This inunnation is provided pursuant to Technical Specifications 6.9.1.2 and 6.9.1.3 and Regulatory Guides 1.16 and 1.68. : An additional report will. follow within three nonths pursuant - to- Technical Specification 6.9.1.3.
Sincerely, l-j
/ e'4
. H. Cdell Manager-Oversight River Bend Nuclear Group Enclosure '
cc: U. S. Nuclear Regulatory Cmmission Region IV 611 Ryan Plaza Drive, Suite 1000 ;
Arlington, TX 76011
, )
NRC Resident Inspector P.O. Box 1051 St. Francisville, IA 70775 Mr. Walt A. Paulson I Project Manager, River Bend Station 1 Document Control Desk Washington, D.C. 20555 h j P005070068 900427
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i STMTUP TEST REFORT'(SUPPI2MElff 15)- :
.27 APRIL 1990
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n-STARTUPTESTREPORT(SUPPLEMENT 15)
- 1. The River Bend - Unit 1 Startup Test Program was concluded on :
June 16, 1986. This supplemental report provides the current '
status of open test Exceptions from the January 27,- 1990 supplement of the Gulf States Utilities Company, River Bend Station - Unit 1. Startup Test Report. Since the January-27, 1990 report, six test-exceptions have been closed and three open test exceptions remain,. These three remaining _ test exceptions are scheduled to be closed by June 1990.
-2. A11~open test' exceptions are categorized as affecting level 2 criteria or lower. Any level I criteria failures- referenced in ' previous supplements were downgraded to level 2 criteria as a result of- appropriate engineering analysis and are considered level 2- criteria in this report, This is
- consistent with the treatment of-all test criteria referenced in the initial Startup Test Report. All open test exceptions were evaluated and approved by the on-site review committee.
for continued, safe,' full power _ operation of River Bend Station - Unit 1,.
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- 3. Currently, the test exceptions are assigned to the individual !
system engineers to which the exceptions are most applicable, ;I It is believed that each engineer's knowledge of the system will aid in expediting the closure of the test exceptions.,
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ST-22 Pressure Regulator I
'IE-22: Status Opm The main turbine pressure regulator failed the level- 2 criteria for incremental regulation. Operation of the systs through actual plant < transients, including recirculation system flow control valve runbacks, single-loop operation, power changes at various rates and numerous startups and shutdowns since initial criticality, has- denonstrated -that this syste performs' I satisfactorily. Engineering is evaluating data collected ~ during plant power maneuvers to evaluate the closure of this test exception. This exception has been determined 'not~ to impact safe, full power operation.
ST-25C/D Main Steam Line Flow Instrtsaantation
'JE-3 : Status: Open
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'Ihe elbow tap flow versus delta P curves are not within +.5% of the design curves. Elbow tap flow data were taken during~ power ascension following the first refueling outage. Engineering is evaluating field data to determine required main steam line flow instrumentation calibration changes. General Electric (GE) has-evaluated this data and has agreed with GSU that this~ level 2 ;
test exception does not impact safe, full power operation. '
ST-30C Hecirculation Systen Performance ;
'IE-3 : Status: Open The recirculation system flow control valve mismatch that existed was reduced frun 14% to 7% and the core and drive flow shortfalls l have been resolved. Evaluation 'is continuing to resolve the ;
below design acceptance of the M ratio for the loop B problem. t Retest may be required to adequately disposition the M ratio problem due to the reduced flow control valve mismatch.D . A retest procedure has been drafted by on-site GE personnel. Evaluation of data obtained during plant power maneuvers continues. .This level 2 test exception does not impact safe, full. power operation.
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