L-08-317, Core Operating Limits, and Pressure and Temperature Limits Report

Core Operating Limits, and Pressure and Temperature Limits Report

ML083650031
Person / Time
Site:	Davis Besse
Issue date:	12/16/2008
From:	Allen B FirstEnergy Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-08-317
Download: ML083650031 (45)

Text

FENOC F0NO % 5501 North State Route 2 FirstEnergyNuclear Operating Company Oak Harbor, Ohio 43449 Barry S. Allen 419-321-7676 Vice President- Nuclear Fax: 419-321-7582 December 16, 2008 L-08-317 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001

SUBJECT:

Davis-Besse Nuclear Power Station, Unit 1 Docket Number 50-346, License No. NPF-3 Core Operating Limits Report and Pressure and Temperature Limits Report Enclosed please find the current Davis-Besse Nuclear Power Station, Unit 1 (DBNPS)

Core Operating Limits Report (COLR) and the Pressure and Temperature Limits Report (PTLR). Both reports support the implementation of License Amendment No. 279, Improved Technical Specifications. Enclosure 1 contains the COLR and is submitted in accordance with the DBNPS Technical Specification 5.6.3. Enclosure 2 contains the PTLR and is submitted in accordance with the DBNPS Technical Specification 5.6.4.

There are no regulatory commitments contained in this letter. If there are any questions or if additional information is required, please contact Mr. Thomas A. Lentz, Manager -

Fleet Licensing, at (330) 761-6071.

Sincerely, Barry S. Allen

Enclosures:

A. FirstEnergy Nuclear Operating Company, Davis-Besse Unit 1, Cycle 16, Core Operating Limits Report, Revision 2 B. FirstEnergy Nuclear Operating Company, Davis-Besse Unit 1, 21 Effective Full Power Years Pressure and Temperature Limits Report, Revision 0

ý4W)1

Davis-Besse Nuclear Power Station, Unit 1 L-08-317 Page 2 cc: NRC Region III Administrator NRC Resident Inspector NRR Project Manager Utility Radiological Safety Board

Enclosure A L-08-317 FirstEnergy Nuclear Operating Company, Davis-Besse Unit 1, Cycle 16, Core Operating Limits Report, Revision 2 (34 Pages)

Cycle 16 COLR Page 1 of 34 Revision 2 FIRSTENERGY NUCLEAR OPERATING COMPANY DAVIS-BESSE UNIT 1 CYCLE 16 CORE OPERATING LIMITS REPORT Prepared by D. B. Kelley,"--

Reviewed by q ~L ~

P. R. Gilles Approved by J. lnd LIST OF EFFECTIVE PAGES Page 1 through 34 Rev. 2

Cycle 16 COLR Page 2 of 34 Revision 2 1.0 Core Operating Limits This CORE OPERATING LIMITS REPORT for DB-1 Cycle 16 has been prepared in accordance with the requirements of Improved Technical Specification 5.6.3. The Core Operating Limits have been developed using the methodology provided in reference 2.0 (1). The licensed length of Cycle 16 is 730 EFPDs (based on a reactor thermal rating of 2817 MWt).

The following cycle-specific core Operating Limits, Protective Limit and Flux -A Flux -

Flow Reactor Protection System Allowable Values are included in this report:

1. SL 2.1.1.1 Reactor Core Safety Limits

2. LCO 3.1.1 SHUTDOWN MARGIN (SDM)

3. LCO 3.1.3 Moderator Temperature Coefficient (MTC)

4. LCO 3.1.7 Position Indicator Channels

5. LCO 3.1.8 PHYSICS TESTS Exceptions - MODE 1

6. LCO 3.1.9 PHYSICS TESTS Exceptions - MODE 2

7. LCO 3.2.1 Regulating Rod Insertion Limits

8. LCO 3.2.2 AXIAL POWER SHAPING ROD (APSR) Insertion Limits

9. LCO 3.2.3 AXIAL POWER IMBALANCE Operating Limits

10. LCO 3.2.4 QUADRANT POWER TILT (QPT)

11. LCO 3.2.5 Power Peaking Factors

12. LCO 3.3.1 Reactor Protection Systems (RPS) Instrumentation Function 8: (Flux - AFlux - Flow) Allowable Value

13. LCO 3.9.1 Boron Concentration

14. TRM 8.1.3 Rod Program 2.0 References

1) BAW-1 01 79P-A, Rev. 6, "Safety Criteria and Methodology for Acceptable Cycle Reload Analyses", August, 2001.

2) BAW-10164P-A, Rev. 6, "RELAP5/MOD2-B&W - An Advanced Computer Program for Light Water Reactor LOCA and Non-LOCA Transient Analysis",

June, 2007.

3) BAW-10243P-A, "Statistical Fuel Assembly Hold Down Methodology",

September, 2005.

Cycle 16 COLR Page 3 of 34 Revision 2 Table of Contents Page Reactor Core Safety Limits Figure 1 AXIAL POWER IMBALANCE Protective Limits 5 SHUTDOWN MARGIN (SDM)

Table 1 Shutdown Margin Requirements 6 Moderator Temperature Coefficient (MTC)

Table 2 Moderator Temperature Coefficient Limit 7 Position Indicator Channels Table 3 Absolute Position Indicator (API) / Relative Position Indicator (RPI)

Agreement Limit 8 Regulating Rod Insertion Limits Figure 2a Regulating Group Position Operating Limits - Four RC Pumps From 0 to 300 +/- 10 EFPD 9 Figure 2b Regulating Group Position Operating Limits - Four RC Pumps After 300 +/- 10 EFPD 10 Figure 2c Regulating Group Position Operating Limits - Three RC Pumps From 0 to 300 +/- 10 EFPD 11 Figure 2d Regulating Group Position Operating Limits - Three RC Pumps After 300 +/- 10 EFPD 12 AXIAL POWER SHAPING ROD (APSR) Insertion Limits Figure 3 APSR Position Operating Limits - 2817 MWt RTP 13 AXIAL POWER IMBALANCE Operating Limits Figure 4a AXIAL POWER IMBALANCE Operating Limits - Four RC Pumps From 0 to 350 +/- 10 EFPD 14 Figure 4b AXIAL POWER IMBALANCE Operating Limits - Four RC Pumps From 350 +/- 10 to 600 +/- 10 EFPD 15 Figure 4c AXIAL POWER IMBALANCE Operating Limits - Four RC Pumps After 600 +/- 10 EFPD 16 Figure 4d AXIAL POWER IMBALANCE Operating Limits - Three RC Pumps From 0 to 350 +/- 10 EFPD 17 Figure 4e AXIAL POWER IMBALANCE Operating Limits - Three RC Pumps From 350 +/- 10 to 600 +/- 10 EFPD 18 Figure 4f AXIAL POWER IMBALANCE Operating Limits - Three RC Pumps After 600 +/- 10 EFPD 19 QUADRANT POWER TILT (QPT)

Table 4 QUADRANT POWER TILT Limits -2817 MW 20

Cycle 16 COLR Page 4 of 34 Revision 2 Power Peaking Factors Table 5 Power Peaking Factors - Fa (NAS) 21 Table 6 Power Peaking Factors - FQ (FIDMS) 24 Table 7 Power Peaking Factors - FN AH 28 Figure 5 Maximum Allowable Radial Peak For FNAH in Mark-B Fuel Assemblies 28 Figure 6 Maximum Allowable Radial Peak For FNAH in Mark-B-HTP Fuel Assemblies 29 Table 8 Maximum Allowable Radial Peak For FNAH in Mark-B Fuel Assemblies 30 Table 9 Maximum Allowable Radial Peak For FN Hin Mark-B-HTP Fuel Assemblies 31 Reactor Protection System (RPS) Instrumentation Figure 7 Flux-AFlux-Flow (or Power/Imbalance/Flow) Allowable Values 32 Boron Concentration Table 10 Refueling Boron Concentration Limit 33 Rod Program Figure 8 Control Rod Core Locations and Group Assignments 34

Cycle 16 COLR Page 5 of 34 Revision 2 Figure 1 AXIAL POWER IMBALANCE Protective Limits 2817MWt RTP This Figure is referred to by Improved Technical Specification 2.1.1.1 120 -

(-38.66, 110.2) (37.09, 110.2)

/110-4 PUMP LIMIT

(-45.54, 100.0) 100 + (45.88, 100.0)

(-38.66, 90.70) (37.09, 90.70)

(-45.54, 80.50)

/ 80 4 3 PUMP LIMIT (45.88, 80.5) 70 +

UNACCEPTABLE E UNACCEPTABLE OPERATION a OPERATION 0~ 60 +

a.

w 50+

M I-40 + ACCEPTABLE 2 OPERATION FOR SPECIFIED 30 + RC PUMP COMBINATION 20 +

10+

-80 -70 -60 -50 -40 -30 -20 -10 0 10 20 30 40 50 60 70 80 AXIAL POWER IMBALANCE, %

Required Measured Reactor Coolant Flow to Ensure Pumps Operating Flow, gpm Compliance, gpm 4 380,000 389,500 3 283,860 290,957

Cycle 16 COLR Page 6 of 34 Revision 2 Table 1 Shutdown Margin Requirements Verify SHUTDOWN MARGIN per the table below.

IMPROVED TECHNICAL REQUIRED SHUTDOWN SPECIFICATIONS LCO APPLICABILITY MARGIN REFERENCE MODE 1* >1 %Ak/k 3.1.4, 3.1.5 MODE 2* 1%Ak/k 1> 3.1.4, 3.1.5, 3.3.9 MODE 3 >1 %Ak/k 3.1.1, 3.3.9 MODE 4 >1 %Ak/k 3.1.1, 3.3.9 MODE5 >1 %Ak/k 3.1.1, 3.3.9 MODE 1 PHYSICS TESTS 1 %Ak/k 3.1.8 Exceptions**

MODE 2 PHYSICS TESTS 1 %Ak/k 3.1.9 Exceptions

• The required Shutdown Margin capability of 1%Aklk in MODE 1 and MODE 2 is preserved by the Regulating Rod Insertion Limits specified in Figures 2a through 2d as required by Improved Technical Specification 3.2.1.

• • Entry into Mode 1 Physics Tests Exceptions is not supported by existing analyses (Regulating Rod Shutdown Margin Insertion Limits assumptions may not be met) and as such requires actual shutdown margin to be - 1 %Ak/k (via alternate verification or calculation).

Cycle 16 COLR Page 7 of 34 Revision 2 Table 2 Moderator Temperature Coefficient Limit These limits are referred to by Improved Technical Specifications 3.1.3

1. Lower Limit:

MTC at HFP > -3 .7 6 x10-4 Ak/k/°F

2. The following Upper Limits may not be exceeded without prior NRC approval:

MTC <0.9 x 10-4Ak/k/°F when Thermal Power <95% RTP MTC <0.0 x 10" Ak/k/°F when Thermal Power >95% RTP

3. The following Upper Limits may not be exceeded for operation in Modes 1 and 2:

I9:bEýb5"-

---

-------------- ......... I ------

8.0E--05 - - - - - ----- --- - --- - - -----

8.0EI-05 - - - - - - - - -- - - - - - - - - -- - - - - - - - - - - - -- - - - - - - - - - - - -- - - - - ----- -- - - - - - - - - -- - - - -

.2-0

• OE-05 - - - - -- - - - - - - - - - - - -- - - - - - -- - - - - - - - - - - -- - - - - - - - - - - -- - - - - - - --- - - - - - - - - -- - - - - - - - - - - - -- - - - - - I- - ---- - - -- - - - - - - - - -

0 5}0E-05.-

,0 77 7:-,% - - - - - - --- --- 7-7z, M)

Aý3 0E-05 -

- - - - - - - - - - - - - - - - - - - - - - - 7: - - - --- - - - -- - - ---- ----- --- - - - .-. 7 - - - - - -- - - - - - --- - - - ------ - - - ---- ----- . . . .... . . ....

3 0E-:05 -

1.OE-05ý.l -- - - - - - - - - - - -- - - - - - - - - - -- - - - - - - - - - -- -- - - - - - - --

0.0E-00,

ý.0 20 4A0 '60. MO:

~100 Pecent Ful Powe.r-

Cycle 16 COLR Page 8 of 34 Revision 2 Table 3 Absolute Position Indicator (API) / Relative Position Indicator (RPI)

A-greement Limit This limit is referred to by Improved Technical Specifications 3.1.7 The absolute position indicator channels and the relative position indicator channels agree within 3.46%.

Cycle 16 COLR Page 9 of 34 Revision 2 Figure 2a Regulating Group Position Operating Limits 0 to 300 +10 EFPD, Four RC Pumps--2817MWt RTP Davis-Besse 1, Cycle 16 This Figure is referred to by Improved Technical Specifications 3.2.1 110 100 90 w Unacceptable 0: Operation 0~ 80

-L Operation 70 Shutdown Restricted Margin 60 Limit 0

uj 50 (D

_I I II II I I 40 0

CL 30 SI PI 7, F MF 20 0 25 / 50 75 10 2 5 7 0 2 5 7 0 10 0

Rod Index, %Withdrawn 01 75 100 I

I 1 I Group 5 0 25 75 100 1 1 I I i I I Group 6 01 100 I

Group 7 Note 1: A Rod Group overlap of 25 +/- 5% between sequential withdrawn groups 5 and 6, and 6 and 7, shall be maintained.

Note 2: Instrument error is accounted for in these Operating Limits.

Cycle 16 COLR Page 10 of 34 Revision 2 Figure 2b Regulating Group Position Operating Limits After 300 +10 EFPD, Four RC Pumps--2817MWt RTP Davis-Besse 1, Cycle 16 This Figure is referred to by Improved Technical Specifications 3.2.1 110 100 90 Lu 013. 80 Unacceptable Operation

"-J 70 I--

0~ Operation 60 Restricted a) 50 Shutdown UJ Margin (L

0) Limit a-40 30 a) Acceptable if 03 Operation 20 10 0

0 25 50 75 100 125 150 175 200 225 250 275 300 Rod Index, %Withdrawn 0II 75 100I Group 5 0 25 75 100 I 1 I f I I r Group 6 01 100 I

Group 7 Note 1: A Rod Group overlap of 25 +5% between sequential withdrawn groups 5 and 6, and 6 and 7, shall be maintained.

Note 2: Instrument error is accounted for in these Operating Limits.

Cycle 16 COLR Page 11 of 34 Revision 2 Figure 2c Regulating Group Position Operating Limits 0 to 300 +10 EFPD, Three RC Pumps--2817 MWt RTP Davis-Besse 1, Cycle 16 This Figure is referred to by Improved Technical Specifications 3.2.1 110

÷H 100 I-90 w

0 80 LI O

70 +/- Unacceptable SOperation II 111 60

._1 Shutdown Operation 50 Margin 411 IIi*1:1::1:]:1 a) Limit 0

a. 40 0J 30 IIL 20 10 Ti -t- f-I-- -t t--

Operation Acceptable 1:#_

0 0 25 50 II75 IIIIIIII II!11111 100 1--

125 150 175 200 225 250 275 I

300 Rod Index, %Withdrawn 01 75 100 I

Group 5 0 25 75 100 1 1 I Group 6 01 25 100 I

Group 7 Note 1: A Rod Group overlap of 25 +/- 5% between sequential withdrawn groups 5 and 6, and 6 and 7, shall be maintained.

Note 2: Instrument error is accounted for in these Operating Limits.

Cycle 16 COLR Page 12 of 34 Revision 2 Figure 2d Regulating Group Position Operating Limits After 300 +10 EFPD, Three RC Pumps--2817MWt RTP Davis-Besse 1, Cycle 16 This Figure is referred to by Improved Technical Specifications 3.2.1 110 fH i'll'ii

tj 100 90 I I i I

3- 80

._j 0 70 i i i i i Jnacceptabl e 60 Operation T7 FI-50 OA'I I I I I Operation 0 Shutdown Restricted L0 Margin C-D 40 FýF Limit a(

0~ 30 0o RF 20 Acceptable -

Operation ,

10 0 I 0 25 50 75 100 125 150 175 200 225

-Hi i H i i i 250 275 300 Rod Index, %Withdrawn 01 75 100 I

Group 5 0 25 75 100 1 1 I Group 6 01 25 100 I

Group 7 Note 1: A Rod Group overlap of 25 +5% between sequential withdrawn groups 5 and 6, and 6 and 7, shall be maintained.

Note 2: Instrument error is accounted for in these Operating Limits.

Cycle 16 COLR Page 13 of 34 Revision 2 Figure 3 APSR Position Operating Limits- 2817 MWt RTP This Figure is referred to by Improved Technical Specifications 3.2.2 Before APSR Pull: 0 EFPD to 675 +/- 10 EFPD, Three or Four RC pumps operation Lower Limit: 0 %WD Upper Limit: 100 %WD After APSR Pull: 675 +/- 10 EFPD to End-of-Cycle Three or Four RC pumps operation Insertion Prohibited (maintain > 99%WD)

• Power restricted to 75.37% for 3-pump operation.

Cycle 16 COLR Page 14 of 34 Revision 2 Figure 4a AXIAL POWER IMBALANCE Operating Limits 0 to 350 +10 EFPD, Four RC Pumps--2817 MWt RTP Davis-Besse 1, Cycle 16 This Figure is referred to by Improved Technical Specification 3.2.3

-60 -50 -40 -30 -20 -10 0 10 20 30 40 50 60 AXIAL POWER IMBALANCE % LEGEND FULL INCORE Note 1: Instrument error is accounted for in these Operating Limits.

EXCORE

Cycle 16 COLR Page 15 of 34 Revision 2 Figure 4b AXIAL POWER IMBALANCE Operating Limits 350 +10 to 600 +10 EFPD, Four RC Pumps--2817MWt RTP Davis-Besse 1, Cycle 16 This Figure is referred to by Improved Technical Specification 3.2.3

-50 -40 -30 -20 -10 0 10 20 30 40 50 AXIAL POWER IMBALANCE % LEGEND Note 1: Instrument error is accounted for in these Operating Limits. FULL INCORE EXCORE Cycle 16 COLR Page 16 of 34 Revision 2 Figure 4c AXIAL POWER IMBALANCE Operating Limits After 600 +10 EFPD, Four RC Pumps--2817MWt RTP Davis-Besse 1, Cycle 16 This Figure is referred to by Improved Technical Specification 3.2.3

-50 -40 -30 -20 -10 0 10 20 30 40 50 AXIAL POWER IMBALANCE % LEGEND Note 1: Instrument error is accounted for in these Operating Limits. FULL INCORE EXCORE p

Cycle 16 COLR Page 17 of 34 Revision 2 Figure 4d AXIAL POWER IMBALANCE Operating Limits 0 to 350 +10 EFPD, Three RC Pumps--2817 MWt RTP Davis-Besse 1, Cycle 16 This Figure is referred to by Improved Technical Specification 3.2.3

-60 -50 -40 -30 -20 -10 0 10 20 30 40 50 60 AXIAL POWER IMBALANCE % LEGEND Note 1: Instrument error is accounted for in these Operating Limits. FULL INCORE EXCORE Cycle 16 COLR Page 18 of 34 Revision 2 Figure 4e AXIAL POWER IMBALANCE Operating Limits 350 +10 to 600 +10 EFPD, Three RC Pumps--2817MWt RTP Davis-Besse 1, Cycle 16 This Figure is referred to by Improved Technical Specification 3.2.3

-50 -40 -30 -20 -10 0 10 20 30 40 50 AXIAL POWER IMBALANCE % LEGEND Note 1: Instrument error is accounted for in these Operating Limits. FULL INCORE EXCORE

Cycle 16 COLR Page 19 of 34 Revision 2 Figure 4f AXIAL POWER IMBALANCE Operating Limits After 600 +10 EFPD, Three RC Pumps--2817MWt RTP Davis-Besse 1, Cycle 16 This Figure is referred to by Improved Technical Specification 3.2.3

-50 -40 -30 -20 -10 0 10 20 30 40 50 AXIAL POWER IMBALANCE % LEGEND Note 1: Instrument error is accounted for in these Operating Limits. FULL INCORE EXCORE

Cycle 16 COLR Page 20 of 34 Revision 2 Table 4 QUADRANT POWER TILT Limits - 2817 MWt This Table is referred to by Improved Technical Specifications 3.2.4 From 0 EFPD to EOC-16 Steady-state Limit Steady-state Limit QUADRANT for THERMAL for THERMAL POWER TILT as POWER < 60% POWER >60% Transient Limit Maximum Limit measured by: (%) (%) (%) (%)

Symmetric Incore 7.90 4.25 10.03 20.00 Detector System

Cycle 16 COLR Page 21 of 34 Revision 2 Table 5 Power Peakina Factors - Fo (NAS)

This Table is referred to by Improved Technical Specifications 3.2.5 The measured FQ shall be increased by 1.4% to account for manufacturing tolerances and further increased by 7.5% to account for measurement uncertainty before comparing to the limits.

Heat Flux Hot Channel Factor F,* 2817 MWt RTP FQ shall be limited by the following relationships:

Fa - LHRalow (Bu) / [LHRavg

• P] (for P 5 1.0)

LHRalow (Bu) = See the following tables LHRavg = 6.4119 kW/ft at 2817 MWt for Batch 9K Mark-B8A fuel LHR vg = 6.4209 kW/ft at 2817 MWt for Batches 15C3 and 15E Mark-B10K fuel LHRavg = 6.4209 kW/ft at 2817 MWt for Batches 16C2, 16D2 and 16E2 Mark-B12 fuel LHRavg = 6.4321 kW/ft at 2817 MWt for Batch 17A-E Mark-B-HTP fuel LHRavg = 6.4209 kW/ft at 2817 MWt for Batch 18A-C Mark-B-HTP fuel P = ratio of THERMAL POWER / RATED THERMAL POWER Bu = fuel burnup (MWd/mtU)

Batch 9K U02 Fuel (Mark-B8A) LHRALLOw kW/ftL 0 24,500 52,000 60,000 Axial Secqment MWd/mtU MWd/mtU MWd/mtU MWd/mtU 1 16.1 16.1 12.0 10.2 2 15.8 15.8 12.0 10.2 3 15.0 15.0 12.0 10.2 4 15.0 15.0 12.0 10.2 5 15.4 15.4 12.0 10.2 6 15.4 15.4 12.0 10.2 7 14.6 14.6 12.0 10.2 8 14.3 14.3 12.0 10.2 (a) Linear interpolation for allowable LHR between specified burnup points is valid for these tables.

Cycle 16 COLR Page 22 of 34 Revision 2 Table 5 (continued)

)ALLO Batch 15C3 and 15E U02 Fuel (Mark-B1OK) LHRA. kW/ft 0 35,000 58,000 59,000 60,000 62,000 Axial Segment MWd/mtU MWd/mtU MWd/mtU MWd/mtU MWd/mtU MWd/mtU 1 17.6 16.8 14.7 14.4 14.1 13.5 2 17.5 16.7 14.7 14.4 14.1 13.5 3 17.0 15.6 14.6 14.4 14.1 13.5 4 16.6 15.3 14.4 14.4 14.1 13.5 5 16.0 15.3 14.2 14.1 14.1 13.5 6 15.3 15.3 13.7 13.7 13.6 13.5 7 14.7 14.7 13.2 13.1 13.1 13.0 8 14.5 14.5 13.0 12.9 12.9 12.8 Batch 16C2, 16D2, and 16E2 U02 Fuel (Mark-B12) LHRALLL kW/ftf 0 35,000 58,000 59,000 60,000 62,000 Axial Segment MWd/mtU MWd/mtU MWd/mtU MWd/mtU MWd/mtU MWd/mtU 1 17.6 16.8 14.7 14.4 14.1 13.5 2 17.5 16.7 14.7 14.4 14.1 13.5 3 17.0 15.6 14.6 14.4 14.1 13.5 4 16.6 15.3 14.4 14.4 14.1 13.5 5 16.0 15.3 14.2 14.1 14.1 13.5 6 15.3 15.3 13.7 13.7 13.6 13.5 7 14.7 14.7 13.2 13.1 13.1 13.0 8 14.5 14.5 13.0 12.9 12.9 12.8 Batch 17A-17E U02 Fuel (Mark-B-HTP) LHRALLOw kW/fta 0 40,000 62,000 Axial Segment MWd/mtU MWd/mtU MWd/mtU 1 17.6 17.2 13.6 2 17.5 17.1 13.5 3 17.1 16.7 13.2 4 17.0 16.7 13.2 5 16.5 16.2 13.1 6 15.9 16.0 13.1 7 15.3 15.4 12.8 8 15.1 15.2 12.6 (a) Linear interpolation for allowable LHR between specified burnup points is valid for these tables

Cycle 16 COLR Page 23 of 34 Revision 2 Table 5 (continued)

Batch 18A-18C U02 Fuel (Mark-B-HTP) LHROLLow kW/ftL 0 40,000 62,000 Axial Segment MWd/mtU MWd/mtU MWd/mtU 1 17.6 17.2 13.6 2 17.5 17.1 13.5 3 17.1 16.7 13.2 4 17.0 16.7 13.2 5 16.5 16.2 13.1 6 15.9 16.0 13.1 7 15.3 15.4 12.8 8 15.1 15.2 12.6 (a) Linear interpolation for allowable LHR between specified burnup points is valid for these tables

Cycle 16 COLR Page 24 of 34 Revision 2 Table 6 Power Peaking Factors - Fo (FIDMS)

This Table is referred to by Improved Technical Specifications 3.2.5 The measured Fa shall be increased by 1.4% to account for manufacturing tolerances and further increased by 7.5% to account for measurement uncertainty before comparing to the limits.

Heat Flux Hot Channel Factor F_ 2817 MWt RTP FQ shall be limited by the following relationships:

F.5 LHRallow (Bu) / [LHRavg

• P] (for P < 1.0)

LHRallow (Bu) = See the following tables LHRavg = 6.4119 kW/ft at 2817 MWt for Batch 9K Mark-B8A fuel LHR vg = 6.4209 kW/ft at 2817 MWt for Batches 15C3 and 15E Mark-B10K fuel LHRavg = 6.4209 kW/ft at 2817 MWt for Batches 16C2, 16D2 and 16E2 Mark-B12 fuel LHR vg = 6.4321 kW/ft at 2817 MWt for Batch 17A-E Mark-B-HTP fuel LHRavg = 6.4209 kW/ft at 2817 MWt for Batch 18A-C Mark-B-HTP fuel P = ratio of THERMAL POWER / RATED THERMAL POWER Bu = fuel burnup (MWd/mtU)

Batch 9K - U02 Fuel LHRALLOw kW/ft*

Core Elevation 24,500 52,000 60,000 (ft) 0 MWd/mtU MWd/mtU MWd/mtU MWd/mtU 0.000 16.3 16.3 12.0 10.2 2.506 15.9 15.9 12.0 10.2 4.264 15.1 15.1 12.0 10.2 6.021 15.5 15.5 12.0 10.2 7.779 16.0 16.0 12.0 10.2 9.536 15.4 15.4 12.0 10.2 12.000 14.3 14.3 12.0 10.2 Linear interpolation for allowable LHR between specified burnup points is valid for these tables

Cycle 16 COLR Page 25 of 34 Revision 2 Table 6 (continued)

Batches 15C3 and 15E - U02 Fuel LHR ALLw kW/ft*

Core 35,000 58,000 59,000 60,000 62,000 Elevation (ft) 0 MWd/mtU MWd/mtU MWd/mtU MWd/mtU MWd/mtU MWd/mtU 0.000 17.6 16.8 14.7 14.4 14.1 13.5 2.506 17.6 16.8 14.7 14.4 14.1 13.5 4.264 17.1 15.7 14.7 14.4 14.1 13.5 6.021 16.6 15.3 14.4 14.4 14.1 13.5 7.779 16.0 15.8 14.2 14.1 14.1 13.5 9.536 15.3 15.3 13.7 13.7 13.6 13.5 12.000 14.5 14.5 13.0 12.9 12.9 12.8 Linear interpolation for allowable LHR between specified burnup points is valid for these tables.

Batch 16C2, 16D2, and 16E2 - U02 Fuel LHRALLOw kW/ft*

Core 35,000 58,000 59,000 60,000 62,000 Elevation (ft) 0 MWd/mtU MWd/mtU MWd/mtU MWd/mtU MWd/mtU MWd/mtU 0.000 17.6 16.8 14.7 14.4 14.1 13.5 2.506 17.6 16.8 14.7 14.4 14.1 13.5 4.264 17.1 15.7 14.7 14.4 14.1 13.5 6.021 16.6 15.3 14.4 14.4 14.1 13.5 7.779 16.0 15.8 14.2 14.1 14.1 13.5 9.536 15.3 15.3 13.7 13.7 13.6 13.5 12.000 14.5 14.5 13.0 12.9 12.9 12.8 Linear interpolation for allowable LHR between specified burnup points is valid for these tables.

Batch 17A-E - U02 Fuel LHRALLow kW/ft*

Core Elevation (ft) 0 MWd/mtU 40,000 MWd/mtU 62,000 MWd/mtU 0.000 17.6 17.2 13.6 2.506 17.6 17.2 13.6 4.264 17.2 16.8 13.3 6.021 17.0 16.7 13.2 7.779 16.5 16.2 13.1 9.536 15.9 16.0 13.3 12.000 15.1 15.2 12.6 Linear interpolation for allowable LHR between specified burnup points is valid for these tables.

Batch 18A-C - U02 Fuel LHRALLOw kW/ft*

Core Elevation (ft) 0 MWd/mtU 40,000 MWd/mtU 62,000 MWd/mtU 0.000 17.6 17.2 13.6 2.506 17.6 17.2 13.6 4.264 17.2 16.8 13.3 6.021 17.0 16.7 13.2 7.779 16.5 16.2 13.1 9.536 15.9 16.0 13.3 12.000 15.1 15.2 12.6 Linear interpolation for allowable LHR between specified burnup points is valid for these tables.

Cycle 16 COLR Page 26 of 34 Revision 2 Table 6 (continued)

Batch 15 - 2 wt% Gadolinia Fuel LHRALLw kW/ft*

Core 35,000 58,000 59,000 60,000 62,000 Elevation (ft) 0 MWd/mtU MWd/mtU MWd/mtU MWd/mtU MWd/mtU MWd/mtU 0.000 16.5 15.7 13.9 13.6 13.3 12.8 2.506 16.5 15.7 13.9 13.6 13.3 12.8 4.264 16.0 14.7 13.9 13.6 13.3 12.8 6.021 15.5 14.3 13.6 13.6 13.3 12.8 7.779 15.0 14.8 13.4 13.3 13.3 12.8 9.536 14.3 14.3 13.0 12.9 12.9 12.8 12.000 13.6 13.6 12.4 12.3 12.3 12.2 Linear interpolation for allowable LHR between specified burnup points is valid for these tables.

Batch 16 - 4 wt% Gadolinia Fuel LHR ALLw kW/ft*

Core 35,000 58,000 59,000 60,000 62,000 Elevation (ft) 0 MWd/mtU MWd/mtU MWd/mtU MWd/mtU MWd/mtU MWd/mtU 0.000 15.8 15.1 13.3 13.0 12.7 12.2 2.506 15.8 15.1 13.3 13.0 12.7 12.2 4.264 15.3 14.1 13.3 13.0 12.7 12.2 6.021 14.9 13.7 13.0 13.0 12.7 12.2 7.779 14.3 14.2 12.9 12.8 12.8 12.2 9.536 13.7 13.7 12.4 12.3 12.3 12.2 12.000 13.0 13.0 11.8 11.7 11.7 11.6 Linear interpolation for allowable LHR between specified burnup points is valid for these tables.

Batches 15 and 16 - 8 wt% Gadolinia Fuel LHRALLOw kW/ft*

Core 35,000 58,000 59,000 60,000 62,000 Elevation (ft) 0 MWd/mtU MWd/mtU MWd/mtU MWd/mtU MWd/mtU MWd/mtU 0.000 14.9 14.2 12.4 12.1 11.9 11.4 2.506 14.9 14.2 12.4 12.1 11.9 11.4 4.264 14.5 13.3 12.4 12.1 11.9 11.4 6.021 14.0 12.9 12.2 12.2 11.9 11.4 7.779 13.5 13.4 12.0 11.9 11.9 11.4 9.536 12.9 12.9 11.6 11.5 11.5 11.4 12.000 12.2 12.2 11.0 10.9 10.9 10.8 Linear interpolation for allowable LHR between specified burnup points is valid for these tables.

Batches 17 and 18 - 4 wt% Gadolinia Fuel LHRALLw kW/ft*

Core Elevation (ft) 0 MWd/mtU 40,000 MWd/mtU 62,000 MWd/mtU 0.000 15.8 15.7 12.3 2.506 15.8 15.7 12.3 4.264 15.4 15.2 12.0 6.021 15.2 15.1 11.9 7.779 14.8 14.7 11.8 9.536 14.3 14.5 12.0 12.000 13.6 13.8 11.4 Linear interpolation for allowable LHR between specified burnup points is valid for these tables.

Cycle 16 COLR Page 27 of 34 Revision 2 Table 6 (continued)

Batches 17 and 18- 8 wt% Gadolinia Fuel LHRALLOw kW/ft*

Core Elevation (ft) 0 MWd/mtU 40,000 MWd/mtU 62,000 MWd/mtU 0.000 14.9 14.9 11.5 2.506 14.9 14.9 11.5 4.264 14.5 14.6 11.2 6.021 14.4 14.5 11.1 7.779 13.9 14.0 11.0 9.536 13.4 13.9 11.2 12.000 12.7 13.2 10.6 Linear interpolation for allowable LHR between specified burnup points is valid for these tables.

Cycle 16 COLR Page 28 of 34 Revision 2 Table 7 Power Peakinq Factors - FNAH This Table is referred to by Improved Technical Specifications 3.2.5 Enthaloy Rise Hot Channel Factors - F-AH FNH 5 MARP [1 + (1/RH) (1 - P/Pm)] (see note below)

MARP = Maximum Allowable Radial Peak, see MARP Figures and data Tables P = THERMAL POWER / RATED THERMAL POWER and P < 1.0 Pm = 1.0 for 4-RCP operation Pm = 0.75 for 3-RCP operation 1/RH = 0.3 Note: The measured FNAH shall be increased by 5.0% to account for measurement uncertainty prior to comparing to the limits.

Figure 5 Maximum Allowable Radial Peak for FNAH in Mark-B Fuel Assemblies

• 2.1 2.0 1.9 1.8 1.7 1.6 1.5 1.4 1.1 1.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9 Axial Peak

• This figure is applicable to all Mark-B fuel in the core. Linear interpolation and extrapolation above x/L of 0.8 are acceptable. For axial heights < x/L of 0.2, the value at x/L of 0.2 will be used.

Cycle 16 COLR Page 29 of 34 Revision 2 Figure 6 Maximum Allowable Radial Peak for FNAH in Mark-B-HTP Fuel Assemblies

• 2.1

• 2.0 1.9

• 1.8 4! 1.7

. 1.6 1.5 S1.4 1.3 1.1 1.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9 Axial Peak

• This figure is applicable to all Mark-B-HTP fuel in the core. Linear interpolation is acceptable.

The MARP values are based on an active fuel height of 142.75 inches.

Cycle 16 COLR Page 30 of 34 Revision 2 Table 8 Maximum Allowable Radial Peak for FNA^ in Mark-B Fuel Assemblies Axial Peak x/L Axial Heiqht (inches) MAP Limit MARP Limit 0.2 28.12 2.0415 1.9264 0.4 56.24 2.0345 1.9198 1.1 0.6 84.36 2.0221 1.9081 0.8 112.48 1.9934 1.8810 0.2 28.12 2.2918 1.9824 0.4 56.24 2.2749 1.9678 1.2 0.6 84.36 2.2470 1.9437 0.8 112.48 2.1601 1.8685 0.2 28.12 2.5521 2.0378 0.4 56.24 2.5197 2.0119 1.3 0.6 84.36 2.4387 1.9472 0.8 112.48 2.2719 1.8140 0.2 28.12 3.0022 2.0775 0.4 56.24 2.8272 1.9564 1.5 0.6 84.36 2.6367 1.8246 0.8 112.48 2.4553 1.6991 0.2 28.12 3.1839 1.9441 0.4 56.24 2.9911 1.8263 1.7 0.6 84.36 2.7902 1.7037 0.8 112.48 2.6084 1.5927 0.2 28.12 3.2865 1.7955 0.4 56.24 3.0945 1.6906 1.9 0.6 84.36 2.9062 1.5877 0.8 112.48 2.7279 1.4903

Cycle 16 COLR Page 31 of 34 Revision 2 1

Table 9 Maximum Allowable Radial Peak for FOAH in Mark-B-HTP Fuel Assemblies Axial Axial Axial Height MARP Axial Height MARP Peak x/L (inches) MAP Limit Limit Peak xIL (inches) MAP Limit Limit 0.0 0.000 2.03286 1.91828 0.0 0.000 2.79510 1.81332 0.1 14.275 2.03375 1.91912 0.1 14.275 2.66285 1.72752 0.14 19.985 2.03379 1.91916 0.14 19.985 2.63106 1.70690 0.2 28.550 2.03355 1.91893 0.2 28.550 2.69787 1.75024 0.4 57.100 2.03179 1.91727 0.4 57.100 2.75779 1.78912 1.1 0.5 71.375 2.03107 1.91659 1.6 0.5 71.375 2.79658 1.81428 0.6 85.650 2.03099 1.91652 0.6 85.650 2.71189 1.75934 0.8 114.200 2.03178 1.91726 0.8 114.200 2.46394 1.59848 0.88 125.620 1.98623 1.87428 0.88 125.620 2.36299 .1.53299 0.9 128.475 1.98774 1.87570 0.9 128.475 2.37234 1.53906 1.0 142.750 1.86518 1.76005 1.0 142.750 2.21845 1.43922 0.0 0.000 2.33414 2.01903 0.0 0.000 2.81571 1.71924 0.1 14.275 2.33416 2.01905 0.1 14.275 2.66718 1.62855 0.14 19.985 2.33413 2.01902 0.14 19.985 2.63022 1.60598 0.2 28.550 2.33248 2.01760 0.2 28.550 2.691 95 1.64367 0.4 57.100 2.33024 2.01566 0.4 57.100 2.76735 1.68971 1.2 0.5 71.375 2.32955 2.01506 1.7 0.5 71.375 2.80468 1.71250 0.6 85.650 2.32916 2.01472 0.6 85.650 2.77165 1.69234 0.8 114.200 2.15618 1.86510 0.8 114.200 2.52074 1.53913 0.88 125.620 2.07666 1.79631 0.88 125.620 2.42051 1.47793 0.9 128.475 2.07869 1.79807 0.9 128.475 2.43041 1.48398 1.0 142.750 1.95649 1.69236 1.0 142.750 2.27373 1.38831 0.0 0.000 2.66591 2.12863 0.0 0.000 2.83401 1.63428 0.1 14.275 2.64485 2.11181 0.1 14.275 2.66992 1.53965 0.14 19.985 2.62777 2.09817 0.14 19.985 2.62789 1.51542 0.2 28.550 2.66761 2.12998 0.2 28.550 2.68772 1.54992 0.4 57.100 2.65903 2.12313 0.4 57.100 2.7774 1.60163 1.3 0.5 71.375 2.58224 2.06182 1.8 0.5 71.375 2.80694 1.61867 0.6 85.650 2.46978 1.97202 0.6 85.650 2.82218 1.62746 0.8 114.200 2.24712 1.79424 0.8 114.200 2.57398 1.48433 0.88 125.620 2.15963 1.72438 0.88 125.620 2.47403 1.42669 0.9 128.475 2.16184 1.72615 0.9 128.475 2.48254 1.43160 1.0 142.750 2.02976 1.62069 1.0 142.750 2.32589 1.34126 0.0 0.000 2.74599 2.03596 0.0 0.000 2.85122 1.55767 0.1 14.275 2.65413 1.96785 0.1 14.275 2.67423 1.46097 0.14 19.985 2.63176 1.95126 0.14 19.985 2.62778 1.43560 0.2 28.550 2.69213 1.99602 0.2 28.550 2.68609 1.46745 0.4 57.100 2.74771 2.03723 0.4 57.100 2.78418 1.52104 1.4 0.5 71.375 2.68391 1.98993 1.9 0.5 71.375 2.80567 1.53278 0.6 85.650 2.56032 1.89829 0.6 85.650 2.83113 1.54669 0.8 114.200 2.33307 1.72980 0.8 114.200 2.62225 1.43258 0.88 125.620 2.23716 1.65869 0.88 125.620 2.52166 1.37762 0.9 128.475 2.24237 1.66256 0.9 128.475 2.53147 1.38298 1.0 142.750 2.09699 1.55477 1.0 142.750 2.37605 1.29807 0.0 0.000 2.77184 1.91811 0.1 14.275 2.66225 1.84228 0.14 19.985 2.63504 1.82345 0.2 28.550 2.69706 1.86637 0.4 57.100 2.75139 1.90396 1.5 0.5 71.375 2.75241 1.90467 0.6 85.650 2.64282 1.82883 0.8 114.200 2.39919 1.66024 0.88 125.620 2.30027 1.59179 0.9 128.475 2.30907 1.59788 1.0 142.750 2.15988 1.49464

Cycle 16 COLR Page 32 of 34 Revision 2 Figure 7 Flux-AFlux-Flow (Power/Imbalance/Flow)

Allowable Values This Figure is referred to by Improved Technical Specifications 3.3.1

% RATED THERMAL POWER UNACCEPTABLE UNACCEPTABLE OPERATION OPERATION 120 Curve shows trip

(-17.( 0,108.0) (17.0,108.0)*

setpoint for an approximately MI=+1.00. 25% flow reduc-

,tion for three pump operation

(-30.6,94.4) (283,860 gpm).

The actual set-point will be

(-17.( calculated by the (30.6,77.1) Reactor Protection System and will be

(-30.6,67.0) directly propor-tional to the I I "60 actual flow with three numns.

IACCEPTABLE OPERATION FOR ISPECIFIED RC PUMP (30.6,49.7)

COMBINATION 4

I I 40 I I -20 I I I I I.

6 1. II

-80 -60 -40 -20 0 - 20 40 60 80 AXIAL POWER IMBALANCE,  %

Cycle 16 COLR Page 33 of 34 Revision'2 Table 10 Refuelina Boron Concentration Limit This limit is referred to by Improved Technical Specifications 3.9.1 The minimum required boron concentration for use during refueling shall be sufficient to ensure: a Keff of 0.95 or less, plus an additional 1% Ak/k conservatism allowance for uncertainties.

Cycle 16 COLR Page 34 of 34 Revision 2 Figure 8 Control Rod Core Locations and Group Assignments Davis-Besse 1, Cycle 16 This Figure is referred to by Technical Requirements Manual 8.1.3 1 N (X)

(W) (Y)

LjX-jGroup Number (Z)

Grou2 No of Rods Function Grouw No of Rods Function 1 4 Safety 5 12 Control 2 8 Safety 6 8 Control 3 4 Safety 7 8 Control 4 9 Safety 8 8 APSR Total 61

Enclosure B L-08-317 FirstEnergy Nuclear Operating Company, Davis-Besse Unit 1, 21 Effective Full Power Years Pressure and Temperature Limits Report, Revision 0 (7 Pages)

21 EFPY PTLR Page 1 of 7 Revision 0 FIRSTENERGY NUCLEAR OPERATING COMPANY DAVIS-BESSE UNIT 1 21 EFFECTIVE FULL POWER YEARS PRESSURE AND TEMPERATURE LIMITS REPORT Prepared by: Jessica Kemp Reviewed by: Dennis Blakely Approved by: Kevin Zellers 1,*-L

21 EFPY PTLR Page 2 of 7 Revision 0 FirstEnergy Nuclear Operating Company Davis-Besse Unit 1 21 Effective Full Power Year Pressure and temperature Limit Report 1.0 Introduction This Pressure and Temperature Limit Report (PTLR) provides the information required by Davis-Besse Nuclear Power Station (DBNPS) Technical Specification 5.6.4 to ensure that the Reactor Coolant System Pressure Boundary is operated in accordance with its design.

The PTLR provides the RCS Operating Limits in Section 2.0, which satisfy Technical Specification 5.6.4.a. The Analytical Methods used to develop the limits, including determination of the vessel neutron fluence, are provided in Section 3.0, fulfilling Technical Specification 5.6.4.b. The PTLR Requirements are provided in Section 4.0 of the report, fulfilling Technical Specification 5.6.4.c.

Revisions to the PTLR are to be submitted to the NRC after issuance.

2.0 RCS Pressure and Temperature Limits

a. The Reactor Coolant System (except the pressurizer) temperature and pressure shall be limited in accordance with the limit lines shown on Figures 1, 2 and 3 during heatup, cooldown, criticality and inservice leak, and hydrostatic testing with (Reference 1):

1. A maximum heatup of 50OF in any one hour period, and

2. A maximum cooldown of 100cF in any one hour period with a cold leg temperature of_> 270OF and a maximum cooldown of 50'F in any one hour period with a cold leg temperature of < 270 0F.

b. During periods of low temperature operation (Tavg <280 °F), Technical Specification 3.4.12 provides additional requirements for RCS pressure and temperature limits. Those limits are maintained in the Technical Specifications because they are not determined using methods generically approved by the NRC.

21 EFPY PTLR Page 3 of 7 Revision 0 Figure 1 Reactor Coolant System Pressure-Temperature Limits for Heatup and Core Criticality for the First 21 EFPY 2600. I. I .

2400 Notes: . . . . .

2200 Fbr (Ramp). ,imted by atS Fstep ,h',ge Is6ohold., L sA 18rate 1.Alowablebyheatup - -

~~~flelowed minute 2000 2000 2.When decay heat system (DH) Is operating without RC pump operllng, Indicated OH return C"1800 temperature to the reactor vassel shall be used. a no m . .. Ct

3. The acceptable pressure and temperature combinations am below and to the right of the  ; Crtical

'1600 " r..a j

1.. rs*ment ,,r Isnot asocunted !or Inthese ,mt.

~2 1400 - - - - . - a S1000 85 327 C 115 330 800 -_0 178 477 F E 230 477 600 1 t-i, F 238 810--_

G 280 1211

- 400 E,. 345 2500

.. A.. J C' '  ; I 339 0 200 A a J 339 1130 a a 1K 402 2500 050l 1100 I150 2 200 25 250 3 300 3 350 400 450 Indicated Reactor Coolant Inlet Temperature, F

21 EFPY PTLR Page 4 of 7 Revision 0 Figure 2 Reactor Coolant System Pressure-Temperature Limits for Cooldown for the First 21 EFPY 2600 2400 I. Allowable coo*down rate above 270 F Is 100 F/hr (Ramp), limited by ......... ........ ........ ........ ... ". .......

a 15 F atep change followed by an g minute hold.

2200

2. Allowable cooldown rate below 270 F Is50 F/hr (Ramp), limited by a IS F atep change followed by an 18 mlnute hold.

2000

3. A msximum step ,emperature change of 15 F Is allowablo when removing: "1"nt mp Press bO 1800 al RC pumps from operation wilh the DHR system operaling. The step I.... . ... ..............

temperature change Is def-ned as AC temp minus the R reAu70.156 ..

to the reactoroantsystemprorto stopping n pumps. A/8 120 108

"".... ..... 308 -- ...... :.. . .

1600

4. When the decay heat removal system (DH) Is operating wilhout any , C 170 477 1400 RO pumps operatg. Indcated DH return temperature to the ...... ........ .*. D 195 477 ..............

reacor vessel shall be used. .,

E 198 640 1200 S. The acceptable pressure and temperature combinations .. . F

.................... 270 3 1419 below and to Ow tight of the limit curve. G 315 2219 4.1 S4.05.232 .H.405-2326 c,. 1000 6. Instrument error Is not accounted for In these Omits. 483 2500 800 4-................I4....)-4.........4 .....4 ..... ..................

250 I I 48 D ...... ............ *......... +...... .. +.........T'

+.........;.........+......... ,*.................... ........t. ..

600 400 . ..... ...........

111... ...-.

.. .. ................. .D'

' I,

.** t I

200 A i I I ,I I  :

0 5'0 100 150 200 250 300 350 400 450 500 Indicated Reactor Coolant Inlet Temperature, F

21 EFPY PTLR Page 5 of 7.

Revision 0 Figure 3 Reactor Coolant System Pressure-Temperature Heatup.and Cooldown Limits for Inservice Leak and Hydrostatic Tests

. for the First 21 EFPY U*nn I Notes:

1 2400 1. Allowable hoetup rate Is 50 F/hr (Ramp). Ulmitod by a 15 F stop change

• 4 4 4 4 followed by an IS minute hold.

• 4 4 4 I

2200

• I I I

2. Allowable cooldown rate above 270 F Is 100 F/hr (Ramp), limited by

• 1 1 *

• S 4 4 a IS F stop change followed by an g minute hold.

2000-1800

3. Allowable cooldown rate below 270 F Is 50 Fhr (Ramp). limIted by a 15 F step change followed by an 18 minute hold.

Ia-i..~-'i 4~-.4.--.~ ~

I 4~

0 1600

4. A maximum step temperature change of 15 F Is allowable when removIn*

all RC pumps from operation with the DHR system operating. The step T . .

)/ . ~1~

temperature change Is defined as RO tamp minus the DHR return temp, Point Temp o Press 1400 -- *" the reactor coolant system priot to stopping all R0 pumps. '.

A 70 254 O 5. When the decay heal removal system (DH) Is operaming without any , B 90 364 1200 RO pumps operating. Indlcated.DH return temperature to the i ii~

I i

I 125 477 O

U I- 1000 reactor vessel shall be used.

6. The acceptable pressure and temperature combinations an

! C D

E 205 215 477 935  :

00 i below and to the right of the limIt curve. F 250 1242 800  : r "

G U

4) 600

7. Instrument error Is not accounted for In these Ilmits.

m  !

/ 1 318 2500

_ * ...  : , i I

400 A  : ( i  ::  :  :: i 200 .. , , ., , .

0 50 100 150 200 250 300 350 400 Indicated Reactor Coolant Inlet Temperature, F

21 EFPY PTLR Page 6 of 7 Revision 0 3.0 Analytical Methods 3.1 The limits provided in Figures 1, 2, and 3 are valid until the Reactor Vessel has accumulated 21 Effective Full Power Years (EFPY) of fast (E> 1 MeV) neutron fluence.

3.2 The Pressure-Temperature (P/T) Limits were generated using the methods described in BAW-10046A (Reference 4).

3.3 The P/T limits contained in the PTLR (applicable through 21 Effective Full Power Years (EFPY)) were generated in accordance with the methods described in BAW-10046A (Reference 4), consistent with the requirements of 10 CFR 50 Appendix G, and Regulatory Guide 1.99, Revision 2. The NRC has reviewed the methods described in BAW-10046A (Reference 4) and approved the topical report by issuance of a Safety Evaluation Report (SER) dated April 30, 1986. Section 1.2 of BAW-1 0046A states that it is applicable to all current B&W nuclear steam systems.

3.4 The neutron fluence is calculated using the methodology described in BAW-2108 (Reference 5). This methodology was approved by the NRC in the SER of Amendment 199 (Reference 1).

3.5 The Davis-Besse Reactor Vessel Material Surveillance Program complies with the requirements of Appendix H to 10 CFR 50 and is described in BAW-1 543A (Reference 6). This information was approved by the NRC in the SER of Amendment 199 (Reference 1).

3.6 The PORV (valve RC-2A) is not currently used for Low Temperature Overpressure Protection (LTOP), thus not required in ITS 3.4.12, "Low Temperature Overpressure Protection (LTOP)." Therefore, the PTLR does not include any PORV lift setting requirements.

3.7 Davis-Besse calculates Adjusted Reference Temperature (ART) in accordance with Regulatory Guide 1.99, Revision 2. This information was approved by the NRC in the SER of Amendment 199 (Reference 1).

3.8 The NRC has previously determined that the current limiting ART calculation complies with the NUREG-0800, Standard Review Plan 5.3.2, as documented in the SER of Amendment 199 (Reference 1). This is not meant to infer a commitment to NUREG-0800 by DBNPS.

3.9 The NRC has previously determined that the Davis-Besse P/T limit curves comply with 10 CFR 50 Appendix G as documented in the SER of Amendment 199 (Reference 1).

21 EFPY PTLR Page 7 of 7 Revision 0 3.10 Davis-Besse has not tested any plant-specific capsules since the last time P/T limit curves were adjusted and approved by the NRC in Amendment 199. Therefore no changes need be made at this time.

4.0 PTLR Requirements 4.1 The PTLR has been prepared in accordance with the requirements of Technical Specification 5.6.4. The PTLR shall be provided to the NRC upon issuance for each reactor vessel fluence period and for any revision or supplement thereto. Davis-Besse will continue to meet the requirements of 10 CFR 50, Appendix G and any changes to the Davis-Besse P/T limits will be generated in accordance with the NRC approved methodology described in TS 5.6.4.

5.0 References 5.1 Safety Evaluation by the Office of Nuclear Reactor Regulation Related to Amendment No. 199 to Facility Operating License No. NPF-3 Davis-Besse Nuclear Power Station, Unit No. 1. Attached to correspondence dated July 20,1995.

5.2 Improved Technical Specification 5.6.4 5.3 Improved Technical Specification 3.4.12 5.4 BAW-10046A, Revision 2 "Methods of Compliance with Fracture Toughness and Operational Requirements of 10 CFR 50 Appendix G."

5.5 BAW-2108, Revision 1, "Fluence Tracking System," dated May 1992.

5.6 BAW-1 543A, "Master Integrated Reactor Vessel Material Surveillance Program."

5.7 Additional References Technical Specification 5.6.4, Reactor Coolant System (RCS)

Pressure and Temperature Limits Report (PTLR)

License Amendment 116, Serial No. 1490 Dated March 30,1988, Attachment 1, Page 5 Improved Technical Specification Conversion Project (LAR 06-0003) Section 5.6, Description of Change L03 Current Technical Specification 3/4.4.9, Pressure/Temperature Limits