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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
1 m ,
I -. a j L*]l&
Q _.....n. . -
3.5.2 control Rod Group and Power Distribution Limits Applicability This specification applies to power distribution and operation of control rods during power operation.
Obiective To assure an acceptable core power distribution during power operation, to set a limit on potential reactivity insertion from a hypothetical control rod ejection, and to assure core subcriticality after a reactor trip.
Specification 3.5.2.1 The available shutdown margin shall be not less than 1% Ak/k with the highest worth control rod fully withdrawn.
3.5.2.2 Operation with inoperable rods:
- a. Operation with more than one inoperable rod,as defined in Specification 4.7.1 and 4.7.2.3, in the safety or regulating rod groups shall not be permitted.
- b. If a control rod in the regulating or safety rod groups is declared inoperable in the withdrawn position as defined in Specification 4.7.1.1 and 4.7.1.3, an evaluation shall be initiated immediately to verify the existance of 1% Ak/k hot shutdown margin. Boration may be initiated either to the worth of the inoperable rod or until the regulating and l transient rod groups are fully withdrawn, whichever occurs ,
first. Simultaneously a program of exercising the remain- )
ing regulating and safety rods shall be initiated to verify operability,
- c. If within one (1) hour of determination of an inoperable rod as defined in Specification 4.7.1, it is not determined that a 1% Ak/k hot shutdown margin exists combining the l worth of the inoperable rod with each of the other rods, i the reactor snall be brought to the hot standby condition i until this margin is established. '
- d. Following the determination of an inoperable rod as defined in Specification 4.7.1, all rods shall be exercised within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and exercised weekly until the rod problem is sol-ved. i 1
- e. If a control rod in the regulating or safety rod groups is declared inoperable per 4.7.1.2, power shall be. reduced to 60% of the thermal power allowable for the reactor cool-ant pump combination.
l 7 911270 7 yp i
s T i
)
I i
I
- c. Except for physics tests or exercising control rods, the control '
rod withdrawal limits are specified on Figures 3.5.2-1A1, 3.5.2-1B1, 3.5.2-1A2, and 3.5.2-1B2 for four pump operation and on Figure 3.5.2-2A and 3.5.2-2B for three or two pump operation. If the con-trol rod position limits are exceeded, corrective measures shall be taken immediately to achieve an acceptable control rod position.
Acceptable control rod positions shall be attained within four hours.
- d. Except for physics tests, power shall not be increased above the power level cutoff (see Figures 3.5.2-1) unless the xenon reactivity l is within 10% of the equilibrium value for operation at rated power and j asymptotically approaching stability. ;
i 3.5.2.6 Reactor Power Imbalance shall be monitored on a frequency not to exceed two hours during power cperation above 40 percent rated power. Except for physics tests, imbalance shall be maintained within the envelope
, defined by Figure 3.5.2-3A and 3.5.2-3B. If the imbalance is not within the envelope defined by Figure 3.5.2-3A and 3.5.2-3B, corrective measures shall be taken to achieve an acceptable imbalance. If an acceptable imbalance is not achieved within four hours, reactor power shall be reduced until imbalance limits are met.
3.5.2.7 The control rod drive patch panels shall be locked at all times with limited access to be authorized by the superintendent.
Bases The power-imbalance envelope defined in Figure 3.5.2-3A and 3.5.2-3B is based on LOCA analyses which have defined the .cximum linear heat rate (see Figure 3.5.2-4) such that the maximum clad temper o 1111 not exceed the Interim Acceptance Criteria. Corrective measures w.. ou taken immediattly should the indicated quadrant tilt, rod position, or imbalance be outside tLsir specified boundary.
Operation in a situa* ton that would cause the interim acceptance criteria to be approached should a LOCA occur is highly improbable because all of the power dis-tribution parameters (quadrant tilt, rod position, and imbalance) must be at their limits while simultaneously all other engineering and uncertainty factors are also at their limits.* Conservatism is introduced by application of:
- a. Nuclear uncertainty factors
- b. Thermal calibration
- c. Fuel densification effects
- d. Hot rod manufacturing tolerance factors The 30 percent overlap between successive control rod groups is allowed since the worth of a rod is lower at the upper and lower part of the stroke.
Control rods are arranged in groups or banks defined as follows:
l l
- Actual operating limits depend on whether or not incore or excore detectors are used and their respective instrument and calibratien errors. The method used to define the operating li=its is defined in plant operating procedures.
1 3.5-8 4
,e . - , ,- -.
, r . - - - ,-
/
3 5 5 l l 1 ROD INDEX I S THE PERCENTAGE SUM OF THE WITHDRAWAL OF THE OPER ATING GROUPS.
- 2. THE ADDI TION AL RESTRICTI ONS 0.J W I THDR AW AL (H ASHED ARE A) ARE IN EFFECT AFTER 285 FULL POWER DAYS OF OPERATION.
125 188 235 284 ,
100 - _
l 92 _
/
172 250 80 _
POWER _
RESTRICTED REGION LEVEL CUT 0FF j PERMISSIBLE u
% OPERATING j GO -
8 REGION
<= ~
5 l e
g 40 -
l a.
20 - _
t t t g g 50 100 150 200 250 300 Rod Index," Withdrawal 100 0 25 50 75 I I t I a 0 25 50 75 100 GROUP 7 i i . . .
GROUP 8 0 25 50 75 t00
' ' ' ' J GROUP 5 CCNTROL R00 GROUP WITH0RAWAL LIMITS FOR 4 PUMP OPERATION l
. UNIT 1 l onthn) OCONEE NUCLEAR STATION 3.5-8b -
s
' -' Figure 3.5.2-1A1
3 , I I g g 1 ROD INDEX I S THE P ERCENTAGE SlM OF THE WI THDR AWAL OF THE OPER ATt NG GROUPS.
2 THE ADDITION AL RESTRI CTI ONS ON WI TH DR A A AL (H ASHED ARE A) ARE IN EFFECT AFTER 285 FULL PO*ER DAYS OF OPERATION.
125 265 284 100 - f q ,
M E 92 -
" POWER LEVEL J 246 RESTRICTED AEGION 3
= CUTOFF 80 -
WITH0RAWAL LIMIT
[
o et N N
- 60 - y S -
% PERMISSIBLE
40 -
~ .
1 20 - .
l l
0 i i i , ,
50 100 150 200 250 300 Rod index, 5 Withdrawal 0 25 50 75 100 8 I i e 3 0 25 50 75 100 GROUP 7 i i i i ,
0 25 50 75 100 GROUP 6 i t f g g GROUP 5 CONTROL R00 GROUP WITH0RAWAL LIMITS FOR 4 PUMP OPERATION
' UNIT 1 j
3.5-8c (mteowta OCONEE NUCLEAF STATION Figure 3.5.2-1 A2 l
- w. .
)
I i s e s
- 1. ROD INDEX I S THE PERCENTAGE SUM OF THE WITHORAWAL OF TH E OP ER AT I NG GROUP S.
- 2. THE ADDITIONAL RESTRICTIONS ON WITHDRAAAL (HASHED AREAS) ARE MODI FI ED AFTER 435 FULL POWER D AYS OF OPERATION. (SEE FIGURE 3.5.2 1B)
- 291.4 WITH0RAWAL LIMIT 125 189 246 100 -
90 -
, 85.5 .__
= b 264 182 y 80 y,
RESTRICTED REGION
\ POWER l.EVEL CUT 0FF M l g 60 -
PERMISSIBLE
.d
'=
[ OPERATING f g REGION i h 40 -
f -
20 - -
l t i I I I 50 100 150 200 250 300 Rod index, 'I Withdrawal 0 25 50 75 100 I I i t I Group 7 0 25 50 75 100 i f f e I Group 6 0 25 50 75 100 t t t t I Group 5 CONTROL R00 GROUP WITH0RAWAL LIMITS FOR 4 PUMP OPERATION m UNIT 2 3 5-Sd 'gou rma OCONEE NUCLEAR STATION Figure 3.5.2-181
s
/
, e a i s i 1 ROD INDEX l S THE PERCENTAGE SUM OF THE WI THDRAWAL OF THE OPERATING GROUPS.
2 THE ADDITIONAL RESTRI CTlONS ON WI THDRAWAL (HASHED AREAS) ARE IN EFFECT AFTER 435 FULL POWER DAYS OF OPERATION.
291.4 125 270 100 -
,j 90 -
, 85.5 -
fg 80 RESTRICTED REGION POWER ]
LEVEL Withdrawal Limit 250 -
j CUT 0FF g 60 -
~
k PERMISSIBLE o s OPERATING
- 2 g O REGION
$ 40 -
[ -
20 - -
/
f f I i 1 50 100 150 200 250 300 Rod Index. ') Withdrawal 0 25 50 75 100 e i 1 1 I Group 7 0 25 50 75 100 l i f f I Group 6 0 25 50 75 100 t t t t i Group 5 CONTROL R00 GROUP WITH0RAWAL LIMITS FOR 4 PUMP OPERATION UNIT 2 3.5-8e ! k OCONEE NUCLEAR STATION Figure 3.5.2-182
/
s u I 3 1 1 ROD INDEX 1 S THE PERCENTAGE SUM OF THE #1 THDRAWAL OF THE OPERATING GROUPS.
5 a
125 291.4 b100 - .
u s
RESTRICTED
[
REGION -
g 80 5 .%
' l
\
C.4 l
= 60 -
s -
PERMISSIBLE l
5 [ OPERATING 2 N REGION 3
e 40 -
l E
20 - -
1 I I I t 50 100 150 200 250 300 Rod index, $ Withdrawal 0 25 50 75 100 R R R t I Group 7 0 25 50 75 100 f f i e Group 6 0 25 50 75 100 e i t t l Group 5 CONTROL R00 GROUP WITH0RAWAL LIMITS FOR 3 AND 2 PUMP OPERATION i
l l
UNIT 1 3.5-8f ;ent row OCONEE NUCLEAR STATION l Figure 3.5.2-2A I
1 ,
J
. i i i i i
- t. ROD INDEX t S THE PERCENTAGE SUM OF THE WI THDR AWAL OF THE OPERATI NG GROUPS.
=
2
~
125 b100 - _
8
?
=
RESTRICTED REGION -
g 80 w
2 .c g 60 -
.S PERMISSIBLE S s OPERATING 2 REGION o
40 - -
20 - _
i , i , ,
50 100 150 200 250 300 Rod Index, ' Withdrawal 0 25 50 75 100 1 1 I e t Graup 7 0 25 50 75 100 i t i t t Group 6 25 50 75 100 t t i Gr0uu 5 CONTROL R00 GROUP WITH0RAWAL LIMITS FOR 3 AND 2 PUMP OPERATION l
UNIT 2 3.5-8g #E ste OCONEE NUCLEAR STATION Y Figure 3.5.'2-28
3 POWER LEVEL,fi 120 --
RESTRICTED REGION 20.4 +5 100 --
80 __
-31 61 60 __ 61 - +24 l I
40 -_
PERMISSIBLE OPERATING REGION 20 _ _
1 l l l l
-40 20 0 20 40 I Core imbalance.fs OPERATIONAL POWER lMBALANCE ENVELOPE i
1 1
3.5-8h (ount.rowen g UNIT 1 OCONEE NUCLEAR STATION Figure 3.5.2-3A
m POWER LEVEL, f, RESTRICTED REGION
-20.4 +6.1
~~100
__ 80 4
1
-29 61 __60 61 - +22 1
1 PERMISSIBLE OPERATING REGION
- 40 l
l l
_ _20 40 20 0 +20 +40 Care imbalance, ",
OPERATIONAL POWER IMBALANCE ENVELOPE UNIT 2 3.5-81 (ouu r' win OCONEE NUCLEAR STATION o
M Figure 3.5.2-3B
. . )i
'h i
20 18
.,s y
a 16
% \
- !E )
S a
14 l
l 12 2 4 6 8 10 12 0
Axial Location From Bottom Of Core,Ft; l I
l l
LOCA LIMITED MAXIMUM ALLOWABLE LINEAR HEAT RATE 1
1 3.5-83 'sat rom Y. OCONEE NUCLEAR STATION Figure 3.5.2-4 1
