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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20155C6391998-10-26026 October 1998
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
[Table view]
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211A9881999-08-18018 August 1999
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
[Table view] |
Text
ATTACHMENT 1 PROPOSED TECHNICAL SPECIFICATION REVISION OCONEE 3, CYCLE 6 Pages 2.1-3d 3.5-20 2.1-9 3.5-20a 2.1-12 3.5-20b 2.3-10 3.5-23 3.1-23 (New) 3.5-23a 3.2-2 3.5-23b 3.5-13 3.5-26 3.5-17 3.5-26a 3.5-17a 3.5-26b 3.5-17b 8009030 513
Section Page 1.5.4 Instrument Channel Calibration 1-3 1.5.5 Heat Balance Check 1-4 1.5.6 Heat Balance Calibration 1-4 1.6 POWER DISTRIBUTION 1-4 1.7 CONTAINMENT INTEGRITY 1-4 2 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.1-1 2.1 SAFETY LIMITS, REACTOR CORE 2.1-1 2.2 SAFETY LIMITS, REACTOR COOLANT SYSTEM PRESSURE 2.2-1 2.3 LIMITING SAFETY SYSTEM SETTINGS, PROTECTIVE 2.3-1 INSTRUMENTATION 3 LIMITING CONDITIONS FOR OPERATION 3.1-1 3.1 REACTOR COOLANT SYSTEM 3.1-1 3.1.1 Operational Components 3.1-1 3.1.2 Pressurization, Heatup, and Cooldown Limitations 3.1-3 3.1.3 Minimum Conditions for Criticality 3.1-8 3.1.4 Reactor Coolant System Activity 3.1-10 3.1.5 Chemistry 3.1-12 3.1.6 Leakage 3.1-14 3.1.7 Moderator Temperature Coefficient of Reactivity 3.1-17 3.1.8 Single Loop Restrictions 3.1-19 3.1.9 Low Power Physics Testing Restrictions 3.1-20 3.1.10 Control Rod Operation 3.1-21 3.1.11 Shutdown Margin 3.1-23 3.2 HIGH PRESSURE INJECTION AND CHEMICAL ADDITION SYSTEMS 3.2-1 3.3 EMERGENCY CORE COOLING, REACTOR BUILDING COOLING, REACTOR 3.3-1 BUILDING SPRAY AND LOW PRESSURE SERVICE WATER SYSTEMS 11
- 2. The combination of radial and axial peak that causes central fuel melting at the hot spot. The limit is 20.15 kw/ft for Unit 3.
Power peaking is not a directly observable quantity, and, therefore, limits have been established on the bases of the reactor power imbalance produced by the power peaking.
The specified flow rates for Curves 1, 2 and 3 of Figure 2.1-2C correspond to the expected minimum flow rates with four pumps, three pumps and one pump in each loop, respectively.
The maximum thermal power for three-pump operation is 87.2 percent due to a power level trip produced by the flux-flow ratio 74.7 percent flow x 1.08 =
80.7 percent power plus the maximum calibration and instrument error (Reference 4). The maximum thermal power for other coolant pump conditions are produced in a similar manner.
For each curve of Figure 2.1-3C a pressure-temperature point above and to the left of the curve would result in a DNBR greater than 1.30 or a local quality at the point of minimum DNBR less than 22 percent for that particular reactor coolant pump situation. The curve of Figure 2.1-1C is the most restrictive of all possible reactor coolant pump-maximum thermal power combinations shown in Figure 2.1-3C.
References (1) Correlation of Critical Heat Flux in a Bundle Cooled by Pressurized Water, BAW-10000, March 1970.
(2) Oconee 3, Cycle.3 - Reload Report - BAW-1453, August, 1977.
(3) Admendment 1 - Oconee 3, Cycle 4 - Reload Report - BAW-1486, June 12, 1978.
(4) Oconee 3, Cycle 6 - Reload Report - BAW- 1634, August, 1980 2.1-3d
THERMAL POWER LEVEL, %
120 112 I ACCEPTABLE 110 M,= 0. 79 I4 PUMPI 1lOPERATION 10 M2 =-2. 54
(-55,90) 904 ACCEPTABLE.
3 & 4 PUMP 80 80 (40,9501) 707.17~
OPERATION 70
(-55,65.17) (40,65.17)
- 59. 42 ACCEPTABLE UA 2,3 &.4 PUMP OPERATION- 50
(-55,37.42) - 0.(40, 37.42)
- 30
-20 UNACCEPTABLE UNACCEPTABLE OPERATION ifOPERATION Iv' - 10 I
-60 -50 -40 -30 -20 -10 0 10 20 30 40 50 60 Reactor Power Imnalance, %
CORE PROTECTION SAFETY LIMITS UNIT 3 UKEPOWEOCONEE NUCLEAR STATION Figure 2.1-2C 2.1-9
2400 ACCEPTABLE OPERATION o 2200
- 2000 S1 '2 3 W/
1800 1600 I 560 580 600 620 640 Reactor Coolant Outlet Temperature,F Power, Pumps Type of Curve Coolant Flow, gpm % Operating Lim 1 374,880 (100%)* 112 4 DNBR 2 280,035 (74.7%) 87.2 3 DNBR 3 183,690 (49.0%) 59.4 2 Quality
- 106.5% of first-core dusign flow.
CORE PROTECTION SAFETY LIMITS UNIT 3 2.1-12 OCONEE NUCLEAR STATION Fiqure 2.1-3C
- 0a THERMAL POWER LEVEL, %
(.14,11) 108 1108)
ACCEPTABLE I
.4PUMP - 100 M M1 = 0.88 [OPERATION M 2 = -1. 76
-90
(-40,85) . (30,85)
ACCEPTABLE 80 PUMP 70 OPERATION 60
(-40,57.67) (30,57.67) 52.92 5
ACCEPTABLE PUMP 40 OPERATION
(-40,29.92) 30 (30,29-.92)
-- 20 UNACCEPTABLE UNACCEPTABLE OPERATION - - 10 - c I OPERATION mI Ii iIia; I I t
-60 -50 30 -20 -10 0 10 20 30 40 50 Power Imnalance, %
PROTECTIVE SYSTEM MAXIMUM ALLOWABLE SETPOINTS UNIT 3 UKEPOWE OCONEE NUCLEAR STATION Figure 2.3-2C 2.3-10
Bases A sufficient SHUTDOWN MARGIN ensures that 1) the reactor can be made subcritical from all operating conditions, 2) the reactivity transients associated with postulated accident conditions are controllable within acceptable limits, and
- 3) the reactor will be maintained sufficiently subcritical to preclude inadvertent criticality in the shutdown condition.
During power operation and startup the SHUTDOWN MARGIN is known to be within limits if all control rods are OPERABLE and withdrawn to or beyond the insertion limits specified in Specification 3.5.2.
During refueling conditions equivalent protection is provided in the requirements of Specification 3.8.4.
3.1-23
Bases The high pressure injection system and chemical addition system provide con trol of the reactor coolant system boron concentration.(1) This is normally accomplished by using any of the three high pressure injection pumps in series with a boric acid pump associated with either the boric acid mix tank or the concentrated boric acid storage tank. An alternate method of boration will be the use of the high pressure injection pumps taking suction directly from the borated water storage tank.(2)
The quantity of boric acid in storage in the concentrated boric acid storage tank or the borated water storage tank is sufficient to borate the reactor coolant system to a 1% Ak/k subcritical margin at cold conditions (70 0 F) with the maximum worth stuck rod and no credit for xenon at the worst time in core life. The current cycles for each unit, Oconee 1 Cycle 6, Oconee 2 Cycle 5, and Oconee 3 Cycle 6 were analyzed with the most limiting case selected as the basis for all three units. Since only the present cycles were analyzed, the specifications will be reevaluated with each reload. A minimum of 995 ft. 3 of 8,700 ppm boric acid in the concentrated boric acid storage tank, or a minimum of 350,000 gallons of 1800 ppm boric acid in the borated water storage tank (3) will satisfy the requirements. The volume requirements include a 10%
margin and, in addition, allow for a deviation of 10 EFPD in the cycle length.
The specification assures that two supplies are available whenever the reactor is critical so that a single failure will not prevent boration to a cold con dition. The required amount of boric acid can be added in several ways. Using only one 10 gpm boric acid pump taking suction from.the concentrated boric acid storage tank would require approximately 12.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> .to inject the required boron. An alternate method of addition is to inject boric acid from the borated water storage tank using the makeup pumps. The required boric acid can be injected in less than six hours using only one of the makeup pumps.
The concentration of boron in the concentrated boric acid storage tank may be higher than the concentration which would crystallize at ambient conditions.
For this reason, and to assure a flow of boric acid is available when needed, these tanks and their associated piping will be kept at least 10 0 F above the crystallization temperature for the concentration present. The boric acid concentration of 8,700 ppm in the concentrated boric acid storage tank cor responds to a crystallization temperature of 77 0F and therefore a temperature requirement of 87 0F. Once in the high pressure injection system, the concen trate is sufficiently well mixed and diluted so that normal system temperatures assure boric acid solubility.
REFERENCES (1) FSAR, Section 9.1; 9.2 (2) FSAR, Figure 6.2 (3) Technical Specification 3.3 3.2-2
REFERENCES (1) FSAR, Section 3.2.2.1.2 (2) FSAR, Section 14.2.2.2 (3) FSAR, SUPPLEMENT 9 (4) B&W FUEL DENSIFICATION REPORT BAW-1409 (UNIT 1)
BAW-1396 (UNIT 2)
BAW-1400 (UNIT 3)
(5) Oconee 1, Cycle 4 - Reload Report - BAW 1447, March, 1977, Section 7.11 (6) Oconee 3, Cycle 6 - Reload Report - BAW-1634, August, 1980.
3.5-13
(158, 102) (267, 102) 100 POWER LEVEL go 90 CU(261.92)
CUTOFF =
100% FP) 80 SHUTDOWN MARGIN (251,80 LIMIT RESTRICTED 70 REGION OPERATION IN THIS KW/FT LIMIT
'c 60 REGION NOT ALLOWED 50 (83, 50)
PERMISSIBLE OPERATING REGION 40 30 20 (0,14) , 13,15) 10 0
0 20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 0 25 50 75 100 Rod Index, S Witnarawn Bank 5 0 25 50 75 100 I II Bank 6 0 25 50 75 100 Bank 7 ROD POSITION LIMITS FOR FOUR-PUMP OPERATION FROM 0 TO 200 + 10 EFPD UNIT 3 DUKEPOWER OCONEE NUCLEAR STATION Figure 3.5.2-id 3.5-17
100 (208.102) (267,102)
POWER LEVEL '
90 CUTOFF = 100%FP (261.92) 80 SHUTDOWN MARGIN --- 510 (251,80)
LIMIT RESTRICTED 70 - OPERATION IN THIS REGION 3r REGION NOT ALLOWED CD Lo C.4 60 50 - (135,50) PERMISSIBLE OPERATING REGION 40 30 (84,27) 20 (0,10) (58.15) 0 20 40 60 80 100 120 140 150 180 200 220 240 260 280 300 0 25 50 75 100 Rod Index, 5 Witndrawn Bank 6 0 25 50 75 100 II I I Bank 7 0 25 50 75 100 I I I I Bank 7 ROD POSITION LIMITS FOR FOUR-PUMP OPERATION AFTER 200 + 10 EFPD UNIT 3 UKEPOWEOCONEE NUCLEAR STATION Figure 3.5.2-1C2 3.5-17a
Figure 3.5.2-1C3 Deleted During Oconee Unit 3, Cycle 6 Operation 3.3-1b
K. 0 A - RESTRICTED 3-RCP 100 -B - RESTRICTED 2.3-RCP.
90 80 (158,77) 242.77) (30077) 70 3-RCP SHUTDOWN MARGIN LIMIT B PERMSSIBLE OPERATING M 60 REGION 3-RCP co
( 158,52) (300,52) 50 2-RCP (164, 52)
SM LIMIT 40 A (83, 3.8) KW FT LIMIT 30 PERMISSIBLE OPERATING REGION (94,30) 2,3-RCP (83,25) 20 13,12) A 10 (0-8) 3,8.
0L
- 0. 20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 O 25 50 75 100 Rod Index, 5 Witnerawn Bank 5 0 25 50 75 100 Bank 6 0 25 50 75 100 SI I I Bank 7 ROD POSITION LIMITS FOR TWO- & THREE- PUMP OPERATION FROM 0 to 200 + 10 EFPD UNIT 3 UKEPOWE OCONEE NUCLEAR STATION Figure 3.5.2-2C1 3.5.20
t00 A - RESTRICT 3-RCP 90 B - RESTRICT 2,3-RCP 80 (242,77) (300,77)
(208,77) 70 - 3 OPERATION IN THIS REGION NOT ALLOWED ull) 60 (208, 52)
(15850 (300, 52)
S 50 50 40 3.-RCP (135,38) 2-RCP SHUTDOWN MARGIN -1g- .g...SHUTDOWN MARGIN 30 - LI1M IT 1,5 2 ) LIMIT.
PERMISSIBLE OPERATING 20 - REGION 2.3-RCP (58,12) 10 0 20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 0 25 50 75 100 Rod Index, %Witndrawn Bank 5 0 25 50 75 100 Bank 6 0 25 50 75 100 Bank 7 ROD POSITION LIMITS FOR TWO- & THREE- PUMP OPERATION AFTER 200 + 10 EFPD UNIT 3 DUKEPOWO OCONEE NUCLEAR STATION Figure 3.5.2-2C2 3.5-20a
Figure 3.5.2-2C3 Deleted During Oconee Unit 3, Cycle 6 Operation 3.5-20b
RESTRICTED REGION (23.102)
(-30,102)
(-29,92) (25,92)
(-38,80) 80 (25, 80)
- 60 C
PERMISSIBLE OPERATING REGION 40 20 I I 0 I
-40 -30 -20 -10 0 +10 +20 +30 Axial, Power Imoalance, %
OPERATIONAL POWER IMBALANCE ENVELOPE UNIT 3 DUKEPOWER OCONEE NUCLEAR STATION Figure 3.5.2-3C1 3.5-23
Figure 3.5.2-3C2 Deleted During Oconee Unit 3, Cycle 6 Operation 3.5- 2 3a
Figure 3.5.2-3C3 Deleted During Oconee Unit 3, Cycle 6 Operation 3.5-23b
(6. 5, 102) 100 - (36,102) RESTRICTED REGION (6. 5,92) (34' 5, 92) 80 (0(80) (55, 80) 60 CN (100. 50) 40 PERMISSIBLE OPERATING REGION 20 0I 0 20 40 60 80 100 Bank 8 Position, % Witndrawn APSR POSITION LIMITS FOR OPERATION FROM 0 TO 200 + 10 EFPD UNIT 3 DUKEPOWEROCONEE NUCLEAR STATION Figure 3.5.2-4c1 3.5-26
- 100 (13, 102) 100 (36, 102)
RESTRICTED REGION (11.5,92) (459 )
80 (0,80) (55,80) to0 (100,50)
PERMISSIBLE OPERATING REGION 3 40 20 0 of 0 20 40 60 80 100 Bank 8 Position, % Witndrawn APSR POSITION LIMITS FOR OPERATION AFTER 200 + 10 EFPD UNIT 3 UHPOWE OCONEE NUCLEAR STATION Figure 3.5.2-4C2 3.5-26a
Figure 3.5.2-4C3 Deleted During Oconee Unit 3, Cycle 6 Operation
- 3. 5-26b
ATTACHMENT 2 OCONEE UNIT 3, CYCLE 6 RELOAD REPORT BAW-1634 I.
