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Category:TECHNICAL SPECIFICATIONS
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[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20212J2721999-10-0101 October 1999 Proposed Tech Specs,Modifying DG Fuel Oil Storage Requirements ML20210G2971999-07-29029 July 1999 Proposed Tech Specs LCO 3.1.7 Re Standby Liquid Control Sys ML20210A4041999-07-15015 July 1999 Ei Hatch Nuclear Plant Unit 1,Extended Power Uprate Startup Test Rept for Cycle 19 ML20204J6031999-03-19019 March 1999 Ei Hatch Nuclear Plant Unit 2 Extended Power Uprate Startup Test Rept for Cycle 15 ML20203C5931999-02-0505 February 1999 Proposed Tech Specs Pages Revising TS to Implement Previously Approved Generic Changes ML20199J9081999-01-21021 January 1999 Proposed Tech Specs Increasing Allowable Values for Reactor Bldg & Refueling Floor Ventilation Exhaust Radiation Monitors ML20197H5171998-12-0404 December 1998 Proposed Tech Specs Section 2.1.1.2,deleting Footnote Which Specifies That SLMCPRs Are for Cycle 18 Only & TS Section 5.6.5.b.2 ML20236U2551998-07-22022 July 1998 Proposed Tech Specs Increasing Allowable Values for High Radiation Trip for Reactor Bldg & Refueling Floor Ventilation Exhaust Monitors ML20217A0861998-04-30030 April 1998 Ei Hatch Nuclear Plant,Units 1 & 2,Process for Implementing Technical Requirements of 10CFR54,License Renewal Rule HL-5558, Edwin I Hatch Nuclear Plant,Unit 1,Power Uprate Startup Test Rept for Cycle 181998-02-17017 February 1998 Edwin I Hatch Nuclear Plant,Unit 1,Power Uprate Startup Test Rept for Cycle 18 ML20197K1861997-12-18018 December 1997 Marked-up Pages to Licenses DPR-57 & NPF-5,respectively. Proposed Changes Delete or Modify Existing License Conditions,Surveillance Requirements That Have Been Completed & Exemptions That Are No Longer in Effect ML20211J1861997-10-0101 October 1997 Corrected TS Pages Unit 1 & 2 Page 3.4-8,Unit 1 Page 3.5-6 & Unit 2 Page 3.5-5 Provided in Order for Util to Issue Amends 208 & 150 to Manual Holders ML20211A2301997-09-19019 September 1997 Proposed Tech Specs Page 2.0-1 & Corresponding mark-up Page Re SLMCPR ML20210J0491997-08-0808 August 1997 Proposed Tech Specs,Allowing Plant to Operate at Uprated Power Level of 2763 Mwt Which Represents Power Level Increase of 8% HL-5438, Ei Hatch Nuclear Plant - Unit 2 Power Uprate Startup Test Rept for Cycle 141997-07-21021 July 1997 Ei Hatch Nuclear Plant - Unit 2 Power Uprate Startup Test Rept for Cycle 14 ML20141B7591997-05-0909 May 1997 Proposed Tech Specs 2.1.1.2,revising Safety Limit Minimum Critical Power Ratio to Reflect Results of Cycle Specific Calculation Performed for Unit 1 Operating Cycle 18,expected to Commence in Nov 1997 ML20141B8561997-05-0909 May 1997 Proposed Tech Specs,Revising Operability Requirements for Rod Block Monitor Sys HL-5376, Proposed Tech Specs 3.4.9 Re Reactor Coolant Sys Pressure & Temp Limits1997-04-29029 April 1997 Proposed Tech Specs 3.4.9 Re Reactor Coolant Sys Pressure & Temp Limits ML20133F3641997-01-0707 January 1997 Proposed Tech Specs Providing Alternate Method of Testing S/Rvs During Shutdown Conditions Rather than During Unit Startup as Is Currently Done ML20138G6271996-12-19019 December 1996 Rev 11 to ODCM for Ei Hatch Nuclear Plant ML20132G2261996-12-17017 December 1996 Proposed Tech Specs Re pressure-temp Limits ML20132E0161996-12-13013 December 1996 Proposed Tech Specs Re Physical Security & Contigency Plan & Guard Training & Qualification Plan ML20135D4881996-12-0303 December 1996 Proposed Tech Specs Revising SLMCPR Values Based Upon Unique plant-evaluations for Current Cycle 13 & Use of GE-13 Fuel in Next Cycle 14 ML20129H9181996-10-29029 October 1996 Proposed Tech Specs,Associating Changes W/Installation of Digital Power Range Neutron Monitoring Sys & Incorporation of long-term Stability Solution Hardware ML20128M8701996-10-0707 October 1996 Proposed Tech Specs to Licenses DPR-57 & NPF-5,increasing Nominal Mechanical Pressure Relief Setpoints for All SRVs & Allow Operation W/One SRV & Associated Functions Inoperable ML20113F5541996-09-19019 September 1996 Proposed Tech Specs,Clarifying Applicability of Certain Surveillances Addressing Rvp & Temp Limits & Replacing Vessel Pressure & Temp Limit Curves W/New Curves ML20117M2251996-09-11011 September 1996 Proposed Tech Specs,Authorizing Southern Nuclear to Become Licensed Operator & to Have Exclusive Responsibility & Control Over Physical Const,Operation & Maint of Plant HL-5192, Edwin I Hatch Nuclear Plant,Unit 1,Power Uprate Startup Test Rept for Cycle 171996-07-18018 July 1996 Edwin I Hatch Nuclear Plant,Unit 1,Power Uprate Startup Test Rept for Cycle 17 ML20115J4861996-07-16016 July 1996 Proposed Tech Specs,Reflecting Changes Through June 1996, Satisfying Requirements of 10CFR50.71 ML20212C1491996-05-31031 May 1996 Stability Monitor ML20117H1391996-05-21021 May 1996 Proposed Tech Specs 3.5.2,ECCS - Shutdown & 3.5.2.2.b SR for Units 1 & 2 Revise to Change Unit 1 CST Water Level Requirement from 12 Feet to 13 Feet & Change Unit 2 CST Water Level Requirement from 12 Feet to 15 Feet ML20100P1041996-03-0404 March 1996 Ei Hatch Nuclear Plant Unit 2 Power Uprate Startup Test Rept for Cycle 13 ML20100H7431996-02-21021 February 1996 Proposed Tech Specs,Revising Changes of Drywell Air Temp LCO from 350 F to 150 F ML20094K3831995-11-10010 November 1995 Proposed Tech Specs,Reflecting Implementation of 10CFR50,App J,Option B ML20093G9401995-10-0505 October 1995 Inservice Insp Program Third 10-Year Interval for Ei Hatch Nuclear Plant Units 1 & 2 ML20092H6461995-07-24024 July 1995 Ei Hatch Nuclear Plant Units 1 & 2 IST Program ML20085K4011995-06-20020 June 1995 Proposed Tech Specs for Power Uprate ML20086E8471995-06-19019 June 1995 Rev 0 to Field Disposition Instruction (Fdi) HT2-0121-12900. Fdi Documents Design Requirements & Matl Required to Install Stabilizers for Shroud Horizontal Welds ML20086E8311995-06-0909 June 1995 Rev 0 to Fabrication Spec 25A5719, Fabrication of Shroud Stabilizer ML20086E8141995-06-0606 June 1995 Rev 1 to Code Design Spec 25A5717, Shroud Stabilizers ML20085A1661995-06-0606 June 1995 Proposed Tech Specs Re Secondary Containment Draw Down & Vacuum Surveillance Requirement Acceptance Criteria ML20086E8121995-05-17017 May 1995 Rev 0 to Design Spec 25A5718, Shroud Repair Hardware ML20082V3791995-05-0404 May 1995 Proposed Tech Specs,Minimizing Thermal Stratification Events ML20082L3331995-04-14014 April 1995 Proposed Tech Specs Re Elimination of Selected Response Time Testing Requirements from TS ML20081F3471995-03-14014 March 1995 Proposed Improved Ts,Permitting Drywell & Wetwell Purge Valves Isolated by Drywell Radiation Monitor Signal to Be Opened W/Inoperable Drywell Radiation Monitor ML20077S0331995-01-13013 January 1995 Proposed Tech Specs Allowing Plant to Operate at Uprated Power Level of 2558 Mwt ML20077D8921994-12-0202 December 1994 Proposed Deleted ETS ML20078G7161994-11-0101 November 1994 Proposed Tech Specs,Converting Current TSs to Improved TS Consistent w/NUREG-1433 ML20076L6911994-10-19019 October 1994 Proposed Improved Tech Specs,Rev F ML20149G3751994-10-13013 October 1994 Proposed Tech Specs,Lowering ATWS-RPT Setpoint by Approx 2 Ft 2 Inches Allowing Restarting Recirculation Pump Following RPT When Temp Differential Between Coolant at Reactor Bottom Head & Reactor Steam Dome Cannot Be Obtained 1999-07-29
[Table view] |
Text
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SLs 2.0 2.0 SAFETY LIMITS'(SLs) 2.1 SLs- l 2.1.1 Reactor Core SLs 2.1.1.1 With the reactor steam dome pressure < 785 psig or core flow < 10% rated core flow:
THERMAL POWER shall be s 25% RTP.
2.1.1.2 With the reactor steam dome pressure a 785 psig and core
' flow 210% rated core flow:
MCPR shall be 21.10 for two recirculation loop operation or 21.12 for single recirculation loop operation.
2.1.1.3 Reactor vessel water level shall be greater than the top of active irradiated fuel.
2.1.2 Reactor Coolant System (RCS) Pressure SL Reactor steam dome pressure shall be s 1325 psig.
2.2 SL Violations With any SL violation, the following actions shall be completed:
2.2.1 Within I hour, notify the NRC Operations Center, in accordance with 10 CFR 50.72.
2.2.2 Within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s:
2.2.2.1 Restore compliance with all SLs; and 2.2.2.2 Insert all insertable control rods.
2.2.3 Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, notify the plant manager, the corporate executive responsible for overall plant nuclear safety, and the offsite review committee.
9705160025 970509' DR ADOCK 050003 1 (continued)
HATCH UNIT 1 2.0-1 MCPR ,
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SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs 2.1.1.1 With the reactor steam dome pressure < 785 psig or core flow < 10% rated core flow:
THERMAL POWER shall be s 25% RTP.
2.1.1.2 With the reactor steam dome pressure h 785 psig and core flow 210% rat igor flow:
1.10 MCP ska be 2 htP or two recirculation loop operation or a F 00- r sin e recirculation loop operation.
i.I 2.1.1.3 Reactor vessel water level shall be greater than the top of active irradiated fuel.
2.1.2 ' Reactor Coolant System (RCS) Pressure SL Reactor steam dcme pressure shall be s 1325 psig.
. 2.2 SL Violations With any SL violation, the following actions shall be completed:
^
2.2.1 Within I hour, notify the NRC Operations Center, in accordance l
with 10 CFR 50.72. !
1 2.2.2 Within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s:
2.2.2.1 Restore compliance with all SLs; and 2.2.2.2 Insert all insertable control rods.
2.2.3 Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, notify the plant manager, the corporate executive responsible for overall plant nuclear safety, and the offsite review committee.
(continued)
HATCH UNIT 1 2.0-1 = Amend::r.t-Nor-195-~
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1 I ATTACllMENT 1 Edwin I. Ilatch Nuclear Plant - Unit 1 Request to Revise Technical Specifications:
Safety Limit Minimum Critical Power Ratios (SLMCPR)
Affidavit of Proprietary Information i
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4 9 [ws GENuclentEnergy i GeneralBeat Company P. O Bon 7M 1%mmgns, hC 26@2
I, James F. Klapproth, being duly sworn, depose and state as follows: i l
l i- (1)I am Manager, Product Definition, General Electric Company ("GE") and have been delegated the ftmction of reviewing the information described in paragraph (2) which is sought to be withheld, and have been authorized to apply for its withholding.
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(2) The information sought to be withheld is contained in the letter number HL-5368 from H. L. Sumner,.fr. to NRC, Proposed Change to Edwin L Hatch NuclearPlant Unit 1 Technical l Specification Conceming the Safety Limit Minimum Critical Power Ratio (SLMCPR), April 15, l 1997. The proprietary text is denoted by enclosure within double brackets.
!S) In making this application for withholding of proprietary information of which it is the j owner, GE relics upon the exemption from disclosure set forth in the Freedom of 3 3' 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) and 2.790(a)(4) for " trade secrets
- . and commercial or financial information obtained from a person and privileged or confidential" (Exemption 4). The material for which exemption from disclosure is here i
sought is all " confidential commercial infonnation," and some portions also qualify under the narrower definition of " trade secret," within the meanings assigned to those tenns for purposes of FOIA Exemption 4 in, respectively, Critical Mass Encrev Project v.
Nuclear Regulatory Commission. 975F2d871 (DC Cir.1992), and Public Citizen Health Research Groun v. FDA. 704F2dl280 (DC Cir.1983).
(4) Some examples of categories ofinformation which fit into the defimition of proprietary infonnation are:
- a. Information that - discloses a process, method, or apparatus, including i 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;
- c. -Infonnation which reveals cost or price information, production capacities, .
budget levels, or commercial strategies of General Electric, its customers, or its !
suppliers; i
, d. Information which reveals aspects of past, present, or future General Electric !
customer-funded development plans and programs, of potential commercial i value to General Electric; ' -
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- e. _Information which ! discloses patentable' subject matter for.which it may be desirable to obtain patent protection.
. The information sought'to be withheld is considered to' be proprieta.y for the reasons set forth in both paragraphs (4)a. and (4)b., above. !
(5) The infonnation sought to be withheld is being submitted to NRG in confidence. The .;
infonnation is of a sort customarily held in confidence by GE, and is in fact so held. Its:
initial' designation as proprietary information, and the subsequent steps taken to prevent - i its unauthorized disclosure, are as set forth in (6) and (7) following. The infonnation j sought to be withheld has, to the best of my knowledge and belief, consistently been held . j in confidence 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 j agreements which provide for maintenance of th' e infonnation in confidence.
(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 information in relation to industry knowledge. Access to such !
documents within GE is limited on a "need to know" basis. I 1
, (7) The procedure for approval of external release of such a document typically requires. :
review by the staff manager, project manager, principal scientist or other equivalent 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 j accuracy of the proprietary designation. Disclosures outside GE are limited to regulatory l bodies, customers, and potential customers, and their agents, suppliers, and licensees,
- and othen with a legitimate need for the information, and then only in accordance with appropriate regulatory provisions or proprietary agreements.
(8) The information identified in paragraph (2) is classified as proprie*ary because it contains details of GE's Safety Limit MCPR analysis and the corresponding results which ;
GE has applied to El Hatch Unit I actual core design for cycle 18 with GE's GEIS fuel.
i The development of the methods used in these analysis, along with the testing, !
development and approval of the supporting critical power correlation was achieved at a significant cost, on the order of several million dollars, to GE.
(9) Public disclosure of the infonnation 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 fuel design is part of GE's comprehensive BWR safety and ;
-technology base, and its commercial value extends beyond the original development !
s 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 NRG-approved methods. ;
, The research, development, engineering, analytical, and NRC review costs comprise a substantialinvestment of time and money by GE.
. The precise value of the expertise to devise an evaluation process and apply the correct analytical methodology is difficult to quantify, but it clearly is substantial. i Page 2 l 1
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l GE's competitive advantage will be lost ifits competitors are able to use the results of the GE experience to nonnalize or verify their own process or if they are able to claim an equivalent understanding by demonstrating that they can anive at the same or similar conclusions.
The value of this information to GF 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 provide ;
competitors with a windfall, and deprive GE of the opportunity to exercise its competitive advantage to seek an adequate return on its large investment in developing these very valuable analytical tools.
State of North Carolina ) gg',
County of New lianover )
Ja mes F. Klapproth, being duly sworn, deposes and says:
That he has read the foregoing affidavit and the matters stated therein are true and correct to the 1 est of his knowledge, infonnation, and belief.
-th Executed at Wilmington, North Carolina, this il dayof hG .19 %
c t 1sV Wh James F. Klapproth h General Electric Company Subscribed and sworn before me this l day of 'l[ .1997
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ATTACIIMENT 2 Edwin L IIatch Nuclear Plant - Unit I Request to Revise Technical Specifications:
Safety Limit Minimum Critical Power Ratios (SLMCPR)
Nonproprietary Version of the Basis for Change Request l
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