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MONTHYEARML20082D2221983-11-16016 November 1983 Application to Amend License DPR-40,revising Tech Specs to Incorporate Administrative Changes to Achieve Agreement Between Tech Specs & New Reporting Requirements,Effective 840101 Project stage: Request ML20082D2291983-11-16016 November 1983 Proposed Tech Specs Re Administrative Controls Project stage: Other ML20082D2151983-11-18018 November 1983 Forwards Application for Amend to License DPR-40,revising Tech Specs to Incorporate Administrative Changes to Achieve Agreement Between Tech Specs & New Reporting Requirements, Effective 840101.Certificate of Svc Encl Project stage: Request ML20083G6201983-12-30030 December 1983 Proposed Changes to Tech Specs Deleting Licensee & Significant Event Reporting Requirements & Changing Wording Project stage: Request ML20083G6051983-12-30030 December 1983 Revised Application for Amend to License DPR-40,consisting of Proposed Tech Spec Changes Re Deletion of Licensee & Significant Event Reporting Requirements & Changing Wording Project stage: Request ML20126K5041985-06-17017 June 1985 Proposed Tech Specs Revising LER Sys,Per Generic Ltr 83-43 Guidelines Project stage: Other ML20126K3921985-06-17017 June 1985 Application for Amend to License DPR-40,revising 831118 Application for Amend Re LER Sys.Rev Prepared for Generic Ltr 83-43 Guidelines Project stage: Request ML20202J8351986-07-0808 July 1986 Proposed Tech Specs,Incorporating Reporting Requirements of 10CFR50.72 & 50.73,per Generic Ltr 83-43 Project stage: Other ML20202J8011986-07-0808 July 1986 Supplemental Application for Amend to License DPR-40, Revising Tech Specs to Incorporate Reporting Requirements of 10CFR50.72 & 50.73,per Generic Ltr 83-43 Project stage: Supplement ML20214K4301986-08-13013 August 1986 Safety Evaluation Supporting Amend 99 to License DPR-40 Project stage: Approval ML20214K4241986-08-13013 August 1986 Amend 99 to License DPR-40,revising Tech Specs to Incorporate Requirements of 10CFR50.72 & 50.73 Project stage: Other ML20214K4111986-08-13013 August 1986 Forwards Amend 99 to License DPR-40 & Safety Evaluation. Amend Changes Tech Specs to Incorporate Requirements of 10CFR50.72 & 50.73 Project stage: Approval 1983-12-30
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20195B4441999-05-26026 May 1999 Proposed Tech Specs Relocating pressure-temp Curves, Predicted Radiation Induced NDTT Shift Curve & LTOP Limits to FCS Unit 1 RCS pressure-temp Limits Rept ML20205J7671999-03-31031 March 1999 Proposed Tech Specs Increasing Min Required RCS Flow Rate & Changing SRs for RCS Flow Rate LIC-99-0001, Proposed Tech Specs Relocating Three cycle-specific Parameter Limits from FCS TS to COLR1999-01-29029 January 1999 Proposed Tech Specs Relocating Three cycle-specific Parameter Limits from FCS TS to COLR ML20151U3871998-09-0404 September 1998 Revised Bases of TS Sections 1.3(8),2.0.1(2),2.1.6,2.3,2.4, 2.13,2.15,3.1 & 3.6 ML20217B8241998-03-18018 March 1998 Proposed Tech Specs Re Requirements for Alternate Shutdown Panel & Associated Auxiliary Feedwater Panel ML20217B8611998-03-18018 March 1998 Proposed Tech Specs 5.2 & 5.11.2,changing Title of Shift Supervisor to Shift Manager ML20217P2041998-03-0303 March 1998 Proposed Tech Specs Pages,Revising TS 2.6 & Basis by Replacing Refs to TS 3.5(4) W/Refs to TS 5.19 ML20199L8951998-01-30030 January 1998 Proposed Tech Specs,Reflecting Relocation of pressure-temp Curves,Predicted Radiation Induced NDTT Shift Curve & LTOP Limits to FCS Unit 1 RCS PT Limits Rept ML20199L7291998-01-30030 January 1998 Proposed Tech Specs Deleting Section 3.E Re License Term ML20202B0931998-01-30030 January 1998 Proposed Tech Specs Section 2.5 Re Steam & Feedwater Sys ML20203G4311997-12-11011 December 1997 Proposed Tech Specs,Adding New LCO to TS 2.15 Pertaining to Inoperable ESF Logic Subsystem ML20199K1391997-11-21021 November 1997 Proposed Tech Specs 5.19 Re Containment Leakage Rate Testing Program ML20217G4601997-10-0303 October 1997 Proposed Tech Specs Pages Revising TS Surveillance 3.9, Auxiliary Feedwater Sys, to Clarify What Flow Paths Are Required to Be Tested & Delete Specific Discharge Pressure ML20196J0851997-07-25025 July 1997 Proposed Tech Specs Implementing Option B of 10CFR50,App J & Allowing Frequency of Conducting ILRT & Local Leak Rate Testing to Be Based on Component Performance ML20137Y1801997-04-17017 April 1997 Proposed Tech Specs Re Administrative Changes to License DPR-40 ML20137H4941997-03-26026 March 1997 Proposed Tech Specs Incorporating Addl Restrictions on Operation of MSSVs ML20138L4361997-02-20020 February 1997 Proposed Tech Specs 5.0 Re Administrative Controls LIC-96-0183, Proposed Tech Specs 5.0 Re Administrative Controls & Table of Contents1996-11-20020 November 1996 Proposed Tech Specs 5.0 Re Administrative Controls & Table of Contents ML20129E5161996-10-24024 October 1996 Proposed Tech Specs 4.3.2,regarding Reactor Core & Control to Allow Use of Either Zircaloy or ZIRLO Cladding Proposed Additional Reference to Westinghouse Topical Report, WCAP-12610-P-A, Vantage + Fuel Assembly Rept ML20129C2621996-10-22022 October 1996 Proposed Tech Specs 5.0 Re Administrative Controls & 5.9.5 Re Core Operating Limits Rept LIC-96-0125, Proposed Tech Specs Revising Paragraph 2.B(2) of License to Allow Use of Source Matl as Reactor Fuel.Ts 4.3.2 Revision Would Include Depleted U in Describing Reactor Core1996-08-23023 August 1996 Proposed Tech Specs Revising Paragraph 2.B(2) of License to Allow Use of Source Matl as Reactor Fuel.Ts 4.3.2 Revision Would Include Depleted U in Describing Reactor Core ML20115G0041996-07-15015 July 1996 Proposed Tech Specs 4.3.2 Re Reactor Core & Control ML20112D3211996-05-31031 May 1996 Proposed Tech Specs Re LCO for Trisodium Phosphate & Increasing Min Required Amount of Trisodium Phosphate Contained in Containment Sump Mesh Baskets ML20117H6981996-05-20020 May 1996 Proposed Tech Specs,Clarifying Surveillance Test Requirements Found in TS 3-1,Tables 3-1,3-2,3-3 & 3-3A ML20117H5931996-05-17017 May 1996 Proposed Tech Specs,Relocating Operability Requirements for Shock Suppressors (Snubbers) to USAR & or Plant Procedures & Incorporating Snubber Exam & Testing Requirements Into TS 3.3 ML20097C3081996-02-0101 February 1996 Proposed Tech Specs,Allowing Increase in Initial Nominal U-235 Enrichment Limit of Fuel Assemblies That May Be Stored in Spent Fuel Pool LIC-96-0008, Proposed Tech Specs Placing Sirw Tank Low Level Channels in Bypass Rather than Tripped Condition1996-01-22022 January 1996 Proposed Tech Specs Placing Sirw Tank Low Level Channels in Bypass Rather than Tripped Condition ML20094N8631995-11-16016 November 1995 Proposed Tech Specs,Adding LCO & Surveillance Test for Safety Related Inverters & Deleting Nonsafety Related Instrument Buses ML20092G0771995-09-0606 September 1995 Proposed Tech Spec 2.7,extending Allowed Outage Time from 7 Days Per Month to 7 Days W/ Addl Once Per Cycle 10 Day Allowed Outage Time ML20087E0281995-08-0404 August 1995 Proposed Tech Specs Reducing Minimum Operable Containment Radiation High Signal Channels ML20086D5341995-06-27027 June 1995 Proposed Tech Specs Re Reformation & Clarification of TS Re Chemical & Vol Control Sys ML20091G3601995-06-26026 June 1995 Proposed Tech Specs Re Extension of Allowed Outage Time for an Inoperable Low Pressure SI Pump ML20086D3851995-06-26026 June 1995 Proposed Tech Specs Re Audit Frequencies for Plant QA Program ML20084G7751995-05-31031 May 1995 Proposed Tech Specs,Requesting Amend to Provide Addl Restrictions on Operation of CCW Sys Heat Exchangers ML20083C0091995-05-0808 May 1995 Proposed Tech Specs,Incorporating Proposed Revs Per GL 93-05 to Specs 2.3,3.1,3.2,3.3 & 3.6 ML20087G9691995-04-0707 April 1995 Proposed Tech Specs Re Relocation of Axial Power Distribution Figure for License DPR-40 ML20082J0851995-04-0707 April 1995 Proposed Tech Specs Re Administrative Changes to License DPR-40 ML20080S0291995-03-0101 March 1995 Proposed Tech Specs Reflecting Administrative Revs to TS 5.5 & 5.8,per GL 93-07 & Revs Unrelated to GL 93-07 to TS 2.5, 2.8,2.11,3.2 & 3.10 ML20078P8251995-02-10010 February 1995 Proposed Tech Specs 2.10 to Relocate Requirements for Incore Instrumentation Sys ML20077S1691995-01-0909 January 1995 Proposed Tech Specs,Reflecting Deletion of Requirements for Toxic Gas Monitoring Sys ML20078G8981994-11-11011 November 1994 Proposed Tech Specs 5.2 & 5.5,reflecting Administrative Changes ML20024J3921994-10-0707 October 1994 Proposed Tech Specs,Deleting SRs in TS 3.6(3)a for Eight Raw Water Backup Valves to Containment Cooling Coils,Deleting SRs in TS 3.2,Table 3-5,item 6 for 58 Raw Water Valves & Revising Basis of TS 2.4 to Reflect Changes ML20069H9261994-06-0606 June 1994 Proposed Tech Specs Incorporating Changes to Credit Leak Before Break Methodology to Resolve USI A-2, Asymmetrical Blowdown Loads on Rcps ML20069D8451994-05-25025 May 1994 Proposed Tech Specs Requesting one-time Schedular Exemption from 10CFR50.36a(2) ML20062N4211993-12-28028 December 1993 Proposed TS Tables 3-1 & 3-2 Re Min Frequencies for Checks, Calibrs & Testing of RPS & Min Frequencies for Checks, Calibrs & Testing of ESFs & Instrumentation & Controls, Respectively LIC-93-0228, Proposed Tech Specs Incorporating Changes to Leak Before Break Methodology to Resolve Unresolved Safety Issue A-2, Asymmetrical Blowdown Loads on Reactor Primary Coolant Sys1993-08-20020 August 1993 Proposed Tech Specs Incorporating Changes to Leak Before Break Methodology to Resolve Unresolved Safety Issue A-2, Asymmetrical Blowdown Loads on Reactor Primary Coolant Sys ML20045H1791993-07-12012 July 1993 Proposed TS 2.14,Table 2-1,Item 6.b Re ESF Sys Initiation, Degraded Voltage Setting Limits LIC-93-0159, Proposed Tech Specs Incorporating Administrative Changes1993-06-17017 June 1993 Proposed Tech Specs Incorporating Administrative Changes ML20128E5341993-02-0808 February 1993 Proposed Tech Specs Deleting Section 5.9.4 Re Radioactive Effluent Release Rept.Draft Chemistry Manual Procedure Encl ML20128C0461993-02-0101 February 1993 Proposed TS Figures 2-1A & 2-1B Re pressure-temp Limits for Heatup & Cooldown,Respectively 1999-05-26
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20195B4441999-05-26026 May 1999 Proposed Tech Specs Relocating pressure-temp Curves, Predicted Radiation Induced NDTT Shift Curve & LTOP Limits to FCS Unit 1 RCS pressure-temp Limits Rept ML20205J7671999-03-31031 March 1999 Proposed Tech Specs Increasing Min Required RCS Flow Rate & Changing SRs for RCS Flow Rate LIC-99-0001, Proposed Tech Specs Relocating Three cycle-specific Parameter Limits from FCS TS to COLR1999-01-29029 January 1999 Proposed Tech Specs Relocating Three cycle-specific Parameter Limits from FCS TS to COLR LIC-98-0141, SG Eddy Current Test Rept for 1998 Refueling Outage. with1998-10-27027 October 1998 SG Eddy Current Test Rept for 1998 Refueling Outage. with ML20151U3871998-09-0404 September 1998 Revised Bases of TS Sections 1.3(8),2.0.1(2),2.1.6,2.3,2.4, 2.13,2.15,3.1 & 3.6 ML20217B8611998-03-18018 March 1998 Proposed Tech Specs 5.2 & 5.11.2,changing Title of Shift Supervisor to Shift Manager ML20217B8241998-03-18018 March 1998 Proposed Tech Specs Re Requirements for Alternate Shutdown Panel & Associated Auxiliary Feedwater Panel ML20217P2041998-03-0303 March 1998 Proposed Tech Specs Pages,Revising TS 2.6 & Basis by Replacing Refs to TS 3.5(4) W/Refs to TS 5.19 ML20199L7291998-01-30030 January 1998 Proposed Tech Specs Deleting Section 3.E Re License Term ML20199L8951998-01-30030 January 1998 Proposed Tech Specs,Reflecting Relocation of pressure-temp Curves,Predicted Radiation Induced NDTT Shift Curve & LTOP Limits to FCS Unit 1 RCS PT Limits Rept ML20202B0931998-01-30030 January 1998 Proposed Tech Specs Section 2.5 Re Steam & Feedwater Sys ML20203G4311997-12-11011 December 1997 Proposed Tech Specs,Adding New LCO to TS 2.15 Pertaining to Inoperable ESF Logic Subsystem ML20199K1391997-11-21021 November 1997 Proposed Tech Specs 5.19 Re Containment Leakage Rate Testing Program ML20217G4601997-10-0303 October 1997 Proposed Tech Specs Pages Revising TS Surveillance 3.9, Auxiliary Feedwater Sys, to Clarify What Flow Paths Are Required to Be Tested & Delete Specific Discharge Pressure ML20211N7591997-10-0202 October 1997 Rev 0 to Fort Calhoun Station Unit 1 Operating Instruction, OI-ES-3, Engineered Safeguard Controls Normal Mode 1,2 & 3 Alignment Check ML20211N7521997-09-21021 September 1997 Rev 2 to Fort Calhoun Operations Dept Policy & Directive OPD-6-04, Annunciator Marking ML20211N7471997-09-12012 September 1997 Rev 2 to Fort Calhoun Operations Dept Policy & Directive OPD-6-08, Plastic Label Usage ML20211N7661997-08-25025 August 1997 Rev 4 to Fort Calhoun Station Unit 1 Annunciator Response Procedure ARP-1, APR-1 Annunciator Response Procedure ML20211N7411997-08-24024 August 1997 Rev 0 to Fort Calhoun Operations Dept Policy & Directive OPD-5-14, Test Monitor Program ML20196J0851997-07-25025 July 1997 Proposed Tech Specs Implementing Option B of 10CFR50,App J & Allowing Frequency of Conducting ILRT & Local Leak Rate Testing to Be Based on Component Performance ML20137Y1801997-04-17017 April 1997 Proposed Tech Specs Re Administrative Changes to License DPR-40 ML20137H4941997-03-26026 March 1997 Proposed Tech Specs Incorporating Addl Restrictions on Operation of MSSVs ML20138L4361997-02-20020 February 1997 Proposed Tech Specs 5.0 Re Administrative Controls ML20134J6841997-01-20020 January 1997 Rev 5,Change a to Security Training & Qualification Program LIC-96-0183, Proposed Tech Specs 5.0 Re Administrative Controls & Table of Contents1996-11-20020 November 1996 Proposed Tech Specs 5.0 Re Administrative Controls & Table of Contents ML20129E5161996-10-24024 October 1996 Proposed Tech Specs 4.3.2,regarding Reactor Core & Control to Allow Use of Either Zircaloy or ZIRLO Cladding Proposed Additional Reference to Westinghouse Topical Report, WCAP-12610-P-A, Vantage + Fuel Assembly Rept ML20129C2621996-10-22022 October 1996 Proposed Tech Specs 5.0 Re Administrative Controls & 5.9.5 Re Core Operating Limits Rept LIC-96-0125, Proposed Tech Specs Revising Paragraph 2.B(2) of License to Allow Use of Source Matl as Reactor Fuel.Ts 4.3.2 Revision Would Include Depleted U in Describing Reactor Core1996-08-23023 August 1996 Proposed Tech Specs Revising Paragraph 2.B(2) of License to Allow Use of Source Matl as Reactor Fuel.Ts 4.3.2 Revision Would Include Depleted U in Describing Reactor Core ML20115G0041996-07-15015 July 1996 Proposed Tech Specs 4.3.2 Re Reactor Core & Control ML20112D3211996-05-31031 May 1996 Proposed Tech Specs Re LCO for Trisodium Phosphate & Increasing Min Required Amount of Trisodium Phosphate Contained in Containment Sump Mesh Baskets ML20117H6981996-05-20020 May 1996 Proposed Tech Specs,Clarifying Surveillance Test Requirements Found in TS 3-1,Tables 3-1,3-2,3-3 & 3-3A ML20117H5931996-05-17017 May 1996 Proposed Tech Specs,Relocating Operability Requirements for Shock Suppressors (Snubbers) to USAR & or Plant Procedures & Incorporating Snubber Exam & Testing Requirements Into TS 3.3 ML20129C5351996-03-0101 March 1996 Rev 0 to Incore Instrumentation Operability Requirements ML20097C3081996-02-0101 February 1996 Proposed Tech Specs,Allowing Increase in Initial Nominal U-235 Enrichment Limit of Fuel Assemblies That May Be Stored in Spent Fuel Pool LIC-96-0008, Proposed Tech Specs Placing Sirw Tank Low Level Channels in Bypass Rather than Tripped Condition1996-01-22022 January 1996 Proposed Tech Specs Placing Sirw Tank Low Level Channels in Bypass Rather than Tripped Condition ML20108A7161995-12-19019 December 1995 Rev 7 to CH-ODCM-0001, ODCM, Incorporating TS Amend 171 for Section 3.1 Update/Reflect Changing Environ ML20094N8631995-11-16016 November 1995 Proposed Tech Specs,Adding LCO & Surveillance Test for Safety Related Inverters & Deleting Nonsafety Related Instrument Buses ML20092G0771995-09-0606 September 1995 Proposed Tech Spec 2.7,extending Allowed Outage Time from 7 Days Per Month to 7 Days W/ Addl Once Per Cycle 10 Day Allowed Outage Time ML20091P4011995-09-0101 September 1995 Rev 3 to Fort Calhoun Station ISI Program Plan Third Ten-Yr Interval 1993-2003 ML20087E0281995-08-0404 August 1995 Proposed Tech Specs Reducing Minimum Operable Containment Radiation High Signal Channels ML20086D5341995-06-27027 June 1995 Proposed Tech Specs Re Reformation & Clarification of TS Re Chemical & Vol Control Sys ML20091G3601995-06-26026 June 1995 Proposed Tech Specs Re Extension of Allowed Outage Time for an Inoperable Low Pressure SI Pump ML20086D3851995-06-26026 June 1995 Proposed Tech Specs Re Audit Frequencies for Plant QA Program ML20085M0081995-06-15015 June 1995 Rev 2 to ISI Program Plan for 1993-2003 Interval ML20084G7751995-05-31031 May 1995 Proposed Tech Specs,Requesting Amend to Provide Addl Restrictions on Operation of CCW Sys Heat Exchangers ML20083C0091995-05-0808 May 1995 Proposed Tech Specs,Incorporating Proposed Revs Per GL 93-05 to Specs 2.3,3.1,3.2,3.3 & 3.6 ML20087G9691995-04-0707 April 1995 Proposed Tech Specs Re Relocation of Axial Power Distribution Figure for License DPR-40 ML20082J0851995-04-0707 April 1995 Proposed Tech Specs Re Administrative Changes to License DPR-40 ML20108A7121995-03-15015 March 1995 Rev 6 to CH-ODCM-0001, ODCM, Incorporating New TS Amend 164 ML20080S0291995-03-0101 March 1995 Proposed Tech Specs Reflecting Administrative Revs to TS 5.5 & 5.8,per GL 93-07 & Revs Unrelated to GL 93-07 to TS 2.5, 2.8,2.11,3.2 & 3.10 1999-05-26
[Table view] |
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5.0 ADMINISTRATIVE CONTROLS 5.5.3 Fire Protection Inspection
- a. An independent fire protection and loss prevention inspection and audit shall be performed annually utilizing either qualified off-site licensee per-sonnel or an outside fire protection firm. The audit and inspection program responsibility shall rest with the Safety Audit and Review Committee.
- b. An inspection and audit cf the fire protection and loss prevention program by an outside qualified fire consultant shall be performed at intervals no greater than 3 years.
5.6 Reportable Occurrence Action 5.6.1 The following action shall be taken in the event of a RE-PORTABLE OCCURRENCE:
- a. Each Reportable Occurrence requiring 1, 4, or 24 l hour notification to the Commission shall be review-cd by the Plant Review Committee and submitted to the Safety Audit and Review Committee and the
, Section Manager - Operations.
5.7 Safety Limit Violation 5.7.1 The following actions shall be taken in the event a Safety Limit is violated:
- a. The provisions of 10 CFR 50.36(c)(1)(i) shall be complied with immediately.
- b. The safety limit violation shall be reported to the -
Section Manager - Operations and to the Safety Audit and Review Committee immediately.
- c. A Safety Limit Violation Report shall be prepared.
The report shall be reviewed by the Plant Review Committee. This report shall describe (1) appli-cable circumstances preceding the violation, (2) ef-fects of the violation upon facility components,
, systems or structures, and (3) corrective action taken to prevent recurrence.
- d. The Safety Limit Violation Report shall be submit-ted to the Safety Audit and Review Committee and l the Section Manager - Operations within 10 days of the violation.
O 285 PDR AmendmentNo./, p4,38 5-9
5.0 ADMINISTRATIVE CONTROLS l 5.8 Procedures 5.8.1 Written procedures and administrative policies shall be established, implemented and maintained that meet or ex- '
ceed the minimum requirements of sections 5.1 and 5.3 of ANSI N18.7-1972 and Appendix A of USNRC Regulatory Guide 1.33 except as provided in 5.8.2 and 5.8.3 below.
5.8.2 Each procedure and administrative policy of 5.8.1 above, and changes thereto, shall be reviewed by the Plant Re-view Committee and approved by the Manager - Fort Calhoun Station prior to implementation and periodically as set forth in each document.
5.8.3 Temporary changes to procedute 5.8.1 above may be made provided:
- a. The intent of the original procedure is not alter-ed.
- b. The change is approved by two members of the plant supervisory staff, at least one of whom holds a Senior Reactor Operator's License on the unit af-fected.
- c. The change is documented, reviewed by the Plant Re-view Committee and approved by the Manager - Fort Calhoun Station within 14 days of implementation.
5.8.4 Written procedures approved per 5.8.2 above shall be im-plemented which govern the selection of fuel assemblies to be placed in Region 2 of the spent fuel racks (Techni-cal Specification 2.8(12). These procedures shall re-quire an independent verification of initial enrichment requirements and fuel burnup calculations for a fuel bundle to assure the " acceptance" criteria for placement in Region 2 are met. This independent verification shall
, be performed by individuals or groups other than those l who performed the initial acceptance criteria assessment, l but who raay be from the same organization.
5.9 Reporting Requirements i
In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following identified reports shall be submitted to the Director of the appropriate Regional Office of Inspection and Enforce-ment unless otherwise noted, l
l Amendment No. A,I 19', )$, 75 5-10
__ _ . . _ _ . _ - _ _ _ _ ,_ _ _ . _ . - - _ . _ _ _ _ _ _ _ . ~ . . _. ._ ._.._. . _ _ . _ . _ _ . . _
- 5.0 ADMINISTRATIVE CONTROLS 5.9.1 Routine Reports
- a. Startup Report. A summary report of plant startup and power escalation testing shall be submitted fol-lowing (1) receipt of an operating license, (2) amendment to the license involving a planned in-crease in power level, (3) installation of fuel that has a different design or has been manu-factured by a different fuel supplier, and (4) modi-fications that may have significantly altered the
, nuclear, thermal, or hydraulic performance of the plant. The report shall address each of the tests identified in the USAR and shall in general include a description of the measured values of the operat-ing conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described.
Any additional specific details required in license conditions based on other commitments shall be in-cluded in this report.
Startup reports shall be submitted within (1) 90 dcys following completion of the startup test pro-gram, (2) 90 days following resumption or commence-ment of commercial power operation, or (3) 9 months following initial criticality, whichever is earli-est. If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commence-ment of commercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed,
- b. Annual Occupational Exposure Report. An annual oc-cupational exposure report should be submitted prior to March 1 of each year. The report shall consist of a tabulation on an annual basis of the number of station, utility and other personnel (in-cluding contractors) receiving exposures greater than 100 mrem /yr and their associated man rem ex-posure according to Amendment No. 9, 35, 75 5-11 t
e ,,,a - - -.:,---- ,----nw,- -,.,--,--,.-,,--.-----..-------.e , , - - , - - - - - - - - , , - , - , - - , , - , ,-u , v---,,--n-
5.9.2 Continued (7) Any event or situation, related to the health and safety of the public or onsite personnel, or protection of the environment, for which a news release is planned or noti-fication to other government agencies has been or will be made. Such an event may in-l clude an onsite fatality or inadvertent re-4 lease of radioactive!y contaminated
. materials but shall not include non-radio-l logical effluent releases to the environ-ment.
- c. Twenty-Four (24) Hour Notification Following Radio-logical Events Notification to the NRC shall be made, within 24 i hours of discovery of the event, of any event in-volving licensed material possessed by the licensee that may have caused or threatens to cause one or more of the following:
NOTE: The method of NRC notification shall be the same as that required for one (1) hour notification in 5 5.9.2(a ) .
(1)** Exposure of the whole body of any individual to 5 rems or more of radiation; exposure of the skin of the whole body of any individual
! to 30 rems or more of radiation; or exposure of the feet, ankles, hands or forearms to 75 rems or more of radiation.
(2)** The release of radioactive material in con-centrations which, if averaged over a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, would exceed 500 times the limits specified for such materials in Ap-
, pendix B, Table II, of 10 CPR Part 20.
1 (3)** A loss of one day or more of the operation of any facilities affected, j
(4)** Damage to property in excess of $2,000.
i d. . Thirty (30) Day Written Reports (LER's)
! A Licensee Event Report (LER) shall be submitted to l the U.S. Nuclear Regulatory Commission, Document Control Desk, Washington, D.C. with a copy to Region IV of the NRC, within 30 days after the dis-covery of the event, for any of the following:
(1) Any Reportable Occurrence previously listed in these Technical Specifications requiring a 1, 4 , or 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> MRC notification that is denoted by a **. '
5-14b l
_ _ - . . - , _ _ _ _ _ __. _. . ~ . _ . ~ . _ _ . _ _ _ _ _ _ _ _ _ . _ _. . _.__ _ . -. _ _ _ _.
1 1
(
5.9.2 Continued (2) Any operation or condition prohibited by the Technical Specifications Safety Limits, Limiting Safety System Settings, or Limiting Conditions for Operation.
(3) Any event where a single cause or condition caused at least one independent train or channel to become inoperable in multiple
- systems or two independent trains or chan-nels to become inoperable in a single system designed to
(i) Shutdown the reactor and maintain it in a safe shutdown condition; (ii) Remove residual heat; (iii) Control to release of radioactive j material; or (iv) Mitigate the consequences of an ac-cident.
(4) Each exposure of an individual to radiation in excess of the applicable limits in 10 CPR l
20.101 or 10 CFR 20.104(a) or these Techni-cal Specifications.
(5) Each exposure of an individual to radio-active material in excess of the applicable limits in 10 CPR 20.103(a)(1), 10 CPR 20.103(a)(2), or 10 CFR 20.104(b), of these Technical Specifications.
(6) Levels of radiation or concentrations of radioactive material in a restricted area in excess of any other applicable limit in these Technical Specifications.
(7) Levels of radiation or concentrations of radioactive material (whether or not in-volving excessive exposure of any indivi-l dual) in an unrestricted area in excess of ten times any applicable limit set forth in 10 CPR Part 20, or in these Technical Speci-fications.
i (8) Any level of radiation or release of radio-active material in excess of limits speci-l fied by 40 CPR Part 190, " Environmental Radi-i ation Protection Standards for Nuclear Power Operations," or in excess of license condi-tions related to compliance with 40 CPR Part 190.
l 5-14c
DISCUSSION, JUSTIFICATION, AND SIGNIFICANT HAZARDS CONSIDERATIONS The following changes are being proposed to the Port Calhoun Station Technical Specifications in order to make those specifi-j cations conform with the new Significant Event and LER reporting
- requirements. Paragraphs 5.7.l(b) and (d) are being revised by deletion of the reporting requirements to the Commission. These reporting requirements have been superseded by reporting require-j ments set forth in the new rules on Significant Event and LER re-porting. The requirement deleted from Section 5.7.l(b), which re-quires immediate reporting of Safety Limit violations, is covered
- under the proposed Technical Specification 5.9.2(4). The require-ment for a 10-day dritten report to the Commission in the event of i a Safety Limit violation has been superseded by the new 30-day LER reporting requirements in 10 CFR 50 and is covered in the Techni-Cdl Specifications under Section 5.9.2(d)(2).
Significant hazards considerations are:
(1) This proposed amendment will not involve a significant in-crease in the probability or consequences of an accident pre-viously evaluated. The requirement for immediate notifi-cation of the Commission in the event of a Safety Limit violation has not been deleted. Notificatien or the Commis-
- sion within one hour of the event is still required by a different section of the Technical Specifications. The deletion of the requirement to notify the Commission in writing within 10 days of the Safety Limit viola tion could
- not possibly involve an increase in the probability or con-
- sequences of a previously evaluated accident because it is "after the fact". This reporting requirement has been super-seded by the new rule on LER reporting.
(2) The proposed amendment will not create the possibility of a new or different kind of accident from any accident previous-ly evaluated. These changes are purely administrative in l nature and they do not reduce the District's reporting re-quirements for Safety Limit violations. The lengthening of j the time requirement for submitting a written report from 10 days to 30 days could not possibly create an unevaluated ac-cident as this only affects the District after the Safety Limit violation has occurred and has no direct safety impact j on plant operation..
l l (3) The proposed amendment does not involve a significant re-duction in margin of safety. The proposed amendment is administrative in nature and "after the fact" (i.e., only affects the District in an administrative manner after the safety violation has occurred).
ATTACHMENT H
i A change to Section 5.6.1 of the Fort Calhoun Station Technical Specifications is being proposed which will delete Section 5.6.l(a) requiring the Commission be notified and a report sub-mitted pursuant,to the requirements of Technical Specification 5.9.2. This change is being made because the requirement in Section 5.6.1(a) is redundant and, therefore, unnecessary. The reporting requirements to the Commission are clearly identified in Section 5.9.2 of the Techni, cal Specifications. Section 5.6.l(b) of the Technical Specifications is being changed to include 1 and l 4-hour reporting requirements to that specification.
Significant hazards considerations are:
(1) This proposed amendment will not involve a significant in-l crease in the probability or consequences of an accident pre-viously evaluated. The proposed change is administrative in nature and in no reduces the reporting requirements from those set forth in the new Significant Event Reporting and
, LER rule.
(2) The proposed amendment will not create the possibility of a new or different kind of accident-from any accident pre-viously evaluated. The change is administrative in nature and in no way alters the reporting requirements set forth in the new Significant Event Reporting and LER rule. The change is conservative in the fact that additional reporting requirements are included in the: specification (i.e., 1 and 4-hour notification requirements).
(3) The proposed amendment does not involve a significant re-
- duction in a margin of safety. The change is administrative in nature and does not eliminate any reporting requirembnts.
Section 5.9.2(d)(2) of the proposed Technical Specifications for LER reporting is being amended to specify in more detail what oper-ations or conditions, prohibited by Technical Specifications are re-quired to be reported. .The District believes the intent of the LER rule provides' for reporting of events or condi tions that might lead to serious accidents or significant safety events. The NRC-developed criterion is based on potential consequences of the event as the' measure of significance, not specifically the type of initiation events or causes of the event. Based on the NRC-
, developed criterion, the type of event must be f ully hnalyzed
] before it could be determined if the event wao repostable or not.
Therefore, the District believes the LER requirements are intended to apply to. equipment' failures or major events,that affect plant safety and not administrative or surveillance type problems, un-less the consequences of those administrative events lead to a significant event f ro.n the standpoint of safety. The proposed wording of Section 5.9.2(d)(2) supports'this reporting philosophy by more precisely defining what events are required to be re-ported.
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