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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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GULF STATES UTILITIES COMPANY I RIVER BEND STATION-UNIT 1 STARTUP TEST REPORT (SUPPLEMENT 7) 15 APRIL 1988
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5
d STARTUP TEST REPORT (SUPPLEMENT 7)
- 1. The River Bend Unit 1 Startup Teat Program officially was concluded on June 16, 1986. This report contains an update on the status of test exceptions which were open as of the January 27, 1988 supplement to the Gulf States Utilities Company, River Bend Unit 1, Startup Test Report. Since the January 27th report, no test exceptions have been closed. A total of thirteen (13) open test exceptions remain.
- 2. All open test exceptions are categorized as affecting level 2 criteria or lower. Any level I critoria failures referenced in previous reports were downgraded to level 2 criteria as a result of appropriate engineering analysis and are considered level ? 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 cleared for continued safe full power operation.
- 3. Currently, the exceptions are assigned to the individual system engineers to which the exceptions are applicable. It is felt that each engineers's knowledge of the system would thus aid in expediting the closure of the exceptions.
Page 2 of 6
ST-1 Chemistry and Radiochemistry TE 13: !! EPA pre-filter efficiency did not meet level 2 acceptance criteria. Existing radionuclide levels continue to be insufficient to adequately measure filter efficiency. Data is being reviewed by GSU and it may be possible to close the TE, as is.
STATUS: Open TE 16: Insufficient radionuclide levels to determine off-gas pre- and post treatment monitor response versus release rate. This exception is to be resubmitted to the FRC for review and possible acceptance.
STATUS: Open Note: These level 2 test exceptions have been evaluated as not impacting safe, full power operation.
ST-13 Process Computer TE 12: Temperature calibration problems were discovered as a result of EOP testing. These problems are still in t'.se process of being corrected. Testing will be completed upon corrective maintenance on RTD calibration problem.
Instrumentation and Controls calibration work is being worked as manpower permits. This level 2 exception was evaluated as not impacting safe, full power operation.
STATUS: Open ST-22 Pressure Regulator TE 22: Pressure regulator failed level 2 criteria for incremental regulation. This exception will require i retest, and a test procedure has been drafted by on-site j GE personnel which will perform the retest. This exception has been determined not to impact safe, full power operation.
STATUS: Open i
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ST-23A Water Level Setpoint, Manual Feedwater Flow Changes i
TE 19: Results of feedwater study by GE nearly complete to determine required modifications (if any) to conduct !
retest. Retest is required due to flow transmitters ;
being recalibrated. A retest procedure for this test exception has been drafted by on-site GE personnel.
This level 2 exception was evaluated as not impacting ,
safe, full power operation.
STATUS: Open ,
ST-25C/D Main Steam Line Flow Instrumentation '
TE 3: The elbow tap flow versus delta P curves are not within
+5% of the design curves. Elbow tap flou data was taken Buring power oscension following the First Refueling
- Outage (RF-1). Engineering is evaluating field data to determine required main steam line flow instrumentation calibration changes. A Modification Request (MR) is ,
being processed to change applicable vendor i j documentation. General Electric has evaluated this data
- and agreed that this level 2 test exception does not j impact safe, full power operation. !
i i STATUS: Open ST-30C Recirculation System Performance i
i TE 3: The Flow Control Valve mismatch that existed was reduced
! from 14% to 7% and the core and drive flow shortfalls l have been resolved. GE and GSU evaluation is continuing I on resolving the M ratio below design acceptance for Loop B problem. Retest will be necessary to satisfy the disposition of the M ratio problem due to the reduced Flow Control Valve mismatch. A retest procedure has been drafted by on-site GE personnel. This level 2 test exception does not impact safe, full power operation. .
STATUS: Open t
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l ST-74 Offgas System ,
TE 14: This TE was created as a result of the level 2 failures resulting from the retest of TE 12. The data from the rotest is being evaluated by GSU for diaposition. This level 2 test exception does not impact safe, full power operation.
STATUS: Open i
ST-95 Emergency Response Information System TE 3: Module SD-10 for performing scram timing failed. . Work requests for correcting the problem was completed. ,
q' However, this module failed again. during the retest. l Plant Maintenance and Engineering personnel have not yet determined the cause of the second failure. This level 2 exception does not impact safe, full power operation.
STATUS: Open t
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ST-100 Piping Vibration TE 16: Vibration data for MSS Points T42 and T220 was not available due to failure of ERIS data collection panel !
4 113. Panel 113 has been repaired. Lanyard pots for ;
MSS-T220 were refurbished and calibrated during the !
first refueling outage. This level 2 test exception ,
does not impact safe, full power operation. ,
I STATUS: Open TE 20: During generator load rejection (ST-27) points MSS I. T-42Z, T-235X, Y, & Z, & FWS T-144X failed level 1 s
- criteria. MSS T-42X and FWS T-144Y and Z failed level 2 criteria. No data was available for condensate test l point T/S-525 since CNN-AOV 119 failed to open. This test exception is open pending retest. Computer pointe ;
l are available. The lanyard pots for points MSS-T235, ,
I CNM-T525 and FWS-T144 were refurbished and calibrated ;
during the first refueling outage. The test data was reviewed and found acceptable for continued safe, full power operation (downgraded to level 2) by S&W/NuPE.
STATUS: Open i ,
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TE 21: Test points MSS T-200, FWS T-39, SVV T-39, and T-35 were not operable during generator load rejection. Requires repair to ERIS data collection panel 107. This work was not scheduled for the refueling outage, however, the piping vibration sensors in the field were checked out.
This level 2 test exception remains open for ratest and does not impact safe, full power operation.
STATUS: Open ST-104 ESF Area Cooling TE 2: Measured ESP room temperature in the HPCS, RCIC, gHR A, RHR B, RHR C, exceed level 3 criteria of 90 F. No further progress has been made since the last supplement update. This level 3 test exception does not impact safe, full power operation.
STATUS: Open d
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. 6 GULF STATES UTILITIES COMPANY A414 85 4D $f Af TON POST OFFICE 801 220 SY f AANCIS%iLLE Lou!51ANI 70'76 ARE A Coot 604 63% 6094 346 4651 April 29, 1988 RBG- 27778 File Nos. 09.5, G9.25.1.5 U.S. Nuclear Regulatory Commission Document Control Desk k'ashington, D.C. 20555 Gentlemen:
River Bend Station - Unit 1 Docket No. 50-458 Enclosed is Supplement 7 to the Startup Report for River Bend Station - Unit 1. This report covers the period through April 15, 1988. This information is provided pursuant to Technical Specifications 6.9.1.2 and 6.9.1.3 and Regulatory Guides 1.16 and 1.68. An additional report will follow within three months pursuant to Technical Specification 6.9.1.3.
Sincerely.
. 2* /$ e-c 4 J. E. Booker Manager-River Bend Oversight River Bend Nuclear Group JEB/LAE/ /ch Enclosure ec: U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 NRC Resident Inspector P.O. Box 1051 St. Francisvfile LA 70775 l
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