ML19312C244
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| ML19312C244 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 11/03/1976 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML19312C243 | List: |
| References | |
| NUDOCS 7912110836 | |
| Download: ML19312C244 (1) | |
Similar Documents at Oconee | |
|---|---|
Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20155C6391998-10-26026 October 1998
[Table view]Proposed Tech Specs Tables 4.1-1 & 4.1-2,revised Surveillance Frequency of Refueling Outage to 18 Months ML20154C1021998-09-30030 September 1998 Proposed Tech Specs Changing UFSAR by Increasing Max Rod Internal Pressure in Spent Fuel Pool from 1,200 to 1,300 Psig ML20236V9611998-07-27027 July 1998 Corrected TS Bases Pages 3.5-30b of 961211 & 3.16-2 of 970205,correcting Amend Numbers ML20236T5171998-07-20020 July 1998 Proposed Tech Specs Re one-time Extension to Functional Test Frequencies for Hydraulic & Mechanical Snubbers ML20236R1901998-07-16016 July 1998 Proposed Tech Specs Extending TS Surveillances TS 4.20.2(a), Table 4.20-1,items 1,2 & 4,TS 4.1-1,Table 4.1-1,items 8,9,10 & 11 & TS 4.5.1.2.1,item b(1) ML16141A8111994-04-20020 April 1994 Proposed Tech Spec Table 4.1-2, Min Equipment Test Frequency. ML20044C9581993-05-0404 May 1993 Proposed TS 4.7.1, Control Rod Trip Time Test. ML18032A3441987-05-29029 May 1987 Proposed Tech Specs,Clarifying Trip Level Setting in Table 3.2.A for Standby Gas Treatment Sys Relative Humidity Heater ML16134A6761982-08-11011 August 1982 Proposed Tech Spec Revisions Re Reload Design Calculations for Cycle 7 ML16134A6731982-05-0303 May 1982 Proposed Tech Spec Changes Re Core Protection Safety Limits, Protective Sys Max Allowable Setpoints & Rod Position Limits ML15223A7671982-01-12012 January 1982 Proposed Revisions to Tech Spec Section 3.1.2 Re Heatup Cooldown & Inservice Test Limitations for RCS ML16148A4421981-11-13013 November 1981 Proposed Tech Spec Revision Re Core Protection Safety Limits Protective Sys Max Allowable Setpoints & Rod Position Limits ML16148A4351981-10-28028 October 1981 Proposed Revision to Tech Spec Figure 3.5.2-4B2,allowing Cycle 5 to Run at 100% Full Power W/Axial Power Shaping Rods Fully Inserted ML16148A4281981-08-19019 August 1981 Proposed Revision to Tech Spec Figures 3.5-16a,3.5.19a, 3.5-22 & 3.5-25a Re Extension of Operating Limits ML15223A7321981-05-29029 May 1981 Proposed Tech Specs 2.1-2,2.1-3,2.1-7,2.3-5,3.2-1,3.2-2, 3.3-1,3.3-2,3.3-3,3.3-4,3.3-5,3.3-6,3.5-9,3.5-10,3.5-15, 3.5-15a & b,3.5-18,3.5-18a,b,c,d & e,3.5-21,3.5-21a & B, 3.5-24,3.5-24a & b,3.8-2 & 3.8-3 Re Core Protection ML16134A6651980-08-25025 August 1980 Proposed Tech Specs Revision for Cycle 6 ML16148A3351980-07-16016 July 1980 Proposed Revision to Tech Spec 3.3.1.c Allowing Continued Operation of Unit 2 of Full Rated Power While Maint Continues on HPI Pump Until 800718 ML19318B9731980-06-24024 June 1980 Proposed Tech Spec Interpreting Term Operable as Applied to Various Tech Spec Requirements ML16148A2691979-11-16016 November 1979 Proposed Changes to Tech Spec Pages 2.1,2.3,3.2 & 3.5. Changes Affect Core Protection Limits,Reactor Protective Sys Max Allowable Setpoints & Vol Requirements for Borated Water Storage Tank ML19317D2701978-09-25025 September 1978 Proposed Tech Spec 3.5.2 Re Control Rod Group & Power Distribution Limits & Table 4.1-2 Re Min Equipment Test Frequency ML19317D2621978-09-18018 September 1978 Proposed Revisions to Tech Specs 2.1,2.3,3.2 & 3.5 Re Core Protection Safety Limits & Protective Sys Max Allowable Setpoints ML19317D2731978-09-0606 September 1978 Revised Tech Spec Page,Figure 2.3-2A,re Protective Sys Max Allowable Setpoints ML19317D2491978-08-22022 August 1978 Proposed Revision to Tech Specs 4.18 Re Hydraulic Shock Suppressors (Snubbers) ML19322B9961978-08-21021 August 1978 Proposed Revision to Tech Spec 2.3 Re Cycle 5 ML19312B7931978-07-17017 July 1978 Proposed Tech Spec 3.1.6.4,changing Steam Generator Leak Rate Limit ML19308D6271978-06-28028 June 1978 Tech Spec Change Request Re Paragraph 2.B(6),stipulating That Byproduct & SNM Associated W/Four Fuel Assemblies Acquired by Fl Power Corp from Duke Power Co Previously Irradiated in Oconee 1 May Be Possessed ML19317D2301978-06-26026 June 1978 Proposed Tech Specs 2.1,2.3,3.2,3.5 & 4.1 Required to Support Operation of Unit 1 at Full Rated Power During Cycle 5,including Core Protection Safety Limits & Protective Sys Mac Allowable Setpoint ML19316A6501978-06-22022 June 1978 Proposed Replacement Page for Tech Spec 4.1-2 Re Min Equipment Test Frequency ML19316A5381978-06-14014 June 1978 Proposed Changes to Tech Specs Re thermal-hydraulics Analysis.Revision to BAW-1486, Unit 3,Cycle 4 Reload Rept. ML19312B8161978-06-12012 June 1978 Proposed Tech Specs 3.8,4.4 & 4.6 Re Fuel Loading & Refueling,Structural Integrity & Emergency Power Periodic Testing ML19317D2341978-06-0909 June 1978 Proposed Tech Spec 3.9 Deleting Requirements Not Applicable to Liquid Effluent Monitoring Sys Due to Installation of Offline Monitor ML19317D2221978-06-0808 June 1978 Proposed Tech Spec 3.1 Allowing Max 1 Gallon Per Minute Leakage Through Steam Generator Tubes Prior to Initiation of Unit Shutdown ML19317D2121978-06-0202 June 1978 Proposed Tech Spec 4.2 Allowing re-insp of Reactor Coolant Outlet Nozzles at Future Refueling Outage ML19316A5271978-05-30030 May 1978 Proposed Revisions to Tech Specs 2.3,3.2 & 3.5.2.4 to Support Cycle 4 Operation at Full Power ML19312B7971978-04-27027 April 1978 Proposed Tech Spec 6.4,incorporating Operating Procedure Requirements Re B&W Small Break ECCS Analysis ML19312B8091978-04-20020 April 1978 Proposed Tech Spec 3.3 Incorporating New Tech Spec 3.3.8 Requiring Operability of Three HPI Pumps for Each Unit During Power Operation Above 60% Full Power ML19317D2001978-03-20020 March 1978 Proposed Tech Spec 3.5 Including 6.03% Quadrant Power Tilt Limit & Provision for Notifying NRC If Tilt Exceeds 3.5% ML19317D2131978-02-21021 February 1978 Proposed Tech Spec 3.1. Incorporating Revision to Pressurization,Heatup & Cooldown Limitations.B&W 780125 Ltr to Util Re Corrections to Errors Discovered in B&W Rept BAW-1436 Encl ML19317D2211978-02-16016 February 1978 Proposed Tech Spec 2.3 Deleting Loss of One Pump Trip Setpoint,Outdated Info & Setpoints Associated W/Single Loop Operation ML19340A2641978-02-0808 February 1978 Tech Specs 3.3.2 Through 3.3.5 for ECCS ML19316A4801978-02-0101 February 1978 Proposed Changes to Tech Spec 3.7 Re Limiting Conditions for Operation & Surveillance Requirements for 125 Volt Distribution Sys ML19317D2271978-01-23023 January 1978 Proposed Tech Spec 3.5 Incorporating Control Rod Position & Axial Imbalance Limits to Period After 100 Plus or Minus 10 Effective Full Power Days ML19312B7891978-01-0303 January 1978 Proposed Tech Spec 2.3-9 & 10 Re Computer Software Used to Process Incore Detector Signal.Includes Modified power-imbalance Trip Setpoints to Account for Bias in Positive Imbalance Measured by Incore Detector Sys ML19316A5081977-12-0202 December 1977 Amend to Tech Specs 3.9 Re Radwaste Discharge ML19312B8001977-12-0202 December 1977 Proposed Tech Spec 6.6.2.1 Providing Requirement for Prompt Written Notification of Certain ROs by Telephone,Mailgram or Facsimile Transmission ML19312B7771977-11-0909 November 1977 Proposed Tech Spec 3.5.2 Permitting Operation of Unit 1 During Cycle 4 in Unrodded Mode ML19312B8061977-10-31031 October 1977 Proposed Tech Specs 6.6-1,-2,-3 & -4 Deleting Redundant Info Currently Being Reported in Annual Operating Rept ML19312B8101977-10-26026 October 1977 Proposed Tech Specs 3.5-9 & 3.5-24a,deleting Existing Reactor Core Quadrant Power Tilt & Control Rod Position Limits & Instituting More Conservative Limits ML19312B8151977-10-0707 October 1977 Proposed Changes to Tech Specs 3.7 & 4.6 Re Auxiliary Electrical Systems & Emergency Power Periodic Testing ML19329A4011977-10-0606 October 1977 Revised Tech Specs,Table 4.1-3 Re Min Sampling Frequency 1998-09-30 Category:TECHNICAL SPECIFICATIONS & TEST REPORTS MONTHYEARML20211A9881999-08-18018 August 1999
[Table view]Rev 5 to DPC Nuclear Security Training & Qualification Plan ML20204B4141999-03-27027 March 1999 Revised Oconee Nuclear Station Selected Licensee Commitments, List of Effective Pages ML20155C6391998-10-26026 October 1998 Proposed Tech Specs Tables 4.1-1 & 4.1-2,revised Surveillance Frequency of Refueling Outage to 18 Months ML20154L7191998-10-0505 October 1998 Rev 8 to DPC Nuclear Security & Contingency Plan, for Oconee,Mcguire & Catawba Nuclear Stations ML20154C1021998-09-30030 September 1998 Proposed Tech Specs Changing UFSAR by Increasing Max Rod Internal Pressure in Spent Fuel Pool from 1,200 to 1,300 Psig ML20236V9611998-07-27027 July 1998 Corrected TS Bases Pages 3.5-30b of 961211 & 3.16-2 of 970205,correcting Amend Numbers ML20236T5171998-07-20020 July 1998 Proposed Tech Specs Re one-time Extension to Functional Test Frequencies for Hydraulic & Mechanical Snubbers ML20236R1901998-07-16016 July 1998 Proposed Tech Specs Extending TS Surveillances TS 4.20.2(a), Table 4.20-1,items 1,2 & 4,TS 4.1-1,Table 4.1-1,items 8,9,10 & 11 & TS 4.5.1.2.1,item b(1) ML20217F2841998-04-20020 April 1998 Rev 7 to DPC Nuclear Security & Contingency Plan, for Oconee,Mcguire & Catawba Nuclear Stations ML20141F1521997-06-25025 June 1997 Rev 4 to Nuclear Security Training & Qualification Plan ML20134K5401996-10-31031 October 1996 Rev 6 to Chemistry Manual 5.1, Emergency Response Guidelines ML20117J0181996-08-15015 August 1996 Revised Chapter 16 of Oconee Selected Licensee Commitments Manual ML20095H1291995-12-0505 December 1995 Rev to ONS Selected Licensee Commitments (SLC) Manual, Revising SLC 16.6.1, Containment Leakage Tests to Reflect Current Plant Configuration & Update Testing Info ML20091P2461995-08-21021 August 1995 Rev to ONS Selected Licensee Commitments Manual ML16141A8111994-04-20020 April 1994 Proposed Tech Spec Table 4.1-2, Min Equipment Test Frequency. ML15224A3521993-10-26026 October 1993 Safety Assurance Directive 6.1, Oconee Nuclear Site Safety Assurance Emergency Response Organization. ML20044C9581993-05-0404 May 1993 Proposed TS 4.7.1, Control Rod Trip Time Test. ML20045F0721993-04-0707 April 1993 Rev 9 to Corporate Process Control Program Manual. ML20097D9451992-05-28028 May 1992 Rev 11 to Training & Qualification Plan ML20096C2561992-04-30030 April 1992 Public Version of Revised Crisis Mgt Implementing Procedures (Cmip),Including Rev 46 to CMIP-1,Rev 39 to CMIP-4,Rev 45 to CMIP-5,Rev 49 to CMIP-6,Rev 48 to CMIP-7,Rev 42 to CMIP-9 & Rev 3 to CMIP-15 ML20096D5451992-04-0707 April 1992 Public Version of Revised Crisis Mgt Implementing Procedures (Cmip),Including Rev 45 to CMIP-1,Rev 27 to CMIP-13 & Notification of Deletion of CMIP-8.Procedure CMIP-8 Reserved for Future Use ML20092M5891992-02-0606 February 1992 Public Version of Revised Crisis Mgt Implementing Procedures,Including Rev 43 to CMIP-1,Rev 43 to CMIP-5,Rev 33 to CMIP-8,Rev 25 to CMIP-13,Rev 6 to CMIP-18,Rev 4 to CMIP-22 & Rev 38 to CMIP-4 ML20094H2391992-01-0101 January 1992 Rev 33 to McGuire Nuclear Station Odcm ML20094H2511992-01-0101 January 1992 Rev 34 to Catawba Nuclear Station Odcm ML20087F3931991-12-11011 December 1991 Public Version of Rev 13 to Crisis Mgt Implementing Procedure CMIP-11, Emergency Classification - Mcguire. W/ 920121 Release Memo ML20086K8831991-11-18018 November 1991 Public Version of Revised Crisis Mgt Implementing Procedures (Cmips),Including Rev 42 to CMIP-1,Rev 29 to CMIP-2,Rev 42 to CMIP-5,Rev 12 to CMIP-11 & Rev 37 to CMIP-21 ML20086G7711991-10-16016 October 1991 Public Version of Revs to Crisis Mgt Implementing Procedures (Cmip),Including Rev 41 to CMIP-1,rev 37 to CMIP-4,rev 41 to CMIP-5,rev 46 to CMIP-6 & CMIP-7,rev 32 to CMIP-8,rev 40 to CMIP-9,delete CMIP-12 & Rev 24 to CMIP-13 ML20082C7441991-06-11011 June 1991 Public Version of Rev 13 to Crisis Mgt Implementing Procedure CMIP-12, Classification of Emergency for Oconee Nuclear Station ML20076A7241991-06-10010 June 1991 Public Version of Crisis Mgt Implementing Procedures, Including Rev 39 to CMIP-1,rev 28a to CMIP-2,rev 44 to CMIP-7,rev 39 to CMIP-9 & Rev 10 to CMIP-11 ML20081J9841991-06-10010 June 1991 Rev 3 to EDA-1, Procedure for Estimating Food Chain Doses Under Post-Accident Conditions ML20081K0101991-06-0606 June 1991 Rev 8 to EDA-3, Offsite Dose Projections for McGuire Nuclear Station ML20072S0521991-03-15015 March 1991 Public Version of Revised Crisis Mgt Implementing Procedures,Including Rev 9 to CMIP-11, Classification of Emergency for McGuire Nuclear Station & Rev 11 to CMIP-12, Classification of Emergency for Oconee Nuclear Station ML20066G3621991-02-0101 February 1991 Public Version of Crisis Mgt Implementing Procedures, Including Rev 28 to CMIP-2,Rev 34 to CMIP-4,Rev 38 to CMIP-5,Rev 43 to CMIP-6,Rev 42 to CMIP-7,Rev 29 to CMIP-8, Rev 37 to CMIP-9 & Rev 34 to CMIP-21 ML20082P7611991-01-0101 January 1991 Rev 30 to Odcm,Catawba Nuclear Station ML20072S9621991-01-0101 January 1991 Public Version of Rev 12 to Crisis Mgt Implementing Procedure CMIP-12, Classification of Emergency for Oconee Nuclear Station ML20082P7711991-01-0101 January 1991 Rev 31 to Odcm,Mcguire Nuclear Station ML20072P9621990-11-0808 November 1990 Rev 9 to Crisis Mgt Implementing Procedure CMIP-12, Classification of Emergency for Oconee Nuclear Station ML20028H2211990-10-31031 October 1990 Public Versions of Revised Crisis Mgt Implementing Procedures,Including Rev 37 to CMIP-1,Rev 27a to CMIP-2,Rev 33 to CMIP-4,Rev 37 to CMIP-5 & Rev 42 to CMIP-6 ML20059F4301990-08-22022 August 1990 Public Version of Rev 27 to Crisis Mgt Implementing Procedure CMIP-2, News Group Plan ML20063Q2721990-08-14014 August 1990 Public Version of Revised Crisis Mgt Implementing Procedures,Including Rev 36 to CMIP-1,Rev 32 to CMIP-4,Rev 36 to CMIP-5,Rev 41 to CMIP-6,Rev 40 to CMIP-7,Rev 27 to CMIP-8,Rev 35 to CMIP-9 & Rev 7 to CMIP-11 ML20043F4841990-05-23023 May 1990 Public Version of Crisis Mgt Implementing Procedures, Consisting of Rev 20 to CMIP-13 & Deletion of CMIP-15 & CMIP-17 ML20043B2651990-05-0909 May 1990 Revised Crisis Mgt Implementing Procedures,Including Rev 35 to CMIP-1,Rev 26 to CMIP-2,Rev 31 to CMIP-4,Rev 35 to CMIP-5,Rev 40 to CMIP-6,Rev 39 to CMIP-7,Rev 26 to CMIP-8, Rev 33 to CMIP-9,Rev 2 to CMIP-14 & Rev 10 to CMIP-16 ML20043F4621990-04-20020 April 1990 Rev 5 to Oconee-specific Process Control manual.W/900606 Ltr ML20006C0571990-01-18018 January 1990 Public Version of Rev 33 to Crisis Mgt Implementing Procedure CMIP-1, Recovery Manager & Immediate Staff & Rev 24 to CMIP-2, News Group Plan. ML16152A8951990-01-0202 January 1990 Rev 33 to Public Version of Crisis Mgt Plan for Nuclear Stations. ML15264A1571990-01-0202 January 1990 Revised Crisis Mgt Implementing Procedures,Including Rev 32 to CMIP-1,Rev 29 to CMIP-4,Rev 33 to CMIP-5,Rev 38 to CMIP-6,Rev 37 to CMIP-7,Rev 32 to CMIP-9,Rev 1 to CMIP-14 & Rev 30 to CMIP-21 ML20012A3801990-01-0101 January 1990 Rev 28 to, Offsite Dose Calculation Manual,Oconee,Mcguire & Catawba Nuclear Stations. ML20012A3791990-01-0101 January 1990 Rev 27 to, Offsite Dose Calculation Manual,Oconee Nuclear Station. ML20011D2441989-12-0101 December 1989 Crisis Mgt Implementing Procedures. ML20012A3731989-11-15015 November 1989 Rev 4 to, Process Control Program Oconee Nuclear Station. 1999-08-18 |
Text
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NOV 0 3 576 d
PLANT SYSTEMS SPRAY AND/OR S;RINKLER SYSTEMS _
LIMITING CONDITION FOR OPERATION 3.7.11.2 The spray and/or sprinkler systems located in the following .
areas shall be OPERABLE:
a.
- b. (Plantdependent) c.
APPLICABILITY: All modes ACTIONS:
With a spray and/or sprinkler system inoperable establish a continuous fire watch with backup fire suppression equipment in the unprotectedarea(s),and
- 1. In MODES 1, 2., 3 or 4 restore the system to OPERABLE status within 7' days or be in at least HOT STANCBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
- 2. In MODES 5 or 6 restore the system to OPERABLE status within 7 days or prepare and' submit a Special Report to the Comission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of ino;:erability and the plans for restoring the system to OPERABLE status.
. SURVEILLANCE REOUIREMENTS The spray and/or spinkler systems sftall be demonstrated to be 4.7.11.2 OPERABLE:
- a. At least once per 92 days by cycling each testable valve through one complete cycle. ,
- b. At least once per 12 months:
- 1. By performing a system functional test which includes simulated automatic actuation of the system and ,
verifying that the aut:matic valves in the flow path l actuate to their correct positions.
27TinspectToE'of sorav headers to verify their integrity
- 3. By inspection of each nozzle to verify no blockage.
- c. At least once per 5 years by an air flow test of the open head spray and/or sorinkler system.
7912110f36 _
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