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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] |
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l ATTACIIMENT 3 l
TECilNICAL SPECIFICATIONS CIIANGES l
License Condition 2 C(13) l l Original l
l "The facility shall net be operated with partial feedwater heating beyond the end of the fuel cycle without prior written approval of the staff. During the normal fuel cycle, the facility shall not be operated with a feedwater heating capacity which would result in a rated thermal power feedwater temperature less than 320 F without prior written approval of the staff." l l
Revised "He fee"!!y the!! et M rpreted ":9 pr!e! feet-'e 'er*: ;; byend e end of 6e fue! eye!e
. ..:,qe. .t p :m. m.: .. ., 2pm.m..g me.qg gt3rr During the -^~ 2! power operation fue! :ycle, the facility shall not be operated with a feedwater heating capacity which would result in a rated thermal power feedwater temperature less than 320 *F-w4det pr:c- " :'te appre 72! ef *he g.,
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l 9804160467 980409 PDR ADOCK 05000458 P PDR l
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ATTACHMENT 4 NEDC-32549P l
Note: this document provides the propriettsy portions of the aforementioned request, General l
Electric Report NEDC-32549P. EOI requests that this attachment be held proprietary in accordance with 10 CFR 2.790(b) for the reasons stated in the attached General Electric affidavit.
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I General Electric Company AFFIDAVIT l
l I, George B. Stramback, being duly sworn, depose and state as follows:
(1) I am Project Manager, Regulatory Services, General Electric Company ("GE") and j have been delegated the function of reviewing the information described in '
paragraph (2) which is sought to be withheld, and have been authorized to apply for its withholding.
l (2) The information sought to be withheld is contained in the GE proprietary report NEDC-32549P, Safety Review for River Bend Station Cycle 7 Final Feedwater 7'emperature Reduction, Revision 0, Class 111 (GE Proprietary Information), dated May 1997. The proprietary information is delineated by bars marked in the margin j adjacent to the specific material. l l
(3) In making this application for withholding of proprietary information of which it is 1 l the owner, GE relies upon the exemption from disclosure set forth in the Freedom of Information Act ("FOIA"),5 USC Sec. 552(b)(4), and the Trade Secrets Act,18 USC Sec.1905, and NRC regulations 10 CFR 9.17(a)(4), 2.790(a)(4), and l 2.790(d)(1) for " trade secrets and commercial or financial information obtained from a person and privileged or confidential" (Exemption 4). The material for which l exemption from disclosure is here sought is all " confidential commercial information", and some portions also qualify under the narrower definition of " trade l
l secret", within the meanings assigned to those terms for purposes of FOIA Exemption 4 in, respectively, Critical Mass Enernv Proiect v. Nuclear Regulatory Commission. 975F2d871 (DC Cir.1992), and Public Citizen Health Research Group l v. FDA,704F2dR80 (DC Cir.1983).
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l (4) Some examples of categories of information which fit into the defimition of l proprietary infomiation are:
i
- a. Information that discloses a process, method, or apparatus, including supporting data and analyses, where prevention ofits use by General Electric's competitors without license from General Electric constitutes a competitive economic advantage over other companies;
- b. Information which, if used by a competitor, would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing of a similar product; GBS-97 4-afRBFFWI. doc Amdavit Page 1 L
f 1
j c. Information which reveals cost or price infonnation, production capacities, budget levels, or commercial strategies of General Electric, its customers, or its suppliers;
- d. Information which reveals aspects of past, present, or future General Electric customer-funded development plans and programs, of potential commercial value to General Electric; l
- e. Information which discloses patentable subject matter for which it may be
- desirable to obtain patent protection.
l l The information sought to be withheld is considered to be proprietary for the reasons set forth in both paragraphs (4)a. and (4)b., above.
(5) The information sought to be withheld is being submitted to NRC in conGdence. l The information is of a sort customarily held in confidence by GE, and is in fact so held. The information sought to be withheld has, to the best of my knowledge and belief, consistently been held in conndence by GE, no public disclosure has been made, and it is not available in public sources. All disclosures to third parties including any required transmittals to NRC, have been made, or must be made, pursuant to regulatory provisions or proprietary agreements which provide for maintenance of the information in conndence. Its initial designation as proprietary information, and the subsequent steps taken to prevent its unauthorized disclosure, are as set forth in paragraphs (6) and (7) following.
(6) Initial approval of proprietary treatment of a document is made by the manager of the originating component, the person most likely to be acquainted with the value and sensitivity of the infonnation in relation to industry knowledge. Access to such documents within GE is limited on a "need to know" basis. I (7) The procedure for approval of external release of such a document typically requires j review by the staff manager, project manager, principal scientist or other equivalent l
authority, by the manager of the cognizant marketing function (or his delegate), and !
by the Legal Operation, for technical content, competitive effect, and determination of the accuracy of the proprietary designation. Disclosures outside GE are limited to regulatory bodies, customers, and potential customers, and their agents, suppliers, and licensees, and others with a legitimate need for the information, and then only in accordance with appropriate regulatory provisions or propnetary agreements.
\
l l (8) The information identi6ed in paragraph (2), above, is classified as proprietary I because it contains detailed results of analytical models, methods and processes, including computer codes, which GE has developed, obtained NRC approval mf, and i applied to perform evaluations of different plant conditions and parameters for the BWRs.
l G BS-97-4-atRBFFW l . doc Afridavit Page 2 l
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- l The development and approval of the BWR models, methods, processes and computer codes was achieved at a significant cost, on the order of a million dollars, to GE.
The development of the evaluation process along with the interpretation and anplication of the analytical results is derived from the extensive experience i database that constitutes a major GE asset.
(9) Public disclosure of the information sought to be withheld is likely to cause substantial hann to GE's competitive position and foreclose or reduce the availability of profit-making opportunities. The infonnation is part of GE's comprehensive l BWR safety and technology base, and its commercial value extends beyond the l original development cost. The value of the technology base goes beyond the extensive physical database and analytical methodology and includes development of the expertise to determine and apply the appropriate evaluation process. In addition, the technology base includes the value derived from providing analyses done with NRC-approved methods.
l The research, development, engineering, analytical and NRC review costs comprise a substantial investment of time and money by GE.
l The precise value of the expertise to devise an evaluation process and apply the l correct analytical methodology is difficult to quantify, but it clearly is substantial.
GE's competitive advantage will be lost ifits competitors are able to use the results of the GE experience to normalize or verify their own process or if they are able to l claim an equivalent understanding by demonstrating that they can arrive at the same
! or similar conclusions.
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The value of this intbrmation to GE would be lost if the information were disclosed to the public. Making such information available to competitors without their ,
having been required to undertake a similar expenditure of resources would unfairly l l
l provide competitors with a windfall, and deprive GE of the opportunity to exercise l l
its competitive advantage to seek an adequate return on its large investment in developing these very valuable analytical tools.
i GBS-97-4-afRBFFW1. doc Aflidavit Page 3
B STATE OF CALIFORNIA )
) ss:
COUNTY OF SANTA CLARA )
George B. Stramback, being duly sworn, deposes and says:
That he has read the foregoing affidavit and the matters stated therein are true and correct to the best of his know! edge, information, and belief.
Executed at San Jose, California, this 5~ day of 9451 1997.
V Nefd> $ &
G(orge B. str"amback General Electric Company Subscribed and sworn before me this Sf/t day of 'b/ 1997.
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a.
otary Public, State'of- D5tirolniaT I l JUUE A Cum 5 Commwone insaw ; I Mcry Putsc-CcWorm
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- 8 uvCennDesesoc i
Sarso Clara Courh
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G BS-97-4-afRBFFWl. doc Afridavit Page 4 c_-_.