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Category:FUEL CYCLE RELOAD REPORTS
MONTHYEARML20212H6311999-08-19019 August 1999 Rev 2 to PECO-COLR-P2C13, COLR for Pbaps,Unit 2,Reload 12 Cycle 13 ML20198C6751998-11-0505 November 1998 Rev 3 to COLR for PBAPS Unit 3,Reload 11,Cycle 12 ML20155H7721998-10-12012 October 1998 Rev 1 to COLR for Peach Bottom Atomic Power Station Unit 2, Reload 12,Cycle 13 ML20249C4791998-06-0202 June 1998 Rev 6 to COLR for PBAPS Unit 2 Reload 11,Cycle 12 ML20249C4751998-05-0707 May 1998 Rev 5 to COLR for PBAPS Unit 2 Reload 11,Cycle 12 ML20249C4721998-04-0707 April 1998 Rev 4 to COLR for PBAPS Unit 2 Reload 11,Cycle 12 ML20217G9981998-03-10010 March 1998 Rev 2 to PECO-COLR-P3C12, COLR for PBAPS Unit 3 Reload 11, Cycle 12 ML20203E1751998-01-23023 January 1998 Rev 3 to PECO-COLR-P2C12, COLR for Pbaps,Unit 2,Reload 11, Cycle 12 ML20199F7491997-11-0303 November 1997 Rev 1 to PECO-COLR-P3C12, COLR for Pbaps,Unit 3,Reload 11, Cycle 12 ML20198P1471997-08-13013 August 1997 Rev 0 to PECO-COLR-P3C12, COLR for PBAPS Unit 3,Reload 11, Cycle 12 ML20093N6641995-09-29029 September 1995 Rev 0 to Core Operating Limits Rept for PBAPS Unit 3, Reload 10,Cycle 11 ML20076H4331994-09-29029 September 1994 COLR for PBAPS Unit 2 Reload 10,Cycle 11 ML20064L8781994-03-15015 March 1994 COLR for Peach Bottom Unit 2,Reload 9,Cycle 10 ML20058C3531993-11-0303 November 1993 COLR for Peach Bottom Atomic Power Station Unit 3,Reload 9, Cycle 10 ML20095D2071992-04-20020 April 1992 Startup Rept,Cycle 9 ML20094K0481991-12-12012 December 1991 Rev 0 to Core Operating Limits Rept for Peach Bottom Atomic Power Station Unit 3,Reload 8,Cycle 9 ML20070U7581991-02-13013 February 1991 Rev 0 to, Core Operating Limits Rept for Peach Bottom Atomic Power Station Unit 2 Reload 8,Cycle 9 ML20034C3851990-04-23023 April 1990 Core Operating Limits Rept for Peach Bottom Atomic Power Station,Unit 2,Reload 7,Cycle 8 ML20034C3861990-04-23023 April 1990 Core Operating Limits Rept for Peach Bottom Atomic Power Station,Unit 3,Reload 7,Cycle 8 ML20150E6591988-01-31031 January 1988 Rev 0 to 23A5889, Supplemental Reload Licensing Submittal for Peach Bottom Atomic Power Station,Unit 3,Reload 7,Cycle 8 ML20100F0451985-03-31031 March 1985 Rev 1 to Supplemental Reload Licensing Submittal for Peach Bottom Atomic Power Station Unit 3,Reload 6 ML20096H1311984-06-30030 June 1984 Rev 0 to Supplemental Reload Licensing Submittal for Peach Atomic Power Station Unit 2,Reload G ML20064B9841982-12-31031 December 1982 Supplemental Reload Licensing Submittal for Peach Bottom Atomic Power Station,Unit 3,Reload 5 ML20054M0801982-06-30030 June 1982 To Supplemental Reload Licensing Submittal for Peach Bottom Atomic Power Station Unit 3,Reload 4 ML20054J3391982-05-31031 May 1982 Supplemental Reload Licensing Submittal for Peach Bottom Atomic Power Station,Unit 2,Reload 5, Revision 1 ML20003E1541981-02-28028 February 1981 GE BWR Reload 1 Licensing Amend for Peach Bottom Atomic Power Station Unit 3,Fast Scram Control Rod Drive. Suppl 3 ML20003E1551981-02-28028 February 1981 Supplemental Reload Licensing Submittal for Peach Bottom Atomic Power Station Unit 3,Reload 4, Class 1 ML19284A8701980-02-29029 February 1980 Supplemental Reload Licensing Submittal for Reload 4 ML19225D0941979-07-31031 July 1979 Supplemental Reload Licensing Submittal for Reload 3 ML19247B0261979-07-31031 July 1979 GE BWR Reload 1 Licensing Amend for Fast Scram Control Rod Drive,Suppl 2 1999-08-19
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEAR05000278/LER-1999-005-03, :on 990920,uplanned Esfas During Planned Mod Activitives in Main CR Were Noted.Caused by Inattention to Detail by Individuals Performing Work.All CR Mods Were Ceased to Allow Review of Mod Work Packages.With1999-10-20020 October 1999
- on 990920,uplanned Esfas During Planned Mod Activitives in Main CR Were Noted.Caused by Inattention to Detail by Individuals Performing Work.All CR Mods Were Ceased to Allow Review of Mod Work Packages.With
ML20217K9931999-10-14014 October 1999 Safety Evaluation Supporting Amend 234 to License DPR-56 ML20217B4331999-10-0505 October 1999 Safety Evaluation Supporting Amend 233 to License DPR-56 05000278/LER-1999-004-03, :on 990901,3A RPS Bus Was Inadvertently Deenergized,During Planned Mod Activities on Main CR Panel. Caused by Electrician Failing to Self Check Work.All CR Work Was Ceased Immediately & Shutdown Meeting Held1999-10-0101 October 1999
- on 990901,3A RPS Bus Was Inadvertently Deenergized,During Planned Mod Activities on Main CR Panel. Caused by Electrician Failing to Self Check Work.All CR Work Was Ceased Immediately & Shutdown Meeting Held
ML20217G3541999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Pbaps,Units 2 & 3. with ML20216H7091999-09-24024 September 1999 Safety Evaluation Supporting Amends 229 & 232 to Licenses DPR-44 & DPR-56,respectively ML15112A7681999-09-20020 September 1999 SER Accepting Revision 25 of Pump & Valve Inservice Testing Program,Third 10-year Interval for Plant,Units 1,2 & 3 ML20212D1281999-09-17017 September 1999 Safety Evaluation Supporting Proposed Alternatives CRR-03, 05,08,09,10 & 11 05000278/LER-1999-003-03, :on 990814,HPCIS Was Declared Inoperable Due to Erratic Behavior Resulting in Loss of Single High Train Safety Sys.Caused by Weakness in Procedural Guidance. Readjusted Hydraulic Governor Needle Valve.With1999-09-13013 September 1999
- on 990814,HPCIS Was Declared Inoperable Due to Erratic Behavior Resulting in Loss of Single High Train Safety Sys.Caused by Weakness in Procedural Guidance. Readjusted Hydraulic Governor Needle Valve.With
ML20212A5871999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Peach Bottom,Units 2 & 3.With ML20211D5501999-08-23023 August 1999 Safety Evaluation Supporting Amends 228 & 231 to Licenses DPR-44 & DPR-56,respectively ML20212H6311999-08-19019 August 1999 Rev 2 to PECO-COLR-P2C13, COLR for Pbaps,Unit 2,Reload 12 Cycle 13 ML20210N7641999-07-31031 July 1999 Monthly Operating Repts for Jul 1999 for PBAPS Units 2 & 3. with 05000277/LER-1999-005-01, :on 990616,failure to Maintain Provisions of FP Program Occurred.Caused by Less than Adequate Engineering Rigor in Both Development & Review Analysis.Fire Watch Immediately Established.With1999-07-16016 July 1999
- on 990616,failure to Maintain Provisions of FP Program Occurred.Caused by Less than Adequate Engineering Rigor in Both Development & Review Analysis.Fire Watch Immediately Established.With
ML20209H1121999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Pbaps,Units 2 & 3. with ML20195H8841999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Pbaps,Units 2 & 3. with 05000278/LER-1999-002-02, :on 990406,safeguard Sys to Unrelated Door Was Inadvertently Disabled by Security Alarm Station Operator. Caused by Noncompliance with Procedures & Less than Adequate Shift Turnover.Briefed Personnel on Event.With1999-05-0606 May 1999
- on 990406,safeguard Sys to Unrelated Door Was Inadvertently Disabled by Security Alarm Station Operator. Caused by Noncompliance with Procedures & Less than Adequate Shift Turnover.Briefed Personnel on Event.With
ML20206N1661999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Pbaps,Units 2 & 3. with ML20206A2921999-04-20020 April 1999 Safety Evaluation Concluding That Proposed Changes to EALs for PBAPS Are Consistent with Guidance in NUMARC/NESP-007 & Identified Deviations Meet Requirements of 10CFR50.47(b)(4) & App E to 10CFR50 05000278/LER-1999-001-03, :on 990312,ESF Actuation of Rcics Occurred Due to High Steam Flow Signal During Sys Restoration.Temporary Change to Restoration Procedure Was Initiated to Open RCIC Outboard Steam Isolation Valve in Smaller Increments1999-04-0808 April 1999
- on 990312,ESF Actuation of Rcics Occurred Due to High Steam Flow Signal During Sys Restoration.Temporary Change to Restoration Procedure Was Initiated to Open RCIC Outboard Steam Isolation Valve in Smaller Increments
ML20205K7411999-04-0707 April 1999 Safety Evaluation Supporting Amends 227 & 230 to Licenses DPR-44 & DPR-56,respectively ML20205P5851999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Peach Bottom Units 2 & 3.With ML20207G9971999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Peach Bottom Units 2 & 3.With 05000278/LER-1998-009-01, :on 981227,unplanned Esfa Were Noted.Caused by Transformer Insulator Failure.Replaced Failed Insulator. with1999-01-20020 January 1999
- on 981227,unplanned Esfa Were Noted.Caused by Transformer Insulator Failure.Replaced Failed Insulator. with
ML20199E3471998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Peach Bottom,Units 1 & 2.With ML20206P1651998-12-31031 December 1998 Fire Protection for Operating Nuclear Power Plants, Section Iii.F, Automatic Fire Detection ML20205K0381998-12-31031 December 1998 PECO Energy 1998 Annual Rept. with ML20206D3651998-12-31031 December 1998 1998 PBAPS Annual 10CFR50.59 & Commitment Rev Rept. with ML20206D3591998-12-31031 December 1998 1998 PBAPS Annual 10CFR72.48 Rept. with 05000277/LER-1998-008-01, :on 981130,circuit Breaker SU-25 Tripped.Caused by Less than Adequate Procedural Guidance.Operators Verified Sys Integrity & Successfully Returned Sys to Svc.With1998-12-30030 December 1998
- on 981130,circuit Breaker SU-25 Tripped.Caused by Less than Adequate Procedural Guidance.Operators Verified Sys Integrity & Successfully Returned Sys to Svc.With
05000277/LER-1998-007-02, :on 981107,failure to Meet TS & Associated LCO Requirments of Absolute Difference in APRM & Calculated Power of Less than 2% Was Noted.Caused by Substitute Valves Being Used.Removed Substitute Valves.With1998-12-0404 December 1998
- on 981107,failure to Meet TS & Associated LCO Requirments of Absolute Difference in APRM & Calculated Power of Less than 2% Was Noted.Caused by Substitute Valves Being Used.Removed Substitute Valves.With
ML20196G7021998-12-0202 December 1998 SER Authorizing Proposed Alternative to Delay Exam of Reactor Pressure Vessel Shell Circumferential Welds by Two Operating Cycles ML20196E8261998-11-30030 November 1998 Response to NRC RAI Re Reactor Pressure Vessel Structural Integrity at Peach Bottom Units 2 & 3 ML20198B8591998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Pbaps,Units 2 & 3. with 05000278/LER-1998-005-03, :on 981025,inadvertent Unit 3 Electrical Bus E33 Trip (Esfa) During Performance of Unit 2 Electrical Bus E32 Surveillance Test Was Noted.Caused by Personnel Error. Sp S12M-54-E32-XXF4 Was Completed.With1998-11-20020 November 1998
- on 981025,inadvertent Unit 3 Electrical Bus E33 Trip (Esfa) During Performance of Unit 2 Electrical Bus E32 Surveillance Test Was Noted.Caused by Personnel Error. Sp S12M-54-E32-XXF4 Was Completed.With
ML20206R2571998-11-17017 November 1998 PBAPS Graded Exercise Scenario Manual (Sections 1.0 - 5.0) Emergency Preparedness 981117 Scenario P84 ML20198C6751998-11-0505 November 1998 Rev 3 to COLR for PBAPS Unit 3,Reload 11,Cycle 12 ML20195E5341998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Pbaps,Units 2 & 3. with ML20155C6071998-10-26026 October 1998 Safety Evaluation Supporting Amend 226 to License DPR-44 ML20155C1681998-10-22022 October 1998 Safety Evaluation Accepting Proposed Alternative Plan for Exam of Reactor Pressure Vessel Shell Longitudinal Welds ML20155H7721998-10-12012 October 1998 Rev 1 to COLR for Peach Bottom Atomic Power Station Unit 2, Reload 12,Cycle 13 05000277/LER-1998-006-02, :on 980915,automatic RWCU Isolation Occurred While Placing RWCU Sys in Svc.Caused by Unexpected Surge of Water.Procedure Change Was Initiated to Open MO-2-12-74 & RWCU Sys Was Successfully Returned to Svc.With1998-10-0909 October 1998
- on 980915,automatic RWCU Isolation Occurred While Placing RWCU Sys in Svc.Caused by Unexpected Surge of Water.Procedure Change Was Initiated to Open MO-2-12-74 & RWCU Sys Was Successfully Returned to Svc.With
ML20154J2401998-10-0505 October 1998 Safety Evaluation Supporting Amends 224 & 228 to Licenses DPR-44 & DPR-56,respectively ML20154H4771998-10-0505 October 1998 Safety Evaluation Supporting Amends 225 & 229 to Licenses DPR-44 & DPR-56,respectively ML20154G6821998-10-0101 October 1998 SER Related to Request for Relief 01A-VRR-1 Re Inservice Testing of Automatic Depressurization Sys Safety Relief Valves at Peach Bottom Atomic Power Station,Units 2 & 3 ML20154G6631998-10-0101 October 1998 Safety Evaluation Supporting Amends 223 & 227 to Licenses DPR-44 & DPR-56,respectively ML20154H5541998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Pbaps,Units 2 & 3. with 05000278/LER-1998-004-03, :on 980820,automatic RWCU Isolation Occurred While Placing B RWCU Sys Demineralizer in Svc.Caused by less-than-adequate Control of Equipment.Isolated B Demineralizer & Returned RWCU Sys to Svc1998-09-18018 September 1998
- on 980820,automatic RWCU Isolation Occurred While Placing B RWCU Sys Demineralizer in Svc.Caused by less-than-adequate Control of Equipment.Isolated B Demineralizer & Returned RWCU Sys to Svc
05000277/LER-1998-005-02, :on 980824,noted Failure to Meet TS Actions for Suppression chamber-to-drywell Vacuum Breaker Not Being Fully Seated.Caused by Personnel Failing to Take All TS Required Actions.Temporary Procedure Changes Were Made1998-09-18018 September 1998
- on 980824,noted Failure to Meet TS Actions for Suppression chamber-to-drywell Vacuum Breaker Not Being Fully Seated.Caused by Personnel Failing to Take All TS Required Actions.Temporary Procedure Changes Were Made
ML20153B9651998-09-14014 September 1998 Safety Evaluation Supporting Amend 9 to License DPR-12 1999-09-30
[Table view] |
Text
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IFI'RODUCTIQLLAMLEIRitiARY This report provides the cycle-specific parameter limits for:
- ' Average Planar Linear Heat Generation Rate (APLHGR);
Minimum Critical Power Ratio (MCPR); Flow Adjustment Factor (K ); Linear f
- Heat Generation Rate (LHGR);
and Rod Block - Monitor flow biased upscale setpoints for Peach Dottom Atomic Power Station Unit 3,
Cycle 9,
Reload 8.
These values have been determined using NRC-approved methodology and are established such that all applicable limits of the plant safety analysis are met.
This report is submitted in accordance with Technical Specificatlon 6.9.1.0 of Reference (1).
Preparation of this report was performed in accordance with PECo Nuclear Group Procedure NP-11F122.
bEUiGR LIlflTS The limiting APLHGR valae for the most limiting lattice (excluding natural uranium) of each fuel type an a function of AVERAGE PLANAR EXPOSURE is given jn Figures 1 through 6.
Figures 1 through 6 are used when hand calculations are required as specified r
in Technical Specification 3.5.I.
The reduction factors for use during single recirculation' loop operation are shown in Table 1.
These values are documented in Reference (3).-
FCPR LTliTIS The - MCPR values for-use in Technical Specification 3.5.K for and
'each fuel type are given in Figures 7 through 10 and in Tables 2 3.
Table 2 is used when the requirement of 4.5.K.2.a is met.
When this requirement cannot be met, the operating Limit MCPR values as a function of TAU are given in Figures 7 through 10.
At times when the surveillance requirement of specification 4.5.K.2 is not performed Table 3 is used.
These values are documented in Reference (2).
The K core flow - adjustment factor for use in Technical.
Specificatiod 3.5.K is given in Figure 11.
ff The MCPR limits to be used during cycle extension (Increased Core' Flow (ICF), Final Feedwater Temperature Reduction, and Power Coastdown) following EOC are the EOC-2000 Mwd /st to EOC, --Increased Core Flow Limits.
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ROD.llACK MON 12'pjLEllT1'AltD'S The N value for the RBM flow biased upscale setpoints for use in Technical Specification 3.2.C is given in Tabic 4.
This value is
. documented in Referenco (2).
JdHEAR HEAT GEt!EFATION RNES The LUGR value for use in Technical Specification 3.5.J for each fuel type in given in Table 5.
These values are documented in Ecference (4).
FXFFRENCES
- 1) " Technical Specifications and Bases for Peach Botton Atomic Power Station Unit 3", Docket No. 50-278, Appendix A to License No.
DPR-56.
?
2)
" Supplemental Reload Licensing Report for Peach Botton Atomic Power Station Unit 3,. Rolond 8, Cycle 9",
Revision 0, October 1991.
L
- 3) " Loss-of-Coolant Accident Analyses for Peach Botton Atomic
. Power Station Unit 3",
Suppleuent 1,'
NEDE-24082-P-2, Revision 1,
January 1988 an amended.
- 4) " General Electric Standard Application for Reactor Fuel",
NEDE-24011-P-A-10,. February 1991; and NEDE-24011-P-A-10-US, March 1991.
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1.24
- 1.24 - - - -
1.22
- 1.22 -
1.20 1.20 -
i-g g
0.0 0.1 0.2 0.3 -
0.4 0.5 0.6 '
O.7-0.3 0.9 1.0
- OPT B
-T
. OPT A (STANDARD OPERATING CONDMONS)
FIGURE 7
- z-
rtco ruer nanag ment section reco-cot.a-raans
!PD3R81Coro Operating Limits Report Page 12,-Rev. 0 4
6 MCPR OPERATING LIMIT VERSUS T
~
FUELTYPES BP/P8X8R & GE8X8EB 1.40 l
1.40 c
1.33 1,38 -
THIS FIGURE IS REFERRED TO BY 1.30 -
TECHNICAL SPECIFICATION 3.5.K 3,3s
~
1.34 1.34 -
EM'/
osst &cTO
~
- 1.32 -
.O[T 6 t
,c /
1.32 0U g49.5 h 1.30 - Z s
A'afMDf-1.30 o
/
50 I
1.28 1.28 --
77,oG --
p--
'/
j
-'1.26 1.26-j I
1.24-1.24 L -
1.22-
-- 1.22 -
1.20. -
i.20
' O.0 0.1 0.2
- 0.3 0.4 0.5 0.6
. 0.7 0.8 0.9 1.0 OPT B T
OPT A (INCREASED COREFLOW)
FIGURE 8 5
i w
-#,r v,W
~
wi-%'
4 e
me-----wm'-*r-e-me%,--
n-
--c--
a
N
- PEco Fuel Management Section-PECO-COLR-PB3R8
.PB3R8 Core _ Operating Limits Report _
Page 13, Rev. 0 MCPR OPERATING LIMIT VERSUS T
~
FUEL TYPE GE8X8NB 1A0 1.40 -._
1.38 --
1.38 i
THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.5 K 3,3s l
1.36 -
4 1.34 -
Ol G
pOSgEO E
2000 g g[T 1.32 1.32. -
7 RBEFOBEEO y IN g' 3o -
3OOp02jco#D 1.30 x
p 1.28 -
1.28
> 1.26 -
1.26
- 1.24. --
1.24
\\
~ 1.22 1.22
~
1.20 C
-1.20 i
i_
i i
g i
i 0.0 -
0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 OPT B T
OPT A (STANDARD OPERATING Col /DITIONS)
FIGURE 9
l PECO-COLR-PB3R8 PEco Fuel Management Section PB3R8 pore operating Limits Report Page 14, Rev. 0
~
MCPR OPERATING LIMIT VERSUS T FUEL TYPE GE8X8NB 1.40 1.40
~
1.38
- T ---
1.38 -
-t THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.5.K 1.36 1.36 -
/
-4 1.34
- ~ ~ - - -
1.34 -
O--
1.32 hf 1.32 1.30 b.1.30 -
l 7 -
2 1.28 1.28 -
1.26 1.26 -
~
1.24 1.24 - -
1.22 1.22 -
r-r-
i l
1.20 1.20 l
i i
j 0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 OPT B T
OPT A (INCREASED COREFLOW)
FIGURE 10
-(
-1
' ] {;.,-
0 0 '
Kf. Factor vs Core Flow f
a:
1.4 _
Om m :5 0W no.
1.35 4 THIS FIGUREIS REFERRED TO BY E+ E TECHNICAL SPECIFICATIO. 3.5.1 -
N 1.3 ~
x x
{,
~
\\
8.fr 1.25
\\
==
ft H x
W 1.2 -
X i
\\ NN N 8
Kf 1.15 -
x x
i
<=
NN NN NNN
\\
1.1 -~
NN 2
I j
Manutd Flow Cortd g
s x
1.05 -
scoopTuba se+ pow eswon j/
N remon dsoTwo Flow Madrnern = 102.5%
~ '87 "
1 2
"*" ".".*frman = 112.0%
flow M m
/
~
Flow MaMrnurn = 117.0%
0.95 _
mm DM co
?
~
gn O.9 tn o 20 25 30
-35 40 45 50 55 60 65 70 75 80 85 90 95 100
'E 5'4 Core Flow % of Rated
?5
- e o us FIGURE 11 e
i i
y
~.. _..
?,, :.;?)
PECO-COLR-PD3R8
' ' ' PECb Fuel Management Section' Page 16, Rev. 0
'fcPB.%8 ' Core Opciating' Limits Report
-g
-TABLE 1 SINGLE IDOP REDUCTION FACTORS E!EL TYPE Egp_UCTION FACTOR 0.81 BP/P8X8R :
-GE8X8EB; 0.73
-- GE8X8ND 0.73 r
1 --
'h i
THIS TABLE IS REFERRED.TO BY -
a
- si.
1 w c,
' TECIINICAL SPECIFICATION. 3.5.I
PECO-COLR *B3R8 PECQ Fuel Management'Section' Page 17, Rev. 0
...PB3R8 Core Operating Limits Report r
TABLE 2 OPERATING LIMIT MCPR VALUES FOR VARIOUS CORE EXPOSURES
FUEL TYEE EOR INCRJMENTAL CYCIJi_ SORE AVERAGE FJPOSUAE BOC TO 2000 MWD /T 2000 MWD /T BEFORE EOC
-)
BEFORE EOC
?O EOC Standard.Opprafinn Conditions 1;
BP/P8X8R 1.27 1.29 GE8X8EB 1.27 3.29 GE8X8NB 1.29 1.30 Increased Core Flow BP/P8X8R 1.27 1.30 GE8X8EB 1.27 1.30
- GE8X8NB 1.29-1.31
- If. Technical Specification Requirement 4.5.K.2.a is met.
- * - These values-- shall be increased by- 0.01 for single loop operation.
THIS TABLE IS REFERRED TO BY 6
L TECHNICAL SPECIFICATION 3.5.K x
4 V -
.*. PECo,Fual Management Section PECO-COLR-PB3R8
~
"- PB3RB Coro Operating Limits Report Page 18, Rev. 0 TABLE 3 OPEP ATING LIMIT MCPR VAIDES FOR VARIOUS CORE EXPOSURES
FUEL T1PE FOR INCREMEE['AL CYCLE CORE _ AVERAGE EXEQ11EE BOC TO 2000 MWD /T 2000 MWD /T BEFORE EOC BEFORE ECC TO EOC Standard Opgrpting_ Conditions BP/P8X8R 1.32 1.33 GEBX8EB
-1.32 1.33 GE8X8NB 1.32 1.34 Incrnqngd Core Flow BP/P8XBR 1.33 1.34 GE8X8EB.
1.33 1.34 GEBX8HB' 1.33-1.35
- If Technical Specification Surveillance Requirement 4.5.K.2 is not perforlacd.
These values shall -be increased by 0.01 for singic loop operation.
THIS TABLE IS REFERRED TO BY TECHNICA!. SPECIFICATION 3.5 K 4
O
s m.
... j.
?
..PECo Fue -l Management'Section PECO-COLR-PD3RB
,PB3RB Core Operating Limits Report Page 19, Rev. 0 v-TAllIE__4 ROD BIACK HONITOR SETPOINT N=110 THIS TABLE IS REFERRED TO BY TECFDfICAL SPECIFICATION 3.2.C
+
N y
99 w
-M y'
am,
- .e PECO-COLR-PB3RS PEco,Fual Management Section
- PD3R0 Coro Operating Limits Report Pagc 20, Rev. 0
~
r t
TABLE 5 DESIGN T,TRA_lLIIEA.T CENERATLO_lLJATE LTMITji
?
- EUEJ, TYPJ 11[GR LTMLT BP/ PBX 8R 13.4 KW/ft GEBX8EB 14.4 KW/ft GE8X8NB 14.4 KW/ft e
THIS TABLE IS REFERRED TO BY
^
h TECHNICAL SPECIFICATION 3.5 J
~
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