Text

Units 1 & 2, Technical Specifications
	ML020240279
Person / Time
Site:	Farley
Issue date:	01/04/2002
From:	Hardy D; Southern Nuclear Operating Co
To:	Rinaldi F; Office of Nuclear Reactor Regulation
References
	FNF-125-NRC-DC
	Download: ML020240279 (64)
	v • d • e

FNP- 125-NRC-DC JANUARY 4, 2002 MR. FRANK RINALDI U. S. NUCLEAR REGULATORY COMMISSION MAIL STOP O-8H12 PD II-1 WASHINGTON, DC 20555 DEAR SIR, ATTACHED ARE THE FOLLOWING AMENDMENTS FOR FARLEY NUCLEAR PLANT TECHNICAL SPECIFICATIONS UNIT 1 AMENDMENT NO. 151 UNIT 2 AMENDMENT NO. 143 UNIT 1 CORE OPERATING LIMITS REPORT REVISION I CYCLE 18 DATED DECEMBER 2001 UNIT 2 CORE OPERATING LIMITS REPORT REVISION I CYCLE 15 DATED DECEMBER 2001 REVISION 10 OF THE TECHNICAL SPECIFICATIONS BASES FOR FARLEY NUCLEAR PLANT.

PLEASE REPLACE YOUR COPY OF THE EFFECTIVE PAGES WITH THE ATTACHED REVISED COPIES.

IF YOU HAVE QUESTIONS PLEASE CALL ME AT 334-899-5156 EXTENSION 3402.

SINCERELY,

.0 "

DONNIE HARDY DOCUMENT CONTROL SUPERVISOR DCH:llb CC: FILE RTYPE: A4.54 Memo Disk 3-NRC oo

THE FOLLOWING AMEMDMENTS ARE BEING ISSUED AND ARE TO BE FILED IN THE TECHNICAL SPECIFICATIONS.

UNIT 1 AMEMDMENT 151 UNIT 2 AMENDMENT 143 THE TRANSMITTAL SHOWS UNIT 1 AMENDMENT 151 AND 152 UNIT 2 AMENDMENT 143 AND 144 YOUf WILL NOQT HAVE A~NYTHIING TO~ FIEFOR AMENDMENT 152 AND, 44-,THS D~INOTAFiECAN TCHLNICAL, SPECIFICATION PAE HISIS AN UPAE FOLT)NtV UNIT 1 AMENDMENT 150 AND UNIT 2 AMENDMENT 142 WILL BE IMPLEMENTED AT A LATER DATE.

ATTACHMENT TO LICENSE AMENDMENT NO. 151 TO FACILITY OPERATING LICENSE NO. NPF-2 DOCKET NO. 50-348 ATTACHMENT TO LICENSE AMENDMENT NO. 143 TO FACILITY OPERATING LICENSE NO. NPF-8 DOCKET NO. 50-364 Replace the following pages of the Appendix A Technical Specifications and associated Bases with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Insert 2.0-1 2.0-1 2.0-2 3.3.1-20 3.3.1-20 3.3.1-21 3.3.1-21 3.4.1-1 3.4.1-1 3.4.1-2 3.4.1-2 5.6-2 5.6-2 5.6-3 5.6-3 5.6-4 5.6-4 5.6-5 5.6-5 5.6-6 5.6-6 B 2.1.1-2 B 2.1.1-2 B 2.1.1-3 B 2.1.1-3 B 2.1.1-4 B 2.1.1-4 B 3.4.1-2 B 3.4.1-2 B 3.4.1-3 B 3.4.1-3

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UNIT 1 AND UNIT 2 FNP TECHNICAL SPECIFICATIONS (TS)

LIST OF EFFECTIVE PAGES This LOEP is current through amendment numbers 152 on Unit 1 and 144 on Unit 2.

NOTE: The following amendments (U1/U2) do not affect any TS page: 150/142 (TORMIS; FSAR only; will be implemented at a later date) and 152/144 (update Facility Operating License; FOL only).

AMENDMENT NO. AMENDMENT NO.

AMENDMENT NO. U-2 PAGE U-I U-2 PAGE U-1 PA-.P U-I U-2 TS 3.1.4-3 ................... 146 ........ 137 3.3.2-1 .................... 146 ........ 137 Appendix "A" cover Sheet 3.1.5-1 ................... 146 ........ 137 3.3.2-2 .................... 146 ........ 137 i .............................. 146 ....... 137 3.1.5-2 ................... 146 ........ 137 3.3.2-3 .................... 146 ........ 137 ii ............................. 146 ....... 137 3.1.6-1 ................... 146 ........ 137 3.3.2-4 .................... 146 ........ 137 iii ............................ 146 ....... 137 3.1.6-2 ................... 146 ........ 137 3.3.2-5 .................... 146 ........ 137 iv ............................ 146 ....... 137 3.1.6-3 ................... 146 ........ 137 3.3.2-6 .................... 146 ........ 137 Section 1.0 Tab 3.1.7-1 ................... 146 ........ 137 3.3.2-7 .................... 146 ........ 137 1.1-1 ....................... 146 ....... 137 3.1.7-2 ................... 146 ........ 137 3.3.2-8 .................... 146 ........ 137 1.1-2 ....................... 146 ....... 137 3.1.7-3 ................... 146 ........ 137 3.3.2-9 .................... 146 ........ 137 1.1-3 ....................... 149 ....... 141 3.1.7-4 ................... 146 ........ 137 3.3.2-10 .................. 146 ........ 137 1.1-4 ....................... 149 ....... 141 3.1.8-1 ................... 146 ........ 137 3.3.2-11 .................. 147 ........ 138 1.1-5 ....................... 149 ....... 141 3.1.8-2 ................... 146 ........ 137 3.3.3-1 .................... 146 ........ 137 1.1-6 ....................... 149 ....... 141 Section 3.2 Tab 3.3.3-2 .................... 146 ........ 137 1.1-7 ....................... 146 ....... 137 3.2.1-1 ................... 146 ........ 137 3.3.3-3 .................... 146 ........ 137 1.2-1 ....................... 146 ....... 137 3.2.1-2 ................... 146 ........ 137 3.3.4-1 .................... 146 ........ 137 1.2-2 ....................... 146 ....... 137 3.2.1-3 ................... 146 ........ 137 3.3.4-2 .................... 146 ........ 137 1.2-3 ....................... 146 ....... 137 3.2.1-4 ................... 146 ........ 137 3.3.4-3 .................... 146 ........ 137 1.3-1 ....................... 146 ....... 137 3.2.1-5 ................... 146 ........ 137 3.3.5-1 .................... 146 ........ 137 1.3-2 ....................... 146 ....... 137 3.2.2-1 ................... 146 ........ 137 3.3.5-2 .................... 146 ........ 137 1.3-3 ....................... 146 ....... 137 3.2.2-2 ................... 146 ........ 137 3.3.5-3 .................... 146 ........ 137 1.3-4 ....................... 146 ....... 137 3.2.2-3 ................... 146 ........ 137 3.3.5-4 .................... 146 ........ 137 1.3-5 ....................... 146 ....... 137 3.2.3-1 ................... 146 ........ 137 3.3.6-1 .................... 146 ........ 137 1.3-6 ....................... 146 ....... 137 3.2.4-1 ................... 146 ........ 137 3.3.6-2 .................... 146 ........ 137 1.3-7 ....................... 146 ....... 137 3.2.4-2 ................... 146 ........ 137 3.3.6-3 .................... 146 ........ 137 1.3-8 ....................... 146 ....... 137 3.2.4-3 ................... 146 ........ 137 3.3.6-4 .................... 146 ........ 137 1.3-9 ....................... 146 ....... 137 3.2.4-4 ................... 146 ........ 137 3.3.7-1 .................... 146 ........ 137 1.3-10 ..................... 146 ....... 137 Section 3.3 Tab 3.3.7-2 .................... 146 ........ 137 1.3-11 ..................... 146 ....... 137 3.3.1-1 ................... 146 ........ 137 3.3.7-3 .................... 146 ........ 137 1.3-12 ..................... 146 ....... 137 3.3.1-2 ................... 146 ........ 137 3.3.7-4 .................... 146 ........ 137 1.3-13 ..................... 146 ....... 137 3.3.1-3 ................... 146 ........ 137 3.3.8-1 .................... 146 ........ 137 1.4-1 ....................... 146 ....... 137 3.3.1-4 ................... 146 ........ 137 3.3.8-2 .................... 146 ........ 137 1.4-2 ....................... 146 ....... 137 3.3.1-5 ................... 146 ........ 137 3.3.8-3 .................... 146 ........ 137 1.4-3 ....................... 146 ....... 137 3.3.1-6 ................... 146 ........ 137 3.3.8-4 .................... 146 ........ 137 1.4-4 ....................... 146 ....... 137 3.3.1-7 ................... 146 ........ 137 Section 3.4 Tab Section 2.0 Tab 3.3.1-8 ................... 146 ........ 137 3.4.1-1 .................... 151 ........ 143 2.0-1 ....................... 151 ....... 143 3.3.1-9 ................... 146 ........ 137 3.4.1-2 .................... 151 ........ 143 Section 3.0 Tab 3.3.1-10 ................. 146 ........ 137 3.4.2-1 .................... 146 ........ 137 3.0-1 ....................... 146 ....... 137 3.3.1-11 ................. 146 ........ 137 3.4.3-1 .................... 146 ........ 137 3.0-2 ....................... 146 ....... 137 3.3.1-12 ................. 146 ........ 137 3.4.3-2 .................... 146 ........ 137 3.0-3 ....................... 146 ....... 137 3.3.1-13 ................. 146 ........ 137 3.4.4-1 .................... 146 ........ 137 Section 3.1 Tab 3.3.1-14 ................. 146 ........ 137 3.4.5-1 .................... 146 ........ 137 3.1.1-1 .................... 146 ....... 137 3.3.1-15 ................. 146 ........ 137 3.4.5-2 .................... 147 ........ 138 3.1.2-1 .................... 146 ....... 137 3.3.1-16 ................. 146 ........ 137 3.4.6-1 .................... 146 ........ 137 3.1.2-2 .................... 146 ....... 137 3.3.1-17 ................. 147 ........ 138 3.4.6-2 .................... 147 ........ 138 3.1.3-1 .................... 146 ....... 137 3.3.1-18 ................. 146 ........ 137 3.4.7-1 .................... 147 ........ 138 3.1.3-2 .................... 146 ....... 137 3.3.1-19 ................. 146 ........ 137 3.4.7-2 .................... 147 ........ 138 3.1.4-1 .................... 146 ....... 137 3.3.1-20 ................. 151 ........ 143 3.4.7-3 .................... 146 ........ 137 3.1.4-2 .................... 146 ....... 137 3.3.1-21 ................. 151 ........ 143 3.4.8-1 .................... 146 ........ 137 Page I of 3 T:\Operations\OPS Staff\DRC\TS Amendments\LOEP\152-144.doc

UNIT 1 AND UNIT 2 FNP TECHNICAL SPECIFICATIONS (TS)

LIST OF EFFECTIVE PAGES This LOEP is current through amendment numbers 152 on Unit I and 144 on Unit 2.

NOTE: The following amendments (U1/U2) do not affect any TS page: 150/142 (TORMIS; FSAR only; will be implemented at a later date) and 152/144 (update Facility Operating License; FOL only).

AMENDMENT NO. AMENDMENT NO. AMENDMENT NO.

PAGE U-I U-2 PAGE U-1 U-2 PAGE U-I U-2 3.4.8-2 .................... 146 ....... 137 3.6.2-5 ................... 146 ........ 137 Section 3.8 Tab 3.4.9-1 .................... 146 ....... 137 3.6.3-1 ................... 146 ........ 137 3.8.1-1 .................... 146 ........ 137 3.4.9-2 .................... 146 ....... 137 3.6.3-2 ................... 146 ........ 137 3.8.1-2 .................... 146 ........ 137 3.4.10-1 .................. 146 ....... 137 3.6.3-3 ................... 146 ........ 137 3.8.1-3 .................... 146 ........ 137 3.4.10-2 .................. 146 ....... 137 3.6.3-4 ................... 146 ........ 137 3.8.1-4 .................... 146 ........ 137 3.4.11-1 .................. 146 ....... 137 3.6.3-5 ................... 146 ........ 137 3.8.1-5 .................... 146 ........ 137 3.4.11-2 .................. 146 ....... 137 3.6.3-6 ................... 146 ........ 137 3.8.1-6 .................... 146 ........ 137 3.4.11-3 .................. 146 ....... 139 3.6.4-1 ................... 146 ........ 137 3.8.1-7 .................... 146 ........ 137 3.4.114 .................. 146 ....... 139 3.6.5-1 ................... 146 ........ 137 3.8.1-8 .................... 146 ........ 137 3.4.12-1 .................. 146 ....... 137 3.6.6-1 ................... 146 ........ 137 3.8.1-9 .................... 146 ........ 137 3.4.12-2 .................. 146 ....... 137 3.6.6-2 ................... 146 ........ 137 3.8.1-10 .................. 146 ........ 137 3.4.12-3 .................. 146 ....... 137 3.6.6-3 ................... 146 ........ 137 3.8.1-11 .................. 146 ........ 137 3.4.124 .................. 146 ....... 137 3.6.7-1 ................... 146 ........ 137 3.8.1-12 .................. 146 ........ 137 3.4.13-1 .................. 147 ....... 138 3.6.7-2 ................... 146 ........ 137 3.8.1-13 .................. 146 ........ 137 3.4.13-2 .................. 146 ....... 137 3.6.8-1 ................... 146 ........ 137 3.8.1-14 .................. 146 ........ 137 3.4.14-1 .................. 146 ....... 137 3.6.8-2 ................... 146 ........ 137 3.8.2-1 .................... 146 ........ 137 3.4.14-2 .................. 146 ....... 137 3.6.9-1 ................... 146 ........ 137 3.8.2-2 .................... 146 ........ 137 3.4.14-3 .................. 146 ....... 137 Section 3.7 Tab 3.8.2-3 .................... 146 ........ 137 3.4.144 .................. 146 ....... 137 3.7.1-1 ................... 146 ........ 137 3.8.3-1 .................... 146 ........ 137 3.4.15-1 .................. 146 ....... 137 3.7.1-2 ................... 146 ........ 137 3.8.3-2 .................... 146 ........ 137 3.4.15-2 .................. 146 ....... 137 3.7.1-3 ................... 146 ........ 137 3.8.3-3 .................... 146 ........ 137 3.4.15-3 .................. 146 ....... 137 3.7.1-4 ................... 146 ........ 137 3.8.4-1 .................... 146 ........ 137 3.4.16-1 .................. 147 ....... 138 3.7.2-1 ................... 146 ........ 137 3.8.4-2 .................... 146 ........ 137 3.4.16-2 .................. 147 ....... 138 3.7.2-2 ................... 146 ........ 137 3.8.4-3 .................... 146 ........ 137 3.4.16-3 .................. 146 ....... 137 3.7.3-1 ................... 146 ........ 137 3.8.44 .................... 146 ........ 137 3.4.164 .................. 147 ....... 138 3.7.3-2 ................... 146 ........ 137 3.8.5-1 .................... 146 ........ 137 Section 3.5 Tab 3.7.4-1 ................... 146 ........ 137 3.8.5-2 .................... 146 ........ 137 3.5.1-1 .................... 146 ....... 137 3.7.4-2 ................... 146 ........ 137 3.8.6-1 .................... 146 ........ 137 3.5.1-2 .................... 146 ....... 137 3.7.5-1 ................... 146 ........ 137 3.8.6-2 .................... 146 ........ 137 3.5.2-1 .................... 146 ....... 137 3.7.5-2 ................... 146 ........ 137 3.8.6-3 .................... 146 ........ 137 3.5.2-2 .................... 146 ....... 137 3.7.5-3 ................... 146 ........ 137 3.8.64 .................... 146 ........ 137 3.5.2-3 .................... 146 ....... 137 3.7.6-1 ................... 146 ........ 137 3.8.7-1 .................... 146 ........ 137 3.5.3-1 .................... 146 ....... 137 3.7.7-1 ................... 146 ........ 137 3.8.7-2 .................... 146 ........ 137 3.5.3-2 .................... 146 ....... 137 3.7.7-2 ................... 146 ........ 137 3.8.8-1 .................... 146 ........ 137 3.5.3-3 .................... 146 ....... 137 3.7.8-1 ................... 146 ........ 137 3.8.8-2 .................... 146 ........ 137 3.5.4-1 .................... 146 ....... 137 3.7.8-2 ................... 146 ........ 137 3.8.9-1 .................... 146 ........ 137 3.5.4-2 .................... 146 ....... 137 3.7.9-1 ................... 146 ........ 137 3.8.9-2 .................... 146 ........ 137 3.5.5-1 .................... 146 ....... 137 3.7.10-1 ................. 146 ........ 137 3.8.10-1 .................. 146 ........ 137 3.5.5-2 .................... 146 ....... 137 3.7.10-2 ................. 146 ........ 137 3.8.10-2 .................. 146 ........ 137 3.5.5-3 .................... 146 ....... 137 3.7.11-1 ................. 146 ........ 137 Section 3.9 Tab 3.5.6-1 .................... 146 ....... 137 3.7.11-2 ................. 146 ........ 137 3.9.1-1 .................... 146 ........ 137 Section 3.6 Tab 3.7.12-1 ................. 146 ........ 137 3.9.2-1 .................... 146 ........ 137 3.6.1-1 .................... 146 ....... 137 3.7.12-2 ................. 146 ........ 137 3.9.2-2 .................... 146 ........ 137 3.6.1-2 .................... 146 ....... 137 3.7.13-1 ................. 146 ........ 137 3.9.3-1 .................... 146 ........ 137 3.6.2-1 .................... 146 ........ 137 3.7.14-1 ................. 146 ........ 137 3.9.3-2 .................... 146 ........ 137 3.6.2-2 .................... 146 ....... 137 3.7.15-1 ................. 146 ........ 137 3.9.4-1 .................... 146 ........ 137 3.6.2-3 .................... 146 ....... 137 3.7.15-2 ................. 146 ........ 137 3.9.4-2 .................... 146 ........ 137 3.6.2-4 .................... 146 ....... 137 3.7.16-1 ................. 146 ........ 137 3.9.5-1 .................... 146 ........ 137 Page 2 of 3 T:\Operations\OPS StafLDRC\TS Amendments\LOEP\152-144.doc

UNIT 1 AND UNIT 2 FNP TECHNICAL SPECIFICATIONS (TS)

LIST OF EFFECTIVE PAGES This LOEP is current through amendment numbers 152 on Unit 1 and 144 on Unit 2.

NOTE: The following amendments (U1/U2) do not affect any TS page: 150/142 (TORMIS; FSAR only; will be implemented at a later date) and 152/144 (update Facility Operating License; FOL only).

AMENDMENT NO. AMENDMENT NO. AMENDMENT NO.

PAGE U-1 U-2 PAGE U-1 U-2 PAGE U-I U-2 3.9.5-2 .................... 146 ....... 137 3.9.5-3 .................... 146 ....... 137 3.9.6-1 .................... 146 ....... 137 Section 4.0 Tab 4.0-1 ....................... 146 ....... 137 4.0-2 ....................... 146 ....... 137 4.0-3 ....................... 146 ....... 137 4.0-4 ....................... 146 ....... 137 4.0-5 ....................... 146 ....... 137 4.0-6 ....................... 146 ....... 137 4.0-7 ....................... 146 ....... 137 4.0-8 ....................... 146 ....... 137 4.0-9 ....................... 146 ....... 137 Section 5.0 Tab 5.1-1 ....................... 146 ....... 137 5.2-1 ....................... 146 ....... 137 5.2-2 ....................... 146 ....... 137 5.2-3 ....................... 146 ....... 137 5.3-1 ....................... 146 ....... 137 5.4-1 ....................... 146 ....... 137 5.5-1 ....................... 146 ....... 137 5.5-2 ....................... 146 ....... 137 5.5-3 ....................... 146 ....... 137 5.5-4 ....................... 146 ....... 137 5.5-5 ....................... 147 ....... 138 5.5-6 ....................... 147 ....... 138 5.5-7 ....................... 147 ....... 138 5.5-8 ....................... 147 ....... 138 5.5-9 ....................... 147 ....... 138 5.5-10 ..................... 147 ....... 138 5.5-11 ..................... 147 ....... 138 5.5-12 ..................... 147 ....... 138 5.5-13 ..................... 147 ....... 138 5.5-14 ..................... 147 ....... 138 5.5-15 ..................... 148 ....... 140 5.5-16 ..................... 147 ....... 138 5.5-17 ..................... 147 ....... 138 5.5-18 ..................... 147 ....... 138 5.6-1 ....................... 146 ....... 137 5.6-2 ....................... 151 ....... 143 5.6-3 ....................... 15 1 ....... 143 5.6-4 ....................... 151 ....... 143 5.6-5 ....................... 151 ....... 143 5.6-6 ....................... 151 ....... 143 5.7-1 ....................... 146 ....... 137 5.7-2 ....................... 146 ....... 137 Page 3 of 3 T:\Operations\OPS Staff\DRC\TS Amendments\LOEP\152-144.doc

SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs 2.1.1.1 In MODES I and 2, the departure from nucleate boiling ratio (DNBR) shall be maintained within the 95/95 DNB criterion correlation specified in the COLR.

2.1.1.2 In MODES I and 2, the peak fuel centerline temperature shall be Maintained < 5080 F, decreasing by 58OF per 10,000 MWD/MTU.

0 2.1.2 RCS Pressure SL

< 2735 psig.

In MODES 1, 2, 3, 4, and 5, the RCS pressure shall be maintained 2.2 SL Violations within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

2.2.1 If SL 2.1.1 is violated, restore compliance and be in MODE 3 2.2.2 If SL 2.1.2 is violated:

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

2.2.2.1 In MODE 1 or 2, restore compliance and be in MODE 3 within 2.2.2.2 In MODE 3, 4, or 5, restore compliance within 5 minutes.

Amendment No. 151 (Unit 1)

Farley Units I and 2 2.0-1 Amendment No. 143 (Unit 2)

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 6 of 8)

Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWAB TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS LE VALUE SETPOINT

18. Reactor Trip 1,2 2 trains R, V SR 3.3.1.4 NA NA Breakers ()

3 (a), 4 (a), 5 (a) 2 trains C, V SR 3.3.1.4 NA NA

19. Reactor Trip 1,2 1 each per U SR 3.3.1.4 NA NA Breaker RIB Undervoltage and 3 (a), 4 (a), 5 (a) C SR 3.3.1.4 NA NA Shunt Trip 1 each per Mechanisms RTB

20. Automatic Trip 1,2 2 trains 0, V SR 3.3.1.5 NA NA Logic 3 (a), 4 (a), 5 (a) 2 trains C, V SR 3.3.1.5 NA NA (a) With RTBs closed and Rod Control System capable of rod withdrawal.

() Including any reactor trip bypass breaker that is racked in and closed for bypassing an RTB.

Farley Units 1 and 2 3.3.1-19 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 7 of 8)

Reactor Trip System Instrumentation Note 1: Overtemperature AT Trip Setpoint The Overtemperature AT Function Allowable Value shall not exceed the following by more than 0.4% of AT span.

rIS) [T I + T'KV/P P)-fl(Ajs ATLI1+(I + T:S)

"¢~ss A To: K,-K2,(]+ 01+ T2s) I (1+ 'r6s) jr.i Where: AT is measured loop AT, *F.

ATo is the indicated loop AT at RTP and reference T,,g, OF.

s is the Laplace transform operator, sec".

T is the measured loop average temperature, OF.

T' is the reference T=, at RTP, <

OF.

P is the measured pressurizer pressure, psig.

P' is the nominal pressurizer operating pressure = *psig.

K ='* K2==*/*F K3 = * /psi

'T,

sec "V2< sec

",5< *sec ".6<

sec r4 = *sec fl(AI) is a function of the indicated difference between top and bottom detectors on of the power-range nuclear ion chambers; with gains to be selected based measured instrument response during plant startup tests such that:

f1(Al) = *{" when (qt - qb)_< * % RTP

%+of(q,RTP

- qk)}

when * % RTP < (qt - qb)< * % RTP

{(qt- qb)" *} when (qt - qb)> * % RTP Where qt and qb are percent RTP in the upper and lower halves of the core, respectively, and q, + qb is the total THERMAL POWER in percent RTP.

as specified in the COLR I Amendment No. 151 (Unit 1)

Farley Units 1 and 2 3.3.1-20 Amendment No. 143 (Unit 2)

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 8 of 8)

Reactor Trip System Instrumentation Note 2: Overpower AT The Overpower AT Function Allowable Value shall not exceed the following Trip Setpoint by more than 0.4% of AT span.

4 s) <ATo K4 -

1 -" -f2 (Ax 1)

AT (1+

(1+ 1'r's) 1 + 3'-3s 3S 1i+ T 6 S T1-K T 1+ T'6s Where: AT is measured loop AT, °F.

ATo is the indicated loop AT at RTP and reference T,,, OF.

s is the Laplace transform operator, sec-.

T is the measured loop average temperature, OF.

T" is the reference Tv, at RTP, <

OF.

1K4 =* Ks = */°F for increasing T8, K6 = */eF when T > T' K5 = *I°F for decreasing T,,, K6 = */OF when T < T" "r3 >

sec r4 = *sec

-Ts < sec T6 <

sec f2(AI) = *% RTP for all Al.

as specified in the COLR Farley Units 1 and 2 3.3.1-21 Amendment No. 151 (Unit 1)

Amendment No. 143 (Unit 2)

RCS Pressure, Temperature, and Flow DNB Limits 341 3.4 REACTOR COOLANT SYSTEM (RCS)

Limits 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB)

LCO 3.4.1 RCS DNB parameters for pressurizer pressure, RCS average temperature, and RCS total flow rate shall be within the limits specified in the COLR. The minimum RCS total flow rate shall be > 263,400 GPM when using the precision heat balance method, > 264,200 GPM when using the elbow tap method, and --the limit specified in the COLR.

APPLICABILITY: MODE 1.

Pressurizer pressure limit does not apply during:

a. THERMAL POWER ramp > 5% RTP per minute; or

b. THERMAL POWER step > 10% RTP.

ACTIONS REQUIRED ACTION COMPLETION TIME CONDITION A.1 Restore RCS DNB 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months A. One or more RCS DNB parameters not within parameter(s) to within limits, limit.

B.1 Be in MODE 2. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months B. Required Action and associated Completion Time not met.

3.4.1-1 Amendment No. 151 (Unit 1)

Farley Units 1 and 2 Amendment No. 143 (Unit 2)

RCS Pressure, Temperature, and Flow DNB Limits 3.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.1.1 Verify pressurizer pressure is within the limit 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months specified in the COLR.

SR 3.4.1.2 Verify RCS average temperature is within the 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months limit specified in the COLR.

SR 3.4.1.3 Verify RCS total flow rate is within the limits. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.1.4 ---- NOTE--

Not required to be performed until 7 days after

>90% RTP.

Verify by measurement that RCS total flow rate is 18 months within the limits.

Farley Units 1 and 2 3.4.1-2 Amendment No. 1 1 (Unit 1)

Amendment No. 143 (Unit 2)

Reporting Requirements 5.6 5.0 ADMINISTRATIVE CONTROLS 5.6 Reporting Requirements The following reports shall be submitted in accordance with 10 CFR 50.4.

5.6.1 Occupational Radiation Exposure Report

NOTE --------------------------------------------------

A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station.

A tabulation on an annual basis of the number of station, utility, and other personnel (including contractors), for whom monitoring was performed, receiving an annual deep dose equivalent > 100 mrems and the associated collective deep dose equivalent (reported in person - rem) according to work and job functions (e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling). This tabulation supplements the requirements of 10 CFR 20.2206. The dose assignments to various duty functions may be estimated based on pocket ionization chamber, thermoluminescence dosimeter (TLD),

electronic dosimeter, or film badge measurements. Small exposures totaling

< 20 percent of the individual total dose need not be accounted for. In the aggregate, at least 80 percent of the total deep dose equivalent received from external sources should be assigned to specific major work functions. The report covering the previous calendar year shall be submitted by April 30 of each year.

5.6.2 Annual Radiological Environmental Operating Report

NOTE ------------------------

A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station.

The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, and analyses of trends of the results of the radiological environmental monitoring program for the reporting period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (ODCM), and in 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C.

Farley Units 1 and 2 5.6-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.3 Radioactive Effluent Release Report

--- ~NOTE-A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

The Radioactive Effluent Release Report covering the operation of the unit in the previous year shall be submitted prior to May 1 of each year in accordance with 10 CFR 50.36a. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit.

The material provided shall be consistent with the objectives outlined in the ODCM and Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR Part 50, Appendix I, Section IV.B.1.

5.6.4 Monthly Operatinq Reports Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the pressurizer power operated relief valves or pressurizer safety valves, shall be submitted on a monthly basis no later than the 15th of each month following the calendar month covered by the report. In the event a RHR relief valve or a RCS vent is used to mitigate a RCS pressure transient, the monthly operating report shall describe the circumstances initiating the transient, the effect of the RHR relief valves or vent on the transient, and any corrective action necessary to prevent recurrence.

5.6.5 CORE OPERATING LIMITS REPORT (COLR)

a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:

1. Reactor Core Safety Limits for THERMAL POWER, Reactor Coolant System highest loop average temperature and pressurizer pressure for Safety Limit 2.1.1,

2. SHUTDOWN MARGIN limit for MODES 2 (with kf,< 1), 3, 4, and 5 for LCO 3.1.1,

3. Moderator Temperature Coefficient BOL and EOL limits and 300 ppm and 100 ppm surveillance limits for LCO 3.1.3, (continued)

Farley Units I and 2 5.6-2 Amendment No. 151 (Unit 1)

Amendment No. 143 (Unit 2)

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)

4. Shutdown Bank Insertion Limits for LCO 3.1.5,

5. Control Bank Insertion Limit for LCO 3.1.6,

6. Heat Flux Hot Channel Factor FaRTP limits, K(Z) figure, W(Z) values, and Fa(Z) Penalty Factors for LCO 3.2.1, "7. Nuclear Enthalpy Rise Hot Channel Factor limits, F6HRTP, and Power Factor Multiplier, PFA, for LCO 3.2.2,

8. Axial Flux Limits for LCO 3.2.3,

9. Reactor Trip System Instrumentation Overtemperature AT (OTAT) and Overpower AT (OPAT) setpoint parameter values for Table 3.3.1-1, 10 Reactor Coolant System pressure, temperature, and flow in LCO 3.4.1,

11. Refueling Operations Boron Concentration for LCO 3.9.1.

be

b. The analytical methods used to determine the core operating limits shall those previously reviewed and approved by the NRC, specifically those described in the following documents:

1. WCAP-9272-P-A, 'Westinghouse Reload Safety Evaluation Methodology," July 1985 (j Proprietary).

(Methodology for LCOs 3.1.1 - SHUTDOWN MARGIN, 3.1.3 Moderator Temperature Coefficient, 3.1.5 - Shutdown Bank Insertion Limit, 3.1.6 - Control Bank Insertion Limits, 3.2.3 - Axial Flux Difference, 3.2.1 - Heat Flux Hot Channel Factor, 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor and 3.9.1 - Boron Concentration.)

2. WCAP-1 0216-P-A, Rev.IA, "Relaxation of Constant Axial Offset Control / FQ Surveillance Technical Specification," February 1994 (W Proprietary).

(Methodology for LCOs 3.2.3 - Axial Flux Difference and 3.2.1 Heat Flux Hot Channel Factor.)

(continued) 5.6-3 Amendment No. 151 (Unit 1)

Farley Units 1 and 2 Amendment No. 143 (Unit 2)

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued) 3a. WCAP-12945-P-A, Volume 1, Revision 2, and Volumes 2 through 5, Revision 1, "Code Qualification Document for Best Estimate LOCA Analysis," March 1998 (W Proprietary).

3b. WCAP-12610-P-A, "Vantage+ Fuel Assembly Reference Core Report," April 1995 LW Proprietary).

(Methodology for LCO 3.2.1 - Heat Flux Hot Channel Factor and LCO 3.4.1- RCS Pressure, Temperature and Flow Departure from Nucleate Boiling Limits.)

4. WCAP-8745-P-A, "Design Bases for the Thermal Overpower AT and Thermal Overtemperature AT Trip Functions," September 1986 (Westinghouse Proprietary)

(Methodology for Overpower AT and Thermal Overtemperature AT Trip Functions)

5. WCAP-14750-P-A Revision 1, "RCS Flow Verification Using Elbow Taps at Westinghouse 3-Loop PWRs. (Westinghouse Proprietary)

(Methodology for minimum RCS flow determination using the elbow tap measurement)

6. WCAP-1 1596-P-A, "Oualification of the Phoenix-P/ANC Nuclear Design System for Pressurized Water Reactor Cores," June 1988 (Methodology for LCO 3.9.1 - Boron Concentration)

7. WCAP-1 1397-P-A "Revised Thermal Design Procedure," April 1989 (Methodology for LCO 2.1.1-Reactor Core Safety Limits, LCO 3.4.1 RCS Pressure, Temperature and Flow Departure from Nucleate Boiling Limits.)

C. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

(continued)

Farley Units 1 and 2 5.6-4 Amendment No. 151 (Unit 1)

Amendment No. 143 (Unit 2)

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)

d. The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

LIMITS 5.6.6 Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE REPORT (PTLR)

a. The reactor coolant system pressure and temperature limits, including heatup and cooldown rates, shall be established and documented in the PTLR for LCO 3.4.3.

b. The analytical methods used to determine the RCS pressure and the temperature limits shall be those previously reviewed and approved by NRC, specifically those described in the NRC letters dated March 31, 1998 and April 3,1998.

c. The PTLR shall be provided to the NRC upon issuance for each reactor fluence period and for any revision or supplement thereto.

5.6.7 EDG Failure Report valid If an individual emergency diesel generator (EDG) experiences four or more failures shall be reported within 30 days.

failures in the last 25 demands, these Reports on EDG failures shall include a description of the failures, underlying causes, and corrective actions taken per the Emergency Diesel Generator Reliability Monitoring Program.

5.6.8 PAM Report When a report is required by Condition B or G of LCO 3.3.3, "Post Accident Monitoring (PAM) Instrumentation," a report shall be submitted within the of following 14 days. The report shall outline the preplanned alternate method monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.

5.6.9 Tendon Surveillance Report the tests Any abnormal degradation of the containment structure detected during required by the Pre-stressed Concrete Containment Tendon Surveillance (continued) 5.6-5 Amendment No. 151 (Unit 1)

Farley Units 1 and 2 Amendment No. 143 (Unit 2)

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.9 Tendon Surveillance Report (continued)

Program shall be reported to the NRC within 30 days. The report shall include a description of the tendon condition, the condition of the concrete (especially at tendon anchorages), the inspection procedures, the tolerances on cracking, and the corrective action taken.

5.6.10 Steam Generator Tube Inspector Report

a. Following each inservice inspection of steam generator tubes, the number of tubes plugged in each steam generator shall be reported to the Commission within 15 days of the completion of the plugging effort.

b. The complete results of the steam generator tube inservice inspection shall be submitted to the Commission within 12 months following the completion of the inspection. This Report shall include:

1. Number and extent of tubes inspected.

2. Location and percent of wall-thickness penetration for each indication of an imperfection.

3. Identification of tubes plugged.

c. Results of steam generator tube inspections which fall into Category C-3 shall be considered a Reportable Event and shall be reported pursuant to 10 CFR 50.73 prior to resumption of plant operation. The written report shall provide a description of investigations conducted to determine the cause of the tube degradation and corrective measures taken to prevent recurrence.

5.6.11 Alternate AC (AACM Source Out of Service Report The NRC shall be notified if the AAC source is out of service for greater than 10 days.

Fadey Units I and 2 5.6-6 Amendment No. 151 (Unit 1)1 Amendment No. 143 (Unit 2) I

Changed Pages List For ITS Bases Revision 10 Replace the following pages of the Technical Specifications Bases with the attached revised pages. The revised pages are identified as Revision 10.

They contain vertical lines indicating area of changes (except LOEP has no rev bars).

Remove Instructions LOEP pages 1 Through 5 Replace B 2.1.1-2 Replace B 2.1.1-3 Replace B 2.1.1-4 Replace B 3.4.1-2 Replace B 3.4.1-3 Replace

UNIT 1 AND UNIT 2 FNP TECHNICAL SPECIFICATIONS (TS) BASES LIST OF EFFECTIVE PAGES THIS LIST IS CURRENT THROUGH REVISION NUMBER - 10

/'k A t*r DtX7TTflNT CCi PA(T RPVtSTON NO. PAGE REVISION NO.

rlTCIiNT'Vj ) r.

BASES B 3.1.4-3 ................................... 0 B 3.2.2-4 ................................... 0 Appendix A Bases Cover Sheet B 3.1.4-4 ................................. 0 B 3.2.2-5 ................................... 0 0 B 3.1.4-5 ................................... 0 B 3.2.2-6 .................................... 0 i ..................................................

ii ................................................... 0 B 3.1.4-6 ................................... 0 B 3.2.2-7 .................................... 0 iii ................................................... 0 B 3.1.4-7 ................................. 0 B 3.2.3-1 ................................... 0 B 3.1.4-8 ................................. 0 B 3.2.3-2 ................................... 0 Section B 2.0 Tab B 2.1.1-1 ................................... 0 B 3.1.4-9 ................................. 0 B 3.2.3-3 ................................... 0 B 2.1.1-2 ................................. 10 B 3.1.4-10 ................................. 0 B 3.2.3-4 .................................... 0 10 B 3.1.5-1 ................................... 0 B 3.2.3-5 ................................... 0 B 2.1.1-3 .................................

B 2.1.1-4 ................................. 10 B 3.1.5-2 ................................. 0 B 3.2.4-1 ................................... 0 0 B 3.1.5-3 ................................. 0 B 3.2.4-2 .................................... 0 B 2.1.2-1 ...................................

B 2.1.2-2 ................................... 0 B 3.1.5-4 ................................. 0 B 3.2.4-3 ................................... 0 B 2.1.2-3 ................................... 0 B 3.1.5-5 ................................. 0 B 3.2.4-4 ................................... 0 B 3.1.6-1 ................................... 0 B 3.2.4-5 ................................... 0 Section B 3.0 Tab B 3.0-1 ..................................... 0 B 3.1.6-2 ................................. 0 B 3.2.4-6 ................................... 0 B 3.0-2 ..................................... 0 B 3.1.6-3 ................................. 0 B 3.2.4-7 .................................... 0 B 3.0-3 ..................................... 0 B 3.1.6-4 ................................. 0 Section B 3.3 Tab B 3.0-4 ..................................... 0 B 3.1.6-5 ................................. 0 B 3.3.1-1 ................................... 0 B 3.0-5 ..................................... 0 B 3.1.6-6 ................................. 0 B 3.3.1-2 ................................... 0 B 3.0-6 ..................................... 0 B 3.1.6-7 ................................. 0 B 3.3.1-3 ................................... 0 0 B 3.1.7-1 ................................... 0 B 3.3.1-4 .................................... 0 B 3.0-7 .....................................

B 3.0-8 ..................................... 0 B 3.1.7-2 ................................. 0 B 3.3.1-5 ................................... 0 B 3.0-9 ..................................... 0 B 3.1.7-3 ................................. 0 B 3.3.1-6 .................................... 0 0 B 3.1.7-4 ................................. 0 B 3.3.1-7 ................................... 0 B 3.0-10 ...................................

B 3.0-11 ................................... 0 B 3.1.7-5 ................................... 0 B 3.3.1-8 ................................... 0 B 3.0-12 ................................... 0 B 3.1.7-6 ................................. 0 B 3.3.1-9 ................................... 0 0 B 3.1.7-7 ................................. 0 B 3.3.1-10 ................................. 0 B 3.0-13 ...................................

B 3.0-14 ................................... 0 B 3.1.8-1 ................................... 0 B 3.3.1-11 ................................. 0 0 B 3.1.8-2 ................................. 0 B 3.3.1-12 ................................. 0 B 3.0-15 ...................................

B 3.1.8-3 ................................... 0 B 3.3.1-13 ................................. 0 Section B 3.1 Tab B 3.1.1-1 ................................... 0 B 3.1.8-4 ................................. 0 B 3.3.1-14 ................................. 0 B 3.1.1-2 ................................... 0 B 3.1.8-5 ................................... 0 B 3.3.1-15 ................................. 0 0 B 3.1.8-6 ................................... 0 B 3.3.1-16 ................................. 0 B 3.1.1-3 ...................................

0 B 3.1.8-7 ................................... 0 B 3.3.1-17 ................................. 0 B 3.1.1-4 ...................................

B 3.1.1-5 ................................... 0 B 3.1.8-8 ................................. 0 B 3.3.1-18 ................................. 0 B 3.1.1-6 ................................... 0 Section B 3.2 Tab B 3.3.1-19 ................................. 0 B 3.1.2-1 ................................... 0 B 3.2.1-1 ................................... 0 B 3.3.1-20 .................................. 9 0 B 3.2.1-2 ................................. 0 B 3.3.1-21 ................................. 0 B 3.1.2-2 ...................................

B 3.1.2-3 ................................... 0 B 3.2.1-3 ................................... 0 B 3.3.1-22 ................................. 0 0 B 3.2.1-4 ................................. 0 B 3.3.1-23 ................................. 0 B 3.1.2-4 ...................................

B 3.1.2-5 ................................... 0 B 3.2.1-5 ................................. 0 B 3.3.1-24 ................................. 0 0 B 3.2.1-6 ................................. 0 B 3.3.1-25 ................................. 0 B 3.1.2-6 ...................................

B 3.1.3-1 ................................... 0 B 3.2.1-7 ................................. 0 B 3.3.1-26 ................................. 0 0 B 3.2.1-8 ................................. 0 B 3.3.1-27 ................................. 0 B 3.1.3-2 ...................................

0 B 3.2.1-9 ................................. 0 B 3.3.1-28 ................................. 0 B 3.1.3-3 ...................................

B 3.1.3-4 ................................... 0 B 3.2.1-10 ................................. 0 B 3.3.1-29 ................................. 0 0 B 3.2.1-11 ................................. 0 B 3.3.1-30 .................................. 0 B 3.1.3-5 ...................................

B 3.1.3-6 ................................... 0 B 3.2.2-1 ................................... 0 B 3.3.1-31 ................................. 0 B 3.1.4-1 ................................... 0 B 3.2.2-2 ................................. 0 B 3.3.1-32 ................................. 0 0 B 3.2.2-3 ................................. 0 B 3.3.1-33 ................................. 0 B 3.1.4-2 ...................................

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PAGE REVISION NO. PAGE B 3.3.1-34 ................................. 0 B 3.3.2-24 ................................. 0 B 3.3.5-3 ................................... 0 B 3.3.1-35 ................................. 0 B 3.3.2-25 ................................. 0 B 3.3.54 .................................... 0 B 3.3.1-36 ................................. 0 B 3.3.2-26 ................................. 0 B 3.3.5-5 ................................... 0 B 3.3.1-37 ................................. 0 B 3.3.2-27 ................................. 0 B 3.3.5-6 ................................... 0 B 3.3.1-38 ................................. 0 B 3.3.2-28 ................................. 0 B 3.3.5-7 ................................... 0 B 3.3.1-39 ................................. 0 B 3.3.2-29 ................................. 0 B 3.3.5-8 ................................... 0 B 3.3.1-40 ................................. 0 B 3.3.2-30 ................................. 0 B 3.3.6-1 ................................... 0 B 3.3.1-41 ................................. 0 B 3.3.2-31 ................................. 0 B 3.3.6-2 .................................... 0 B 3.3.1-42 ................................. 0 B 3.3.2-32 ................................. 0 B 3.3.6-3 .................................... 0 B 3.3.1-43 ................................. 0 B 3.3.2-33 ................................. 0 B 3.3.6-4 .................................... 0 B 3.3.1-44 ................................. 0 B 3.3.2-34 ................................. 0 B 3.3.6-5 ................................... 0 B 3.3.1-45 ................................. 0 B 3.3.2-35 ................................. 0 B 3.3.6-6 .................................... 0 B 3.3.1-46 ................................. 0 B 3.3.2-36 ................................. 0 B 3.3.6-7 .................................... 0 B 3.3.1-47 ................................. 0 B 3.3.2-37 ................................. 0 B 3.3.6-8 .................................... 0 B 3.3.1-48 ................................. 0 B 3.3.2-38 ................................. 0 B 3.3.6-9 .................................... 0 B 3.3.1-49 ................................. 0 B 3.3.2-39 ................................. 0 B 3.3.7-1 ................................... 0 B 3.3.1-50 ................................. 0 B 3.3.240 ................................. 0 B 3.3.7-2 ................................... 0 B 3.3.1-51 ................................ 0 B 3.3.24 1 ................................. 0 B 3.3.7-3 ................................... 0 B 3.3.1-52 ................................. 0 B 3.3.2-42 ................................. 0 B 3.3.7-4 ................................... 0 B 3.3.1-53 ................................. 0 B 3.3.2-43 ................................. 0 B 3.3.7-5 ................................... 0 B 3.3.1-54 ................................. 0 B 3.3.2-44 ................................. 0 B 3.3.7-6 .................................... 0 B 3.3.1-55 ................................. 0 B 3.3.2-45 ................................. 0 B 3.3.7-7 .................................... 0 B 3.3.1-56 ................................. 0 B 3.3.246 ................................. 7 B 3.3.7-8 .................................... 0 B 3.3.1-57 ................................. 0 B 3.3.2-47 ................................. 7 B 3.3.8-1 ................................... 0 B 3.3.1-58 ................................. 7 B 3.3.248 ................................. 7 B 3.3.8-2 .................................... 0 B 3.3.1-59 ................................. 7 B 3.3.3-1 ................................... 0 B 3.3.8-3 ................................... 0 B 3.3.1-60 ................................. 7 B 3.3.3-2 ................................... 0 B 3.3.8-4 .................................... 0 B 3.3.2-1 ................................... 0 B 3.3.3-3 ................................... 0 B 3.3.8-5 ................................... 0 B 3.3.2-2 ................................... 0 B 3.3.34 ................................. 0 B 3.3.8-6 .................................... 0 B 3.3.2-3 ................................... 0 B 3.3.3-5 ................................... 0 B 3.3.8-7 ................................... 0 B 3.3.24 ................................... 0 B 3.3.3-6 ................................. 0 B 3.3.8-8 ................................... 0 B 3.3.2-5 ................................... 0 B 3.3.3-7 ................................. 0 B 3.3.8-9 ........................................ 0 B 3.3.2-6 ................................... 0 B 3.3.3-8 ................................. 0 Section B 3.4 Tab B 3.3.2-7 ....................................... 0 B 3.3.3-9 ................................. 0 B 3.4.1-1 ................................... 0 B 3.3.2-8 ................................... 0 B 3.3.3-10 ................................. 0 B 3.4.1-2 ................................. 10 B 3.3.2-9 ................................... 0 B 3.3.3-11 ................................. 0 B 3.4.1-3 ................................. 10 B 3.3.2-10 ................................. 0 B 3.3.3-12 ................................. 0 B 3.4.1-4 .................................... 0 B 3.3.2-11 ................................ 0 B 3.3.3-13 ................................. 0 B 3.4.1-5 .................................... 0 B 3.3.2-12 ................................. 0 B 3.3.3-14 ................................. 0 B 3.4.2-1 ................................... 0 B 3.3.2-13 ................................. 0 B 3.3.3-15 ................................. 0 B 3.4.2-2 .................................... 0 B 3.3.2-14 ................................. 0 B 3.3.3-16 ................................. 0 B 3.4.2-3 .................................... 0 B 3.3.2-15 ................................. 0 B 3.3.3-17 ................................. 0 B 3.4.3-1 ................................... 0 B 3.3.2-16 ................................. 0 B 3.3.4-1 ................................... 0 B 3.4.3-2 .................................... 0 B 3.3.2-17 ................................. 0 B 3.3.4-2 ................................. 0 B 3.4.3-3 .................................... 0 B 3.3.2-18 ................................. 0 B 3.3.4-3 ................................. 0 B 3.4.3-4 .................................... 0 B 3.3.2-19 ................................. 0 B 3.3.4-4 ................................. 0 B 3.4.3-5 .................................... 0 B 3.3.2-20 ................................. 0 B 3.3.4-5 ................................. 0 B 3.4.3-6 .................................... 0 B 3.3.2-21 ................................ 0 B 3.3.4-6 ................................. 0 B 3.4.3-7 .................................... 0 B 3.3.2-22 ................................. 0 B 3.3.5-1 ................................... 0 B 3.4.4-1 ................................... 0 B 3.3.2-23 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PAGE B 3.4.4-3 ................................... 0 B 3.4.13-1 ................................. 0 B 3.5.4-1 ................................... 0 B 3.4.4-4 ................................... 0 B 3.4.13-2 ................................. 5 B 3.5.4-2 ................................... 0 B 3.4.5-1 ................................... 0 B 3.4.13-3 ................................. 5 B 3.5.4-3 ................................... 0 B 3.4.5-2 ................................... 0 B 3.4.134 ................................. 5 B 3.5.4-4 ................................... 0 B 3.4.5-3 ................................... 0 B 3.4.13-5 ................................. 0 B 3.5.4-5 ................................... 0 B 3.4.5-4 ................................... 0 B 3.4.13-6 ................................. 0 B 3.5.4-6 .................................... 0 B 3.4.5-5 ................................... 5 B 3.4.14-1 ................................. 0 B 3.5.5-1 ................................... 0 B 3.4.5-6 ................................... 5 B 3.4.14-2 ................................. 0 B 3.5.5-2 ................................... 0 B 3.4.6-1 ................................... 0 B 3.4.14-3 ................................. 0 B 3.5.5-3 ................................... 0 B 3.4.6-2 ....................................... 0 B 3.4.14-4 ................................. 0 B 3.5.5-4 .................................... 0 B 3.4.6-3 ................................... 0 B 3.4.14-5 ................................. 0 B 3.5.6-1 ................................... 0 B 3.4.64 ................................... 0 B 3.4.14-6 ................................. 6 B 3.5.6-2 .................................... 0 B 3.4.6-5 ................................... 5 B 3.4.14-7 ................................. 0 B 3.5.6-3 ................................... 0 B 3.4.7-1 ....................................... 5 B 3.4.14-8 ................................. 0 B 3.5.6-4 .................................... 0 B 3.4.7-2 ................................... 5 B 3.4.15-1 ................................. 0 B 3.5.6-5 ................................... 0 B 3.4.7-3 ................................... 0 B 3.4.15-2 ................................. 0 Section B 3.6 Tab B 3.4.74 ................................... 5 B 3.4.15-3 ................................. 0 B 3.6.1-1 ................................... 0 B 3.4.7-5 ................................... 5 B 3.4.154 ................................. 0 B 3.6.1-2 ................................... 5 B 3.4.8-1 ................................... 0 B 3.4.15-5 ................................. 0 B 3.6.1-3 ................................... 0 B 3.4.8-2 ................................... 0 B 3.4.15-6 ................................. 0 B 3.6.14 .................................... 4 B 3.4.8-3 ................................... 0 B 3.4.16-1 ................................. 5 B 3.6.1-5 ................................... 0 B 3.4.9-1 ................................... 0 B 3.4.16-2 ................................. 5 B 3.6.2-1 ................................... 0 B 3.4.9-2 ................................... 0 B 3.4.16-3 ................................. 5 B 3.6.2-2 ................................... 5 B 3.4.9-3 ................................... 0 B 3.4.164 ................................. 0 B 3.6.2-3 ................................... 0 B 3.4.94 ................................... 0 B 3.4.16-5 ................................. 0 B 3.6.2-4 .................................... 0 B 3.4.9-5 ................................... 0 B 3.4.16-6 ................................. 0 B 3.6.2-5 ................................... 0 B 3.4.10-1 ............................... 0 Section B 3.5 Tab B 3.6.2-6 .................................... 0 B 3.4.10-2 ................................. 0 B 3.5.1-1 ................................... 0 B 3.6.2-7 .................................... 0 B 3.4.10-3 ................................. 0 B 3.5.1-2 ................................... 0 B 3.6.2-8 .................................... 0 B 3.4.104 ................................. 4 B 3.5.1-3 ................................... 0 B 3.6.3-1 ................................... 0 B 3.4.10-5 ................................. 0 B 3.5.14 ................................... 0 B 3.6.3-2 .................................... 0 B 3.4.11-1 ................................ 0 B 3.5.1-5 ................................... 0 B 3.6.3-3 ........................................ 0 B 3.4.11-2 ................................. 0 B 3.5.1-6 ................................... 0 B 3.6.3-4 .................................... 0 B 3.4.11-3 ................................. 0 B 3.5.1-7 ................................... 0 B 3.6.3-5 ................................... 0 B 3.4.11-4 ................................. 0 B 3.5.1-8 ................................... 0 B 3.6.3-6 .................................... 0 B 3.4.11-5 ................................. 0 B 3.5.2-1 ................................... 0 B 3.6.3-7 .................................... 0 B 3.4.11-6 ................................. 0 B 3.5.2-2 ................................... 0 B 3.6.3-8 .................................... 0 B 3.4.11-7 ................................. 2 B 3.5.2-3 ................................... 0 B 3.6.3-9 .................................... 0 B 3.4.11-8 ................................. 2 B 3.5.24 ................................... 0 B 3.6.3-10 ................................. 0 B 3.4.12-1 ................................. 0 B 3.5.2-5 ................................... 0 B 3.6.3-11 ................................. 0 B 3.4.12-2 ................................. 0 B 3.5.2-6 ................................... 0 B 3.6.3-12 ................................. 0 B 3.4.12-3 ................................. 0 B 3.5.2-7 ................................... 0 B 3.6.3-13 ................................. 0 B 3.4.124 ................................. 0 B 3.5.2-8 ................................... 0 B 3.6.3-14 ................................. 0 B 3.4.12-5 ................................. 0 B 3.5.2-9 ................................. 4 B 3.6.4-1 ........................................ 5 B 3.4.12-6 ................................. 0 B 3.5.2-10 ................................. 0 B 3.6.4-2 .................................... 0 B 3.4.12-7 ................................. 0 B 3.5.3-1 ................................... 0 B 3.6.4-3 ................................... 0 B 3.4.12-8 ................................. 0 B 3.5.3-2 ................................. 4 B 3.6.5-1 ................................... 0 B 3.4.12-9 ................................. 0 B 3.5.3-3 ................................... 0 B 3.6.5-2 .................................... 5 B 3.4.12-10 ............................... 0 B 3.5.34 ................................... 0 B 3.6.5-3 ........................................ 5 B 3.4.12-11 .............................. 0 B 3.5.3-5 ................................... 0 B 3.6.5-4 .................................... 0 Page 3 of 5

UNIT 1 AND UNIT 2 FNP TECHNICAL SPECIFICATIONS (TS) BASES LIST OF EFFECTIVE PAGES THIS LIST IS CURRENT THROUGH REVISION NUMBER - 10 PAGF REVISION NO. PAGE REVISION NO. PAGE REVISION NO.

PAGE REVISION NO. PAGE B 3.6.6-1 ................................... 0 B 3.7.4-5 ................................... 0 B 3.7.14-4 ................................. 0 B 3.6.6-2 ................................... 0 B 3.7.5-1 ................................... 0 B 3.7.15-1 ................................. 0 B 3.6.6-3 ................................... 5 B 3.7.5-2 ................................... 0 B 3.7.15-2 ................................. 0 B 3.6.6-4 ................................... 8 B 3.7.5-3 ................................... 0 B 3.7.15-3 ................................. 0 B 3.6.6-5 ................................... 8 B 3.7.5-4 ................................... 0 B 3.7.154 ................................. 0 B 3.6.6-6 ................................... 8 B 3.7.5-5 ................................... 0 B 3.7.16-1 ...................................... 5 B 3.6.6-7 ................................... 8 B 3.7.5-6 ................................... 0 B 3.7.16-2 ................................. 0 B 3.6.6-8 ................................... 8 B 3.7.5-7 ................................... 0 B 3.7.16-3 ................................. 0 B 3.6.6-9 ................................... 8 B 3.7.5-8 ................................... 0 Section B 3.8 Tab B 3.6.6-10 ................................. 8 B 3.7.5-9 ................................... 0 B 3.8.1-1 ................................... 0 B 3.6.6-11 ................................. 8 B 3.7.5-10 ................................. 0 B 3.8.1-2 .................................... 0 B 3.6.7-1 ................................... 0 B 3.7.6-1 ................................... 0 B 3.8.1-3 .................................... 0 B 3.6.7-2 ................................... 0 B 3.7.6-2 ................................... 0 B 3.8.1-4 .................................... 0 B 3.6.7-3 ................................... 0 B 3.7.6-3 ................................... 0 B 3.8.1-5 ................................... 0 B 3.6.7-4 ................................... 0 B 3.7.6-4 ................................... 0 B 3.8.1-6 ................................... 0 B 3.6.7-5 ................................... 0 B 3.7.7-1 ................................... 0 B 3.8.1-7 ................................... 0 B 3.6.7-6 ................................... 0 B 3.7.7-2 ................................... 0 B 3.8.1-8 ................................... 0 B 3.6.8-1 ................................... 0 B 3.7.7-3 ................................... 0 B 3.8.1-9 ................................... 0 B 3.6.8-2 ................................... 0 B 3.7.7-4 ................................... 0 B 3.8.1-10 ................................. 0 B 3.6.8-3 ................................... 0 B 3.7.7-5 ................................... 0 B 3.8.1-11 ................................. 0 B 3.6.8-4 ................................... 0 B 3.7.8-1 ................................... 0 B 3.8.1-12 ................................. 0 B 3.6.8-5 ................................... 4 B 3.7.8-2 ................................... 0 B 3.8.1-13 ................................. 0 B 3.6.9-1 ................................... 0 B 3.7.8-3 ................................... 0 B 3.8.1-14 ................................. 0 B 3.6.9-2 ................................... 0 B 3.7.84 ................................... 0 B 3.8.1-15 ................................. 0 B 3.6.9-3 ................................... 0 B 3.7.8-5 ................................... 0 B 3.8.1-16 ................................. 0 B 3.6.94 ................................... 4 B 3.7.9-1 ................................... 0 B 3.8.1-17 ................................. 0 Section B 3.7 Tab B 3.7.9-2 ................................... 0 B 3.8.1-18 ................................. 0 B 3.7.1-1 ................................... 0 B 3.7.9-3 ................................... 0 B 3.8.1-19 ................................. 0 B 3.7.1-2 ................................... 0 B 3.7.10-1 ................................. 0 B 3.8.1-20 ................................. 0 B 3.7.1-3 ................................... 0 B 3.7.10-2 ................................. 0 B 3.8.1-21 ................................. 0 B 3.7.14 ................................... 0 B 3.7.10-3 ................................. 0 B 3.8.1-22 ................................. 0 B 3.7.1-5 ................................... 0 B 3.7.104 ................................. 0 B 3.8.1-23 ...................................... 0 B 3.7.1-6 ................................... 0 B 3.7.10-5 ................................. 0 B 3.8.1-24 ................................. 0 B 3.7.1-7 ................................... 0 B 3.7.10-6 ................................. 0 B 3.8.1-25 ................................. 0 B 3.7.2-1 ................................... 0 B 3.7.11-1 ................................. 0 B 3.8.1-26 ................................. 0 B 3.7.2-2 ................................... 0 B 3.7.11-2 ................................. 0 B 3.8.1-27 ................................. 0 B 3.7.2-3 ................................... 0 B 3.7.11-3 ................................. 0 B 3.8.1-28 ................................. 0 B 3.7.24 ................................... 0 B 3.7.11-4 ................................. 0 B 3.8.1-29 ................................. 0 B 3.7.2-5 ................................... 0 B 3.7.12-1 ................................. 0 B 3.8.2-1 ................................... 0 B 3.7.2-6 ................................... 0 B 3.7.12-2 ................................. 0 B 3.8.2-2 .................................... 0 B 3.7.2-7 ................................... 0 B 3.7.12-3 ................................. 0 B 3.8.2-3 .................................... 0 B 3.7.3-1 ................................... 0 B 3.7.12-4 ................................. 0 B 3.8.2-4 .................................... 0 B 3.7.3-2 ................................... 0 B 3.7.12-5 ................................. 0 B 3.8.2-5 .................................... 0 B 3.7.3-3 ................................... 0 B 3.7.12-6 ................................. 0 B 3.8.2-6 .................................... 0 B 3.7.34 ................................... 0 B 3.7.13-1 ................................. 0 B 3.8.3-1 ................................... 0 B 3.7.3-5 ................................... 0 B 3.7.13-2 ................................. 0 B 3.8.3-2 .................................... 0 B 3.7.3-6 ................................... 0 B 3.7.13-3 ................................. 0 B 3.8.3-3 .................................... 0 B 3.7.4-1 ................................... 0 B 3.7.14-1 ................................. 0 B 3.8.34 .................................... 0 B 3.7.4-2 ................................... 0 B 3.7.14-2 ................................. 0 B 3.8.3-5 .................................... 0 B 3.7.4-3 ................................... 0 B 3.7.14-3 ................................. 0 B 3.8.3-6 .................................... 0 B 3.7.4-4 ................................... 0 Page 4 of 5

UNIT 1 AND UNIT 2 FNP TECHNICAL SPECIFICATIONS (TS) BASES LIST OF EFFECTIVE PAGES THIS LIST IS CURRENT THROUGH- REVISION NUMBER -10 PAGF REVISION NO. NO. PAGE REVISION NO. PAGE REVISION NO.

PAGE REVISION B 3.8.3-7 ................................... 0 B 3.9.1-4 ................................. 0 B 3.8.4-1 ................................... 0 B 3.9.2-1 ................................... 3 B 3.8.4-2 ................................... 0 B 3.9.2-2 ................................... 3 B 3.8.4-3 ................................... 0 B 3.9.2-3 ................................... 3 B 3.8.4-4 ................................... 0 B 3.9.2-4 ................................. 3 B 3.8.4-5 ................................... 0 B 3.9.2-5 ................................... 3 B 3.8.4-6 ................................... 0 B 3.9.3-1 ................................... 0 B 3.8.4-7 ................................... 0 B 3.9.3-2 ................................. 0 B 3.8.4-8 ................................... 0 B 3.9.3-3 ................................... 0 B 3.8.4-9 ................................... 0 B 3.9.3-4 ................................. 0 B 3.8.4-10 ................................. 0 B 3.9.3-5 ................................... 4 B 3.8.4-11 ................................ 0 B 3.9.4-1 ................................... 0 B 3.8.5-1 ................................... 0 B 3.9.4-2 ................................... 0 B 3.8.5-2 ................................... 0 B 3.9.4-3 ................................... 0 B 3.8.5-3 ................................... 0 B 3.9.44 ................................. 0 B 3.8.5-4 ................................... 0 B 3.9.5-1 ................................... 0 B 3.8.6-1 ................................... 0 B 3.9.5-2 ................................. 0 B 3.8.6-2 ................................... 0 B 3.9.5-3 ................................... 0 B 3.8.6-3 ................................... 0 B 3.9.5-4 ................................. 0 B 3.8.6-4 ................................... 0 B 3.9.6-1 ................................... 0 B 3.8.6-5 ................................... 0 B 3.9.6-2 ................................. 0 B 3.8.6-6 ................................... 0 B 3.9.6-3 ................................. 0 B 3.8.6-7 ................................... 0 B 3.8.7-1 ................................... 0 B 3.8.7-2 ................................... 0 B 3.8.7-3 ................................... 0 B 3.8.74 ................................... 0 B 3.8.8-1 ................................... 0 B 3.8.8-2 ................................... 0 B 3.8.8-3 ................................... 0 B 3.8.84 ................................... 0 B 3.8.9-1 ................................... 0 B 3.8.9-2 ................................... 0 B 3.8.9-3 ................................... 0 B 3.8.9-4 ................................... 0 B 3.8.9-5 ................................... 0 B 3.8.9-6 ................................... 0 B 3.8.9-7 ................................... 0 B 3.8.9-8 ................................... 0 B 3.8.9-9 ................................... 0 B 3.8.9-10 ................................. 0 B 3.8.10-1 ................................ 0 B 3.8.10-2 ................................. 0 B 3.8.10-3 ................................. 0 B 3.8.10-4 ................................. 0 B 3.8.10-5 ................................. 0 Section B 3.9 Tab B 3.9.1-1 ................................... 0 B 3.9.1-2 ................................... 0 B 3.9.1-3 ................................... 0 Page 5 of 5

Reactor Core SLs B 2.1.1 B 2.0 SAFETY LIMITS (SLs)

B 2.1.1 Reactor Core SLs BASES BACKGROUND GDC 10 (Ref. 1) requires that specified acceptable fuel design limits are not exceeded during steady state operation, normal operational transients, and anticipated operational occurrences (AOOs). This is accomplished by having a departure from nucleate boiling (DNB) design basis, which corresponds to a 95% probability at a 95%

confidence level (the 95/95 DNB criterion) that DNB will not occur on the limiting fuel rod and by requiring that fuel centerline temperature stays below the melting temperature.

The restrictions of this SL prevent overheating of the fuel and cladding, as well as possible cladding perforation, that would result in the release of fission products to the reactor coolant. Overheating of the fuel is prevented by maintaining the steady state peak linear heat rate (LHR) below the level at which fuel centerline melting occurs.

Overheating of the fuel cladding is prevented by restricting fuel operation to within the nucleate boiling regime, where the heat transfer coefficient is large and the cladding surface temperature is slightly above the coolant saturation temperature.

Fuel centerline melting occurs when the local LHR, or power peaking, in a region of the fuel is high enough to cause the fuel centerline temperature to reach the melting point of the fuel. Expansion of the pellet upon centerline melting may cause the pellet to stress the cladding to the point of failure, allowing an uncontrolled release of activity to the reactor coolant.

Operation above the boundary of the nucleate boiling regime could result in excessive cladding temperature because of the onset of DNB and the resultant sharp reduction in heat transfer coefficient. Inside the steam film, high cladding temperatures are reached, and a cladding water (zirconium water) reaction may take place. This chemical reaction results in oxidation of the fuel cladding to a structurally weaker form. This weaker form may lose its integrity, resulting in an uncontrolled release of activity to the reactor coolant.

The proper functioning of the Reactor Protection System (RPS) and main steam safety valves prevents violation of the reactor core SLs.

Farley Units 1 and 2 B 2. 1.1 -1 Revision 0

Reactor Core SLs B 2.1.1 BASES APPLICABLE The fuel cladding must not sustain damage as a result of normal SAFETY ANALYSES operation and AQOs. The reactor core SLs are established to preclude violation of the following fuel design criteria:

a. There must be at least 95% probability at a 95% confidence level (the 95/95 DNB criterion) that the hottest fuel rod in the core does not experience DNB; and

b. The hottest fuel pellet in the core must not experience centerline fuel melting.

In meeting the DNB design criterion, uncertainties in plant operating parameters, nuclear and thermal parameters, fuel fabrication parameters, and computer codes must be considered. As described in the FSAR, the effects of these uncertainties have been statistically combined with the correlation uncertainty to determine design limit DNBR values that satisfy the DNB design criterion.

Additional DNBR margin is maintained by performing the safety analyses to a higher DNB limit. This margin between the design and safety analysis limit DNBR values is used to offset known DNBR penalties (e.g., rod bow and transition core) and to provide DNBR margin for operating and design flexibility.

The Reactor Trip System Functions (Ref. 2), in combination with all the LCOs, are designed to prevent any anticipated combination of transient conditions (i.e., resulting from a Condition I or II event) for Reactor Coolant System (RCS) temperature, pressure, flow, Al and THERMAL POWER level that would result in a departure from nucleate boiling ratio (DNBR) of less than the DNBR limit and preclude the existence of flow instabilities.

Automatic enforcerment of khese reactor core SLs is provided by appropriate operation of the RPS and the steam generator safety valves.

The SLs represent a design requirement for establishing the RPS trip setpoints identified previously. LCO 3.4.1, "RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB)

Limits," or the assumed initial conditions of the safety analyses provide more restrictive limits to ensure that the SLs are not exceeded.

Farley Units 1 and 2 B 21 ý1-2 Revision 10

Reactor Core SLs B 2.1.1 BASES SAFETY LIMITS The reactor core SLs are established to preclude violation of the following fuel design criteria:

a. There must be at least 95% probability at a 95% confidence level (the 95/95 DNB criterion) that the hottest fuel rod in the core does not experience DNB; and

b. The hottest fuel pellet in the core must not experience centerline fuel melting.

The reactor core SLs are used to define the various RPS functions such that the above criteria are satisfied during steady state operation, normal operational transients, and anticipated operational occurrences (AOOs). To ensure that the RPS precludes the violation of the above criteria, additional criteria are applied to the Overtemperature and Overpower AT reactor trip functions. That is, it must be demonstrated that the average enthalpy in the hot leg is less than or equal to the saturation enthalpy and the core exit quality is within the limits defined by the DNBR correlation. Appropriate functioning of the RPS ensures that for variations in the THERMAL POWER, RCS pressure, RCS average temperature, RCS flow rate, and Al that the reactor core SLs will be satisfied during steady state operations, normal operational transients, and AOOs.

APPLICABILITY SL 2.1.1 only applies in MODES 1 and 2 because these are the only.

MODES in which the reactor is critical. Automatic protection functions are required to be OPERABLE during MODES 1 and 2 to ensure operation within the reactor core SLs. The main steam safety valves or automatic protection actions serve to prevent RCS heatup to the reactor core SL conditions or to initiate a reactor trip function, which forces the unit into MODE 3, Setpoints for the reactor trip functions are specified in LCO 3.3.1, "Reactor Trip System (RTS)

Instrumentation." In MODES 3, 4, 5, and 6, Applicability is not required since the reactor is not generating significant THERMAL POWER.

SAFETY LIMIT If SL 2.1.1 is violated, the requirement to go to MODE 3 places the VIOLATIONS unit in a MODE in which this SL is not applicable.

The allowed Completion Time of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months recognizes the importance of bringing the unit to a MODE of operation where this SL is not applicable, and reduces the probability of fuel damage.

.B 2.1.1-3 Revision 10 Farley Units 1 and 2

Reactor Core SLs 3i 2.1.1 BASES REFERENCES 1. 10 CFR 50, Appendix A, GDC 10.

2. FSAR, Section 7.2.

Farley Units 1 and 2 B 2.1.1-4 Revision 10

RCS Pressure, Temperature, and Flow DNB Limits B 3.4.1 B 3.4 REACTOR COOLANT SYSTEM (RCS)

B 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits BASES BACKGROUND These Bases address requirements for maintaining RCS pressure, temperature, and flow rate within limits assumed in the safety analyses. The safety analyses (Ref. 1) of normal operating conditions and anticipated operational occurrences assume initial conditions within the normal steady state envelope. The limits placed on RCS pressure, temperature, and flow rate ensure that the minimum departure from nucleate boiling ratio (DNBR) will be met for each of the transients analyzed.

The RCS pressure limit is consistent with operation within the nominal operational envelope. Pressurizer pressure indications are averaged to come up with a value for comparison to the limit. The indicated limit is based on the average of two control board readings. A lower pressure will cause the reactor core to approach DNB limits.

The RCS coolant average temperature limit is consistent with full power operation within the nominal operational envelope. Indications of temperature are averaged to determine a value for comparison to the limit. The indicated limit is based on the average of two control board readings. A higher average temperature will cause the core to approach DNB limits.

The RCS flow rate normally remains constant during an operational fuel cycle with all pumps running. The minimum RCS flow limit corresponds to that assumed for DNB analyses. A lower RCS flow will cause the core to approach DNB limits.

Operation for significant periods of time outside these DNB limits increases the likelihood of a fuel cladding failure in a DNB limited event.

APPLICABLE The requirements of this LCO represent the initial conditions for DNB SAFETY ANALYSES limited transients analyzed in the plant safety analyses (Ref. 1). The safety analyses have shown that transients initiated from the limits of this LCO will result in meeting the DNB design criterion throughout (continued)

Farley Units 1 and 2 B 3.4.1 -1 Revision 0

RCS Pressure, Temperature, and Flow DNB Limits B 3.4.1 BASES APPLICABLE each analyzed transient. This is the acceptance limit for the RCS DNB SAFETY ANALYSES parameters. Changes to the unit that could impact these parameters (continued) must be assessed for their impact on the DNBR criteria. The transients analyzed for include loss of coolant flow events and dropped or stuck rod events. A key assumption for the analysis of these events is that the core power distribution is within the limits of LCO 3.1.6, "Control Bank Insertion Umits"; LCO 3.2.3, "AXIAL FLUX DIFFERENCE (AFD)"; and LCO 3.2.4, "QUADRANT POWER TILT RATIO (QPTR)."

The pressurizer pressure limit and the RCS average temperature limit specified in the COLR correspond to analytical limits used in the safety analyses, with allowance for measurement uncertainty.

The RCS DNB parameters satisfy Criterion 2 of 10 CFR 50.36(c)(2)(ii).

LCO This LCO specifies limits on the monitored process variables pressurizer pressure, RCS average temperature, and RCS total flow rate -to ensure the core operates within the limits assumed in the safety analyses. Operating within these limits will result in meeting the DNB design criterion in the event of a DNB limited transient.

RCS total flow rate is based on two elbow tap measurements from each loop and contains a measurement error of 2.3% based on Ap measurements from the cold leg elbow taps, which are correlated to past precision heat balance measurements or performing a precision heat balance at the beginning of the current cycle. Potential fouling of the feedwater venturi, which might not be detected, could bias the result from the precision heat balance in a nonconservative manner.

Therefore, a penalty of 0.1% for undetected fouling of the feedwater ventud raises the rnominal flow measurement allowance to 2.4%.

Any fouling that might-bias the flow rate measurement greater than 0.1% can be detected by monitoring and trending various plant performance parameters. If detected, action shall be taken before performing subsequent precision heat balance measurements, i.e.,

either the effect of the fouling shall be quantified and compensated for in the RCS flow rate measurement or the venturi shall be cleaned to eliminate the fouling.

Farley Units 1 and 2 B 3.4,i-2 Revision 10

RCS Pressure, Temperature, and Flow DNB Limits B 3.4.1 BASES APPLICABILITY In MODE 1, the limits on pressurizer pressure, RCS coolant average temperature, and RCS flow rate must be maintained during steady state operation in order to ensure DNBR criteria will be met in the event of an unplanned loss of forced coolant flow or other DNB limited transient. In all other MODES, the power level is low enough that DNB is not a concern.

A Note has been added to indicate the limit on pressurizer pressure is not applicable during short term operational transients such as a THERMAL POWER ramp > 5% RTP per minute or a THERMAL POWER step > 10% RTP. These conditions represent short term perturbations where actions to control pressure variations might be counterproductive. Also, since they represent transients initiated from power levels < 100% RTP, an increased DNBR margin exists to offset the temporary pressure variations.

The DNBR limit on DNB related parameters is provided in SL 2.1.1, "Reactor Core SLs." The conditions that define the DNBR limit are less restrictive than the limits of this LCO, but violation of a Safety Limit (SL) merits a stricter, more severe Required Action. Should a violation of this LCO occur, the operator must check whether or not an SL may have been exceeded.

ACTIONS A.1 RCS pressure and RCS average temperature are controllable and measurable parameters. With one or both of these parameters not within LCO limits, action must be taken to restore parameter(s).

RCS total flow rate is not a controllable parameter and is not expected to vary during steady state operation. If the indicated RCS total flow rate is below the LCO limit, power must be reduced, as required by Required Action B.1, to restore DNB margin and eliminate the potential for violation of the accident analysis bounds.

The 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Completion Time for restoration of the parameters provides sufficient time to adjust plant parameters, to determine the cause for the off normal condition, and to restore the readings within limits, and is based on plant operating experience.

(continued)

Farley Units 1 and 2 B 3.4.1-3 Revision lo

RCS Pressure, Temperature, and Flow DNB Limits B 3.4.1 BASES ACTIONS B.1 (continued)

If Required Action A.1 is not met within the associated Completion Time, the plant must be brought to a MODE in which the LCO does not apply. To achieve this status, the plant must be brought to at least MODE 2 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . In MODE 2, the reduced power condition eliminates the potential for violation of the accident analysis bounds.

The Completion Time of 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months is reasonable to reach the required plant conditions in an orderly manner.

SURVEILLANCE SR 3.4.1.1 REQUIREMENTS Since Required Action A.1 allows a Completion Time of 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to restore parameters that are not within limits, the 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Surveillance Frequency for pressurizer pressure is sufficient to ensure the-pressure can be restored to a normal operation, steady state condition following load changes and other expected transient operations. The 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months interval has been shown by operating practice to be sufficient to regularly assess for potential degradation and to verify operation is within safety analysis assumptions.

SR 3.4.1.2 Since Required Action A.1 allows a Completion Time of 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to restore parameters that are not within limits, the 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Surveillance Frequency for RCS average temperature is sufficient to ensure the temperature can be restored to a normal operation, steady state condition following load changes and other expected transient operations. The 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months interval has been shown by operating practice to be sufficient to regularly assess for potential degradation and to verify operation is within safety analysis assumptions.

SR 3.4.1.3 The 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Surveillance Frequency for RCS total flow rate is a qualitative verification performed using the installed flow indicators on the main control board fed by elbow tap measurements. The 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months interval has been shown by operating practice to be sufficient to regularly assess potential significant flow degradation and to verify operation within safety analysis assumptions.

(continued)

Farley Units 1 and 2 B 3.4.1-4 Revision 0

JOSEPH M. FARLEY NUCLEAR PLANT CORE OPERATING LIMITS REPORT UNIT 1 - CYCLE 18 DECEMBER 2001 REVISION 1 APPROVED FOR ISSUE:

OPERATIONS MANAGER DATE

k CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 18 DECEMBER 2001 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for FNP UNIT 1 CYCLE 18 has been prepared in accordance with the requirements of Technical Specification 5.6.5.

The Technical Requirement affected by this report is listed below:

13.1.1 SHUTDOWN MARGIN - MODES 1 and 2 (with kar> 1)

The Technical Specifications affected by this report are listed below:

2.1.1 Reactor Core Safety Limits for THERMAL POWER 3.1.1 SHUTDOWN MARGIN - MODES 2 (with kfr < 1), 3, 4 and 5 3.1.3 Moderator Temperature Coefficient 3.1.5 Shutdown Bank Insertion Limits 3.1.6 Control Bank Insertion Limits 3.2.1 Heat Flux Hot Channel Factor - FQ(Z) 3.2.2 Nuclear Enthalpy Rise Hot Channnel Factor - F; 3.2.3 Axial Flux Difference 3.3.1 Reactor Trip System Instrumentation Overtemperature AT (OTAT) and Overpower AT (OPAT) Setpoint Parameter Values for Table 3.3.1-1 3.4.1 RCS DNB Parameters for Pressurizer Pressure, RCS Average Temperature, and RCS Total Flow Rate 3.9.1 Boron Concentration Page 1 of 15

k CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 18 DECEMBER 2001 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the following subsections. These limits have been developed using NRC-approved methodologies, including those specified in Technical Specification 5.6.5.

2.1 SHUTDOWN MARGIN - MODES I AND 2 (with kf_ 1.0) (Technical Requirement 13.1.1) 2.1.1 The SHUTDOWN MARGIN shall be greater than or equal to 1.77 percent Ak/k.

2.2 SHUTDOWN MARGIN - MODES 2 (with km < 1.0). 3.4 and 5 (Specification 3.1.1) 2.2.1 Modes 2 (kfr < 1.0), 3 and 4 - The SHUTDOWN MARGIN shall be greater than or equal to 1.77 percent Ak/k.

2.2.2 Mode 5 - The SHUTDOWN MARGIN shall be greater than or equal to 1.0 percent Ak/k.

2.3 Moderator Temnerature Coefficient (Specification 3.1.3) 2.3.1 The Moderator Temperature Coefficient (MTC) limits are:

The BOL/ARO/HZP-MTC shall be less than or equal to +0.7 x 10"4 Ak/k/F for power levels up to 70 percent RTP with a linear ramp to 0 Ak/k/*F at 100 percent RTP.

The EOL/ARO/RTP-MTC shall be less negative than -4.3 x 10 Ak/k/IF.

2.3.2 The MTC Surveillance limits are:

The 300 ppm/ARO/RTP-MTC should be less negative than or equal to

-3.65 x 10-4 Ak/k/F.

The 100 ppm/ARO/RTP-MTC should be less negative than -4.0x 104 Ak/k/ 0 F.

where: BOL stands for Beginning of Cycle Life ARO stands for All Rods Out HZP stands for Hot Zero THERMAL POWER EOL stands for End of Cycle Life RTP stands for RATED THERMAL POWER Page 2 of 15

,L OPERATING LIMITS REPORT. FNP UNIT 1 CYCLE 18 CORE AMCCL DECEMBER 2001 2.4 Shutdown Bank Insertion Limits (Specification 3.1.5) 2.4.1 The shutdown banks shall be withdrawn to a position greater than or equal to 225 steps.

2.5 Control Bank Insertion Limits (Specification 3.1.6) 2.5.1 The control rod banks shall be limited in physical insertion as shown in Figure 1.

2.6 Heat Flux Hot Channel Factor - FQ(Z) (Specification 3.2.1)

FRTP 2.6.1 FQ(Z)*<g

K(Z) for P > 0.5 P

FRTP FQ(Z)* Q *K(Z) for P:5 0.5 0.5 THERMALPOWER where: P=

RA TED THERMALPO WER 2.6.2 FRT =2.50 2.6.3 K(Z) is provided in Figure 2.

FQ(Z) <F*

K(Z) 2.6.4 forP > 0.5 FP *KW(Z)

FQ(Z) F 0.5

K(Z) forP*_< 0.5 0.5 *W(Z) 2.6.5 W(Z) values are provided in Figures 4 through 7.

2.6.6 The FQ (Z) penalty factors are provided in Table 1.

Page 3 of 15

SCORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 18 DECEMBER 2001 2.7 Nuclear Enthalpy Rise Hot Channel Factor - Fv (Specification 3.2.2) 2.7.1 FN, <FRTh*(I + PFw *(- P))

where: P= THERMAL POWER RATED THERMAL POWER 2.7.2 F;T=1.70 2.7.3 PFAf =0.3 2.8 Axial Flux Difference (Specification 3.2.3) 2.8.1 The Axial Flux Difference (AFD) acceptable operation limits are provided in Figure 3.

2.9 Boron Concentration (Specification 3.9.1) 2.9.1 The boron concentration shall be greater than or equal to 2000 ppm.

2.10 Reactor Core Safety Limits for THERMAL POWER (Specification 2.1.1) 2.10.1 In MODES 1 and 2, the combination of THERMAL POWER, Reactor Coolant System (RCS) highest loop average temperature, and pressurizer pressure shall not exceed the safety limits specified in Figure 8.

2.11 Reactor Trip System Instrumentation Overtemperature AT (OTAT) and Overpower AT (OPAT)

Setpoint Parameter Values for Table 3.3.1-1 (Specification 3.3.1) 2.11.1 The Reactor Trip System Instrumentation Overtemperature AT (OTAT) and Overpower AT (OPAT) Setpoint Parameter Values for TS Table 3.3.1-1 are listed in COLR Tables 2 and 3.

2.12 RCS DNB Parameters for Pressurizer Pressure, RCS Average Temperature, and RCS Total Flow Rate (Specification 3.4.1) 2.12.1 RCS DNB Parameters for Pressurizer Pressure, RCS Average Temperature and RCS Total Flow Rate shall be within the limits specified below:

a. Pressurizer pressure > 2209 psig;

b. RCS average temperature < 580.3°F; and

c. The minimum RCS total flow rate shall be> 263,400 GPM when using the precision heat balance method and > 264,200 GPM when using the elbow tap method.

This concentration bounds the condition of kfr_< 0.95 (all rods in less the most reactive rod) and subcriticality (all rods out) over the entire cycle. This concentration includes additional boron to address uncertainties and B'° depletion.

Page 4 of 15

CYCLE 18 DECEMBER 2001 CORE OPERATING LIMITS REPORT, FNP UNIT 1 Table 1 FQ(Z) PENALTY FACTOR Cycle FQ(Z)

Burnup Penalty (MWD/MTU) Factor 4644 1.020 4848 1.023 5052 1.021 5256 1.020 Notes:

with SR 3.2.1.2, is the maximum factor by

1. The Penalty Factor, to be applied to FQ(Z) in accordance (surveillance interval of 31 EFPD plus the which FQ(Z) is expected to increase over a 39 EFPD interval interval per SR 3.0.2) starting from maximum allowable extension not to exceed 25% of the surveillance the burnup at which the FQ(Z) was determined.

2. Linear interpolation is adequate for intermediate cycle bumups.

penalty factor of 1.020 shall be used.

3. For all cycle burnups outside the range of the table, a Page 5 of 15

1 CYCLE 18 DECEMBER 2001 S CORE OPERATING LIMITS REPORT, FNP UNIT Table 2 Reactor Trip System Instrumentation - Overtemperature AT (OTAT)

Setpoint Parameter Values T' _<577.20 F F = 2235 psig K1 = 1.17 K(2 = 0.017/°F K3 = 0.000825/psi tj Ž 30 sec "t2 *-4 sec T6 - 6 sec

=0sec x - 6 sec T4 fi(AI) = -2.48 {23 + (qt - qb)} 7hen (qt - qb) < -23 % RTP 0% of RTP ihen -23% RTP < (qt - qb)

15% RTP vhen (qt - qb) > 15% RTP 2.05 {(qt - qb) - 15)

Page 6 of 15

SCORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 18 DECEMBER 2001 Table 3 Reactor Trip System Instrumentation - Overpower AT (OPAT)

Setpoint Parameter Values T" _< 577.2 0F Ks5 = 0.02/°F for increasing Tavg K6 = 0.00109/°F when T > T" K4 = 1.10 K6 = 0/OF when T _<T" Ks = 0/°F for decreasing Tavg t3 Ž 10 Sec T4 =0sec C5 < 6 sec T6 -<6 sec f 2(AI) = 0% RTP for all Al Page 7 of 15

1 CYCLE 18 DECEMBER 2001 CORE OPERATING LIMITS REPORT. FNP UNIT Figure 1 Rod Bank Insertion Limits versus Rated Thermal Power Fully Withdrawn - 225 to 231 steps, inclusive 2251 200 175 io

150.

". 125 0

0 100

".0 75 50 25 0.5 0.6 0.7 0.8 0.9 1.0 0.0 0.1 0.2 0.3 0.4 Fraction of Rated Thermal Power rods are at a position within the interval > 225 and Fully Withdrawn shall be the condition where control

< 231 steps withdrawn.

control bank withdrawal sequence A, B, C, D and a Note: The Rod Bank Insertion Limits are based on the control bank tip-to-tip distance of 128 steps.

Page 8 of 15

CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 18 DECEMBER 2001 Figure 2 K(Z) - Normalized FQ(Z) as a Function of Core Height 1.2 1_

0 U0.8 co 0.6 0.

N 0.64 0.2 0

0 2 4 6 8 10 12 Core Height (feet)

Page 9 of 15

SCORE OPERATING LIMITS REPORT._FNP UNIT 1 CYCLE 18 DECEMBER 2001 Figure 3 Axial Flux Difference Limits as a Function of Rated Thermal Power for RAOC 120 110 100 90 80 E

0 0.

70 I

0 60 o-50 40 30 20 10 0

-30 -20 -10 0 10 20 30 40 50 40 Axial Flux Difference (Delta I) %

Page 10 of 15

k CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 18 DECEMBER 2001 Figure 4 RAOC W(Z) at 150 MWD/MTU 1.60 Axial Eleva"in BOL Point feet W(Z) 1 12.00 1.0000 2 11.80 1.0000 3 11.60 1.0000 4 11.40 1.0000 5 11.20 1.0000

6 11.00 1.0000 7 10.80 1.0000 1.50

8 10.60 1.0000 9 10.40 1.0000 10 10.20 1.0000 11 10.00 1.2141 12 9.80 1.2076 13 9.60 1.2024 14 9.40 1.1975 15 9.20 1.1911 16 9.00 1.1812 1.40 1.1783 17 8.80 18 8.60 1.1871 A 19 8.40 1.1982 20 8.20 1.2069 21 8.00 1.2134 22 7.80 1.2178 23 7.60 1.2201 24 7.40 1.2205 25 7.20 1.2201 26 7.00 1.2186 27 6.80 1.2156 28 6.60 1.2111 29 6.40 1.2055 30 6.20 1.1989 31 6.00 1.1908 32 5.80 1.1840 33 5.60 1.1848 1.20 1.1951 34 5.40 35 5.20 1.2068 36 5.00 1.2180 37 4.80 1.2287 38 4.60 1.2383 39 4.40 1.2470 40 4.20 1.2546 41 4.00 1.2609 42 3.80 1.2661 43 3.60 1.2698 44 3.40 1.2734 45 3.20 1.2819 46 3.00 1.2905 47 2.80 1.3072 48 2.60 1.3353 49 240 1.3624

- - - - - - 50 2.20 1.3892 1.00-----

51 2.00 1.4156 0 2 4 6 8 10 12

52 1.80 1.0000 Core Height (feet) - 53 1.60 1.0000

54 1.40 1.0000

55 1.20 1.0000

56 1.00 1.0000

57 0.80 1.0000

58 0.60 1.0000 a 59 0.40 1.0000

60 0.20 1.0000 a 61 0.00 1.0000 This figure is referred to by Technical Specification B3.2. 1.

Top and Bottom 15% Excluded per Technical Specification B3.2.1.

Page 11 of 15

4. CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 18 DECEMBER 2001 Figure 5 RAOC W(Z) at 4000 MWDIMTU Elevation MOL-!

Poit! (feet)

12.00 W(Z) 1.0000 a 2 11.80 1.TO0000 11 60 I Mm}0 1.60

4 11.40 1.0000

5 11.20 1.0000

6 11.00 1.0000

7 10.80 1.0000

8 10.60 1.0000

9 10.40 1.0000

10 10.20 1.0000 I1 10.00 1.2512 1.50 12 9.80 1.2412 13 9.60 1.2303 14 9.40 1.2185 15 9.20 1.2058 16 9.00 1.1931 17 8.80 1.1928 18 8.60 1.2049 19 8.40 1.2139 20 8.20 1.2205 1.40 21 8.00 1.2248 22 7.80 1.2268 23 7.60 1.2266 24 7.40 1.2243 25 7.20 1.2208 26 7.00 1.2158 27 6.80 1.2093 28 6.60 1.2013 1.30 29 6.40 1.1921 30 6.20 1.1817 31 6.00 1.1708 32 5.80 1.1574 33 5.60 1.1479 34 5.40 1.1502 35 5.20 1.1569 36 5.00 1.1632 37 4.80 1.1687 1.20 38 4.60 1.1687 39 4.40 1.1775 40 4.20 1.1804 41 4.00 1.1826 42 3.80 1.1835 43 3.60 1.1842 44 3.40 1.1861 45 3.20 1.1866 1.10 46 3.00 1.1955 47 2,80 1.2119 48 2.60 1.2334 49 2.40 1.2557 50 2.20 1.2779 51 2.00 1.2997

52 1.80 1.0000

53 1.60 1.0000

54 1.40 1.0000 1.00

55 1.20 1.0000 0 2 4 6 8 10 12

56 1.00 1.0000

57 0.80 1.000 58 0.60 1.0000 Core Height (feet) *

59 0.40 0.20 1.0600 1.0000

60

61 0.00 1.0000

Top and Bottom 15% Excluded per Technical Specification B3.2. I.

This figure is referred to by Technical Specification B3.2.1.

Page 12 of 15

CYCLE 18 DECEMBER 2001

,k CORE OPERATING LIMITS REPORT. FNP UNIT 1 Figure 6 RAOC W(Z) at 10000 MWD/MTU Axial Elevrion MOL-2 Point fee) WZ 1 12.00 1.0000 2 11.80 1.0000 1.60]

-7 -7

-TF 3 11.60 1.0000 7 4 5

6 7

11-40 11.20 71.00 10.80 1.0000 1.0000 1.0000 1.0000 8 10.60 1.0000 9 10.40 1.0000 10 10.20 1.0000 1.50 11 10.00 1.2482 12 9.80 1.2377 13 9.60 1.2323 14 9.40 1.2262 15 9.20 1.2196 16 9.00 1.2116 17 8.80 1.2175 18 8.60 1.2297 19 8.40 1.2444 1.401 1.2561 20 8.20 21 8.00 1.2650 22 7.80 1.2712 23 7.60 1.2747 24 7.40 1.2755 25 7.20 1.2738 26 7.00 1.2707 N 1.30 27 6.80 1.2659 28 6.60 1.2590 29 6.40 1.2502 30 6.20 1.2397

/X 31 6.00 1.2280 32 5.80 1.2136 SA A 33 5.60 1.2007 34 5.40 1.1972

a 16 35 5.20 1.1965 F 36 5.00 1.1948 1.20 1.1918 37 4.80 38 4.60 1.1875 39 4.40 1.1821 40 4.20 1.1753 41 4.00 1.1685 42 3.80 1.1629 43 3.60 1.1595 1.10 44 3.40 1.1559 45 3.20 1.1517 46 3.00 1.1499 1.1559 47 2.80 48 2.60 1.1607 49 2.40 1.1680 50 2.20 1.1777 5T1 o 2.t 1.1876 T n52 1.80 1.0000 1.0000 1.00

53 1.60

54 1.40 1.0000 0 2 4 6 8 10 12

55 1.20 1.0000

56 1.00 1.0000 Core Height (feet)

57 0-80 1.0000

58 0.60 1.0000

59 0.40 1.0000

60 0.20 1.0000

ý 61 0.00 1.10000

Top and Bottom 15% Excluded per This figure is referred to by Technical Specification B3.2.1. Technical SpSeification B3.2.1I.

Page 13 of 15

DECEMBER 2001 CORE OPERATING LIN1TS REPORT, FNP UNIT 1 CYCLE 18 Figure 7 RAOC W(Z) at 18000 MWD/MTU Axial Elevation EOL Point fe W(Z)

1 12.00 1.0000 1.60

11.80 1.0000

3 I1.60 1.0000

4 11.40 1.0000

5 11.20 1.0000

6 1 1.00 1.0000

7 1080 1.0000

8 10.60 1.0000

9 10.40 1.0000

10 10.20 1.0000 11 10.00 1.2352 12 9.80 1.2287 13 9.60 1.2245 14 9.40 1.2216 15 9.20 1.2294 16 9.00 1.2499 17 8.80 1.2717 1.20 18 8.60 1.2897 1.30 19 8.40 1-3097 20 8.20 13289 21 8.00 1.3447 22 7.80 1.3564 23 7.60 1.3645 A 24 7.40 1.3688 A A 25 7.20 1.3696 26 7.00 1.3670 27 6.80 1.3614 28 6.60 1.3528 29 6.40 1.3417 30 6.20 13280 31 6.00 13125 32 5.30 1.2939 33 5.60 1.2754 34 5.40 1.2686 35 5.20 1.2662 36 5.00 1.2621 37 4.80 1.2559 38 4.60 1.2480 39 4.40 1.2387 40 4.20 1.2274 41 4.00 1.2143 42 3.80 1.1991 43 3.60 1.1850 44 3.40 1.1754 1.10 - - 45 3.20 1.1632 46 3.00 1.1628 47 2.80 1.1760 48 2.60 1.1930 49 2.40 1.2091 50 2.20 1.2248 51 2OO 1.2405

52 1.80 1.0000

53 1.60 1.0000

54 1.40 1.0000 0 2 A 4 8 10 12

55 1.20 1.0000

56 1.00 1.0000 Core Height (feet)

57 0.80 1.0000

58 0.60 1.0000

59 0.40 1.0000

60 0.20 1.0000

61 0.00 1.0000

Top and Bottom 15% Excluded per Technical Specification B3.2.1.

This figure is referred to by Technical Specification B3.2.1.

Page 14 of 15

SCORE LIESREOT DECEMBER 2001 CTINGOPERATN LIMITS REPOW FNP UNIT 1 CYCLE 18 Figure 8 Reactor Core Safety Limits 680 S!I IIII III 1 UNACCEPTABLE 660 640

--.- 2425 psig OPERATIONO 2235 psig

-- 1985 psig 620

-X- 1825 psig I T 60( I I 58(

561 0.0 0.2 0.4 0.6 0.8 1.0 1.2 Power (Fraction of Rated Thermal Power)

Page 15 of 15

JOSEPH M. FARLEY NUCLEAR PLANT CORE OPERATING LIMITS REPORT UNIT 2 - CYCLE 15 DECEMBER 2001 REVISION 1 APPROVED FOR ISSUE:

OPERATIONS MANAGER DATE

DECEMBER 2001 CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 15 1.0 CORE OPERATING LIMITS REPORT has been prepared in accordance This Core Operating Limits Report (COLR) for FNP UNIT 2 CYCLE 15 with the requirements of Technical Specification 5.6.5.

The Technical Requirement affected by this report is listed below:

13.1.1 SHUTDOWN MARGIN - MODES 1 and 2 (with kfr> 1)

The Technical Specifications affected by this report are listed below:

2.1.1 Reactor Core Safety Limits for THERMAL POWER 3.1.1 SHUTDOWN MARGIN -MODES 2 (with k~fr< 1), 3, 4 and 5 3.1.3 Moderator Temperature Coefficient 3.1.5 Shutdown Bank Insertion Limits 3.1.6 Control Bank Insertion Limits 3.2.1 Heat Flux Hot Channel Factor - FQ (Z) 3.2.2 Nuclear Enthalpy Rise Hot Channnel Factor - Fm 3.2.3 Axial Flux Difference Overpower AT 3.3.1 Reactor Trip System Instrumentation Overtemperature AT (OTAT) and (OPAT) Setpoint Parameter Values for Table 3.3.1-1 and RCS 3.4.1 RCS DNB Parameters for Pressurizer Pressure, RCS Average Temperature, Total Flow Rate 3.9.1 Boron Concentration Page 1 of 15

CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 15 DECEMBER 2001 A

2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the following subsections. These limits have been developed using NRC-approved methodologies, including those specified in Technical Specification 5.6.5.

2.1 SHUTDOWN MARGIN - MODES 1 AND 2 (with ke>__ 1.0) (Technical Requirement 13.1.1) 2.1.1 The SHUTDOWN MARGIN shall be greater than or equal to 1.77 percent Ak/k.

2.2 SHUTDOWN MARGIN - MODES 2 (with kz < 1.0), 3. 4 and 5 (Specification 3.1.1) 2.2.1 Modes 2 (kf < 1.0), 3 and 4 - The SHUTDOWN MARGIN shall be greater than or equal to 1.77 percent Ak/k.

2.2.2 Mode 5 - The SHUTDOWN MARGIN shall be greater than or equal to 1.0 percent Ak/k.

2.3 Moderator Temperature Coefficient (Specification 3.1.3) 2.3.1 The Moderator Temperature Coefficient (MTC) limits are:

0 The BOL/ARO/HZP-MTC shall be less than or equal to +0.7 x 10-4 k/k/ F for power 0

levels up to 70 percent RTP with a linear ramp to 0 Ak/k/ F at 100 percent RTP.

0 The EOL/ARO/RTP-MTC shall be less negative than -4.3 x I0-4 Ak/k/ F.

2.3.2 The MTC Surveillance limits are:

The 300 ppm/ARO/RTP-MTC should be less negative than or equal to

-3.65 x 10-4 Ak/k/OF.

The 100 ppm/ARO/RTP-MTC should be less negative than -4.0 x 1 0 -4 Ak/k/F.

where: BOL stands for Beginning of Cycle Life ARO stands for All Rods Out HZP stands for Hot Zero THERMAL POWER EOL stands for End of Cycle Life RTP stands for RATED THERMAL POWER Page 2 of 15

DECEMBER 2001 CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 15 2.4 Shutdown Bank Insertion Limits (Specification 3.1.5) 2.4.1 The shutdown banks shall be withdrawn to a position greater than or equal to 225 steps.

2.5 Control Bank Insertion Limits (Specification 3.1.6) 2.5.1 The control rod banks shall be limited in physical insertion as shown in Figure 1.

2.6 Heat Flux Hot Channel Factor - FQ (Z) (Specification 3.2. 1)

FQnrP 2.6.1 FQ(Z)*_<* Q

K(Z) for P > 0.5 P

T FRY FQ(Z) *_ Q *K(Z) forP5 0.5

0.5 where

P THERMALPOWER RATED THERMAL POWER 2.6.2 FRT" =2.50 2.6.3 K(Z) is provided in Figure 2.

2.6.4 FQ (Z) < F *K(Z) for P > 0.5 P

W(Z)

FRTP

K(Z) 0 FQ (Z) <* 0.5, W(Z) for P5<0.5 2.6.5 W(Z) values are provided in Figures 4 through 7.

2.6.6 The FQ (Z) penalty factors are provided in Table 1.

Page 3 of 15

CYCLE 15 DECEMBER 2001 CORE OPERATING LIMITS REPORT, FNP UNIT 2 2.7 Nuclear Enthalpv Rise Hot Channel Factor - FN, (Specification 3.2.2) 2.7.1 FN <_FRTP *(I÷PF,*(1-P))

THERMAL POWER P =

where:

RATED THERMAL POWER 2.7.2 F4R" =1.70 2.7.3 PFAH 0.3 2.8 Axial Flux Difference (Specification 3.2.3) 3.

2.8.1 The Axial Flux Difference (AFD) acceptable operation limits are provided in Figure 2.9 Boron Concentration (Specification 3.9.1) 2.9.1 The boron concentration shall be greater than or equal to 2000 ppm.

2.10 Reactor Core Safety Limits for THERMAL POWER (Specification 2.1.1) 2.10.1 In MODES I and 2, the combination of THERMAL POWER, Reactor Coolant System (RCS) highest loop average temperature, and pressurizer pressure shall not exceed the safety limits specified in Figure 8.

2.11 Reactor Trip System Instrumentation Overtemperature AT (OTAT) and Overpower AT (OPAT)

Setpoint Parameter Values for Table 3.3.1-1 (Specification 3.3.1) 2.11.1 The Reactor Trip System Instrumentation Overtemperature AT (OTAT) and Overpower AT (OPAT) setpoint parameter values for TS Table 3.3.1-1 are listed in COLR Tables 2 and 3.

2.12 RCS DNB Parameters for Pressurizer Pressure, RCS Average Temperature, and RCS Total Flow Rate (Specification 3.4.1) 2.12.1 RCS DNB parameters for pressurizer pressure, RCS average temperature and RCS total flow rate shall be within the limits specified below:

a. Pressurizer pressure > 2209 psig;

b. RCS average temperature < 580.3°F; and

c. The minimum RCS total flow rate shall be > 263,400 GPM when using the precision heat balance method and Ž 264,200 GPM when using the elbow tap method.

This concentration bounds the condition of k<ff* 0.95 (all rods in less the most reactive rod) and subcritieality (aj rods out) over the entire cycle. This concentration includes additional boron to address uncertainties and B10 depletion.

Page 4 of 15

DECEMBER 2001 k CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 15 Table 1 FQ(Z) PENALTY FACTOR Cycle FQ(Z)

Burnup Penalty (MWD/MTU) Factor 30 1.029 354 1.031 557 1.031 761 1.029 965 1.026 1372 1.020 4428 1.020 4632 1.021 4836 1.029 5040 1.038 5243 1.036 6262 1.020 Notes:

1. The Penalty Factor, to be applied to FQ(Z) in accordance with SR 3.2.1.2, is the maximum factor by which FQ(Z) is expected to increase over a 39 EFPD interval (surveillance interval of 31 EFPD plus the maximum allowable extension not to exceed 25% of the surveillance interval per SR 3.0.2) starting from the burnup at which the FQ(Z) was determined.

2. Linear interpolation is adequate for intermediate cycle bumups.

3. For all cycle burnups outside the range of the table, a penalty factor of 1.020 shall be used.

Page 5 of 15

DECEMBER 2001

.A CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 15 Table 2 Reactor Trip System Instrumentation - Overtemperature AT (OTAT)

Setpoint Parameter Limits T' _<577.2 0 F P = 2235 psig K1 = 1.17 K2 = 0.017/'F K3 = 0.000825/psi ci >30 sec T2 *54 sec T5 <6 sec T6 -*6 sec 4= 0 sec f1(AI) = -2.48 {23 + (qt - qb)} V vhen (qt - qb) < -23% RTP 0% of RTP Vvhen -23% RTP < (qt -qb)

15% RTP 2.05 {(qt- qb) - 151 vhen (qt - qb) > 15% RTP Page 6 of 15

15 DECEMBER 2001

.A CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE Table 3 Reactor Trip System Instrumentation - Overpower AT (OPAT)

Setpoint Parameter Values T" < 577.2 0 F K4 = 1.10 K5 = 0.02/'F for increasing Tavg K16 = 0.00109/IF when T > T" Ks = 0/°F for decreasing Tavg K6 = 0/°F when T _<T"

"-3 >10 sec T4 =0 sec

",5< 6 sec T6 < 6 sec f 2(AI) = 0% RTP for all Al Page 7 of 15

15 DECEMBER 2001

.A CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE Figure 1 Rod Bank Insertion Limits versus Rated Thermal Power Fully Withdrawn - 225 to 231 steps, inclusive 225 1 55 , 2ý5 11111 11 Jill 11 1111 H 200 I L04 I I (1 87)

ZI I I I L I LA I I 175 I I I LA B nkC-Iz I . .. I I LOO A I I I I I I I 1 101 11 150

.00 I I 1 110, I I lz I V I 101 1 1 111 'br I

. 125 0

000 (0"1114) 0 CL Bank D

'~75 I I I LOOO I I Yl IZI I s0 25 I I I 1 00`11 1 10, I I LOOT --

(.070, 0) 0 0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 Fraction of Rated Thermal Power Fully Withdrawn shall be the condition where control rods are at a position within the interval >_ 225 and

231 steps withdrawn.

Note: The Rod Bank Insertion Limits are based on the control bank withdrawal sequence A, B, C, D and a control bank tip-to-tip distance of 128 steps.

Page 8 of 15

4A CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 15 DECEMBER 2001 Figure 2 K(Z) - Normalized FQ(Z) as a Function of Core Height 1.2 1

0 o 0.8 U.

U.

C 0

"V 0.6 aN Core Heig~ht (ft.) K(Z E 0.000 1.000 L_

0 6.000 1.000 Z

12.000 1.000 N- 0.4

-___- FQ= 2.50 0.2

4. + I t t 0 i i i i I I 0 2 4 6 8 10 12 Core Height (feet)

Page 9 of 15

CYCLE 15 DECEMBER 2001

.A CORE OPERATING LIMITS REPORT, FNP UNIT 2 Figure 3 Axial Flux Difference Limits as a Function of Rated Thermal Power for RAOC 120 110

(-12, 100) (+9, 100) 100 Ss80 90 UNACCEPTABLE OPERATION 7 - - UNACCEPTABLE OPERATION a.

ACCEPTABLE E 70 OPERATION S

60

/- \

(U 0s "6SO

(-30, 50) (+24, 50)

40 30 20 -- - - - -- - - - --

10 0

-50 -40 -30 -20 -10 0 10 20 30 40 50 Axial Flux Difference (Delta I) %

Page 10 of 15

15 DECEMBER 2001

.A CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE Figure 4 RAOC W(Z) at 150 MWD/MTU I Axial Pnint I Elevation (feet'1 BOL W(Z)

I 12.00 1.0000

2 11.80 1.0000

3 11.60 1.0000 1.60

4 11.40 1.0000

5 11.20 1.0000

6 11.00 1.0000

7 10.80 1.0000

8 10.60 1.0000

9 10.40 1.0000

10 10.20 1.0000 I1 10.00 1.1830 1.50 12 9.80 1.1798 13 9.60 1.1780 14 9.40 1.1736 15 9.20 1.1682 16 9.00 1.1600 17 8.80 1.1582 18 8.60 1.1686 19 8.40 1.1813 20 8.20 1.1919 1.40 21 8.00 1.2003 A 7.80 1.2067 22 23 7.60 1.2112

__A 24 7.40 1.2138 25 7.20 1.2156 26 7.00 1.2158 27 6.80 1.2143 28 6.60 1.2116 N A 1.30 29 6.40 1.2075 30 6.20 1.2026 31 6.00 1.1957 32 5.80 1.1929 33 5.60 1.1955 34 5.40 1.2082

- -X 35 5.20 1.2205 36 5.00 1.2318 37 4.80 1.2423 1.20 38 4.60 1.2516 39 4.40 1.2600 40 4.20 1.2669 41 4.00 1.2726 42 3.80 1.2770 43 3.60 1.2830 44 3.40 1.2920 45 3.20 1.3049 1.10 46 3.00 1.3197 47 2.80 1.3362 48 2.60 1.3568 49 2.40 1.3813 50 2.20 1.4056 51 2.00 1.4290

52 1 .80 1.0000

53 1.60 1.0000

54 1.40 1.6555 1.00

55 1.20 1.0000 0 2 4 6 8 10 12

56 i .(0 1.0000

57 0.80 1.0000 Core Height (feet)

58 0.60 1.0000

59 0.40 1.0000

60 61 _1,20 0.00 11.0000

.0000

Top and Bottom 15% Excluded per TA-.lrt r,.d~fil.dinn R3.2 1.

Technical 1-ification 133 2 1 This figure is referred to by Technical Specification B3.2.1.

Page 11 of 15

4A CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 15 DECEMBER 2001 Figure 5 RAOC W(Z) at 4000 MWDIMTU Point Elevation MOL-1 Pot (fed) W(Z)

9 12.00 1.0000 12 9i.80 1.0215 1.60 ..... 13 91.60 1.2009 14 91.40 1.2020 15 11.20 1.0000 16 11.00 1.1000 17 10.80 1.1881 18 10.60 1.1987 19 10.40 1.2087 10 10.20 1.0000 I1 10.00 1.2231 1.50 12 9.80 1.2155 13 9.60 1.2093 14 9.40 1.2020 15 9.20 1.1964 16 9.00 1.1890 17 8.80 1.1881 18 8.60 1.1987 19 8.40 1.2087 20 8.20 1.2162 21 8.00 1.2215 22 7.80 1.2243 23 7.60 1.2942 24 7.40 1.2234 25 7.20 1.2208 26 7.00 1.2166 27 6.80 1.2106 N 1.30 28 6.60 1.2033 A 29 6.40 1.1946 30 6.20 1.3046 31 6.00 1.1744 32 15.80 1.1608 33 5.60 1.1530 34 5.40 1.1611 35 1.20 1.1690 36 5.00 1.1752 1.20 -- - - - - 37 4.80 1.1810 38 4.60 1.0000 39 4.40 1.1003 40 4.20 1.1934 41 4.00 1.1958 42 1 5.3.80 1973 43 3.60 1.1982 44 3.40 1.2012 45 3.20 1.2066 1.10 46 3.00 1.2185 47 2.80 1.23'77 4-8 2.60 1.2606

- -49 2.40- 1.2828 50 2.20 104 51 2.00 1.3263

52 1.80 1.0000

53 1.60 I .(DO0

54 1.40 1.0000 1.00- 1.0000

55 1.20 0 2 4 6 8 10 12 S56 1.00 1.00000 57 0.80 1 1.0000 Core Height (feet)

58 0.60 1.0000

59 0.40 1.0000

60 0.20 1.0000

61 0.00 1.0000 Top and Bottom 15% Excl32ed per Technical Specification B3.2. 1.

This figure is referred to by Technical Specification B33.2.1.

Page 12 of 15

DECEMBER 2001 4A CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 15 Figure 6 RAOC W(Z) at 10000 MWDIMTU Axial Elevation MOL-2 Point feet W(Z)

1 12.00 1.0000

2 11.80 1.0000

3 11.60 1.0000 1.60 1.0000

4 11.40

5 11.20 1.0000

6 11.00 1.0000

7 10.80 1.0000

8 10.60 1.0000

9 10.40 1.0000

10 10.20 1.0000 I 110.00 1.2585 1.50 12 9.80 1.2537 13 9.60 1.2482 14 9.40 1.2415 15 9.20 1.2342 16 9.00 1.2238 17 8.80 1.2283 18 8.60 1.2420 19 8.40 1.2567 20 8.20 1.2687 1.40 8.00 1.2776 21 22 7.80 1.2837 23 7.60 1.2869 24 7.40 1.2874 25 7.20 1.2854 26 7.00 1.2818 27 6.80 1.2764 NA 28 6.60 1.2688 1.30 29 6.40 1.2591 30 6.20 1.2477 31 6.00 1.2349 A A . _

32 5.80 1.2199 33 5.60 1.2052 34 5.40 1.1974 Al 35 5.20 1.1955 36 5.00 1.1942 37 4.80 1.1913 1.20 1.1873 A 38 4.60 39 4.40 1.1821 40 4.20 1.1756

__ 41 4.00 1.1681 42 3.80 1.1611 43 3.60 1.1545 44 3.40 1.1473 45 3.20 1.1422 1.10 46 3.00 1.1404 47 2.80 1.1467 48 2.60 1.1562 49 2.40 1.1662 50 2.20 1.1761 51 2.00 1.1859

52 1.80 1.0000

53 1.60 1.0000

54 1.40 1.0000 1.00 1.0000

55 1.20 0 2 4 6 8 10 12

56 1.00 1.0000

57 0.80 1.0000 Core Height (feet)

58 0.60 1.0000

59 0.40 1.0000

60 0.20 1.0000 61 0.00 1.0000 Top and Bottom 15% Excluded per Techntical Specification B3.2. 1.

This figure is referred to by Technical Specification B3.2.1.

Page 13 of 15

15 DECEMBER 2001 4x* CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE Figure 7 RAOC W(Z) at 17000 MWD/MTU Evleation EOL 1.60 w(z) 12.00 1.0000 2 I 1.80 1.0000 3 11.60 1.0000 11.40 1.0000

5 11.20 1.0000

6 I 1.00 1.0000

7 10.80 1.0000

8 10.60 1.0000 1.50 9 10.40- 1.000

10 10.20 1.00(01

!I 10.00 1.2470 12 9.80 1.2392 13 9.60 1.2311 14 9.40 1.2256

'15 9.20 1.2210 16 9.00 1.2152 1.40 17 8.80 1.2107 Is 8.60 1.2139 19 8.40- 1,2383 20 8.20 1.2593 21 8.ý00 1.2764 22 7.80_ 1.2910 23 7.60 1.3022 24 7.*40 1.3103 Ni 25 7.20 1.31 53 S1 26 7.00 1.3178 27 6.80 1.3194 28 6.60 1.3166 29 6.40 1.3124 30 6.20 1.3059 31 6.00 1.2976 32 5.80 1.2861 33 5.60 i. 2753 1.20 34 5.40 1.2725 35 1 5.20 1.2698_

36 5.00 1.2650 37 4.80 1.2582_

38 4.60 1.2493 39 4.40 1.2382_

40 4.20 1.2250 41 4.00 1.2100 42 3T80 1.1988 1.10 43 1 3.60 1.1875 44 1 3.40 1.1745 45 1 3.20 1.1598 46 1 3.00 1.1596 47 1 2.80 1.1724 48 1 2.60 1.1870 1 49 1 2.40 1.2009 50 1 2.20 1.2149 1.00 51 1 2.00 1.2288

52 1 1.80 1.0000 0 2 4 6 8 10 12

53 1 1.60 1.0000

54 1 1.40 1.0000 Core Height (feet)

55 1 1.20 1.00(00

56 1.00 1.0000

57 0.80 1.0000

58 0.0 1.0000

59 0.40 1.0000 0.20 1.0000 S6 61 0.00 1.0000 This figure is referred to by Technical Specification B3.2. 1.

Top and Bottom 15% Excluded per Technical Specification B3.2. 1.

Page 14 of 15

CORE OPERATING LIMITS REPORT, FNP UNIT 2 CYCLE 15 DECEMBER 2001

.A Figure 8 Reactor Core Safety Limits 680 660 640

-- 0-2425 psig

-2235 psig D 620 A 1985 psig

-X-1825 psig 600 580 560 0.0 0.2 0.4 0.6 0.8 1.0 1.2 Power (Fraction of Rated Thermal Power)

Page 15 of 15

ML020240279

Text

0.5 where

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