ML091420374: Difference between revisions
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (StriderTol Bot change) |
||
| (3 intermediate revisions by the same user not shown) | |||
| Line 5: | Line 5: | ||
| author name = | | author name = | ||
| author affiliation = PPL Susquehanna, LLC | | author affiliation = PPL Susquehanna, LLC | ||
| addressee name = Gerlach R | | addressee name = Gerlach R | ||
| addressee affiliation = NRC/Document Control Desk, NRC/NRR | | addressee affiliation = NRC/Document Control Desk, NRC/NRR | ||
| docket = 05000388 | | docket = 05000388 | ||
| Line 15: | Line 15: | ||
=Text= | =Text= | ||
{{#Wiki_filter:May. 15, 2009 Page I of 3 MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2009-23231 USER INFORMATION: | {{#Wiki_filter:May. 15, 2009 Page I of 3 MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2009-23231 USER INFORMATION: | ||
GERLACH*ROSE M EMPL#:028401 CA#: 0363 Address: NUCSA2 Phone#: 254-3194 TRANSMITTAL INFORMATION: | GERLACH*ROSE M EMPL#:028401 CA#: 0363 Address: NUCSA2 Phone#: 254-3194 TRANSMITTAL INFORMATION: | ||
TO: GERLACH*ROSE M 05/15/2009 LOCATION: | TO: GERLACH*ROSE M 05/15/2009 LOCATION: USNRC FROM: NUCLEAR RECORDS DOCUMENT CONTROL CENTER (NUCSA-2) | ||
USNRC FROM: NUCLEAR RECORDS DOCUMENT CONTROL CENTER (NUCSA-2)THE FOLLOWING CHANGES HAVE OCCURRED TO THE HARDCOPY OR ELECTRONIC MANUAL ASSIGNED TO YOU. HARDCOPY USERS MUST ENSURE THE DOCUMENTS PROVIDED MATCH THE INFORMATION ON THIS TRANSMITTAL. | THE FOLLOWING CHANGES HAVE OCCURRED TO THE HARDCOPY OR ELECTRONIC MANUAL ASSIGNED TO YOU. HARDCOPY USERS MUST ENSURE THE DOCUMENTS PROVIDED MATCH THE INFORMATION ON THIS TRANSMITTAL. WHEN REPLACING THIS MATERIAL IN YOUR HARDCOPY MANUAL, ENSURE THE UPDATE DOCUMENT ID IS THE SAME DOCUMENT ID YOU'RE REMOVING FROM YOUR MANUAL. TOOLS FROM THE HUMAN PERFORMANCE TOOL BAG SHOULD BE UTILIZED TO ELIMINATE THE CHANCE OF ERRORS. | ||
WHEN REPLACING THIS MATERIAL IN YOUR HARDCOPY MANUAL, ENSURE THE UPDATE DOCUMENT ID IS THE SAME DOCUMENT ID YOU'RE REMOVING FROM YOUR MANUAL. TOOLS FROM THE HUMAN PERFORMANCE TOOL BAG SHOULD BE UTILIZED TO ELIMINATE THE CHANCE OF ERRORS.ATTENTION: "REPLACE" directions do not affect the Table of Contents, Therefore no TOC will be issued with the updated material.TRM2 -TECHNICAL REQUIREMENTS MANUAL UNIT 2 REMOVE MANUAL TABLE OF CONTENTS DATE: 05/05/2009 ADD MANUAL TABLE OF CONTENTS DATE: 05/14/2009 CATEGORY: | ATTENTION: "REPLACE" directions do not affect the Table of Contents, Therefore no TOC will be issued with the updated material. | ||
DOCUMENTS TYPE: TRM2 4loo | TRM2 - TECHNICAL REQUIREMENTS MANUAL UNIT 2 REMOVE MANUAL TABLE OF CONTENTS DATE: 05/05/2009 ADD MANUAL TABLE OF CONTENTS DATE: 05/14/2009 CATEGORY: DOCUMENTS TYPE: TRM2 4loo | ||
May. 15, 2009 Page 2 of 3 ID: TEXT 2.2 ADD: REV: 8 REMOVE: REV:7 CATEGORY: DOCUMENTS TYPE: TRM2 ID: TEXT 3.1.3 REMOVE: REV:3 ADD: REV: 4 CATEGORY: DOCUMENTS TYPE: TRM2 ID: TEXT 3.10.4 REMOVE: REV:1 CATEGORY: DOCUMENTS TYPE: TRM2 ID: TEXT 3.2.1 ADD: REV: 8 | |||
. REMOVE: REV:7 CATEGORY: DOCUMENTS TYPE: TRM2 ID: TEXT 3.3.9 ADD: REV: 3 REMOVE: REV:2 CATEGORY: DOCUMENTS TYPE: TRM2 ID: TEXT 3.4.4 ADD: REV: 2 REMOVE: REV:1 CATEGORY: DOCUMENTS TYPE: TRM2 | |||
3 | |||
May. 15, 2009 Page 3 of 3 ID: TEXT B3.10.4 REMOVE: REV:0 CATEGORY: DOCUMENTS TYPE: TRM2 ID: TEXT B3.3.9 REMOVE: REV:2 ADD: REV: 3 CATEGORY: DOCUMENTS TYPE: TRM2 ID: TEXT LOES ADD: REV: 50 REMOVE: REV:49 CATEGORY: DOCUMENTS TYPE: TRM2 ID: TEXT TOC ADD: REV: 15 REMOVE: REV:14 ANY DISCREPANCIES WITH THE MATERIAL PROVIDED, CONTACT DCS @ X3107 OR X3136 FOR ASSISTANCE. UPDATES FOR HARDCOPY MANUALS WILL BE DISTRIBUTED WITHIN 3 DAYS IN ACCORDANCE WITH DEPARTMENT PROCEDURES. PLEASE MAKE ALL CHANGES AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX UPON COMPLETION OF UPDATES. FOR ELECTRONIC MANUAL USERS, ELECTRONICALLY REVIEW THE APPROPRIATE DOCUMENTS AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX. | |||
SSES MANUAL Manual Name: TRM2 Manual | |||
==Title:== | |||
TECHNICAL REQUIREMENTS MANUAL UNIT 2 Table Of Contents Issue Date: 05/14/2009 Procedure Name Rev Issue Date Change ID Change Number TEXT LOES 50 05/14/2009 | |||
== | ==Title:== | ||
LIST OF EFFECTIVE SECTIONS TEXT TOC 15 05/14/2009 | |||
==Title:== | |||
TABLE OF CONTENTS TEXT 1.1 0 11/19/2002 | |||
: | |||
=== | ==Title:== | ||
USE AND APPLICATION DEFINITIONS TEXT 2.1 1 | |||
==Title:== | |||
PLANT PROGRAMS AND SETPOINTS TEXT 2.2 8 | |||
== | ==Title:== | ||
PLANT PROGRAMS AND )-/INSTRUMENT TRIP SETPOINT TABLE | |||
==Title:== | |||
APPLICABILITY TECHNICAL REQUIREMENT FOR OPERATION (TRO) APPLICABILITY TEXT 3.1.1 1 11/09/2007 | |||
==1.0 | ==Title:== | ||
REACTIVITY CONTROL SYSTEMS ANTICIPATED TRANSIENT WITHOUT SCRAM ALTERNATE ROD | |||
\ \ ) I INJECTION '(ATWS-ARI) INSTRUMENTATION TEXT 3.1.2 0 11/19/2002 | |||
==Title:== | |||
REACTIVITYCONTROL SYSTEMS CONTROL ROD DRIVE (CRD) HOUSING SUPPORT TEXT 3.1.3 4 05/14/2009 | |||
==Title:== | |||
REACTIVITY CONTROL SYSTEMS CONTROL ROD BLOCK INSTRUMENTATION TEXT 3.1.4 0 11/19/2002 | |||
==Title:== | |||
REACTIVITY CONTROL SYSTEMS CONTROL ROD SCRAM ACCUMULATORS INSTRUMENTATION AND CHECK VALVE TEXT 3.2.1 8 05/14/2009 | |||
==Title:== | |||
CORE OPERATING LIMITS CORE OPERATING LIMITS REPORT (COLR) | |||
Report Date: 05/14/09 Page ~ | |||
Page 1 of of 15 15 Report Date: 05/14/09 | |||
SSES MANUAL Manual Name: TRM2 Manual | |||
==Title:== | |||
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.3.1 0 11/19/2002 | |||
==Title:== | |||
INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION TEXT 3.3.2 2 11/09/2007 | |||
==Title:== | |||
INSTRUMENTATION SEISMIC MONITORING INSTRUMENTATION TEXT 3.3.3 2 11/09/2007 | |||
==Title:== | |||
INSTRUMENTATION METEOROLOGICAL MONITORING INSTRUMENTATION TEXT 3.3.4 5 05/23/2008 | |||
==Title:== | |||
INSTRUMENTATION TRM POST-ACCIDENT MONITORING INSTRUMENTATION TEXT 3.3.5 0 11/19/2002 | |||
==Title:== | |||
INSTRUMENTATION THIS PAGE INTENTIONALLY LEFT BLANK TEXT 3.3.6 2 10/19/2005 | |||
==Title:== | |||
INSTRUMENTATION TRM ISOLATION ACTUATION INSTRUMENTATION TEXT 3.3.7 1 11/09/2007 | |||
==Title:== | |||
INSTRUMENTATION MAIN TURBINE OVERSPEED PROTECTION SYSTEM TEXT 3.3.8 1 10/22/2003 | |||
==Title:== | |||
INSTRUMENTATION TRM RPS INSTRUMENTATION TEXT 3.3.9 3 05/14/2009 | |||
==Title:== | |||
INSTRUMENTATION LPRM UPSCALE ALARM INSTRUMENTATION TEXT 3.3.10 1 12/14/2004 | |||
==Title:== | |||
INSTRUMENTATION REACTOR RECIRCULATION PUMP MG SET STOPS TEXT 3.3.11 1 10/22/2003 | |||
==Title:== | |||
INSTRUMENTATION MVP ISOLATION INSTRUMENTATION TEXT 3.3.12 0 04/16/2009 | |||
==Title:== | |||
WATER MONITORING INSTRUMENTATION Report Date: 05/14/09 Page 2. | |||
Page 2 of of 15 1_55 Report Date: 05/14/09 | |||
SSES MANUAL Manual Name: TRM2 Manual | |||
==Title:== | |||
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.4.1 1 04/26/2006 | |||
==Title:== | |||
REACTOR COOLANT SYSTEM REACTOR COOLANT SYSTEM CHEMISTRY TEXT 3.4.2 1 04/16/2009 | |||
==Title:== | |||
REACTOR COOLANT SYSTEM STRUCTURAL INTEGRITY TEXT 3.4.3 1 11/09/2007 | |||
==Title:== | |||
REACTOR COOLANT SYSTEM REACTOR COOLANT SYSTEM (RCS) | |||
TEXT 3.4.4 2 05/14/2009 | |||
==Title:== | |||
REACTOR COOLANT SYSTEM REACTOR RECIRCULATION FLOW AND ROD LINE LIMIT TEXT 3.4.5 1 04/26/2006 | |||
==Title:== | |||
REACTOR COOLANT SYSTEM REACTOR VESSEL MATERIALS TEXT 3.5.1 1 02/04/2005 | |||
==Title:== | |||
ECCS AND RCIC ADS MANUAL INHIBIT TEXT 3.5.2 1 11/09/2007 | |||
==Title:== | |||
ECCS AND RCIC ECCS AND RCIC SYSTEM MONITORING INSTRUMENTATION TEXT 3.5.3 0 11/19/2002 | |||
==Title:== | |||
ECCS AND RCIC LONG TERM NITROGEN SUPPLY TO ADS TEXT 3.6.1 0 11/19/2002 | |||
==Title:== | |||
CONTAINMENT VENTING OR PURGING TEXT 3.6.2 0 11/19/2002 | |||
==Title:== | |||
CONTAINMENT SUPPRESSION CHAMBER-TO-DRYWELL VACUUM BREAKER POSITION INDICATION TEXT 3.6.3 0 11/19/2002 | |||
==Title:== | |||
CONTAINMENT SUPPRESSION POOL ALARM INSTRUMENTATION TEXT 3.6.4 0 11/19/2002 | |||
==Title:== | |||
CONTAINMENT PRIMARY CONTAINMENT CLOSED SYSTEM BOUNDARIES Page 3 of 15 Report Date: 05/14/09 | |||
SSES MANUAL Manual Name: | |||
==REFERENCE:== | ==REFERENCE:== | ||
T.S. 3.7.6 and 3.2.2 - | |||
CD | |||
_ _ ~~~ _ ~~I _ _ _ _ _ _ | |||
1.2 czý 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR) OD r-(D z-n CD1 0 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS INOPERABLE 0 | |||
-+1 0 | |||
TWO LOOP OPERATION (BOC TO EOC) C" CD FIGURE 5.2-3 | |||
SSES UNIT 2 CYCLE 15 3.6 m (23,3.54) | |||
(100, | LEGEND 3.4 . . J | ||
\A((26, 3.26) | |||
I3 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 3.2 INSERTION TIME | |||
-I (23, 3.02) I N) | |||
CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME | |||
.. u I | |||
-(26, 2.86) CURVE C: CORE POWER | |||
* 26% AND CORE FLOW <50 MLBM/HR 2.8 C | |||
-H- | |||
-J 2.6 C, | |||
SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE -u INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 r-0. | |||
2.4 0CL (D co n 2.2 20 (26.01, 2.06) USED IN DETERMINING MFLCPR 2.0 | |||
~(40, 1.77)- | |||
m 1.8 m A m 1.6 (80,1.48) (100, 1.48) m 1.4 | |||
==REFERENCE:== | ==REFERENCE:== | ||
T.S. 3.7.6 and 3.2.2 ____ _ | |||
1.2 20 30 40 50 60 70 80 90 100 | |||
-0 (D -U Core Power (% RATED) 0) ;0 r-(0 (D z1 MCPR OPERATING LIMIT VERSUS CORE POWER 0) | |||
MAIN TURBINE BYPASS INOPERABLE W N.) | |||
TWO LOOP OPERATION (BOC to EOC) col FIGURE 5.2-4 | |||
PPL Rev. 8 PL-NF-09-002 Rev. 0 Page 17 of 53 EOC-RPT Inoperable SUSQUEHANNA UNIT 2 TRMI3.2-18 EFFECTIVE DATE 04/17/2009 | |||
7-V/) SSES UNIT 2 CYCLE 15 2.2 m LEGEND 2.1 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM | |||
-I INSERTION TIME 2.0 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 1.9 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 USED IN DETERMINING MFLCPR 6- | |||
-u I-E (D 1.7 0 (30, 1.60) | |||
* 1.6 1.5 m | |||
T1 '-u 1.4 m | |||
==REFERENCE:== | ==REFERENCE:== | ||
T.S. 3.3.4.1 and 3.2.2 m 1.3 (108,1.22)- | |||
1.2 30 40 50 60 70 80 90 100 110 N) | |||
Total Core Flow (MLB/HR) | |||
(0 0 -n | |||
-0 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW co 0 EOC-RPT INOPERABLE 0 (0 Ln TWO LOOP OPERATION (BOC TO EOC) W., ,r-FIGURE 5.2-5 | |||
9 Sp) | |||
-9 SSES UNIT 2 CYCLE 15 3.6 I I -II I m | |||
(100, 1.44) | LEGEND 3.4 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 3.2 INSERTION TIME (23, 3.09) 3.0 CURVE 8: REALISTIC AVERAGE SCRAM INSERTION TIME (23, 3.02) 22 CURVE C: CORE POWER | ||
* 26% AND CORE FLOW _*ý 50 MLBMJHR 2.8 C (26, 2.86) -1 2.6 SAFETY ANALYSES ASSUME SFTAAYE PER THAT FOUR SR 3.7.6.1 AND 3.7.6.2 VALVES ARE OPERABLE BYPASS NJ Tu | |||
-D 0 USED IN DETERMINING MFLCPR 2.2 | |||
: 02. -(26.01, 2.03) 2.0 | |||
*0, 4* 1.72) m 1.8 T' | |||
m | |||
* B m 1.6 | |||
_ (80,1.44) (100, 1.44) | |||
==REFERENCE:== | ==REFERENCE:== | ||
T.S. 3.3.4.1 and 3.2.2 _ _ _ _ | |||
m 1.4 CD 1.2 mD 20 30 40 50 60 70 80 90 100 | |||
-0 Core Power (% RATED) (1D z | |||
MCPR OPERATING LIMIT VERSUS CORE POWER 0 m co (D1 6 EOC-RPT INOPERABLE (0 TWO LOOP OPERATION (BOC to EOC) 0 N) | |||
FIGURE 5.2-6 | |||
PPL Rev. 8 PL-NF-09-002 Rev. 0 Page 20 of 53 Backup Pressure Regulator Inoperable SUSQUEHANNA UNIT 2 TRM/3.2-21 EFFECTIVE DATE 04/17/2009 | |||
(-9 CIO SSES UNIT 2 CYCLE 15 | |||
.2.2 I I LEGEND 2.1 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM mQ INSERTION TIME 2.0 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME t | |||
1.9 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 I I USED IN DETERMINING MFLCPR | |||
~1.7 | |||
-0 0) | |||
(30, 1.60) co | |||
~1.6 1.5 m | |||
m 1.4 m | |||
m cz) 1.3 , | |||
==IREFERENCE:== | ==IREFERENCE:== | ||
T.S. 3.7.8 and 3.2.2 | |||
*1 | |||
_ _ __ [ _ _ __ _ _ _0_ _ | |||
(108,1.22) 1_22_ | |||
1.2 30 40 50 60 70 80 9o 100 110 Total Core Flow (MLB/HR) | |||
Co< | |||
Co Z MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW BACKUP PRESSURE REGULATOR INOPERABLE TWO LOOP OPERATION (BOC TO EOC) CD FIGURE 5.2-7 | |||
E 4 (A | |||
SSES UNIT 2 CYCLE 15 3.6 m | |||
ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 ,2.17) USED IN DETERMINING MFLCPR (80 1.45)-- | LEGEND 3.4 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 3.2 (23, 3.09) INSERTION TIME i CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.0 (26, 2.96) | ||
(23, 3.02) CURVE C: CORE POWER <26% AND CORE FLOW *50 MLBMJHR 2.8 C (26, 2.86) | |||
XA -32.6 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES | |||
.4- (26.01,2.42) ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 -u 03S2.4 F-. | |||
a. | |||
0 ,2.17) USED IN DETERMINING MFLCPR (D 0 | |||
L. 2.2 2.0 (80 1.45) m 1.8 | |||
-n m 1.6 -- | |||
==REFERENCE:== | ==REFERENCE:== | ||
T.S. 3.7.8 and 3.2.21-- ,1.5 m 1.4 (100, 1.36) | |||
Nm 1.2 C) 20 30 40 80 90 100 50 60 70 Core Power (% RATED) -D CD z,-n x | |||
:7 | |||
: 0) 0 MCPR OPERATING LIMIT VERSUS CORE POWER 6 | |||
BACKUP PRESSURE REGULATOR INOPERABLE 0 lpo (0i TWO LOOP OPERATION (BOC to EOC) | |||
FIGURE 5.2-8 | |||
PPL Rev. 8 PL-NF-09-002 Rev. 0 Page 23 of 53 Table 5.3-1 Average Scram Time Fraction Table For Use With Scram Time Dependent MCPR Operating Limits Control Rod Average Scram Time to Position (seconds) | |||
Position 45 0.470 0.520 39 0.630 0.860 25 1.500 1.910 5 2.700 3.440 Average Scram Realistic Maximum Insertion Time Allowable SUSQUEHANNA UNIT 2 TRM/3.2-24 EFFECTIVE DATE 04/17/2009 | |||
PPL Rev. 8 PL-NF-09-002 Rev. 0 Page 24 of 53 6.0 LINEAR HEAT GENERATION RATE (LHGR) 6.1 Technical Specification Reference Technical Specification 3.2.3 and 3.7.6 6.2 Description The maximum LHGR for ATRIUMm-10 fuel shall not exceed the LHGR limit determined from Figure 6.2-1. The LHGR limit in Figure 6.2-1 is valid for Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, and Backup Pressure Regulator Operable and Inoperable. | |||
To protect against both fuel centerline melting and cladding strain during anticipated system transients initiated from reduced power and flow conditions, power and flow dependent LHGR limit multipliers are provided. | To protect against both fuel centerline melting and cladding strain during anticipated system transients initiated from reduced power and flow conditions, power and flow dependent LHGR limit multipliers are provided. The following figures are applicable to EOC-RPT Operable and Inoperable and Backup Pressure Regulator Operable and Inoperable: | ||
The following figures are applicable to EOC-RPT Operable and Inoperable and Backup Pressure Regulator Operable and Inoperable: | a) Main Turbine Bypass Operable Figure 6.2-2: Flow-Dependent LHGR Limit Multiplier Figure 6.2-3: Power-Dependent LHGR Limit Multiplier b) Main Turbine Bypass Inoperable Figure 6.2-4: Flow-Dependent LHGR Limit Multiplier Figure 6.2-5: Power-Dependent LHGR Limit Multiplier The LGHR limit and LHGR limit multipliers in Figures 6.2-1 through 6.2-5 are valid for both Two Loop and Single Loop operation. | ||
a) Main Turbine Bypass Operable Figure 6.2-2: Flow-Dependent LHGR Limit Multiplier Figure 6.2-3: Power-Dependent LHGR Limit Multiplier b) Main Turbine Bypass Inoperable Figure 6.2-4: Flow-Dependent LHGR Limit Multiplier Figure 6.2-5: Power-Dependent LHGR Limit Multiplier The LGHR limit and LHGR limit multipliers in Figures 6.2-1 through 6.2-5 are valid for both Two Loop and Single Loop operation. | SUSQUEHANNA UNIT 2 - TRM/3.2-25 EFFECTIVE DATE 04/17/2009 | ||
SUSQUEHANNA UNIT 2 -TRM/3.2-25 EFFECTIVE DATE 04/17/2009 V)C-CA 16.0 C-S 14 | |||
1~~ | |||
V) | |||
C-CA SSES UNIT 2 CYCLE 15 16.0 C-S 14.0 0.0, 13.4...... 90,go 3.4 | |||
==REFERENCE:== | ==REFERENCE:== | ||
T.S. 3.2.3 | |||
-H 12,0 ....................................... | |||
E a, | |||
l BI I i Ii I a a I I I I I I.I. l I I l | |||
* l I I iI la | |||
,2 0 N) | |||
, 10.0 I I allI co | |||
...... IIll S . | |||
I S .......... . | |||
.~i I. I I | |||
I Ii I IIIIII ......... | |||
0. | |||
48.0 m | |||
m 6.0 7'44'00, 7.10: | |||
m C=) | |||
CD CDJ 4.0 110 0 10000 20000 30000 40000 50000 60000 70000 80000 Pellet Exposure (MWD/MTU) | |||
LINEAR HEAT GENERATION RATE LIMIT VERSUS PELLET EXPOSURE .0 (cI 60 ATRIUM TM -10 FUEL FIGURE 6.2-1 | |||
PPL Rev. 8 PL-NF-09-002 Rev. 0 Page 26 of 53 Main Turbine Bypass Operable SUSQUEHANNA UNIT 2 TRM/3.2-27 EFFECTIVE DATE 04/17/2009 | |||
SSES UNIT 2 CYCLE 15 | |||
- - - - - - I - - - - . . . . . . . . . I . . . . . . .I - - I | |||
. .. . . . . + .+ . . . . . . * . . . , . . . * . . .. . . .....+ . . . i.... I.-- - - - - | |||
z :' (80,1.00) , | |||
,,,,,, | 0.00 . .. . . ...... ..... ... .. ..... ..... ..... ,,,,,, | ||
,........ | - ,........ 1 0 .7 0 .. . . . . .. . .... .. .. ... . . . . . . . ... . . . . .. . -- -- -* - . -- - - - - - -- - | ||
1 | (30,0.75) : . . a. .aa " . . . . . . + . . . .. ;.a . . . ..*.a . . ... . . . ..I. . . . . . . . . . . *. | ||
. a. . . . ..*.aaaaaa- . . . " . . . . . . . . | |||
AREOPERABLE PER SR 3.7.6.1 AND 3..7.6.-n 0. | 0.80 - -- -.... ..... | ||
(D r',. a aa a a . . . a1 . 7...' SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 1 | |||
.. 7a ..... .. a.... a-aA......... AREOPERABLE PER SR 3.7.6.1 AND 3..7.6. | |||
: a. . . . a . . . a. . . a. . . . a... . . a . a a l | |||
-n 0.50r- ~ ~ - .a*....... .... ...... ..... a.... ..... .. ... ... ..... ..... ...-..J..... .......... . ...... | |||
S......................................................... | |||
==REFERENCE:== | ==REFERENCE:== | ||
T.S. 3.2. | + a a ,acr T.S. | ||
Et nrrn 3.2.3.....aaandJ t 3.7 ..... | |||
......... | r ma f 0.30 , , ,C 0.40 ..... ..... 'I41,ru r~ | ||
................. | c:) (0 < | ||
a a aI a i | |||
*_AI | |||
... ...... ... I . | .............................. TUBN | ||
......... YASS OPERABLE PE | |||
................. SR3761AN ... | |||
* * ~0,30 , * ..... ATRI'-]1 FUE. | |||
F--+ *30 40 50 60 70 80 90 100 110 | |||
~Total Core Flow (MLBthr) | |||
FLOW DEPENDENT LHGR LIMIT MULTIPLIER 5 MAIN TURBINE BYPASS OPERABLE * , | |||
ATRIUMTM-10 FUEL | |||
* 2 FIGURE 6.2-2 | |||
CD1.10 1SSES UNIT 2 CYCLE 15 m* LEGEND .. | |||
, , ,(94.46,1.00) 1.00 .CURVE A: BASE CURVE 1 7 WER 26 !(100, 1.00) | |||
- CURVE B: CORE POWER 26% AND CORE FLOW* 50 MLBM/HR ... --. -.- (100- | |||
.T r .;-*- ... ........ . ............ ... ...... I ... . . | |||
a aSAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ( | |||
CLARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 co a) (26.01, 0.65) a a a a a | |||
==REFERENCE:== | ==REFERENCE:== | ||
T.S. 3.2.3 and 3.7.6 Ir I a a , a | |||
* a I a a a a . | |||
a aa a . a a aUSED IN DETERMINING FDLRXj-C-,a . I - 4 a 4 . . . I I .. | |||
(23,0.u48) :: 0- * " ;0 -u" a(26,0.42): | |||
- (23,0.39) | |||
..... .. I............... ............ ............ I............ | |||
FIGUR 6NDE.R2NNGFD3 0.30 20 30 40 50 60 70 80 90 100 Core Power (%RATED) ( ; | |||
MAIN TURBINE BYPASS OPERABLE R3 01 ATRIUMM 0 FUEL c F 6- | |||
PPL Rev. 8 PL-NF-09-002 Rev. 0 Page 29 of 53 Main Turbine Bypass Inoperable C' | |||
SUSQUEHANNA UNIT 2 TRM/3.2-30 EFFECTIVE DATE 04/17/2009 | |||
Ilk | |||
.SSES UNIT 2 CYCLE 15 | |||
*J99,1.00 | |||
_ ~~~. | |||
0 ...... *. ........ .. ...... *......* 4 ..... I . ....... ..... | |||
4J *., .. .*. 4 . .=. 4 . .=. . .d .. | |||
..... ........... | . . ............. ,.00 | ||
........ ........................ , . | . | ||
. | * 1. (9 0 8, 0.90 -- --.. .................................... ..... ........... ........ ........................ , . | ||
- - -l ------- 6....... | |||
..... ........... | .. . .. .. . . . .. .... . . .. ... . . . .... 1. tNN 0.s .. . . | ||
......................... | . . . . . . t . . . . . 1. . . . . * . ... . . . -. - .. - . . . . d. i. l . . . . ..I *. l I i* .. . . | ||
. .... ". ..J. . . . . . iI.. . . . . . . . . . . . | |||
N) m 0.7 | |||
............... | -------- . . . . ,1 SAFETY ANALYSES ASSUME , . I THAT TWO OR l I MORE BYPASS | ||
=..,i * , 4 4 VALVES ARE , INOPERABLE | |||
-4 i N) 0 N). ..SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES CD | * . PER. SR 3.7.6.1 OR. 3.7.6.2 i o 4 4 . , . 4 , . o 4, 4* | ||
0.50 .. 4 . . . . | |||
. , , , , , , , 4 , , , | |||
, 4 o 4 o 4 4 4 | |||
-A .. . .. . . ,,4 I,4 | |||
..... ........... ..... ........... 44.......................... ,, R 3.7.6.2 "4. 0.40 ...... . | |||
0.30 A 30 40 50 60 70 80 90 100 110 C) ~Total Core Flow (MLBIHR) W( | |||
C0 n FLOW DEPENDENT LHGR LIMIT MULTIPLIER cz o MAIN TURBINE BYPASS INOPERABLE a (0 ATRIUMTM-10 FUEL0 FIGURE 6.2-4 | |||
~~1.10 1SSES UNIT 2 CYCLE 15 | |||
_-.z: LEGEND .. | |||
........ :(94.46, 1.00) 1,00 CURVE A: BASE CURVE z , (100, 1.00) | |||
- CURVE B: CORE POWER 5 26% AND CORE FLOW 5 50 MLBM/HR ... .... -. | |||
\) | |||
0.90 . . . . . . .. . .. . . . . ..................................... ;... . .............. I............. | |||
-4 i 0. | |||
N) 0.80 0 .. . ..... . ....., .......... , . . | |||
7 .. . . . . .. | |||
I°. . . I . . . .. | |||
... . . . . " . . . . . " . . . . . . n N). . . SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES CD | |||
-- ....... i | |||
(~ ~ ~. | |||
5 . . B . . -. -. -. -- - --.(2601 | |||
. . . . . 0.5)ARE | |||
.*v .. ... . . .i | |||
----- - - * .- INOPERABLE | |||
- - ---- - -*... PER SR 3.7.6.1 OR 3.7.6.2 0 0 -i - - - - | |||
0 C)*, | |||
==REFERENCE:== | ==REFERENCE:== | ||
.T.S. 3.2.3 and 3.7.6 | .T.S. 3.2.3 and 3.7.6 S...... --- 1... -- USED IN DETERMINING FDLRX | ||
S (23, 0.46) ....' ......... | ,.. 0 .60... | ||
............... | Fri (26,0.48): | ||
.4....... | S (23,0.46) .... ' ......... ............... .4....... .............................. | ||
.............................. | I USED IN DTRINGFDR | ||
:(260.42). | :(260.42). | ||
(23,0.39) m 0.30( ,. )' | |||
.. .... .... ......... | 1 20 30 40 so 60 70 80 90 100 Core Power (% RATED) | ||
....... ....... | S(0.(D Z POWER DEPENDENT L*GR LIMIT MULTIPLIER MAIN TURBINE BYPASS INOPERABLE 0% ( | ||
ATRIU '10 FUEL C FIGURE 6.2-5 TED)-5 FIGURE cW r- | |||
PPL Rev. 8 PL-NF-09-002 Rev. 0 | |||
!O Page 32 of 53 AND OPERABILITY 7.0 ROD BLOCK MONITOR (RBM) SETPOINTS REQUIREMENTS 7.1 Technical Specification Reference Technical Specification 3.3.2.1 7.2 Description The RBM Allowable Value and Trip Setpoints for; a) Low Power Range Setpoint, b) Intermediate Power Range Setpoint, c) High Power Range Setpoint, e) Low Power Range - Upscale, f) Intermediate Power Range - Upscale, and g) High Power Range - Upscale shall be established as specified in Table 7.2-1. The RBM setpoints are valid for Two Loop and Single Loop Operation, Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, and Backup Pressure Regulator Operable and Inoperable. | |||
The RBM system design objective is to block erroneous control rod withdrawal initiated by the operator before fuel design limits are violated. If the full withdrawal of any control rod would not violate a fuel design limit, then the RBM system is not required to be operable. Table 7.2-2 provides RBM system operability requirements to ensure that fuel design limits are not violated. | |||
4o SUSQUEHANNA UNIT 2 TRM/3.2-33 EFFECTIVE DATE 04/17/2009 | |||
PPL Rev. 8 PL-NF-09-002 Rev. 0 Page 33 of 53 Table 7.2-1 RBM Setpoints Allowable Nominal Trip Function Value(') Setpoint Low Power Range Setpoint 28.0 24.9 Intermediate Power Range Setpoint 63.0 61.0 High Power Range Setpoint 83.0 81.0 Low Power Range - Upscale 123.4 123.0 Intermediate Power Range - Upscale 113.6 113.2 High Power Range - Upscale 110.6 110.2 (1) Power setpoint function (Low, Intermediate, and High Power Range Setpoints) determined in percent of rated thermal power. Upscale trip setpoint function (Low, Intermediate, and High Power Range - Upscale) determined in percent of reference level. | |||
Table 7.2-2 RBM System Operability Requirements Thermal Power MCPR (2.3) | |||
(% of Rated) a: 28 and < 90 < 1.80 a90 and < 95 < 1.47 | |||
> 95 < 1.52 (2) Applicable to Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, and Backup Pressure Regulator Operable and Inoperable. | |||
(3) Applicable to both Two Loop and Single Loop Operation. | |||
*0 SUSQUEHANNA UNIT 2 TRM/3.2-34 EFFECTIVE DATE 04/1712009 | |||
PPL Rev. 8 PL-NF-09-002 Rev. 0 Page 34 of 53 8.0 RECIRCULATION LOOPS - SINGLE LOOP OPERATION 8.1 Technical Specification Reference Technical Specification 3.2.1, 3.2.2, 3.2.3, 3.3.4.1, 3.4.1, 3.7.6, and 3.7.8 8.2 Description APLHGR The APLHGR limit for ATRIUMTM-10 fuel shall be equal to the APLHGR Limit from Figure 8.2-1. | |||
The APLHGR limits in Figure 8.2-1 are valid for Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, and Backup Pressure Regulator Operable and Inoperable in Single Loop operation. | |||
Minimum Critical Power Ratio Limit The MCPR limit is specified as a function of core power, core flow, and plant equipment operability status. The MCPR limits for all fuel types (ATRIUMTM -1 0) shall be the greater of the Flow-Dependent or the Power-Dependent MCPR, depending on the applicable equipment operability status. | |||
a) Main Turbine Bypass / EOC-RPT / Backup Pressure Regulator Operable Figure 8.2-2: Flow-Dependent MCPR value determined from BOC to EOC Figure 8.2-3: Power-Dependent MCPR value determined from BOC to EOC b) Main Turbine Bypass Inoperable Figure 8.2-4: Flow-Dependent MCPR value determined from BOC to EOC Figure 8.2-5: Power-Dependent MCPR value determined from BOC to EOC c) EOC-RPT Inoperable Figure 8.2-6: Flow-Dependent MCPR value determined from BOC to EOC Figure 8.2-7: Power-Dependent MCPR value determined from BOC to EOC d) Backup Pressure Regulator Inoperable Figure 8.2-8: Flow-Dependent MCPR value determined from BOC to EOC Figure 8.2-9: Power-Dependent MCPR value determined from BOC to EOC SUQEAN NT2 CE0/720 R/.-5EFCIV SUSQUEHANNA UNIT 2 TRM/3.2-35 EFFECTIVE DATE 04/17/2009 | |||
PPL Rev. 8 PL-NF-09-002 Rev. 0 Page 35 of 53 The MCPR limits in Figures 8.2-2 through 8.2-9 are valid only for Single Loop operation. | |||
Linear Heat Generation Rate Limit The LHGR limits for Single Loop Operation are defined in Section 6.0. | |||
RBM Setpoints and Operability Requirements The RBM setpoints and operability requirements for Single Loop Operation are defined in Section 7.0. | |||
4,Q SUQEANAUI TM---3,FETIEDT 0/720 SUSQUEHANNA UNIT 2 TRMi3.2-36 EFFECTIVE DATE 04/17/2009 | |||
SSES UNIT 2 CYCLE 15 | |||
.CD 16.0 rn. | |||
I , , i l l i l t ii! i i 14.0 t i II l l I | |||
t i i it t i ,, I REFERENCE T.S. 3.4.1 and 3.2.1 | |||
, i I i i i l l I ,i I , I I , i i i , t l l, , ,i i i | |||
, ,t l i USED INDETERMINING MAPRAT | |||
. .. . . . . . ..... !..I............I | |||
:-: 12.0 E .............. .. ........ .. .... .. .. ... ...... l * * .* .... | |||
-c i t | |||
* l , i I i !i . I Si i I RFRNE.S.3.4.1ad. .21 (D | |||
.0 . . .. .. . .ISDIN DETERM INING APRA li l t I li t , , It i i i li i ,i i ii , , it , , | |||
I 8.0 m - .................... | |||
.. . ... . 4. | |||
m P--I | |||
* .. %..l..J..t. ,'"...4..A. '. .. ..... ,.... .. . ... 670 0, 5I.6 6.0 m | |||
c> | |||
m 4.0 ci 0.0 10000.0 20000.0 30000.0 40000.0 50000.0 60000.0 70000.0 C) | |||
Average Planar Exposure (MWD/MTU) M) (D r-(0 < k AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS AVERAGE PLANAR EXPOSURE SINGLE LOOP OPERATION o (0o 6~ | |||
o'1 0 ATRIUMr-10 FUEL Wj N FIGURE 8.2-1 | |||
PPL Rev. 8 PL-NF-09-002 Rev. 0 Page 37 of 53 Main Turbine Bypass / EOC-RPT I Backup Pressure Regulator Operable 0< SUSQUEHANNA UNIT 2 TRM/3.2-38 EFFECTIVE DATE 04/17/2009 | |||
CA CA SSES UNIT 2 CYCLE 15 4.6 P1 LEGEND 4.4 2: | |||
4.2 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME | |||
-I 4.0 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.8 3.6 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES | |||
--4 3.2 | |||
-o CL 0) | |||
CD 0- | |||
~2.6 2.4 P1 2.2 m | |||
m P1 | |||
-1 2.0 P1 1.8 (108, 1.55) | |||
-H 1.6 m T.S. 3.4.1 and 3.2.21...__.. A | |||
==REFERENCE:== | ==REFERENCE:== | ||
1.4 I. | |||
SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 USED IN DETERMINING MFLCPR (26.01, 2.55)(40, 2. 17)--(60, 1.98)- -(100, 1.98)-B" | -a 30 40 50 60 70 80 90 100 110 N) | ||
Total Core Flow (MLBIHR) DCD | |||
'-0 CD' MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW | |||
-n W0 6 MAIN TURBINE BYPASS / EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE 0p 0, | |||
SINGLE LOOP OPERATION (BOC to EOC) | |||
FIGURE 8.2-2 | |||
SSES UNIT 2 CYCLE 15 C=1 4.6 . .. .... _ ._ I I I | |||
_LEGEND 4.4 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 4.2 INSERTION TIME 4.0 (23, 3.87) CURVE B: REALISTIC AVERAGE SCRAM TIME 3.8 (23, 3.78) -(26, 3.71) CURVE C: CORE POWER <26% AND CORE FLOW *50 MLBMIHR CI.. 3.6 c -_(26,3.58) | |||
E3.4 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 3.2 | |||
-U r'- | |||
3.0 USED IN DETERMINING MFLCPR 0 (D 2.8 (26.01, 2.55) | |||
E 2.6 2.4 (40, 2. 17)- | |||
m 2.2 | |||
-I-f m -(60, 1.98)- -(100, 1.98)- | |||
m C~-f 2.0 | |||
-H m 1.8 B ci 1.6 " | |||
==REFERENCE:== | ==REFERENCE:== | ||
T.S. 3.4.1 and 3.2-2 ri-f 1.4 20 30 40 50 60 70 80 90 100 Core Power (% RATED) CD -u ci -D 0 z MCPR OPERATING LIMIT VERSUS CORE POWER 0) 10 MAIN TURBINE BYPASS / EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE Co co -n SINGLE LOOP OPERATION (BOC to EOC) 0 0x FIGURE 8.2-3 | |||
PPL Rev. 8 PL-NF-09-002 Rev. 0 Page 40 of 53 Main Turbine Bypass Inoperable SUSQUEHANNA UNIT 2 TRM/3.2-41 EFFECTIVE DATE 04/17/2009 | |||
(A (A | |||
SSES UNIT 2 CYCLE 15 4.6 rn LEGEND 4.4 4.2 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM cz INSERTION TIME | |||
-H 4.0 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.8 3.6 SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS ! | |||
3.4 VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 | |||
-- A | |||
;00 3.2 TU | |||
:K "* 3.0 CL USED IN DETERMINING MFLCPR 0 (D, 0, 2.8 a.. (30, 2.52) a 2.6 A 2.4 m 2.2 m | |||
2.0 m | |||
1.8 -- J | |||
==REFERENCE:== | ==REFERENCE:== | ||
T.S.l3.4.1,13.7.6, and .2.2 m | |||
1.6 C) L-_______ _________ I________ _________________ _______________ I_______ | |||
1.4 30 40 50 60 70 80 90 100 110 N), | |||
Total Core Flow (MLB/HR) | |||
(D MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS INOPERABLE 0--h SINGLE LOOP OPERATION (BOC to EOC) 0 N) | |||
FIGURE 8.2-4 | |||
UC) | |||
SSES UNIT 2 CYCLE 15 4.6 i I LEGEND 4.4 234.43) | |||
X\ | |||
I.-' | |||
CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 4.2 i INSERTION TIME (26,4.08) 4.0 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.8 (23, 3. 78)Hj CURVE C: CORE POWER *n26% AND CORE FLOW <50 MLBM/HR 3.6 (26, 3.58) | |||
I., | |||
-t-t S3.4 _______ L | |||
(40, 2.23)(60, 2.05) -(100, 2.05)-...4.a B | --A S.. SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS o | ||
PPL Rev. 8 PL-NF-09-002 Rev. 0 Page 43 of 53 EOC-RPT Inoperable SUSQUEHANNA UNIT 2 TRM/3,2-44 EFFECTIVE DATE 04/17/2009 (J~m:1: 2: 2: | C 3.2 VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 3.0 I I-I N) I - - TI-0 USED IN DETERMINING MFLCPR c- | ||
"D | |||
= 2.8 | |||
: a. (26.01,2.59).... | |||
L) 2.6 2.4 (40, 2.23) 2.2 (60, 2.05) -(100, 2.05)- | |||
rn Mn 2.0 ... 4.a B | |||
-nl 1.8 | |||
-D 1.6 1.4 20 30 40 50 60 70 80 90 100 N.) | |||
C7, Core Power (% RATED) Q)CD Cc < | |||
(D Z MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS INOPERABLE 0 CIDC SINGLE LOOP OPERATION (BOC to EOC) cn 0 W N) | |||
FIGURE 8.2-5 | |||
PPL Rev. 8 PL-NF-09-002 Rev. 0 Page 43 of 53 EOC-RPT Inoperable SUSQUEHANNA UNIT 2 TRM/3,2-44 EFFECTIVE DATE 04/17/2009 | |||
(J~ | |||
SSES UNIT 2 CYCLE 15 4.6 I F I m LEGEND | |||
:1: | |||
4.4 2: | |||
2: | |||
4.2 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM cz 2: | |||
INSERTION TIME | |||
-I 4.0 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.8 3.6 | |||
~SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES S3.4 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 cn3.2 3.0 CL | |||
__USED IN DETERMINING MFLCPR 0, | |||
: 0. 2.8 -o IX (L | |||
2.6 2.4 m 2.2 -(30, 2.02) A TI | |||
-71 B 2.0 m 1.8 *-- "=--- -108, 1.55) - | |||
==REFERENCE:== | ==REFERENCE:== | ||
T.S. 3.4.1, 3.3.4.1, and 3.2.2 ............ | |||
1.6 m | |||
1.4 CD 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR) -c n) | |||
(0 CD C0 z MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW 0 | |||
. EOC-RPT INOPERABLE | |||
-h 0 SINGLE LOOP OPERATION (BOC to EOC) Cr (A) | |||
FIGURE 8.2-6 | |||
SSES UNIT 2 CYCLE 15 LI) 4.6 | |||
(60, 2.00) A B (100, 2.00)- | .r 4.4 1 i ~~~I L- %2 - It I | ||
l l I- I I 4.2 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 4.0 -(23, 3.87)- | |||
CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.8 N IN-(23, 3.78)- (26,3.71) 3.6 h- C ý(26, 3.58) | |||
CURVE C: CORE POWER 5 26% AND CORE FLOW 5 50 MLBMIHR 3.4 r - _ | |||
m, 3.2 -.... SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES | |||
_ - _ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 -u 3.0 | |||
: 00. CD W 2.8 USED IN DETERMINING MFLCPR 0.. | |||
(26.01, 2.55)i .... .... co | |||
;2.6 2.4 =ý(40, 2.17)1 2.2 m "-_._____ (60, 2.00) A B (100, 2.00)- r-u 2.0 1.8 1.6 | |||
==REFERENCE:== | ==REFERENCE:== | ||
T.S. 3.4.1, 3.3.4.1, and 3.2.2 1.4 cz) 20 30 40 50 60 70 80 90 100 Core Power (% RATED) CO MCPR OPERATING LIMIT VERSUS CORE POWER CD EOC-RPT INOPERABLE 6 z, | |||
0n lp SINGLE LOOP OPERATION (BOC to EOC)' W' FIGURE 8.2-7 | |||
PPL Rev. 8 PL-NF-0g-002 Rev. 0 Page 46 of 53 Backup Pressure Regulator Inoperable SUSQUEHANNA UNIT 2 TRM/3.2-47 EFFECTIVE DATE 04/17/2009 | |||
V) | |||
SSES UNIT 2 CYCLE 15 4.6 m I I 4.4 .1 4-.-- LEGEND 4.2 4 + 4- CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM c-" | |||
INSERTION TIME 4.0 * + 4-CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.8 4 + 4-3.6 4 -I. | |||
SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES | |||
°wi~._3.4 4 4-4 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 m3,2 N.) | |||
3.0 I 1-USED IN DETERMINING MFLCPR K- (- | |||
: 0. CD 0 | |||
W 2.8 2L 2.6 2.4 rn 2.2 | |||
**11 Ra(30,E2.02) A m | |||
2.0 | |||
-1 -ý-IEFRENE: | |||
.S.3.41, .7., ad 32.2 1.8 m | |||
1.6 C) 1.4 30 40 50 60 70 80 90 100 110 C:) Total Core Flow (MLB/HR) -U (D r-CD <IL MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW CD BACKUP PRESSURE REGULATOR INOPERABLE 0 c )- | |||
SINGLE LOOP OPERATION (BOC to EOC) Oi C.) | |||
FIGURE 8.2-8 | |||
. E SSES UNIT 2 CYCLE 15 | |||
*4 V/) | |||
4.6 I 4 LEGEND 4.4 F 4 N) 4,2 I CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM I | |||
INSERTION TIME 4.0 -(23, 3.87) 1 4 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.81 (23, 3.8 (26, 3.71) ____ | |||
-- | CURVE C: CORE POWER *26% AND CORE FLOW : 50 MLBM/HR 3.6 -__C i~ .8 | ||
__(26, 3.5i8) 3.4 m | |||
SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 3.2 ... (26.01, 3,04)i ARE OPERABLE PER SR 3.7.6.1 AND 3,7.6.2 | |||
-a q A (4,2.73) USED IN DETERMINING MFLCPR (D c:3 "J 2.8 02 L._ | |||
O 2.4 C:) | |||
0 2.4 (60, 2.28) (100,2.28)- | |||
B o2.2 2.0 1.8 -- | |||
==IREFERENCE:== | ==IREFERENCE:== | ||
T.S. 3.4.1, 3.7.8, and 3.2.2I 1.6 1.4 20 30 40 50 60 70 80 90 100 Core Power (% RATED) CD CD MCPR OPERATING LIMIT VERSUS CORE POWER 0 " | |||
02 BACKUP PRESSURE REGULATOR INOPERABLE 0 (40 SINGLE LOOP OPERATION (BOC to EOC) C,, | |||
0 FIGURE 8.2-9 | |||
PPL Rev. 8 PL-NF-09-002 Rev. 0 Page 49 of 53 9.0 POWER / FLOW MAP 9.1 Technical Specification Reference Technical Specification 3.3.1.1 9.2 Description Monitor reactor conditions to maintain THERMAL POWER I core flow outside of Stability Regions I and II of the Power / Flow map, Figure 9.1. | |||
SUSQUEHANNA UNIT 2 TRM/3.2-50 EFFECTIVE DATE 04/17/2009 | If the OPRM Instrumentation is OPERABLE per TS 3.3.1.1, Region I of the Power/ Flow map is considered an immediate exit region. | ||
If the OPRM Instrumentation is inoperable per TS 3.3.1.1, Region I of the Power | |||
/ Flow map is considered an immediate scram region. | |||
Region II of the Power / Flow map is considered an immediate exit region regardless of the operability of the OPRM Instrumentation. | |||
SUSQUEHANNA UNIT 2 TRM/3.2-50 EFFECTIVE DATE 04/17/2009 | |||
PPL Rev. 8 PL-NF-09-002 Rev. 0 Page 50 of 53 19fl 120 I Pupse ii - | |||
.iA... | |||
4~.~ | |||
POWER IFLOW UNIT 120 110- 110 Ijnitial f Date:I STILT REGION '4- APRM Rod Block IFOPIM INOPERABLE.AEAE 4I II Trip Setpoint 100 - SCRAM1AWON-27G-02 100 IF OPRMOPERABLE IMMEDIATE | |||
-EXIT IAW ON-27S-002 r1 rT 1 2-- F S TABILTY REGION IMMEDIATELY EAIT AW ON-27"-OZ 0 L1 -I LIJ__LL 90 90- RESTICTED REGION (As defined in A~ttachment G to 100% | |||
MDAP-QA-0333)r IF ABOVEMELLIA BOUJNDARY, L .L - -I : | |||
IMMEDIAYELY EAITIAWN ON-278-O3.044 4 80 80 1J T -1 T | |||
: 1. 4 4 1- -64Al 4 -1 2 T, j L 12,_: - - L I I LU TT 70 70 rl r -in-,- - r -r: r 1 I 4 44 1. : | |||
IT,, I,-,- - 1111 - r, 1111 I~ r1~ : | |||
L_ | |||
~j. ++ | |||
L A J-:_ -LAJ-I--L J 4 1 1 14 j 60 A | |||
60 0 | |||
CL 60% | |||
4.4..4 Rod Line E 50 50 T* ?J | |||
~1* 4 - 4 4-i F - | |||
] | |||
1 *lFf* | |||
+ -k 4.44- -- 4.-,-' | |||
*4441,i. -:: | |||
4444 T I Friv 1, 4 4 4-4 4. 4 -4 4 I- 1 444 iri i - | |||
rrT4 r"-i. | |||
40 Naturall-Clirculation 40 T1- 4 444 no .. .. r T TI 7-1 rri- | |||
-LIi J_ L Li1 J_ _L L I~ J_- _,L Ll | |||
* I:I .' - ri r -.. | |||
:11-1 L IT I JI -r- r-T T 1-,- r i -i -I- r i -I- r rT 1 -I I- r- r -I -r r -r- | |||
_ LI J.4, L J.J .L]L I J_ _L J - U L I J -1 -t- II i- I- 44 4 | |||
.L _L L 1i J t I4 I4I I I I I I4 I4I I | |||
30 Approx I - - I4 I I 30 One Pump L.J -I- L ILJ J-I L I I I L I I i- L L 1j 4 4I 1 I I 1 30% Speed. -1 -_L2 -J _r 4 4 I- L4-1-4 I I I J - -4-- -4p-4--iI - | |||
7 4444I 44 I4 4 1 1 7r ý 20 App- 20 1- 4' 4.4 4 I -444 | |||
-- I I-1- 4 4ý1ý .:-q -I- ý1,-1_ 1-4-4.41-- -4I-4 Two Pump I II T 1 30% Speed. - F -- FC i' T I -*-FT Approx 4 4 4. 4 4II I I-F Ti-- | |||
4 I. I FIIII -rF, T | |||
;ýT 4 T 71' T - r iri i-Orve Pump I - | |||
10 . . . . . . . . 10 1 pe | |||
.T.4 4 1il 1 rT 1- 1 1- .11 r 7 :1- r T 1r11 - - Fr-1 11 | |||
, .1 j ,I 1 .1 j _1_: L A J - Li I J. LL J.J | |||
-FI 4r 7i 1i 44' r'. I- T -i -I - - r 7 - r , - -r - - L-.rJ-,4 - r r -ri "i..1J L L I J L L .1 i-1 L. L L I ýj F I IL J -1 L I J i -. - T -r4 r T. | |||
0 0 10 20 30 40 50 60 70 80 90 100 110 Total Core Flow (Mlbm/hr) | |||
(for SLO <75% Pump Speed Use Form GO-200-009-2) | |||
Figure 9.1 SSES Unit 2 Cycle 15 Power/ Flow Map SUSQUEHANNA UNIT 2 TRM/3.2-51 EFFECTIVE DATE 04/17/2009 | |||
PPL Rev. 8 PL-NF-09-002 Rev. 0 Page 51 of 53 10.0 OPRM SETPOINTS 10.1 Technical Specification Reference Technical Specification 3.3.1.1 10.2 Description Setpoints for the OPRM Instrumentation are established that will reliably detect and suppress anticipated stability related power oscillations while providing a high degree of confidence that the MCPR Safety limit is not violated. The setpoints are described in Section 2.0 and are listed below: | |||
Sp = 1.12 Np 16 FP = 60 Mlbm / hr SUSQUEHANNA UNIT 2 TRM/3.2-52 EFFECTIVE DATE 04/17/2009 | |||
PPL Rev. 8 PL-NF-09-002 Rev. 0 Page 52 of 53 | |||
==11.0 REFERENCES== | |||
Revision | |||
11.1 The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents: | |||
: 1. XN-NF-81-58(P)(A), Revision 2 and Supplements 1 and 2, "RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model," Exxon Nuclear Company, March 1984. | |||
: 2. EMF-2361(P)(A), Revision 0, "EXEM BWR-2000 ECCS Evaluation Model,". | |||
Framatome ANP, May 2001. | |||
: 3. EMF-2292(P)(A), Revision 0, "ATRIUMT M-10: Appendix K Spray Heat Transfer Coefficients," Siemens Power Corporation, September 2000. | |||
: 4. XN-NF-84-105(P)(A), Volume I and Volume 1 Supplements I and 2, "XCOBRA-T: A Computer Code for BWR Transient Thermal-Hydraulic Core Analysis," Exxon Nuclear Company, February 1987. | |||
: 5. XN-NF-80-19(P)(A), Volume 1 and Supplements 1 and 2, "Exxon Nuclear Methodology for Boiling Water Reactors: Neutronic Methods for Design and Analysis," Exxon Nuclear Company, March 1983. | |||
.'6. XN-NF-80-19(P)(A), Volumes 2, 2A, 2B, and 2C "Exxon Nuclear Methodology for Boiling Water Reactors: EXEM BWR ECCS Evaluation Model," Exxon Nuclear Company, September 1982. | |||
: 7. XN-NF-80-19(P)(A), Volume 3 Revision 2 "Exxon Nuclear Methodology for Boiling Water Reactors Thermex: Thermal Limits Methodology Summary Description," Exxon Nuclear Company, January 1987. | |||
: 8. XN-NF-80-1 9(P)(A), Volume 4, Revision 1, "Exxon Nuclear Methodology for Boiling Water Reactors: Application of the ENC Methodology to BWR Reloads," Exxon Nuclear Company, June 1986. | |||
: 9. XN-NF-85-67(P)(A), Revision 1, "Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel," Exxon Nuclear Company, Inc., | |||
September 1986. | |||
: 10. ANF-524(P)(A), Revision 2 and Supplements I and 2, "Advanced Nuclear Fuels Corporation Critical Power Methodology for Boiling Water Reactors," | |||
November 1990. | |||
: 11. NE-092-001 A, Revision 1, "Licensing Topical Report for Power Uprate With Increased Core Flow," Pennsylvania Power & Light Company, December 1992 and NRC SER (November 30, 1993). | |||
SUSQUEHANNA UNIT 2 TRM/3.2-53 EFFECTIVE DATE 0411712009 | |||
PPL Rev. 8 PL-NF-09-002 Rev. 0 Page 53 of 53 | |||
: 12. ANF-89-98(PXA) Revision 1 and Supplement 1, "Generic Mechanical Design Criteria for BWR Fuel Designs," Advanced Nuclear Fuels Corporation, May 1995. | |||
NOTE-------------- | : 13. EMF-2209(P)(A), Revision 2, "SPCB Critical Power Correlation," Framatome ANP, September 2003. | ||
Only required to be met when an alternate method to detect and suppress thermal hydraulic instability oscillations is required by LCO 3.3.1.1 Required Action 1.1.Verify total core flow as a function of THERMAL POWER is outside of Region I and II of the Power Flow map as specified in the COLR.TRS 3.3.9.2 Perform CHANNEL CALIBRATION on the LPRM 24 months Upscale alarm 24 months TRS 3.3.9.3 Verify OPRM parameter setpoints and settings are within limits SUSQUEHANNA | : 14. EMF-85-74(P)(A), Revision 0, Supplement 1(P)(A) and Supplement 2(P)(A), | ||
-UNIT 2 TRM / 3.3-21 c EFFECTIVE DATE 03/27/2007 OPRM Instrumentation 3.3.9 | "RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model," | ||
& GRBA | Siemens Power Corporation, February 1998. | ||
& GRBA Amplitude Trip Setpoint/ABA | : 15. EMF-2158(P)(A), Revision 0, "Siemens Power Corporation Methodology for Boiling Water Reactors: Evaluation and Validation of CASMO-4/Microburn-B2," Siemens Power Corporation, October 1999. | ||
-UNIT 2 TRM / 3.3-21d EFFECTIVE DATE 03/27/2007 OPRM Instrumentation PPL Rev. 3 B 3.3.9 B 3.3.9 OPRM Instrumentation BASES TRO The OPRM system configuration governs its operation in accordance with the licensing analysis. | : 16. EMF-CC-074(P)(A), Volume 4, Revision 0, "BWR Stability Analysis - | ||
Several configuration parameters are intrinsic to the trip function safety setpoint bases or provide settings for defense-in-depth algorithm features that are not assumed in the basis for the protection system safety analysis (Reference 2, Reference 3).Each of the setting values may be used as the process setpoint or device setting without further adjustment for uncertainties. | Assessment of STAIF with Input from MICROBURN-B2," Siemens Power Corporation, August 2000. | ||
Setpoints and Settings Bases TOL(_F) Period Tolerance The specified range of values for the period tolerance has been demonstrated to provide continuous confirmations upon transition from stable reactor operation to a growing reactor instability. | : 17. NEDO-32465-A, "BWROG Reactor Core Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications," August 1996. | ||
A range of values is provided to allow system tuning to avoid spurious alarms on period confirmations. | : 18. ANF-913(P)(A), Volume 1 Revision 1 and Volume I Supplements 2, 3, and 4, "COTRANSA2: A Computer Program for Boiling Water Reactor Transient Analyses," Advanced Nuclear Fuels Corporation, August 1990. | ||
Limiting the setpoint adjustment range provides assurance that the Period Based Detection Algorithm will provide sufficient confirmations for a growing instability. | : 19. ANF-1358(P)(A), Revision 3, "The Loss of Feedwater Heating Transient in Boiling Water Reactors," Framatome ANP, September 2005. | ||
f Conditioning Filter Cutoff Frequency The specified value for the Conditioning Filter Cutoff Frequency has been demonstrated to provide continuous confirmations upon transition from stable reactor operation to a growing reactor instability. | SUSQUEHANNA UNIT 2 TRM/3 .2-54 EFFECTIVE DATE 04/17/2009 | ||
Setting minimizes impact on signal amplitude and provides assurance that the Period Based Detection Algorithm will provide sufficient confirmations for a growing instability. | |||
O Tmin Oscillation Period Lower Time Limit Tmax Oscillation Period Upper Time Limit The Oscillation Period Time Limit parameters establish the range of detectable oscillation periods of OPRM cell signals for signal oscillations associated with reactor core thermal-hydraulic instability.(continued) | OPRM Instrumentation PPL Rev. 3 3.3.9 3.3 Instrumentation 3.3.9 OPRM Instrumentation Configuration TRO 3.3.9 Oscillation Power Range Monitor (OPRM) supporting setpoints and settings shall be within the specified limits. | ||
SUSQUEHANNA | APPLICABILITY: Thermal POWER Ž23% RTP ACTIONS | ||
-UNIT 2 TRM / B 3.3-18 EFFECTIVE DATE 03/27/2007 OPRM Instrumentation PPL Rev. 3 B 3.3.9 B 3.3.9 OPRM Instrumentation BASES TRO LPRMmin (continued) | ------------------ NOTE ------------------------------------------------------------- | ||
This value determines the availability and resulting sensitivity of cells in the reactor core in the event of LPRM channel failures. | : 1. Separate Condition entry is allowed for each channel CONDITION REQUIRED ACTION COMPLETION TIME A. OPRM Setpoints and A.1 Enter the condition referenced in Immediately Settings not in accordance Table 3.3.9-1 for the parameter with Table 3.3.9-1 B. As required by Required B.1 Declare affected OPRM channel Immediately Action A.1 and referenced inoperable. | ||
The minimum LPRM per cell parameter is an assumption of the OPRM trip setpoint (Sp) basis calculation. | in Table 3.3.9.1 C. As required by Required C.1 Restore the OPRM Setpoints and 120 days Action A.1 and referenced Settings to within the specified in Table 3.3.9-1 limits. | ||
Amplitude and Growth Rate Based Algorithm Parameters S1 Peak Threshold Setpoint/ABA | OR C.2 Declare affected OPRM channel Immediately inoperable. | ||
& GRBA S2 Valley Threshold Setpoint/ABA | D. Alternate method to detect D.1 Initiate monitoring to detect entry Immediately and suppress thermal into Conditions E, F, and/or G. | ||
& GRBA Smax Amplitude Trip Setpoint/ABA DR3 Growth Rate Factor Setpoint/GRBA These parameters calibrate the Amplitude and Growth Rate Based Algorithm, described in References 2 and 3, which provides an OPRM trip output to the Reactor Protection System. The OPRM design and licensing basis takes no credit for the Amplitude and Growth Rate Based Algorithm. | hydraulic instability oscillations required by LCO 3.3.1.1 Required Action 1.1 (continued) | ||
The algorithm is provided as a defense-in-depth feature in the event of unanticipated power oscillations. | SUSQUEHANNA - UNIT 2 TRM / 3.3-21 EFFECTIVE DATE 04/15/2009 | ||
These Amplitude and Growth Rate Based Algorithm Parameters are considered sufficient to provide backup protection and to avoid spurious trips by maximizing margin to expected operating conditions and transients. | |||
ACTIONS The required actions assure that the system settings that support the Period Based Algorithm setpoint analysis, and those parameters that define the Amplitude and Growth Rate Based Algorithm are returned in a timely manner to the values assumed in the analysis (Reference 2, Reference | OPRM Instrumentation PPL Rev. 3 3.3.9 ACTIONS (continued) | ||
CONDITION REQUIRED ACTION COMPLETION TIME E. ------- NOTE ----------- | |||
SUSQUEHANNA | Only applicable as required by Required Action D.1 Total core flow as a E.1 Place reactor mode switch in Immediately function of THERMAL the shutdown position. | ||
-UNIT 2 TRM / B 3.3-19 EFFECTIVE DATE 03/27/2007 OPRM Instrumentation B 3.3.9 | POWER within Region I of the Power Flow map as specified in the COLR. | ||
Note 1 has been provided to modify the ACTIONS related to affected OPRM channels. | OR Total core flow as a function of THERMAL POWER within Region II of the Power Flow map as specified in the COLR and less than 50% of required LPRM upscale alarms OPERABLE F. - -------- NOTE----- | ||
Technical Specification Section 1.3, Completion Times, specifies that once a Condition has been entered, subsequent divisions, subsystems, components, or variables expressed in the Condition discovered to be inoperable or not within limits will not result in separate entry into the Condition. | Only applicable as required by Required Action D.1 and when in Region II of the Power Flow map as specified in the COLR. | ||
Technical Specification Section 1.3 also specifies that Required Actions of the Condition continue to apply for each additional failure, with Completion Times based on initial entry into the Condition. | Two or more APRM F.1 Place the reactor mode switch Immediately readings oscillating with in the shutdown position. | ||
However, the Required Actions for affected OPRM channels provide appropriate compensatory measures. | one or more oscillating | ||
As such, a Note has been provided that allows separate Condition entry for each affected OPRM channel.B.1 Several parameter settings are essential for the proper operation of the OPRM period-based trip algorithm. | >_10% of RTP peak-to-peak OR (continued) | ||
The permissible values of Period Confirmation Tolerance, Averaging Filter time constant, Conditioning Filter Cutoff Frequency, and minimum operable LPRM per cell parameters are limited by the setpoint basis calculations and system transient response analysis. | SUSQUEHANNA - UNIT 2 TRM / 3.3-21 a EFFECTIVE DATE 11/15/2004 | ||
The Minimum and Maximum Oscillation Period settings limit the algorithm window to the cell signal resonances that can be associated with unstable thermal-hydraulic conditions. | |||
Because the ability of the OPRM channel to perform its safety function is affected by these parameter settings, the affected OPRM channel must be considered inoperable when these conditions are not met.Operability is evaluated for each inoperable channel and Required Actions taken in accordance with LCO 3.3.1.1.C.1 The design objective for the Amplitude and Growth Rate Based Algorithms is to provide automatic action to limit the size of these unanticipated oscillations, thereby preventing fuel cladding damage. Several parameter settings define the function of the Amplitude and Growth Rate Based Algorithm. | OPRM Instrumentation PPL Rev. 3 3.3.9 CONDITION REQUIRED ACTION COMPLETION TIME | ||
The OPRM design and licensing basis takes no credit for the Amplitude and Growth Rate Based Algorithm, which is provided as a defense-in-depth feature in the event of unanticipated oscillations.(continued) | + -I F. (continued) | ||
SUSQUEHANNA | Two or more LPRM upscale alarms activating and deactivating with a period Ž1 second and *5 seconds. | ||
-UNIT 2 TRM / B 3.3-19a EFFECTIVE DATE 03/27/2007 OPRM Instrumentation PPL Rev. 3 B 3.3.9 B 3.3.9 OPRM Instrumentation BASES ACTIONS C.1 (continued) | OR Sustained LPRM 2 oscillations >10 W/cm peak-to-peak with a period | ||
Because the ability of the OPRM channel to perform its safety function is not affected by these parameter settings, the affected OPRM channel need not be immediately considered inoperable when these conditions are not met.These parameters are to be maintained for conformance with the licensing requirement of a defense-in-depth feature in addition to the licensed OPRM trip function. | Ž1 second and *<5 seconds. | ||
This is corrected by returning the parameters to conformance within 120 days of identification. | + | ||
Since the Amplitude and Growth Rate Based parameters affect only the defense-in-depth response within each channel, failure to maintain the proper parameters in the channel affects only the operability of that channel.D.1 This Action is to be taken | G. NOTE--------- | ||
When operating in Region I of the Power / Flow map specified in the COLR, or when operating in Region II of the Power / Flow map specified in the COLR with less than 50% of the required LPRM upscale alarms OPERABLE, the potential for thermal-hydraulic oscillations is greatly increased and sufficient margin may not be available for operator response to suppress potential thermal-hydraulic oscillations. | Only applicable as required by Required Action D.1. | ||
Therefore, the reactor mode switch must be immediately placed in the shutdown position. | Total core flow as a G.1 Initiate action to restore total core Immediately function of THERMAL flow as a function of THERMAL POWER is within Region II POWER outside of Region II. | ||
Action is taken immediately to place the plant in a condition where any potential for thermal-hydraulic instabilities will be terminated. | of the Power Flow map as specified in the COLR. | ||
H. Less than 50% of the H.1 Post sign on the reactor control 1 hour required LPRM Upscale panel that less than 50% of the Alarms are OPERABLE LPRM Upscale Alarms are I_ OPERABLE. | |||
SUSQUEHANNA - UNIT 2 TRM /3.3-21 b EFFECTIVE DATE 03/27/2007 | |||
OPRM Instrumentation PPL Rev. 3 3.3.9 TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE FREQUENCY TRS 3.3.9.1 ------------------- NOTE-------------- | |||
Only required to be met when an alternate method to detect and suppress thermal hydraulic instability oscillations is required by LCO 3.3.1.1 Required Action 1.1. | |||
Verify total core flow as a function of THERMAL POWER is outside of Region I and II of the Power Flow map as specified in the COLR. | |||
TRS 3.3.9.2 Perform CHANNEL CALIBRATION on the LPRM 24 months Upscale alarm 24 months TRS 3.3.9.3 Verify OPRM parameter setpoints and settings are within limits SUSQUEHANNA - UNIT 2 TRM / 3.3-21 c EFFECTIVE DATE 03/27/2007 | |||
OPRM Instrumentation PPL Rev. 3 3.3.9 Table 3.3.9-1 OPRM SETPOINTS AND SETTINGS CONDITIONS REFERENCE D FROM OPRM REQUIRED PARAMETER DESCRIPTION ACTION A.1 VALUE | |||
: 1. TOL (E) Period Tolerance B Ž0.10 and | |||
< 0.30 sec | |||
: 2. fc Conditioning Filter Cutoff Frequency B 1.5 Hz | |||
: 3. Tmin Oscillation Period Lower Time Limit B _ 1.0 and | |||
*1.2 sec | |||
: 4. Tmax Oscillation Period Upper Time Limit B 3.5 sec | |||
: 5. LPRMmin Minimum LRPMs/Cell Required for Cell B Ž2 Operability | |||
: 6. S1 Peak Threshold Setpoint/ABA & GRBA C Ž1.10 and | |||
*1.20 | |||
: 7. S2 Valley Threshold Setpoint/ABA & GRBA C _ 0.85 and | |||
_ 0.95 | |||
: 8. Smax Amplitude Trip Setpoint/ABA C Ž1.30 and | |||
< 1.50 | |||
: 9. DR3 Growth Rate Factor Setpoint/GRBA C > 1.30 and | |||
*1.60 SUSQUEHANNA - UNIT 2 TRM / 3.3-21d EFFECTIVE DATE 03/27/2007 | |||
OPRM Instrumentation PPL Rev. 3 B 3.3.9 B 3.3.9 OPRM Instrumentation BASES TRO The OPRM system configuration governs its operation in accordance with the licensing analysis. Several configuration parameters are intrinsic to the trip function safety setpoint bases or provide settings for defense-in-depth algorithm features that are not assumed in the basis for the protection system safety analysis (Reference 2, Reference 3). | |||
Each of the setting values may be used as the process setpoint or device setting without further adjustment for uncertainties. | |||
Setpoints and Settings Bases TOL(_F) Period Tolerance The specified range of values for the period tolerance has been demonstrated to provide continuous confirmations upon transition from stable reactor operation to a growing reactor instability. A range of values is provided to allow system tuning to avoid spurious alarms on period confirmations. Limiting the setpoint adjustment range provides assurance that the Period Based Detection Algorithm will provide sufficient confirmations for a growing instability. | |||
f Conditioning Filter Cutoff Frequency The specified value for the Conditioning Filter Cutoff Frequency has been demonstrated to provide continuous confirmations upon transition from stable reactor operation to a growing reactor instability. Setting minimizes impact on signal amplitude and provides assurance that the Period Based Detection Algorithm will provide sufficient confirmations for a growing instability. | |||
O Tmin Oscillation Period Lower Time Limit Tmax Oscillation Period Upper Time Limit The Oscillation Period Time Limit parameters establish the range of detectable oscillation periods of OPRM cell signals for signal oscillations associated with reactor core thermal-hydraulic instability. | |||
(continued) | |||
SUSQUEHANNA - UNIT 2 TRM / B 3.3-18 EFFECTIVE DATE 03/27/2007 | |||
OPRM Instrumentation PPL Rev. 3 B 3.3.9 B 3.3.9 OPRM Instrumentation BASES TRO LPRMmin (continued) | |||
This value determines the availability and resulting sensitivity of cells in the reactor core in the event of LPRM channel failures. The minimum LPRM per cell parameter is an assumption of the OPRM trip setpoint (Sp) basis calculation. | |||
Amplitude and Growth Rate Based Algorithm Parameters S1 Peak Threshold Setpoint/ABA & GRBA S2 Valley Threshold Setpoint/ABA & GRBA Smax Amplitude Trip Setpoint/ABA DR3 Growth Rate Factor Setpoint/GRBA These parameters calibrate the Amplitude and Growth Rate Based Algorithm, described in References 2 and 3, which provides an OPRM trip output to the Reactor Protection System. The OPRM design and licensing basis takes no credit for the Amplitude and Growth Rate Based Algorithm. | |||
The algorithm is provided as a defense-in-depth feature in the event of unanticipated power oscillations. These Amplitude and Growth Rate Based Algorithm Parameters are considered sufficient to provide backup protection and to avoid spurious trips by maximizing margin to expected operating conditions and transients. | |||
ACTIONS The required actions assure that the system settings that support the Period Based Algorithm setpoint analysis, and those parameters that define the Amplitude and Growth Rate Based Algorithm are returned in a timely manner to the values assumed in the analysis (Reference 2, Reference 3) or that the affected channel is declared inoperable and the applicable Required Action of LCO 3.3:1.1 is then entered, or an alternate method to detect and suppress thermal hydraulic instability oscillations is employed. | |||
(continued) | |||
SUSQUEHANNA - UNIT 2 TRM / B 3.3-19 EFFECTIVE DATE 03/27/2007 | |||
OPRM Instrumentation PPL Rev. 3 B 3.3.9 B 3.3.9 OPRM Instrumentation BASES ACTIONS Note 1 has been provided to modify the ACTIONS related to affected OPRM (continued) channels. Technical Specification Section 1.3, Completion Times, specifies that once a Condition has been entered, subsequent divisions, subsystems, components, or variables expressed in the Condition discovered to be inoperable or not within limits will not result in separate entry into the Condition. Technical Specification Section 1.3 also specifies that Required Actions of the Condition continue to apply for each additional failure, with Completion Times based on initial entry into the Condition. However, the Required Actions for affected OPRM channels provide appropriate compensatory measures. As such, a Note has been provided that allows separate Condition entry for each affected OPRM channel. | |||
B.1 Several parameter settings are essential for the proper operation of the OPRM period-based trip algorithm. The permissible values of Period Confirmation Tolerance, Averaging Filter time constant, Conditioning Filter Cutoff Frequency, and minimum operable LPRM per cell parameters are limited by the setpoint basis calculations and system transient response analysis. The Minimum and Maximum Oscillation Period settings limit the algorithm window to the cell signal resonances that can be associated with unstable thermal-hydraulic conditions. | |||
Because the ability of the OPRM channel to perform its safety function is affected by these parameter settings, the affected OPRM channel must be considered inoperable when these conditions are not met. | |||
Operability is evaluated for each inoperable channel and Required Actions taken in accordance with LCO 3.3.1.1. | |||
C.1 The design objective for the Amplitude and Growth Rate Based Algorithms is to provide automatic action to limit the size of these unanticipated oscillations, thereby preventing fuel cladding damage. Several parameter settings define the function of the Amplitude and Growth Rate Based Algorithm. The OPRM design and licensing basis takes no credit for the Amplitude and Growth Rate Based Algorithm, which is provided as a defense-in-depth feature in the event of unanticipated oscillations. | |||
(continued) | |||
SUSQUEHANNA - UNIT 2 TRM / B 3.3-19a EFFECTIVE DATE 03/27/2007 | |||
OPRM Instrumentation PPL Rev. 3 B 3.3.9 B 3.3.9 OPRM Instrumentation BASES ACTIONS C.1 (continued) | |||
Because the ability of the OPRM channel to perform its safety function is not affected by these parameter settings, the affected OPRM channel need not be immediately considered inoperable when these conditions are not met. | |||
These parameters are to be maintained for conformance with the licensing requirement of a defense-in-depth feature in addition to the licensed OPRM trip function. This is corrected by returning the parameters to conformance within 120 days of identification. | |||
Since the Amplitude and Growth Rate Based parameters affect only the defense-in-depth response within each channel, failure to maintain the proper parameters in the channel affects only the operability of that channel. | |||
D.1 This Action is to be taken ifthe Period Based Detection Algorithm trip function is not available in accordance with LCO 3.3.1.1, and initiation of an alternate method to Detect and Suppress thermal hydraulic instability oscillations is required by the referenced LCO Required Actions. The applicable Conditions are entered as required. | |||
E.1 As directed from Required Action D.1, this Action provides preemptive protection through Power/Flow Map operating restrictions. | |||
When operating in Region I of the Power / Flow map specified in the COLR, or when operating in Region II of the Power / Flow map specified in the COLR with less than 50% of the required LPRM upscale alarms OPERABLE, the potential for thermal-hydraulic oscillations is greatly increased and sufficient margin may not be available for operator response to suppress potential thermal-hydraulic oscillations. Therefore, the reactor mode switch must be immediately placed in the shutdown position. Action is taken immediately to place the plant in a condition where any potential for thermal-hydraulic instabilities will be terminated. | |||
Identification of which LPRMs are Upscale can be determined by a number of methods in the control room. The most commonly used method is visual and audible observance of the LPRM Upscale Annunciator and Alarm followed with identification of the individual LPRMs feeding the annunciation/ | Identification of which LPRMs are Upscale can be determined by a number of methods in the control room. The most commonly used method is visual and audible observance of the LPRM Upscale Annunciator and Alarm followed with identification of the individual LPRMs feeding the annunciation/ | ||
alarm. Identification of individual LPRM Upscale is possible by observance of the various Operator display assemblies and control panel monitors including PICSY.(continued) | alarm. Identification of individual LPRM Upscale is possible by observance of the various Operator display assemblies and control panel monitors including PICSY. | ||
SUSQUEHANNA | (continued) | ||
-UNIT 2 TRM / B 3.3-19b EFFECTIVE DATE 03/27/2007 OPRM Instrumentation PPL Rev. 3 B 3.3.9 B 3.3.9 OPRM Instrumentation BASES ACTIONS F.1 (continued) | SUSQUEHANNA - UNIT 2 TRM / B 3.3-19b EFFECTIVE DATE 03/27/2007 | ||
OPRM Instrumentation PPL Rev. 3 B 3.3.9 B 3.3.9 OPRM Instrumentation BASES ACTIONS F.1 (continued) | |||
As directed from Required Action D.1, this Action provides guidance for Operator action in response to thermal-hydraulic instability oscillations. | As directed from Required Action D.1, this Action provides guidance for Operator action in response to thermal-hydraulic instability oscillations. | ||
When operating in Region II of the Power/Flow map specified in the COLR immediate response is necessary when there are indications that thermal hydraulic oscillations are occurring as defined in the CONDITION. | When operating in Region II of the Power/Flow map specified in the COLR immediate response is necessary when there are indications that thermal hydraulic oscillations are occurring as defined in the CONDITION. | ||
LPRM upscale alarms are required to detect reactor core thermal-hydraulic instability events. The criteria for determining which LPRM upscale alarms are required is based on assignment of these alarms to designated core zones. These core zones consist of the level A, B, and C alarms in 4 or 5 adjacent LPRM strings. The number and location of LPRM strings in each zone assure that with 50% or more of the associated LPRM upscale alarms OPERABLE sufficient monitoring capability is available to detect core wide and regional oscillations. | LPRM upscale alarms are required to detect reactor core thermal-hydraulic instability events. The criteria for determining which LPRM upscale alarms are required is based on assignment of these alarms to designated core zones. These core zones consist of the level A, B, and C alarms in 4 or 5 adjacent LPRM strings. The number and location of LPRM strings in each zone assure that with 50% or more of the associated LPRM upscale alarms OPERABLE sufficient monitoring capability is available to detect core wide and regional oscillations. Operating plant instability data is used to determine the specific LPRM strings assigned to each zone. | ||
Operating plant instability data is used to determine the specific LPRM strings assigned to each zone.Identification of which LPRMs are Upscale can be determined by a number of methods in the control room. The most commonly used method is visual and audible observance of the LPRM Upscale Annunciator and Alarm followed with identification of the individual LPRMs feeding the annunciation/ | Identification of which LPRMs are Upscale can be determined by a number of methods in the control room. The most commonly used method is visual and audible observance of the LPRM Upscale Annunciator and Alarm followed with identification of the individual LPRMs feeding the annunciation/ | ||
alarm. Identification of individual LPRM Upscale is possible by observance of the various Operator display assemblies and control panel monitors including PICSY.G.1 As directed from Required Action D.1, this Action provides guidance for Operator action in response to operation in conditions that may lead to thermal-hydraulic instability oscillations. | alarm. Identification of individual LPRM Upscale is possible by observance of the various Operator display assemblies and control panel monitors including PICSY. | ||
When operating in Region II of the Power/Flow map specified in the COLR, the potential for thermal-hydraulic oscillations is increased and sufficient margin may not be available for operator response to suppress potential thermal-hydraulic oscillations. | G.1 As directed from Required Action D.1, this Action provides guidance for Operator action in response to operation in conditions that may lead to thermal-hydraulic instability oscillations. | ||
Therefore, action must be initiated immediately to restore operation outside of Regions II of the Power/Flow map specified in the COLR. This can be accomplished by either decreasing THERMAL POWER with control rod insertion or increasing core flow by increasing recirculation pump speed. The starting of a recirculation pump will not be used as a means to exit the excluded Regions because the starting of a recirculation pump with the plant operating above the 70% rod line is prohibited due to potential instability problems.(continued) | When operating in Region II of the Power/Flow map specified in the COLR, the potential for thermal-hydraulic oscillations is increased and sufficient margin may not be available for operator response to suppress potential thermal-hydraulic oscillations. Therefore, action must be initiated immediately to restore operation outside of Regions II of the Power/Flow map specified in the COLR. This can be accomplished by either decreasing THERMAL POWER with control rod insertion or increasing core flow by increasing recirculation pump speed. The starting of a recirculation pump will not be used as a means to exit the excluded Regions because the starting of a recirculation pump with the plant operating above the 70% rod line is prohibited due to potential instability problems. | ||
SUSQUEHANNA | (continued) | ||
-UNIT 2 TRM / B 3.3-19c EFFECTIVE DATE 04/17/2009 OPRM Instrumentation PPL Rev. 3 B 3.3.9 B 3.3.9 OPRM Instrumentation BASES ACTIONS H.1 (continued) | SUSQUEHANNA - UNIT 2 TRM / B 3.3-19c EFFECTIVE DATE 04/17/2009 | ||
The LPRMs provide a capability to monitor power in selected locations of the reactor core. The LPRM Upscale Alarm Instrumentation provides information concerning local power oscillations. | |||
Condition F requires a reactor scram when operating in Region II of the Power/Flow map specified in the COLR with indications that thermal hydraulic oscillations are occurring. | OPRM Instrumentation PPL Rev. 3 B 3.3.9 B 3.3.9 OPRM Instrumentation BASES ACTIONS H.1 (continued) | ||
The number and location of LPRM strings in each zone assures that with 50% or more of the associated LPRM upscale alarms OPERABLE any power oscillations which could occur would be detected and proper actions can be taken.Identification, of which LPRMs are Upscale can be determined by a number of methods in the control room. The most commonly used method is visual and audible observance of the LPRM Upscale Annunciator and Alarm followed with identification of the individual LPRMs feeding the annunciation/ | The LPRMs provide a capability to monitor power in selected locations of the reactor core. The LPRM Upscale Alarm Instrumentation provides information concerning local power oscillations. Condition F requires a reactor scram when operating in Region II of the Power/Flow map specified in the COLR with indications that thermal hydraulic oscillations are occurring. The number and location of LPRM strings in each zone assures that with 50% or more of the associated LPRM upscale alarms OPERABLE any power oscillations which could occur would be detected and proper actions can be taken. | ||
alarm. Identification of individual LPRM Upscale is possible by observance of the various Operator display assemblies and control panel monitors including PICSY.A sign is posted in the Control Room to ensure that plant operators are aware of the system condition if a plant transient results in the plant entering into the instability region.TRS TRS 3.3.9.1 Required only when the OPRM trip function is not available, this TRS ensures the combination of core flow and THERMAL POWER are within required limits to prevent uncontrolled thermal hydraulic oscillations by ensuring the recirculation loops are within the limits established by the Power / Flow map specified in the COLR. At low recirculation flows and high reactor power, the reactor exhibits increased susceptibility to thermal-hydraulic instability. | Identification, of which LPRMs are Upscale can be determined by a number of methods in the control room. The most commonly used method is visual and audible observance of the LPRM Upscale Annunciator and Alarm followed with identification of the individual LPRMs feeding the annunciation/ | ||
The Power / Flow map specified in the COLR is based on guidance provided in References 7, 8, and 9 which also provided the guidance on how to respond to operation in these conditions. | alarm. Identification of individual LPRM Upscale is possible by observance of the various Operator display assemblies and control panel monitors including PICSY. | ||
The 24 hour Frequency is based on operating experience and the operators inherent knowledge of the current reactor status, including significant changes in THERMAL POWER and core flow to ensure the requirements are constantly met.TRS 3.3.9.2 This TRS is to be performed at the specified Frequency to ensure that the LPRM Upscale Alarm Instrumentation are maintained OPERABLE.(continued) | A sign is posted in the Control Room to ensure that plant operators are aware of the system condition if a plant transient results in the plant entering into the instability region. | ||
SUSQUEHANNA | TRS TRS 3.3.9.1 Required only when the OPRM trip function is not available, this TRS ensures the combination of core flow and THERMAL POWER are within required limits to prevent uncontrolled thermal hydraulic oscillations by ensuring the recirculation loops are within the limits established by the Power / Flow map specified in the COLR. At low recirculation flows and high reactor power, the reactor exhibits increased susceptibility to thermal-hydraulic instability. The Power / Flow map specified in the COLR is based on guidance provided in References 7, 8, and 9 which also provided the guidance on how to respond to operation in these conditions. The 24 hour Frequency is based on operating experience and the operators inherent knowledge of the current reactor status, including significant changes in THERMAL POWER and core flow to ensure the requirements are constantly met. | ||
-UNIT 2 TRM / B 3.3-19d EFFECTIVE DATE 03/27/2007 OPRM Instrumentation B 3.3.9 | TRS 3.3.9.2 This TRS is to be performed at the specified Frequency to ensure that the LPRM Upscale Alarm Instrumentation are maintained OPERABLE. | ||
The parameter setpoint verification surveillance compares the desired settings and setpoints to the values contained in the processor memory.This surveillance is required to assure that the settings are maintained in accordance with the setpoint analysis. | (continued) | ||
The frequency is based on the OPRM CALIBRATION frequency per SR 3.3.1.1.18. | SUSQUEHANNA - UNIT 2 TRM / B 3.3-19d EFFECTIVE DATE 03/27/2007 | ||
REFERENCES | |||
OPRM Instrumentation PPL Rev. 3 B 3.3.9 B 3.3.9 OPRM Instrumentation BASES TRS TRS 3.3.9.3 (continued) | |||
The parameter setpoint verification surveillance compares the desired settings and setpoints to the values contained in the processor memory. | |||
This surveillance is required to assure that the settings are maintained in accordance with the setpoint analysis. The frequency is based on the OPRM CALIBRATION frequency per SR 3.3.1.1.18. | |||
REFERENCES 1. NEDO-31960-A, BWROG Long Term Solution Licensing Methodology | |||
: 2. NEDO-31960-A, Supp. 1, BWROG Long Term Solution Licensing Methodology | : 2. NEDO-31960-A, Supp. 1, BWROG Long Term Solution Licensing Methodology | ||
: 3. NEDO-32465-A, BWROG Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology and Reload Applications | : 3. NEDO-32465-A, BWROG Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology and Reload Applications | ||
: 4. Deleted 5. Generic Letter 94-02, Long-Term Solutions and Upgrade Of Interim Operating Recommendations for Thermal-Hydraulic Instabilities in Boiling Water Reactors 6. LCO 3.3.1.1, Reactor Protection System (RPS) Instrumentation | : 4. Deleted | ||
: 7. GE Service Information Letter No. 380, "BWR Core Thermal Hydraulic Stability," Revision 1, February 10, 1984 8. Letter, L. A. England to M. J. Virgilio, "BWR Owner's Group Guidelines for Stability Interim Corrective Action," June 6, 1994 9. EMF-CC-074(P)(A), Volume 4, Revision 0, "BWR Stability Analysis: Assessment of STAIF with Input from MICROBURN-B2," November 1999 10. NEDC-3241OP-A, "Nuclear Measurement Analysis and Control Power Range Neutron Monitor (NUMAC PRNM) Retrofit Plus Option III Stability Trip Function" SUSQUEHANNA | : 5. Generic Letter 94-02, Long-Term Solutions and Upgrade Of Interim Operating Recommendations for Thermal-Hydraulic Instabilities in Boiling Water Reactors | ||
-UNIT 2 TRM / B 3.3-19e EFFECTIVE DATE 03/27/2007 Reactor Recirculation Flow and Rod Line Limit 3.4.4 | : 6. LCO 3.3.1.1, Reactor Protection System (RPS) Instrumentation | ||
MODES 1, 2, 3, and 4 during recirculation pump start.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the TRO A. 1 Restore parameter(s) to Prior to recirculation not met within limits pump start TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE FREQUENCY TRS 3.4.4.1 Verify the operating loop flow rate is ___ 50% of rated Once within 15 loop flow rate and that the reactor is operating at a minutes prior to each THERMAL POWER/core flow condition below the recirculation pump 70% rod line shown the Power Flow map specified in start the COLR.SUSQUEHANNA UNIT 2 TRM / 3.4-12 EFFECTIVE DATE 04/17/2009}} | : 7. GE Service Information Letter No. 380, "BWR Core Thermal Hydraulic Stability," Revision 1, February 10, 1984 | ||
: 8. Letter, L. A. England to M. J. Virgilio, "BWR Owner's Group Guidelines for Stability Interim Corrective Action," June 6, 1994 | |||
: 9. EMF-CC-074(P)(A), Volume 4, Revision 0, "BWR Stability Analysis: | |||
Assessment of STAIF with Input from MICROBURN-B2," November 1999 | |||
: 10. NEDC-3241OP-A, "Nuclear Measurement Analysis and Control Power Range Neutron Monitor (NUMAC PRNM) Retrofit Plus Option III Stability Trip Function" SUSQUEHANNA - UNIT 2 TRM / B 3.3-19e EFFECTIVE DATE 03/27/2007 | |||
Reactor Recirculation Flow and Rod Line Limit PPL Rev. 2 3.4.4 3.4 Reactor Coolant System (RCS) 3.4.4 Reactor Recirculation Flow and Rod Line Limit TRO 3.4.4 Operating loop flow rate shall be < 50% of rated loop flow rate and the reactor shall be operating at a THERMAL POWER/core flow condition below the 70% rod line shown in the Power Flow map specified in the I. | |||
COLR. | |||
APPLICABILITY: MODES 1, 2, 3, and 4 during recirculation pump start. | |||
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the TRO A. 1 Restore parameter(s) to Prior to recirculation not met within limits pump start TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE FREQUENCY TRS 3.4.4.1 Verify the operating loop flow rate is ___ | |||
50% of rated Once within 15 loop flow rate and that the reactor is operating at a minutes prior to each THERMAL POWER/core flow condition below the recirculation pump 70% rod line shown the Power Flow map specified in start the COLR. | |||
SUSQUEHANNA UNIT 2 TRM / 3.4-12 EFFECTIVE DATE 04/17/2009}} | |||
Latest revision as of 12:15, 12 March 2020
| ML091420374 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 05/15/2009 |
| From: | Susquehanna |
| To: | Gerlach R Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML091420374 (116) | |
Text
May. 15, 2009 Page I of 3 MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2009-23231 USER INFORMATION:
GERLACH*ROSE M EMPL#:028401 CA#: 0363 Address: NUCSA2 Phone#: 254-3194 TRANSMITTAL INFORMATION:
TO: GERLACH*ROSE M 05/15/2009 LOCATION: USNRC FROM: NUCLEAR RECORDS DOCUMENT CONTROL CENTER (NUCSA-2)
THE FOLLOWING CHANGES HAVE OCCURRED TO THE HARDCOPY OR ELECTRONIC MANUAL ASSIGNED TO YOU. HARDCOPY USERS MUST ENSURE THE DOCUMENTS PROVIDED MATCH THE INFORMATION ON THIS TRANSMITTAL. WHEN REPLACING THIS MATERIAL IN YOUR HARDCOPY MANUAL, ENSURE THE UPDATE DOCUMENT ID IS THE SAME DOCUMENT ID YOU'RE REMOVING FROM YOUR MANUAL. TOOLS FROM THE HUMAN PERFORMANCE TOOL BAG SHOULD BE UTILIZED TO ELIMINATE THE CHANCE OF ERRORS.
ATTENTION: "REPLACE" directions do not affect the Table of Contents, Therefore no TOC will be issued with the updated material.
TRM2 - TECHNICAL REQUIREMENTS MANUAL UNIT 2 REMOVE MANUAL TABLE OF CONTENTS DATE: 05/05/2009 ADD MANUAL TABLE OF CONTENTS DATE: 05/14/2009 CATEGORY: DOCUMENTS TYPE: TRM2 4loo
May. 15, 2009 Page 2 of 3 ID: TEXT 2.2 ADD: REV: 8 REMOVE: REV:7 CATEGORY: DOCUMENTS TYPE: TRM2 ID: TEXT 3.1.3 REMOVE: REV:3 ADD: REV: 4 CATEGORY: DOCUMENTS TYPE: TRM2 ID: TEXT 3.10.4 REMOVE: REV:1 CATEGORY: DOCUMENTS TYPE: TRM2 ID: TEXT 3.2.1 ADD: REV: 8
. REMOVE: REV:7 CATEGORY: DOCUMENTS TYPE: TRM2 ID: TEXT 3.3.9 ADD: REV: 3 REMOVE: REV:2 CATEGORY: DOCUMENTS TYPE: TRM2 ID: TEXT 3.4.4 ADD: REV: 2 REMOVE: REV:1 CATEGORY: DOCUMENTS TYPE: TRM2
May. 15, 2009 Page 3 of 3 ID: TEXT B3.10.4 REMOVE: REV:0 CATEGORY: DOCUMENTS TYPE: TRM2 ID: TEXT B3.3.9 REMOVE: REV:2 ADD: REV: 3 CATEGORY: DOCUMENTS TYPE: TRM2 ID: TEXT LOES ADD: REV: 50 REMOVE: REV:49 CATEGORY: DOCUMENTS TYPE: TRM2 ID: TEXT TOC ADD: REV: 15 REMOVE: REV:14 ANY DISCREPANCIES WITH THE MATERIAL PROVIDED, CONTACT DCS @ X3107 OR X3136 FOR ASSISTANCE. UPDATES FOR HARDCOPY MANUALS WILL BE DISTRIBUTED WITHIN 3 DAYS IN ACCORDANCE WITH DEPARTMENT PROCEDURES. PLEASE MAKE ALL CHANGES AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX UPON COMPLETION OF UPDATES. FOR ELECTRONIC MANUAL USERS, ELECTRONICALLY REVIEW THE APPROPRIATE DOCUMENTS AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX.
SSES MANUAL Manual Name: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 Table Of Contents Issue Date: 05/14/2009 Procedure Name Rev Issue Date Change ID Change Number TEXT LOES 50 05/14/2009
Title:
LIST OF EFFECTIVE SECTIONS TEXT TOC 15 05/14/2009
Title:
TABLE OF CONTENTS TEXT 1.1 0 11/19/2002
Title:
USE AND APPLICATION DEFINITIONS TEXT 2.1 1
Title:
PLANT PROGRAMS AND SETPOINTS TEXT 2.2 8
Title:
PLANT PROGRAMS AND )-/INSTRUMENT TRIP SETPOINT TABLE
Title:
APPLICABILITY TECHNICAL REQUIREMENT FOR OPERATION (TRO) APPLICABILITY TEXT 3.1.1 1 11/09/2007
Title:
REACTIVITY CONTROL SYSTEMS ANTICIPATED TRANSIENT WITHOUT SCRAM ALTERNATE ROD
\ \ ) I INJECTION '(ATWS-ARI) INSTRUMENTATION TEXT 3.1.2 0 11/19/2002
Title:
REACTIVITYCONTROL SYSTEMS CONTROL ROD DRIVE (CRD) HOUSING SUPPORT TEXT 3.1.3 4 05/14/2009
Title:
REACTIVITY CONTROL SYSTEMS CONTROL ROD BLOCK INSTRUMENTATION TEXT 3.1.4 0 11/19/2002
Title:
REACTIVITY CONTROL SYSTEMS CONTROL ROD SCRAM ACCUMULATORS INSTRUMENTATION AND CHECK VALVE TEXT 3.2.1 8 05/14/2009
Title:
CORE OPERATING LIMITS CORE OPERATING LIMITS REPORT (COLR)
Report Date: 05/14/09 Page ~
Page 1 of of 15 15 Report Date: 05/14/09
SSES MANUAL Manual Name: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.3.1 0 11/19/2002
Title:
INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION TEXT 3.3.2 2 11/09/2007
Title:
INSTRUMENTATION SEISMIC MONITORING INSTRUMENTATION TEXT 3.3.3 2 11/09/2007
Title:
INSTRUMENTATION METEOROLOGICAL MONITORING INSTRUMENTATION TEXT 3.3.4 5 05/23/2008
Title:
INSTRUMENTATION TRM POST-ACCIDENT MONITORING INSTRUMENTATION TEXT 3.3.5 0 11/19/2002
Title:
INSTRUMENTATION THIS PAGE INTENTIONALLY LEFT BLANK TEXT 3.3.6 2 10/19/2005
Title:
INSTRUMENTATION TRM ISOLATION ACTUATION INSTRUMENTATION TEXT 3.3.7 1 11/09/2007
Title:
INSTRUMENTATION MAIN TURBINE OVERSPEED PROTECTION SYSTEM TEXT 3.3.8 1 10/22/2003
Title:
INSTRUMENTATION TRM RPS INSTRUMENTATION TEXT 3.3.9 3 05/14/2009
Title:
INSTRUMENTATION LPRM UPSCALE ALARM INSTRUMENTATION TEXT 3.3.10 1 12/14/2004
Title:
INSTRUMENTATION REACTOR RECIRCULATION PUMP MG SET STOPS TEXT 3.3.11 1 10/22/2003
Title:
INSTRUMENTATION MVP ISOLATION INSTRUMENTATION TEXT 3.3.12 0 04/16/2009
Title:
WATER MONITORING INSTRUMENTATION Report Date: 05/14/09 Page 2.
Page 2 of of 15 1_55 Report Date: 05/14/09
SSES MANUAL Manual Name: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.4.1 1 04/26/2006
Title:
REACTOR COOLANT SYSTEM REACTOR COOLANT SYSTEM CHEMISTRY TEXT 3.4.2 1 04/16/2009
Title:
REACTOR COOLANT SYSTEM STRUCTURAL INTEGRITY TEXT 3.4.3 1 11/09/2007
Title:
REACTOR COOLANT SYSTEM REACTOR COOLANT SYSTEM (RCS)
TEXT 3.4.4 2 05/14/2009
Title:
REACTOR COOLANT SYSTEM REACTOR RECIRCULATION FLOW AND ROD LINE LIMIT TEXT 3.4.5 1 04/26/2006
Title:
REACTOR COOLANT SYSTEM REACTOR VESSEL MATERIALS TEXT 3.5.1 1 02/04/2005
Title:
ECCS AND RCIC ADS MANUAL INHIBIT TEXT 3.5.2 1 11/09/2007
Title:
ECCS AND RCIC ECCS AND RCIC SYSTEM MONITORING INSTRUMENTATION TEXT 3.5.3 0 11/19/2002
Title:
ECCS AND RCIC LONG TERM NITROGEN SUPPLY TO ADS TEXT 3.6.1 0 11/19/2002
Title:
CONTAINMENT VENTING OR PURGING TEXT 3.6.2 0 11/19/2002
Title:
CONTAINMENT SUPPRESSION CHAMBER-TO-DRYWELL VACUUM BREAKER POSITION INDICATION TEXT 3.6.3 0 11/19/2002
Title:
CONTAINMENT SUPPRESSION POOL ALARM INSTRUMENTATION TEXT 3.6.4 0 11/19/2002
Title:
CONTAINMENT PRIMARY CONTAINMENT CLOSED SYSTEM BOUNDARIES Page 3 of 15 Report Date: 05/14/09
SSES MANUAL Manual Name: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.7. 1 0 11/19/2002
Title:
PLANT SYSTEMS EMERGENCY SERVICE WATER SYSTEM (ESW) SHUTDOWN TEXT 3.7. 2 0 11/19/2002
Title:
PLANT SYSTEMS ULTIMATE HEAT SINK (UHS) AND GROUND WATER LEVEL TEXT 3.7.3.1 2 04/16/2009
Title:
PLANT SYSTEMS FIRE SUPPRESSION WATER SUPPLY SYSTEM TEXT 3.7.3.2 3 04/16/2009
Title:
PLANT SYSTEMS SPRAY AND SPRINKLER SYSTEMS TEXT 3.7.3.3 3 04/16/2009
Title:
PLANT SYSTEMS C02 SYSTEMS TEXT 3.7.3.4 2 04/16/2009
Title:
PLANT SYSTEMS HALON SYSTEMS TEXT 3.7.3.5 2 04/16/2009
Title:
PLANT SYSTEMS FIRE HOSE STATIONS TEXT 3.7.3.6 2 04/16/2009
Title:
PLANT SYSTEMS YARD FIRE HYDRANTS AND HYDRANT HOSE HOUSES TEXT 3.7.3.7 1 04/26/2006
Title:
PLANT SYSTEMS FIRE RATED ASSEMBLIES TEXT 3.7.3.8 7 11/09/2007
Title:
PLANT SYSTEMS FIRE DETECTION INSTRUMENTATION TEXT 3.7.4 1 04/26/2006
Title:
PLANT SYSTEMS SOLID RADWASTE SYSTEM TEXT 3.7.5.1 0 11/19/2002
Title:
PLANT SYSTEMS MAIN CONDENSER OFFGAS HYDROGEN MONITOR Report Date: 05/14/09 Page 4 4 of of 15 15 Report Date: 05/14/09
SSES MA.NTAL Manual Name: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.7.5.2 0 11/19/2002
Title:
PLANT SYSTEMS MAIN CONDENSER OFFGAS EXPLOSIVE GAS MIXTURE TEXT 3.7.5.3 1 04/26/2006
Title:
PLANT SYSTEMS LIQUID HOLDUP TANKS TEXT 3.7.6 2 06/27/2008
Title:
PLANT SYSTEMS ESSW PUMPHOUSE VENTILATION TEXT 3.7.7 2 09/05/2008
Title:
PLANT SYSTEMS MAIN CONDENSER OFFGAS PRETREATMENT LOGARITHMIC RADIATION MONITORING INSTRUMENTATION TEXT 3.7.8 6 06/21/2007
Title:
PLANT SYSTEMS SNUBBERS TEXT 3.7.9 1 08/28/2006
Title:
PLANT SYSTEMS CONTROL STRUCTURE HVAC TEXT 3.7.10 1 12/14/2004
Title:
PLANT SYSTEMS SPENT FUEL STORAGE POOLS (SFSPS)
TEXT 3.7.11 0 04/16/2009
Title:
PLANT SYSTEMS TEXT 3.8.1 2 02/04/2005
Title:
ELECTRICAL POWER PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES TEXT 3.8.2.1 2 11/09/2007
Title:
ELECTRICAL POWER MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION -
CONTINUOUS TEXT 3.8.2.2 2 12/14/2004
Title:
ELECTRICAL POWER MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION -
AUTOMATIC T EXT 3.8.3 0 11/19/2002
Title:
ELECTRICAL POWER DIESEL GENERATOR (DG) MAINTENANCE ACTIVITIES Page5 of 15 Report Date: 05/14/09
SSES MANUAL Manual Name: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.8.4 1 02/04/2005
Title:
ELECTRICAL POWER 24 VDC ELECTRICAL SUBSYSTEM TEXT 3.8.5 0 11/19/2002
Title:
ELECTRICAL POWER DEGRADED VOLTAGE PROTECTION TEXT 3.8.6 0 11/19/2002
Title:
ELECTRICAL POWER EMERGENCY SWITCHGEAR ROOM COOLING TEXT 3.8.7 0 12/14/2006
Title:
BATTERY MAINTENANCE AND MONITORING PROGRAM TEXT 3.9.1 0 11/19/2002
Title:
REFUELING OPERATIONS DECAY TIME TEXT 3.9.2 0 11/19/2002
Title:
REFUELING OPERATIONS COMMUNICATIONS TEXT 3.9.3 0 11/19/2002
Title:
REFUELING OPERATIONS REFUELING PLATFORM TEXT 3.10.1 1 04/26/2006
Title:
MISCELLANEOUS SEALED SOURCE CONTAMINATION TEXT 3.10.2 1 04/09/2007
Title:
MISCELLANEOUS SHUTDOWN MARGIN TEST RPS INSTRUMENTATION TEXT 3.10.3 1 04/26/2006
Title:
MISCELLANEOUS INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)
TEXT 3.11.1.1 1 04/26/2006
Title:
RADIOACTIVE EFFLUENTS LIQUID EFFLUENTS CONCENTRATION TEXT 3.11.1.2 1 04/26/2006
Title:
RADIOACTIVE EFFLUENTS LIQUID EFFLUENTS DOSE Report Date: 05/14/09 Page ~6 of of 15 15 Report Date: 05/14/09
SSE.S MANUJAL Manual Name: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.11.1.3 1 04/26/2006
Title:
RADIOACTIVE EFFLUENTS LIQUID WASTE TREATMENT SYSTEM TEXT 3.11.1.4 1 12/14/2004
Title:
RADIOACTIVE EFFLUENTS LIQUID RADWASTE EFFLUENT MONITORING INSTRUMENTATION TEXT 3.11.1.5 2 05/02/2007
Title:
RADIOACTIVE EFFLUENTS RADIOACTIVE LIQUID PROCESS MONITORING INSTRUMENTATION TEXT 3.11.2.1 3 04/26/2006
'Title: RADIOACTIVE EFFLUENTS DOSE RATE TEXT 3.11.2.2 1 04/26/2006
Title:
RADIOACTIVE EFFLUENTS DOSE - NOBLE GASES TEXT 3.11.2.3 1 04/26/2006
Title:
RADIOACTIVE EFFLUENTS DOSE - IODINE, TRITIUM, AND RADIONUCLIDES.IN PARTICULATE FORM TEXT 3.11.2.4 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT SYSTEM TEXT 3.11.2.5 3 11/14/2006
Title:
RADIOACTIVE EFFLUENTS VENTILATION EXHAUST TREATMENT SYSTEM TEXT 3.11.2.6 3 05/02/2007
Title:
RADIOACTIVE EFFLUENTS RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION TEXT 3.11.3 1 04/26/2006
Title:
RADIOACTIVE EFFLUENTS TOTAL DOSE TEXT 3.11.4.1 3 04/26/2006
Title:
RADIOACTIVE EFFLUENTS MONITORING PROGRAM TEXT 3.11.4.2 2 04/26/2006
Title:
RADIOACTIVE EFFLUENTS LAND USE CENSUS Report Date: 05/14/09 Page27 Page of of i~
15 Report Date: 05/14/09
SSES MANUAL Manual Name: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.11.4.3 1 04/26/2006
Title:
RADIOACTIVE EFFLUENTS INTERLABORATORY COMPARISON PROGRAM TEXT 3.12.1 0 11/19/2002
Title:
LOADS CONTROL PROGRAM CRANE TRAVEL-SPENT FUEL STORAGE POOL TEXT 3.12.2 4 04/17/2008
Title:
-LOADS CONTROL PROGRAM HEAVY LOADS REQUIREMENTS TEXT 3.12.3 0 11/19/2002
Title:
LOADS CONTROL PROGRAM LIGHT LOADS REQUIREMENTS TEXT B3.0 4 05/23/2008
Title:
APPLICABILITY BASES TECHNICAL REQUIREMENT FOR OPERATION (TRO) APPLICABILITY TEXT B3.1.1 1 11/09/2007
Title:
REACTIVITY CONTROL SYSTEM BASES ANTICIPATED TRANSIENT WITHOUT SCRAM ALTERNATE ROD INJECTION (ATWS-ARI) INSTRUMENTATION TEXT B3.1.2 0 11/19/2002
Title:
REACTIVITY CONTROL SYSTEM BASES CONTROL ROD DRIVE (CRD) HOUSING SUPPORT TEXT B3.1.3 3 04/10/2007
Title:
REACTIVITY CONTROL SYSTEM BASES CONTROL ROD BLOCK INSTRUMENTATION TEXT B3.1.4 0 -11/19/2002
Title:
REACTIVITY CONTROL SYSTEM BASES CONTROL ROD SCRAM ACCUMULATORS INSTRUMENTATION AND CHECK VALVE TEXT B3.2.1 0 11/19/2002
Title:
CORE OPERATING LIMITS BASES CORE OPERATING LIMITS REPORT (COLR)
TEXT B3.3.1 0 11/19/2002
Title:
INSTRUMENTATION BASES RADIATION MONITORING INSTRUMENTATION TEXT B3.3.2 1 .11/09/2007
Title:
INSTRUMENTATION BASES SEISMIC MONITORING INSTRUMENTATION PageE of 15 Report Date: 05/14/09
SSES MANUAL Manual Name: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.3.3 2 11/09/2007
Title:
INSTRUMENTATION BASES METEOROLOGICAL MONITORING INSTRUMENTATION TEXT B3.3.4 3 11/09/2007
Title:
INSTRUMENTATION BASES TRM POST ACCIDENT MONITORING (PAM) INSTRUMENTATION TEXT B3.3.5 2 11/09/2007
Title:
INSTRUMENTATION BASES THIS PAGE INTENTIONALLY LEFT BLANK TEXT B3.3.6 3 10/19/2005
Title:
INSTRUMENTATION BASES TRM ISOLATION ACTUATION INSTRUMENTATION TEXT B3.3.7 1 11/09/2007
Title:
INSTRUMENTATION BASES MAIN TURBINE OVERSPEED PROTECTION SYSTEM TEXT B3.3.8 1 10/22/2003
Title:
INSTRUMENTATION BASES TRM RPS INSTRUMENTATION TEXT B3.3.9 3 05/14/2009
Title:
INSTRUMENTATION BASES LPRM UPSCALE ALARM INSTRUMENTATION TEXT B3.3.10 1 12/18/2008
Title:
INSTRUMENTATION BASES REACTOR RECIRCULATION PUMP MG SET STOPS TEXT B3.3.11 1 10/22/2003
Title:
INSTRUMENTATION BASES MVP ISOLATION INSTRUMENTATION TEXT B3.3.12 0 04/16/2009
Title:
WATER MONITORING INSTRUMENTATION TEXT B3.4.1 0 11/19/2002
Title:
REACTOR COOLANT SYSTEM BASES REACTOR COOLANT SYSTEM CHEMISTRY TEXT B3.4.2 1 04/16/2009
Title:
REACTOR COOLANT SYSTEM BASES STRUCTURAL INTEGRITY Report Date: 05/14/09 Page9.2 Page of of 15 15 Report Date: 05/14/09
SSES MANUAMJ Manual Name: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.4.3 1 11/09/2007
Title:
REACTOR COOLANT SYSTEM BASES HIGH/LOW PRESSURE INTERFACE LEAKAGE MONITOR TEXT B3.4.4 0 11/19/2002
Title:
REACTOR COOLANT SYSTEM BASES REACTOR RECIRCULATION FLOW AND ROD LINE LIMIT TEXT B3.4.5 0 11/19/2002
Title:
REACTOR COOLANT SYSTEM BASES REACTOR VESSEL MATERIALS TEXT B3.5.1 0 11/19/2002
Title:
ECCS AND RCIC BASES ADS MANUAL INHIBIT TEXT B3.5.2 1 11/09/2007
Title:
ECCS AND RCIC BASES ECCS AND RCIC SYSTEM MONITORING INSTRUMENTATION TEXT B3.5.3 1 11/09/2007
Title:
ECCS AND RCIC BASES LONG-TERM NITROGEN SUPPLY TO ADS-TEXT B3.6.1 0 11/19/2002
Title:
CONTAINMENT BASES VENTING OR PURGING TEXT B3.6.2 0 11/19/2002
Title:
CONTAINMENT BASES SUPPRESSION CHAMBER-TO-DRYWELL VACUUM BREAKER POSITION INDICATION TEXT B3.6.3 1 04/19/2007
Title:
CONTAINMENT BASES SUPPRESSION POOL ALARM INSTRUMENTATION TEXT B3.6.4 1 12/14/2004
Title:
CONTAINMENT BASES PRIMARY CONTAINMENT CLOSED SYSTEM BOUNDARIES TEXT B3.7.1 0 11/19/2002
Title:
PLANT SYSTEMS BASES EMERGENCY SERVICE WATER SYSTEM (SHUTDOWN)
TEXT B3.7.2 0 11/19/2002
Title:
PLANT SYSTEMS BASES ULTIMATE HEAT SINK (UHS) GROUND WATER LEVEL Page 10 of 15 Report Date: 05/14/09
SSES MANUAL Manual Name: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.7.3.1 2 01/07/2008
Title:
PLANT SYSTEMS BASES FIRE SUPPRESSION WATER SUPPLY SYSTEM TEXT B3.7.3.2 2 04/26/2006
Title:
PLANT SYSTEMS BASES SPRAY AND SPRINKLER SYSTEMS TEXT B3.7.3.3 0 11/19/2002
Title:
PLANT SYSTEMS BASES C02 SYSTEMS TEXT B3.7.3.4 1 04/26/2006
Title:
PLANT SYSTEMS BASES HALON SYSTEMS TEXT B3.7.3.5 1 04/26/2006
Title:
PLANT SYSTEMS BASES FIRE HOSE STATIONS TEXT B3.7.3.6 1 04/26/2006
Title:
PLANT SYSTEMS BASES YARD FIRE HYDRANTS AND HYDRANT HOSE HOUSES TEXT B3.7.3.7 0 11/19/2002
Title:
PLANT SYSTEMS BASES FIRE RATED ASSEMBLIES TEXT B3.7.3.8 1 01/12/2004
Title:
PLANT SYSTEMS BASES FIRE DETECTION INSTRUMENTATION TEXT B3.7.4 0 11/19/2002
Title:
PLANT SYSTEMS BASES SOLID RADWASTE SYSTEM TEXT B3.7.5.1 0 11/19/2002
Title:
PLANT SYSTEMS BASES MAIN CONDENSER OFFGAS HYDROGEN MONITOR TEXT B3.7.5.2 0 11/19/2002
Title:
PLANT SYSTEMS BASES MAIN CONDENSER OFFGAS EXPLOSIVE GAS MIXTURE TEXT B3.7.5.3 0 11/19/2002
Title:
PLANT SYSTEMS BASES LIQUID HOLDUP TANKS Report Date: 05/14/09 Page 11 Page 11 of of 15 15 Report Date: 05/14/09
SSES MANUAL Manual Name: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.7.6 2 06/27/2008
Title:
PLANT SYSTEMS BASES ESSW PUMPHOUSE VENTILATION TEXT B3.7.7 2 01/31/2008
Title:
PLANT SYSTEMS BASES MAIN CONDENSER OFFGAS PRETREATMENT LOGARITHMIC RADIATION MONITORING INSTRUMENTATION TEXT B3.7.8 3 06/21/2007
Title:
PLANT SYSTEMS BASES SNUBBERS TEXT B3.7.9 1 12/14/2004
Title:
PLANT SYSTEMS BASES CONTROL STRUCTURE HVAC TEXT B3.7.10 1 12/14/2004
Title:
PLANT SYSTEMS BASES SPENT FUEL STORAGE POOLS TEXT B3.7.11 .0 04/16/2009
Title:
STRUCTURAL INTEGRITY TEXT B3.8.1 1 02/04/2005
Title:
ELECTRICAL POWER BASES PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES TEXT B3.8.2.1 0 11/19/2002
Title:
ELECTRICAL POWER BASES MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION -
CONTINUOUS TEXT B3.8.2.2 1 09/17/2004
Title:
ELECTRICAL POWER BASES MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION -
AUTOMATIC TEXT B3.8.3 0 11/19/2002
Title:
ELECTRICAL POWER BASES DIESEL GENERATOR (DG) MAINTENANCE ACTIVITIES TEXT B3.8.4 0 11/19/2002
Title:
ELECTRICAL POWER BASES 24 VDC ELECTRICAL POWER SUBSYSTEM TEXT B3.8.5 0 11/19/2002
Title:
ELECTRICAL POWER BASES DEGRADED VOLTAGE PROTECTION Report Date: 05/14/09 Page iZ 12 of of 1~.
25 Report Date: 05/14/09
,SSES MANUAL Manual Name: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.8.6 1 02/04/2005
Title:
ELECTRICAL POWER BASES EMERGENCY SWITCHGEAR ROOM COOLING TEXT B3.8.7 0 12/14/2006
Title:
BATTERY MAINTENANCE AND MONITORING PROGRAM TEXT B3.9.1 0 11/19/2002
Title:
REFUELING OPERATIONS BASES DECAY TIME TEXT B3.9.2 0 11/19/2002
Title:
REFUELING OPERATIONS BASES COMMUNICATIONS TEXT B3.9.3 0 11/19/2002 I
Title:
REFUELING OPERATIONS BASES REFUELING PLATFORM TEXT B3.10.1 0 11/19/2002
Title:
MISCELLANEOUS BASES SEALED SOURCE CONTAMINATION TEXT B3.10.2 1 04/10/2007
Title:
MISCELLANEOUS BASES SHUTDOWN MARGIN TEST RPS INSTRUMENTATION TEXT B3.10.3 0 11/19/2002
Title:
MISCELLANEOUS BASES INDEPENDENT SPENT FUEL STORAGE, INSTALLATION (ISFSI)
TEXT B3.11.1.1 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES LIQUID EFFLUENTS CONCENTRATION TEXT B3.11.1.2 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES LIQUID EFFLUENTS DOSE TEXT B3.11.1.3 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES LIQUID WASTE TREATMENT SYSTEM TEXT B3.11.1.4 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES LIQUID RADWASTE EFFLUENT MONITORING INSTRUMENTATION Page 13 ý, of 15 Report Date: 05/14/09
,ssEs MANUAL Manual Name: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2.
TEXT B3.11.1.5 0. 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES RADIOACTIVE LIQUID PROCESS MONITORING INSTRUMENTATION TEXT B3.11.2.1 1 12/14/2004
Title:
RADIOACTIVE EFFLUENTS BASES DOSE RATE TEXT B3.11.2.2 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES DOSE T NOBLE GASES TEXT B3;11.2.3 0 11/19'/2002
Title:
RADIOACTIVE EFFLUENTS BASES DOSE - IODINE, TRITIUM, AND RADIONUCLIDES IN PARTICULATES FORM TEXT B3.11.2.4 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES GASEOUS RADWASTE TREATMENT SYSTEM TEXT B3.11.2.5 4 11/14i2006
Title:
RADIOACTIVE EFFLUENTS BASES VENTILATION EXHAUST TREATMENT SYSTEM TEXT B3.11.2.6 1 01/27/2004
Title:
RADIOACTIVE EFFLUENTS BASES RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION TEXT B3.11.3 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES TOTAL DOSE TEXT B3.11.4.1 2 01/06/2006
Title:
RADIOACTIVE EFFLUENTS BASES MONITORING PROGRAM TEXT B3.11.4.2 0 11/19,/2002
Title:
RADIOACTIVE EFFLUENTS BASES LAND USE CENSUS TEXT B3.11.4.3 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES INTERLABORATORY COMPARISON'PROGRAM TEXT B3 .12.1 1 10/04/2007
Title:
LOADS CONTROL PROGRAM BASES CRANE'TRAVEL-SPENT FUEL STORAGE POOL Report Date: 05/14/09 Page 14 14 of of 15 15 Report Date: 05/14/09
SSES MANUA-L Manual Name: TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.12.2 0 11/19/2002
Title:
LOADS CONTROL PROGRAM BASES HEAVY LOADS REQUIREMENTS TEXT B3.12.3 0 11/19/2002
Title:
LOADS CONTROL PROGRAM BASES LIGHT LOADS REQUIREMENTS TEXT 4.1 0 09/27/2003
Title:
ADMINISTRATIVE CONTROLS ORGANIZATION TEXT 4.2 0 09/27/2003
Title:
ADMINISTRATIVE CONTROLS REPORTABLE EVENT ACTION TEXT 4.3 0 09/27/2003
Title:
ADMINISTRATIVE CONTROLS SAFETY LIMIT VIOLATION TEXT 4.4 1 12/18/2008
Title:
ADMINISTRATIVE CONTROLS PROCEDURES & PROGRAMS TEXT 4.5 0 09/27/2003
Title:
ADMINISTRATIVE CONTROLS REPORTING REQUIREMENTS TEXT 4.6 0 09/27/2003
Title:
ADMINISTRATIVE CONTROLS RADIATION PROTECTION PROGRAM TEXT 4.7 0 09/27/2003
Title:
ADMINISTRATIVE CONTROLS TRAINING Report Date: 05/14/09 j5.
Page 1_5 of of 15 15 Report Date: 05/14/09
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 15 TABLE OF CONTENTS (TECHNICAL REQUIREMENTS MANUAL)
SECTION TITLE PAGE 1.0 US E A ND A P P LIC A T IO N ........................................................................... 1.0-1 1.1 Defin itio n s ..................................................................................... T R M/1 .0-2 2.0 P LA NT P R O G R A MS .................................................................................. 2 .0-1 2.1 P la nt P ro g ra m s ..................................................................................... 2 .0-1 2.2 Instrument Trip Setpoint Table ..................................................... TRM/2.0-5 3.0 A P P LIC A B ILITY ................................................................................. T R M/3.0-1 3.0 (TRO) - TR for Operation (TRO) Applicability ............................... TRM/3.0-1 3.0 (TRS) - TR Surveillance (TRS) Applicability ........................... - TRM/3.0-3 3.1 REACTIVITY CONTROL SYSTEMS ....................
TRM/3.1-1 3.1.1 Alternate Rod Injection ........................... ... . ..... . ,).../TRM/3. 1-1 3.1.2 CRD Housing Support ................................... . 3.1-4 3.1.3 Control Rod Block Instrumentation .................................. /............. 3.1-5 3.1.4 Control Rod Scram Accumulators Instrumentation and, Check Valve .................................... TRM/3.1-9 3.2 CORE OPERATING LIMITS REPORT ................................................... 3.2-1 3.2.1 Core Operating Limits Report .... ...... ................................. 3.2-1 INSTRUMENTATION ..................................... TRM/3.3-1 3.3 . . . .................
3.3.1 Radiation Monitoring Instrumentation ..................................... TRM/3.3-1 3.3.2 Seismic Monitoring lnstrumentationr ............................................ TRM/3.3-4 3.3.3 Meteorological Monitoring Instrumentation ................................... TRM/3.3-7 3.3.4 TRM Post-Accident Monitoring/instrumentation ............................ TRM/3.3-9 3.3.5 Section Not Used . ............. TRM/3.3-12 3.3.6 TRM Containment Isolation Instrumentation ............... TRM/3.3-13 3.3.7 Turbine Overspeed Protection System ......................................... TRM/3.3-17 3.3.8 S ection Not-U sed. ......................................................................... T R M/3.3-19 3.3.9 O PRM ristru mentation ................................................................. TRM /3.3-21 3.3.10 Reactor Recirculation Pump MG Set Electrical and MlechanicaLS/tops ......................................................................... TR M/3.3-22 3.3.11 M,\VVPisolation Instrumentation ...................................................... TRM/3.3-24 3.3.12 ate Monitoring Instrumentation ................................................. TRM/3.3-26 3.4 REACTOR COOLANT SYSTEM .......................................................... TRM/3.4-1 3.4.1 Reactor Coolant System Chemistry ....................................................... 3.4-1 3.4.2 Not Use d ......................................................................................... T R M/3 .4-6 3.4.3 High/Low Pressure Interface Leakage Monitors .................................... 3.4-9 3.4.4 Reactor Recirculation Flow and Rod Line Limit ............................ TRM/3.4-12 3.4.5 Reactor Vessel Material Surveillances Program ........................... TRM/3.4-13 SUSQUEHANNA - UNIT 2 TRM / TOC-1 EFFECTIVE DATE 04/17/2009
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 15 TABLE OF CONTENTS (TECHNICAL REQUIREMENTS MANUAL)
SECTION TITLE PAGE 3.5 EMERGENCY CORE COOLING AND RCIC ..................................... TRM/3.5-1 3.5.1 A D S Manual Inhibit ...................................................................... T RM /3.5-1 3.5.2 ECCS and RCIC System Monitoring Instrumentation ............. 3.5-3 3.5.3 Long Term Nitrogen Supply to ADS ...................................................... 3.5-6 3 .6 CO NT A INME NT .......................................................................................... 3 .6-1 3.6.1 V E NT ING or PU RG ING ........................................................................ 3.6-1 3.6.2 Suppression Chamber-to-Drywell Vacuum Breaker Position Indication .......................................... 3.6-3 3.6.3 Suppression Pool Alarm Instrumentation ............................................... 3.6-4 3.6.4 Primary Containment Closed System Boundaries ........................ TRM/3.6-7 3.7 PLA NT SYST EM S .............................................................................. TR M/3.7-1 3.7.1 Emergency Service Water System (Shutdown) ............................ TRM/3.7-1 3.7.2 Ultimate Heat Sink and Ground Water Level .................. 3.7-3 3.7.3.1 Fire Suppression Water Supply System ................. TRM/3.7-4 3.7.3.2 Spray and Sprinkler Systems ........................................................ TRM/3.7-8 3.7.3.3 C0 2 system s ................................................................................ T R M/3.7-12 3.7.3.4 Halon System s ............................................................................. T R M/3.7-16 3.7.3.5 Fire Hose Stations ........................................................................ TR M/3.7-18 3.7.3.6 Yard Fire Hydrants and Hydrant Hose Houses ............................. TRM/3.7-22 3.7.3.7 Fire Rated Assemblies .................................................................. TRM/3.7-24 3.7.3.8 Fire Detection Instrumentation ...................................................... TRM/3.7-26 3.7.4 Solid Radwaste System ................................................................ TRM/3.7-34 3.7.5.1 Main Condenser Offgas Hydrogen Monitor ................... 3.7-37 3.7.5.2 Main Condenser Explosive Gas Mixture ....................................... TRM/3.7-38 3.7.5.3 Liquid Holdup Tanks ..................................................................... TRM/3.7-39 3.7.6 ESSW Pumphouse Ventilation .............................................................. 3.7-40 3.7.7 Main Condenser Offgas Pretreatment Logarithmic Radiation Monitoring Instrumentation ........................................................... TRM/3.7-41 3.7.8 S nubbers ...................................................................................... T R M/3.7-43 3.7.9 Control Structure HVAC ................................................................ TRM/3.7-49 3.7.10 Spent Fuel Storage Pools (SFSPs) .............................................. TRM/3.7-51 3.7.11 Structural Integrity ......................................................................... TR M/3.7-54 3.8 ELECTRICAL POWER ....................................................................... TRM/3.8-1 3.8.1 Primary Containment Penetration Conductor Overcurrent P rotective Devices ........................................................................ T R M/3.8-1 3.8.2.1 Motor Operated Valves Thermal Overload Protection -
C o ntinuous ................................................................................... T R M/3 .8-5 3.8.2.2 Motor Operated Valves Thermal Overload Protection -
A uto m atic ...................................................................................... T R M/3.8-11 3.8.3 Diesel Generator (DG) Maintenance Activities ................. 3.8-13 SUSQUEHANNA - UNIT 2 TRM / TOC-2 EFFECTIVE DATE 04/17/2009
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 15 TABLE OF CONTENTS (TECHNICAL REQUIREMENTS MANUAL)
SECTION TITLE PAGE 3.8.4 24VDC Electrical Power Subsystem ............................................. TRM/3.8-15 3.8.5 Degraded Voltage Protection ........................................................ TRM/3.8-21 3.8.6 Emergency Switchgear Room Cooling .................................................. 3.8-24 3.8.7 Battery Monitoring and Maintenance Program .............................. TRM/3.8-26 3.9 REFUELING OPERATIONS ....................................................................... 3.9-1 3 .9 .1 De cay T ime .......................................................................................... 3 .9-1 3 .9 .2 C o m munications ..................................................................................... 3 .9-2 3.9.3 Refueling P latform .................................................................................. 3.9-3 3.10 MISCELLANEOUS ............................................................................. TRM/3.10-1 3.10.1 Sealed Source Contamination ...................................................... TRM/3.10-1 3.10.2 MODE 5 Shutdown Margin Test RPS Instrumentation .......................... 3.10-4 3.10.3 Independent Spent Fuel Storage Installation (ISFSI) .................... TRM/3.10-7 3.10.4 Section Not Used .......................................................................... TRM/3.10-8 3.11 RADIOACTIVE EFFLUENTS .............................................................. TRM/3. 11-1 3.11.1 Liquid E ffluents ............................................................................. T RM/3.11-1 3.11.1.1 Liquid Effluents Concentration ...................................................... TRM/3.11-1 3.11.1.2 Liquid Effluents Dose ................................................................... TRM/3.11-4 3.11.1.3 Liquid Waste Treatment System .................................................. TRM/3.11-6 3.11.1.4 Liquid Radwaste Effluent Monitoring Instrumentation ............................ 3.11-8 3.11.1.5 Radioactive Liquid Process Monitoring Instrumentation ............... TRM/3.11-13 3.11.2 Gaseous Effluents ........................................................................ TRM/3.11-17 3.11.2 .1 Dose Rate ............................................................... :..................... T RM/3 .11-17 3.11.2.2 Dose - Noble Gases ..................................................................... TRM/3.11-20 3.11.2.3 Dose - Iodine, Tritium, and Radionuclides in P articulate Form ........................................................................... T RM/3.11-2 1 3.11.2.4 Gaseous Radwaste Treatment System ........................................ TRM/3.11-22 3.11.2.5 Ventilation Exhaust Treatment System ......................................... TRM/3.11-23 3.11.2.6 Radioactive Gaseous Effluent Monitoring Instru m e ntatio n ...................................................................................... 3 .11-2 6 3.11.3 Total Dose .................................................................................... T RM/3.11-33 3.11.4 Radiological Environmental Monitoring ......................................... TRM/3.11-35 3.11.4.1 Monitoring Program ...................................................................... TRM/3.11-35 3.11.4.2 Land Use Census ......................................................................... TRM/3.11-45 3.11.4.3 Interlaboratory Comparison Program ............................................ TRM/3.11-47 3.12 LOADS CONTROL PROGRAM .......................................................... TRM/3.12-1 3.12.1 Crane Travel - Spent Fuel Storage Pool ....................................... TRM/3.12-1 3.12.2 Heavy Loads Requirements ......................................................... TRM/3.12.3 3.12.3 Light Loads Requirements ........................................................... TRM/3.12-5 SUSQUEHANNA - UNIT 2 TRM /,TOC-3 EFFECTIVE DATE 04/17/2009
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 15 TABLE OF CONTENTS (TECHNICAL REQUIREMENTS MANUAL)
SECTION TITLE PAGE 4.0 ADMINISTRATIVE CONTROLS ................................................................. 4.0-1 4 .1 O rg a niza tio n ......................................................................................... 4 .0 -1 4.2 Reportable Event Action ....................................................................... 4.0-2 4 .3 S afety Lim it Violation ............................................................................ .4 .0-3 4.4 Procedures and Program s .................................................................... 4.0-4 4.5 Reporting Requirements. ....... ............ ............. 0-5 4.6 Radiation Protection Program ................................................................ 4.0-7 4 .7 T ra ining.................................................................................................. 4 .0 -8 TRM/TOC-4 EFFECTIVE DATE 04/17/2009 SUSQUEHANNA - UNIT SUSQUEHANNA - UNIT 22 TRM /TOC-4 EFFECTIVE DATE 04/17/2009
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 15 TABLE OF CONTENTS (TECHNICAL REQUIREMENTS MANUAL)
SECTION TITLE PAGE B 3.0 (TRO) - TR for Operation (TRO) Applicability ...................................... B 3.0-1 B 3.0 (TRS) - TR Surveillance (TRS) Applicability ......................................... B 3.0-9 B 3.1.1 Alternate Rod Injection ................................................................ TRM/B 3.1-1 B 3.1.2 CRD Housing Support ......................................................................... B 3.1-4 B 3.1.3 Control Rod Block Instrumentation .............................................. TRM/B 3.1-5 B 3.1.4 Control Rod Scram Accumulators Instrumentation and Check Valve ......................................................................... TRM/B 3.1-8 B 3.2.1 Core Operating Limits Report (COLR) ................................................. B 3.2-1 B 3.3.1 Radiation Monitoring Instrumentation .......................................... TRM/B 3.3-1 B 3.3.2 Seismic Monitoring Instrumentation ............................................. TRM/B 3.3-2 B 3.3.3 Meteorological Monitoring Instrumentation .................................. TRM/B 3.3-3 B 3.3.4 TRM Post-Accident Monitoring Instrumentation ........................... TRM/B 3.3-4 B 3.3.5 Section Not Used ......................................................................... TRM/B 3.3-9 B 3.3.6 TRM Containment Isolation Instrumentation ........................................ B 3.3-10 B 3.3.7 Turbine Overspeed Protection System ........................................ TRM/B 3.3-14 B 3.3.8 Section Not Used ......................................................................... TRM/B 3.3-15 B 3.3.9 OPRM Instrumentation ................................................................ TRM/B 3.3-18 B 3.3.10 Reactor Recirculation Pump MG Set Electrical and Mechanical Stops ........................................................................ TRM/B 3.3-20 B 3.3.11 MVP Isolation Instrumentation ..................................................... TRM/B 3.3-22 B 3.3.12 Water Monitoring Instrumentation ................................................ TRM/B 3.3-24 B 3.4.1 Reactor Coolant System Chemistry ..................................................... B 3.4-1 B 3.4 .2 Not Used ............................................................................... :...... T R M/B 3.4-2 B 3.4.4 Reactor Recirculation Flow and Rod Line Limit ........................... TRM/B 3.4-5 B 3.4.5 Reactor Vessel Material Surveillances Program .................................. B 3.4-6 B 3.5.1 A DS Manual Inhibit .............................................................................. B 3.5-1 B 3.5.2 ECCS and RCIC System Monitoring Instrumentation .................. TRM/B 3.5-3 B 3.5.3 Long Term Nitrogen Supply to ADS .................................................... B 3.5-4 B 3.6.1 VENTING or PURGING ............................................................... TRM/B 3.6-1 B 3.6.2 Suppression Chamber-to-Drywell Vacuum Breaker Position Ind ic atio n ............................................................................................. B 3 .6 -3 B 3.6.3 Suppression Pool Alarm Instrumentation ............................................. B 3.6-4 B 3.6.4 Primary Containment Closed System, Boundaries ....................... TRM/B 3.6-6 B 3.7.1 Emergency Service Water System (Shutdown) ................................... B 3.7-1 B 3.7.2 Ultimate Heat Sink and Ground Water Level ....................................... B 3.7-2 B 3.7.3.1 Fire Suppression Water Supply System ..................................... TRM/B 3.7-3 TRM/TOC-5 EFFECTIVE DATE 04/17/2009 SUSQUEHANNA - UNIT SUSQUEHANNA -
UNIT 2 2 TRM / TOC-5 EFFECTIVE DATE 04/17/2009
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 15 TABLE OF CONTENTS (TECHNICAL REQUIREMENTS MANUAL)
SECTION TITLE PAGE B 3.7.3.2 Spray and Sprinkler Systems ...................................................... TRM/B 3.7-5 B 3.7.3.3 C02 Systems .............................................................................. TRM/B 3.7-7 B 3.7.3.4 Halon Systems ............................................................................ TRM/B 3.7-8 B 3.7.3.5 Fire Hose Stations ....................................................................... TRM/B 3.7-10 B 3.7.3.6 Yard Fire Hydrants and Hydrant Hose Houses ............................ TRM/B 3.7-11 B 3.7.3.7 Fire Rated Assemblies................................................................. TRM/B 3.7-12 B 3.7.3.8 Fire Detection Instrumentation ..................................................... TRM/B 3.7-14 B 3.7.4 Solid Radwaste System ............................................................... TRM/B 3.7-15 B 3.7.5.1 Main Condenser Offgas Hydrogen Monitor ......................................... B 3.7-17 B 3.7.5.2 Main Condenser Explosive Gas Mixture .............................................. B 3.7-19 B 3.7.5.3 Liquid Holdup Tanks ............................................................................ B 3.7-20 B 3.7.6 ESSW Pumphouse Ventilation .................................................... TRM/B 3.7-21 B 3.7.7 Main Condenser Offgas Pretreatment Logarithmic Radiation Monitoring Instrumentation .......................................................... TRM/B 3.7-22 B 3.7.8 S nubbers ..................................................................................... T R M/B 3.7-24 B 3.7.9 Control Structure HVAC ............................................................... TRM/B 3.7-31 B 3.7.10 Spent Fuel Storage Pools ............................................................ TRM/B 3.7-33 B 3.7.11 Structural Integrity ........................................................................ TRM/B 3.7-36 B 3.8.1 Primary Containment Penetration Conductor Overcurrent Protective Devices ....................................................................... TRM/B 3.8-1 B 3.8.2.1 Motor Operated Valves Thermal Overload Protection -
C ontinuous ................................................................................. T R M/B 3 .8-3 B 3.8.2.2 Motor Operated Valves Thermal Overload Protection -
A uto m atic ..................................................................................... T R M/B 3 .8-4 B 3.8.3 Diesel Generator (DG) Maintanence Activities ............................ TRM/B 3.8-5 B 3.8.4 24VDC Electrical Power Subsystem ............................................ TRM/B 3.8-6 B 3.8.5 Degraded Voltage Protection ...................................................... TRM/B 3.8-16 B 3.8.6 Emergency Switchgear Room Cooling ........................................ TRM/B 3.8-17 B 3.8.7 Battery Monitoring and Maintenance Program ............................. TRM/B 3.8-18 B .3 .9 .1 D ecay Tim e ......................................................................................... B 3 .9-1 B 3.9.2 C om m unications .................................................................................. B 3.9-2 B 3.9.3 R efueling P latform ............................................................................... B 3.9-3 B 3.10.1 Sealed Source Contamination ........................... B 3.10-1 B 3.10.2 MODE 5 Shutdown Margin Test RPS Instrumentation ........................ B 3.10-2 B 3.10.3 Independent Spent Fuel Storage Installation (ISFSI) ................... TRM/B 3.10-4 B 3.10.4 Section Not Used ......................................................................... TRM/B 3.10-6 B 3.11.1.1 Liquid Effluents Concentration ............................................................. B 3.11-1 B 3.11.1.2 Liquid Effluents Dose .......................................................................... B 3.11-4 B 3.11.1.3 Liquid Waste Treatment System ......................................................... B 3.11-6 B 3.11.1.4 Liquid Radwaste Effluent Monitoring Instrumentation .......................... B 3.11-7 B 3.11.1.5 Radioactive Liquid Process Monitoring Instrumentation .............. TRM/B 3.11-10 SUSQUEHANNA - UNIT 2 TRM / TOC-6 EFFECTIVE DATE 04/17/2009
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 15 TABLE OF CONTENTS (TECHNICAL REQUIREMENTS MANUAL)
SECTION TITLE PAGE B 3.11.2.1 D ose Rate .................................................................................... T R M/B 3 .11-12 B 3.11.2.2 Dose - Noble Gases .................................. B 3.11-16 B 3.11.2.3 Dose - Iodine, Tritium, and Radionuclides in P a rticulate Fo rm ................................................................................... B 3 .11-18 B 3.11.2.4 Gaseous Radwaste Treatment System ....................................... TRM/B 3.11-20 B 3.11.2.5 Ventilation Exhaust Treatment System ......................................... TRM/B 3.11-21 B 3.11.2.6 Radioactive Gaseous Effluent Monitoring Instrumentation .................................. TRM/B 3.11-24 B 3.11.3 T o ta l Do se ........................................................................................... B 3 .1 1-2 6 B 3.11.4.1 Monitoring Program ..................................................................... TRM /B 3.11-28 B 3.11.4.2 Land Use Census ................................................................................ B 3.11-34 B 3.11.4.3 Interlaboratory Comparison Program ........................................... TRM/B 3.11-36 B 3.12 LOADS CONTROL PROGRAM ................................................... TRM/B 3.12-1 B.3.12.1 Crane Travel - Spent Fuel Storage Pool ..................................... TRM/B 3.12-1 B.3.12.2 Heavy Loads Requirements ........................................................ TRM/B 3.12-2 B.3.12.3 Light Loads Requirements ........................................................... TRM/B 3.12-3 TRM2 Text TOC 4/29/09 SUSQUEHANNA - UNIT 2 TRM / TOC-7 EFFECTIVE DATE 04/17/2009
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 50 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date TOC TABLE OF CONTENTS 04/17/2009 1.0 USE AND APPLICATION
.Page TRM / 1.0-1 08/31/1998 Page TRM / 1.0-2 10/04/2002
.Page TRM / 1.0-3 08/31/1998 2.0 PLANT PROGRAMS Page 2.0-1 08/31/1998 Pages TRM / 2.0-2 and TRM 2.0-3 01/28/2005 Page TRM / 2.0-4 06/25/2002 Page TRM / 2.0-5 04/12/1999 Page TRM / 2.0-6 04/15/2009 Page TRM / 2.0-7 05/15/2008 Page TRM / 2.0-8 04/15/2009 Pages TRM / 2.0-9 through TRM / 2.0-11 11/15/2004 Page TRM / 2.0-12 04/15/2009 Pages TRM / 2.0-13 and TRM / 2.0-14 11/15/2004 Page TRM / 2.0-15 11/15/2005 3.0 APPLICABILITY Pages TRM / 3.0-1 and TRM / 3.0-2 04/14/2008 Page TRM / 3.0-3 03/15/2002 Page TRM / 3.0-4 11/30/2005 3.1 REACTIVITY CONTROL SYSTEMS Page TRM / 3.1-1 10/31/2007 Pages TRM / 3.1-2 through TRM / 3.1-5 08/31/1998 Page TRM / 3.1-6 03/27/2007 Page TRM / 3.1-7 04/15/2009 Page TRM / 3.1-8 03/27/2007 Pages TRM / 3.1-9 and TRM / 3.1-9a 02/18/1999 Page TRM / 3.1-10 02/18/1999 3.2 CORE OPERATING LIMITS REPORT Page TRM / 3.2-1 08/31/1998 Pages TRM / 3.2-2 through TRM / 3.2-54 04/17/2009 3.3 INSTRUMENTATION Pages TRM / 3.3-1 through TRM / 3.3-3 07/16/1999 Pages TRM / 3.3-4 and TRM / 3.3-5 10/31/2007 Page 3.3-6 08/31/1998 Page TRM 3.3-7 10/31/2007 Page 3.3-8 08/31/1998 SUSQUEHANNA - UNIT 2 TRM / LOES-1 S EFFECTIVE DATE 04/17/2009
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 50 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date Page TRM / 3.3-9 04/12/2007 Page TRM / 3.3-9a 12/17/1998 Page TRM / 3.3-10 10/31/2007 Page TRM / 3.3-11 06/02/2005 Page TRM / 3.3-11 a 04/14/2008 Page TRM / 3.3-12 03/30/2001 Page TRM / 3.3-13 09/13/2005 Page TRM / 3.3-14 12/14/1998 Page TRM / 3.3-15 10/22/2003 Page TRM / 3.3-16 06/27/2001 Page TRM / 3.3-17 06/14/2002 Page TRM / 3.3-18 10/31/2007 Pages TRM / 3.3-19 and TRM / 3.3-20 10/22/2003 Page TRM / 3.3-21 04/15/2009 Page TRM / 3.3-2.1a 11/15/2004 Pages TRM /3.3-21b through TRM / 3.3-21d 03/27/2007 Page TRM / 3.3-22 12/03/2004 Pages TRM / 3.3-23 and TRM / 3.3-24 05/16/2003 Page TRM / 3.3-25 10/22/2003 Pages TRM / 3.3-26 and TRM / 3.3-27 04/07/2009 3.4 REACTOR COOLANT SYSTEM Page TRM / 3.4-1 03/31/2006 Pages 3.4-2 through 3.4-5 10/23/1998 Pages TRM / 3.4-6 through TRM / 3.4-8 04/01/2009 Page 3.4-9 08/31/1998 Page 3.4-10 10/31/2007 Page 3.4-11 08/31/1998 Page TRM / 3.4-12 04/17/2009 Page TRM / 3.4-13 03/31/2006 3.5 EMERGENCY CORE COOLING AND RCIC Page TRM / 3.5-1 01/28/2005 Pages 3.5-2 and 3.5-3 08/31/1998 Page TRM / 3.5-4 10/31/2007 Pages 3.5-5 through 3.5-7 08/31/1998 3.6 CONTAINMENT Pages 3.6-1 through 3.6-4 08/31/1998 Page TRM / 3.6-5 01/07/2002 Page 3.6-6 08/31/1998 Pages TRM / 3.6-7 through TRM / 3.6-9 12/31/2002 SUSQUEHANNA - UNIT 2 TRM / LOES-2 EFFECTIVE DATE 04/17/2009
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 50 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date 3.7 PLANT SYSTEMS Pages TRM / 3.7-1 and TRM / 3.7-2 07/29/1999 Page 3.7-3 08/31/1998 Page TRM / 3.7-4 03/31/2006 Page TRM / 3.7-5 04/07/2009 Pages TRM / 3.7-6 through TRM / 3.7-8 08/02/1999 Pages TRM / 3.7-9 and TRM / 3.7-10 04/07/2009 Page TRM / 3.7-11 01/21/2000 Page TRM / 3.7-12 08/02/1999 Page TRM / 3.7-13 04/07/2009 Page TRM / 3.7-14 08/09/2005 Pages TRM / 3.7-15 and TRM / 3.7-16 08/02/1999 Page TRM / 3.7-17 04/07/2009 Page TRM / 3.7-18 08/02/1999 Page TRM / 3.7-19 04/07/2009 Pages TRM / 3.7-20 through TRM / 3.7-22 08/02/1999 Page TRM / 3.7-23 04/07/2009 Page TRM / 3.7-24 03/31/2006 Pages TRM / 3.7-25 and TRM / 3.7-26 08/02/1999 Page TRM / 3.7-27 10/31/2007 Page TRM / 3.7-28 11/29/2006 Page TRM / 3.7-29 11/16/2001 Page TRM / 3.7-30 11/30/2005 Page TRM / 3.7-31 11/16/2001 Page TRM / 3.7-32 01/09/2004 Page TRM / 3.7-33 10/05/2002 Page TRM / 3.7-34 03/31/2006 Pages TRM / 3.7-35 and TRM / 3.7-36 02/01/1999 Pages 3.7-37 through 3.7-38 08/31/1998 Page TRM / 3.7-39 03/31/2006 Page TRM / 3.7-40 02/14/2005 Page TRM / 3.7-40a 06/20/2008 Page TRM / 3.7-41 .09/04/2008 Page TRM / 3.7-42 08/31/1998 Pages TRM / 3.7-43 through TRM / 3.7-45 10/05/2006 Page TRM / 3.7-46 06/07/2007 Page TRM / 3.7-47 10/05/2006 Page TRM / 3.7-48 06/07/2007 Page TRM / 3.7-49 03/09/2001 Page TRM / 3.7-50 08/16/2006 Page TRM / 3.7-51 12/03/2004 Page TRM / 3.7-52 04/15/2003 Page TRM / 3.7-53 07/29/1999 Pages TRM / 3.7-54 through TRM/ 3.7-56 04/01/2009 SUSQUEHANNA - UNIT 2 TRM I LOES-3 EFFECTIVE DATE 04/17/2009
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 50 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date 3.8 ELECTRICAL POWER Page TRM / 3.8-1 04/02/2002 Pages TRM / 3.8-2 and TRM / 3.8-3 01/28/2005 Page TRM / 3.8-4 01/31/2005 Pages TRM / 3.8-5 and TRM / 3.8-6 04/02/2002 Pages TRM / 3.8-7 through TRM / 3.8-10 10/31/2007 Page TRM / 3.8-11 08/10/2004 Page TRM / 3.8-12 12/03/2004 Pages 3.8-13 and 3.8-14 08/31/1998 Page TRM / 3.8-15 01/28/2005 Pages TRM / 3.8-16 and TRM / 3.8-17 04/02/2002 Page 3.8-18 02/01/1999 Page TRM / 3.8-19 04/02/2002 Page TRM / 3.8-20 02/01/1999 Pages TRM / 3.8-21 through TRM / 3.8-23 06/06/1999 Pages 3.8-24 and 3.8-25 08/31/1998 Pages TRM / 3.8-26 through TRM / 3.8-29 11/29/2006 3.9 REFUELING OPERATIONS Pages 3.9-1 through 3.9-3 08/31/1998 3.10 MISCELLANEOUS Page TRM / 3.10-1 03/31/2006 Pages 3.10-2 through 3.10-4 08/30/1998 Pages TRM / 3.10-5 and TRM /3.10-6 03/27/2007 Page TRM / 3.10-7 03/31/2006 3.11 RADIOACTIVE EFFLUENTS Page TRM / 3.11-1 03/31/2006 Pages 3.11-2 through 3.11-3 08/31/1998 Page TRM / 3.11-4 03/31/2006 Page 3.11-5 08/31/1998 Page TRM / 3.11-6 03/31/2006 Pages 3.11-7 through 3.11-9 08/31/1998 Page TRM / 3.11-10 12/03/2004 Pages 3.11-11 and 3.11-12 08/31/1998 Page TRM / 3.11-13 04/12/2007 Page TRM / 3.11-14 12/03/1004 Pages 3.11-15 and 3.11-16 09/01/1998 Page TRM / 3.11-17 03/31/2006 Page 3.11-18 -08/31/1998 Page TRM / 3.11-19 08/15/2005 Pages TRM / 3.11-20 and TRM / 3.11-21 03/31/2006 SUSQUEHANNA - UNIT 2 TRM / LOES-4 EFFECTIVE DATE 04/17/2009
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 50 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date Page TRM / 3.11-22 04/02/2002 Page TRM / 3.11-23 11/14/2006 Page TRM / 3.11-24 05/13/2005 Page TRM / 3.11-25 04/12/2007 Pages TRM / 3.11-26 through TRM / 3.11-28 01/21/2004 Page TRM / 3.11-29 12/03/2004 Pages TRM 3.11-30 through TRM / 3.11-32 01/21/2004 Page TRM / 3.11-33 03/31/2006 Page 3.11-34 08/31/1998 Page TRM / 3.11-35 03/31/2006 Pages TRM / 3.11-36 through TRM / 3.11-39 11/30/2005 Pages 3.11-40 through 3.11-44 08/31/1998 Page TRM / 3.11-45 03/31/2006 Page 3.11-46 08/31/1998
.Page TRM / 3.11-47 03/31/2006 3.12 LOADS CONTROL PROGRAM Pages TRM / 3.12-1 through TRM / 3.12-3 02/05/1999 Page TRM / 3.12-4 03/14/2008 Page TRM / 3.12-5 02/05/1999 4.0 ADMINISTRATIVE CONTROLS Pages TRM / 4.0-1 through TRM / 4.0-3 08/31/1998 Page TRM / 4.0-4 12/11/2008 Pages TRM / 4.0-5 through TRM / 4.0-8 08/31/1998 SUSQUEHANNA - UNIT 2 TRM / LOES-5 EFFECTIVE DATE 04/17/2009
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 50 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date B 3.0 APPLICABILITY BASES Pages TRM / B 3.0-1 through TRM / B 3.0-3 08/31/1998 Page TRM / B 3.0-4 01/10/2007 Page TRM / B 3.0-5 04/14/2008 Page TRM B 3.0-6 08/31/1998 Page TRM / B 3.0-7 04/12/2007 Pages TRM / B 3.0-8 through TRM / B 3.0-10 08/31/1998 Pages TRM / B 3.0-11 and TRM / B 3.0-12 03/15/2002 Pages TRM / B 3.0-13 and TRM / B 3.0-14 11/30/2005 Page TRM / B 3.0-15 03/15/2002 B 3.1 REACTIVITY CONTROL SYSTEMS BASES Page TRM / B 3.1-1 07/13/1999 Pages TRM / B 3.1-2 and TRM / B 3.1-3 10/31/2007 Page B 3.1-4 08/31/1998 Pages TRM / B 3.1-5 through TRM / B 3.1-7 03/27/2007 Page TRM / B 3.1-8 02/18/1999 B 3.2 CORE OPERATING LIMITS BASES Page B 3.2-1 08/31/1998 B 3.3 INSTRUMENTATION BASES Page TRM / B 3.3-1 04/07/2000 Pages TRM / B 3.3-2 and TRM / B-3.3-2a 10/31/2007 Pages TRM / B 3.3-3 and TRM / B 3.3-3a 10/31/2007 Pages TRM / B 3.3-4 and TRM / B 3.3-5 05/30/2006 Pages TRM / B 3.3-6 through TRM / B 3.3-9 10/31/2007 Page B 3.3-10 08/31/1998 Pages TRM / B 3.3-11 and TRM / B 3.3-12 09/13/2005 Page TRM / B 3.3-13 12/03/2004 Page TRM / B 3.3-14 06/25/2002 Page TRM / B 3.3-14a 10/31/2007 Page TRM / B 3.3-14b 06/14/2002 Pages TRM / B 3.3-15 through TRM / B 3.3-17 10/22/2003 Pages TRM / B 3.3-18 and TRM / B 3.3-19 03/27/2007 Pages TRM / B 3.3-19a and TRM / B 3.3-19b 03/27/2007 Page TRM / B 3.3-19c 04/17/2009 Pages TRM / B 3.3-19d and TRM / B 3.3-19e 03/27/2007 Page TRM / B 3.3-20 12/11/2008 Page TRM / B 3.3-21 05/16/2003 Page TRM / B 3.3-22 10/22/2003 Page TRM / B 3.3-23 05/16/2003 Pages TRM / B 3.3-24 and TRM / B 3.3-25 04/07/2009 SUSQUEHANNA - UNIT 2 TRM / LOES-6 EFFECTIVE DATE 04/17/2009
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 50 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date B 3.4 REACTOR COOLANT SYSTEM BASES Page TRM / B 3.4-1 08/31/1998 Pages TRM / B 3.4-2 and TRM / B3.4-3 04/01/2009 Pages TRM / B 3.4-4 and TRM / B 3.4-4a 10/31/2007 Page TRM / B 3.4-5 10/15/1999 Page B 3.4-6 08/31/1998 B 3.5 ECCS AND RCIC BASES Pages B 3.5-1 and B 3.5-2 08/31/1998 Pages TRM / B 3.5-3 and TRM / B 3.5-3a 10/31/2007 Page B 3.5-4 08/31/1998 Page TRM / B 3.5-5 10/31/2007 B 3.6 CONTAINMENT BASES Page TRM / B 3.6-1 07/26/2001 Page TRM / B 3.6-2 02/01/1999 Page B 3.6-3 08/31/1998 Page TRM / B 3.6-4 03/29/2007 Page TRM / B 3.6-5 04/04/2007 Page TRM / B 3.6-6 12/03/2004 Pages TRM / B 3.6-7 through TRM / B 3.6-11 12/31/2002 B 3.7 PLANT SYSTEMS BASES Pages B 3.7-1 and B 3.7-2 08/31/1998 Pages TRM / B 3.7-3 and TRM / B 3.7-3a 12/27/2007 Page TRM / B 3.7-4 03/31/2006 Page TRM / B 3.7-5 08/02/1999 Pages TRM / B 3.7-6 and TRM / B 3.7-6a 03/31/2006 Pages TRM / B 3.7-7 and TRM / B 3.7-7a 08/02/1999 Page TRM / B 3.7-8 08/02/1999 Page TRM / B 3.7-9 03/31/2006 Page TRM / B 3.7-10 08/02/1999 Pages TRM / B 3.7-10a through TRM / B 3.7-11 a 03/31/2006 Pages TRM / B 3.7-12 through TRM / B 3.7-14 08/02/1999 Pages TRM / B 3.7-14a and TRM / B 3.7-14b 01/09/2004 Pages TRM / B 3.7-15 and TRM / B 3.7-16 02/01/1999 Pages B 3.7-17 through B 3.7-20 08/31/1998 Page TRM / B 3.7-21 02/14/2005 Page TRM / B 3.7-21a 06/20/2008 Pages TRM / B 3.7-22 and TRM / B 3.7-23 01/30/2008 Pages TRM / B 3.7-24 through TRM / B 3.7-29 10/05/2006 Page TRM / B 3.7-30 06/07/2007 Pages TRM / B 3.7-30a and TRM / B 3.7-30b 10/05/2006 Page TRM / B 3.7-32 03/09/2001 Page TRM / B 3.7-33 04/15/2003 SUSQUEHANNA - UNIT 2 TRM / LOES-7 EFFECTIVE DATE 04/17/2009
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 50 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date Page TRM / B 3.7-34 12/03/2004 Page TRM / B 3.7-35 07/05/2000 Pages TRM / B 3.7-36 through TRM / B 3.7-40 04/01/2009 B 3.8 ELECTRICAL POWER BASES Page TRM / B 3.8-1 04/02/2002 Pages TRM / B 3.8-2 and TRM / B 3.8-2a 01/28/2005 Page TRM / B 3.8-3 04/02/2002 Page TRM / B 3.8-3a 04/02/2002 Page TRM / B 3.8-4 04/02/2002 Page TRM / B 3.8-4a 08/10/2004 Page TRM / B 3.8-5 08/31/1998 Pages TRM / B 3.8-6 through TRM / B 3.8-16 04/02/2002 Page TRM / B 3.8-17 01/28/2005 Pages TRM / B 3.8-18 through TRM / B 3.8-24 11/29/2006 B.3.9 REFUELING OPERATIONS BASES Pages B 3.9-1 and B 3.9-2 08/31/1998 Pages B 3.9-3 through B 3.9-7 10/23/1998 B 3.10 MISCELLANEOUSBASES Page B 3.10-1 08/31/1998 Pages TRM / B 3.10-2 and TRM / B 3.10-3 03/27/2007 Pages TRM / B 3.10-4 and TRM / B 3.10-5 08/23/1999 B 3.11 RADIOACTIVE EFFLUENTS BASES Pages B 3.11-1 through B 3.11-9 08/31/1998 Page TRM / B 3.11-10 02/01/1999 Pages TRM/B 3.11-11 and TRM/B 3.11-11 a 04/07/2000 Pages TRM/B 3.11-12 and TRM/B 3.11-13 02/01/1999 Page TRM / B 3.11-14 12/03/2004 Page TRM / B 3.11-15 02/01/1999 Pages B 3.11-16 through B 3.11-19 08/31/1998 Page TRM / B 3.11-20 04/02/2002 Page TRM / B 3.11-20a 04/02/2002 Page TRM / B 3.11-21 05/13/2005 Pages TRM / B 3.11-22 and TRM / B 3.11-23 11/14/2006 Page TRM / B 3.11-23a 05/13/2005 Pages TRM / B 3.1-1-24 and TRM / B 3.11-25 01/21/2004 Pages B 3.11-26 through B 3.11-27 08/31/1998 Pages TRM / B 3.11-28 and TRM / B 3.11-29 11/30/2005 Page TRM / B 3.11-30 12/03/2004 Pages B 3.11-31 through B 3.11-35, 08/31/1998 Page TRM / B 3.11-36 02/12/1999 SUSQUEHANNA - UNIT 2 TRM / LOES-8 EFFECTIVE DATE 04/17/2009
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 50 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date B.3.12 LOADS CONTROL PROGRAM BASES Page TRM / B 3.12-1 09/19/2007 Pages TRM / B 3.12-2 and TRM / B 3.12-3 02/05/1999 TRM2 text LOES.doc 4/28/09 SUSQUEHANNA - UNIT 2 TRM / LOES-9 EFFECTIVE DATE 04/17/2009
Instrument Trip Setpoint Program PPL Rev. 8 2.2 2.0 PLANT PROGRAMS AND SETPOINTS 2.2 Instrument Trip Setpoint Table The Instrument Trip Setpoint Limits in Table 2.2-1 are the Trip Setpoint value limits that were contained in the Instrumentation Setpoint tables for protection systems and other functions important to safety that were included in the scope of the original Standard Technical Specifications. Actual instrument setpoints are established utilizing the Allowable Values specified in the Technical Specifications and Technical Requirements. Allowable Values are established in the Reference LCOs and TROs identified in this Table. TRO references are enclosed in square brackets.
Instrumentation process setpoints for the listed subsystems and trip functions are set consistent with the Trip Setpoint Limit Column of Table 2.2-1. Actual setpoints are established in accordance with engineering procedures.
Alarm setpoints and other non-protection system trip settings as may be found in the Technical Specifications or in the Technical Requirements are not included in this table.
Reference NDAP-QA-1104 Setpoint Change Control SUSQUEHANNA - UNIT 2 TRM / 2.0-5 EFFECTIVE DATE 04/02/1999
Instrument Trip Setpoint Program PPL Rev. 8 2.2 TABLE 2.2-1 (Page 1 of 8)
INSTRUMENTATION SETPOINTS SYSTEM/REFERENCE LCO [TRO] TRIP FUNCTION TRIP SETPOINT 2.2.1 Reactor Protection 2.2.1.1 3.3.1.1 Intermediate Range Monitor, Neutron Flux - <120/125 divisions of full scale High 2.2.1.2 3.3.1.1 Average Power Range Monitor, Neutron Flux -
- 18% of RATED THERMAL POWER High (Setdown) 2.2.1.3 3.3.1.1 Average Power Range Monitor, Simulated 0.55 W + 58.7%
Thermal Power - High Two Loop Operation 2.2.1.4 3.3.1.1 Average Power Range Monitor, Simulated 0.55 (W - AW) + 5 8 .7 %(b)
Thermal Power- High Single Loop Operation 2.2.1.5 3.3.1.1 Average Power Range Monitor, Simulated
- 113.5% of RATED THERMAL Thermal Power - High Flow Clamp POWER 2.2.1.6 3.3.1.1 Average Power Range Monitor, Neutron Flux -
- 118% of RATEDTHERMAL High POWER 2.2.1.7 3.3.1.1 Reactor Vessel Steam Dome Pressure - High _<1087 psig 2.2.1.8 3.3.1.1 Reactor Vessel Water Level - Low, Level 3 > 13.0 inches(a) 2.2.1.9 3.3.1.1 Main Steam Isolation Valve - Closure < 10% closed 2.2.1.10 This Section Not Used 2.2.1.11 3.3.1.1 Drywell Pressure- High
- 1.72 psig 2.2.1.12 3.3.1.1 Scram Discharge Volume Water Level - High -
- 65 gallons Level Transmitter 2.2.1.13 3.3.1.1 Scram Discharge Volume Water Level - High - *61 gallons Float Switch 2.2.1.14 3.3.1.1 Turbine Stop Valve - Closure <5.5% closed 2.2.1.15 3.3.1.1 Turbine Control Valve Fast Closure, Trip Oil 500 psig Pressure - Low (continued)
(a) See Figure 2.2-1.
(b) For single loop operation, the value of AW = 8.7.
SUSQUEHANNA - UNIT 2 TRM / 2.0-6 EFFECTIVE DATE 04/15/2009
Instrument Trip Setpoint Program PPL Rev. 8 2.2 TABLE 2.2-1 (Page 2 of 8)
INSTRUMENTATION SETPOINTS SYSTEM/REFERENCE LCO [TRO] TRIP FUNCTION TRIP SETPOINT 2.2.1.16 OPRM Instrumentation 2.2.1.16.1 3.3.1.1 Sp PBA Amplitude Trip See COLR - TRO 3.2 2.2.1.16.2 3.3.1.1 Np PBA Successive Confirmation Count Trip See COLR - TRO 3.2 2.2.1.16.3 [3.3.9] TOL.(E) Period Tolerance 0.10 sec 2.2.1.16.4 [3.3.9] fc Conditioning Filter Cutoff Frequency 1.50 Hz 2.2.1.16.5 [3.3.9] Tmin Oscillation Period Lower Time Limit 1.00 sec 2.2.1.16.6 [3.3.9] Tmax Oscillation Period Upper Time Limit 3.50 sec 2.2.1.16.7 [3.3.9] LPRMmin Minimum LRPMs/CeII Required for 2 Cell Operability 2.2.1.16.8 [3.3.9] S1 Peak Threshold Setpoint/ABA &GRBA 1.20 2.2.1.16.9 [3.3.9] S2 Valley Threshold Setpoint/ABA & GRBA 0.85 2.2.1.16.10 [3.3.9] Smax Amplitude Trip Setpoint/ABA 1.50 2.2.1.16.11 [3.3.9] DR3 Growth Rate Factor Setpoint/GRBA 1.60 2.2.2 Isolation Actuation Instrumentation 2.2.2.1 Primary Containment Isolation 2.2.2.1.1 3.3.6.1 Reactor Vessel Water Level Low, Level 3 >13.0 inches(a) 2.2.2.1.2 3.3.6.1 Reactor Vessel Water Level Low Low, Level 2 > -38.0 inches(a) 2.2.2.1.3 3.3.6.1 Reactor Vessel Water Level Low Low Low, > -129 inches(a)
Level 1 2.2.2.1.4 3.3.6.1 Drywell Pressure- High < 1.72 psig 2.2.2.1.5 3.3.6.1 SGTS Exhaust Radiation - High
- 23.0 mR/hr 2.2.2.1.6 [3.3.6] Main Steam Line Radiation - High High < 15 x full power background without hydrogen injection (continued)
(a)See Figure 2.2-1 SUSQUEHANNA - UNIT 2 TRM / 2.0-7 EFFECTIVE DATE 05/15/2008
Instrument Trip Setpoint Program PPL Rev. 8 2.2 TABLE 2.2-1 (Page 3 of 8)
INSTRUMENTATION SETPOINTS SYSTEM/REFERENCE LCO
[TRO] TRIP FUNCTION TRIP SETPOINT 2.2.2.2 Secondary Containment Isolation 2.2.2.2.1 3.3.6.2 Reactor Vessel Water Level - Low Low, > -38.0 inches(a)
Level 2 2.2.2.2.2 3.3.6.2 Drywell Pressure - High
- 1.72 psig 2.2.2.2.3 3.3.6.2 Refuel Floor High Exhaust Duct Radiation - < 18 mR/hr High 2.2.2.2.4 3.3.6.2 Railroad Access Shaft Exhaust Duct <_5 mR/hr Radiation - High 2.2.2.2.5 3.3.6.2 Refuel Floor Wall Exhaust Duct Radiation - < 21 mR/hr High 2.2.2.3 Main Steam Line Isolation 2.2.2.3.1 3.3.6.1 Reactor Vessel Water Level - Low Low Low, >-129 inches(a)
Level 1 2.2.2.3.2 3.3.6.1 Main Steam Line Pressure - Low _ 861 psig 2.2.2.3.3 3.3.6.1 Main Steam Line Flow - High < 173 psid 2.2.2.3.4 3.3.6.1 Condenser Vacuum - Low > 9.0 inches Hg vacuum 2.2.2.3.5 3.3.6.1 Reactor Building Main Steam Line Tunnel < 1771F Temperature - High 2.2.2.3.6 This Section Not Used 2.2.2.3.7 [3.3.6] Reactor Building Main Steam Line Tunnel < 991F A Temperature - High 2.2.2.3.8 [3.3.6] Turbine Building Main Steam Tunnel < 1971F Temperature - High 2.2.2.4 Reactor Water Cleanup System Isolation 2.2.2.4.1 3.3.6.1 Reactor Vessel Water Level - Low Low, >-38 inches(a)
Level 2 2.2.2.4.2 3.3.6.1 RWCU A Flow - High _ 59 gpm 2.2.2.4.3 3.3.6.1 RWCU Flow - High < 462 gpm 2.2.2.4.4 3.3.6.1 RWCU Penetration Area Temperature - High < 131OF 2.2.2.4.5 [3.3.6] RWCU Penetration Room Area A < 691F Temperature - High 2.2.2.4.6 3.3.6.1 RWCU Pump Area Temperature - High < 147OF 2.2.2.4.7 [3.3.6] RWCU Pump Room Area A Temperature - < 69OF High 2.2.2.4.8 3.3.6.1 RWCU Heat Exchanger Area Temperature - < 1471F High 2.2.2.4.9 [3.3.6] RWCU Heat Exchanger Room Area < 69OF A Temperature - High (continued)
(a)See Figure 2.2-1.
SUSQUEHANNA - UNIT 2 TRM / 2.0-8 EFFECTIVE DATE 04/15/2009
Instrument Trip Setpoint Program PPL Rev. 8 2.2 TABLE 2.2-1 (Page 4 of 8)
INSTRUMENTATION SETPOINTS SYSTEM/REFERENCE LCO
[TRO] TRIP FUNCTION TRIP SETPOINT 2.2.2.5 Reactor Core Isolation Cooling System Isolation 2.2.2.5.1 3.3.6.1 RCIC Steam Line A Pressure - High <138 inches H2 0 2.2.2.5.2 3.3.6.1 RCIC Steam Supply Line Pressure - Low > 60 psig 2.2.2.5.3 3.3.6.1 RCIC Turbine Exhaust Diaphragm Pressure < 10.0 psig
- High 2.2.2.5.4 3.3.6.1 RCIC Equipment Room Temperature - High < 1671F 2.2.2.5.5 3.3.6.1 RCIC Pipe Routing Area Temperature - High < 1671F 2.2.2.5.6 3.3.6.1 RCIC Emergency Area Cooler Temperature - < 1671F High 2.2.2.5.7 3.3.6.1 Drywell Pressure - High < 1.72 psig 2.2.2.5.8 [3.3.6] RCIC Equipment Room A Temperature - High < 891F 2.2.2.5.9 [3.3.6] RCIC Pipe Routing Area A Temperature - < 89 0F High 2.2.2.6 High Pressure Coolant Injection System Isolation 2.2.2.6.1 3.3.6.1 HPCI Steam Line A Pressure - High <370 inches H 2 0 2.2.2.6.2 3.3,6.1 HPCI Steam Supply Line Pressure - Low > 104 psig 2.2.2.6.3 3.3.6.1 HPCI Turbine Exhaust Diaphragm Pressure - *< 10 psig High 2.2.2.6.4 3.3.6.1 HPCI Equipment Room Temperature - High < 1671F 2.2.2.6.5 3.3.6.1 HPCI Emergency Area Cooler Temperature - < 1671F High 2.2.2.6.6 3.3.6.1 HPCI Pipe Routing Area Temperature - High < 1671F 2.2.2.6.7 3.3.6.1 Drywell Pressure - High < 1.72 psig 2.2.2.6.8 [3.3.6] HPCI Equipment Room A Temperature - High < 891F 2.2.2.6.9 [3.3.6] HPCI Pipe Routing Area A Temperature - < 89OF High 2.2.2.7 Shutdown Cooling/System Isola tion 2.2.2.7.1 3.3.6.1 Reactor Vessel Water Level - Low, Level 3 > 13.0 inches(a) 2.2.2.7.2 3.3.6.1 Reactor Vessel Steam Dome Pressure - High < 98 psig 2.2.2.27.3 [3.3.6] RHR Flow - High < 25,000 gpm 2.2.3 ECCS Actuation 2.2.3.1 Core Spray System 2.2.3.1.1 3.3.5.1 Reactor Vessel Water Level - Low Low Low, >_-129 inches(a)
Level 1 2.2.3.1.2 3.3.5.1 Drywell Pressure - High < 1.72 psig 2.2.3.1.3 3.3.5.1 Reactor Vessel Steam Dome Pressure - Low >413, < 427 psig injection permissive (continued)
(a) See Figure 2.2-1.
SUSQUEHANNA - UNIT 2 TRM / 2.0-9 EFFECTIVE DATE 11/15/2004
Instrument Trip Setpoint Program PPL Rev. 8 2.2 TABLE 2.2-1 (Page 5 of 8)
INSTRUMENTATION SETPOINTS SYSTEM/REFERENCE LCO
[TRO] TRIP FUNCTION TRIP SETPOINT 2.2.3.2 LPCI Mode of RHR System 2.2.3.2.1 3.3.5.1 Reactor Vessel Water Level - Low Low Low, >-129 inches(a)
Level 1 2.2.3.2.2 3.3.5.1 Drywell Pressure - High < 1.72 psig 2.2.3.2.3 3.3.5.1 Reactor Vessel Steam Dome Pressure - Ž413, *427 psig Low, injection permissive 2.2.3.2.4 3.3.5.1 Reactor Vessel Steam Dome Pressure - > 236 psig, decreasing Low, Recirculation Discharge Valve permissive 2.2.3.3 HPCI System 2.2.3.3.1 3.3.5.1 Reactor Vessel Water Level - Low Low, >_-38 inches(a)
Level 2 2.2.3.3.2 3.3.5.1 Drywell Pressure - High *<1.72 psig 2.2.3.3.3 3.3.5.1 Condensate Storage Tank Level - Low > 36.0 inches above tank bottom 2.2.3.3.4 3.3.5.1 Reactor Vessel Water Level - High, Level 8 _ 54 inches 2.2.3.4 Automatic Depressurization System (ADS) 2.2.3.4.1 3.3.5.1 Reactor Vessel Water Level - Low Low Low, >-129 inches Level 1 2.2.3.4.2 3.3.5.1 Drywell Pressure - High *1.72 psig 2.2.3.4.3 3.3.5.1 ADS Timer <102 seconds 2.2.3.4.4 3.3.5.1 Core Spray Pump Discharge Pressure - High > 135, < 155 psig 2.2.3.4.5 3.3.5.1 Low Pressure Coolant Injection Pump > 121,
- 129 psig Discharge Pressure - High 2.2.3.4.6 3.3.5.1 Reactor Vessel Water Level - Low, Level 3 > 13 inches Confirmatory 2.2.3.4.7 3.3.5.1 ADS Drywell Pressure Bypass Timer <420 seconds 2.2.3.5 Loss of Power - ECCS Actuation 2.2.3.5.1 4.16kv ESS Bus Undervoltage (Loss of Voltage < 20%)
2.2.3.5.1.1 3.3.8.1 Bus Undervoltage _ 823.2, < 856.8 Volts 2.2.3.5.1.2 3.3.8.1 Time delay > 0.4,:5 0.6 seconds (continued)
(a)See Figure 2.2-1.
SUSQUEHANNA - UNIT 2 TRM / 2.0-10 EFFECTIVE DATE 11/15/2004
Instrument Trip Setpoint Program PPL Rev. 8 2.2 TABLE 2.2-1 (Page 6 of 8)
INSTRUMENTATION SETPOINTS SYSTEM/REFERENCE LCO
[TRO]. TRIP FUNCTION TRIP SETPOINT 2.2.3.5.2 4.16kV ESS Bus Undervoltage (Degraded Voltage < 65%)
2.2.3.5.2.1 3.3.8.1 Bus Undervoltage _2641.1, <2748.9 Volts 2.2.3.5.2.2 3.3.8.1 Time delay Ž2.7,:5 3.3 seconds 2.2.3.5.3 4.16kV ESS Bus Undervoltage (Degraded Voltage, < 93%)
2.2.3.5.3.1 3.3.8.1 Bus Undervoltage > 3829.3, < 3906.7 Volts 2.2.3.5.3.2 3.3.8.1 Time Delay (Non-LOCA) >_4 minute, 30 seconds
_<5 minute, 30 seconds 2.2.3.5.3.4 3.3.8.1 Time Delay (LOCA) Ž 9, < 11 seconds 2.2.3.5.4 480V ESS Bus 0B565 Undervoltage (Degraded Voltage, < 65%)
2.2.3.5.4.1 [3.8.5] 480V Basis >308.9, <315.1 Volts 2.2.3.5.4.2 [3.8.5] Time Delay Ž4.5, _< 5.5 seconds 2.2.3.5.5 480V ESS Bus 0B565 Undervoltage (Degraded Voltage, < 92%)
2.2.3.5.5.1 [3.8.5] 480V Basis > 437.6, <446.4 Volts 2.2.3.5.5.2 [3.8.5] Time Delay > 9,<5 11 seconds 2.2.4 ATWS Alternate Rod Injection and Recirculation Pump Trip 2.2.4.1 3.3.4.2J[3.1.1] Reactor Vessel, Water Level - Low Low, > -38 inches(a)
Level 2 2.2.4.1 3.3.4.2J3.1.1] Reactor Vessel Steam Dome Pressure - High < 1135 psig 2.2.5 End of Cycle Recirculation Pump Trip 2.2.5.1 3.3.4.1 Turbine Stop Valve-Closure < 5.5% closed 2.2.5.2 3.3.4.1 Turbine Control Valve - Fast Closure >_500 psig 2.2.6 Reactor Core Isolation Cooling System Actuation 2.2.6.1 3.3.5.2 Reactor Vessel Water Level - Low Low, > -38 inches(a)
Level 2 2.2.6.2 3.3.5.2 Reactor Vessel Water Level - High, Level 8 < 54 inches(a) 2.2.6.3 3.3.5.2 Condensate Storage Tank Level - Low _ 36.0 inches above tank bottom (continued)
(a) See Figure 2.2-1.
SUSQUEHANNA - UNIT 2 TRM 2.0-11 EFFECTIVE DATE 11/15/2004
Instrument Trip Setpoint Program PPL Rev. 8 2.2 TABLE 2.2-1 (Page 7 of 8)
INSTRUMENTATION SETPOINTS SYSTEM/REFERENCE LCO
[TRO] TRIP FUNCTION TRIP SETPOINT 2.2.7 Control Rod Block 2.2.7.1 Rod Block Monitor 2.2.7.1.1 3.3.2 Low Power Range - Upscale See COLR - TRO 3.2 3.3.2 Intermediate Power Range - Upscale See COLR - TRO 3.2 3.3.2 High Power Range - Upscale See COLR - TRO 3.2 2.2.7.1.2 3.3.2 Low Power Range Setpoint See COLR - TRO 3.2 3.3.2 Intermediate Power Range Setpoint See COLR - TRO 3.2 3.3.2 High Power Range.Setpoint See COLR - TRO 3.2 2.2.7.2 APRM 2.2.7.2.1 [3.1.3] Simulated Thermal Power-High - Two Loop 0.55 W + 54.2%
Operation 2.2.7.2.2 [3.1.3] Simulated Thermal Power-High - Single 0.55 (W- iAW) + 54.2%(c)
Loop Operation 2.2.7.2.3 [3.1.3] Simulated Thermal Power-High Clamp < 108% of RATED THERMAL POWER 2.2.7.2.4 [3.1.3] Downscale >5% of RATED THERMAL POWER 2.2.7.2.5 [3.1.3] Neutron Flux - High (Setdown) < 12% of RATED THERMAL POWER 2.2.7.3 Source Range Monitors 2.2.7.3.1 [3.1.3] Upscale < 2E5 cps 2.2.7.3.2 [3.1.3] Downscale > 3.0 cps(b) 2.2.7.4 -Intermediate Range Monitors 2.2.7.4.1 [3.1.3] Upscale < 108/125 divisions of full scale 2.2.7.4.2 [3.1.3] Downscale Ž5/125 divisions of full scale 2.2.7.5 Scram Discharge Volume 2.2.7.5.1 [3.1.3] Water Level- High < 35.9 gallons 2.2.7.6 Reactor Coolant System Recirculation Flow 2.2.7.6.1 [3.1.3] Upscale 114%
(continued)
(b)With a signal-to-noise ratio _>2, or within the limits of Figure 2.2-2.
(c)For single loop operation, the valve of AW = 8.7.
SUSQUEHANNA - UNIT 2 TRM / 2.0-12 EFFECTIVE DATE 04/15/2009
Instrument Trip Setpoint Program PPL Rev. 8. 2.2 TABLE 2.2-1 (Page 8 of 8)
INSTRUMENTATION SETPOINTS SYSTEM/REFERENCE LCO
[TRO] TRIP FUNCTION TRIP SETPOINT 2.2.8 CREOASS 2.2.8.1 3.3.7.1 Main Control Room Outside Air Intake _ 5 mR/hr Radiation Monitor 2.2.8.1.1 3.3.7.1 Reactor Vessel Water Level - Low Low, >_-38.0 inches(a)
Level 2 2.2.8.1.2 3.3.7.1 Drywell Pressure - High < 1.72 psig 2.2.8.1.3 3.3.7.1 Refuel Floor High Exhaust Duct Radiation - < 18 mR/hr High 2.2.8.1.4 3.3.7.1 Railroad Access Shaft Exhaust Duct 5 mR/hr Radiation - High 2.2.8.1.5 3.3.7.1 Refuel Floor Wall Exhaust Duct Radiation - < 21 mR/hr High 2.2.9 Feedwater/Main Turbine Trip System Actuation 2.2.9.1 3.3.2.2 Reactor Vessel Level - High <54.0 inches(a) 2.2.10 MVP Isolation 2.2.10.1 [3.3.11] Main Steam Line Radiation- High High < 15 x full power background without hydrogen injection (a)See Figure 2.2-1 SUSQUEHANNA - UNIT 2 TRM / 2.0-13 EFFECTIVE DATE 11/15/2004
Instrument Trip Setpoint Table PPL Rev. 8 2.2 FIGURE 2.2-1 REACTOR VESSEL WATER LEVEL SUSQUEHANNA - UNIT 2 TRMV / 2.0-14 EFFECTIVE DATE 11/15/2004
Instrument Trip Setpoint Table PPL Rev. 8 2.2 Instrument Trip Setpoint Table 2.2 3
2.8 2.6 2.4 2.2 2
V,) 1.8 0C 1.6 cc 0 1.4 z 1.2 1
or) 0.8 0.6 0.4 0.2 0
2 6 10 14 18 22 26 30 Signal-to-Noise Ratio Figure 2.2-2 Minimum SRM Trip Setpoint Versus Signal-to-Noise Ratio SUSQUEHANNA - UNIT 2 TRM / 2.0-15 EFFECTIVE DATE 11/15/2005
Control Rod Block Instrumentation PPL Rev. 4 3.1.3 3.1 Reactivity Control Systems 3.1.3 Control Rod Block Instrumentation TRO 3.1.3 The control rod block instrumentation for each function in Table 3.1.3-1 shall be OPERABLE.
APPLICABILITY: According to Table 3.1.3-1 ACTIONS
NOTE- ------------------------------------------------------
Separate condition entry is allowed for each channel CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Enter the Condition referenced Immediately channels inoperable, in Table 3.1.3-1 for the channel.
B. As required by Required B.1 Place at least one inoperable 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from Action A. 1 and channel in the tripped discovery of loss of referenced in condition. trip capability Table 3.1.3-1. AND B.2 Place the inoperable channel in 7 days the tripped condition.
C. As required by Required C.1 Place the inoperable channel in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Action A. 1 and the tripped condition.
referenced in Table 3:1.3-1.
D. Required Actions and D.1 Suspend Control Rod Immediately Completion Time of withdrawal.
Conditions B or C not met.
SUSQUEHANNA - UNIT 2 TRM / 3.1-5 EFFECTIVE DATE 8/31/1998
Control Rod Block Instrumentation PPL Rev. 4 3.1.3 TECHNICAL REQUIREMENT SURVEILLANCE
NOTES ---------------------------
- 1. Refer to Table 3.1.3-1 to determine .which TRSs apply for each Control Rod Block Function.
- 2. Neutron detectors may be excluded from CHANNEL CALIBRATION.
- 3. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided at least one other OPERABLE channel in the same trip system is monitoring that parameter.
SURVEILLANCE FREQUENCY TRS 3.1.3.1 Perform CHANNEL CHECK 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> TRS 3.1.3.2 ---------------------- NOTE--- ----------
For Function 1.a, not required to be performed when.
entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering MODE 2.
Perform CHANNEL FUNCTIONAL TEST 184 days TRS 3.1.3.3 Perform CHANNEL FUNCTIONAL TEST 7 days TRS 3.1.3.4 Perform CHANNEL FUNCTIONAL TEST 92 days TRS 3.1.3.5 Perform CHANNEL CALIBRATION 184 days TRS 3.1.3.6 ---------------------- NOTE -------------
Neutron Detectors are excluded.
Perform CHANNEL CALIBRATION 24 months TRS 3.1.3.7 Perform LOGIC SYSTEM FUNCTIONAL TEST 24 months SUSQUEHANNA - UNIT 2 TRM / 3.1-6 EFFECTIVE DATE 03/27/2007
Control Rod Block Instrumentation PPL Rev. 4 3.1.3 TABLE 3.1.3-1 (Page 1 of 2)
CONTROL ROD BLOCK INSTRUMENTATION CONDITIONS APPLICABLE REFERENCED MODES OR OTHER FROM SPECIFIED REQUIRED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS ACTION A.1 REQUIREMENTS VALUE
- 1. APRM
- b. Simulated Thermal 1 3 B TRS 3.1.3.2 0.55 W +
Power - High TRS 3.1.3.6 56.2%()
- 2. Source Range Monitors
(a) When performing Shutdown Margin Demonstration per Technical Specification 3.10.8.
(b) 0.55 (W - AW) + 56.2% when reset for single loop operation per LCO 3.4.1, "Recirculation Loops Operating." For single loop operation, the value of AW = 8.7.
(c) When not automatically bypassed with SRM counts > 100 cps or the IRM channels on range 3 or higher.
(d) When not automatically bypassed with IRM channels on range 8 or higher.
- 0) With any control rod withdrawn from a core cell containing one or more fuel assemblies.
SUSQUEHANNA - UNIT 2 TRM / 3.1-7 EFFECTIVE DATE 04/15/2009
Control Rod Block Instrumentation PPL Rev. 4 3.1.3 TABLE 3.1.3-1 (Page 2 of 2)
CONTROL ROD BLOCK INSTRUMENTATION CONDITIONS APPLICABLE REFERENCED MODES OR OTHER FROM SPECIFIED REQUIRED REQUIRED SURVEILLANCE ALLOWABL FUNCTION CONDITIONS CHANNELS ACTION A.1 REQUIREMENTS VALUE
- d. Downscale 2(e) 3 B TRS 3.1.3.3 _1.8 cpsM TRS 3.1.3.6 TRS 3.1.3.7 5 (i)(0) 2 B TRS 3.1.3.3 > 1.8 cpsM TRS 3.1.3.6 TRS 3.1.3.7
- b. Neutron 2, 56) 6 B TRS 3.1.3.1 <110/125 Flux - High TRS 3.1.3.3 divisions of TRS 3.1.3.5 full scale TRS 3.1.3.7 C. Inop 2, 50) .6 B TRS 3.1.3.3 NA TRS 3.1.3.7
- d. Downscale 2 (g) 5 i) 6 B TRS 3.1.3.1 3/125 TRS 3.1.3.3 divisions of TRS 3.1.3.5 full scale TRS 3.1.3,7
- 5. Reactor Coolant System Recirculation Flow
- a. Upscale 1 3 C TRS 3.1.3.2 _<117/125 TRS 3.1.3.6 divisions of full scale (e) When not automatically bypassed with IRMs on range 3 or higher.
(D With a signal-to-noise ratio >_2, or within the limits of TS Figure 3.3.1.2-1.
(g)
When not automatically bypassed with IRM channels on range 1.
(h)
When more than one control rod is withdrawn. Not applicable to control rods removed per Technical Specification 3.10.5 or 3.10.6.
(i)
Not required when eight or fewer fuel assemblies (adjacent to the SRMs) are in the core.
(J)
With any control rod withdrawn from a core cell containing one or more fuel assemblies.
SUSQUEHANNA - UNIT 2 TRM / 3.1-8 EFFECTIVE DATE 03/27/2007
Core Operating Limits Report (COLR)
PPL Rev. 8 3.2.1 3.2 Core Operating Limits Report (COLR) 3.2.1 Core Operating Limits Report (COLR)
TRO 3.2.1 The Core Operating Limits specified in the attached COLR shall be met.
APPLICABILITY: Specified in the referenced Technical Specifications.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Core Operating Limits not A.1 Perform action(s) Specified in referenced met. described in referenced Technical Technical Specification. Specifications.
TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE FREQUENCY
--- NOTE -------------- N/A No associated Surveillances. Surveillances are implemented in the applicable TechnicalSpecifications.
SUSQUEHANNA - UNIT 2 TRM / 3.2-1 EFFECTIVE DATE 08/31/1998
PPL Rev. 8 PL-NF-09-002 Rev. 0 OQI Page 1 of 53 Susquehanna SES Unit 2 Cycle 15 03 CORE OPERATING LIMITS REPORT Nuclear Fuels Engineering April 2009 PFi, SUSQUEHANNA UNIT 2 TRM/3.2- 2 EFFECTIVE DATE 04/17/2009
PPL Rev. 8 PL-NF-09-002 Rev. 0 Page 2 of 53 CORE OPERATING LIMITS REPORT REVISION DESCRIPTION INDEX Rev. Affected 1 No. jSections Description/Purpose of Revision 0 ALL Issuance of this COLR is in support of Unit 2 Cycle 15 operation.
FORM NFP-QA-008-2, Rev. 1 SUSQUEHANNA UNIT 2 TRM/3.2 EFFECTIVE DATE 04/17/2009
PPL Rev. 8 PL-NF-09-002 Rev. 0 Page 3 of 53 SUSQUEHANNA STEAM ELECTRIC STATION Unit 2 Cycle 15 CORE OPERATING LIMITS REPORT Table of Contents
1.0 INTRODUCTION
..................................................................................................... 4 2:0 D EFIN ITIO N S ........................................................................................................ 5 3.0 SHUTDOWN MARGIN ............................................................................................ 6 4.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) ................... 7 5.0 MINIMUM CRITICAL POWER RATIO (MCPR)..................................................... 9 6.0 LINEAR HEAT GENERATION RATE (LHGR) ........................................................ 24 7.0 ROD BLOCK MONITOR (RBM) SETPOINTS AND OPERABILITY REQUIREMENTS ................................................................................................ 32 8.0 RECIRCULATION LOOPS - SINGLE LOOP OPERATION ..................................... 34 9-0 POWER / FLOW MAP ........................................................................................... 49 10.0 OPRM SETPOINTS ................................................................................................ 51 11.0 R E FE R E N C E S ............................................................................................................ 52 SUSQUEHANNA UNIT 2 TRM/3.2-4 EFFECTIVE DATE 04/17/2009
PPL Rev. 8 PL-NF-09-002 Rev. 0 Page 4 of 53
1.0 INTRODUCTION
This CORE OPERATING LIMITS REPORT for Susquehanna Unit 2 Cycle 15 is prepared in accordance with the requirements of Susquehanna Unit 2, Technical Specification 5.6.5. As required by Technical Specifications 5.6.5, core shutdown margin, the core operating limits, RBM setpoints, and OPRM setpoints presented herein were developed using NRC-approved methods and are established such that all applicable limits of the plant safety analysis are met.
SUSQUEHANNA UNIT 2 TRM/3,2-5 EFFECTIVE DATE 04/17/2009
PPL Rev. 8 PL-NF-09-002 Rev. 0 Page 5 of 53
. 2.0 DEFINITIONS Terms used in this COLR but not defined in Section 1.0 of the Technical Specifications or Section 1.1 of the Technical Requirements Manual are provided below.
2.1 The AVERAGE PLANAR EXPOSURE at a specified height shall be equal to the total energy produced per unit length at the specified height divided by the total initial weight of uranium per unit length at that height.
2.2 The PELLET EXPOSURE shall be equal to the total energy produced per unit length of fuel rod at the specified height divided by the total initial weight of uranium per unit length of that rod at that height.
2.3 FDLRX is the ratio of the maximum LHGR calculated by the core monitoring system for each fuel bundle divided by the LHGR limit for the applicable fuel bundle type.
2.4 LHGRFACf is a multiplier applied to the LHGR limit when operating at less than 108 Mlbm/hr core flow. The LHGRFACf multiplier protects against both fuel centerline melting and cladding strain during anticipated system transients initiated from core flows less than 108 Mlbm/hr.
2.5 LHGRFAC, is a multiplier applied to the LHGR limit when operating at less than 100%
rated power. The LHGRFACP multiplier protects against both fuel centerline melting and cladding strain during anticipated system transients initiated from partial power conditions.
2.6 MFLCPR is the ratio of the applicable MCPR operating limit for the applicable fuel bundle type divided by the MCPR calculated by the core monitoring system for each fuel bundle.
2.7 MAPRAT is the ratio of the maximum APLHGR calculated by the core monitoring system for each fuel bundle divided by the APLGHR limit for the applicable fuel bundle type.
2.8 OPRM is the Oscillation Power Range Monitor. The Oscillation Power Range Monitor (OPRM) will reliably detect and suppress anticipated stability related power oscillations while providing a high degree of confidence that the MCPR safety limit is not violated.
2.9 Np is the OPRM setpoint for the number of consecutive confirmations of oscillation half-cycles that will be considered evidence of a stability related power oscillation.
2.10 Sp is the OPRM trip setpoint for the peak to average OPRM signal.
2.11 Fp is the core flow, in Mlbm / hr, below which the OPRM RPS trip is activated.
SUSQUEHANNA UNIT 2 TRM/3.2- 6 EFFECTIVE DATE 04/17/2009
PPL Rev. 8 PL-NF-09-002 Rev. 0 Page 6 of 53 3.0 SHUTDOWN MARGIN 3.1 Technical Specification Reference Technical Specification 3.1.1 3.2 Description The SHUTDOWN MARGIN shall be equal to or greater than:
a) 0.38% Ak/k with the highest worth rod analytically determined OR b) 0.28% Ak/k with the highest worth rod determined by test Since core reactivity will Vary during the cycle as a function of fuel depletion and poison burnup, Beginning of Cycle (BOC) SHUTDOWN MARGIN (SDM) tests must also account for changes in core reactivity during the cycle. Therefore, the SDM measured at BOC must be equal to or greater than the applicable requirement from either 3.2.a or 3.2.b plus an adder, "R". The adder, "R", is the difference between the calculated value of maximum core reactivity (that is, minimum SDM) during the operating cycle and the calculated BOC core reactivity. If the value of "R" is zero (that is, BOC is the most reactive point in the cycle) no correction to the BOC measured value is required.
The SHUTDOWN MARGIN limits provided In 3.2a and 3.2b are applicable in MODES 1, 2, 3, 4, and 5. This includes core shuffling.
SUSQUEHANNA UNIT 2 TRM/3.2-7 EFFECTIVE DATE 04/17/2009
PPL Rev. 8 PL-NF-09-002 Rev. 0 Page 7 of 53 4.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) 4.1 Technical Specification Reference Technical Specification 3.2.1 4.2 Description The APLHGRs for ATRIUMTM-10 fuel shall not exceed the limit shown in Figure 4.2-1.
The APLHGR limits in Figure 4.2-1 are valid for Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, and Backup Pressure Regulator Operable and Inoperable in Two Loop operation. The APLHGR limits for Single Loop operation are provided in Section 8.0.
SUSQUEHANNA UNIT 2 TRM/3.2-8 EFFECTIVE DATE 04/17/2009
SSES UNIT 2 CYCLE 15 16.0 m
REFERENCEETS32 3.2.1 14.0 ................... ....... R.........
NH
. . ,12.5. 15000,12.5.~~UE .... IN DTRINING MAPRAT:
.0.0 , >. - ____________* _
- _ , , ,' 'o , S
. o. . . o. .. . .. . . . .°. *. . . .° .° . .=. . . .= . . .. . * .. . .. .o . . .- . ... o. . . . ..*.o - , .=-. .--. .*. . - .- --.
E 12.0 4w
. . . .. . ... .. . . . V..... .. . ........
8.0 7-. --- 8.
r-H
- N) -I jo m
-ri 6.0 . .. .................. . . ......:67000, 6.9:
m
--4
, ... . . . . . I N . . .. . . . . ... . .M m
CD 4.0 rQo 0 10000 20000 30000 40000 50000 60000 70000 CD
ý-D Average Planar Exposure (MWD/MTU) (0 X<-
(D* Z AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS C>
AVERAGE PLANAR EXPOSURE TWO LOOP OPERATION ATRIUMT -10 FUEL Cs) rQ FIGURE 4.2-1
PPL Rev. 8 PL-NF-09-002 Rev. 0 Page 9 of 53 5.0 MINIMUM CRITICAL POWER RATIO (MCPR) 5.1 Technical Specification Reference Technical Specification 3.2.2, 3.3.4.1, 3.7.6, and, 3.7.8 5.2 Description The MCPR limit is specified- as a function of core power, core flow, average scram insertion time per Section 5.3 and plant equipment operability status. The MCPR limits for all fuel types (ATRIUM TM-1 0) shall be the greater of the Flow-Dependent or the Power-Dependent MCPR, depending on the applicable equipment operability status.
a) Main Turbine Bypass / EOC-RPT / Backup Pressure Regulator Operable Figure 5.2-1: Flow-Dependent MCPR value determined from BOC to EOC Figure 5.2-2: Power-Dependent MCPR value determined from BOC to EOC b) Main Turbine Bypass Inoperable Figure 5.2-3: Flow-Dependent MCPR value determined from BOC to EOC Figure 5.2-4: Power-Dependent MCPR value determined from BOC to EOC c) EOC-RPT Inoperable Figure 5.2-5: Flow-Dependent MCPR value determined from BOC to EOC Figure 5.2-6: Power-Dependent MCPR value determined from BOC to EOC d) Backup Pressure Regulator Inoperable Figure 5.2-7: Flow-Dependent MCPR value determined from BOC to EOC Figure 5.2-8: Power-Dependent.MCPR value determined from BOC to EOC The MCPR limits in Figures 5.2-1 through 5.2-8 are valid for Two Loop operation.
The MCPR limits for Single Loop operation are provided in Section 8.0.
SUSQUEHANNA UNIT 2 TRM/3.2-10 EFFECTIVE DATE 04/17/2009
PPL Rev. 8 PL-NF-09-002 Rev. 0 Page 10 of 53 5.3 Average Scram Time Fraction If the average measured scram times are greater than the Realistic Scram times listed in Table 5.3-1 then the MCPR operating limits corresponding to the Maximum Allowable Average Scram Insertion Time must be implemented.
Determining MCPR operating limits based on interpolation between scram insertion times is not permitted. The evaluation of scram insertion time data, as it relates to the attached table should be performed per Reactor Engineering procedures.
SUSQUEHANNA UNIT 2 TrRM!3.2-11 EFFECTIVE DATE 04/17/2009
PPL Rev. 8 PL-NF-09-002 Rev. 0 Page 11 of 53 Main Turbine Bypass / EOC-RPT I Backup Pressure Regulator Operable SUSQUEHANNA UNIT 2 TRM/3.2-12 EFFECTIVE DATE 04/17/2009
k /
SSES UNIT 2 CYCLE 15 C=
CA 2.2 I II I LEGEND 2.1 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 2.0 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 1.9 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 E1.8
.-J USED IN DETERMINING MFLCPR I 1.7
- 0. CD (30,1.60) 02 o 1.6 1.5 A B 1.4 rJ m
1.3 ~(108, 1.22)
C>,
1.2 30 40 50 60 70 80 90 100 110 Total Core Flow (MLBIHR) -o CD r; Co 1<
CD MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW N)
MAIN TURBINE BYPASS / EOC-RPT I BACKUP PRESSURE REGULATOR OPERABLE 0 TWO LOOP OPERATION (BOC TO EOC)
C.) N)
FIGURE 5.2-1
C=)
SSES UNIT 2 CYCLE 15 3.6 V)
_-N m E
-C I-CD L co cl) m m
(100, 1.35)
(100,1.32)
CD 20 30 40 50 60 70 80 90 100 Core Power (% RATED) oJ(D IDn (D3 CD W
MCPR OPERATING LIMIT VERSUS CORE POWER -n 6
MAIN TURBINE BYPASS / EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE Co 0
TWO LOOP OPERATION (BOC TO EOC) c:
0o c:
FIGURE 5.2-2
PPL Rev. 8 PL-NF-09-002 Rev. 0 Page 14 of 53 Main Turbine Bypass Inoperable ii' SUSQUEHANNA UNIT 2 TRM/3.2-15 EFFECTIVE DATE 04/17/2009
CY)
SSES UNIT 2 CYCLE 15 2.2 m LEGEND 2.1 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME (30, 2.00) CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 2.0 SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE 1.9 _INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 USED IN DETERMINING MFLCPR
~A 1.7 00 0
o1.6 ~(108, 1.49) 1.5 m
1.4 m
1.3
REFERENCE:
T.S. 3.7.6 and 3.2.2 -
CD
_ _ ~~~ _ ~~I _ _ _ _ _ _
1.2 czý 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR) OD r-(D z-n CD1 0 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS INOPERABLE 0
-+1 0
TWO LOOP OPERATION (BOC TO EOC) C" CD FIGURE 5.2-3
SSES UNIT 2 CYCLE 15 3.6 m (23,3.54)
LEGEND 3.4 . . J
\A((26, 3.26)
I3 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 3.2 INSERTION TIME
-I (23, 3.02) I N)
CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME
.. u I
-(26, 2.86) CURVE C: CORE POWER
- 26% AND CORE FLOW <50 MLBM/HR 2.8 C
-H-
-J 2.6 C,
SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE -u INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 r-0.
2.4 0CL (D co n 2.2 20 (26.01, 2.06) USED IN DETERMINING MFLCPR 2.0
~(40, 1.77)-
m 1.8 m A m 1.6 (80,1.48) (100, 1.48) m 1.4
REFERENCE:
T.S. 3.7.6 and 3.2.2 ____ _
1.2 20 30 40 50 60 70 80 90 100
-0 (D -U Core Power (% RATED) 0) ;0 r-(0 (D z1 MCPR OPERATING LIMIT VERSUS CORE POWER 0)
MAIN TURBINE BYPASS INOPERABLE W N.)
TWO LOOP OPERATION (BOC to EOC) col FIGURE 5.2-4
PPL Rev. 8 PL-NF-09-002 Rev. 0 Page 17 of 53 EOC-RPT Inoperable SUSQUEHANNA UNIT 2 TRMI3.2-18 EFFECTIVE DATE 04/17/2009
7-V/) SSES UNIT 2 CYCLE 15 2.2 m LEGEND 2.1 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM
-I INSERTION TIME 2.0 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 1.9 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 USED IN DETERMINING MFLCPR 6-
-u I-E (D 1.7 0 (30, 1.60)
- 1.6 1.5 m
T1 '-u 1.4 m
REFERENCE:
T.S. 3.3.4.1 and 3.2.2 m 1.3 (108,1.22)-
1.2 30 40 50 60 70 80 90 100 110 N)
Total Core Flow (MLB/HR)
(0 0 -n
-0 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW co 0 EOC-RPT INOPERABLE 0 (0 Ln TWO LOOP OPERATION (BOC TO EOC) W., ,r-FIGURE 5.2-5
9 Sp)
-9 SSES UNIT 2 CYCLE 15 3.6 I I -II I m
LEGEND 3.4 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 3.2 INSERTION TIME (23, 3.09) 3.0 CURVE 8: REALISTIC AVERAGE SCRAM INSERTION TIME (23, 3.02) 22 CURVE C: CORE POWER
- 26% AND CORE FLOW _*ý 50 MLBMJHR 2.8 C (26, 2.86) -1 2.6 SAFETY ANALYSES ASSUME SFTAAYE PER THAT FOUR SR 3.7.6.1 AND 3.7.6.2 VALVES ARE OPERABLE BYPASS NJ Tu
-D 0 USED IN DETERMINING MFLCPR 2.2
- 02. -(26.01, 2.03) 2.0
- 0, 4* 1.72) m 1.8 T'
m
- B m 1.6
_ (80,1.44) (100, 1.44)
REFERENCE:
T.S. 3.3.4.1 and 3.2.2 _ _ _ _
m 1.4 CD 1.2 mD 20 30 40 50 60 70 80 90 100
-0 Core Power (% RATED) (1D z
MCPR OPERATING LIMIT VERSUS CORE POWER 0 m co (D1 6 EOC-RPT INOPERABLE (0 TWO LOOP OPERATION (BOC to EOC) 0 N)
FIGURE 5.2-6
PPL Rev. 8 PL-NF-09-002 Rev. 0 Page 20 of 53 Backup Pressure Regulator Inoperable SUSQUEHANNA UNIT 2 TRM/3.2-21 EFFECTIVE DATE 04/17/2009
(-9 CIO SSES UNIT 2 CYCLE 15
.2.2 I I LEGEND 2.1 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM mQ INSERTION TIME 2.0 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME t
1.9 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 I I USED IN DETERMINING MFLCPR
~1.7
-0 0)
(30, 1.60) co
~1.6 1.5 m
m 1.4 m
m cz) 1.3 ,
IREFERENCE:
T.S. 3.7.8 and 3.2.2
- 1
_ _ __ [ _ _ __ _ _ _0_ _
(108,1.22) 1_22_
1.2 30 40 50 60 70 80 9o 100 110 Total Core Flow (MLB/HR)
Co<
Co Z MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW BACKUP PRESSURE REGULATOR INOPERABLE TWO LOOP OPERATION (BOC TO EOC) CD FIGURE 5.2-7
E 4 (A
SSES UNIT 2 CYCLE 15 3.6 m
LEGEND 3.4 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 3.2 (23, 3.09) INSERTION TIME i CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.0 (26, 2.96)
(23, 3.02) CURVE C: CORE POWER <26% AND CORE FLOW *50 MLBMJHR 2.8 C (26, 2.86)
XA -32.6 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES
.4- (26.01,2.42) ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 -u 03S2.4 F-.
a.
0 ,2.17) USED IN DETERMINING MFLCPR (D 0
L. 2.2 2.0 (80 1.45) m 1.8
-n m 1.6 --
REFERENCE:
T.S. 3.7.8 and 3.2.21-- ,1.5 m 1.4 (100, 1.36)
Nm 1.2 C) 20 30 40 80 90 100 50 60 70 Core Power (% RATED) -D CD z,-n x
- 7
- 0) 0 MCPR OPERATING LIMIT VERSUS CORE POWER 6
BACKUP PRESSURE REGULATOR INOPERABLE 0 lpo (0i TWO LOOP OPERATION (BOC to EOC)
FIGURE 5.2-8
PPL Rev. 8 PL-NF-09-002 Rev. 0 Page 23 of 53 Table 5.3-1 Average Scram Time Fraction Table For Use With Scram Time Dependent MCPR Operating Limits Control Rod Average Scram Time to Position (seconds)
Position 45 0.470 0.520 39 0.630 0.860 25 1.500 1.910 5 2.700 3.440 Average Scram Realistic Maximum Insertion Time Allowable SUSQUEHANNA UNIT 2 TRM/3.2-24 EFFECTIVE DATE 04/17/2009
PPL Rev. 8 PL-NF-09-002 Rev. 0 Page 24 of 53 6.0 LINEAR HEAT GENERATION RATE (LHGR) 6.1 Technical Specification Reference Technical Specification 3.2.3 and 3.7.6 6.2 Description The maximum LHGR for ATRIUMm-10 fuel shall not exceed the LHGR limit determined from Figure 6.2-1. The LHGR limit in Figure 6.2-1 is valid for Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, and Backup Pressure Regulator Operable and Inoperable.
To protect against both fuel centerline melting and cladding strain during anticipated system transients initiated from reduced power and flow conditions, power and flow dependent LHGR limit multipliers are provided. The following figures are applicable to EOC-RPT Operable and Inoperable and Backup Pressure Regulator Operable and Inoperable:
a) Main Turbine Bypass Operable Figure 6.2-2: Flow-Dependent LHGR Limit Multiplier Figure 6.2-3: Power-Dependent LHGR Limit Multiplier b) Main Turbine Bypass Inoperable Figure 6.2-4: Flow-Dependent LHGR Limit Multiplier Figure 6.2-5: Power-Dependent LHGR Limit Multiplier The LGHR limit and LHGR limit multipliers in Figures 6.2-1 through 6.2-5 are valid for both Two Loop and Single Loop operation.
SUSQUEHANNA UNIT 2 - TRM/3.2-25 EFFECTIVE DATE 04/17/2009
1~~
V)
C-CA SSES UNIT 2 CYCLE 15 16.0 C-S 14.0 0.0, 13.4...... 90,go 3.4
REFERENCE:
T.S. 3.2.3
-H 12,0 .......................................
E a,
l BI I i Ii I a a I I I I I I.I. l I I l
- l I I iI la
,2 0 N)
, 10.0 I I allI co
...... IIll S .
I S .......... .
.~i I. I I
I Ii I IIIIII .........
0.
48.0 m
m 6.0 7'44'00, 7.10:
m C=)
CD CDJ 4.0 110 0 10000 20000 30000 40000 50000 60000 70000 80000 Pellet Exposure (MWD/MTU)
LINEAR HEAT GENERATION RATE LIMIT VERSUS PELLET EXPOSURE .0 (cI 60 ATRIUM TM -10 FUEL FIGURE 6.2-1
PPL Rev. 8 PL-NF-09-002 Rev. 0 Page 26 of 53 Main Turbine Bypass Operable SUSQUEHANNA UNIT 2 TRM/3.2-27 EFFECTIVE DATE 04/17/2009
SSES UNIT 2 CYCLE 15
- - - - - - I - - - - . . . . . . . . . I . . . . . . .I - - I
. .. . . . . + .+ . . . . . . * . . . , . . . * . . .. . . .....+ . . . i.... I.-- - - - -
z :' (80,1.00) ,
0.00 . .. . . ...... ..... ... .. ..... ..... ..... ,,,,,,
- ,........ 1 0 .7 0 .. . . . . .. . .... .. .. ... . . . . . . . ... . . . . .. . -- -- -* - . -- - - - - - -- -
(30,0.75) : . . a. .aa " . . . . . . + . . . .. ;.a . . . ..*.a . . ... . . . ..I. . . . . . . . . . . *.
. a. . . . ..*.aaaaaa- . . . " . . . . . . . .
0.80 - -- -.... .....
(D r',. a aa a a . . . a1 . 7...' SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 1
.. 7a ..... .. a.... a-aA......... AREOPERABLE PER SR 3.7.6.1 AND 3..7.6.
- a. . . . a . . . a. . . a. . . . a... . . a . a a l
-n 0.50r- ~ ~ - .a*....... .... ...... ..... a.... ..... .. ... ... ..... ..... ...-..J..... .......... . ......
S.........................................................
REFERENCE:
+ a a ,acr T.S.
Et nrrn 3.2.3.....aaandJ t 3.7 .....
r ma f 0.30 , , ,C 0.40 ..... ..... 'I41,ru r~
c:) (0 <
a a aI a i
- _AI
.............................. TUBN
................. SR3761AN ...
- * ~0,30 , * ..... ATRI'-]1 FUE.
F--+ *30 40 50 60 70 80 90 100 110
~Total Core Flow (MLBthr)
FLOW DEPENDENT LHGR LIMIT MULTIPLIER 5 MAIN TURBINE BYPASS OPERABLE * ,
ATRIUMTM-10 FUEL
- 2 FIGURE 6.2-2
CD1.10 1SSES UNIT 2 CYCLE 15 m* LEGEND ..
, , ,(94.46,1.00) 1.00 .CURVE A: BASE CURVE 1 7 WER 26 !(100, 1.00)
- CURVE B: CORE POWER 26% AND CORE FLOW* 50 MLBM/HR ... --. -.- (100-
.T r .;-*- ... ........ . ............ ... ...... I ... . .
a aSAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES (
CLARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 co a) (26.01, 0.65) a a a a a
REFERENCE:
T.S. 3.2.3 and 3.7.6 Ir I a a , a
- a I a a a a .
a aa a . a a aUSED IN DETERMINING FDLRXj-C-,a . I - 4 a 4 . . . I I ..
(23,0.u48) :: 0- * " ;0 -u" a(26,0.42):
- (23,0.39)
..... .. I............... ............ ............ I............
FIGUR 6NDE.R2NNGFD3 0.30 20 30 40 50 60 70 80 90 100 Core Power (%RATED) ( ;
MAIN TURBINE BYPASS OPERABLE R3 01 ATRIUMM 0 FUEL c F 6-
PPL Rev. 8 PL-NF-09-002 Rev. 0 Page 29 of 53 Main Turbine Bypass Inoperable C'
SUSQUEHANNA UNIT 2 TRM/3.2-30 EFFECTIVE DATE 04/17/2009
Ilk
.SSES UNIT 2 CYCLE 15
- J99,1.00
_ ~~~.
0 ...... *. ........ .. ...... *......* 4 ..... I . ....... .....
4J *., .. .*. 4 . .=. 4 . .=. . .d ..
. . ............. ,.00
.
- 1. (9 0 8, 0.90 -- --.. .................................... ..... ........... ........ ........................ , .
- - -l ------- 6.......
.. . .. .. . . . .. .... . . .. ... . . . .... 1. tNN 0.s .. . .
. . . . . . t . . . . . 1. . . . . * . ... . . . -. - .. - . . . . d. i. l . . . . ..I *. l I i* .. . .
. .... ". ..J. . . . . . iI.. . . . . . . . . . . .
N) m 0.7
. . . . ,1 SAFETY ANALYSES ASSUME , . I THAT TWO OR l I MORE BYPASS
=..,i * , 4 4 VALVES ARE , INOPERABLE
- . PER. SR 3.7.6.1 OR. 3.7.6.2 i o 4 4 . , . 4 , . o 4, 4*
0.50 .. 4 . . . .
. , , , , , , , 4 , , ,
, 4 o 4 o 4 4 4
-A .. . .. . . ,,4 I,4
..... ........... ..... ........... 44.......................... ,, R 3.7.6.2 "4. 0.40 ...... .
0.30 A 30 40 50 60 70 80 90 100 110 C) ~Total Core Flow (MLBIHR) W(
C0 n FLOW DEPENDENT LHGR LIMIT MULTIPLIER cz o MAIN TURBINE BYPASS INOPERABLE a (0 ATRIUMTM-10 FUEL0 FIGURE 6.2-4
~~1.10 1SSES UNIT 2 CYCLE 15
_-.z: LEGEND ..
........ :(94.46, 1.00) 1,00 CURVE A: BASE CURVE z , (100, 1.00)
- CURVE B: CORE POWER 5 26% AND CORE FLOW 5 50 MLBM/HR ... .... -.
\)
0.90 . . . . . . .. . .. . . . . ..................................... ;... . .............. I.............
-4 i 0.
N) 0.80 0 .. . ..... . ....., .......... , . .
7 .. . . . . ..
I°. . . I . . . ..
... . . . . " . . . . . " . . . . . . n N). . . SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES CD
-- ....... i
(~ ~ ~.
5 . . B . . -. -. -. -- - --.(2601
. . . . . 0.5)ARE
.*v .. ... . . .i
- - * .- INOPERABLE
- - ---- - -*... PER SR 3.7.6.1 OR 3.7.6.2 0 0 -i - - - -
0 C)*,
REFERENCE:
.T.S. 3.2.3 and 3.7.6 S...... --- 1... -- USED IN DETERMINING FDLRX
,.. 0 .60...
Fri (26,0.48):
S (23,0.46) .... ' ......... ............... .4....... ..............................
I USED IN DTRINGFDR
- (260.42).
(23,0.39) m 0.30( ,. )'
1 20 30 40 so 60 70 80 90 100 Core Power (% RATED)
S(0.(D Z POWER DEPENDENT L*GR LIMIT MULTIPLIER MAIN TURBINE BYPASS INOPERABLE 0% (
ATRIU '10 FUEL C FIGURE 6.2-5 TED)-5 FIGURE cW r-
PPL Rev. 8 PL-NF-09-002 Rev. 0
!O Page 32 of 53 AND OPERABILITY 7.0 ROD BLOCK MONITOR (RBM) SETPOINTS REQUIREMENTS 7.1 Technical Specification Reference Technical Specification 3.3.2.1 7.2 Description The RBM Allowable Value and Trip Setpoints for; a) Low Power Range Setpoint, b) Intermediate Power Range Setpoint, c) High Power Range Setpoint, e) Low Power Range - Upscale, f) Intermediate Power Range - Upscale, and g) High Power Range - Upscale shall be established as specified in Table 7.2-1. The RBM setpoints are valid for Two Loop and Single Loop Operation, Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, and Backup Pressure Regulator Operable and Inoperable.
The RBM system design objective is to block erroneous control rod withdrawal initiated by the operator before fuel design limits are violated. If the full withdrawal of any control rod would not violate a fuel design limit, then the RBM system is not required to be operable. Table 7.2-2 provides RBM system operability requirements to ensure that fuel design limits are not violated.
4o SUSQUEHANNA UNIT 2 TRM/3.2-33 EFFECTIVE DATE 04/17/2009
PPL Rev. 8 PL-NF-09-002 Rev. 0 Page 33 of 53 Table 7.2-1 RBM Setpoints Allowable Nominal Trip Function Value(') Setpoint Low Power Range Setpoint 28.0 24.9 Intermediate Power Range Setpoint 63.0 61.0 High Power Range Setpoint 83.0 81.0 Low Power Range - Upscale 123.4 123.0 Intermediate Power Range - Upscale 113.6 113.2 High Power Range - Upscale 110.6 110.2 (1) Power setpoint function (Low, Intermediate, and High Power Range Setpoints) determined in percent of rated thermal power. Upscale trip setpoint function (Low, Intermediate, and High Power Range - Upscale) determined in percent of reference level.
Table 7.2-2 RBM System Operability Requirements Thermal Power MCPR (2.3)
(% of Rated) a: 28 and < 90 < 1.80 a90 and < 95 < 1.47
> 95 < 1.52 (2) Applicable to Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, and Backup Pressure Regulator Operable and Inoperable.
(3) Applicable to both Two Loop and Single Loop Operation.
- 0 SUSQUEHANNA UNIT 2 TRM/3.2-34 EFFECTIVE DATE 04/1712009
PPL Rev. 8 PL-NF-09-002 Rev. 0 Page 34 of 53 8.0 RECIRCULATION LOOPS - SINGLE LOOP OPERATION 8.1 Technical Specification Reference Technical Specification 3.2.1, 3.2.2, 3.2.3, 3.3.4.1, 3.4.1, 3.7.6, and 3.7.8 8.2 Description APLHGR The APLHGR limit for ATRIUMTM-10 fuel shall be equal to the APLHGR Limit from Figure 8.2-1.
The APLHGR limits in Figure 8.2-1 are valid for Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, and Backup Pressure Regulator Operable and Inoperable in Single Loop operation.
Minimum Critical Power Ratio Limit The MCPR limit is specified as a function of core power, core flow, and plant equipment operability status. The MCPR limits for all fuel types (ATRIUMTM -1 0) shall be the greater of the Flow-Dependent or the Power-Dependent MCPR, depending on the applicable equipment operability status.
a) Main Turbine Bypass / EOC-RPT / Backup Pressure Regulator Operable Figure 8.2-2: Flow-Dependent MCPR value determined from BOC to EOC Figure 8.2-3: Power-Dependent MCPR value determined from BOC to EOC b) Main Turbine Bypass Inoperable Figure 8.2-4: Flow-Dependent MCPR value determined from BOC to EOC Figure 8.2-5: Power-Dependent MCPR value determined from BOC to EOC c) EOC-RPT Inoperable Figure 8.2-6: Flow-Dependent MCPR value determined from BOC to EOC Figure 8.2-7: Power-Dependent MCPR value determined from BOC to EOC d) Backup Pressure Regulator Inoperable Figure 8.2-8: Flow-Dependent MCPR value determined from BOC to EOC Figure 8.2-9: Power-Dependent MCPR value determined from BOC to EOC SUQEAN NT2 CE0/720 R/.-5EFCIV SUSQUEHANNA UNIT 2 TRM/3.2-35 EFFECTIVE DATE 04/17/2009
PPL Rev. 8 PL-NF-09-002 Rev. 0 Page 35 of 53 The MCPR limits in Figures 8.2-2 through 8.2-9 are valid only for Single Loop operation.
Linear Heat Generation Rate Limit The LHGR limits for Single Loop Operation are defined in Section 6.0.
RBM Setpoints and Operability Requirements The RBM setpoints and operability requirements for Single Loop Operation are defined in Section 7.0.
4,Q SUQEANAUI TM---3,FETIEDT 0/720 SUSQUEHANNA UNIT 2 TRMi3.2-36 EFFECTIVE DATE 04/17/2009
SSES UNIT 2 CYCLE 15
.CD 16.0 rn.
I , , i l l i l t ii! i i 14.0 t i II l l I
t i i it t i ,, I REFERENCE T.S. 3.4.1 and 3.2.1
, i I i i i l l I ,i I , I I , i i i , t l l, , ,i i i
, ,t l i USED INDETERMINING MAPRAT
. .. . . . . . ..... !..I............I
- -: 12.0 E .............. .. ........ .. .... .. .. ... ...... l * * .* ....
-c i t
- l , i I i !i . I Si i I RFRNE.S.3.4.1ad. .21 (D
.0 . . .. .. . .ISDIN DETERM INING APRA li l t I li t , , It i i i li i ,i i ii , , it , ,
I 8.0 m - ....................
.. . ... . 4.
m P--I
- .. %..l..J..t. ,'"...4..A. '. .. ..... ,.... .. . ... 670 0, 5I.6 6.0 m
c>
m 4.0 ci 0.0 10000.0 20000.0 30000.0 40000.0 50000.0 60000.0 70000.0 C)
Average Planar Exposure (MWD/MTU) M) (D r-(0 < k AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS AVERAGE PLANAR EXPOSURE SINGLE LOOP OPERATION o (0o 6~
o'1 0 ATRIUMr-10 FUEL Wj N FIGURE 8.2-1
PPL Rev. 8 PL-NF-09-002 Rev. 0 Page 37 of 53 Main Turbine Bypass / EOC-RPT I Backup Pressure Regulator Operable 0< SUSQUEHANNA UNIT 2 TRM/3.2-38 EFFECTIVE DATE 04/17/2009
CA CA SSES UNIT 2 CYCLE 15 4.6 P1 LEGEND 4.4 2:
4.2 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME
-I 4.0 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.8 3.6 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES
--4 3.2
-o CL 0)
CD 0-
~2.6 2.4 P1 2.2 m
m P1
-1 2.0 P1 1.8 (108, 1.55)
-H 1.6 m T.S. 3.4.1 and 3.2.21...__.. A
REFERENCE:
1.4 I.
-a 30 40 50 60 70 80 90 100 110 N)
Total Core Flow (MLBIHR) DCD
'-0 CD' MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW
-n W0 6 MAIN TURBINE BYPASS / EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE 0p 0,
SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8.2-2
SSES UNIT 2 CYCLE 15 C=1 4.6 . .. .... _ ._ I I I
_LEGEND 4.4 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 4.2 INSERTION TIME 4.0 (23, 3.87) CURVE B: REALISTIC AVERAGE SCRAM TIME 3.8 (23, 3.78) -(26, 3.71) CURVE C: CORE POWER <26% AND CORE FLOW *50 MLBMIHR CI.. 3.6 c -_(26,3.58)
E3.4 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 3.2
-U r'-
3.0 USED IN DETERMINING MFLCPR 0 (D 2.8 (26.01, 2.55)
E 2.6 2.4 (40, 2. 17)-
m 2.2
-I-f m -(60, 1.98)- -(100, 1.98)-
m C~-f 2.0
-H m 1.8 B ci 1.6 "
REFERENCE:
T.S. 3.4.1 and 3.2-2 ri-f 1.4 20 30 40 50 60 70 80 90 100 Core Power (% RATED) CD -u ci -D 0 z MCPR OPERATING LIMIT VERSUS CORE POWER 0) 10 MAIN TURBINE BYPASS / EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE Co co -n SINGLE LOOP OPERATION (BOC to EOC) 0 0x FIGURE 8.2-3
PPL Rev. 8 PL-NF-09-002 Rev. 0 Page 40 of 53 Main Turbine Bypass Inoperable SUSQUEHANNA UNIT 2 TRM/3.2-41 EFFECTIVE DATE 04/17/2009
(A (A
SSES UNIT 2 CYCLE 15 4.6 rn LEGEND 4.4 4.2 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM cz INSERTION TIME
-H 4.0 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.8 3.6 SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS !
3.4 VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2
-- A
- 00 3.2 TU
- K "* 3.0 CL USED IN DETERMINING MFLCPR 0 (D, 0, 2.8 a.. (30, 2.52) a 2.6 A 2.4 m 2.2 m
2.0 m
1.8 -- J
REFERENCE:
T.S.l3.4.1,13.7.6, and .2.2 m
1.6 C) L-_______ _________ I________ _________________ _______________ I_______
1.4 30 40 50 60 70 80 90 100 110 N),
Total Core Flow (MLB/HR)
(D MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS INOPERABLE 0--h SINGLE LOOP OPERATION (BOC to EOC) 0 N)
FIGURE 8.2-4
UC)
SSES UNIT 2 CYCLE 15 4.6 i I LEGEND 4.4 234.43)
X\
I.-'
CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 4.2 i INSERTION TIME (26,4.08) 4.0 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.8 (23, 3. 78)Hj CURVE C: CORE POWER *n26% AND CORE FLOW <50 MLBM/HR 3.6 (26, 3.58)
I.,
-t-t S3.4 _______ L
--A S.. SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS o
C 3.2 VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 3.0 I I-I N) I - - TI-0 USED IN DETERMINING MFLCPR c-
"D
= 2.8
- a. (26.01,2.59)....
L) 2.6 2.4 (40, 2.23) 2.2 (60, 2.05) -(100, 2.05)-
rn Mn 2.0 ... 4.a B
-nl 1.8
-D 1.6 1.4 20 30 40 50 60 70 80 90 100 N.)
C7, Core Power (% RATED) Q)CD Cc <
(D Z MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS INOPERABLE 0 CIDC SINGLE LOOP OPERATION (BOC to EOC) cn 0 W N)
FIGURE 8.2-5
PPL Rev. 8 PL-NF-09-002 Rev. 0 Page 43 of 53 EOC-RPT Inoperable SUSQUEHANNA UNIT 2 TRM/3,2-44 EFFECTIVE DATE 04/17/2009
(J~
SSES UNIT 2 CYCLE 15 4.6 I F I m LEGEND
- 1:
4.4 2:
2:
4.2 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM cz 2:
INSERTION TIME
-I 4.0 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.8 3.6
~SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES S3.4 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 cn3.2 3.0 CL
__USED IN DETERMINING MFLCPR 0,
- 0. 2.8 -o IX (L
2.6 2.4 m 2.2 -(30, 2.02) A TI
-71 B 2.0 m 1.8 *-- "=--- -108, 1.55) -
REFERENCE:
T.S. 3.4.1, 3.3.4.1, and 3.2.2 ............
1.6 m
1.4 CD 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR) -c n)
(0 CD C0 z MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW 0
-h 0 SINGLE LOOP OPERATION (BOC to EOC) Cr (A)
FIGURE 8.2-6
.r 4.4 1 i ~~~I L- %2 - It I
l l I- I I 4.2 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 4.0 -(23, 3.87)-
CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.8 N IN-(23, 3.78)- (26,3.71) 3.6 h- C ý(26, 3.58)
CURVE C: CORE POWER 5 26% AND CORE FLOW 5 50 MLBMIHR 3.4 r - _
m, 3.2 -.... SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES
_ - _ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 -u 3.0
- 00. CD W 2.8 USED IN DETERMINING MFLCPR 0..
(26.01, 2.55)i .... .... co
- 2.6 2.4 =ý(40, 2.17)1 2.2 m "-_._____ (60, 2.00) A B (100, 2.00)- r-u 2.0 1.8 1.6
REFERENCE:
T.S. 3.4.1, 3.3.4.1, and 3.2.2 1.4 cz) 20 30 40 50 60 70 80 90 100 Core Power (% RATED) CO MCPR OPERATING LIMIT VERSUS CORE POWER CD EOC-RPT INOPERABLE 6 z,
0n lp SINGLE LOOP OPERATION (BOC to EOC)' W' FIGURE 8.2-7
PPL Rev. 8 PL-NF-0g-002 Rev. 0 Page 46 of 53 Backup Pressure Regulator Inoperable SUSQUEHANNA UNIT 2 TRM/3.2-47 EFFECTIVE DATE 04/17/2009
V)
SSES UNIT 2 CYCLE 15 4.6 m I I 4.4 .1 4-.-- LEGEND 4.2 4 + 4- CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM c-"
INSERTION TIME 4.0 * + 4-CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.8 4 + 4-3.6 4 -I.
SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES
°wi~._3.4 4 4-4 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 m3,2 N.)
3.0 I 1-USED IN DETERMINING MFLCPR K- (-
- 0. CD 0
W 2.8 2L 2.6 2.4 rn 2.2
- 11 Ra(30,E2.02) A m
2.0
-1 -ý-IEFRENE:
.S.3.41, .7., ad 32.2 1.8 m
1.6 C) 1.4 30 40 50 60 70 80 90 100 110 C:) Total Core Flow (MLB/HR) -U (D r-CD <IL MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW CD BACKUP PRESSURE REGULATOR INOPERABLE 0 c )-
SINGLE LOOP OPERATION (BOC to EOC) Oi C.)
FIGURE 8.2-8
. E SSES UNIT 2 CYCLE 15
- 4 V/)
4.6 I 4 LEGEND 4.4 F 4 N) 4,2 I CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM I
INSERTION TIME 4.0 -(23, 3.87) 1 4 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.81 (23, 3.8 (26, 3.71) ____
CURVE C: CORE POWER *26% AND CORE FLOW : 50 MLBM/HR 3.6 -__C i~ .8
__(26, 3.5i8) 3.4 m
SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 3.2 ... (26.01, 3,04)i ARE OPERABLE PER SR 3.7.6.1 AND 3,7.6.2
-a q A (4,2.73) USED IN DETERMINING MFLCPR (D c:3 "J 2.8 02 L._
O 2.4 C:)
0 2.4 (60, 2.28) (100,2.28)-
B o2.2 2.0 1.8 --
IREFERENCE:
T.S. 3.4.1, 3.7.8, and 3.2.2I 1.6 1.4 20 30 40 50 60 70 80 90 100 Core Power (% RATED) CD CD MCPR OPERATING LIMIT VERSUS CORE POWER 0 "
02 BACKUP PRESSURE REGULATOR INOPERABLE 0 (40 SINGLE LOOP OPERATION (BOC to EOC) C,,
0 FIGURE 8.2-9
PPL Rev. 8 PL-NF-09-002 Rev. 0 Page 49 of 53 9.0 POWER / FLOW MAP 9.1 Technical Specification Reference Technical Specification 3.3.1.1 9.2 Description Monitor reactor conditions to maintain THERMAL POWER I core flow outside of Stability Regions I and II of the Power / Flow map, Figure 9.1.
If the OPRM Instrumentation is OPERABLE per TS 3.3.1.1, Region I of the Power/ Flow map is considered an immediate exit region.
If the OPRM Instrumentation is inoperable per TS 3.3.1.1, Region I of the Power
/ Flow map is considered an immediate scram region.
Region II of the Power / Flow map is considered an immediate exit region regardless of the operability of the OPRM Instrumentation.
SUSQUEHANNA UNIT 2 TRM/3.2-50 EFFECTIVE DATE 04/17/2009
PPL Rev. 8 PL-NF-09-002 Rev. 0 Page 50 of 53 19fl 120 I Pupse ii -
.iA...
4~.~
POWER IFLOW UNIT 120 110- 110 Ijnitial f Date:I STILT REGION '4- APRM Rod Block IFOPIM INOPERABLE.AEAE 4I II Trip Setpoint 100 - SCRAM1AWON-27G-02 100 IF OPRMOPERABLE IMMEDIATE
-EXIT IAW ON-27S-002 r1 rT 1 2-- F S TABILTY REGION IMMEDIATELY EAIT AW ON-27"-OZ 0 L1 -I LIJ__LL 90 90- RESTICTED REGION (As defined in A~ttachment G to 100%
MDAP-QA-0333)r IF ABOVEMELLIA BOUJNDARY, L .L - -I :
IMMEDIAYELY EAITIAWN ON-278-O3.044 4 80 80 1J T -1 T
- 1. 4 4 1- -64Al 4 -1 2 T, j L 12,_: - - L I I LU TT 70 70 rl r -in-,- - r -r: r 1 I 4 44 1. :
IT,, I,-,- - 1111 - r, 1111 I~ r1~ :
L_
~j. ++
L A J-:_ -LAJ-I--L J 4 1 1 14 j 60 A
60 0
CL 60%
4.4..4 Rod Line E 50 50 T* ?J
~1* 4 - 4 4-i F -
]
1 *lFf*
+ -k 4.44- -- 4.-,-'
- 4441,i. -::
4444 T I Friv 1, 4 4 4-4 4. 4 -4 4 I- 1 444 iri i -
rrT4 r"-i.
40 Naturall-Clirculation 40 T1- 4 444 no .. .. r T TI 7-1 rri-
-LIi J_ L Li1 J_ _L L I~ J_- _,L Ll
- I:I .' - ri r -..
- 11-1 L IT I JI -r- r-T T 1-,- r i -i -I- r i -I- r rT 1 -I I- r- r -I -r r -r-
_ LI J.4, L J.J .L]L I J_ _L J - U L I J -1 -t- II i- I- 44 4
.L _L L 1i J t I4 I4I I I I I I4 I4I I
30 Approx I - - I4 I I 30 One Pump L.J -I- L ILJ J-I L I I I L I I i- L L 1j 4 4I 1 I I 1 30% Speed. -1 -_L2 -J _r 4 4 I- L4-1-4 I I I J - -4-- -4p-4--iI -
7 4444I 44 I4 4 1 1 7r ý 20 App- 20 1- 4' 4.4 4 I -444
-- I I-1- 4 4ý1ý .:-q -I- ý1,-1_ 1-4-4.41-- -4I-4 Two Pump I II T 1 30% Speed. - F -- FC i' T I -*-FT Approx 4 4 4. 4 4II I I-F Ti--
4 I. I FIIII -rF, T
- ýT 4 T 71' T - r iri i-Orve Pump I -
10 . . . . . . . . 10 1 pe
.T.4 4 1il 1 rT 1- 1 1- .11 r 7 :1- r T 1r11 - - Fr-1 11
, .1 j ,I 1 .1 j _1_: L A J - Li I J. LL J.J
-FI 4r 7i 1i 44' r'. I- T -i -I - - r 7 - r , - -r - - L-.rJ-,4 - r r -ri "i..1J L L I J L L .1 i-1 L. L L I ýj F I IL J -1 L I J i -. - T -r4 r T.
0 0 10 20 30 40 50 60 70 80 90 100 110 Total Core Flow (Mlbm/hr)
(for SLO <75% Pump Speed Use Form GO-200-009-2)
Figure 9.1 SSES Unit 2 Cycle 15 Power/ Flow Map SUSQUEHANNA UNIT 2 TRM/3.2-51 EFFECTIVE DATE 04/17/2009
PPL Rev. 8 PL-NF-09-002 Rev. 0 Page 51 of 53 10.0 OPRM SETPOINTS 10.1 Technical Specification Reference Technical Specification 3.3.1.1 10.2 Description Setpoints for the OPRM Instrumentation are established that will reliably detect and suppress anticipated stability related power oscillations while providing a high degree of confidence that the MCPR Safety limit is not violated. The setpoints are described in Section 2.0 and are listed below:
Sp = 1.12 Np 16 FP = 60 Mlbm / hr SUSQUEHANNA UNIT 2 TRM/3.2-52 EFFECTIVE DATE 04/17/2009
PPL Rev. 8 PL-NF-09-002 Rev. 0 Page 52 of 53
11.0 REFERENCES
11.1 The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:
- 1. XN-NF-81-58(P)(A), Revision 2 and Supplements 1 and 2, "RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model," Exxon Nuclear Company, March 1984.
- 2. EMF-2361(P)(A), Revision 0, "EXEM BWR-2000 ECCS Evaluation Model,".
Framatome ANP, May 2001.
- 3. EMF-2292(P)(A), Revision 0, "ATRIUMT M-10: Appendix K Spray Heat Transfer Coefficients," Siemens Power Corporation, September 2000.
- 4. XN-NF-84-105(P)(A), Volume I and Volume 1 Supplements I and 2, "XCOBRA-T: A Computer Code for BWR Transient Thermal-Hydraulic Core Analysis," Exxon Nuclear Company, February 1987.
- 5. XN-NF-80-19(P)(A), Volume 1 and Supplements 1 and 2, "Exxon Nuclear Methodology for Boiling Water Reactors: Neutronic Methods for Design and Analysis," Exxon Nuclear Company, March 1983.
.'6. XN-NF-80-19(P)(A), Volumes 2, 2A, 2B, and 2C "Exxon Nuclear Methodology for Boiling Water Reactors: EXEM BWR ECCS Evaluation Model," Exxon Nuclear Company, September 1982.
- 7. XN-NF-80-19(P)(A), Volume 3 Revision 2 "Exxon Nuclear Methodology for Boiling Water Reactors Thermex: Thermal Limits Methodology Summary Description," Exxon Nuclear Company, January 1987.
- 8. XN-NF-80-1 9(P)(A), Volume 4, Revision 1, "Exxon Nuclear Methodology for Boiling Water Reactors: Application of the ENC Methodology to BWR Reloads," Exxon Nuclear Company, June 1986.
- 9. XN-NF-85-67(P)(A), Revision 1, "Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel," Exxon Nuclear Company, Inc.,
September 1986.
- 10. ANF-524(P)(A), Revision 2 and Supplements I and 2, "Advanced Nuclear Fuels Corporation Critical Power Methodology for Boiling Water Reactors,"
November 1990.
- 11. NE-092-001 A, Revision 1, "Licensing Topical Report for Power Uprate With Increased Core Flow," Pennsylvania Power & Light Company, December 1992 and NRC SER (November 30, 1993).
SUSQUEHANNA UNIT 2 TRM/3.2-53 EFFECTIVE DATE 0411712009
PPL Rev. 8 PL-NF-09-002 Rev. 0 Page 53 of 53
- 12. ANF-89-98(PXA) Revision 1 and Supplement 1, "Generic Mechanical Design Criteria for BWR Fuel Designs," Advanced Nuclear Fuels Corporation, May 1995.
- 13. EMF-2209(P)(A), Revision 2, "SPCB Critical Power Correlation," Framatome ANP, September 2003.
- 14. EMF-85-74(P)(A), Revision 0, Supplement 1(P)(A) and Supplement 2(P)(A),
"RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model,"
Siemens Power Corporation, February 1998.
- 15. EMF-2158(P)(A), Revision 0, "Siemens Power Corporation Methodology for Boiling Water Reactors: Evaluation and Validation of CASMO-4/Microburn-B2," Siemens Power Corporation, October 1999.
- 16. EMF-CC-074(P)(A), Volume 4, Revision 0, "BWR Stability Analysis -
Assessment of STAIF with Input from MICROBURN-B2," Siemens Power Corporation, August 2000.
- 17. NEDO-32465-A, "BWROG Reactor Core Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications," August 1996.
- 18. ANF-913(P)(A), Volume 1 Revision 1 and Volume I Supplements 2, 3, and 4, "COTRANSA2: A Computer Program for Boiling Water Reactor Transient Analyses," Advanced Nuclear Fuels Corporation, August 1990.
- 19. ANF-1358(P)(A), Revision 3, "The Loss of Feedwater Heating Transient in Boiling Water Reactors," Framatome ANP, September 2005.
SUSQUEHANNA UNIT 2 TRM/3 .2-54 EFFECTIVE DATE 04/17/2009
OPRM Instrumentation PPL Rev. 3 3.3.9 3.3 Instrumentation 3.3.9 OPRM Instrumentation Configuration TRO 3.3.9 Oscillation Power Range Monitor (OPRM) supporting setpoints and settings shall be within the specified limits.
APPLICABILITY: Thermal POWER Ž23% RTP ACTIONS
NOTE -------------------------------------------------------------
- 1. Separate Condition entry is allowed for each channel CONDITION REQUIRED ACTION COMPLETION TIME A. OPRM Setpoints and A.1 Enter the condition referenced in Immediately Settings not in accordance Table 3.3.9-1 for the parameter with Table 3.3.9-1 B. As required by Required B.1 Declare affected OPRM channel Immediately Action A.1 and referenced inoperable.
in Table 3.3.9.1 C. As required by Required C.1 Restore the OPRM Setpoints and 120 days Action A.1 and referenced Settings to within the specified in Table 3.3.9-1 limits.
OR C.2 Declare affected OPRM channel Immediately inoperable.
D. Alternate method to detect D.1 Initiate monitoring to detect entry Immediately and suppress thermal into Conditions E, F, and/or G.
hydraulic instability oscillations required by LCO 3.3.1.1 Required Action 1.1 (continued)
SUSQUEHANNA - UNIT 2 TRM / 3.3-21 EFFECTIVE DATE 04/15/2009
OPRM Instrumentation PPL Rev. 3 3.3.9 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME E. ------- NOTE -----------
Only applicable as required by Required Action D.1 Total core flow as a E.1 Place reactor mode switch in Immediately function of THERMAL the shutdown position.
POWER within Region I of the Power Flow map as specified in the COLR.
OR Total core flow as a function of THERMAL POWER within Region II of the Power Flow map as specified in the COLR and less than 50% of required LPRM upscale alarms OPERABLE F. - -------- NOTE-----
Only applicable as required by Required Action D.1 and when in Region II of the Power Flow map as specified in the COLR.
Two or more APRM F.1 Place the reactor mode switch Immediately readings oscillating with in the shutdown position.
one or more oscillating
>_10% of RTP peak-to-peak OR (continued)
SUSQUEHANNA - UNIT 2 TRM / 3.3-21 a EFFECTIVE DATE 11/15/2004
OPRM Instrumentation PPL Rev. 3 3.3.9 CONDITION REQUIRED ACTION COMPLETION TIME
+ -I F. (continued)
Two or more LPRM upscale alarms activating and deactivating with a period Ž1 second and *5 seconds.
OR Sustained LPRM 2 oscillations >10 W/cm peak-to-peak with a period
Ž1 second and *<5 seconds.
+
G. NOTE---------
Only applicable as required by Required Action D.1.
Total core flow as a G.1 Initiate action to restore total core Immediately function of THERMAL flow as a function of THERMAL POWER is within Region II POWER outside of Region II.
of the Power Flow map as specified in the COLR.
H. Less than 50% of the H.1 Post sign on the reactor control 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> required LPRM Upscale panel that less than 50% of the Alarms are OPERABLE LPRM Upscale Alarms are I_ OPERABLE.
SUSQUEHANNA - UNIT 2 TRM /3.3-21 b EFFECTIVE DATE 03/27/2007
OPRM Instrumentation PPL Rev. 3 3.3.9 TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE FREQUENCY TRS 3.3.9.1 ------------------- NOTE--------------
Only required to be met when an alternate method to detect and suppress thermal hydraulic instability oscillations is required by LCO 3.3.1.1 Required Action 1.1.
Verify total core flow as a function of THERMAL POWER is outside of Region I and II of the Power Flow map as specified in the COLR.
TRS 3.3.9.2 Perform CHANNEL CALIBRATION on the LPRM 24 months Upscale alarm 24 months TRS 3.3.9.3 Verify OPRM parameter setpoints and settings are within limits SUSQUEHANNA - UNIT 2 TRM / 3.3-21 c EFFECTIVE DATE 03/27/2007
OPRM Instrumentation PPL Rev. 3 3.3.9 Table 3.3.9-1 OPRM SETPOINTS AND SETTINGS CONDITIONS REFERENCE D FROM OPRM REQUIRED PARAMETER DESCRIPTION ACTION A.1 VALUE
- 1. TOL (E) Period Tolerance B Ž0.10 and
< 0.30 sec
- 2. fc Conditioning Filter Cutoff Frequency B 1.5 Hz
- 3. Tmin Oscillation Period Lower Time Limit B _ 1.0 and
- 1.2 sec
- 4. Tmax Oscillation Period Upper Time Limit B 3.5 sec
- 5. LPRMmin Minimum LRPMs/Cell Required for Cell B Ž2 Operability
- 6. S1 Peak Threshold Setpoint/ABA & GRBA C Ž1.10 and
- 1.20
- 7. S2 Valley Threshold Setpoint/ABA & GRBA C _ 0.85 and
_ 0.95
- 8. Smax Amplitude Trip Setpoint/ABA C Ž1.30 and
< 1.50
- 9. DR3 Growth Rate Factor Setpoint/GRBA C > 1.30 and
- 1.60 SUSQUEHANNA - UNIT 2 TRM / 3.3-21d EFFECTIVE DATE 03/27/2007
OPRM Instrumentation PPL Rev. 3 B 3.3.9 B 3.3.9 OPRM Instrumentation BASES TRO The OPRM system configuration governs its operation in accordance with the licensing analysis. Several configuration parameters are intrinsic to the trip function safety setpoint bases or provide settings for defense-in-depth algorithm features that are not assumed in the basis for the protection system safety analysis (Reference 2, Reference 3).
Each of the setting values may be used as the process setpoint or device setting without further adjustment for uncertainties.
Setpoints and Settings Bases TOL(_F) Period Tolerance The specified range of values for the period tolerance has been demonstrated to provide continuous confirmations upon transition from stable reactor operation to a growing reactor instability. A range of values is provided to allow system tuning to avoid spurious alarms on period confirmations. Limiting the setpoint adjustment range provides assurance that the Period Based Detection Algorithm will provide sufficient confirmations for a growing instability.
f Conditioning Filter Cutoff Frequency The specified value for the Conditioning Filter Cutoff Frequency has been demonstrated to provide continuous confirmations upon transition from stable reactor operation to a growing reactor instability. Setting minimizes impact on signal amplitude and provides assurance that the Period Based Detection Algorithm will provide sufficient confirmations for a growing instability.
O Tmin Oscillation Period Lower Time Limit Tmax Oscillation Period Upper Time Limit The Oscillation Period Time Limit parameters establish the range of detectable oscillation periods of OPRM cell signals for signal oscillations associated with reactor core thermal-hydraulic instability.
(continued)
SUSQUEHANNA - UNIT 2 TRM / B 3.3-18 EFFECTIVE DATE 03/27/2007
OPRM Instrumentation PPL Rev. 3 B 3.3.9 B 3.3.9 OPRM Instrumentation BASES TRO LPRMmin (continued)
This value determines the availability and resulting sensitivity of cells in the reactor core in the event of LPRM channel failures. The minimum LPRM per cell parameter is an assumption of the OPRM trip setpoint (Sp) basis calculation.
Amplitude and Growth Rate Based Algorithm Parameters S1 Peak Threshold Setpoint/ABA & GRBA S2 Valley Threshold Setpoint/ABA & GRBA Smax Amplitude Trip Setpoint/ABA DR3 Growth Rate Factor Setpoint/GRBA These parameters calibrate the Amplitude and Growth Rate Based Algorithm, described in References 2 and 3, which provides an OPRM trip output to the Reactor Protection System. The OPRM design and licensing basis takes no credit for the Amplitude and Growth Rate Based Algorithm.
The algorithm is provided as a defense-in-depth feature in the event of unanticipated power oscillations. These Amplitude and Growth Rate Based Algorithm Parameters are considered sufficient to provide backup protection and to avoid spurious trips by maximizing margin to expected operating conditions and transients.
ACTIONS The required actions assure that the system settings that support the Period Based Algorithm setpoint analysis, and those parameters that define the Amplitude and Growth Rate Based Algorithm are returned in a timely manner to the values assumed in the analysis (Reference 2, Reference 3) or that the affected channel is declared inoperable and the applicable Required Action of LCO 3.3:1.1 is then entered, or an alternate method to detect and suppress thermal hydraulic instability oscillations is employed.
(continued)
SUSQUEHANNA - UNIT 2 TRM / B 3.3-19 EFFECTIVE DATE 03/27/2007
OPRM Instrumentation PPL Rev. 3 B 3.3.9 B 3.3.9 OPRM Instrumentation BASES ACTIONS Note 1 has been provided to modify the ACTIONS related to affected OPRM (continued) channels. Technical Specification Section 1.3, Completion Times, specifies that once a Condition has been entered, subsequent divisions, subsystems, components, or variables expressed in the Condition discovered to be inoperable or not within limits will not result in separate entry into the Condition. Technical Specification Section 1.3 also specifies that Required Actions of the Condition continue to apply for each additional failure, with Completion Times based on initial entry into the Condition. However, the Required Actions for affected OPRM channels provide appropriate compensatory measures. As such, a Note has been provided that allows separate Condition entry for each affected OPRM channel.
B.1 Several parameter settings are essential for the proper operation of the OPRM period-based trip algorithm. The permissible values of Period Confirmation Tolerance, Averaging Filter time constant, Conditioning Filter Cutoff Frequency, and minimum operable LPRM per cell parameters are limited by the setpoint basis calculations and system transient response analysis. The Minimum and Maximum Oscillation Period settings limit the algorithm window to the cell signal resonances that can be associated with unstable thermal-hydraulic conditions.
Because the ability of the OPRM channel to perform its safety function is affected by these parameter settings, the affected OPRM channel must be considered inoperable when these conditions are not met.
Operability is evaluated for each inoperable channel and Required Actions taken in accordance with LCO 3.3.1.1.
C.1 The design objective for the Amplitude and Growth Rate Based Algorithms is to provide automatic action to limit the size of these unanticipated oscillations, thereby preventing fuel cladding damage. Several parameter settings define the function of the Amplitude and Growth Rate Based Algorithm. The OPRM design and licensing basis takes no credit for the Amplitude and Growth Rate Based Algorithm, which is provided as a defense-in-depth feature in the event of unanticipated oscillations.
(continued)
SUSQUEHANNA - UNIT 2 TRM / B 3.3-19a EFFECTIVE DATE 03/27/2007
OPRM Instrumentation PPL Rev. 3 B 3.3.9 B 3.3.9 OPRM Instrumentation BASES ACTIONS C.1 (continued)
Because the ability of the OPRM channel to perform its safety function is not affected by these parameter settings, the affected OPRM channel need not be immediately considered inoperable when these conditions are not met.
These parameters are to be maintained for conformance with the licensing requirement of a defense-in-depth feature in addition to the licensed OPRM trip function. This is corrected by returning the parameters to conformance within 120 days of identification.
Since the Amplitude and Growth Rate Based parameters affect only the defense-in-depth response within each channel, failure to maintain the proper parameters in the channel affects only the operability of that channel.
D.1 This Action is to be taken ifthe Period Based Detection Algorithm trip function is not available in accordance with LCO 3.3.1.1, and initiation of an alternate method to Detect and Suppress thermal hydraulic instability oscillations is required by the referenced LCO Required Actions. The applicable Conditions are entered as required.
E.1 As directed from Required Action D.1, this Action provides preemptive protection through Power/Flow Map operating restrictions.
When operating in Region I of the Power / Flow map specified in the COLR, or when operating in Region II of the Power / Flow map specified in the COLR with less than 50% of the required LPRM upscale alarms OPERABLE, the potential for thermal-hydraulic oscillations is greatly increased and sufficient margin may not be available for operator response to suppress potential thermal-hydraulic oscillations. Therefore, the reactor mode switch must be immediately placed in the shutdown position. Action is taken immediately to place the plant in a condition where any potential for thermal-hydraulic instabilities will be terminated.
Identification of which LPRMs are Upscale can be determined by a number of methods in the control room. The most commonly used method is visual and audible observance of the LPRM Upscale Annunciator and Alarm followed with identification of the individual LPRMs feeding the annunciation/
alarm. Identification of individual LPRM Upscale is possible by observance of the various Operator display assemblies and control panel monitors including PICSY.
(continued)
SUSQUEHANNA - UNIT 2 TRM / B 3.3-19b EFFECTIVE DATE 03/27/2007
OPRM Instrumentation PPL Rev. 3 B 3.3.9 B 3.3.9 OPRM Instrumentation BASES ACTIONS F.1 (continued)
As directed from Required Action D.1, this Action provides guidance for Operator action in response to thermal-hydraulic instability oscillations.
When operating in Region II of the Power/Flow map specified in the COLR immediate response is necessary when there are indications that thermal hydraulic oscillations are occurring as defined in the CONDITION.
LPRM upscale alarms are required to detect reactor core thermal-hydraulic instability events. The criteria for determining which LPRM upscale alarms are required is based on assignment of these alarms to designated core zones. These core zones consist of the level A, B, and C alarms in 4 or 5 adjacent LPRM strings. The number and location of LPRM strings in each zone assure that with 50% or more of the associated LPRM upscale alarms OPERABLE sufficient monitoring capability is available to detect core wide and regional oscillations. Operating plant instability data is used to determine the specific LPRM strings assigned to each zone.
Identification of which LPRMs are Upscale can be determined by a number of methods in the control room. The most commonly used method is visual and audible observance of the LPRM Upscale Annunciator and Alarm followed with identification of the individual LPRMs feeding the annunciation/
alarm. Identification of individual LPRM Upscale is possible by observance of the various Operator display assemblies and control panel monitors including PICSY.
G.1 As directed from Required Action D.1, this Action provides guidance for Operator action in response to operation in conditions that may lead to thermal-hydraulic instability oscillations.
When operating in Region II of the Power/Flow map specified in the COLR, the potential for thermal-hydraulic oscillations is increased and sufficient margin may not be available for operator response to suppress potential thermal-hydraulic oscillations. Therefore, action must be initiated immediately to restore operation outside of Regions II of the Power/Flow map specified in the COLR. This can be accomplished by either decreasing THERMAL POWER with control rod insertion or increasing core flow by increasing recirculation pump speed. The starting of a recirculation pump will not be used as a means to exit the excluded Regions because the starting of a recirculation pump with the plant operating above the 70% rod line is prohibited due to potential instability problems.
(continued)
SUSQUEHANNA - UNIT 2 TRM / B 3.3-19c EFFECTIVE DATE 04/17/2009
OPRM Instrumentation PPL Rev. 3 B 3.3.9 B 3.3.9 OPRM Instrumentation BASES ACTIONS H.1 (continued)
The LPRMs provide a capability to monitor power in selected locations of the reactor core. The LPRM Upscale Alarm Instrumentation provides information concerning local power oscillations. Condition F requires a reactor scram when operating in Region II of the Power/Flow map specified in the COLR with indications that thermal hydraulic oscillations are occurring. The number and location of LPRM strings in each zone assures that with 50% or more of the associated LPRM upscale alarms OPERABLE any power oscillations which could occur would be detected and proper actions can be taken.
Identification, of which LPRMs are Upscale can be determined by a number of methods in the control room. The most commonly used method is visual and audible observance of the LPRM Upscale Annunciator and Alarm followed with identification of the individual LPRMs feeding the annunciation/
alarm. Identification of individual LPRM Upscale is possible by observance of the various Operator display assemblies and control panel monitors including PICSY.
A sign is posted in the Control Room to ensure that plant operators are aware of the system condition if a plant transient results in the plant entering into the instability region.
TRS TRS 3.3.9.1 Required only when the OPRM trip function is not available, this TRS ensures the combination of core flow and THERMAL POWER are within required limits to prevent uncontrolled thermal hydraulic oscillations by ensuring the recirculation loops are within the limits established by the Power / Flow map specified in the COLR. At low recirculation flows and high reactor power, the reactor exhibits increased susceptibility to thermal-hydraulic instability. The Power / Flow map specified in the COLR is based on guidance provided in References 7, 8, and 9 which also provided the guidance on how to respond to operation in these conditions. The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Frequency is based on operating experience and the operators inherent knowledge of the current reactor status, including significant changes in THERMAL POWER and core flow to ensure the requirements are constantly met.
TRS 3.3.9.2 This TRS is to be performed at the specified Frequency to ensure that the LPRM Upscale Alarm Instrumentation are maintained OPERABLE.
(continued)
SUSQUEHANNA - UNIT 2 TRM / B 3.3-19d EFFECTIVE DATE 03/27/2007
OPRM Instrumentation PPL Rev. 3 B 3.3.9 B 3.3.9 OPRM Instrumentation BASES TRS TRS 3.3.9.3 (continued)
The parameter setpoint verification surveillance compares the desired settings and setpoints to the values contained in the processor memory.
This surveillance is required to assure that the settings are maintained in accordance with the setpoint analysis. The frequency is based on the OPRM CALIBRATION frequency per SR 3.3.1.1.18.
REFERENCES 1. NEDO-31960-A, BWROG Long Term Solution Licensing Methodology
- 2. NEDO-31960-A, Supp. 1, BWROG Long Term Solution Licensing Methodology
- 3. NEDO-32465-A, BWROG Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology and Reload Applications
- 4. Deleted
- 5. Generic Letter 94-02, Long-Term Solutions and Upgrade Of Interim Operating Recommendations for Thermal-Hydraulic Instabilities in Boiling Water Reactors
- 6. LCO 3.3.1.1, Reactor Protection System (RPS) Instrumentation
- 7. GE Service Information Letter No. 380, "BWR Core Thermal Hydraulic Stability," Revision 1, February 10, 1984
- 8. Letter, L. A. England to M. J. Virgilio, "BWR Owner's Group Guidelines for Stability Interim Corrective Action," June 6, 1994
- 9. EMF-CC-074(P)(A), Volume 4, Revision 0, "BWR Stability Analysis:
Assessment of STAIF with Input from MICROBURN-B2," November 1999
- 10. NEDC-3241OP-A, "Nuclear Measurement Analysis and Control Power Range Neutron Monitor (NUMAC PRNM) Retrofit Plus Option III Stability Trip Function" SUSQUEHANNA - UNIT 2 TRM / B 3.3-19e EFFECTIVE DATE 03/27/2007
Reactor Recirculation Flow and Rod Line Limit PPL Rev. 2 3.4.4 3.4 Reactor Coolant System (RCS) 3.4.4 Reactor Recirculation Flow and Rod Line Limit TRO 3.4.4 Operating loop flow rate shall be < 50% of rated loop flow rate and the reactor shall be operating at a THERMAL POWER/core flow condition below the 70% rod line shown in the Power Flow map specified in the I.
COLR.
APPLICABILITY: MODES 1, 2, 3, and 4 during recirculation pump start.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the TRO A. 1 Restore parameter(s) to Prior to recirculation not met within limits pump start TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE FREQUENCY TRS 3.4.4.1 Verify the operating loop flow rate is ___
50% of rated Once within 15 loop flow rate and that the reactor is operating at a minutes prior to each THERMAL POWER/core flow condition below the recirculation pump 70% rod line shown the Power Flow map specified in start the COLR.
SUSQUEHANNA UNIT 2 TRM / 3.4-12 EFFECTIVE DATE 04/17/2009