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| number = ML15329A166 | | number = ML15329A166 | ||
| issue date = 11/11/2015 | | issue date = 11/11/2015 | ||
| title = | | title = Technical Requirements Manual | ||
| author name = Gerlach R | | author name = Gerlach R | ||
| author affiliation = Susquehanna Nuclear, LLC | | author affiliation = Susquehanna Nuclear, LLC | ||
| addressee name = | | addressee name = | ||
| Line 15: | Line 15: | ||
=Text= | =Text= | ||
{{#Wiki_filter:Nov. 11, 2015 Page 1 of 2 MANIJAL HARD COPY DISTRIBUTION DOCUMENT TRANMSMITTAL 2015-45734 USER INFORMATION: | |||
GERLACH*ROSEY N EMPL#:028401 CA#: 0363 Address: NUCSA2 Phone#: 254-3194 TRANSMITTAL INFORMATION: | |||
TO: GERLACH*ROSEY N 11/11/2015 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 MNAL. 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. | |||
TRMI - TECHNICAL REQUIREMENTS MANUAL UNIT 1 REMOVE MANUAL TABLE OF CONTENTS DATE: 11/03/2015 ADD MANUAL TABLE OF CONTENTS DATE: 11/10/2015 CATEGORY: DOCUMENTS TYPE: TRM1 4oc2 | |||
Nov. 11, 2015 Page 2 of 2 ID: TEXT 3.2.1 REMOVE: REV:15 ADD: REV: 16 CATEGORY: DOCUMENTS TYPE: TEMI ID: TEXT 3.3.7 REMOVE: REV:1 ADD: REV: 2 CATEGORY: DOCUMENTS TYPE: TRMI ID: TEXT B3.3.7 REMOVE: REV:I1 ADD: REV: 2 CATEGORY: DOCUMENTS TYPE: TRMI ID: TEXT LOES REMOVE: REV: 83 ADD: REV: 84 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 MNUALm Manual Name:z TRM1 Manual | |||
==Title:== | |||
TECHNICAL REQUIREMENTS MANUAL UNIT 1 Table Of Contents Issue Date: 1LI/I10/2 015 Procedure Name Rev Issue Date Change ID Change Numiber TEXT LOES 84 11/10 /2 015 | |||
==Title:== | |||
LIST OF EF:FECTIVE SECTIONS TEXT TOC 25 04/28/2015 | |||
==Title:== | |||
TABLE OF CONTENTS TEXT 1.1 1 01/31/2014 | |||
==Title:== | |||
USE AND APPLICATION DEFINITIONS TEXT 2.1 2 04/28/2015 | |||
==Title:== | |||
PLANT PROGRAMS AND SETPOINTS PLANT PROGRAMS TEXT 2.2 10 01/31/2014 | |||
==Title:== | |||
PLANT PROGRAMS AND SETPOINTS INSTRUMENT TRIP SETPOINT TABLE TEXT 3.0 5 03/05 | |||
==11.0 REFERENCES== | ==11.0 REFERENCES== | ||
................ | ................ ................................................................ 61 SUSQUEHANNA UNIT 1 TRM/3.2-4 SUSQEHANA NITTR/3..-4DATE 11/04/2015 EFFECTIVE | ||
................................................................ | |||
Rev. 16 PL-NF-14-0O1 Rev. 2 Page 4 of 62 1.0 iNTRODUCTION This CORE OPERATING LIMITS REPORT for Susquehanna Unit t Cycle 19 is prepared in accordance with the requirements of Susquehanna Unit 1, 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. | |||
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 | SUSQUEHANNA UNIT 1 TRM/3.2-5 UNT I RM/32-5 SUSQEHANA EFFECTIVE DATE 11/04/2015 | ||
The Oscillation Power | |||
2.9 Np is the OPRM setpoint for the number of consecutive confirmations | Rev. 16 PL-NF- 14-001 Rev. 2 Page 5 of 62 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. | ||
2.10 Sp is the OPRM trip setpoint for the peak to average OPRM signal.2.11 Fp is the core flow, in Mlbm I hr, below which the OPRM RPS trip is activated. | 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. | ||
SUSQUEHANNA UNIT | 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. | ||
If the value of "R" is zero (that is, BOG is the most reactivepoint in | 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. | ||
The SHUTDOWN MARGIN limits provided in 3.2a and 3.2b are applicable | 2.4 LHGRFACT is a multiplier applied to the LHGR limit when operating at less than 108 Mlbm/hr core flow. The LHGRFAC1 multiplier protects against both fuel centerline melting and cladding strain during anticipated system transients initiated from core flows less than 108 Mlbmlhr. | ||
SUSQUEHANNA UNIT | 2.5 LHGRFACp is a multiplier applied to the LHGR limit when operating at less than RATED THERMAL POWER. The LHGRFACp multiplier protects against both fuel centerline melting and cladding strain during anticipated system transients initiated from partial power conditions. | ||
The APLHGR | 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. | ||
........4 | 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. | ||
.1 1111I | 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. | ||
* I IIaIaI IaI IaIaI aI IaI Ia | 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. | ||
I I ~ ~ a a a | 2.10 Sp is the OPRM trip setpoint for the peak to average OPRM signal. | ||
-TWO LOOP OPERATION ATRIUMTM-10 | 2.11 Fp is the core flow, in Mlbm I hr, below which the OPRM RPS trip is activated. | ||
The MCPR limits for Single Loop operation are provided in Section 8.0.5.4 Averauqe Scram Time | SUSQUEHANNA UNIT 1 TRM/3.2-6 SLJSUEHNNAUNITI EFFECTIVE TMI32-6 DATE 111/0412015 | ||
Determining MCPR operating limits based on interpolation between scram insertion times is | |||
The evaluation of scram insertion time data, as it relates to | Rev. 16 PL-NF-1 4-001 Rev. 2 Page 6 of 62 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: | ||
SUSQUEHANNA | 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 (BOG) SHUTDOWN MARGIN (SDM) tests must also account for changes in core reactivty during the cycle. Therefore, the SUM 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 8DM) during the operating cycle and the calculated BOG core reactivity. If the value of "R" is zero (that is, BOG is the most reactivepoint in the cycle) no correction to the BOG measured value is required. | ||
, ... .. .. .. .. ... .. ,,,,, .. .. .. ........ ... .. 1 ... .. ..... ... ..... ... ............ .I J ... .... .,J , , = ... ... . | 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. | ||
SSES UNIT 1 CYCLE | SUSQUEHANNA UNIT t TRM/3.2-7 SUSQEHANA UNTI RM/32-7 EFFECTIVE DATE 11104/2015 | ||
Rev. 16 PL-NF-14-O01 Rev. 2 Page?7 of 62 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 ATRIUMT'-10 fuel shall not exceed the limit shown in Figure 4.2-1. | |||
-I"I--- | 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 1 TRM/3.2-8 SUSQEHANA UNT I RM/32-8 EFFECTIVE DATE 11/04/20 15 | |||
9! | |||
02 SSES UNIT I CYCLE 19 C | |||
*16.0 C , 1111 a a I IIl | |||
, I 1, I , 1 111III Ia' II1 1,1 , , I. . III . . la | |||
. . ma | |||
.a rn 1 1 1a I I a aIn 1 I II 4 i i i i i l l i ___ 1 1 1 1 a 11__ | |||
.-- I 1 I I I I I I I I I I I K I I 2 iI * - 1 | |||
* 1I | |||
* l O = . I 2 z | |||
z 1[4.0 I 1 K I 1 II I I I I-- I4 j a I --t-1 . t. I I--1I- . I l | |||
.. l 2lI IlIIl | |||
.. ................... l | |||
. . . . . . . . ' 4. i. . . . | |||
I a al U I I I I C | |||
,IIII2, ,K,2,*,*,t*IaI*I | |||
;! IIlIt I i i l | |||
i a a a a a t II i mi I i I 2 II! i i 1 i i I 12.0 12 5 I00 a . a: .* 5 0 ,1 . . : ..... .. .. I I 1... I .. .2.. . .. | |||
i ~i i ll I i i iai aii i I I I II 1 I Il l i l l l l l | |||
/ 1 /1 1 11 l l1Il l1/ I | |||
. . 1I .1 ._ , , . . I. I .I I ! | |||
II | |||
/ | |||
I I I I II ii iIa i i i i i i 1nIi 1 a1 1 0I I i iI iI 1 iI i iI i 11 liii !1 1*11I11111I1 .1 1111I 1 ,< | |||
i 1 i i i i i i iai a i1I a . . . . . . I I a a a a a*,,. a a .a.a.a.a.a.a.a 0) | |||
* I IIaIaI IaI IaIaI aI al IaI a Ia l l | |||
'-I | |||
., ., ,*! . ! | |||
* I I aI a ,," ,a a l I a I I1la.lal Il laimla.! | |||
a m I I ~ ~ a a a i l l',I al I. II l .a. "* a | |||
** I3l lllam K a a " *a--a-- * *: II ' Il i iii l liIa 1 a i' a l a l a1 1a1 1 a1 a g all 1 1 1 11I a aI aI I II a a n a ai i a a a Ia a I | |||
-I', | |||
"-1 I I I I I! l l Ii.. a ~ | |||
Cn-, aI /a ia li1 aII alal a_ | |||
a a | |||
aal a iI__la1a1a1a1a1a l | |||
i | |||
.*~* _L __*. | |||
I a a | |||
.J aL2 tI 6.0 la la aal la | |||
, , , ,*H , , | |||
aal aal I I , I , I I I.1._ 3 - | |||
.-t | |||
-- I mr 4.0 0 10000 20000 30000 40000 Average Planar Exposure (MWDIMTU) 50000 60000 70000 0 | |||
-* ,r-SI) | |||
AVERAGE AVERAGE PLANAR LINEAREXPOSURE PLANAR HEAT GENERATION RATE LIMIT VERSUS | |||
-TWO LOOP OPERATION Coz ATRIUMTM-10 FUEL C:'(D7 FIGURE 4.2-1 | |||
Rev. 18 PL-NF-14-001 Rev. 2 Page 9 of 62 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 Technical Requirements Manual Reference Technical Requirements Manual 3.3.7 5.3 Description The MOPR 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-1O) shall be the greater of the Flow-Dependent or the Power-Dependent MOPR, depending on the applicable equipment operability status. | |||
a) Main Turbine Bypass I EOO-RPT I Backup Pressure Regulator Operable Figure 5.2-1: Flow-Dependent MCPR value determined from BOO to EDOC Figure 5.2-2: Power-Dependent MOPR value determined from BOO to EGOC b) Main Turbine Bypass lnoperable Figure 6.2-3: Flow-Dependent MCPR value determined from BOO to EDOC Figure 5.2-4: Power-Dependent MOPR value determined from BOO to EGOC c) EOC-RPT Inoperable Figure 5.2-5: Flow-Dependent MCPR value determined from BOO to EOC Figure 5.2-6: Power-Dependent MCPR value determined from BOG to EOO d) Backup Pressure Regulator Inoperable Figure 5.2-7: Flow-Dependent MCPR value determined from BOO to EDOC Figure 5.2-8: Power Dependent MCPR value determined from BOG to EDOC e) One Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) Closed Figure 5.2-0: Flow-Dependent MCPR value determined from BOO to EGG Figure 5.2-1 O:Power-Dependent MCPR value determined from BOO to EDO SUSQUEHANNA UNIT 1 TRM/3.2-10 SUSQEHANA UITTRM3.2I EFFECTIVE 0DATE 11/04/2015 | |||
Rev. 16 PL-NF-1 4-001 Rev. 2 Page 10 of 62 The MCPR limits in Figures 5.2-1 through 5.2-10 are valid for Two Loop operation. | |||
The MCPR limits for Single Loop operation are provided in Section 8.0. | |||
5.4 Averauqe Scram Time Fraction Ifthe 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 UNIT1 TRM/3.2-11 SUSQEHANA UITTRM3.21 EFFECTIVE IDATE 11104/2015 | |||
Rev. i6 PL-NF-14-O01 Rev. 2 Page Iiof 62 Main Turbine Bypass I EOC-RPT I Backup Pressure Regulator Operable SUSQUEHANNA UNIT 1 TRM/3.2-12 NITTR/32I 2DATE 1110412015 EFFECTIVE SUSQEHANA | |||
C' SSES UNIT 1 CYCLE 19 C 2.2 c, | |||
2,1 z | |||
z 2.0 z | |||
1.9 | |||
._E 1.8 1.7 CD k* 0. | |||
CA 0o 1.6 <) | |||
1.5 m 1.4 Ill C) | |||
H 1.3 rn ci 1.2 H 30 40 50 60 70 80 90 100 110 Total Core Flow (MLBIHR) | |||
-o "o n, I Ill (.Q0 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS 1 EOC-RPT I BACKUP PRESSURE REGULATOR OPERABLE TWO LOOP OPERATION (BOC TO EOC) | |||
FIGURE 5.2-1 * -< 0 | |||
. . .. . . . .. .... . .. ..... ...... .... .... .. . ... ... . . . . .. . . . . .. . . .... . .. ........ ,... .. .. .. .. . .. .. ,,,,,.. .. .. . . . . . ... ... .. 1... .. . . . .. . .. . .... ... . .. . . .. . . . .. . I J . .. .... . ,J , , =. .. ... . | |||
cj SSES UNIT 1 CYCLE 19 0 | |||
z z | |||
C z | |||
1J H 0. | |||
0 m | |||
0 20 30 40 50 60 70 80 90 100 Core Power (% RATED) | |||
"13 -O | |||
*, I-MCPR OPERATING LIMIT VERSUS CORE POWER 0" MAIN TURBINE BYPASS I EOC-RPT I BACKUP PRESSURE REGULATOR OPERABLE TWO LOOP OPERATION (BOO TO EOC) (3 " | |||
n Ii --. | |||
FIGURE 5.2-2 | |||
Rev. 16 PL-NF- 14-001 Rev. 2 Page 14 of 62 Main Turbine Bypass Inoperable SUSQUEHANNA UNIT1 TRM/3.2-15 UITTRM3.2l EFFECTIVE SUSQEHANA 5DATE 1 1/04/2015 | |||
0 SSES UNIT 1 CYCLE 19 2.2 03 C | |||
===2.1 LEGENDA=== | |||
MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME | |||
-CURVE CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME z | |||
C 2.0 z | |||
-1 1.9 I INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 1.8 H. '1.7 0J o-01 1,6 1.5 | |||
-I"I 1.4 | |||
--- I EEENCE:_T.S. 3.7.6 and 3.2.2 ___________ __________ | |||
'1.3 m | |||
Hr iii 1.2 30 40 50 60 70 80C I0 100 110 Total Gore Flow (MLB/H-R) | |||
--t "D " | |||
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS INOPERABLE TWO LOOP OPERATION (BOC TO EOC) | |||
FIGURE 5.2-3 ,.-4 < | |||
Q)"* | |||
0 | |||
CI, SSES UNIT 1 CYCLE 19 C 3.6 Ci, C | |||
mR c | |||
Z | |||
-t | |||
.E_ | |||
-H 0 | |||
$o O. | |||
-.4 | |||
-11 "51 m | |||
z3 | |||
-H | |||
<m Fi 20 30 40 50 60 70 80 90 100 Core Power (% RATED) | |||
(73 -U 51 MCPR OPERATING LIMIT VERSUS CORE POWER CD CD- | |||
*MAIN TURBINE BYPASS INOPERABLE Z TWO LOOP OPERATION (BOC to EOC) 77 FIGURE 5.2-4 -- h 0) | |||
Rev. 16 PL-NF-14-001 Rev. 2 Page 17 of 62 EOC-RPT Inoperable SUSQUEHANNA UNIT 1 TRM/3,2-18 SUSQEHANA UITTRM3.2I EFFECTIVE 8DATE 11/04/2015 | |||
CD SSES UNIT 1 CYCLE 19 2.2 03 LEGEND C | |||
m 2.1 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM | |||
= | |||
INSERTION TIME 2.0 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME C | |||
z 1.9 4. SAFETY* ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 | |||
-H E I I IJ 1.8 L. | |||
USED INDETER[MIN1NG MFLCPR I | |||
-4. 1.7 0. | |||
C0 o CD 1.6 -3. | |||
C) 1.5 | |||
-rr 1.4 | |||
==REFERENCE:== | |||
T.S. 3.3.4.1 and 3.2.2 | |||
--Il | |||
<r m 1.3 m | |||
1.2 30 40 50 60 70 80 90 100 110 U Total Core Flow (MLBIHR) | |||
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW EOC-RPT INOPERABLE *QcD TWO LOOP OPERATION (BOC TO EOC) | |||
FIGURE 5.2-5 0"" | |||
ci SSES UNIT 1 CYCLE 19 C | |||
I z | |||
z z | |||
E 0 | |||
(D 0 | |||
C) m n-I 0 | |||
H m | |||
0 50 60 90 H* 20 30 40 Core Power (% RATED) 70 80 100 n-MCPR OPERATING LIMIT VERSUS CORE POWER *(D Z EOC-RPT INOPERABLE TWO LOOP OPERATION (BOC to EQO) O-" -1 FIGURE 5.2-8 (O1*-- | |||
Rev. 16 PL-NF-14-0O1 Rev. 2 Page 20 of 62 Backup Pressure Regulator Inoperable SUSQUEHANNA UNIT 1 TRM/3.2-21 NIT TR/3.-21 DATE 11/04/2015 EFFECTIVE SUSQEHANA | |||
SSES UNIT 1 CYCLE 19 Cn 2.2 LEGEND m | |||
2.1 _____________ -CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME z | |||
C 2.0 ________ -CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME z | |||
1.9 _______ _______ - SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 1.8 I-1.7 r*o 0 A BI | |||
: 10. 0, 1.6 1.5 m | |||
"1 1.4 rri 0 | |||
==IREFERENCE:== | ==IREFERENCE:== | ||
TS. 3.7.8 and 3.2.2~ | |||
1.3 I-~ { 4 1 ~~-f 108, 1.221 m 1.2 30 40 50 60 70 80 90 100 110 Total Core Flow (MVLB/HR) | |||
"-D "- | |||
0 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW BACKUP PRESSURE REGULATOR INOPERABLE "'.) | |||
0 o', TWO LOOP OPERATION (BOC TO EQO) | |||
FIGURE 5.2-7 "*' <c 0 0)" | |||
SSES UNIT I CYCLE 19 60 C | |||
z 0, | |||
.2 | |||
-Il CD C | |||
-3. | |||
0) | |||
'i,, | |||
100,1.35 m | |||
20 30 40 50 60 (% RATED) 70 Core Power 80 90 100 o1 T1 T1 | |||
-L | |||
*Q2 Z~ | |||
MCPR OPERATING LIMIT VERSUS CORE POWER BACKUP PRESSURE REGULATOR INOPERABLE TWO LOOP OPERATION (BOO to EOC) | |||
FIGURE 5.2-8 -,h . 0 0)' ,C | |||
Rev. 16 PL-NE-14-001 Rev. 2 Page 23 of 62 One TSV. or TCV Closed SUSQUEHANNA UNIT 1 TRM/3.2-24 SUSQEHANA UIT ITR IS.-24 EFFECTIVE DATE 11104/2015 | |||
SSES UNIT 1 CYCLE 19 2.2 I LEGEND 2,1 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 2.0 _______ | |||
SSES UNIT | _______ -CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME | ||
-r" 1.9 130, 1.831 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES NJ I ARE OPERABLE PER SR 3.7.5.1 AND 3.7.6.2 U' .4-1.8 | |||
*_ USED IN DETERMINING MFLCPR E2 1.7 C., 1.6 CD 1.5 m | |||
-I-1 1.4 m | |||
==REFERENCE:== | ==REFERENCE:== | ||
T.S. 3.2.2 and TRM 3.3.71 0 | |||
I-4 1.3 | |||
_ _ I _ I_ _ _ _ _ _ _ _ _ _ | |||
1.2 m | |||
30 40 50 60 70 80 90 100 110 Total Core Flow (MLBIHR) 0 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW CD Z N) | |||
ONE TSV OR TCV CLOSED* | |||
TWO LOOP OPERATION (BOC TO EOC) - ,-< | |||
FIGURE 5.2-9 0 | |||
*Operatofl with one TSV or TCV closed is only supported at power levels -<75%rated power. | |||
cj SSES UNIT 1 CYCLE 19 C | |||
m z | |||
C z | |||
S 0.- | |||
-I 0m | |||
*0 CD m | |||
-n m | |||
m C) | |||
-9 20 30 40 50 60 70 80 | |||
*Core Power (% RATED) | |||
MCPR OPERATING LIMIT VERSUS CORE POWER | |||
*ONE TSV OR TCV CLOSED Co I TWO LOOP OPERATION (BOC TO EOC) | |||
FIGURE 5.2-10 | |||
Rev. 16 PL-NF-14-O01 Rev. 2 Page 26 of 62 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 - oo70 3.440 Average Scram Realistic Maximum Insertion Time Allowable SUSQUEHANNA UNIT 1 SUQEAN NTITRM/3.2-27 EFFECTIVE DATE 11/0412015 | |||
: 1. . . .1 I * ... A... . . - -- a L.~cgaa. . .. .. * .1 L. * -- . .*... ..&. aaau I 1S a. . .... aJ L&...aa......a..n. | |||
Rev. 16 PL-NF- 14-001 Rev. 2 Page 27 of 62 6.0 LINEAR HEAT GENERATION RA*TE (LHGR) 6.1 Technical Specification Reference Technical Specification 3.2.3, 3.3.4.1, 3.7.6, and 3.7.8 6.2 Technical Requirements Manual Reference Technical Requirements Manual 3.3.7 6.3 Description The maximum LHGR for ATRIUMTZ-I 0 fuel shall not exceed the LHGR limit determiined 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 in the following figures: | |||
a) Main Turbine Bypass Operable Figure 6.2-2: Flow-Dependent LHGR Uimit Multiplier Figure 6.2-3: Power-Dependent LHGR Limit Multipiier b) Main Turbine Bypass Inoperable Figure 6.2-4: Flow-Dependent LHGR Limit Multiplier Figure 6.2-5: Power-Dependent LHGR Limit Multiplier c) One Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) Closed Figure 6.2-6: Flow-Dependent LHGR Limit Multiplier Figure 6.2-7: Power-Dependent LHGR Limit Multiplier | |||
* The LHGR limits and LHGR limit multipliers in Figures 6.2-2 and 6.2-3 are applicable to EOC-RPT Operable and Inoperable and Backup Pressure Regulator Operable and Inoperable. | |||
* The LGHR limits and LHGR limit multipliers in Figures 6.2-1 through 6.2-7 are valid for both Two Loop and Single Loop operation. | |||
SUSQUEHANNA UNIT 1 TRM/3.2-28 SUSQEHANA EFFECTIVE NITTRI3.-28 DATE 11/04/2015 | |||
C,) | |||
SSES UNIT 1 CYCLE 19 C 16.0 Ii Ii II ii i iI ii ii a ili a iI l Ii i !i Co a a la a a l la l a l 0 a a | |||
a a | |||
a a I I I I El 11111 ' I* I I | |||
C I ! | |||
m lala al ala a alalala alIlal al a la aa a a a a L +/- Z .... L 1 - - .....t....J......- | |||
= - | |||
z '14.0 0.,3.---- f=--I--+ I 900 ,-I--S-I--.. | |||
4 ..J- REFERENCE; T.S 3.2.3 z L- i- - - I I I a a a. a . . a . .a . .a . .a . I & a 1 a a a a I a I a. I. ~ alala IaI-aI I I IaIaI l aI IaI a Ial al l lalal lala C | |||
a[ | |||
a a | |||
a aI la a al ia I Ia a a a ia a I alalalala I a la alaa a a a a | |||
a la a | |||
l n | |||
a .a .a a l la aal . . . . 1I t. t. .1 I .. . .. . .. ..... .. . | |||
4" z La-Ial lal la"1a1 aI 1ajj ~ I i jII !i i l 12.0 al a lala alalal aI a i l a a /aaa a a1 1 a a1 2 a . .a. a. a a a a, a a Iaf a a I a at aIa aI a a.a.a. a. a aIa a ala aIalal lii l al al l al a l 0 | |||
Cu ~II I I II Ia I I I I I Ia 1 1 11 1 11 1 ~I I Ia I aaI a I I a | |||
I l | |||
aaI Ia a. I a a I | |||
al I a I I II a | |||
H C a I l lall l la iala lalala al aialaIa a | |||
'a" 10.0 Cu a- ta l al la a al | |||
-- al-- aI a 4aIaa a- a- a aIaI a aI a--a a- a a-- a- a a aI IIaa a a IIaI I aa aIa a4 - I * - | |||
0 aa a a a a a a a aia a aIa a Iaaatai i iiaa a a ,aaa a a a ,aaa aa a Il | |||
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N) CD a a i a a lalala a la a a a a a al a | |||
la. | |||
a"a a | |||
a a | |||
a ai a a alal a | |||
a a | |||
a a | |||
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ia a a l la la a | |||
a la l | |||
a l | |||
a la a | |||
l i | |||
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Ial a lI ll l a 1 l i l lI l . a. al | |||
.a. l 1 l 7 l iI al~ | |||
l l l l1l l l lal lal l lanl l l i mm I I I II I I I I I I I I I I I I I I | |||
-I- 6.0 rn .a.. .a.. a a j , , I a , , t , ,I a a ,iI, a a I ! | |||
H 11 11 1 1 11 1111 ai lal a all a a al a aI 1 I a I a a a C 4.0 0 10000 20000 30000 40000 50000 60000 70000 80000 H | |||
Pellet Exposure (MWDIMTU) rr T-0 " | |||
-I- UNEAR HEAT GENERATION RATETMLIMIT VERSUS PELLET EXPOSURE ATRIUM -10 FUEL FIGURE 6.2-1 Oco a-0")' 0 | |||
Rev. 16 PL-NF-'I4-001 Rev. 2 Page 29 of 62 Main Turbine Bypass Operable SUSQUEHANNA UNIT 1 TRM/3.2-30 SUSQEHANA NITTR/3.-30 DATE 11/04/2015 EFFECTIVE | |||
C,, | |||
SSES UNIT 1 CYCLE 19 Co 1.10 1.00 z | |||
z 0.90 | |||
-I-- | |||
0.80 | |||
-I ._1 | |||
('3 0.70 a, <D | |||
('3 | |||
._) | |||
0.60 0,50 | |||
-n r-n m 0.40 m | |||
0.30 | |||
-I 30 40 50 60 70 80 90 100 110 m: Total Core Flow (MLB/hr) | |||
: 0) FLOW DEPENDENT LHGR LIMIT MULTIPLIER NJ MAIN TURBINE BYPASS OPERABLE (03 ATRIUMT*-10 FUEL FIGURE 8.2-2 | |||
SSES UNIT 1 CYCLE 19 1.10 L I & "" 'U"' ........... * " ' | |||
* m L 4 4 * | |||
* A A i C | |||
m3 LEGEND | |||
.. " ' ' | |||
* t I " I I i | |||
I ii Fji o T ---- ,-------~.------.I-------, 9 CURVE A: BASE CURVE 1.00 CURVE B: CORE POWER __26% AND CORE FLOW <_.0 MLBM1HR | |||
* I TI rS I 1 31 1 --- I - . ..- j. a .I - * -- - | |||
0.90 I I I I a I i I I | |||
"-I II l l* i I [ aI I li l i k I I | |||
I | |||
.1_J IIS | |||
_ _ J. _ | |||
I | |||
. 1 IJ ; | |||
1 _1 J LI z | |||
I-- | |||
0.80 I I I I I 1 1 5 I I I I I 1 I I I I I | |||
,.I I l ARE OPRAL PE SR ANI37lI... | |||
0.70 . . ..._ | |||
* 1*. 1. * * ._ ._ . . . . . . . . . | |||
C) /II I I 1 I ___ _ _ ___ ___ __ ___ ___ _ | |||
1_- | |||
H 0. | |||
0 0.60 | |||
__..,. . IL.__J._.I * ..- 1 REOERABENCE: TSR 3.2.3,1 3.A4N 3.7.6 an 8 I I | |||
iH i _ 1i_ | |||
; / | |||
0.50 - | |||
03 iL I yr i I" '-- "" ' "- - ! . .. .... .. . . .. .-. -- - '- - -l . - - * - * - ; ' .. . . | |||
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I I... | |||
II -'-I.... | |||
I | |||
.. F - I-' | |||
, ~l, I- | |||
* I I * --I - - - - -l-I | |||
, , I | |||
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3I - * | |||
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i I I I I I I I I I I I | |||
! ,, IJ, J I I I I I r I I I I I I I - 3 I I 0 0.30 I I II I r I I 1 2,0 30 40 50 Core Power 60 (% RATED) 70 80 90 100 POWER DEPENDENT LHGR LIMIT MULTIPLIER MAIN TURBINE BYPASS OPERABLE o ,z AT*iUMTM-10 FUEL FIGURE 6.2-3 | |||
Rev. 16 PL-NF-14-O01 Rev. 2 Page 32 of 62 Main Turbine Bypass Inoperable SUSQUEHANNA UNIT I TRM/3.2-33 SUSQEHANA NITTR/3.-33 DATE 11t10412015 EFFECTIVE | |||
SSES UNIT 1 CYCLE 19 Co 1.10 I | |||
z 1.00 C: | |||
Z 0.90 0. | |||
0.80 | |||
.-I "-J C;, ._ 0.70 C;o 0, | |||
C),. 0) 03 0.60 0o Ct 0.50 m | |||
C) | |||
-H m1 0.40 0 | |||
H-1 m] 0.30 30 40 50 60 Total Core Flow 70 80 90 100 110 (MLB/HR) | |||
"0 "- | |||
nD FLOW DEPENDENT LHGR LIMIT MULTIPLIER C.D z MAIN TURBINE BYPASS INOPERABLE 01 ATRIUMTMea-t FUEL -Il 0O FIGURE 6.2-4 0 | |||
CO, SSES UNIT 1 CYCLE 19 C 1.10 03 m | |||
= | |||
z z | |||
C z | |||
a.. | |||
.5. | |||
.5 0 | |||
--I -I a, | |||
1'3 a, oD 0 | |||
I.. | |||
I | a) 0 0. | ||
m m | |||
0 | |||
.-I m | |||
0 4> 20 30 40 50 60 (% RATED) 70 Core Power 80 90 100 | |||
--I, 01" POWER DEPENDENT LH-GR LIMIT MULTIPLIER MAIN TURBINE BYPASS INOPERABLE Co C? ATRIUMTM.-10 FUEL FIGURE 6.2-,5 0"C* | |||
Rev. 16 PL-NF-14-00l Rev. 2 Page 35 of 62 One TSV or TCV Closed SUSQUEHANNA UNIT 1 TRM/3.2-36 NITTR/3.-36DATE 11/04/2015 EFFECTIVE SUSQEHANA | |||
The RBM system design objective is to block erroneous control rod withdrawal initiated by the operator before fuel design limits are violated. | |||
0 O SSES UNIT 1 CYCLE 19 1.10 C | |||
Table 7.2-2 provides RBM | i"1 1.00 C | ||
SUSQUEHANNA UNIT | z 0.90 a, | ||
-H1 0.80 | |||
-_J 0.70 CD CD | |||
",4 0.60 U.. | |||
0.50 | |||
-T1 | |||
-IT 0.40 m | |||
m 0.30 0 30 40 50 60 Total Core 70Flow (MLB/hr) 80 90 100 110 rl3 FLOW DEPENDENT LHGR LIMIT MULTIPLIER 0 ONE TSV OR TCV CLOSED* 0-" 0 ATRIUMTM-t10 FUEL D' I, -= | |||
FIGURE 6.2-6 | |||
*Operation with one TSV or TCV closed is only supported at power [evels | |||
* 75% rated power. | |||
n ,, n | |||
C', | |||
SSES UNIT 1 CYCLE 19 C | |||
03 m | |||
C z | |||
13 | |||
{.i | |||
--I ,-J | |||
.1_ | |||
C,) | |||
0 cc 0L 0) mT "rn ml 0 | |||
m1 H3 20 30 40 50 (% RATED) | |||
Core Power 60 70 80 rn | |||
-I POWER DEPENDENT LHGR LIMIT MULTIPLIER CD Z ONE TSV OR TCV CLOSED ATRIUMTM-10 FUEL *i-- n FIGURE 6,2-7 c0* | |||
Rev. 16 PL-NF-14-OO1 Rev. 2 Page 38 of 82 7.0 ROD BLOCK MONITOR (RBM SETFOINTS AND OPERABILITY 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, d) Low Power Range - Upscale, e) Intermediate Power Range - Upscale, and I) 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. Ifthe 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. | |||
SUSQUEHANNA UNIT 1 TRM/3.2-39 NITTRIS.-39 DATE 11/04/2015 SUSQEHANA EFFECTIVE | |||
Rev. 16 PL-NF-14-001 Rev. 2 Page 39 of 62 Table 7.2-I RBM Setpoints Allowable Nominal Trip Function Value( 1 ) 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 117.4 117.0 High Power Range - Upscale 107.6 107.2 (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) | |||
> 28 andc<90 < 1.76 | |||
~90 and <95 <1.47 | |||
>_95 < 1.70 (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. | (3 Applicable to both Two Loop and Single Loop Operation. | ||
SUSQUEHANNA UN]T | SUSQUEHANNA UN]T 1 TRMI3.2-40 SUSQEHANA NITTRI3.-40 DATE 11/04/201 5 EFFECTIVE | ||
Rev. 18 PL-NF-1 4- | |||
Minimum Critical Power Ratio Limit-The MCPR limit is specified as a function of core power, core flow, and | Rev. 18 PL-NF-1 4-001 Rev. 2 Page 40 of 62 8.0 REGIRCULATION 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 Technical Req~uirements Manual Reference Technical Requirements Manual 3.3.7 8.3 Description APLHGR The APLHGR limit for ATRlUMTM-I 0 fuel shall be equal to the APLHGR Limit from Figure 8.2-1. | ||
Linear Heat Generation Rate | 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 (ATRIUM TM-10) shall be the greater of the Flow-Dependent or the Power-Dependent MCPR, depending on the applicable equipment operability status. | |||
-L~l l l l l l l lI l l i l | a) Main Turbine Bypass I 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 [noperable 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 IEOC c) EOC-RPT Inoperable Figure 8.2-6: Flow-Dependent MCPR value determined from BOG to EOC Figure 8.2-7: Power-Dependent MCPR value determined from BOC to EOC SUSQUEHANNA UNIT 1 TRMI3.2-41 NIT TRI3.-41EFFECTIVE SUSQEHANA DATE 11/04/2015 | ||
...... ..... ..... .......... | |||
... ..... .......... | Rev. 18 PL-NF-14-OO1 Rev. 2 Page 4l of 62 d) Backup Pressure Regulator Inoperable Figure 8.2-8: Flow-Dependent MCPR value determined from BOO to EGOC Figure 8.2-9: Power-Dependent MCPR value determined from BOO to EDO e) One Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) Closed Figure 8.2-1O:Flow-Dependent MOPR value determined from BOO to EDO Figure 8.2-11 :Power-Dependent MOPR value determined from BOO to EOC The MOPR limits in Figures 8.2-2 through 8.2-1 1 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 andOperabilityRequirem~ents The RBM setpoints and operability requirements for Single Loop Operation are defined in Section 7.0. | ||
......... | SUSQUEHANNA UNIT 1 TRM/3.2-42 NITTRI3.-42 DATE 1110412015 EFFECTIVE SUSQEHANA | ||
....... ...... ... .. i, .... .. ... ... ... .... .. . | |||
Rev. 16 PL-NF.-14-001 Rev. | C 16.0 T T T r T ~ T ~ u 1 1 ~ I r QI I I ' I I l Il l t I I la 1 l l 9 i0 1 ' | ||
I E lI I I Ii l l l llI lI l | |||
: z. 1. .1. II .11 .. II1lIti1 1 I, i I s I i I r I,.i m i . m m m ii.m n l4...4 mm~~u mm.4.*" | |||
I11I 1 I I Ii lIlC Il IlIII1I I1I1 l i l 1 Il l l ~l t l I! ~ l l l O l 1 1 I I I l I I I I Ii ~ll I I l1 1 1I tltitjilt SED IND*ERINIG0 | |||
* -- J- I---. ii! I I-I.-- -- I-- j--i-..J..-,Lf lf...f I I1 1'I II£ I Ii 1 I I | |||
I I I | |||
1 I1 I1 1 1 1 1 I* I I 1 I IIlli I l II l I I I I I 0l3l l l l l l l I 1 1 | |||
= *oo , Ioo I IO ll .I , II I II I, 1I I I I I I I I I I I l l3 l I [ II II IIII l Il l lI I 1 1 1 I mI.._1111l1 I I lllll1 :11! l111 l1!. 1 l11l Iiii II ! II 11 11 lll ll l Il I ll HI I I I I , l l l l I , | |||
I I I I I" I l l II I l l~ll | |||
,I l li | |||
, , I l l l:l I | |||
l1 1 | |||
:l l l 67000,5.6 l | |||
1o 1 11 1111 1 Il liIljlIlIIIIIl l l ll II l l l Illl I l l I I Il l 4.0 L U' i41-- LI4l2 M - -L -- ~L- AJ-J L..L | |||
........... ... -- , I , ,. , I 0.0 l1000. l 2000.0 ll 000. 4000.08000.06000.07000. | |||
-L~l l l l l l l lI l l i l l Averag PlanalEpour MWIMTU)l o = a l l l l l l l l2l l l i t l l A ' I I I I l * . . Ca AVRAEPLNR INA HA GENERATION RAELMITlERSUtll o AERAE PANA EPOSRE..SIGL.LOP.OERAIO ATRIUMTMAOll FUELll l l owlll FIGURE 8.2-1ll l l l l l l lI I | |||
...... , , J2J*** | |||
..... . . . .. . .. .... .....*.. ....................... . ..... ..... ..... .......... ... * . .... .......... ... ... ................. ...... ................... ......... ....... . ..... . .. .. r*, i, . ... .. ... . .. ... .... .. . | |||
Rev. 16 PL-NF.-14-001 Rev. 2 Page 43 of 62 Main Turbine Bypass I EOC-RPT/I Backup Pressure Regulator Operable SUSQUEHANNA UNIT 1 TRM/3.2-44 UITTRM3.2-44 SUSQEHANA EFFECTIVE DATE 11/0412.015 | |||
9 SSES UNIT 1 CYCLE 19 3.6 I I I LEGEND m 3.4 4. a- CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM z INSERTION TIME z 3.2 + I 4-C CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME z | |||
3.0 t 1--i. | |||
m I II II . . I H0 4-. | |||
D.1 o~ | |||
2.8 2.6 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES L | |||
ARE OPERABLE PER SR 3.7.6.t AND 3.7.6.2 I I Ii USED INDETERMINING MFLCPR K | |||
0, 2.4 0 | |||
2.2 2.0 i'1 | |||
-m '.8 rI, | |||
==REFERENCE:== | ==REFERENCE:== | ||
" | " T.S. 3.4.1 and 3.2.21 108, 1.49' 1.6 H | ||
T.S. 3.4.1 and 3.2.21 | -m 0 '1.4 1N1 70 80 90 100 110 0 30 40 50 60 Total Core Flow (MLB/HR) | ||
~ I" | MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW Co MAIN TURBINE BYPASS 1 EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE SINGLE LOOP OPERATION (BOC to EOC) | ||
FIGURE 8.2-2 | |||
9 0 SSES UNIT I CYCLE 19 4.6 o0 4.4 ___ LEGEND 4.2 | |||
________CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM | |||
____INSERTION TIME z 4.0 ____________CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME | |||
~-CURVE C: CORE POWER _<26% AND coRE FLOW | |||
* 50 MLBM/HR 3.6 S 3.4 | |||
--fl!SAFETY ANALYSES ASSUME THAT F~OUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 3.2 Ho 03 3.0 _____USED IN DETERMINING MFLCPR 1. | |||
N) | |||
CD 0 2.8 0); | |||
0) 2.6 2.4 2.2 f 140. 2.08! | |||
,4 0A-B-BT* | |||
4 -.-------- ~ I "t100, ' | |||
2.0 F *, ... .. . .. . | |||
-Iil m | |||
t 1.8 0 REEEC: T.S. 3.4.1 and 3.2.2 "Z 1.6 Hr o 1.4 20 100 mn 2040 50co 60*( RAE70 80 90 "0 " | |||
MCPR OPERATING LIMIT VERSUS CORE POWER CD MAIN TURBINE BYPASS I EOC-RPT I BACKUP PRESSURE REGULATOR OPERABLE SINGLE LOOP OPERATION (BOC to EOC) | |||
FIGURE 8.2-3 °< I | |||
"* O 0)' C | |||
Rev. 16 PL-NF-14-OO1 Rev. 2 Page 46 of 62 Main Turbine Bypass Inoperable SUSQUEHANNA UNIT1 TRM/3.2-47 SUSQEHANA NITTR/3.-47 DATE 1110412015 EFFECTIVE | |||
C' SSES UNIT 1 CYCLE 19 4.2 I I II C- | |||
________ ________ LEGEND 4.0 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 3.8 - INSERTION TIME z | |||
z | |||
________________CURVE B: REALISTIC AVERAGE SCRAM iNSERTiON TIME 3.6 z | |||
3.4 | |||
- SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS - | |||
,4D 3.2 VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 o* 3.0 H0 0 | |||
CD co3 0) 2.4. | |||
2.2 m 2.0 "I1 m . | |||
1.8 -1 | |||
==REFERENCE:== | ==REFERENCE:== | ||
T.S. 3.4.1, 3.7.6,, and22 -- _,118 0 | |||
m 1.6 _ _ _ _ _I _ _ _-_-_-_ | |||
1.4 m | |||
30 40 50 60 Total Core 70 80 90 t00 110 Flow (MLB/HR) 0 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW CD Z | |||
-J. MAIN TURBINE BYPASS INOPERABLE SINGLE LOOP OPERATION (BOC to EOC) | |||
FIGURE 8,2-4 0 o)" | |||
C, SSES UNIT I CYCLE 19 4.2 123,4A41 * =* *l "1 I " m l C-Cin I LEGEND 4.0 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM F INSERTION TIME z 3.8 z CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME | |||
~, 3,61 ____________ 4-Z | |||
-I 3.6 CURVE C: CORE POWER_*26% AND CORE F~LOW _<50 MLBMIHR | |||
.t-l 3.4 I m | |||
.1.a 1I~Z~38 I--.*- 4. I-I E | |||
-I Cu 3.2 ISAFETY VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6,2 ANALYSES ASSUME THAT TWO OR MORE BYPASS w 3.0 USED IN DETERMINING MFLCPR I-0. | |||
1~oi C~) 0 | |||
.41 CD N) | |||
: a. 2.8 CO 0 ______ _ ________ 0) 2.6 2.4 2,2 m | |||
2.0 0r | |||
==REFERENCE:== | ==REFERENCE:== | ||
T.S. ,3.4.1, 3.7.6, and 3.2.2 .. | |||
-I 1.8 20 30 40 6060 Power (%o o70RATED) 80 90 100 50Core "0 "T CD MCPR OPERATING LIMIT VERSUS CORE POWER Com I N) MAIN TURBINE BYPASS INOPERABLE .CD SINGLE LOOP OPERATION (BOC to EOC) | |||
FIGURE 8,2-5 ow. | |||
: h. h< .- | |||
Rev. 16 PL-NF-14-O0l Rev. 2 Page 49 of 62 EOC-RPT Inoperable SUSQUEHANNA UNIT 1 TRM/3.2-50 SUSQEHANA NIT TR/3.-5OEFFECTIVE DATE 11/0412015 | |||
p SSES UNIT 1 CYCLE 19 4.0 LEGEND m 3.8 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM~ | |||
z 3.6 ________________INSERTION TIME z | |||
C CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.4 z | |||
3,2 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVESl E 3.0 - ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 | |||
,U | |||
-1 I-2,8 USED IN DETERMINING MFLCPR 4, | |||
0. | |||
2.6 0 | |||
N, 0I 2.4 0) 2.2 2.0 m 1.8 0 | |||
==REFERENCE:== | ==REFERENCE:== | ||
T.S 3..,.341 and 3.2.2 _ "_-_-_-[_08t" 1.6 1.4 m 30 40 50 60 70 80 9t0 100 110 Total Core Flow (MLB/HR) | |||
*, ,I-0 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW 4* EOC-RPT INOPERABLE -Q* .: | |||
SINGLE LOOP OPERATION (BOC to EOC) | |||
FIGURE 8.2-6 | |||
C* | |||
SSES UNIT 1 CYCLE 19 Cb 0* | |||
z | |||
.-I C.' | |||
CD C., | |||
N) | |||
C,' 0) | |||
'-I"1 | |||
['11 | |||
-IT m | |||
1-1 20 30 40 5060 Power' (% RATED) 70 80Core 80 90 100 m -U -D MCPR OPERATING LIMIT VERSUS CORE POWER Co z EOC-RPT INOPERABLE 0,- | |||
SINGLE LOOP OPERATION (BOC to EOC) ,C FIGURE 8.2-7 ow' 0 | |||
Rev. 15 PL-NF-14-OO1 Rev. 2 Page 52 of 62 Backup Pressure Regulator Inoperable SUSQUEHANNA UNIT 1 TRM/3.2-53 SUSQEHANA NITTRIS.-53 DATE 11/04/2016 EFFECTIVE | |||
C', | |||
SSES UNIT I CYCLE 19 CO 4.0 I I I I m 3.8 | |||
I , " "SAFETY ANALYSES ASSUME THAT FOUR BYPASS | *:MAXIMUM ALLOWABLE AVERAGE SCRAM z | ||
3.6 INSERTION TIME V | |||
I . | |||
C I: REALISTIC AVERAGE SCRAM INSERTION TIME z 3.4 4 4.- | |||
3.2 f , , .. ,I.,,.I,, I , " " | |||
S C | |||
3.0 2,8 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 USED IN DETERMINING MFLCPR 2 | |||
H* C) a. | |||
0 2,6 CD 0~ | |||
C, 2.4 2,2 2.0 r-n | |||
-n' rni 1.8 A- | |||
__---_ _ _ ___ __ B | |||
==REFERENCE:== | ==REFERENCE:== | ||
T.S. 3.4.1, 3.7.8, and 3.2.2[ ____.__ .. _. _ _ .J._108, 1.48 1.6 m | |||
1,4 30 40 50 60 70 80 90 100 110 Total Core Flow (MLBJHR) w r 0* | |||
MOPR OPERATING LIMIT VERSUS TOTAL CORE FLOW BACKUP PRESSURE REGULATOR INOPERABLE 01 SINGLE LOOP OPERATION (BOC to EGOC) | |||
FIGURE 8.2-8 0O" 0 | |||
' I * . ...... .... ....... ".............. ... ...... . ... . .. ... . . . ............ ...... .............. ......................... ................. ................. .. .. * .. . . =. . ... * " *LZ*:* I* *,.,. L*** ............ ..... | |||
CD SSES UNIT 1 CYCLE 19 C " 'I-0* | |||
C 4.4 ---- LEGEND m UM ALLOWABLE AVERAGE SCRAM | |||
-i- 4.2 CURVE A: MAXIM z ____ | |||
___ ___INSERi nION TIME z | |||
C 4.0 CURVE B: REALI* | |||
STIC AVERAGE SCRAM INSERTION TiME 3._____,_.__1CURVE C: CORE POWER < 26% AND CORE FLOW < 60 MLBMIHR I | |||
I I rY ANALYSES ASSUME THAT FOUR BYPASS VALVES l--- | |||
ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 3.0 26.01, 2.90 E | |||
USED IN DETERMINING MFLCPR CD 0.= 2.6 A *1* | |||
0) | |||
O- 60, 2.18 U* 4 4 1100 " | |||
2.2 1 m | |||
2.0 m | |||
1.8 | |||
==REFERENCE:== | ==REFERENCE:== | ||
T.S. 3.4.1, 3.7.8, and 3.2.2J11ii 1.4 | |||
.-I 20 30 40 60 ... ... 60 ... .. .. 70 80 90 100 m uore r'ower rio KAIi )uJ MCPR OPERATING LIMIT VERSUS CORE POWER CD J\) BACKUP PRESSURE REGULATOR INOPERABLE "11 0J SINGLE LOOP OPERATION (BOO to EOC) | |||
FIGURE 8.2-9 (:I' .Q DO O-- | |||
Rev. 16 PL-NF-14-001 Rev. 2 Page 55 of 62 One TSV or TCV CloSed SUSQUEHANNA UNIT 1 TRM/3.2-56 NITTR/3.-56 DATE 11/04/2015 EFFECTIVE SUSQEHANA | |||
Rev. | |||
S SSES UNIT 1 CYCLE 19 3,6 0o C | |||
6.01, 2.40_____ | -i- 3.4 z | ||
_________ | z 3.2 z | ||
- | 3.0 2.8 E | ||
.... .......... | 0. | ||
........ | 2.6 | ||
T .. .. ............. | -*1 2.4 k* *0 0-C, 2.2 2.0 rri "11 1.8 m | ||
.... ...... ... ... .... -:-.! .. ... .= | 1.6 m | ||
Rev. 16 PL-NF-14-OO1 Rev. | 1.4 r'ri 110 30 40 50 60 70 80 90 100 Total Core Flow (MLB/HR) | ||
SUSQUEHANNA | C 0* MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW o ,-n ONE TSV OR TCV CLOSED* | ||
" | cj SINGLE LOOP OPERATION (BOC to EOC) | ||
FIGURE 8.2-10 o~ | |||
1'r%-h* | |||
* Operation with one TSV or TCV closed is only supported at power levels -<75% rated power. | |||
0 oi) | |||
SSES UNIT 1 CYCLE 19 4.6I I I I 4.4 LEGEND m | |||
4.2 ______ CURVE *: MAXIMUM ALLOWABLE AVERAGE SCRAM z INSERTION TIME z 4.0 CURVE E3: REALISTIC AVERAGE SCRAM INSERTION TIME C | |||
z 23 .61 23,3.7 CURVE c.: CORE POWER < 26% AND CORE FLOW < 50 MLBM/HR 3.6 | |||
"* 26, 3.56-" | |||
C......SAFETY ANALYSES ASSUMEtt THAT FOUR BYPASS VALVES t 3.4 26,C 3.33 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 3.2 | |||
-- ___________USED IN DETERMINING MFLCPR 3.0 C,i CJ1 2.8 CD 0) 2.6 | |||
___ _ _ __ _ _ _ __ _ _ _ _6,19 2.4 2.2 _________ 6.01, 2.40_____ _________ - 519 2.0 n | |||
1.8 1.6 m | |||
1.4 20 30 40 50 60 70 80 Core Power (%RATED) | |||
-0 7ci MCPR OPERATING LIMIT VERSUS CORE POWER w"I-ONE TSV OR TCV CLOSED 01 SINGLE LOOP OPERATION (BOC to EOC) | |||
FIGURE 8.2-11 0)' | |||
* i jq L. . ... *....... . . ..... . ... . . .......... . . .. .......... ........ T.. .. ............. .... ...... * * * * * ... ... .... -:-.! | |||
.. ... .= | |||
Rev. 16 PL-NF-14-OO1 Rev. 2 Page 58 of 62 9.0 POWERI/FLOW MAP 9.1 Technical Specification Reference Technical Specification 3.3.1.1 9.2 Description Monitor reactor conditions to maintain THERMAL POWER / core flow outside of Stability Regions I and II of the Power/IFlow map, Figure 9.1. | |||
Ifthe 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 perT"S 3.3.1.1, Region I of the Power! | |||
Flow map is considered an immediate sca region. | |||
Region Ilof the Power!/Flow map is considered an immediate exit region regardless of the operability of the OPRM Instrumentation. | |||
SUSQUEHANNA UNIT1 TRM/3.2-59 SUSQEHANA NITTR/3.-59 DATE 11104/2015 EFFECTIVE | |||
Rev. 16 PL-NF-14-O01 Rev. 2 Page 59 of 62 120 | |||
==Purpose:== | |||
* 120 110* | |||
InitialI/Date: " I 1100 100 9o. 90 80 70 L. | |||
60 0 | |||
fi-50 40 If 30 201 10 | |||
-H-I-I-4--]l- 0*- | |||
0 10 20 30 40 50 50 70 80 90 100 110 Total Core Flow (Mlbmlhr) | |||
(for SLO <75% Pump Speed Use Form GO-100-009-2) | (for SLO <75% Pump Speed Use Form GO-100-009-2) | ||
Figure 9.1 SSES Unit 1 Cycle 19 Power/IFlow Map SUSQUEHANNA UNIT 1 TRM/3.2-60 SUSQEHANA NITTR/3.-60 DATE 11104/2015 EFFECTIVE | |||
Rev. 16 PL-NF-14-001 Rev. 2 Page 60 of 62 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 fisted below: | |||
SF = 1.11 Np = 15 Fp = 60OMlbm /hr SUSQUEHANNA UNIT ! TRM/3.2-61 UNT SUSQEHANA DATE 11/04/20 15 I RM/32-61EFFECTIVE | |||
Rev. 16 PL-NF-14-001 Rev. 2 Page 61 of 82 | |||
==11.0 REFERENCES== | ==11.0 REFERENCES== | ||
11.1 The analytical methods used to determine the core operating limits shall be | 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), | : 1. XN-NF-81-58(P)(A), Revision 2 and Supplements I and 2, "RQDEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model," Exxon Nuclear Company, March 1984. | ||
Revision 2 and Supplements I and 2, "RQDEX2 Fuel | : 2. EMF-2361 (P)(A), Revision 0, "EXEM BWR-2000 ECCS Evaluation Model," | ||
Revision 0, "ATRlUMW-10: | Framatome ANP, May 2001. | ||
Appendix K Spray Heat | : 3. EMF-2292(P)(A), Revision 0, "ATRlUMW-10: Appendix K Spray Heat Transfer Coefficients," Siemens Power Corporation, September 2000. | ||
Siemens Power Corporation, September 2000.4. XN-NF-84-105(P)(A), | : 4. XN-NF-84-105(P)(A), Volume 1 and Volume I Supplements 1 and 2, lJXCOBRA-T: A Computer Code for BWR Transient Thermal-Hydraulic Core Analysis," Exxon Nuclear Company, February 1987. | ||
Volume 1 and Volume I Supplements 1 and 2,lJXCOBRA-T: | : 5. XN-NF-80-19(P)(A), Volume 1 and Supplements I and 2, "Exxon Nuclear Methodology for Boiling Water Reactors: Neutronic Methods for Design and Analysis," Exxon Nuclear Company, March 1983. | ||
A Computer Code for BWR Transient Thermal-Hydraulic | : 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, t' Exxon Nuclear Company, September 1982. | ||
Exxon Nuclear Company, February 1987.5. XN-NF-80-19(P)(A), | : 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. | ||
Volume 1 and Supplements I and 2, "Exxon | : 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. | ||
Neutronic Methods for Design | : 9. XN-NF-85-67(P)(A), Revision 1, "Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel," Exxon Nuclear Company, Inc., | ||
Exxon Nuclear Company, March 1983.6. XN-NF-80-19(P)(A), | September 1986. | ||
Volumes 2, 2A, 2B, and 2C "Exxon Nuclear Methodology for Boiling Water Reactors: | : 10. ANF-524(P)(A), Revision 2 and Supplements 1 and 2, "Advanced Nuclear Fuels Corporation Critical Power Methodology for Boiling Water Reactors1 " | ||
EXEM BWR ECCS Evaluation Model,t' | November 1990. | ||
Volume 3 Revision 2 "Exxon Nuclear Methodology | : 11. NE-092-001A, Revision 1, "Licensing Topical Report for Power Uprate With increased Core Flow," Pennsylvania Power & Light Company, December 1992 and NRC SER (November 30, 1993). | ||
Thermal Limits Methodology | : 12. ANF-89-98(P)(A) Revision 1 and Supplement 1, "Generic Mechanical Design Criteria for BWR Fuel Designs," Advanced Nuclear Fuels Corporation, May 1995. | ||
Exxon Nuclear Company, January 1987.8. XN-NF-80-1 9(P)(A), | SUSQUEHANNA UNiT1 TRM/3.2-62 EFFECTIVE DATE 11/04/2015 | ||
Volume 4, Revision 1, "Exxon Nuclear Methodology | |||
Application of the ENC Methodology to | Rev. 16 PL-NF-14-001 Rev. 2 Page 62 of 62 | ||
Exxon Nuclear Company, June 1986.9. XN-NF-85-67(P)(A), | : 13. EMF-22O9(P)(A), Revision 3, "SPCB Critical Power Correlation," AREVA NP, September 2009. | ||
Revision 1, "Generic Mechanical Design for | : 14. EMF-85-74(P)(A), Revision 0, Supplement 1(P)(A) and Supplement 2(P)(A), | ||
Revision 2 and Supplements 1 and 2, "Advanced | "RQDEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model," | ||
Revision 1 and Supplement 1, "Generic Mechanical | Siemens Power Corporation, February 1998. | ||
Advanced Nuclear Fuels Corporation, | : 15. EMF-2168(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. | ||
Revision 3, "SPCB Critical Power Correlation," | : 16. EMF-CC-074(P)(A), Volume 4, Revision 0, "BWR Stability Analysis - | ||
AREVA NP,September 2009.14. EMF-85-74(P)(A), | Assessment of STAiF with Input from MICROBURN-B2," Siemens Power Corporation, August 2000. | ||
Revision 0, Supplement 1(P)(A) and Supplement 2(P)(A),"RQDEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model,"Siemens Power Corporation, February 1998.15. EMF-2168(P)(A), | : 17. NEDO-32465-A, "BWROG Reactor Core Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications," August 1996. | ||
Revision 0, "Siemens Power Corporation Methodology | : 18. ANF-913(P)(A), Volume t Revision I and Volume I Supplements 2, 3, and 4, "COTRANSA2: A Computer Program for Boiling Water Reactor Transient Analyses," Advanced Nuclear Fuels Corporation, August 1990. | ||
Evaluation and Validation of CASMO-4/Microburn-B2," Siemens Power Corporation, October 1999.16. EMF-CC-074(P)(A), | : 19. ANF-1 358(P)(A), Revision 3, "The Loss of Feedwater Heating Transient in Boiling Water Reactors," Framatome ANP, September 2005. | ||
Volume 4, Revision 0, "BWR Stability Analysis | SUSQUEHANNA UNIT1 TRM/3.2-63 SUSQEHANA EFFECTIVE NITTR/3.-63 DATE 11/04/2015 | ||
Siemens | Main Turbine Overspeed Protection System Rev. 2 3.3.7 3.3 Instrumentation 3.3.7 Main Turbine Overspeed Protection System TRO 3.3.7 One Main Turbine Overspeed Protection System shall be OPERABLE. | ||
APPLICABILITY: MODES I and 2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Two of eight stop valves A.1.1 Close one of the inoperable 72 hours and control valves valves. | |||
Volume t Revision I and Volume I Supplements 2, 3, and 4,"COTRANSA2: | inoperable. | ||
A Computer Program for Boiling Water Reactor Transient Analyses," | AND A.1 .2 Limit THERMAL POWER 12 hours following | ||
Advanced Nuclear Fuels Corporation, August 1990.19. ANF-1 358(P)(A), | < 75% RTP. closure of the inoperable valve AND A.1.3 Apply the following limits for a 12 hours following closed Turbine Stop Valve or closure of the Turbine Control Valve as inoperable valve specified in the COLR: | ||
Revision 3, "The Loss of Feedwater Heating Transient | : a. LCO 3.2.2, 'MINIMUM CRITICAL POWER RATIO (MCPR)," | ||
Framatome ANP, September 2005.SUSQUEHANNA | : b. LCO 3.2.3, 'LINEAR HEAT GENERATION RATE (LHGR)." | ||
APPLICABILITY: | OR A.2 Isolate main turbine from the 72 hours steam supply. | ||
MODES I and | (continued) | ||
SUSQUEHANNA-UNIT1 TRM / 3.3-17 SUSQEHANA-UITITRM 3.-17EFFECTIVE DATE 11/04/2015 | |||
< 75% RTP. closure of | |||
SUSQUEHANNA-UNIT1 TRM / 3.3- | Main Turbine Overspeed Protection System Rev. 2 3.3.7 ACTIONS (continued) | ||
CONDITION REQUIRED ACTION COMPLETION | CONDITION REQUIRED ACTION COMPLETION TIME B. Two of twelve intercept B.1 Close either the intercept 72 hours valves and intermediate valve or the intermediate stop stop valves inoperable, valve within one of the affected combined intermediate valves. | ||
-UNI I RM | OR 8.2 Isolate main turbine from the 72 hours steam supply. | ||
------------- | C. Turbine Overspeed C.1 Isolate main turbine from the 6 hours Protection System steam supply. | ||
~NOTE---- | inoperable for reasons other than Condition A or B. | ||
--------When a channel is placed in an inoperable status solely for performance of | SUSQUEHANNA-UNIT1 TRM / 3.3-17a SUSQEHANA | ||
SURVEILLANCE FREQUENCY | -UNI I RM DATE 11/04/2015 I3.317aEFFECTIVE | ||
--NOTE--..........----...... | |||
The provisions of TRS 3.0.4 are not applicable TRS 3.3.7.1 Cycle each high pressure turbine control valve from the 92 | Main Turbine Overspeed Protection System Rev. 2 3.3.7 TECHNICAL REQUIREMENT SURVEILLANCE | ||
The provisions of TRS 3.0.4 are not applicable TRS 3.3.7.2 Cycle each low pressure turbine combined intermediate 92 | ------------- ~NOTE---- -------- | ||
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 up to 6 hours provided the redundant overspeed trip device is OPERABLE. | |||
SURVEILLANCE FREQUENCY | |||
-- NOTE--..........----...... | |||
The provisions of TRS 3.0.4 are not applicable TRS 3.3.7.1 Cycle each high pressure turbine control valve from the 92 days running position and observe valve closure. | |||
-- -- NOTE--............................... | |||
The provisions of TRS 3.0.4 are not applicable TRS 3.3.7.2 Cycle each low pressure turbine combined intermediate 92 days valve from the running position and observe valve closure. | |||
NOTE---------------------..... | NOTE---------------------..... | ||
The provisions of TRS 3.0.4 are not applicable TRS 3.3.7.3 Cycle each high pressure turbine stop valves from the 92 | The provisions of TRS 3.0.4 are not applicable TRS 3.3.7.3 Cycle each high pressure turbine stop valves from the 92 days running position and observe valve closure. | ||
TRS 3.3.7.5 Disassemble one of each type valve identified in 40 months on | TRS 3.3.7.4 Perform a CHANNEL CALIBRATION of main turbine 24 months overspeed protection instrumentation. | ||
SUSQUEHANNA-UNIT1 TRM / 3.3- | TRS 3.3.7.5 Disassemble one of each type valve identified in 40 months on a TRS 3.3.7.1, TRS 3.3.7.2, and TRS 3.3.7.3, perform a STAGGERED TEST visual and surface inspection of valve seats, disks and BASIS stems and verify no unacceptable flaws or corrosion. | ||
Either device, when initiated, will close the main stop valves, | SUSQUEHANNA-UNIT1 TRM / 3.3-18 SUSQEHANA UNT I RM3.-18EFFECTIVE DATE 10/31/2007 | ||
Main Turbine Overspeed Protection System (MTOPS) OPERABILITY is | |||
Note that for this statement to | Main Turbine Overspeed Protection System Rev. 2 B 3.3.7 B 3.3.7 Main Turbine Overspeed Protection System BASES TRO The Main Turbine Overspeed Protection System is designed to protect the main turbine from excessive overspeed by initiating a turbine trip by fast closure of the turbine control valves and closure of the intercept valves to essentially secure all steam flow to the turbine (Ref. 1). | ||
Failure of only one valve in a | To protect the turbine generator from overspeed conditions, two trip devices are provided. Either device, when initiated, will close the main stop valves, control valves, and combined intermediate valves thus isolating the turbine (Ref. 2). | ||
These two trip devices are as follows: | |||
SUSQUEHANNA | *A mechanical overspeed trip which is initiated ifthe turbine speed reaches approximately 10% above rated speed, and o An electrical overspeed trip which serves as a backup to the mechanical trip and is initiated at approximately 12% above rated speed. | ||
-UNIT | OPERABILITY of at least I of the 2 overspeed protection systems is required for the Turbine Overspeed Protection System to be considered OPERABLE. | ||
-UNI I TM / | Main Turbine Overspeed Protection System (MTOPS) OPERABILITY is also based upon the ability of the valves that control steam flow to the turbine to close following the receipt of a closure signal. The 4 stop valves, 4 control valves, 6 intermediate stop valves, and 6 intercept valves make up a system of 20 valves. A single failure to any one of the above system of 20 valves will not prevent a turbine trip (Ref. 2). Hence, if 19 of the 20 noted valves are OPERABLE, the MTOPS is OPERABLE. Note that for this statement to be true, the intermediate stop valves and intercept valves are considered separate valves. Overspeed protection is only disabled on a CIV failure if both valves within a CIV are inoperable. Failure of only one valve in a CIV does not prevent an overspeed trip, and does not affect operability. Actions to close one inoperable valve if two valves are inoperable maintain the unit within the analysis in Ref. 2. However, redundancy is reduced and repairs should be completed in accordance with the corrective action program. | ||
ACTIONS The Actions are defined to ensure proper corrective measures are taken | Excessive turbine overspeed could generate potentially damaging missiles that could present a personnel and equipment hazard. MTOPS is not necessary to provide adequate protection of the public health and safety and is not required to obviate the possibility of an abnormal situation or event giving rise to an immediate threat to the public health and safety. | ||
A.1.l, A.1.2, A.1.3 and A. | (continued) | ||
The 72-hour Completion Time provides a reasonable time | SUSQUEHANNA - UNIT 1 TRM / B 3.3-14 SUSQEHANA | ||
The required action | -UNI I TM | ||
If the MCPR and LHGR limits are not | /BDATE 3.-14EFFECTIVE 06/25/2002 | ||
This time is provided to stabilize operation with a closed Turbine Stop | |||
The 72-hour Completion Time provides | Main Turbine Overspeed Protection System Rev. 2 B 3.3.7 B 3.3.7 Main Turbine Overspeed Protection System BASES (continued) | ||
SUSQUEHANNA-UNIT1 TRM / B 3.3- | ACTIONS The Actions are defined to ensure proper corrective measures are taken in response to the inoperable components. | ||
If the MTOPS is inoperable for reasons other than conditions A or B, | A.1.l, A.1.2, A.1.3 and A.2 If two of eight stop valves and control valves are inoperable, action must be taken to restore at least one of the valves to OPERABLE status in 72 hours. | ||
The TRSs are modified by a Note to indicate that when a channel is placed | This action ensures steam isolation to the turbine in the event of an overspeed condition, and maintains the unit within the bounds of the FSAR analysis. The 72-hour Completion Time provides a reasonable time to troubleshoot the problem, make repairs, and reduce power in an orderly manner if required without challenging plant systems. The required action if the problem is not resolved is to close one of the inoperable valves, or to isolate the main turbine from the steam supply. If one of the inoperable valves is closed, then limit thermal power to less than or equal to 75% of rated power, and apply Minimum Critical Power Ratio (MCPR) and Linear Heat Generation Rate (LHGR) limits as specified in the COLR within 12 hours. Restricting thermal power to less than or equal to 75% of rated power eliminates possible shock loads to the turbine blades that could occur from a non-uniform circumferential steam flow distribution entering the HP turbine for this configuration. If the MCPR and LHGR limits are not in compliance with the applicable requirements at the end of this period, the ACTIONS required by the applicable specifications must be implemented. | ||
This time is provided to stabilize operation with a closed Turbine Stop Valve or Turbine Control Valve. | |||
The 6 hour testing allowance | B.1 and B.2 If two of twelve intercept valves and intermediate stop valves are inoperable, action must be taken to restore at least one of these valves to OPERABLE status in 72 hours. This action ensures steam isolation to the turbine in the event of an overspeed condition. The 72-hour Completion Time provides a reasonable time to troubleshoot the problem, make repairs, and reduce power in an orderly manner ifrequired without challenging plant systems. | ||
TRS 3.3.7.1, TRS 3.3.7.2, and TRS 3.3.7. | The required action ifthe problem is not resolved is to close either the intercept valve or the intermediate stop valve within one of the affected combined intermediate valves, or to isolate the main turbine from the steam supply. | ||
and four high | (continued) | ||
The 92 | SUSQUEHANNA-UNIT1 TRM / B 3.3-14a SUSQEHANA-NITI TR | ||
SUSQUEHANNA | / 3.314aEFFECTIVE DATE 11/04/2015 | ||
-UNIT | |||
This TRS is for the performance of a CHANNEL CALIBRATION of | Main Turbine Overspeed Protection System Rev. 2 B 3.3.7 B 3.3.7 Main Turbine Overspeed Protection System BASES ACTIONS C.1 (continued) | ||
The calibration is a complete check of the instrument channel from the sensing device | If the MTOPS is inoperable for reasons other than conditions A or B, then action must be taken to isolate the main turbine from the steam supply. | ||
The Frequency of 24 months is a typical refueling cycle and considers channel reliability. | 6 hours allows a reasonable amount of time to complete the plant shutdown associated with isolating the main turbine from the steam supply. | ||
TRS 3.3.7. | TRS The TRSs are performed at the specified Frequency to ensure that the turbine overspeed protection function is maintained OPERABLE. | ||
is required to | The TRSs are modified by a Note to indicate that 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 hours provided the redundant overspeed trip device is OPERABLE. Upon completion of the Surveillance, or expiration of the 6 hour allowance, the channel must be returned to OPERABLE status or the applicable Condition entered and Required Actions taken. This Note is based on the average time required to perform channel Surveillance. The 6 hour testing allowance does not significantly reduce the probability that the Main Turbine Overspeed Protection System will function when necessary. | ||
REFERENCES | TRS 3.3.7.1, TRS 3.3.7.2, and TRS 3.3.7.3 Verification of the movement of each of the four high pressure turbine control valves, six low pressure turbine combined intermediate valves (composed of 6 intermediate stop valves and 6 intercept valves), and four high pressure turbine stop valves ensures the OPERABILITY of each valve and that it will be able to close in the event of a turbine trip condition. The 92 day Frequency is based upon current surveillance practice as recommended by the turbine vendor and described in the FSAR (Ref. 3). | ||
(continued) | |||
SUSQUEHANNA - UNIT 1 TRM / B 3.3-14b SUSQEHANA-NIT TRM/ | |||
B3.314bEFFECTIVE DATE 11/04/2015 | |||
Main Turbine Overspeed Protection System Rev. 2 B 3.3.7 B 3.3.7 Main Turbine Overspeed Protection System BASES TRS TRS 3.3.7.4 (continued) | |||
This TRS is for the performance of a CHANNEL CALIBRATION of the required main turbine overspeed protection instrumentation. The calibration is a complete check of the instrument channel from the sensing device to main turbine trip initiation. The Frequency of 24 months is a typical refueling cycle and considers channel reliability. | |||
TRS 3.3.7.5 The disassembly and inspection of the valves referenced ensures that abnormal wear is not occurring which could result in the valves inability to close upon receipt of a close signal. The Frequency is such that only one of each type valve (i.e., high pressure turbine stop; high pressure turbine control; and low pressure turbine combined intermediate), is required to be inspected within a 40 month period. If unacceptable flaws or excessive corrosion are found in a valve, all valves of its type are inspected (Ref. 3). | |||
Valve bushings are inspected and cleaned, and bore diameters are checked for proper clearance. | |||
REFERENCES 1. FSAR Section 7.7:1.5 | |||
: 2. FSAR Section 10.2.2.6. | |||
: 3. FSAR Section 10.2.3.6. | : 3. FSAR Section 10.2.3.6. | ||
SUSQUEHANNA-UNIT1 TRM / B 3.3-14c SUSQEHANA | |||
-UNITI TR | |||
/ 3.314cEFFECTIVE DATE 11/04/2015 | |||
Nov. 11, 2015 Page 1 of 2 MANIJAL HARD COPY DISTRIBUTION DOCUMENT TRANMSMITTAL 2015-45734 USER INFORMATION: | |||
GERLACH*ROSEY N EMPL#:028401 CA#: 0363 Address: NUCSA2 Phone#: 254-3194 TRANSMITTAL INFORMATION: | |||
TO: GERLACH*ROSEY N 11/11/2015 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 MNAL. 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. | |||
TRMI - TECHNICAL REQUIREMENTS MANUAL UNIT 1 REMOVE MANUAL TABLE OF CONTENTS DATE: 11/03/2015 ADD MANUAL TABLE OF CONTENTS DATE: 11/10/2015 CATEGORY: DOCUMENTS TYPE: TRM1 4oc2 | |||
Nov. 11, 2015 Page 2 of 2 ID: TEXT 3.2.1 REMOVE: REV:15 ADD: REV: 16 CATEGORY: DOCUMENTS TYPE: TEMI ID: TEXT 3.3.7 REMOVE: REV:1 ADD: REV: 2 CATEGORY: DOCUMENTS TYPE: TRMI ID: TEXT B3.3.7 REMOVE: REV:I1 ADD: REV: 2 CATEGORY: DOCUMENTS TYPE: TRMI ID: TEXT LOES REMOVE: REV: 83 ADD: REV: 84 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 MNUALm Manual Name:z TRM1 Manual | |||
==Title:== | |||
TECHNICAL REQUIREMENTS MANUAL UNIT 1 Table Of Contents Issue Date: 1LI/I10/2 015 Procedure Name Rev Issue Date Change ID Change Numiber TEXT LOES 84 11/10 /2 015 | |||
==Title:== | |||
LIST OF EF:FECTIVE SECTIONS TEXT TOC 25 04/28/2015 | |||
==Title:== | |||
TABLE OF CONTENTS TEXT 1.1 1 01/31/2014 | |||
==Title:== | |||
USE AND APPLICATION DEFINITIONS TEXT 2.1 2 04/28/2015 | |||
==Title:== | |||
PLANT PROGRAMS AND SETPOINTS PLANT PROGRAMS TEXT 2.2 10 01/31/2014 | |||
= | |||
==11.0 REFERENCES== | ==11.0 REFERENCES== | ||
................ | ................ ................................................................ 61 SUSQUEHANNA UNIT 1 TRM/3.2-4 SUSQEHANA NITTR/3..-4DATE 11/04/2015 EFFECTIVE | ||
................................................................ | |||
Rev. 16 PL-NF-14-0O1 Rev. 2 Page 4 of 62 1.0 iNTRODUCTION This CORE OPERATING LIMITS REPORT for Susquehanna Unit t Cycle 19 is prepared in accordance with the requirements of Susquehanna Unit 1, 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. | |||
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 | SUSQUEHANNA UNIT 1 TRM/3.2-5 UNT I RM/32-5 SUSQEHANA EFFECTIVE DATE 11/04/2015 | ||
The Oscillation Power | |||
2.9 Np is the OPRM setpoint for the number of consecutive confirmations | Rev. 16 PL-NF- 14-001 Rev. 2 Page 5 of 62 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. | ||
2.10 Sp is the OPRM trip setpoint for the peak to average OPRM signal.2.11 Fp is the core flow, in Mlbm I hr, below which the OPRM RPS trip is activated. | 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. | ||
SUSQUEHANNA UNIT | 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. | ||
If the value of "R" is zero (that is, BOG is the most reactivepoint in | 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. | ||
The SHUTDOWN MARGIN limits provided in 3.2a and 3.2b are applicable | 2.4 LHGRFACT is a multiplier applied to the LHGR limit when operating at less than 108 Mlbm/hr core flow. The LHGRFAC1 multiplier protects against both fuel centerline melting and cladding strain during anticipated system transients initiated from core flows less than 108 Mlbmlhr. | ||
SUSQUEHANNA UNIT | 2.5 LHGRFACp is a multiplier applied to the LHGR limit when operating at less than RATED THERMAL POWER. The LHGRFACp multiplier protects against both fuel centerline melting and cladding strain during anticipated system transients initiated from partial power conditions. | ||
The APLHGR | 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. | ||
........4 | 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. | ||
.1 1111I | 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. | ||
* I IIaIaI IaI IaIaI aI IaI Ia | 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. | ||
I I ~ ~ a a a | 2.10 Sp is the OPRM trip setpoint for the peak to average OPRM signal. | ||
-TWO LOOP OPERATION ATRIUMTM-10 | 2.11 Fp is the core flow, in Mlbm I hr, below which the OPRM RPS trip is activated. | ||
The MCPR limits for Single Loop operation are provided in Section 8.0.5.4 Averauqe Scram Time | SUSQUEHANNA UNIT 1 TRM/3.2-6 SLJSUEHNNAUNITI EFFECTIVE TMI32-6 DATE 111/0412015 | ||
Determining MCPR operating limits based on interpolation between scram insertion times is | |||
The evaluation of scram insertion time data, as it relates to | Rev. 16 PL-NF-1 4-001 Rev. 2 Page 6 of 62 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: | ||
SUSQUEHANNA | 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 (BOG) SHUTDOWN MARGIN (SDM) tests must also account for changes in core reactivty during the cycle. Therefore, the SUM 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 8DM) during the operating cycle and the calculated BOG core reactivity. If the value of "R" is zero (that is, BOG is the most reactivepoint in the cycle) no correction to the BOG measured value is required. | ||
, ... .. .. .. .. ... .. ,,,,, .. .. .. ........ ... .. 1 ... .. ..... ... ..... ... ............ .I J ... .... .,J , , = ... ... . | 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. | ||
SSES UNIT 1 CYCLE | SUSQUEHANNA UNIT t TRM/3.2-7 SUSQEHANA UNTI RM/32-7 EFFECTIVE DATE 11104/2015 | ||
Rev. 16 PL-NF-14-O01 Rev. 2 Page?7 of 62 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 ATRIUMT'-10 fuel shall not exceed the limit shown in Figure 4.2-1. | |||
-I"I--- | 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 1 TRM/3.2-8 SUSQEHANA UNT I RM/32-8 EFFECTIVE DATE 11/04/20 15 | |||
9! | |||
02 SSES UNIT I CYCLE 19 C | |||
*16.0 C , 1111 a a I IIl | |||
, I 1, I , 1 111III Ia' II1 1,1 , , I. . III . . la | |||
. . ma | |||
.a rn 1 1 1a I I a aIn 1 I II 4 i i i i i l l i ___ 1 1 1 1 a 11__ | |||
.-- I 1 I I I I I I I I I I I K I I 2 iI * - 1 | |||
* 1I | |||
* l O = . I 2 z | |||
z 1[4.0 I 1 K I 1 II I I I I-- I4 j a I --t-1 . t. I I--1I- . I l | |||
.. l 2lI IlIIl | |||
.. ................... l | |||
. . . . . . . . ' 4. i. . . . | |||
I a al U I I I I C | |||
,IIII2, ,K,2,*,*,t*IaI*I | |||
;! IIlIt I i i l | |||
i a a a a a t II i mi I i I 2 II! i i 1 i i I 12.0 12 5 I00 a . a: .* 5 0 ,1 . . : ..... .. .. I I 1... I .. .2.. . .. | |||
i ~i i ll I i i iai aii i I I I II 1 I Il l i l l l l l | |||
/ 1 /1 1 11 l l1Il l1/ I | |||
. . 1I .1 ._ , , . . I. I .I I ! | |||
II | |||
/ | |||
I I I I II ii iIa i i i i i i 1nIi 1 a1 1 0I I i iI iI 1 iI i iI i 11 liii !1 1*11I11111I1 .1 1111I 1 ,< | |||
i 1 i i i i i i iai a i1I a . . . . . . I I a a a a a*,,. a a .a.a.a.a.a.a.a 0) | |||
* I IIaIaI IaI IaIaI aI al IaI a Ia l l | |||
'-I | |||
., ., ,*! . ! | |||
* I I aI a ,," ,a a l I a I I1la.lal Il laimla.! | |||
a m I I ~ ~ a a a i l l',I al I. II l .a. "* a | |||
** I3l lllam K a a " *a--a-- * *: II ' Il i iii l liIa 1 a i' a l a l a1 1a1 1 a1 a g all 1 1 1 11I a aI aI I II a a n a ai i a a a Ia a I | |||
-I', | |||
"-1 I I I I I! l l Ii.. a ~ | |||
Cn-, aI /a ia li1 aII alal a_ | |||
a a | |||
aal a iI__la1a1a1a1a1a l | |||
i | |||
.*~* _L __*. | |||
I a a | |||
.J aL2 tI 6.0 la la aal la | |||
, , , ,*H , , | |||
aal aal I I , I , I I I.1._ 3 - | |||
.-t | |||
-- I mr 4.0 0 10000 20000 30000 40000 Average Planar Exposure (MWDIMTU) 50000 60000 70000 0 | |||
-* ,r-SI) | |||
AVERAGE AVERAGE PLANAR LINEAREXPOSURE PLANAR HEAT GENERATION RATE LIMIT VERSUS | |||
-TWO LOOP OPERATION Coz ATRIUMTM-10 FUEL C:'(D7 FIGURE 4.2-1 | |||
Rev. 18 PL-NF-14-001 Rev. 2 Page 9 of 62 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 Technical Requirements Manual Reference Technical Requirements Manual 3.3.7 5.3 Description The MOPR 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-1O) shall be the greater of the Flow-Dependent or the Power-Dependent MOPR, depending on the applicable equipment operability status. | |||
a) Main Turbine Bypass I EOO-RPT I Backup Pressure Regulator Operable Figure 5.2-1: Flow-Dependent MCPR value determined from BOO to EDOC Figure 5.2-2: Power-Dependent MOPR value determined from BOO to EGOC b) Main Turbine Bypass lnoperable Figure 6.2-3: Flow-Dependent MCPR value determined from BOO to EDOC Figure 5.2-4: Power-Dependent MOPR value determined from BOO to EGOC c) EOC-RPT Inoperable Figure 5.2-5: Flow-Dependent MCPR value determined from BOO to EOC Figure 5.2-6: Power-Dependent MCPR value determined from BOG to EOO d) Backup Pressure Regulator Inoperable Figure 5.2-7: Flow-Dependent MCPR value determined from BOO to EDOC Figure 5.2-8: Power Dependent MCPR value determined from BOG to EDOC e) One Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) Closed Figure 5.2-0: Flow-Dependent MCPR value determined from BOO to EGG Figure 5.2-1 O:Power-Dependent MCPR value determined from BOO to EDO SUSQUEHANNA UNIT 1 TRM/3.2-10 SUSQEHANA UITTRM3.2I EFFECTIVE 0DATE 11/04/2015 | |||
Rev. 16 PL-NF-1 4-001 Rev. 2 Page 10 of 62 The MCPR limits in Figures 5.2-1 through 5.2-10 are valid for Two Loop operation. | |||
The MCPR limits for Single Loop operation are provided in Section 8.0. | |||
5.4 Averauqe Scram Time Fraction Ifthe 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 UNIT1 TRM/3.2-11 SUSQEHANA UITTRM3.21 EFFECTIVE IDATE 11104/2015 | |||
Rev. i6 PL-NF-14-O01 Rev. 2 Page Iiof 62 Main Turbine Bypass I EOC-RPT I Backup Pressure Regulator Operable SUSQUEHANNA UNIT 1 TRM/3.2-12 NITTR/32I 2DATE 1110412015 EFFECTIVE SUSQEHANA | |||
C' SSES UNIT 1 CYCLE 19 C 2.2 c, | |||
2,1 z | |||
z 2.0 z | |||
1.9 | |||
._E 1.8 1.7 CD k* 0. | |||
CA 0o 1.6 <) | |||
1.5 m 1.4 Ill C) | |||
H 1.3 rn ci 1.2 H 30 40 50 60 70 80 90 100 110 Total Core Flow (MLBIHR) | |||
-o "o n, I Ill (.Q0 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS 1 EOC-RPT I BACKUP PRESSURE REGULATOR OPERABLE TWO LOOP OPERATION (BOC TO EOC) | |||
FIGURE 5.2-1 * -< 0 | |||
. . .. . . . .. .... . .. ..... ...... .... .... .. . ... ... . . . . .. . . . . .. . . .... . .. ........ ,... .. .. .. .. . .. .. ,,,,,.. .. .. . . . . . ... ... .. 1... .. . . . .. . .. . .... ... . .. . . .. . . . .. . I J . .. .... . ,J , , =. .. ... . | |||
cj SSES UNIT 1 CYCLE 19 0 | |||
z z | |||
C z | |||
1J H 0. | |||
0 m | |||
0 20 30 40 50 60 70 80 90 100 Core Power (% RATED) | |||
"13 -O | |||
*, I-MCPR OPERATING LIMIT VERSUS CORE POWER 0" MAIN TURBINE BYPASS I EOC-RPT I BACKUP PRESSURE REGULATOR OPERABLE TWO LOOP OPERATION (BOO TO EOC) (3 " | |||
n Ii --. | |||
FIGURE 5.2-2 | |||
Rev. 16 PL-NF- 14-001 Rev. 2 Page 14 of 62 Main Turbine Bypass Inoperable SUSQUEHANNA UNIT1 TRM/3.2-15 UITTRM3.2l EFFECTIVE SUSQEHANA 5DATE 1 1/04/2015 | |||
0 SSES UNIT 1 CYCLE 19 2.2 03 C | |||
===2.1 LEGENDA=== | |||
MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME | |||
-CURVE CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME z | |||
C 2.0 z | |||
-1 1.9 I INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 1.8 H. '1.7 0J o-01 1,6 1.5 | |||
-I"I 1.4 | |||
--- I EEENCE:_T.S. 3.7.6 and 3.2.2 ___________ __________ | |||
'1.3 m | |||
Hr iii 1.2 30 40 50 60 70 80C I0 100 110 Total Gore Flow (MLB/H-R) | |||
--t "D " | |||
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS INOPERABLE TWO LOOP OPERATION (BOC TO EOC) | |||
FIGURE 5.2-3 ,.-4 < | |||
Q)"* | |||
0 | |||
CI, SSES UNIT 1 CYCLE 19 C 3.6 Ci, C | |||
mR c | |||
Z | |||
-t | |||
.E_ | |||
-H 0 | |||
$o O. | |||
-.4 | |||
-11 "51 m | |||
z3 | |||
-H | |||
<m Fi 20 30 40 50 60 70 80 90 100 Core Power (% RATED) | |||
(73 -U 51 MCPR OPERATING LIMIT VERSUS CORE POWER CD CD- | |||
*MAIN TURBINE BYPASS INOPERABLE Z TWO LOOP OPERATION (BOC to EOC) 77 FIGURE 5.2-4 -- h 0) | |||
Rev. 16 PL-NF-14-001 Rev. 2 Page 17 of 62 EOC-RPT Inoperable SUSQUEHANNA UNIT 1 TRM/3,2-18 SUSQEHANA UITTRM3.2I EFFECTIVE 8DATE 11/04/2015 | |||
CD SSES UNIT 1 CYCLE 19 2.2 03 LEGEND C | |||
m 2.1 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM | |||
= | |||
INSERTION TIME 2.0 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME C | |||
z 1.9 4. SAFETY* ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 | |||
-H E I I IJ 1.8 L. | |||
USED INDETER[MIN1NG MFLCPR I | |||
-4. 1.7 0. | |||
C0 o CD 1.6 -3. | |||
C) 1.5 | |||
-rr 1.4 | |||
==REFERENCE:== | |||
T.S. 3.3.4.1 and 3.2.2 | |||
--Il | |||
<r m 1.3 m | |||
1.2 30 40 50 60 70 80 90 100 110 U Total Core Flow (MLBIHR) | |||
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW EOC-RPT INOPERABLE *QcD TWO LOOP OPERATION (BOC TO EOC) | |||
FIGURE 5.2-5 0"" | |||
ci SSES UNIT 1 CYCLE 19 C | |||
I z | |||
z z | |||
E 0 | |||
(D 0 | |||
C) m n-I 0 | |||
H m | |||
0 50 60 90 H* 20 30 40 Core Power (% RATED) 70 80 100 n-MCPR OPERATING LIMIT VERSUS CORE POWER *(D Z EOC-RPT INOPERABLE TWO LOOP OPERATION (BOC to EQO) O-" -1 FIGURE 5.2-8 (O1*-- | |||
Rev. 16 PL-NF-14-0O1 Rev. 2 Page 20 of 62 Backup Pressure Regulator Inoperable SUSQUEHANNA UNIT 1 TRM/3.2-21 NIT TR/3.-21 DATE 11/04/2015 EFFECTIVE SUSQEHANA | |||
SSES UNIT 1 CYCLE 19 Cn 2.2 LEGEND m | |||
2.1 _____________ -CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME z | |||
C 2.0 ________ -CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME z | |||
1.9 _______ _______ - SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 1.8 I-1.7 r*o 0 A BI | |||
: 10. 0, 1.6 1.5 m | |||
"1 1.4 rri 0 | |||
==IREFERENCE:== | ==IREFERENCE:== | ||
TS. 3.7.8 and 3.2.2~ | |||
1.3 I-~ { 4 1 ~~-f 108, 1.221 m 1.2 30 40 50 60 70 80 90 100 110 Total Core Flow (MVLB/HR) | |||
"-D "- | |||
0 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW BACKUP PRESSURE REGULATOR INOPERABLE "'.) | |||
0 o', TWO LOOP OPERATION (BOC TO EQO) | |||
FIGURE 5.2-7 "*' <c 0 0)" | |||
SSES UNIT I CYCLE 19 60 C | |||
z 0, | |||
.2 | |||
-Il CD C | |||
-3. | |||
0) | |||
'i,, | |||
100,1.35 m | |||
20 30 40 50 60 (% RATED) 70 Core Power 80 90 100 o1 T1 T1 | |||
-L | |||
*Q2 Z~ | |||
MCPR OPERATING LIMIT VERSUS CORE POWER BACKUP PRESSURE REGULATOR INOPERABLE TWO LOOP OPERATION (BOO to EOC) | |||
FIGURE 5.2-8 -,h . 0 0)' ,C | |||
Rev. 16 PL-NE-14-001 Rev. 2 Page 23 of 62 One TSV. or TCV Closed SUSQUEHANNA UNIT 1 TRM/3.2-24 SUSQEHANA UIT ITR IS.-24 EFFECTIVE DATE 11104/2015 | |||
SSES UNIT 1 CYCLE 19 2.2 I LEGEND 2,1 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 2.0 _______ | |||
SSES UNIT | _______ -CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME | ||
-r" 1.9 130, 1.831 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES NJ I ARE OPERABLE PER SR 3.7.5.1 AND 3.7.6.2 U' .4-1.8 | |||
*_ USED IN DETERMINING MFLCPR E2 1.7 C., 1.6 CD 1.5 m | |||
-I-1 1.4 m | |||
==REFERENCE:== | ==REFERENCE:== | ||
T.S. 3.2.2 and TRM 3.3.71 0 | |||
I-4 1.3 | |||
_ _ I _ I_ _ _ _ _ _ _ _ _ _ | |||
1.2 m | |||
30 40 50 60 70 80 90 100 110 Total Core Flow (MLBIHR) 0 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW CD Z N) | |||
ONE TSV OR TCV CLOSED* | |||
TWO LOOP OPERATION (BOC TO EOC) - ,-< | |||
FIGURE 5.2-9 0 | |||
*Operatofl with one TSV or TCV closed is only supported at power levels -<75%rated power. | |||
cj SSES UNIT 1 CYCLE 19 C | |||
m z | |||
C z | |||
S 0.- | |||
-I 0m | |||
*0 CD m | |||
-n m | |||
m C) | |||
-9 20 30 40 50 60 70 80 | |||
*Core Power (% RATED) | |||
MCPR OPERATING LIMIT VERSUS CORE POWER | |||
*ONE TSV OR TCV CLOSED Co I TWO LOOP OPERATION (BOC TO EOC) | |||
FIGURE 5.2-10 | |||
Rev. 16 PL-NF-14-O01 Rev. 2 Page 26 of 62 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 - oo70 3.440 Average Scram Realistic Maximum Insertion Time Allowable SUSQUEHANNA UNIT 1 SUQEAN NTITRM/3.2-27 EFFECTIVE DATE 11/0412015 | |||
: 1. . . .1 I * ... A... . . - -- a L.~cgaa. . .. .. * .1 L. * -- . .*... ..&. aaau I 1S a. . .... aJ L&...aa......a..n. | |||
Rev. 16 PL-NF- 14-001 Rev. 2 Page 27 of 62 6.0 LINEAR HEAT GENERATION RA*TE (LHGR) 6.1 Technical Specification Reference Technical Specification 3.2.3, 3.3.4.1, 3.7.6, and 3.7.8 6.2 Technical Requirements Manual Reference Technical Requirements Manual 3.3.7 6.3 Description The maximum LHGR for ATRIUMTZ-I 0 fuel shall not exceed the LHGR limit determiined 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 in the following figures: | |||
a) Main Turbine Bypass Operable Figure 6.2-2: Flow-Dependent LHGR Uimit Multiplier Figure 6.2-3: Power-Dependent LHGR Limit Multipiier b) Main Turbine Bypass Inoperable Figure 6.2-4: Flow-Dependent LHGR Limit Multiplier Figure 6.2-5: Power-Dependent LHGR Limit Multiplier c) One Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) Closed Figure 6.2-6: Flow-Dependent LHGR Limit Multiplier Figure 6.2-7: Power-Dependent LHGR Limit Multiplier | |||
* The LHGR limits and LHGR limit multipliers in Figures 6.2-2 and 6.2-3 are applicable to EOC-RPT Operable and Inoperable and Backup Pressure Regulator Operable and Inoperable. | |||
* The LGHR limits and LHGR limit multipliers in Figures 6.2-1 through 6.2-7 are valid for both Two Loop and Single Loop operation. | |||
SUSQUEHANNA UNIT 1 TRM/3.2-28 SUSQEHANA EFFECTIVE NITTRI3.-28 DATE 11/04/2015 | |||
C,) | |||
SSES UNIT 1 CYCLE 19 C 16.0 Ii Ii II ii i iI ii ii a ili a iI l Ii i !i Co a a la a a l la l a l 0 a a | |||
a a | |||
a a I I I I El 11111 ' I* I I | |||
C I ! | |||
m lala al ala a alalala alIlal al a la aa a a a a L +/- Z .... L 1 - - .....t....J......- | |||
= - | |||
z '14.0 0.,3.---- f=--I--+ I 900 ,-I--S-I--.. | |||
4 ..J- REFERENCE; T.S 3.2.3 z L- i- - - I I I a a a. a . . a . .a . .a . .a . I & a 1 a a a a I a I a. I. ~ alala IaI-aI I I IaIaI l aI IaI a Ial al l lalal lala C | |||
a[ | |||
a a | |||
a aI la a al ia I Ia a a a ia a I alalalala I a la alaa a a a a | |||
a la a | |||
l n | |||
a .a .a a l la aal . . . . 1I t. t. .1 I .. . .. . .. ..... .. . | |||
4" z La-Ial lal la"1a1 aI 1ajj ~ I i jII !i i l 12.0 al a lala alalal aI a i l a a /aaa a a1 1 a a1 2 a . .a. a. a a a a, a a Iaf a a I a at aIa aI a a.a.a. a. a aIa a ala aIalal lii l al al l al a l 0 | |||
Cu ~II I I II Ia I I I I I Ia 1 1 11 1 11 1 ~I I Ia I aaI a I I a | |||
I l | |||
aaI Ia a. I a a I | |||
al I a I I II a | |||
H C a I l lall l la iala lalala al aialaIa a | |||
'a" 10.0 Cu a- ta l al la a al | |||
-- al-- aI a 4aIaa a- a- a aIaI a aI a--a a- a a-- a- a a aI IIaa a a IIaI I aa aIa a4 - I * - | |||
0 aa a a a a a a a aia a aIa a Iaaatai i iiaa a a ,aaa a a a ,aaa aa a Il | |||
, , CD a Ia a la a alalI a a a a a a a a a a a a a l a a a Ialal .a . .a.aa .a .a a a a a a a a a a a a Ia aIa a aI aI .a a .a.. a a N) V aI a al i lalalala a a alal aI a a1 C I l l l l l1-Ta-TaII l l I I-I I-yi rw- l l l- . . . | |||
N) CD a a i a a lalala a la a a a a a al a | |||
la. | |||
a"a a | |||
a a | |||
a ai a a alal a | |||
a a | |||
a a | |||
a a | |||
a a | |||
l a | |||
ia a a l la la a | |||
a la l | |||
a l | |||
a la a | |||
l i | |||
4-a Co 0 aI a I Ia I Ia I a a Ia a Ia a a a la a a l la l la a a al Ia a la a la a a a l 0) 0 I- 8.0 0 I I I Ill I I I a I iII Ia Il I *l lll ali C | |||
Ial a lI ll l a 1 l i l lI l . a. al | |||
.a. l 1 l 7 l iI al~ | |||
l l l l1l l l lal lal l lanl l l i mm I I I II I I I I I I I I I I I I I I | |||
-I- 6.0 rn .a.. .a.. a a j , , I a , , t , ,I a a ,iI, a a I ! | |||
H 11 11 1 1 11 1111 ai lal a all a a al a aI 1 I a I a a a C 4.0 0 10000 20000 30000 40000 50000 60000 70000 80000 H | |||
Pellet Exposure (MWDIMTU) rr T-0 " | |||
-I- UNEAR HEAT GENERATION RATETMLIMIT VERSUS PELLET EXPOSURE ATRIUM -10 FUEL FIGURE 6.2-1 Oco a-0")' 0 | |||
Rev. 16 PL-NF-'I4-001 Rev. 2 Page 29 of 62 Main Turbine Bypass Operable SUSQUEHANNA UNIT 1 TRM/3.2-30 SUSQEHANA NITTR/3.-30 DATE 11/04/2015 EFFECTIVE | |||
C,, | |||
SSES UNIT 1 CYCLE 19 Co 1.10 1.00 z | |||
z 0.90 | |||
-I-- | |||
0.80 | |||
-I ._1 | |||
('3 0.70 a, <D | |||
('3 | |||
._) | |||
0.60 0,50 | |||
-n r-n m 0.40 m | |||
0.30 | |||
-I 30 40 50 60 70 80 90 100 110 m: Total Core Flow (MLB/hr) | |||
: 0) FLOW DEPENDENT LHGR LIMIT MULTIPLIER NJ MAIN TURBINE BYPASS OPERABLE (03 ATRIUMT*-10 FUEL FIGURE 8.2-2 | |||
SSES UNIT 1 CYCLE 19 1.10 L I & "" 'U"' ........... * " ' | |||
* m L 4 4 * | |||
* A A i C | |||
m3 LEGEND | |||
.. " ' ' | |||
* t I " I I i | |||
I ii Fji o T ---- ,-------~.------.I-------, 9 CURVE A: BASE CURVE 1.00 CURVE B: CORE POWER __26% AND CORE FLOW <_.0 MLBM1HR | |||
* I TI rS I 1 31 1 --- I - . ..- j. a .I - * -- - | |||
0.90 I I I I a I i I I | |||
"-I II l l* i I [ aI I li l i k I I | |||
I | |||
.1_J IIS | |||
_ _ J. _ | |||
I | |||
. 1 IJ ; | |||
1 _1 J LI z | |||
I-- | |||
0.80 I I I I I 1 1 5 I I I I I 1 I I I I I | |||
,.I I l ARE OPRAL PE SR ANI37lI... | |||
0.70 . . ..._ | |||
* 1*. 1. * * ._ ._ . . . . . . . . . | |||
C) /II I I 1 I ___ _ _ ___ ___ __ ___ ___ _ | |||
1_- | |||
H 0. | |||
0 0.60 | |||
__..,. . IL.__J._.I * ..- 1 REOERABENCE: TSR 3.2.3,1 3.A4N 3.7.6 an 8 I I | |||
iH i _ 1i_ | |||
; / | |||
0.50 - | |||
03 iL I yr i I" '-- "" ' "- - ! . .. .... .. . . .. .-. -- - '- - -l . - - * - * - ; ' .. . . | |||
l 26 04 N,3 0.40 23 I -" - | |||
0.0. | |||
I I... | |||
II -'-I.... | |||
I | |||
.. F - I-' | |||
, ~l, I- | |||
* I I * --I - - - - -l-I | |||
, , I | |||
-- - It - - | |||
3I - * | |||
/ - f - I- - | |||
I , | |||
-I - d - - | |||
i I I I I I I I I I I I | |||
! ,, IJ, J I I I I I r I I I I I I I - 3 I I 0 0.30 I I II I r I I 1 2,0 30 40 50 Core Power 60 (% RATED) 70 80 90 100 POWER DEPENDENT LHGR LIMIT MULTIPLIER MAIN TURBINE BYPASS OPERABLE o ,z AT*iUMTM-10 FUEL FIGURE 6.2-3 | |||
Rev. 16 PL-NF-14-O01 Rev. 2 Page 32 of 62 Main Turbine Bypass Inoperable SUSQUEHANNA UNIT I TRM/3.2-33 SUSQEHANA NITTR/3.-33 DATE 11t10412015 EFFECTIVE | |||
SSES UNIT 1 CYCLE 19 Co 1.10 I | |||
z 1.00 C: | |||
Z 0.90 0. | |||
.. | 0.80 | ||
.-I "-J C;, ._ 0.70 C;o 0, | |||
C),. 0) 03 0.60 0o Ct 0.50 m | |||
C) | |||
* | -H m1 0.40 0 | ||
H-1 m] 0.30 30 40 50 60 Total Core Flow 70 80 90 100 110 (MLB/HR) | |||
"0 "- | |||
nD FLOW DEPENDENT LHGR LIMIT MULTIPLIER C.D z MAIN TURBINE BYPASS INOPERABLE 01 ATRIUMTMea-t FUEL -Il 0O FIGURE 6.2-4 0 | |||
.. | |||
CO, SSES UNIT 1 CYCLE 19 C 1.10 03 m | |||
= | |||
z z | |||
C z | |||
a.. | |||
.5. | |||
.5 0 | |||
--I -I a, | |||
1'3 a, oD 0 | |||
I.. | |||
a) 0 0. | |||
m m | |||
0 | |||
.-I m | |||
0 4> 20 30 40 50 60 (% RATED) 70 Core Power 80 90 100 | |||
--I, 01" POWER DEPENDENT LH-GR LIMIT MULTIPLIER MAIN TURBINE BYPASS INOPERABLE Co C? ATRIUMTM.-10 FUEL FIGURE 6.2-,5 0"C* | |||
Rev. 16 PL-NF-14-00l Rev. 2 Page 35 of 62 One TSV or TCV Closed SUSQUEHANNA UNIT 1 TRM/3.2-36 NITTR/3.-36DATE 11/04/2015 EFFECTIVE SUSQEHANA | |||
0 O SSES UNIT 1 CYCLE 19 1.10 C | |||
i"1 1.00 C | |||
z 0.90 a, | |||
-H1 0.80 | |||
-_J 0.70 CD CD | |||
",4 0.60 U.. | |||
0.50 | |||
-T1 | |||
-IT 0.40 m | |||
m 0.30 0 30 40 50 60 Total Core 70Flow (MLB/hr) 80 90 100 110 rl3 FLOW DEPENDENT LHGR LIMIT MULTIPLIER 0 ONE TSV OR TCV CLOSED* 0-" 0 ATRIUMTM-t10 FUEL D' I, -= | |||
FIGURE 6.2-6 | |||
*Operation with one TSV or TCV closed is only supported at power [evels | |||
* 75% rated power. | |||
n ,, n | |||
C', | |||
SSES UNIT 1 CYCLE 19 C | |||
03 m | |||
C z | |||
13 | |||
{.i | |||
--I ,-J | |||
.1_ | |||
C,) | |||
0 cc 0L 0) mT "rn ml 0 | |||
m1 H3 20 30 40 50 (% RATED) | |||
Core Power 60 70 80 rn | |||
-I POWER DEPENDENT LHGR LIMIT MULTIPLIER CD Z ONE TSV OR TCV CLOSED ATRIUMTM-10 FUEL *i-- n FIGURE 6,2-7 c0* | |||
Rev. 16 PL-NF-14-OO1 Rev. 2 Page 38 of 82 7.0 ROD BLOCK MONITOR (RBM SETFOINTS AND OPERABILITY 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, d) Low Power Range - Upscale, e) Intermediate Power Range - Upscale, and I) 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. Ifthe 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. | |||
SUSQUEHANNA UNIT 1 TRM/3.2-39 NITTRIS.-39 DATE 11/04/2015 SUSQEHANA EFFECTIVE | |||
Rev. 16 PL-NF-14-001 Rev. 2 Page 39 of 62 Table 7.2-I RBM Setpoints Allowable Nominal Trip Function Value( 1 ) 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 117.4 117.0 High Power Range - Upscale 107.6 107.2 (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) | |||
> 28 andc<90 < 1.76 | |||
~90 and <95 <1.47 | |||
>_95 < 1.70 (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. | (3 Applicable to both Two Loop and Single Loop Operation. | ||
SUSQUEHANNA UN]T | SUSQUEHANNA UN]T 1 TRMI3.2-40 SUSQEHANA NITTRI3.-40 DATE 11/04/201 5 EFFECTIVE | ||
Rev. 18 PL-NF-1 4- | |||
Minimum Critical Power Ratio Limit-The MCPR limit is specified as a function of core power, core flow, and | Rev. 18 PL-NF-1 4-001 Rev. 2 Page 40 of 62 8.0 REGIRCULATION 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 Technical Req~uirements Manual Reference Technical Requirements Manual 3.3.7 8.3 Description APLHGR The APLHGR limit for ATRlUMTM-I 0 fuel shall be equal to the APLHGR Limit from Figure 8.2-1. | ||
Linear Heat Generation Rate | 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 (ATRIUM TM-10) shall be the greater of the Flow-Dependent or the Power-Dependent MCPR, depending on the applicable equipment operability status. | |||
-L~l l l l l l l lI l l i l | a) Main Turbine Bypass I 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 [noperable 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 IEOC c) EOC-RPT Inoperable Figure 8.2-6: Flow-Dependent MCPR value determined from BOG to EOC Figure 8.2-7: Power-Dependent MCPR value determined from BOC to EOC SUSQUEHANNA UNIT 1 TRMI3.2-41 NIT TRI3.-41EFFECTIVE SUSQEHANA DATE 11/04/2015 | ||
...... ..... ..... .......... | |||
... ..... .......... | Rev. 18 PL-NF-14-OO1 Rev. 2 Page 4l of 62 d) Backup Pressure Regulator Inoperable Figure 8.2-8: Flow-Dependent MCPR value determined from BOO to EGOC Figure 8.2-9: Power-Dependent MCPR value determined from BOO to EDO e) One Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) Closed Figure 8.2-1O:Flow-Dependent MOPR value determined from BOO to EDO Figure 8.2-11 :Power-Dependent MOPR value determined from BOO to EOC The MOPR limits in Figures 8.2-2 through 8.2-1 1 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 andOperabilityRequirem~ents The RBM setpoints and operability requirements for Single Loop Operation are defined in Section 7.0. | ||
......... | SUSQUEHANNA UNIT 1 TRM/3.2-42 NITTRI3.-42 DATE 1110412015 EFFECTIVE SUSQEHANA | ||
....... ...... ... .. i, .... .. ... ... ... .... .. . | |||
Rev. 16 PL-NF.-14-001 Rev. | C 16.0 T T T r T ~ T ~ u 1 1 ~ I r QI I I ' I I l Il l t I I la 1 l l 9 i0 1 ' | ||
I E lI I I Ii l l l llI lI l | |||
: z. 1. .1. II .11 .. II1lIti1 1 I, i I s I i I r I,.i m i . m m m ii.m n l4...4 mm~~u mm.4.*" | |||
I11I 1 I I Ii lIlC Il IlIII1I I1I1 l i l 1 Il l l ~l t l I! ~ l l l O l 1 1 I I I l I I I I Ii ~ll I I l1 1 1I tltitjilt SED IND*ERINIG0 | |||
* -- J- I---. ii! I I-I.-- -- I-- j--i-..J..-,Lf lf...f I I1 1'I II£ I Ii 1 I I | |||
I I I | |||
1 I1 I1 1 1 1 1 I* I I 1 I IIlli I l II l I I I I I 0l3l l l l l l l I 1 1 | |||
= *oo , Ioo I IO ll .I , II I II I, 1I I I I I I I I I I I l l3 l I [ II II IIII l Il l lI I 1 1 1 I mI.._1111l1 I I lllll1 :11! l111 l1!. 1 l11l Iiii II ! II 11 11 lll ll l Il I ll HI I I I I , l l l l I , | |||
I I I I I" I l l II I l l~ll | |||
,I l li | |||
, , I l l l:l I | |||
l1 1 | |||
:l l l 67000,5.6 l | |||
1o 1 11 1111 1 Il liIljlIlIIIIIl l l ll II l l l Illl I l l I I Il l 4.0 L U' i41-- LI4l2 M - -L -- ~L- AJ-J L..L | |||
........... ... -- , I , ,. , I 0.0 l1000. l 2000.0 ll 000. 4000.08000.06000.07000. | |||
-L~l l l l l l l lI l l i l l Averag PlanalEpour MWIMTU)l o = a l l l l l l l l2l l l i t l l A ' I I I I l * . . Ca AVRAEPLNR INA HA GENERATION RAELMITlERSUtll o AERAE PANA EPOSRE..SIGL.LOP.OERAIO ATRIUMTMAOll FUELll l l owlll FIGURE 8.2-1ll l l l l l l lI I | |||
...... , , J2J*** | |||
..... . . . .. . .. .... .....*.. ....................... . ..... ..... ..... .......... ... * . .... .......... ... ... ................. ...... ................... ......... ....... . ..... . .. .. r*, i, . ... .. ... . .. ... .... .. . | |||
Rev. 16 PL-NF.-14-001 Rev. 2 Page 43 of 62 Main Turbine Bypass I EOC-RPT/I Backup Pressure Regulator Operable SUSQUEHANNA UNIT 1 TRM/3.2-44 UITTRM3.2-44 SUSQEHANA EFFECTIVE DATE 11/0412.015 | |||
9 SSES UNIT 1 CYCLE 19 3.6 I I I LEGEND m 3.4 4. a- CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM z INSERTION TIME z 3.2 + I 4-C CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME z | |||
3.0 t 1--i. | |||
m I II II . . I H0 4-. | |||
D.1 o~ | |||
2.8 2.6 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES L | |||
ARE OPERABLE PER SR 3.7.6.t AND 3.7.6.2 I I Ii USED INDETERMINING MFLCPR K | |||
0, 2.4 0 | |||
2.2 2.0 i'1 | |||
-m '.8 rI, | |||
==REFERENCE:== | ==REFERENCE:== | ||
" | " T.S. 3.4.1 and 3.2.21 108, 1.49' 1.6 H | ||
T.S. 3.4.1 and 3.2.21 | -m 0 '1.4 1N1 70 80 90 100 110 0 30 40 50 60 Total Core Flow (MLB/HR) | ||
~ I" | MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW Co MAIN TURBINE BYPASS 1 EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE SINGLE LOOP OPERATION (BOC to EOC) | ||
FIGURE 8.2-2 | |||
9 0 SSES UNIT I CYCLE 19 4.6 o0 4.4 ___ LEGEND 4.2 | |||
________CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM | |||
____INSERTION TIME z 4.0 ____________CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME | |||
~-CURVE C: CORE POWER _<26% AND coRE FLOW | |||
* 50 MLBM/HR 3.6 S 3.4 | |||
--fl!SAFETY ANALYSES ASSUME THAT F~OUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 3.2 Ho 03 3.0 _____USED IN DETERMINING MFLCPR 1. | |||
N) | |||
CD 0 2.8 0); | |||
0) 2.6 2.4 2.2 f 140. 2.08! | |||
,4 0A-B-BT* | |||
4 -.-------- ~ I "t100, ' | |||
2.0 F *, ... .. . .. . | |||
-Iil m | |||
t 1.8 0 REEEC: T.S. 3.4.1 and 3.2.2 "Z 1.6 Hr o 1.4 20 100 mn 2040 50co 60*( RAE70 80 90 "0 " | |||
MCPR OPERATING LIMIT VERSUS CORE POWER CD MAIN TURBINE BYPASS I EOC-RPT I BACKUP PRESSURE REGULATOR OPERABLE SINGLE LOOP OPERATION (BOC to EOC) | |||
FIGURE 8.2-3 °< I | |||
"* O 0)' C | |||
Rev. 16 PL-NF-14-OO1 Rev. 2 Page 46 of 62 Main Turbine Bypass Inoperable SUSQUEHANNA UNIT1 TRM/3.2-47 SUSQEHANA NITTR/3.-47 DATE 1110412015 EFFECTIVE | |||
C' SSES UNIT 1 CYCLE 19 4.2 I I II C- | |||
________ ________ LEGEND 4.0 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 3.8 - INSERTION TIME z | |||
z | |||
________________CURVE B: REALISTIC AVERAGE SCRAM iNSERTiON TIME 3.6 z | |||
3.4 | |||
- SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS - | |||
,4D 3.2 VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 o* 3.0 H0 0 | |||
CD co3 0) 2.4. | |||
2.2 m 2.0 "I1 m . | |||
1.8 -1 | |||
==REFERENCE:== | ==REFERENCE:== | ||
T.S. 3.4.1, 3.7.6,, and22 -- _,118 0 | |||
m 1.6 _ _ _ _ _I _ _ _-_-_-_ | |||
1.4 m | |||
30 40 50 60 Total Core 70 80 90 t00 110 Flow (MLB/HR) 0 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW CD Z | |||
-J. MAIN TURBINE BYPASS INOPERABLE SINGLE LOOP OPERATION (BOC to EOC) | |||
FIGURE 8,2-4 0 o)" | |||
C, SSES UNIT I CYCLE 19 4.2 123,4A41 * =* *l "1 I " m l C-Cin I LEGEND 4.0 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM F INSERTION TIME z 3.8 z CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME | |||
~, 3,61 ____________ 4-Z | |||
-I 3.6 CURVE C: CORE POWER_*26% AND CORE F~LOW _<50 MLBMIHR | |||
.t-l 3.4 I m | |||
.1.a 1I~Z~38 I--.*- 4. I-I E | |||
-I Cu 3.2 ISAFETY VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6,2 ANALYSES ASSUME THAT TWO OR MORE BYPASS w 3.0 USED IN DETERMINING MFLCPR I-0. | |||
1~oi C~) 0 | |||
.41 CD N) | |||
: a. 2.8 CO 0 ______ _ ________ 0) 2.6 2.4 2,2 m | |||
2.0 0r | |||
==REFERENCE:== | ==REFERENCE:== | ||
T.S. ,3.4.1, 3.7.6, and 3.2.2 .. | |||
-I 1.8 20 30 40 6060 Power (%o o70RATED) 80 90 100 50Core "0 "T CD MCPR OPERATING LIMIT VERSUS CORE POWER Com I N) MAIN TURBINE BYPASS INOPERABLE .CD SINGLE LOOP OPERATION (BOC to EOC) | |||
FIGURE 8,2-5 ow. | |||
: h. h< .- | |||
Rev. 16 PL-NF-14-O0l Rev. 2 Page 49 of 62 EOC-RPT Inoperable SUSQUEHANNA UNIT 1 TRM/3.2-50 SUSQEHANA NIT TR/3.-5OEFFECTIVE DATE 11/0412015 | |||
p SSES UNIT 1 CYCLE 19 4.0 LEGEND m 3.8 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM~ | |||
z 3.6 ________________INSERTION TIME z | |||
C CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.4 z | |||
3,2 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVESl E 3.0 - ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 | |||
,U | |||
-1 I-2,8 USED IN DETERMINING MFLCPR 4, | |||
0. | |||
2.6 0 | |||
N, 0I 2.4 0) 2.2 2.0 m 1.8 0 | |||
==REFERENCE:== | ==REFERENCE:== | ||
T.S 3..,.341 and 3.2.2 _ "_-_-_-[_08t" 1.6 1.4 m 30 40 50 60 70 80 9t0 100 110 Total Core Flow (MLB/HR) | |||
*, ,I-0 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW 4* EOC-RPT INOPERABLE -Q* .: | |||
SINGLE LOOP OPERATION (BOC to EOC) | |||
FIGURE 8.2-6 | |||
C* | |||
SSES UNIT 1 CYCLE 19 Cb 0* | |||
z | |||
.-I C.' | |||
CD C., | |||
N) | |||
C,' 0) | |||
'-I"1 | |||
['11 | |||
-IT m | |||
1-1 20 30 40 5060 Power' (% RATED) 70 80Core 80 90 100 m -U -D MCPR OPERATING LIMIT VERSUS CORE POWER Co z EOC-RPT INOPERABLE 0,- | |||
SINGLE LOOP OPERATION (BOC to EOC) ,C FIGURE 8.2-7 ow' 0 | |||
Rev. 15 PL-NF-14-OO1 Rev. 2 Page 52 of 62 Backup Pressure Regulator Inoperable SUSQUEHANNA UNIT 1 TRM/3.2-53 SUSQEHANA NITTRIS.-53 DATE 11/04/2016 EFFECTIVE | |||
I , " "SAFETY ANALYSES ASSUME THAT FOUR BYPASS | C', | ||
SSES UNIT I CYCLE 19 CO 4.0 I I I I m 3.8 | |||
*:MAXIMUM ALLOWABLE AVERAGE SCRAM z | |||
3.6 INSERTION TIME V | |||
I . | |||
C I: REALISTIC AVERAGE SCRAM INSERTION TIME z 3.4 4 4.- | |||
3.2 f , , .. ,I.,,.I,, I , " " | |||
S C | |||
3.0 2,8 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 USED IN DETERMINING MFLCPR 2 | |||
H* C) a. | |||
0 2,6 CD 0~ | |||
C, 2.4 2,2 2.0 r-n | |||
-n' rni 1.8 A- | |||
__---_ _ _ ___ __ B | |||
==REFERENCE:== | ==REFERENCE:== | ||
T.S. 3.4.1, 3.7.8, and 3.2.2[ ____.__ .. _. _ _ .J._108, 1.48 1.6 m | |||
1,4 30 40 50 60 70 80 90 100 110 Total Core Flow (MLBJHR) w r 0* | |||
MOPR OPERATING LIMIT VERSUS TOTAL CORE FLOW BACKUP PRESSURE REGULATOR INOPERABLE 01 SINGLE LOOP OPERATION (BOC to EGOC) | |||
FIGURE 8.2-8 0O" 0 | |||
' I * . ...... .... ....... ".............. ... ...... . ... . .. ... . . . ............ ...... .............. ......................... ................. ................. .. .. * .. . . =. . ... * " *LZ*:* I* *,.,. L*** ............ ..... | |||
CD SSES UNIT 1 CYCLE 19 C " 'I-0* | |||
C 4.4 ---- LEGEND m UM ALLOWABLE AVERAGE SCRAM | |||
-i- 4.2 CURVE A: MAXIM z ____ | |||
___ ___INSERi nION TIME z | |||
C 4.0 CURVE B: REALI* | |||
STIC AVERAGE SCRAM INSERTION TiME 3._____,_.__1CURVE C: CORE POWER < 26% AND CORE FLOW < 60 MLBMIHR I | |||
I I rY ANALYSES ASSUME THAT FOUR BYPASS VALVES l--- | |||
ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 3.0 26.01, 2.90 E | |||
USED IN DETERMINING MFLCPR CD 0.= 2.6 A *1* | |||
0) | |||
O- 60, 2.18 U* 4 4 1100 " | |||
2.2 1 m | |||
2.0 m | |||
1.8 | |||
==REFERENCE:== | ==REFERENCE:== | ||
T.S. 3.4.1, 3.7.8, and 3.2.2J11ii 1.4 | |||
.-I 20 30 40 60 ... ... 60 ... .. .. 70 80 90 100 m uore r'ower rio KAIi )uJ MCPR OPERATING LIMIT VERSUS CORE POWER CD J\) BACKUP PRESSURE REGULATOR INOPERABLE "11 0J SINGLE LOOP OPERATION (BOO to EOC) | |||
FIGURE 8.2-9 (:I' .Q DO O-- | |||
Rev. 16 PL-NF-14-001 Rev. 2 Page 55 of 62 One TSV or TCV CloSed SUSQUEHANNA UNIT 1 TRM/3.2-56 NITTR/3.-56 DATE 11/04/2015 EFFECTIVE SUSQEHANA | |||
Rev. | |||
S SSES UNIT 1 CYCLE 19 3,6 0o C | |||
6.01, 2.40_____ | -i- 3.4 z | ||
_________ | z 3.2 z | ||
- | 3.0 2.8 E | ||
.... .......... | 0. | ||
........ | 2.6 | ||
T .. .. ............. | -*1 2.4 k* *0 0-C, 2.2 2.0 rri "11 1.8 m | ||
.... ...... ... ... .... -:-.! .. ... .= | 1.6 m | ||
Rev. 16 PL-NF-14-OO1 Rev. | 1.4 r'ri 110 30 40 50 60 70 80 90 100 Total Core Flow (MLB/HR) | ||
SUSQUEHANNA | C 0* MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW o ,-n ONE TSV OR TCV CLOSED* | ||
" | cj SINGLE LOOP OPERATION (BOC to EOC) | ||
FIGURE 8.2-10 o~ | |||
1'r%-h* | |||
* Operation with one TSV or TCV closed is only supported at power levels -<75% rated power. | |||
0 oi) | |||
SSES UNIT 1 CYCLE 19 4.6I I I I 4.4 LEGEND m | |||
4.2 ______ CURVE *: MAXIMUM ALLOWABLE AVERAGE SCRAM z INSERTION TIME z 4.0 CURVE E3: REALISTIC AVERAGE SCRAM INSERTION TIME C | |||
z 23 .61 23,3.7 CURVE c.: CORE POWER < 26% AND CORE FLOW < 50 MLBM/HR 3.6 | |||
"* 26, 3.56-" | |||
C......SAFETY ANALYSES ASSUMEtt THAT FOUR BYPASS VALVES t 3.4 26,C 3.33 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 3.2 | |||
-- ___________USED IN DETERMINING MFLCPR 3.0 C,i CJ1 2.8 CD 0) 2.6 | |||
___ _ _ __ _ _ _ __ _ _ _ _6,19 2.4 2.2 _________ 6.01, 2.40_____ _________ - 519 2.0 n | |||
1.8 1.6 m | |||
1.4 20 30 40 50 60 70 80 Core Power (%RATED) | |||
-0 7ci MCPR OPERATING LIMIT VERSUS CORE POWER w"I-ONE TSV OR TCV CLOSED 01 SINGLE LOOP OPERATION (BOC to EOC) | |||
FIGURE 8.2-11 0)' | |||
* i jq L. . ... *....... . . ..... . ... . . .......... . . .. .......... ........ T.. .. ............. .... ...... * * * * * ... ... .... -:-.! | |||
.. ... .= | |||
Rev. 16 PL-NF-14-OO1 Rev. 2 Page 58 of 62 9.0 POWERI/FLOW MAP 9.1 Technical Specification Reference Technical Specification 3.3.1.1 9.2 Description Monitor reactor conditions to maintain THERMAL POWER / core flow outside of Stability Regions I and II of the Power/IFlow map, Figure 9.1. | |||
Ifthe 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 perT"S 3.3.1.1, Region I of the Power! | |||
Flow map is considered an immediate sca region. | |||
Region Ilof the Power!/Flow map is considered an immediate exit region regardless of the operability of the OPRM Instrumentation. | |||
SUSQUEHANNA UNIT1 TRM/3.2-59 SUSQEHANA NITTR/3.-59 DATE 11104/2015 EFFECTIVE | |||
Rev. 16 PL-NF-14-O01 Rev. 2 Page 59 of 62 120 | |||
==Purpose:== | |||
* 120 110* | |||
InitialI/Date: " I 1100 100 9o. 90 80 70 L. | |||
60 0 | |||
fi-50 40 If 30 201 10 | |||
-H-I-I-4--]l- 0*- | |||
0 10 20 30 40 50 50 70 80 90 100 110 Total Core Flow (Mlbmlhr) | |||
(for SLO <75% Pump Speed Use Form GO-100-009-2) | (for SLO <75% Pump Speed Use Form GO-100-009-2) | ||
Figure 9.1 SSES Unit 1 Cycle 19 Power/IFlow Map SUSQUEHANNA UNIT 1 TRM/3.2-60 SUSQEHANA NITTR/3.-60 DATE 11104/2015 EFFECTIVE | |||
Rev. 16 PL-NF-14-001 Rev. 2 Page 60 of 62 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 fisted below: | |||
SF = 1.11 Np = 15 Fp = 60OMlbm /hr SUSQUEHANNA UNIT ! TRM/3.2-61 UNT SUSQEHANA DATE 11/04/20 15 I RM/32-61EFFECTIVE | |||
Rev. 16 PL-NF-14-001 Rev. 2 Page 61 of 82 | |||
==11.0 REFERENCES== | ==11.0 REFERENCES== | ||
11.1 The analytical methods used to determine the core operating limits shall be | 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), | : 1. XN-NF-81-58(P)(A), Revision 2 and Supplements I and 2, "RQDEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model," Exxon Nuclear Company, March 1984. | ||
Revision 2 and Supplements I and 2, "RQDEX2 Fuel | : 2. EMF-2361 (P)(A), Revision 0, "EXEM BWR-2000 ECCS Evaluation Model," | ||
Revision 0, "ATRlUMW-10: | Framatome ANP, May 2001. | ||
Appendix K Spray Heat | : 3. EMF-2292(P)(A), Revision 0, "ATRlUMW-10: Appendix K Spray Heat Transfer Coefficients," Siemens Power Corporation, September 2000. | ||
Siemens Power Corporation, September 2000.4. XN-NF-84-105(P)(A), | : 4. XN-NF-84-105(P)(A), Volume 1 and Volume I Supplements 1 and 2, lJXCOBRA-T: A Computer Code for BWR Transient Thermal-Hydraulic Core Analysis," Exxon Nuclear Company, February 1987. | ||
Volume 1 and Volume I Supplements 1 and 2,lJXCOBRA-T: | : 5. XN-NF-80-19(P)(A), Volume 1 and Supplements I and 2, "Exxon Nuclear Methodology for Boiling Water Reactors: Neutronic Methods for Design and Analysis," Exxon Nuclear Company, March 1983. | ||
A Computer Code for BWR Transient Thermal-Hydraulic | : 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, t' Exxon Nuclear Company, September 1982. | ||
Exxon Nuclear Company, February 1987.5. XN-NF-80-19(P)(A), | : 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. | ||
Volume 1 and Supplements I and 2, "Exxon | : 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. | ||
Neutronic Methods for Design | : 9. XN-NF-85-67(P)(A), Revision 1, "Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel," Exxon Nuclear Company, Inc., | ||
Exxon Nuclear Company, March 1983.6. XN-NF-80-19(P)(A), | September 1986. | ||
Volumes 2, 2A, 2B, and 2C "Exxon Nuclear Methodology for Boiling Water Reactors: | : 10. ANF-524(P)(A), Revision 2 and Supplements 1 and 2, "Advanced Nuclear Fuels Corporation Critical Power Methodology for Boiling Water Reactors1 " | ||
EXEM BWR ECCS Evaluation Model,t' | November 1990. | ||
Volume 3 Revision 2 "Exxon Nuclear Methodology | : 11. NE-092-001A, Revision 1, "Licensing Topical Report for Power Uprate With increased Core Flow," Pennsylvania Power & Light Company, December 1992 and NRC SER (November 30, 1993). | ||
Thermal Limits Methodology | : 12. ANF-89-98(P)(A) Revision 1 and Supplement 1, "Generic Mechanical Design Criteria for BWR Fuel Designs," Advanced Nuclear Fuels Corporation, May 1995. | ||
Exxon Nuclear Company, January 1987.8. XN-NF-80-1 9(P)(A), | SUSQUEHANNA UNiT1 TRM/3.2-62 EFFECTIVE DATE 11/04/2015 | ||
Volume 4, Revision 1, "Exxon Nuclear Methodology | |||
Application of the ENC Methodology to | Rev. 16 PL-NF-14-001 Rev. 2 Page 62 of 62 | ||
Exxon Nuclear Company, June 1986.9. XN-NF-85-67(P)(A), | : 13. EMF-22O9(P)(A), Revision 3, "SPCB Critical Power Correlation," AREVA NP, September 2009. | ||
Revision 1, "Generic Mechanical Design for | : 14. EMF-85-74(P)(A), Revision 0, Supplement 1(P)(A) and Supplement 2(P)(A), | ||
Revision 2 and Supplements 1 and 2, "Advanced | "RQDEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model," | ||
Revision 1 and Supplement 1, "Generic Mechanical | Siemens Power Corporation, February 1998. | ||
Advanced Nuclear Fuels Corporation, | : 15. EMF-2168(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. | ||
Revision 3, "SPCB Critical Power Correlation," | : 16. EMF-CC-074(P)(A), Volume 4, Revision 0, "BWR Stability Analysis - | ||
AREVA NP,September 2009.14. EMF-85-74(P)(A), | Assessment of STAiF with Input from MICROBURN-B2," Siemens Power Corporation, August 2000. | ||
Revision 0, Supplement 1(P)(A) and Supplement 2(P)(A),"RQDEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model,"Siemens Power Corporation, February 1998.15. EMF-2168(P)(A), | : 17. NEDO-32465-A, "BWROG Reactor Core Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications," August 1996. | ||
Revision 0, "Siemens Power Corporation Methodology | : 18. ANF-913(P)(A), Volume t Revision I and Volume I Supplements 2, 3, and 4, "COTRANSA2: A Computer Program for Boiling Water Reactor Transient Analyses," Advanced Nuclear Fuels Corporation, August 1990. | ||
Evaluation and Validation of CASMO-4/Microburn-B2," Siemens Power Corporation, October 1999.16. EMF-CC-074(P)(A), | : 19. ANF-1 358(P)(A), Revision 3, "The Loss of Feedwater Heating Transient in Boiling Water Reactors," Framatome ANP, September 2005. | ||
Volume 4, Revision 0, "BWR Stability Analysis | SUSQUEHANNA UNIT1 TRM/3.2-63 SUSQEHANA EFFECTIVE NITTR/3.-63 DATE 11/04/2015 | ||
Siemens | Main Turbine Overspeed Protection System Rev. 2 3.3.7 3.3 Instrumentation 3.3.7 Main Turbine Overspeed Protection System TRO 3.3.7 One Main Turbine Overspeed Protection System shall be OPERABLE. | ||
APPLICABILITY: MODES I and 2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Two of eight stop valves A.1.1 Close one of the inoperable 72 hours and control valves valves. | |||
Volume t Revision I and Volume I Supplements 2, 3, and 4,"COTRANSA2: | inoperable. | ||
A Computer Program for Boiling Water Reactor Transient Analyses," | AND A.1 .2 Limit THERMAL POWER 12 hours following | ||
Advanced Nuclear Fuels Corporation, August 1990.19. ANF-1 358(P)(A), | < 75% RTP. closure of the inoperable valve AND A.1.3 Apply the following limits for a 12 hours following closed Turbine Stop Valve or closure of the Turbine Control Valve as inoperable valve specified in the COLR: | ||
Revision 3, "The Loss of Feedwater Heating Transient | : a. LCO 3.2.2, 'MINIMUM CRITICAL POWER RATIO (MCPR)," | ||
Framatome ANP, September 2005.SUSQUEHANNA | : b. LCO 3.2.3, 'LINEAR HEAT GENERATION RATE (LHGR)." | ||
APPLICABILITY: | OR A.2 Isolate main turbine from the 72 hours steam supply. | ||
MODES I and | (continued) | ||
SUSQUEHANNA-UNIT1 TRM / 3.3-17 SUSQEHANA-UITITRM 3.-17EFFECTIVE DATE 11/04/2015 | |||
< 75% RTP. closure of | |||
SUSQUEHANNA-UNIT1 TRM / 3.3- | Main Turbine Overspeed Protection System Rev. 2 3.3.7 ACTIONS (continued) | ||
CONDITION REQUIRED ACTION COMPLETION | CONDITION REQUIRED ACTION COMPLETION TIME B. Two of twelve intercept B.1 Close either the intercept 72 hours valves and intermediate valve or the intermediate stop stop valves inoperable, valve within one of the affected combined intermediate valves. | ||
-UNI I RM | OR 8.2 Isolate main turbine from the 72 hours steam supply. | ||
------------- | C. Turbine Overspeed C.1 Isolate main turbine from the 6 hours Protection System steam supply. | ||
~NOTE---- | inoperable for reasons other than Condition A or B. | ||
--------When a channel is placed in an inoperable status solely for performance of | SUSQUEHANNA-UNIT1 TRM / 3.3-17a SUSQEHANA | ||
SURVEILLANCE FREQUENCY | -UNI I RM DATE 11/04/2015 I3.317aEFFECTIVE | ||
--NOTE--..........----...... | |||
The provisions of TRS 3.0.4 are not applicable TRS 3.3.7.1 Cycle each high pressure turbine control valve from the 92 | Main Turbine Overspeed Protection System Rev. 2 3.3.7 TECHNICAL REQUIREMENT SURVEILLANCE | ||
The provisions of TRS 3.0.4 are not applicable TRS 3.3.7.2 Cycle each low pressure turbine combined intermediate 92 | ------------- ~NOTE---- -------- | ||
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 up to 6 hours provided the redundant overspeed trip device is OPERABLE. | |||
SURVEILLANCE FREQUENCY | |||
-- NOTE--..........----...... | |||
The provisions of TRS 3.0.4 are not applicable TRS 3.3.7.1 Cycle each high pressure turbine control valve from the 92 days running position and observe valve closure. | |||
-- -- NOTE--............................... | |||
The provisions of TRS 3.0.4 are not applicable TRS 3.3.7.2 Cycle each low pressure turbine combined intermediate 92 days valve from the running position and observe valve closure. | |||
NOTE---------------------..... | NOTE---------------------..... | ||
The provisions of TRS 3.0.4 are not applicable TRS 3.3.7.3 Cycle each high pressure turbine stop valves from the 92 | The provisions of TRS 3.0.4 are not applicable TRS 3.3.7.3 Cycle each high pressure turbine stop valves from the 92 days running position and observe valve closure. | ||
TRS 3.3.7.5 Disassemble one of each type valve identified in 40 months on | TRS 3.3.7.4 Perform a CHANNEL CALIBRATION of main turbine 24 months overspeed protection instrumentation. | ||
SUSQUEHANNA-UNIT1 TRM / 3.3- | TRS 3.3.7.5 Disassemble one of each type valve identified in 40 months on a TRS 3.3.7.1, TRS 3.3.7.2, and TRS 3.3.7.3, perform a STAGGERED TEST visual and surface inspection of valve seats, disks and BASIS stems and verify no unacceptable flaws or corrosion. | ||
Either device, when initiated, will close the main stop valves, | SUSQUEHANNA-UNIT1 TRM / 3.3-18 SUSQEHANA UNT I RM3.-18EFFECTIVE DATE 10/31/2007 | ||
Main Turbine Overspeed Protection System (MTOPS) OPERABILITY is | |||
Note that for this statement to | Main Turbine Overspeed Protection System Rev. 2 B 3.3.7 B 3.3.7 Main Turbine Overspeed Protection System BASES TRO The Main Turbine Overspeed Protection System is designed to protect the main turbine from excessive overspeed by initiating a turbine trip by fast closure of the turbine control valves and closure of the intercept valves to essentially secure all steam flow to the turbine (Ref. 1). | ||
Failure of only one valve in a | To protect the turbine generator from overspeed conditions, two trip devices are provided. Either device, when initiated, will close the main stop valves, control valves, and combined intermediate valves thus isolating the turbine (Ref. 2). | ||
These two trip devices are as follows: | |||
SUSQUEHANNA | *A mechanical overspeed trip which is initiated ifthe turbine speed reaches approximately 10% above rated speed, and o An electrical overspeed trip which serves as a backup to the mechanical trip and is initiated at approximately 12% above rated speed. | ||
-UNIT | OPERABILITY of at least I of the 2 overspeed protection systems is required for the Turbine Overspeed Protection System to be considered OPERABLE. | ||
-UNI I TM / | Main Turbine Overspeed Protection System (MTOPS) OPERABILITY is also based upon the ability of the valves that control steam flow to the turbine to close following the receipt of a closure signal. The 4 stop valves, 4 control valves, 6 intermediate stop valves, and 6 intercept valves make up a system of 20 valves. A single failure to any one of the above system of 20 valves will not prevent a turbine trip (Ref. 2). Hence, if 19 of the 20 noted valves are OPERABLE, the MTOPS is OPERABLE. Note that for this statement to be true, the intermediate stop valves and intercept valves are considered separate valves. Overspeed protection is only disabled on a CIV failure if both valves within a CIV are inoperable. Failure of only one valve in a CIV does not prevent an overspeed trip, and does not affect operability. Actions to close one inoperable valve if two valves are inoperable maintain the unit within the analysis in Ref. 2. However, redundancy is reduced and repairs should be completed in accordance with the corrective action program. | ||
ACTIONS The Actions are defined to ensure proper corrective measures are taken | Excessive turbine overspeed could generate potentially damaging missiles that could present a personnel and equipment hazard. MTOPS is not necessary to provide adequate protection of the public health and safety and is not required to obviate the possibility of an abnormal situation or event giving rise to an immediate threat to the public health and safety. | ||
A.1.l, A.1.2, A.1.3 and A. | (continued) | ||
The 72-hour Completion Time provides a reasonable time | SUSQUEHANNA - UNIT 1 TRM / B 3.3-14 SUSQEHANA | ||
The required action | -UNI I TM | ||
If the MCPR and LHGR limits are not | /BDATE 3.-14EFFECTIVE 06/25/2002 | ||
This time is provided to stabilize operation with a closed Turbine Stop | |||
The 72-hour Completion Time provides | Main Turbine Overspeed Protection System Rev. 2 B 3.3.7 B 3.3.7 Main Turbine Overspeed Protection System BASES (continued) | ||
SUSQUEHANNA-UNIT1 TRM / B 3.3- | ACTIONS The Actions are defined to ensure proper corrective measures are taken in response to the inoperable components. | ||
If the MTOPS is inoperable for reasons other than conditions A or B, | A.1.l, A.1.2, A.1.3 and A.2 If two of eight stop valves and control valves are inoperable, action must be taken to restore at least one of the valves to OPERABLE status in 72 hours. | ||
The TRSs are modified by a Note to indicate that when a channel is placed | This action ensures steam isolation to the turbine in the event of an overspeed condition, and maintains the unit within the bounds of the FSAR analysis. The 72-hour Completion Time provides a reasonable time to troubleshoot the problem, make repairs, and reduce power in an orderly manner if required without challenging plant systems. The required action if the problem is not resolved is to close one of the inoperable valves, or to isolate the main turbine from the steam supply. If one of the inoperable valves is closed, then limit thermal power to less than or equal to 75% of rated power, and apply Minimum Critical Power Ratio (MCPR) and Linear Heat Generation Rate (LHGR) limits as specified in the COLR within 12 hours. Restricting thermal power to less than or equal to 75% of rated power eliminates possible shock loads to the turbine blades that could occur from a non-uniform circumferential steam flow distribution entering the HP turbine for this configuration. If the MCPR and LHGR limits are not in compliance with the applicable requirements at the end of this period, the ACTIONS required by the applicable specifications must be implemented. | ||
This time is provided to stabilize operation with a closed Turbine Stop Valve or Turbine Control Valve. | |||
The 6 hour testing allowance | B.1 and B.2 If two of twelve intercept valves and intermediate stop valves are inoperable, action must be taken to restore at least one of these valves to OPERABLE status in 72 hours. This action ensures steam isolation to the turbine in the event of an overspeed condition. The 72-hour Completion Time provides a reasonable time to troubleshoot the problem, make repairs, and reduce power in an orderly manner ifrequired without challenging plant systems. | ||
TRS 3.3.7.1, TRS 3.3.7.2, and TRS 3.3.7. | The required action ifthe problem is not resolved is to close either the intercept valve or the intermediate stop valve within one of the affected combined intermediate valves, or to isolate the main turbine from the steam supply. | ||
and four high | (continued) | ||
The 92 | SUSQUEHANNA-UNIT1 TRM / B 3.3-14a SUSQEHANA-NITI TR | ||
SUSQUEHANNA | / 3.314aEFFECTIVE DATE 11/04/2015 | ||
-UNIT | |||
This TRS is for the performance of a CHANNEL CALIBRATION of | Main Turbine Overspeed Protection System Rev. 2 B 3.3.7 B 3.3.7 Main Turbine Overspeed Protection System BASES ACTIONS C.1 (continued) | ||
The calibration is a complete check of the instrument channel from the sensing device | If the MTOPS is inoperable for reasons other than conditions A or B, then action must be taken to isolate the main turbine from the steam supply. | ||
The Frequency of 24 months is a typical refueling cycle and considers channel reliability. | 6 hours allows a reasonable amount of time to complete the plant shutdown associated with isolating the main turbine from the steam supply. | ||
TRS 3.3.7. | TRS The TRSs are performed at the specified Frequency to ensure that the turbine overspeed protection function is maintained OPERABLE. | ||
is required to | The TRSs are modified by a Note to indicate that 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 hours provided the redundant overspeed trip device is OPERABLE. Upon completion of the Surveillance, or expiration of the 6 hour allowance, the channel must be returned to OPERABLE status or the applicable Condition entered and Required Actions taken. This Note is based on the average time required to perform channel Surveillance. The 6 hour testing allowance does not significantly reduce the probability that the Main Turbine Overspeed Protection System will function when necessary. | ||
REFERENCES | TRS 3.3.7.1, TRS 3.3.7.2, and TRS 3.3.7.3 Verification of the movement of each of the four high pressure turbine control valves, six low pressure turbine combined intermediate valves (composed of 6 intermediate stop valves and 6 intercept valves), and four high pressure turbine stop valves ensures the OPERABILITY of each valve and that it will be able to close in the event of a turbine trip condition. The 92 day Frequency is based upon current surveillance practice as recommended by the turbine vendor and described in the FSAR (Ref. 3). | ||
(continued) | |||
SUSQUEHANNA - UNIT 1 TRM / B 3.3-14b SUSQEHANA-NIT TRM/ | |||
B3.314bEFFECTIVE DATE 11/04/2015 | |||
Main Turbine Overspeed Protection System Rev. 2 B 3.3.7 B 3.3.7 Main Turbine Overspeed Protection System BASES TRS TRS 3.3.7.4 (continued) | |||
This TRS is for the performance of a CHANNEL CALIBRATION of the required main turbine overspeed protection instrumentation. The calibration is a complete check of the instrument channel from the sensing device to main turbine trip initiation. The Frequency of 24 months is a typical refueling cycle and considers channel reliability. | |||
TRS 3.3.7.5 The disassembly and inspection of the valves referenced ensures that abnormal wear is not occurring which could result in the valves inability to close upon receipt of a close signal. The Frequency is such that only one of each type valve (i.e., high pressure turbine stop; high pressure turbine control; and low pressure turbine combined intermediate), is required to be inspected within a 40 month period. If unacceptable flaws or excessive corrosion are found in a valve, all valves of its type are inspected (Ref. 3). | |||
Valve bushings are inspected and cleaned, and bore diameters are checked for proper clearance. | |||
REFERENCES 1. FSAR Section 7.7:1.5 | |||
: 2. FSAR Section 10.2.2.6. | |||
: 3. FSAR Section 10.2.3.6. | : 3. FSAR Section 10.2.3.6. | ||
SUSQUEHANNA-UNIT1 TRM / B 3.3- | SUSQUEHANNA-UNIT1 TRM / B 3.3-14c SUSQEHANA | ||
-UNITI TR / 3.314cEFFECTIVE DATE 11/04/2015}} | -UNITI TR | ||
/ 3.314cEFFECTIVE DATE 11/04/2015}} | |||
Latest revision as of 08:21, 5 February 2020
| ML15329A166 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 11/11/2015 |
| From: | Gerlach R Susquehanna |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML15329A166 (97) | |
Text
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USE AND APPLICATION DEFINITIONS TEXT 2.1 2 04/28/2015
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Title:
PLANT PROGRAMS AND SETPOINTS INSTRUMENT TRIP SETPOINT TABLE TEXT 3.0 5 03/05/2015
Title:
TECHNICAL REQUIREMENT FOR OPERATION (TRO) APPLICABILITY & SURVEILLANCE (TRS)
APPLICABILITY TEXT 3.1.1 1 11/09/2007
Title:
REACTIVITY CONTROL SYSTEMS ANTICIPATED TRANSIENT WITHOUT SCRAM ALTERNATE ROD INJECTION (ATWS-ARI) INSTRUMENTATION TEXT 3.1.2 0 11/18/2002
Title:
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Title:
REACTIVITY CONTROL SYSTEMS CONTROL ROD BLOCK INSTRUMENTATION TEXT 3.1.4 0 11/18/2002
Title:
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CHECK VALVE TEXT 3.2.1 16 11/10/2015
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CORE OPERATING LIMITS REPORT (COLR)
Report Date: 11/11/15 Pagel Page ! of of i~
16 Report Date: 11/11/15
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Title:
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Title:
INSTRUMENTATION MAIN TURBINE OVERSPEED PROTECTION SYSTEM TEXT 3.3.8 1 10/22/2003
Title:
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Title:
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Title:
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Title:
WATER MONITORING INSTRUMENTATION Report Date: 11/11/15 Page 2 of of 16 I__66 Report Date: 11/11/15
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TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.4.1 1 04/26/2006
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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 HIGH/LOW PRESSURE INTERFACE LEAKAGE MONITORS TEXT 3.4.4 2 04/17/2008
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 3.4.6 2 04/25/2013
Title:
REACTOR RECIRCULATION SINGLE LOOP OPERATION SLO FLOW RATE RESTRICTION TEXT 3.5.1 1 02/04/2005
Title:
EMERGENCY CORE COOLING AND RCIC ADS MANUAL INHIBIT TEXT 3.5.2 1 11/09/2007
Title:
EMERGENCY CORE COOLING AND RCIC ECCS AND RCIC SYSTEM MONITORING INSTRUMENTATION TEXT 3.5.3 0 11/18/2002
Title:
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Title:
CONTAINMENT VENTING OR PURGING TEXT 3.6.2 2 04/29/2014
Title:
SUPPRESSION CHAMBER TO DRYWELL VACUUM BREAKER POSITION INDICATION TEXT 3.6.3 0 11/18/2002
Title:
CONTAINMENT SUPPRESSION POOL ALARM INSTRUMENTATION Report Date: 11/11/15 Page Page~* of of 16 i_*6 Report Date: 11/11/15
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TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.6.4 0 11/18/2002 Titles CONTAINMENT PRIMARY CONTAINMENT CLOSED SYSTEM BOUNDARIES TEXT 3.7.1 0 11/18/2002
Title:
PLANT SYSTEMS EMERGENCY SERVICE WATER SYSTEM (ESW) SHUTDOWN TEXT 3.7.2 0 11/18/2002
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 10 09/27/2012
Title:
. PLANT SYSTEMS FIRE DETECTION INSTRUMENTATION TEXT 3.7.4 1 04/26/2006
Title:
PLANT SYSTEMS SOLID RADWASTE SYSTEM Report Date: 11/11/15 Page Page A4 of of 16 16
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Title:
PLANT SYSTEMS LIQUID HOLDUP TANKS TEXT 3.7.6 3 06/04/2012
Title:
PLANT SYSTEMS ESSW PUMPHOUSE VENTILATION TEXT 3.7.7 2 09/05/2008 Titles PLANT SYSTEMS MAIM CONDENSER 0FFGAS PRETREATMENT LOGARITHMIC RADIATION MONITORING TEXT 3.7.8 5 03/05/2015
Title:
PLANT SYSTEMS SNUBBERS TEXT 3.7.9 2 01/31/2014
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PLANT SYSTEMS CONTROL STRUCTURE HVAC TEXT 3.7.10 1 12/14/2004
Title:
PLANT SYSTEMS SPENT FUEL STORAGE POOLS (SFSPS)
TEXT 3.7o11 0 04/16/2009
Title:
STRUCTURAL INTEGRITY TEXT 3.8.1 2 04/05/2010
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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 PROTECTI( ON -.
CONTINUOUS TEXT 3.8.2.2 2 12/14/2004
Title:
ELECTRICAL POWER MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTICON -
AUTOMATIC Report Date: 11/11/15 Page 5 Page of of 16 16 Report Date: 11/11/15
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Title:
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Title:
BATTERY MAINTENANCE AND MONITORING PROGRALM TEXT 3.9.1 0 11/18/2002
Title:
REFUELING OPERATIONS DECAY TIME TEXT 3.9.2 0 11/18/2002
Title:
REFUELING OPERATIONS COMMUNICATIONS TEXT 3.9.3 0 11/18/2002
Title:
REFUELING OPERATIONS REFUELING PLATFORM TEXT 3.10.1 1 04/26/2006
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MISCELLANEOUS SEAL SOURCE CONTAMINATION TEXT 3.10.2 2 08/08/2006
Title:
MISCELLANEOUS SHUTDOWN MARGIN TEST RPS INSTRUMENTATION TEXT 3.10.3 2 06/15/2010
Title:
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TEXT 3.10.4 2 04/17/2008
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Report Date: 11/11/15 Page *6 Page of of 16 16 Report Date: 11/11/15
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RADIOACTIVE EFFLUENTS RADIOACTIVE LIQUID PROCESS MONITORING INSTRUTMENTATION
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RADIOACTIVE EFFLUENTS DOSE - NOBLE GASES TEXT 3.11.2.3 1 04/26/2006
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Title:
LOADS CONTROL PROGRAM HEAVY LOADS REQUIREMENTS TEXT 3.12.3 0 11/19/2002 0
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Title:
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REACTIVITY CONTROL SYSTEMS BASES CONTROL ROD BLOCK INSTRUMENTATION TEXT B3.1.4 0 11/19/2002
Title:
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INSTRUMENTATION BASES TEN POST ACCIDENT MONITORING (PAM) INSTRUMENTATION
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INSTRUMENTATION BASES THIS PAGE INTENTIONALLY LEFT BLANK Page of 16 Report Date: 11/11/15
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Title:
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Title:
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Title:
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Title:
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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 TEXT B3.7.3.1 3 06/15/2010
Title:
PLANT SYSTEMS BASES FIRE SUPPRESSION WATER SUPPLY SYSTEM
- TEXT B3.7.3.2 2 04/26/2006 W.
Title:
PLANT SYSTEMS BASES SPRAY AND SPRINKLER SYSTEMS Page 1_1 of i__66 Report Date: 11/11/15
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- PLANT SYSTEMS BASES C02 SYSTEMS TEXT B3.7.3.4 3 04/29/2014
Title:
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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 TEXT B3.7.6 4 06/04/2013 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 Report Date: 11/11/15 Page 1/2 Page 12 of of 16 16 Report Date: 11/11/15
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Manual Name : TPR41 Manual
Title:
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Title:
PLANT SYSTEMS BASES SNUBBERS TEXT B3.7.9 2 12/08/2011 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 1 04/14/2010
Title:
STRUCTURAL INTEGRITY TEXT B3.8.1 2 03/10/2010
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:
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Title:
ELECTRICAL POWER BASES DEGRADED VOLTAGE PROTECTION TEXT B3.8.6 2 12/08/2011
Title:
ELECTRICAL POWER BASES EMERGENCY SWITCHGEAR ROOM COOLING TEXT B3.8.7 2 06/04/2013
Title:
BATTERY MAINTENANCE AND MONITORING PROGRAM Report Date: 11/11/15 Page i~
Page 13 of of ii 16 Report Date: 11/11/15
S.~ES MM~AL
<?=Manual Name: TRMI
"*Manual Titles° TECHNICAL REQUIREMENTS MANUAL UNIT 1 0 TEXT B3.9.l 0 11/19/2002
Title:
REFUELING OPERATIONS BASES DECAY TINE TEXT B3.9.2 0 11/19/2002
Title:
REFUELING OPERATIONS BASES COMM4UNICATIONS TEXT B3.9.3 0 11/19/2002
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 03/31/2006
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 B3.10.4 1 04/17/2 008
Title:
MISCELLANEOUS BASES LEADING EDGE FLOW METER (LEFM)
TEXT B3.ii.ioi 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES LIQUID EFFLUENTS CONCENTRATION TEXT B3ol.11Io2 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES LIQUID EFFLUENTS DOSE TEXT B3.ii.i.3 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES LIQUID WASTE TREATMENT SYSTEM TEXT B3.11.I.4 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES LIQUID RADWASTE EFFLUENT MONITORING INSTRUMENTATION TEXT B3.11.I.5 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES RADIOACTIVE LIQUID PROCESS MONITORING INSTRUMENTATION Report Date: 11/11/15 Page 14 Page 14 of of ~i* Report Date: 11/11/15
SSES MANUJAI O Manual Name: TRMI
... Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 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 - NOBLE GASES TEXT B3.11.2.3 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES DOSE - IODINE, TRITIUM, AND RADIONUCLIDES IN SPARTICULATES FORM TEXT B3.11.2.4 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES GASEOUS RADWASTE TREATMENT SYSTEM TEXT B3.11.2.5 5 07/03/2013
Title:
RADIOACTIVE EFFLUENTS BASES VENTILATION EXHqAUST 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 5 03/05/2015
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 TEXT B3.12.2 1 12/03/2010
Title:
LOADS CONTROL PROGRAM BASES HEAVY LOADS REQUIREMENTS Report Date: 11/11/15 Page i~.
15 of of 16 I__66 Report Date: 11/11/15
SSES MANUJAL
- - Manual Name: TRN1
- Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.12.3 0. 11/19/2002
Title:
LOADS CONTROL PROGRAM BASES LIGHT LOADS REQUIREMENTS Report Date: 11/11/15 Page 1616 of of 16 16 Report Date: 11/11/15
SUSQUEHANNA STEAM ELECTRIC STATION Rev. 64 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Titl__ee Effective Date TOC TABLE OF CONTENTS 04/23/2015 1.0 USE AND APPLICATION Page TRM / 1.0-1 10/04/2002 Page TRM / 1.0-2 01/21/2014 Page TRM / 1.0-3 10/04/2002 2.0 PLANT PROGRAMS Page TRM / 2.0-1 04/23/2015 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 01/21/2014 Page TRM / 2.0-6 03/27/2008 Page TRM / 2.0-7 05/15/2008 Pages TRM / 2.0-8 and TRM / 2.0-9 01/07/2011 Page TRM / 2.0-10 02/02/2010 Page TRM / 2.0-11 11/15/2004 Page TRM / 2.0- 12 03/27/2008 Pages TRM / 2.0-13 and TRM / 2.0-1* 11/15/2004 Page TRM / 2.0-15 11/15/2005 3.0 PI"I"LI*.jp?.DILI I I Pages TRM / 3.0-1 and 02/19/2015 Page TRM / 3.0-3 03/15/2002 Page TRM / 3.0-4 02/19/2015 REACTIVITY CON 3.1 Page TRM / 3.* 10/3112007 Pages TRM an 08/31/1998 Pages 3. 5 08/31/1998 Page TR 03/22/2006 04/07/2009 03/27/2008 3.1-9 and TRM / 3.1,9a 02/18/1999
.1-10 02/18/1999 3.2 iERATING LIMITS REPORT 07/07/1999 Pages TRM / 3.2-2 through TRM / 3.2-63 11/04/2015 3.3 INSTRUMENTATION Pages TRM / 3.3-1 through TRM / 3.3-3 07/16/1999 Page TRM / 3.3-4 and TRM / 3.3-5 10/31/2007 Page TRM / 3.3-6 03/10/2011 SUSQUEHANNA-UNIT1 TRM / LOES-1 SUSQEHANA UNT I RM LOS-1EFFECTIVE DATE 11/04/2015
SUSQUEHANNA STEAM ELECTRIC STATION Rev. 84 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date Page TRM / 3.3-7 10/31/2007 Page TRM / 3.3-8 08/31/1998 Page TRM / 3.3-9 10/07/2015 Page T'RM / 3.3-9a 06/30/2010 Page TRM / 3.3-10 10/31/2007 Page TRM /3.3-11 10/07/2015 Page TRM / 3.3-11a 10/07/2015 Page TRM I 3.3-12 03/30/2001 Page TRM / 3.3-13 01/07/2011 Page TRM / 3.3-14 12/1 4/1 998 Page TRM / 3.3-15, 04/11/2014 Page TRM I 3.3-16 01/07/2011 Page TRM / 3.3-17 11/04/2015 Page TRM / 3.3-17a 11/04/2015 Page TRM / 3.3-18 10/31/2007 Pages TRM / 3.3-19 through TRM / 3.3-21 10/22/2003 Page TRM / 3.3-22 03/27/2008 Page TRM / 3.3-22a 11/15/2004 Pages TRM / 3.3-22b through TRM / 3.3-22d 03/22/2006 Page TRM / 3.3-23 12/03/2004 Pages TRM / 3.3-24 and TRM I 3.3-25 05/16/2003 Page, TRM / 3.3-26 10/22/2003 Page TRM / 3.3-27 02/19/2015 Page TRM / 3.3-28 04/07/2009 3.4 REACTOR COOLANT SYSTEM Page TRM / 3.4-1 03/31/2006 Pages TRM / 3.4-2 through TRM / 3.4-5 10/23/11998 Pages TRM / 3.4-6 through TRM / 3.4-8 04/01/2009 Page TRM / 3.4-9 08/31/1998 Page TRM / 3.4-10 10/31/2007 Page TRM / 3.4-11 08/31/1998 Page TRM / 3.4-12 03/27/2008 Page TRM / 3.4-13 03/31/2006 Pages TRM / 3.4-14 and TRM / 3.4-15 04/25/2013 3.5 EMERGENCY CORE COOLING AND RCIC Page TRM / 3.5-1 01/28/2005 Pages TRM / 3.5-2 and TRM / 3.5-3 08/31/1998 Pages TRM / 3.5-4 and TRM / 3.5-5 10/31/2007 Pages 3.5-6 and 3.5-7 08/31/1998 SUSQUEHANNA- UNIT 1 TRM / LOES-2 LOS-2EFFECTIVE I RM UNT SUSQEHANADATE 11/04/2015
SUSQUEHANNA STEAM ELECTRIC STATION Rev. 84 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date 3.6 CONTAI NMENT Page 3.6-1 08/31/1998 Pages TRM / 3.6-2 and TRM I 3.6-2a 04/16/2014 Page 3.6-3 08/31/1998 Page TRM / 3.6-4 01/07/2002 Page 3.6-5 08/31/1998 Pages TRM / 3.6-6 through TRM / 3.6-8 12/31/2002 3.7 PLANT SYSTEMS Pages 3.7-1 through 3.7-3 08/31/1998 Page TRM / 3.7-4 03/31/2006 Pages 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 12/29/1999 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 04/07/2 009 Page TRM / 3.7-24 03/31/2006 Page TRM / 3.7-25 08/02/1999 Page TRM / 3.7-26 09/25/2012 Page TRM / 3.7-27 11/24/2011 Pages TRM / 3.7-28 through TRM / 3.7-34a 09/25/2012 Page TRM / 3,7-35 03/31/2006 Pages TRM / 3.7-36 and TRM / 3.7-37 02/01/1999 Page TRM / 3.7-38 02/19/2015 Page TRM / 3.7-39 08/31/1998 Page TRM / 3.7-40 03/31/2006 Page TRM / 3.7-41 05/24/2012 Pages TRM / 3.7-41a through TRM / 3.7-41c 05/24/2012 Page TRM / 3.7-42 09/04/2008 Page TRM / 3.7-43 08/31/1998 Page TRM / 3.7-44 02/19/2015 Pages TRM / 3.7-45 and TRM / 3.7-46 10/05/2006 Page TRM / 3.7-47 06/07/2007 TRM / LOES-3 EFFECTIVE DATE 11/04/2015 SUSQUEHANNA-UNITI SUSQUEHANNA-UNIT1 TRM / LOES-3 EFFECTIVE DATE 11/04/2015
SUSQUEHANNA STEAM ELECTRIC STATION Rev. 84 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date Page 10/05/2006 Page TRM TRM II 3.7-48 3.7-49 06/07/2007 Pages TRM / 3.7-49a and TRM / 3.7-49b 10/05/2006 Page TRM / 3.7-50 01/21/2014 Page TRM / 3.7-51 08/16/2006 Page TRM / 3.7-52 12/03/2004 Page TRM / 3.7-53 04/15/2003 Page TRM / 3.7-54 07/29/1999 Pages TRM / 3.7-55 through TRM / 3.7-57 04/01/2009 3.8 ELECTRICAL POWER Page TRM / 3.8-1 04/02/2002 Page TRM / 3.8-2 01/28/2005 Pages TRM / 3.8-3 and TRM /3.8-4 03/25/2010 Pages TRM / 3.8-5 and TRM / 3.8-6 04/02/2002 Page TRM / 3.8-7 10/31/2007 Pages TRM / 3.8-8 through TRM / 3.8-10 12/03/2004 Page TRM /3.8-11 09/03/2004 Page TRM / 3.8-12 12/03/2004 Page TRM / 3.8-13 02/19/2015 Page TRM / 3.8-14 08/31/1998 Pages TRM / 3.8-15 through TRM / 3.8-17 04/02/2002 Page 3.8-18 08/31/1998 Page TRM / 3.8-19 04/02/2002 Page 3.8-20 08/31/1998 Pages TRM / 3.8-21 and TRM / 3.8-22 06/06/1999 Page TRM / 3.8-23 11/07/2013 Pages TRM / 3.8-24 and TRM / 3.8-25 11/30/2011 Page TRM / 3.8-26 05/28/2009 Page TRM / 3.8-27 11/29/2006 Pages TRM / 3.8-28 and TRM / 3.8-29 05/28/2009 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 TRM / 3.10-2 and TRM / 3.10-3 08/31/1998 Page TRM / 3.10-4 08/01/2006 Pages TRM / 3.10-5 and TRM / 3.10-6 03/22/2006 Page TRM / 3.10-7 06/10/2010 Page TRM / 3.10-8 03/27/2008 SUSQUEHANNA - UNIT 1 TRM / LOES-4 SUSQEHANA UNT I RM LOS-4EFFECTIVE DATE 11/04/2015
SUSQUEHANNA STEAM ELECTRIC STATION Rev. 84 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date 3.11 RADIOACTIVE EFFLUENTS Page TRM / 3.11-1 03/31/2006 Pages TRM / 3.11-2 and TRM / 3.11-3 08/31/1998 Page TRM / 3.11-4 03/31/2006 Page TRM / 3.11-5 08/31/1998 Page TRM / 3.11-6 03/31/2006 Pages TRM / 3.11-7 and TRM / 3.11-8 08/31/1998 Pages TRM / 3.11-9 and TRM / 3.11-10 10/09/2012 Pages TRM / 3.11-11 and TRM / 3.11-12 08/31/1998 Page TRM /3.11-13 02/19/2015 Page TRM / 3.11-14 12/03/2004 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 Page TRM / 3.11-22 04/02/2002 Page TRM / 3.11-23 11/14/2006 Page TRM / 3.11-24 06/18/2013 Page TRM / 3.11-25 04/12/2007 Pages TRM / 3.11-26 and TRM / 3.11-27 01/21/2004 Page TRM /3.11-28 09/08/2009 Page TRM / 3.11-29 12/03/2004 Pages TRM / 3.11.30 and TRM / 3.11.31 01/21/2004 Page TRM / 3.11.32 04/23/2015 Page TRM / 3.11-33 03/31/2006 Page TRM / 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 Page TRM / 3.11-40 02/19/2015 Pages TRM / 3.11-41 through TRM / 3.11-43 08/31/1998 Page TRM / 3.11-44 08/01/2006 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 4.0-1 through 4.0-3 08/31/1998 Page TRM / 4.0-4 12/11/2008 Pages 4.0-5 through 4.0-8 08/31/1998 SUSQUEHANNA-UNIT1 TRM/LOES-5 SUSQEHANA UNT I RM LOS-5EFFECTIVE DATE 11/04/2015
SUSQUEHANNA STEAM ELECTRIC STATION Rev. 84 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 02/19/2015 Page TRM / B 3.0-4a and TRM / B 3.0-4b 02/19/2015 Page TRM / B 3.0-5 02/19/2015 Page TRM I B 3.0-6 08/31/1998 Page TRM I B 3.0-7 04/12/2007 Pages TRM / B 3.0-8 through TRM I 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 through TRM / B 3.0-15 02/19/2015 B 3.1 REACTIVITY CONTROL SYSTEMS BASES Page TRM / B 3.1-1 07/13/1999 Page TRM / B 3.1-2 04/16/2014 Page TRM /B 3.1-3 10/31/2007 Page B 3.1-4 08/31/1998 Page TRM / B 3.1-5 11/15/2005 Pages TRM I B 3.1-6 and TRM / B 3.1-7 03/22/2006 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 01/21/2014 Page TRM / B 3.3-2 03/10/2011 Page TRM / B 3.3-2a 10/31/2007 Page TRM / B 3.3-3 12/11/2008 Page TRM / B 3.3-3a 10/31/2007 Page TRM / B 3.3-4 06/30/2010 Page TRM / B 3.3-5 10/07/2015 Page TRM I B 3:3-6 06/30/2010 Page TRM I B 3.3-7 10/07/2015 Page TRM / B. 3.3-8 06/30/2010 Page TRM I B 3.3-9 10/31./2007 Pages TRM / B 3.3-10 through TRM I B 3.3-12 01/07/2011 Page TRM / B 3.3-13 01/21/2014 Page TRM / B 3.3-14 06/25/2002 Page TRM / B 3.3-14a 11/04/2015 Page TRM I B 3.3-14b 11/04/2015 Page TRM / B 3.3-14c 11/04/2015 Pages TRM / B 3.3-15 and TRM I B 3.3-16 10/22/2003 Page TRM / B 3.3-17 03/22/2006 Pages TRM / B 3.3-17a through TRM / B 3.3-17c 03/22/2006 Page TRM / B 3.3-17d 03/27/2008 TRM / LOES-6 EFFECTIVE DATE 11/04/2015 SUSQUEHANNA-UNITI SUSQUEHANNA - UNIT 1 TRM / LOES-6 EFFECTIVE DATE 11/04/2015
SUSQUEHANNA STEAM ELECTRIC STATION Rev. 84 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date TRMI IBB3.3-19 Pages TRM / B 3.3-17e andTRM 3.3-17f 03/22/2006 Pages TRM / B 3.3-18 and 08/03/2010 Page TRM / B 3.3-20 10/22/2003 Page TRM / B 3.3-21 05/16/2003 Pages TRM / B 3.3-22 and TRM / B 3.3-23 04/07/2009 B 3.4 REACTOR COOLANT SYSTEM BASES Page B 3.4-1 08/31/1998 Pages TRM / B 3.4-2 and TRM / B 3.4-3 04/01/2009 Pages TRM 1 B 3.4-4 and TRM / B 3.4-4a 10/31/2007 Page TRM / B 3.4-5 10/1 5/1 999 Page B 3.4-6 08/31/1998 Pages TRM / B 3.4-7 and TRM / B 3.4-8 04/25/2013 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 through 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 03/27/2008 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 Page TRM/IB 3.7-3 06/10/2010 Page 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 Page TRM / B 3.7-6 03/3"1/2006 Pages TRM / B 3.7-7 and TRM / B 3.7-7a 08/02/1999 Page TRM / B 3.7-8 O5/2 9/2013 Page TRM / B 3.7-9 04/11/2014 Page TRM / B 3.7-10 08/02/1999 Page TRM / B 3.7-I0a 03/31/2006 Page TRM / B 3.7-11 08/02/1999 Page TRM / B 3.7-11a 03/31/2006 Pages TRM / B 3.7-12 and TRM / B 3.7-13 08/02/1999 Pages TRM / B 3.7-14 and TRM / B 3.7-14a 09/25/20 12 EFFECTIVE DATE 11/04/2015 SUSQUEHANNA SUSQUEHANNA-UNIT1
- UNIT I TRM // LOES-7 TRM LOES-7 EFFECTIVE DATE 11/04/2015
SUSQUEHANNA STEAM ELECTRIC STATION Rev. 84 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date Page TRM / B 3.7-14b 11/24/2011 Pages TRM / B 3.7-15 and TRM I B 3.7-16 0210111999 Pages B 3.7-17 through B 3.7-20 08/31/1998 Page TRM I B 3.7-21 05/29/2013 Pages TRM / B 3.7-21a through TRM / B 3.7-21d 05/24/2012 Pages TRM / B 3.7-21e through TRM / B 3.7-21g 05/29/2013 Page TRM / B 3.7-22 and TRM / B 3.7-23 01/30/2008 Page TRM / B 3.7-24 10/05/2006 Page TRM / B 3.7-25 01/21/2014 Pages TRM / B 3.7-26 through TRM / B 3.7-28 10/05/2006 Pages TRM / B 3.7-29 and TRM I B 3.7-30 06/07/2007 Page TRM / B 3.7-30a 10/05/2006 Page TRM / B 3.7-30b 01/21/2014 Page TRM / B 3.7-31 11/30/2011 Page TRM / B 3.7-32 03/09/2001 Page TRM / B 3.7-33 04/15/2003 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 3.7-39 04/01/2009 Page TRM / B 3.7-40 04/08/2010 ELECTRICAL POWER BASES B 3.8 Page TRM / B 3.8-1 04/02/2002 Page TRM / B 3.8-2 01/28/2005 Page TRM / B 3.8-2a 03/01/2010 Page TRM / B 3.8-3 04/02/2002 Page TRM / B 3.8-3a 04/02/2002 Page TRM / B 3.8-4 09/03/2004 Page TRM / B 3.8-4a 04/02/2002 Page B 3.8-5 08/31/1998 Pages TRM / B 3.8-6 through TRM / B 3.8-15 04/02/2002 Page TRM / B 3.8-16 11/07/2013 Page TRM / B 3.8-17 11/30/2011 Pages TRM / B 3.8-17a and TRM / B 3.8-17b 11/30/2011 Pages TRM / B 3.8-18 through TRM / B 3.8-20 05/29/2013 Pages TRM / B 3.8-21 and TRM I B 3.8-22 05/28/2009 Page TRM I B 3.8-23 05/29/2013 Page TRM / B 3.8-24 05/28/2009 B.3.9 REFUELING OPERATIONS BASES Pages B 3.9-1 through B 3.9-7 08/31/1998 TRM / LOES-8 EFFECTIVE DATE 11/04/2015 SUSQUEHANNA - UNIT UNIT 1I TRM / LOES-8 EFFECTIVE DATE 11/04/2015
SUSQUEHANNA STEAM ELECTRIC STATION Rev. 84 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MAN UAL)
Section Title Effective Date B 3.10 MISCELLANEOUS BASES Page B 3.10-1 08/31/1998 Pages TRM / B 3.10-2 and TRM / B 3.10-3 03/22/2006 Pages TRM / B 3.10-4 and TRM / B 3.10-5 08/23/1999 Page TRM / B 3.10-6 03/27/2008 B 3.11 RADIOACTIVE EFFLUENTS BASES Pages B 3.11-1 through B 3.11-9 08/30/1998 Page TRM / B 3.11-10 02/01/1999 Pages TRM/B 3.11-11 and TRM/B 3.1 1-11a 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 / B3.11-15 02/01/1999 Pages B 3.11-16 through B 3.1 1-19 08/30/1998 Page TRM / B 3.11-20 04/02/2002 Page TRM / B 3.1 1-20a 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 Pages TRM / B 3.1 1-23a and TRM / B 3.1 1-23b 06/18/2013 Pages TRM / B 3.11-24 and TRM / B 3.11-25 01/21/2004 Pages B 3.11-26 and B 3.11-27 08/30/1998 Page TRM / B3.11-28 11/30/2005 Page TRM / B 3.11-29 02/19/2015 Pages TRM / B3.1 1-30 and TRM / B 3.11-31 05/29/2013 Page TRM /B 3.11-32 08/30/1 998 Page TRM / B 3.11-33 06/30/2010 Pages B 3.11-34 and B 3.11-35 08/30/1998 Page TRM / B 3.11-36 02/12/1999 B.3.12 LOADS CONTROL PROGRAM BASES Page TRM / B3.12-1 09/19/2007 Page TRM / B 3.12-2 11/29/2010 Page TRM / B 3.12-3 02/05/1999 TRM1 text LOES 11/4/2015 SUSQUEHANNA - UNIT 1 TRM / LOES-9 SUSQEHANA UNT I RM LOS-9EFFECTIVE DATE 11/04/2015
Core Operating Limits Report (COLR)
Rev. 16 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.
APPLI(CABILITY: SPecified in the referenced Technical Specifications.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME" A. Core Operating Limits not A,1 Perform action(s) described Specified in met. in referenced Technical referenced Specification. Technical Specifications.
TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE FREQUENCY
NOTE-.......... ............. .. N/A No associated Surveillances. Surveillances are implemented in the applicable Technical Specificatiorns.
SUSQUEHANNA-UNIT1 TRM / 3.2-1 SUSQEHANA
-UNI 1 TM/32-1EFFECTIVE DATE 0710711999
Rev. 16 PL-NF-14-001 Rev. 2 Page "i of 62 Susquehanna SES Unit I Cycle 19 CORE OPERATING LIMITS REPORT Nuclear Fuels Engineering September 2015 SUSQUEHANNA UNIT1 TRM!3.2-2 SUSQEHANA UNT I RM/32-2EFFECTIVE DATE 11/0412015
Rev. 16 PL-NF-14-001 Rev. 2 Page 2 of 62 CORE OPERATING LIMITS REPORT REVISION DESCRiPTiON INDEX Rev. Affected ,
No. Sections Description/Purpose of Revision 0 ALL Issuance of this COLR is in support of Unit I Cycle 19 operation.
1 ALL New COLR required due to Power/Flow Map revision.
2 ALL New COLR required for the inclusion of operating limits regarding a Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) closure event.
~J. J FORM NFP-QA-008-2, Rev. 1 SUSQUEHANNA UNIT 1 TRM/3.2-3 TRM/.2-3EFFECTIVE DATE 11/04/2015
Rev. 16 PL-NF-14-00i Rev. 2 Page 3 of 62 SUSQUEHANNA STEAM ELECTRIC STATION Unit I Cycle 19 CORE OPERATING LIMITS REPORT Table of Contents
1.0 INTRODUCTION
............................................................................ 4 2.0 DEFINITIONS................................................................................6 3.0 SHUTDOWN MARGIN ....................................................................... 6 4.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR).................. 7 6.0 MINIMUM CRITICAL POWER RATIO (MCPR)............................................ 9 6.0 LINEAR HEAT GENERATION RATE (LHGR) ...................................... ....... 27 7.0 ROD BLOCK MONITOR (RBM) SETPOINTS AND OPERABILITY REQUIREMENTS ............................................................................ 38 8.0 RECIRCULATION LOOPS - SINGLE LOOP OPERATION............................... 40 9.0 POWER I FLOW MAP .............................................. :......................... 58 10.0 OPRM SETPOINTS.......................................................................... 60
11.0 REFERENCES
................ ................................................................ 61 SUSQUEHANNA UNIT 1 TRM/3.2-4 SUSQEHANA NITTR/3..-4DATE 11/04/2015 EFFECTIVE
Rev. 16 PL-NF-14-0O1 Rev. 2 Page 4 of 62 1.0 iNTRODUCTION This CORE OPERATING LIMITS REPORT for Susquehanna Unit t Cycle 19 is prepared in accordance with the requirements of Susquehanna Unit 1, 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 1 TRM/3.2-5 UNT I RM/32-5 SUSQEHANA EFFECTIVE DATE 11/04/2015
Rev. 16 PL-NF- 14-001 Rev. 2 Page 5 of 62 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 LHGRFACT is a multiplier applied to the LHGR limit when operating at less than 108 Mlbm/hr core flow. The LHGRFAC1 multiplier protects against both fuel centerline melting and cladding strain during anticipated system transients initiated from core flows less than 108 Mlbmlhr.
2.5 LHGRFACp is a multiplier applied to the LHGR limit when operating at less than RATED THERMAL 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 I hr, below which the OPRM RPS trip is activated.
SUSQUEHANNA UNIT 1 TRM/3.2-6 SLJSUEHNNAUNITI EFFECTIVE TMI32-6 DATE 111/0412015
Rev. 16 PL-NF-1 4-001 Rev. 2 Page 6 of 62 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 (BOG) SHUTDOWN MARGIN (SDM) tests must also account for changes in core reactivty during the cycle. Therefore, the SUM 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 8DM) during the operating cycle and the calculated BOG core reactivity. If the value of "R" is zero (that is, BOG is the most reactivepoint in the cycle) no correction to the BOG 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 t TRM/3.2-7 SUSQEHANA UNTI RM/32-7 EFFECTIVE DATE 11104/2015
Rev. 16 PL-NF-14-O01 Rev. 2 Page?7 of 62 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 ATRIUMT'-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 1 TRM/3.2-8 SUSQEHANA UNT I RM/32-8 EFFECTIVE DATE 11/04/20 15
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-- I mr 4.0 0 10000 20000 30000 40000 Average Planar Exposure (MWDIMTU) 50000 60000 70000 0
-* ,r-SI)
AVERAGE AVERAGE PLANAR LINEAREXPOSURE PLANAR HEAT GENERATION RATE LIMIT VERSUS
-TWO LOOP OPERATION Coz ATRIUMTM-10 FUEL C:'(D7 FIGURE 4.2-1
Rev. 18 PL-NF-14-001 Rev. 2 Page 9 of 62 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 Technical Requirements Manual Reference Technical Requirements Manual 3.3.7 5.3 Description The MOPR 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-1O) shall be the greater of the Flow-Dependent or the Power-Dependent MOPR, depending on the applicable equipment operability status.
a) Main Turbine Bypass I EOO-RPT I Backup Pressure Regulator Operable Figure 5.2-1: Flow-Dependent MCPR value determined from BOO to EDOC Figure 5.2-2: Power-Dependent MOPR value determined from BOO to EGOC b) Main Turbine Bypass lnoperable Figure 6.2-3: Flow-Dependent MCPR value determined from BOO to EDOC Figure 5.2-4: Power-Dependent MOPR value determined from BOO to EGOC c) EOC-RPT Inoperable Figure 5.2-5: Flow-Dependent MCPR value determined from BOO to EOC Figure 5.2-6: Power-Dependent MCPR value determined from BOG to EOO d) Backup Pressure Regulator Inoperable Figure 5.2-7: Flow-Dependent MCPR value determined from BOO to EDOC Figure 5.2-8: Power Dependent MCPR value determined from BOG to EDOC e) One Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) Closed Figure 5.2-0: Flow-Dependent MCPR value determined from BOO to EGG Figure 5.2-1 O:Power-Dependent MCPR value determined from BOO to EDO SUSQUEHANNA UNIT 1 TRM/3.2-10 SUSQEHANA UITTRM3.2I EFFECTIVE 0DATE 11/04/2015
Rev. 16 PL-NF-1 4-001 Rev. 2 Page 10 of 62 The MCPR limits in Figures 5.2-1 through 5.2-10 are valid for Two Loop operation.
The MCPR limits for Single Loop operation are provided in Section 8.0.
5.4 Averauqe Scram Time Fraction Ifthe 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 UNIT1 TRM/3.2-11 SUSQEHANA UITTRM3.21 EFFECTIVE IDATE 11104/2015
Rev. i6 PL-NF-14-O01 Rev. 2 Page Iiof 62 Main Turbine Bypass I EOC-RPT I Backup Pressure Regulator Operable SUSQUEHANNA UNIT 1 TRM/3.2-12 NITTR/32I 2DATE 1110412015 EFFECTIVE SUSQEHANA
C' SSES UNIT 1 CYCLE 19 C 2.2 c,
2,1 z
z 2.0 z
1.9
._E 1.8 1.7 CD k* 0.
CA 0o 1.6 <)
1.5 m 1.4 Ill C)
H 1.3 rn ci 1.2 H 30 40 50 60 70 80 90 100 110 Total Core Flow (MLBIHR)
-o "o n, I Ill (.Q0 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS 1 EOC-RPT I BACKUP PRESSURE REGULATOR OPERABLE TWO LOOP OPERATION (BOC TO EOC)
FIGURE 5.2-1 * -< 0
. . .. . . . .. .... . .. ..... ...... .... .... .. . ... ... . . . . .. . . . . .. . . .... . .. ........ ,... .. .. .. .. . .. .. ,,,,,.. .. .. . . . . . ... ... .. 1... .. . . . .. . .. . .... ... . .. . . .. . . . .. . I J . .. .... . ,J , , =. .. ... .
cj SSES UNIT 1 CYCLE 19 0
z z
C z
1J H 0.
0 m
0 20 30 40 50 60 70 80 90 100 Core Power (% RATED)
"13 -O
- , I-MCPR OPERATING LIMIT VERSUS CORE POWER 0" MAIN TURBINE BYPASS I EOC-RPT I BACKUP PRESSURE REGULATOR OPERABLE TWO LOOP OPERATION (BOO TO EOC) (3 "
n Ii --.
FIGURE 5.2-2
Rev. 16 PL-NF- 14-001 Rev. 2 Page 14 of 62 Main Turbine Bypass Inoperable SUSQUEHANNA UNIT1 TRM/3.2-15 UITTRM3.2l EFFECTIVE SUSQEHANA 5DATE 1 1/04/2015
0 SSES UNIT 1 CYCLE 19 2.2 03 C
2.1 LEGENDA
MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME
-CURVE CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME z
C 2.0 z
-1 1.9 I INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 1.8 H. '1.7 0J o-01 1,6 1.5
-I"I 1.4
--- I EEENCE:_T.S. 3.7.6 and 3.2.2 ___________ __________
'1.3 m
Hr iii 1.2 30 40 50 60 70 80C I0 100 110 Total Gore Flow (MLB/H-R)
--t "D "
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS INOPERABLE TWO LOOP OPERATION (BOC TO EOC)
FIGURE 5.2-3 ,.-4 <
Q)"*
0
CI, SSES UNIT 1 CYCLE 19 C 3.6 Ci, C
mR c
Z
-t
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-H 0
$o O.
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<m Fi 20 30 40 50 60 70 80 90 100 Core Power (% RATED)
(73 -U 51 MCPR OPERATING LIMIT VERSUS CORE POWER CD CD-
- MAIN TURBINE BYPASS INOPERABLE Z TWO LOOP OPERATION (BOC to EOC) 77 FIGURE 5.2-4 -- h 0)
Rev. 16 PL-NF-14-001 Rev. 2 Page 17 of 62 EOC-RPT Inoperable SUSQUEHANNA UNIT 1 TRM/3,2-18 SUSQEHANA UITTRM3.2I EFFECTIVE 8DATE 11/04/2015
CD SSES UNIT 1 CYCLE 19 2.2 03 LEGEND C
m 2.1 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM
=
INSERTION TIME 2.0 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME C
z 1.9 4. SAFETY* ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2
-H E I I IJ 1.8 L.
USED INDETER[MIN1NG MFLCPR I
-4. 1.7 0.
C0 o CD 1.6 -3.
C) 1.5
-rr 1.4
REFERENCE:
T.S. 3.3.4.1 and 3.2.2
--Il
<r m 1.3 m
1.2 30 40 50 60 70 80 90 100 110 U Total Core Flow (MLBIHR)
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW EOC-RPT INOPERABLE *QcD TWO LOOP OPERATION (BOC TO EOC)
FIGURE 5.2-5 0""
ci SSES UNIT 1 CYCLE 19 C
I z
z z
E 0
(D 0
C) m n-I 0
H m
0 50 60 90 H* 20 30 40 Core Power (% RATED) 70 80 100 n-MCPR OPERATING LIMIT VERSUS CORE POWER *(D Z EOC-RPT INOPERABLE TWO LOOP OPERATION (BOC to EQO) O-" -1 FIGURE 5.2-8 (O1*--
Rev. 16 PL-NF-14-0O1 Rev. 2 Page 20 of 62 Backup Pressure Regulator Inoperable SUSQUEHANNA UNIT 1 TRM/3.2-21 NIT TR/3.-21 DATE 11/04/2015 EFFECTIVE SUSQEHANA
SSES UNIT 1 CYCLE 19 Cn 2.2 LEGEND m
2.1 _____________ -CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME z
C 2.0 ________ -CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME z
1.9 _______ _______ - SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 1.8 I-1.7 r*o 0 A BI
- 10. 0, 1.6 1.5 m
"1 1.4 rri 0
IREFERENCE:
TS. 3.7.8 and 3.2.2~
1.3 I-~ { 4 1 ~~-f 108, 1.221 m 1.2 30 40 50 60 70 80 90 100 110 Total Core Flow (MVLB/HR)
"-D "-
0 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW BACKUP PRESSURE REGULATOR INOPERABLE "'.)
0 o', TWO LOOP OPERATION (BOC TO EQO)
FIGURE 5.2-7 "*' <c 0 0)"
SSES UNIT I CYCLE 19 60 C
z 0,
.2
-Il CD C
-3.
0)
'i,,
100,1.35 m
20 30 40 50 60 (% RATED) 70 Core Power 80 90 100 o1 T1 T1
-L
- Q2 Z~
MCPR OPERATING LIMIT VERSUS CORE POWER BACKUP PRESSURE REGULATOR INOPERABLE TWO LOOP OPERATION (BOO to EOC)
FIGURE 5.2-8 -,h . 0 0)' ,C
Rev. 16 PL-NE-14-001 Rev. 2 Page 23 of 62 One TSV. or TCV Closed SUSQUEHANNA UNIT 1 TRM/3.2-24 SUSQEHANA UIT ITR IS.-24 EFFECTIVE DATE 11104/2015
SSES UNIT 1 CYCLE 19 2.2 I LEGEND 2,1 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 2.0 _______
_______ -CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME
-r" 1.9 130, 1.831 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES NJ I ARE OPERABLE PER SR 3.7.5.1 AND 3.7.6.2 U' .4-1.8
- _ USED IN DETERMINING MFLCPR E2 1.7 C., 1.6 CD 1.5 m
-I-1 1.4 m
REFERENCE:
T.S. 3.2.2 and TRM 3.3.71 0
I-4 1.3
_ _ I _ I_ _ _ _ _ _ _ _ _ _
1.2 m
30 40 50 60 70 80 90 100 110 Total Core Flow (MLBIHR) 0 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW CD Z N)
TWO LOOP OPERATION (BOC TO EOC) - ,-<
FIGURE 5.2-9 0
cj SSES UNIT 1 CYCLE 19 C
m z
C z
S 0.-
-I 0m
- 0 CD m
-n m
m C)
-9 20 30 40 50 60 70 80
- Core Power (% RATED)
MCPR OPERATING LIMIT VERSUS CORE POWER
FIGURE 5.2-10
Rev. 16 PL-NF-14-O01 Rev. 2 Page 26 of 62 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 - oo70 3.440 Average Scram Realistic Maximum Insertion Time Allowable SUSQUEHANNA UNIT 1 SUQEAN NTITRM/3.2-27 EFFECTIVE DATE 11/0412015
- 1. . . .1 I * ... A... . . - -- a L.~cgaa. . .. .. * .1 L. * -- . .*... ..&. aaau I 1S a. . .... aJ L&...aa......a..n.
Rev. 16 PL-NF- 14-001 Rev. 2 Page 27 of 62 6.0 LINEAR HEAT GENERATION RA*TE (LHGR) 6.1 Technical Specification Reference Technical Specification 3.2.3, 3.3.4.1, 3.7.6, and 3.7.8 6.2 Technical Requirements Manual Reference Technical Requirements Manual 3.3.7 6.3 Description The maximum LHGR for ATRIUMTZ-I 0 fuel shall not exceed the LHGR limit determiined 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 in the following figures:
a) Main Turbine Bypass Operable Figure 6.2-2: Flow-Dependent LHGR Uimit Multiplier Figure 6.2-3: Power-Dependent LHGR Limit Multipiier b) Main Turbine Bypass Inoperable Figure 6.2-4: Flow-Dependent LHGR Limit Multiplier Figure 6.2-5: Power-Dependent LHGR Limit Multiplier c) One Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) Closed Figure 6.2-6: Flow-Dependent LHGR Limit Multiplier Figure 6.2-7: Power-Dependent LHGR Limit Multiplier
- The LHGR limits and LHGR limit multipliers in Figures 6.2-2 and 6.2-3 are applicable to EOC-RPT Operable and Inoperable and Backup Pressure Regulator Operable and Inoperable.
- The LGHR limits and LHGR limit multipliers in Figures 6.2-1 through 6.2-7 are valid for both Two Loop and Single Loop operation.
SUSQUEHANNA UNIT 1 TRM/3.2-28 SUSQEHANA EFFECTIVE NITTRI3.-28 DATE 11/04/2015
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SSES UNIT 1 CYCLE 19 C 16.0 Ii Ii II ii i iI ii ii a ili a iI l Ii i !i Co a a la a a l la l a l 0 a a
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Pellet Exposure (MWDIMTU) rr T-0 "
-I- UNEAR HEAT GENERATION RATETMLIMIT VERSUS PELLET EXPOSURE ATRIUM -10 FUEL FIGURE 6.2-1 Oco a-0")' 0
Rev. 16 PL-NF-'I4-001 Rev. 2 Page 29 of 62 Main Turbine Bypass Operable SUSQUEHANNA UNIT 1 TRM/3.2-30 SUSQEHANA NITTR/3.-30 DATE 11/04/2015 EFFECTIVE
C,,
SSES UNIT 1 CYCLE 19 Co 1.10 1.00 z
z 0.90
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-I ._1
('3 0.70 a, <D
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0.60 0,50
-n r-n m 0.40 m
0.30
-I 30 40 50 60 70 80 90 100 110 m: Total Core Flow (MLB/hr)
- 0) FLOW DEPENDENT LHGR LIMIT MULTIPLIER NJ MAIN TURBINE BYPASS OPERABLE (03 ATRIUMT*-10 FUEL FIGURE 8.2-2
SSES UNIT 1 CYCLE 19 1.10 L I & "" 'U"' ........... * " '
- m L 4 4 *
- A A i C
m3 LEGEND
.. " ' '
- t I " I I i
I ii Fji o T ---- ,-------~.------.I-------, 9 CURVE A: BASE CURVE 1.00 CURVE B: CORE POWER __26% AND CORE FLOW <_.0 MLBM1HR
- I TI rS I 1 31 1 --- I - . ..- j. a .I - * -- -
0.90 I I I I a I i I I
"-I II l l* i I [ aI I li l i k I I
I
.1_J IIS
_ _ J. _
I
. 1 IJ ;
1 _1 J LI z
I--
0.80 I I I I I 1 1 5 I I I I I 1 I I I I I
,.I I l ARE OPRAL PE SR ANI37lI...
0.70 . . ..._
- 1*. 1. * * ._ ._ . . . . . . . . .
C) /II I I 1 I ___ _ _ ___ ___ __ ___ ___ _
1_-
H 0.
0 0.60
__..,. . IL.__J._.I * ..- 1 REOERABENCE: TSR 3.2.3,1 3.A4N 3.7.6 an 8 I I
iH i _ 1i_
- /
0.50 -
03 iL I yr i I" '-- "" ' "- - ! . .. .... .. . . .. .-. -- - '- - -l . - - * - * - ; ' .. . .
l 26 04 N,3 0.40 23 I -" -
0.0.
I I...
II -'-I....
I
.. F - I-'
, ~l, I-
- I I * --I - - - - -l-I
, , I
-- - It - -
3I - *
/ - f - I- -
I ,
-I - d - -
i I I I I I I I I I I I
! ,, IJ, J I I I I I r I I I I I I I - 3 I I 0 0.30 I I II I r I I 1 2,0 30 40 50 Core Power 60 (% RATED) 70 80 90 100 POWER DEPENDENT LHGR LIMIT MULTIPLIER MAIN TURBINE BYPASS OPERABLE o ,z AT*iUMTM-10 FUEL FIGURE 6.2-3
Rev. 16 PL-NF-14-O01 Rev. 2 Page 32 of 62 Main Turbine Bypass Inoperable SUSQUEHANNA UNIT I TRM/3.2-33 SUSQEHANA NITTR/3.-33 DATE 11t10412015 EFFECTIVE
SSES UNIT 1 CYCLE 19 Co 1.10 I
z 1.00 C:
Z 0.90 0.
0.80
.-I "-J C;, ._ 0.70 C;o 0,
C),. 0) 03 0.60 0o Ct 0.50 m
C)
-H m1 0.40 0
H-1 m] 0.30 30 40 50 60 Total Core Flow 70 80 90 100 110 (MLB/HR)
"0 "-
nD FLOW DEPENDENT LHGR LIMIT MULTIPLIER C.D z MAIN TURBINE BYPASS INOPERABLE 01 ATRIUMTMea-t FUEL -Il 0O FIGURE 6.2-4 0
CO, SSES UNIT 1 CYCLE 19 C 1.10 03 m
=
z z
C z
a..
.5.
.5 0
--I -I a,
1'3 a, oD 0
I..
a) 0 0.
m m
0
.-I m
0 4> 20 30 40 50 60 (% RATED) 70 Core Power 80 90 100
--I, 01" POWER DEPENDENT LH-GR LIMIT MULTIPLIER MAIN TURBINE BYPASS INOPERABLE Co C? ATRIUMTM.-10 FUEL FIGURE 6.2-,5 0"C*
Rev. 16 PL-NF-14-00l Rev. 2 Page 35 of 62 One TSV or TCV Closed SUSQUEHANNA UNIT 1 TRM/3.2-36 NITTR/3.-36DATE 11/04/2015 EFFECTIVE SUSQEHANA
0 O SSES UNIT 1 CYCLE 19 1.10 C
i"1 1.00 C
z 0.90 a,
-H1 0.80
-_J 0.70 CD CD
",4 0.60 U..
0.50
-T1
-IT 0.40 m
m 0.30 0 30 40 50 60 Total Core 70Flow (MLB/hr) 80 90 100 110 rl3 FLOW DEPENDENT LHGR LIMIT MULTIPLIER 0 ONE TSV OR TCV CLOSED* 0-" 0 ATRIUMTM-t10 FUEL D' I, -=
FIGURE 6.2-6
- 75% rated power.
n ,, n
C',
SSES UNIT 1 CYCLE 19 C
03 m
C z
13
{.i
--I ,-J
.1_
C,)
0 cc 0L 0) mT "rn ml 0
m1 H3 20 30 40 50 (% RATED)
Core Power 60 70 80 rn
-I POWER DEPENDENT LHGR LIMIT MULTIPLIER CD Z ONE TSV OR TCV CLOSED ATRIUMTM-10 FUEL *i-- n FIGURE 6,2-7 c0*
Rev. 16 PL-NF-14-OO1 Rev. 2 Page 38 of 82 7.0 ROD BLOCK MONITOR (RBM SETFOINTS AND OPERABILITY 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, d) Low Power Range - Upscale, e) Intermediate Power Range - Upscale, and I) 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. Ifthe 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.
SUSQUEHANNA UNIT 1 TRM/3.2-39 NITTRIS.-39 DATE 11/04/2015 SUSQEHANA EFFECTIVE
Rev. 16 PL-NF-14-001 Rev. 2 Page 39 of 62 Table 7.2-I RBM Setpoints Allowable Nominal Trip Function Value( 1 ) 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 117.4 117.0 High Power Range - Upscale 107.6 107.2 (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)
> 28 andc<90 < 1.76
~90 and <95 <1.47
>_95 < 1.70 (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.
SUSQUEHANNA UN]T 1 TRMI3.2-40 SUSQEHANA NITTRI3.-40 DATE 11/04/201 5 EFFECTIVE
Rev. 18 PL-NF-1 4-001 Rev. 2 Page 40 of 62 8.0 REGIRCULATION 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 Technical Req~uirements Manual Reference Technical Requirements Manual 3.3.7 8.3 Description APLHGR The APLHGR limit for ATRlUMTM-I 0 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 (ATRIUM TM-10) shall be the greater of the Flow-Dependent or the Power-Dependent MCPR, depending on the applicable equipment operability status.
a) Main Turbine Bypass I 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 [noperable 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 IEOC c) EOC-RPT Inoperable Figure 8.2-6: Flow-Dependent MCPR value determined from BOG to EOC Figure 8.2-7: Power-Dependent MCPR value determined from BOC to EOC SUSQUEHANNA UNIT 1 TRMI3.2-41 NIT TRI3.-41EFFECTIVE SUSQEHANA DATE 11/04/2015
Rev. 18 PL-NF-14-OO1 Rev. 2 Page 4l of 62 d) Backup Pressure Regulator Inoperable Figure 8.2-8: Flow-Dependent MCPR value determined from BOO to EGOC Figure 8.2-9: Power-Dependent MCPR value determined from BOO to EDO e) One Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) Closed Figure 8.2-1O:Flow-Dependent MOPR value determined from BOO to EDO Figure 8.2-11 :Power-Dependent MOPR value determined from BOO to EOC The MOPR limits in Figures 8.2-2 through 8.2-1 1 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 andOperabilityRequirem~ents The RBM setpoints and operability requirements for Single Loop Operation are defined in Section 7.0.
SUSQUEHANNA UNIT 1 TRM/3.2-42 NITTRI3.-42 DATE 1110412015 EFFECTIVE SUSQEHANA
C 16.0 T T T r T ~ T ~ u 1 1 ~ I r QI I I ' I I l Il l t I I la 1 l l 9 i0 1 '
I E lI I I Ii l l l llI lI l
- z. 1. .1. II .11 .. II1lIti1 1 I, i I s I i I r I,.i m i . m m m ii.m n l4...4 mm~~u mm.4.*"
I11I 1 I I Ii lIlC Il IlIII1I I1I1 l i l 1 Il l l ~l t l I! ~ l l l O l 1 1 I I I l I I I I Ii ~ll I I l1 1 1I tltitjilt SED IND*ERINIG0
- -- J- I---. ii! I I-I.-- -- I-- j--i-..J..-,Lf lf...f I I1 1'I II£ I Ii 1 I I
I I I
1 I1 I1 1 1 1 1 I* I I 1 I IIlli I l II l I I I I I 0l3l l l l l l l I 1 1
= *oo , Ioo I IO ll .I , II I II I, 1I I I I I I I I I I I l l3 l I [ II II IIII l Il l lI I 1 1 1 I mI.._1111l1 I I lllll1 :11! l111 l1!. 1 l11l Iiii II ! II 11 11 lll ll l Il I ll HI I I I I , l l l l I ,
I I I I I" I l l II I l l~ll
,I l li
, , I l l l:l I
l1 1
- l l l 67000,5.6 l
1o 1 11 1111 1 Il liIljlIlIIIIIl l l ll II l l l Illl I l l I I Il l 4.0 L U' i41-- LI4l2 M - -L -- ~L- AJ-J L..L
........... ... -- , I , ,. , I 0.0 l1000. l 2000.0 ll 000. 4000.08000.06000.07000.
-L~l l l l l l l lI l l i l l Averag PlanalEpour MWIMTU)l o = a l l l l l l l l2l l l i t l l A ' I I I I l * . . Ca AVRAEPLNR INA HA GENERATION RAELMITlERSUtll o AERAE PANA EPOSRE..SIGL.LOP.OERAIO ATRIUMTMAOll FUELll l l owlll FIGURE 8.2-1ll l l l l l l lI I
...... , , J2J***
..... . . . .. . .. .... .....*.. ....................... . ..... ..... ..... .......... ... * . .... .......... ... ... ................. ...... ................... ......... ....... . ..... . .. .. r*, i, . ... .. ... . .. ... .... .. .
Rev. 16 PL-NF.-14-001 Rev. 2 Page 43 of 62 Main Turbine Bypass I EOC-RPT/I Backup Pressure Regulator Operable SUSQUEHANNA UNIT 1 TRM/3.2-44 UITTRM3.2-44 SUSQEHANA EFFECTIVE DATE 11/0412.015
9 SSES UNIT 1 CYCLE 19 3.6 I I I LEGEND m 3.4 4. a- CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM z INSERTION TIME z 3.2 + I 4-C CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME z
3.0 t 1--i.
m I II II . . I H0 4-.
D.1 o~
2.8 2.6 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES L
ARE OPERABLE PER SR 3.7.6.t AND 3.7.6.2 I I Ii USED INDETERMINING MFLCPR K
0, 2.4 0
2.2 2.0 i'1
-m '.8 rI,
REFERENCE:
" T.S. 3.4.1 and 3.2.21 108, 1.49' 1.6 H
-m 0 '1.4 1N1 70 80 90 100 110 0 30 40 50 60 Total Core Flow (MLB/HR)
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW Co MAIN TURBINE BYPASS 1 EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8.2-2
9 0 SSES UNIT I CYCLE 19 4.6 o0 4.4 ___ LEGEND 4.2
________CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM
____INSERTION TIME z 4.0 ____________CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME
~-CURVE C: CORE POWER _<26% AND coRE FLOW
- 50 MLBM/HR 3.6 S 3.4
--fl!SAFETY ANALYSES ASSUME THAT F~OUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 3.2 Ho 03 3.0 _____USED IN DETERMINING MFLCPR 1.
N)
CD 0 2.8 0);
0) 2.6 2.4 2.2 f 140. 2.08!
,4 0A-B-BT*
4 -.-------- ~ I "t100, '
2.0 F *, ... .. . .. .
-Iil m
t 1.8 0 REEEC: T.S. 3.4.1 and 3.2.2 "Z 1.6 Hr o 1.4 20 100 mn 2040 50co 60*( RAE70 80 90 "0 "
MCPR OPERATING LIMIT VERSUS CORE POWER CD MAIN TURBINE BYPASS I EOC-RPT I BACKUP PRESSURE REGULATOR OPERABLE SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8.2-3 °< I
"* O 0)' C
Rev. 16 PL-NF-14-OO1 Rev. 2 Page 46 of 62 Main Turbine Bypass Inoperable SUSQUEHANNA UNIT1 TRM/3.2-47 SUSQEHANA NITTR/3.-47 DATE 1110412015 EFFECTIVE
C' SSES UNIT 1 CYCLE 19 4.2 I I II C-
________ ________ LEGEND 4.0 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 3.8 - INSERTION TIME z
z
________________CURVE B: REALISTIC AVERAGE SCRAM iNSERTiON TIME 3.6 z
3.4
- SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS -
,4D 3.2 VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 o* 3.0 H0 0
CD co3 0) 2.4.
2.2 m 2.0 "I1 m .
1.8 -1
REFERENCE:
T.S. 3.4.1, 3.7.6,, and22 -- _,118 0
m 1.6 _ _ _ _ _I _ _ _-_-_-_
1.4 m
30 40 50 60 Total Core 70 80 90 t00 110 Flow (MLB/HR) 0 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW CD Z
-J. MAIN TURBINE BYPASS INOPERABLE SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8,2-4 0 o)"
C, SSES UNIT I CYCLE 19 4.2 123,4A41 * =* *l "1 I " m l C-Cin I LEGEND 4.0 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM F INSERTION TIME z 3.8 z CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME
~, 3,61 ____________ 4-Z
-I 3.6 CURVE C: CORE POWER_*26% AND CORE F~LOW _<50 MLBMIHR
.t-l 3.4 I m
.1.a 1I~Z~38 I--.*- 4. I-I E
-I Cu 3.2 ISAFETY VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6,2 ANALYSES ASSUME THAT TWO OR MORE BYPASS w 3.0 USED IN DETERMINING MFLCPR I-0.
1~oi C~) 0
.41 CD N)
- a. 2.8 CO 0 ______ _ ________ 0) 2.6 2.4 2,2 m
2.0 0r
REFERENCE:
T.S. ,3.4.1, 3.7.6, and 3.2.2 ..
-I 1.8 20 30 40 6060 Power (%o o70RATED) 80 90 100 50Core "0 "T CD MCPR OPERATING LIMIT VERSUS CORE POWER Com I N) MAIN TURBINE BYPASS INOPERABLE .CD SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8,2-5 ow.
- h. h< .-
Rev. 16 PL-NF-14-O0l Rev. 2 Page 49 of 62 EOC-RPT Inoperable SUSQUEHANNA UNIT 1 TRM/3.2-50 SUSQEHANA NIT TR/3.-5OEFFECTIVE DATE 11/0412015
p SSES UNIT 1 CYCLE 19 4.0 LEGEND m 3.8 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM~
z 3.6 ________________INSERTION TIME z
C CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.4 z
3,2 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVESl E 3.0 - ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2
,U
-1 I-2,8 USED IN DETERMINING MFLCPR 4,
0.
2.6 0
N, 0I 2.4 0) 2.2 2.0 m 1.8 0
REFERENCE:
T.S 3..,.341 and 3.2.2 _ "_-_-_-[_08t" 1.6 1.4 m 30 40 50 60 70 80 9t0 100 110 Total Core Flow (MLB/HR)
- , ,I-0 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW 4* EOC-RPT INOPERABLE -Q* .:
SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8.2-6
C*
SSES UNIT 1 CYCLE 19 Cb 0*
z
.-I C.'
CD C.,
N)
C,' 0)
'-I"1
['11
-IT m
1-1 20 30 40 5060 Power' (% RATED) 70 80Core 80 90 100 m -U -D MCPR OPERATING LIMIT VERSUS CORE POWER Co z EOC-RPT INOPERABLE 0,-
SINGLE LOOP OPERATION (BOC to EOC) ,C FIGURE 8.2-7 ow' 0
Rev. 15 PL-NF-14-OO1 Rev. 2 Page 52 of 62 Backup Pressure Regulator Inoperable SUSQUEHANNA UNIT 1 TRM/3.2-53 SUSQEHANA NITTRIS.-53 DATE 11/04/2016 EFFECTIVE
C',
SSES UNIT I CYCLE 19 CO 4.0 I I I I m 3.8
- MAXIMUM ALLOWABLE AVERAGE SCRAM z
3.6 INSERTION TIME V
I .
C I: REALISTIC AVERAGE SCRAM INSERTION TIME z 3.4 4 4.-
3.2 f , , .. ,I.,,.I,, I , " "
S C
3.0 2,8 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 USED IN DETERMINING MFLCPR 2
H* C) a.
0 2,6 CD 0~
C, 2.4 2,2 2.0 r-n
-n' rni 1.8 A-
__---_ _ _ ___ __ B
REFERENCE:
T.S. 3.4.1, 3.7.8, and 3.2.2[ ____.__ .. _. _ _ .J._108, 1.48 1.6 m
1,4 30 40 50 60 70 80 90 100 110 Total Core Flow (MLBJHR) w r 0*
MOPR OPERATING LIMIT VERSUS TOTAL CORE FLOW BACKUP PRESSURE REGULATOR INOPERABLE 01 SINGLE LOOP OPERATION (BOC to EGOC)
FIGURE 8.2-8 0O" 0
' I * . ...... .... ....... ".............. ... ...... . ... . .. ... . . . ............ ...... .............. ......................... ................. ................. .. .. * .. . . =. . ... * " *LZ*:* I* *,.,. L*** ............ .....
CD SSES UNIT 1 CYCLE 19 C " 'I-0*
C 4.4 ---- LEGEND m UM ALLOWABLE AVERAGE SCRAM
-i- 4.2 CURVE A: MAXIM z ____
___ ___INSERi nION TIME z
C 4.0 CURVE B: REALI*
STIC AVERAGE SCRAM INSERTION TiME 3._____,_.__1CURVE C: CORE POWER < 26% AND CORE FLOW < 60 MLBMIHR I
I I rY ANALYSES ASSUME THAT FOUR BYPASS VALVES l---
ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 3.0 26.01, 2.90 E
USED IN DETERMINING MFLCPR CD 0.= 2.6 A *1*
0)
O- 60, 2.18 U* 4 4 1100 "
2.2 1 m
2.0 m
1.8
REFERENCE:
T.S. 3.4.1, 3.7.8, and 3.2.2J11ii 1.4
.-I 20 30 40 60 ... ... 60 ... .. .. 70 80 90 100 m uore r'ower rio KAIi )uJ MCPR OPERATING LIMIT VERSUS CORE POWER CD J\) BACKUP PRESSURE REGULATOR INOPERABLE "11 0J SINGLE LOOP OPERATION (BOO to EOC)
FIGURE 8.2-9 (:I' .Q DO O--
Rev. 16 PL-NF-14-001 Rev. 2 Page 55 of 62 One TSV or TCV CloSed SUSQUEHANNA UNIT 1 TRM/3.2-56 NITTR/3.-56 DATE 11/04/2015 EFFECTIVE SUSQEHANA
S SSES UNIT 1 CYCLE 19 3,6 0o C
-i- 3.4 z
z 3.2 z
3.0 2.8 E
0.
2.6
-*1 2.4 k* *0 0-C, 2.2 2.0 rri "11 1.8 m
1.6 m
1.4 r'ri 110 30 40 50 60 70 80 90 100 Total Core Flow (MLB/HR)
C 0* MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW o ,-n ONE TSV OR TCV CLOSED*
cj SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8.2-10 o~
1'r%-h*
0 oi)
SSES UNIT 1 CYCLE 19 4.6I I I I 4.4 LEGEND m
4.2 ______ CURVE *: MAXIMUM ALLOWABLE AVERAGE SCRAM z INSERTION TIME z 4.0 CURVE E3: REALISTIC AVERAGE SCRAM INSERTION TIME C
z 23 .61 23,3.7 CURVE c.: CORE POWER < 26% AND CORE FLOW < 50 MLBM/HR 3.6
"* 26, 3.56-"
C......SAFETY ANALYSES ASSUMEtt THAT FOUR BYPASS VALVES t 3.4 26,C 3.33 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 3.2
-- ___________USED IN DETERMINING MFLCPR 3.0 C,i CJ1 2.8 CD 0) 2.6
___ _ _ __ _ _ _ __ _ _ _ _6,19 2.4 2.2 _________ 6.01, 2.40_____ _________ - 519 2.0 n
1.8 1.6 m
1.4 20 30 40 50 60 70 80 Core Power (%RATED)
-0 7ci MCPR OPERATING LIMIT VERSUS CORE POWER w"I-ONE TSV OR TCV CLOSED 01 SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8.2-11 0)'
- i jq L. . ... *....... . . ..... . ... . . .......... . . .. .......... ........ T.. .. ............. .... ...... * * * * * ... ... .... -:-.!
.. ... .=
Rev. 16 PL-NF-14-OO1 Rev. 2 Page 58 of 62 9.0 POWERI/FLOW MAP 9.1 Technical Specification Reference Technical Specification 3.3.1.1 9.2 Description Monitor reactor conditions to maintain THERMAL POWER / core flow outside of Stability Regions I and II of the Power/IFlow map, Figure 9.1.
Ifthe 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 perT"S 3.3.1.1, Region I of the Power!
Flow map is considered an immediate sca region.
Region Ilof the Power!/Flow map is considered an immediate exit region regardless of the operability of the OPRM Instrumentation.
SUSQUEHANNA UNIT1 TRM/3.2-59 SUSQEHANA NITTR/3.-59 DATE 11104/2015 EFFECTIVE
Rev. 16 PL-NF-14-O01 Rev. 2 Page 59 of 62 120
Purpose:
- 120 110*
InitialI/Date: " I 1100 100 9o. 90 80 70 L.
60 0
fi-50 40 If 30 201 10
-H-I-I-4--]l- 0*-
0 10 20 30 40 50 50 70 80 90 100 110 Total Core Flow (Mlbmlhr)
(for SLO <75% Pump Speed Use Form GO-100-009-2)
Figure 9.1 SSES Unit 1 Cycle 19 Power/IFlow Map SUSQUEHANNA UNIT 1 TRM/3.2-60 SUSQEHANA NITTR/3.-60 DATE 11104/2015 EFFECTIVE
Rev. 16 PL-NF-14-001 Rev. 2 Page 60 of 62 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 fisted below:
SF = 1.11 Np = 15 Fp = 60OMlbm /hr SUSQUEHANNA UNIT ! TRM/3.2-61 UNT SUSQEHANA DATE 11/04/20 15 I RM/32-61EFFECTIVE
Rev. 16 PL-NF-14-001 Rev. 2 Page 61 of 82
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 I and 2, "RQDEX2 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, "ATRlUMW-10: Appendix K Spray Heat Transfer Coefficients," Siemens Power Corporation, September 2000.
- 4. XN-NF-84-105(P)(A), Volume 1 and Volume I Supplements 1 and 2, lJXCOBRA-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 I 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, t' 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 1 and 2, "Advanced Nuclear Fuels Corporation Critical Power Methodology for Boiling Water Reactors1 "
November 1990.
- 11. NE-092-001A, Revision 1, "Licensing Topical Report for Power Uprate With increased Core Flow," Pennsylvania Power & Light Company, December 1992 and NRC SER (November 30, 1993).
- 12. ANF-89-98(P)(A) Revision 1 and Supplement 1, "Generic Mechanical Design Criteria for BWR Fuel Designs," Advanced Nuclear Fuels Corporation, May 1995.
SUSQUEHANNA UNiT1 TRM/3.2-62 EFFECTIVE DATE 11/04/2015
Rev. 16 PL-NF-14-001 Rev. 2 Page 62 of 62
- 13. EMF-22O9(P)(A), Revision 3, "SPCB Critical Power Correlation," AREVA NP, September 2009.
- 14. EMF-85-74(P)(A), Revision 0, Supplement 1(P)(A) and Supplement 2(P)(A),
"RQDEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model,"
Siemens Power Corporation, February 1998.
- 15. EMF-2168(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 t Revision I 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-1 358(P)(A), Revision 3, "The Loss of Feedwater Heating Transient in Boiling Water Reactors," Framatome ANP, September 2005.
SUSQUEHANNA UNIT1 TRM/3.2-63 SUSQEHANA EFFECTIVE NITTR/3.-63 DATE 11/04/2015
Main Turbine Overspeed Protection System Rev. 2 3.3.7 3.3 Instrumentation 3.3.7 Main Turbine Overspeed Protection System TRO 3.3.7 One Main Turbine Overspeed Protection System shall be OPERABLE.
APPLICABILITY: MODES I and 2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Two of eight stop valves A.1.1 Close one of the inoperable 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and control valves valves.
AND A.1 .2 Limit THERMAL POWER 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> following
< 75% RTP. closure of the inoperable valve AND A.1.3 Apply the following limits for a 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> following closed Turbine Stop Valve or closure of the Turbine Control Valve as inoperable valve specified in the COLR:
OR A.2 Isolate main turbine from the 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> steam supply.
(continued)
SUSQUEHANNA-UNIT1 TRM / 3.3-17 SUSQEHANA-UITITRM 3.-17EFFECTIVE DATE 11/04/2015
Main Turbine Overspeed Protection System Rev. 2 3.3.7 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME B. Two of twelve intercept B.1 Close either the intercept 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> valves and intermediate valve or the intermediate stop stop valves inoperable, valve within one of the affected combined intermediate valves.
OR 8.2 Isolate main turbine from the 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> steam supply.
C. Turbine Overspeed C.1 Isolate main turbine from the 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Protection System steam supply.
inoperable for reasons other than Condition A or B.
SUSQUEHANNA-UNIT1 TRM / 3.3-17a SUSQEHANA
-UNI I RM DATE 11/04/2015 I3.317aEFFECTIVE
Main Turbine Overspeed Protection System Rev. 2 3.3.7 TECHNICAL REQUIREMENT SURVEILLANCE
~NOTE---- --------
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 up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the redundant overspeed trip device is OPERABLE.
SURVEILLANCE FREQUENCY
-- NOTE--..........----......
The provisions of TRS 3.0.4 are not applicable TRS 3.3.7.1 Cycle each high pressure turbine control valve from the 92 days running position and observe valve closure.
-- -- NOTE--...............................
The provisions of TRS 3.0.4 are not applicable TRS 3.3.7.2 Cycle each low pressure turbine combined intermediate 92 days valve from the running position and observe valve closure.
NOTE---------------------.....
The provisions of TRS 3.0.4 are not applicable TRS 3.3.7.3 Cycle each high pressure turbine stop valves from the 92 days running position and observe valve closure.
TRS 3.3.7.4 Perform a CHANNEL CALIBRATION of main turbine 24 months overspeed protection instrumentation.
TRS 3.3.7.5 Disassemble one of each type valve identified in 40 months on a TRS 3.3.7.1, TRS 3.3.7.2, and TRS 3.3.7.3, perform a STAGGERED TEST visual and surface inspection of valve seats, disks and BASIS stems and verify no unacceptable flaws or corrosion.
SUSQUEHANNA-UNIT1 TRM / 3.3-18 SUSQEHANA UNT I RM3.-18EFFECTIVE DATE 10/31/2007
Main Turbine Overspeed Protection System Rev. 2 B 3.3.7 B 3.3.7 Main Turbine Overspeed Protection System BASES TRO The Main Turbine Overspeed Protection System is designed to protect the main turbine from excessive overspeed by initiating a turbine trip by fast closure of the turbine control valves and closure of the intercept valves to essentially secure all steam flow to the turbine (Ref. 1).
To protect the turbine generator from overspeed conditions, two trip devices are provided. Either device, when initiated, will close the main stop valves, control valves, and combined intermediate valves thus isolating the turbine (Ref. 2).
These two trip devices are as follows:
- A mechanical overspeed trip which is initiated ifthe turbine speed reaches approximately 10% above rated speed, and o An electrical overspeed trip which serves as a backup to the mechanical trip and is initiated at approximately 12% above rated speed.
OPERABILITY of at least I of the 2 overspeed protection systems is required for the Turbine Overspeed Protection System to be considered OPERABLE.
Main Turbine Overspeed Protection System (MTOPS) OPERABILITY is also based upon the ability of the valves that control steam flow to the turbine to close following the receipt of a closure signal. The 4 stop valves, 4 control valves, 6 intermediate stop valves, and 6 intercept valves make up a system of 20 valves. A single failure to any one of the above system of 20 valves will not prevent a turbine trip (Ref. 2). Hence, if 19 of the 20 noted valves are OPERABLE, the MTOPS is OPERABLE. Note that for this statement to be true, the intermediate stop valves and intercept valves are considered separate valves. Overspeed protection is only disabled on a CIV failure if both valves within a CIV are inoperable. Failure of only one valve in a CIV does not prevent an overspeed trip, and does not affect operability. Actions to close one inoperable valve if two valves are inoperable maintain the unit within the analysis in Ref. 2. However, redundancy is reduced and repairs should be completed in accordance with the corrective action program.
Excessive turbine overspeed could generate potentially damaging missiles that could present a personnel and equipment hazard. MTOPS is not necessary to provide adequate protection of the public health and safety and is not required to obviate the possibility of an abnormal situation or event giving rise to an immediate threat to the public health and safety.
(continued)
SUSQUEHANNA - UNIT 1 TRM / B 3.3-14 SUSQEHANA
-UNI I TM
/BDATE 3.-14EFFECTIVE 06/25/2002
Main Turbine Overspeed Protection System Rev. 2 B 3.3.7 B 3.3.7 Main Turbine Overspeed Protection System BASES (continued)
ACTIONS The Actions are defined to ensure proper corrective measures are taken in response to the inoperable components.
A.1.l, A.1.2, A.1.3 and A.2 If two of eight stop valves and control valves are inoperable, action must be taken to restore at least one of the valves to OPERABLE status in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
This action ensures steam isolation to the turbine in the event of an overspeed condition, and maintains the unit within the bounds of the FSAR analysis. The 72-hour Completion Time provides a reasonable time to troubleshoot the problem, make repairs, and reduce power in an orderly manner if required without challenging plant systems. The required action if the problem is not resolved is to close one of the inoperable valves, or to isolate the main turbine from the steam supply. If one of the inoperable valves is closed, then limit thermal power to less than or equal to 75% of rated power, and apply Minimum Critical Power Ratio (MCPR) and Linear Heat Generation Rate (LHGR) limits as specified in the COLR within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Restricting thermal power to less than or equal to 75% of rated power eliminates possible shock loads to the turbine blades that could occur from a non-uniform circumferential steam flow distribution entering the HP turbine for this configuration. If the MCPR and LHGR limits are not in compliance with the applicable requirements at the end of this period, the ACTIONS required by the applicable specifications must be implemented.
This time is provided to stabilize operation with a closed Turbine Stop Valve or Turbine Control Valve.
B.1 and B.2 If two of twelve intercept valves and intermediate stop valves are inoperable, action must be taken to restore at least one of these valves to OPERABLE status in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. This action ensures steam isolation to the turbine in the event of an overspeed condition. The 72-hour Completion Time provides a reasonable time to troubleshoot the problem, make repairs, and reduce power in an orderly manner ifrequired without challenging plant systems.
The required action ifthe problem is not resolved is to close either the intercept valve or the intermediate stop valve within one of the affected combined intermediate valves, or to isolate the main turbine from the steam supply.
(continued)
SUSQUEHANNA-UNIT1 TRM / B 3.3-14a SUSQEHANA-NITI TR
/ 3.314aEFFECTIVE DATE 11/04/2015
Main Turbine Overspeed Protection System Rev. 2 B 3.3.7 B 3.3.7 Main Turbine Overspeed Protection System BASES ACTIONS C.1 (continued)
If the MTOPS is inoperable for reasons other than conditions A or B, then action must be taken to isolate the main turbine from the steam supply.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> allows a reasonable amount of time to complete the plant shutdown associated with isolating the main turbine from the steam supply.
TRS The TRSs are performed at the specified Frequency to ensure that the turbine overspeed protection function is maintained OPERABLE.
The TRSs are modified by a Note to indicate that 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 the redundant overspeed trip device is OPERABLE. Upon completion of the Surveillance, or expiration of the 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> allowance, the channel must be returned to OPERABLE status or the applicable Condition entered and Required Actions taken. This Note is based on the average time required to perform channel Surveillance. The 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> testing allowance does not significantly reduce the probability that the Main Turbine Overspeed Protection System will function when necessary.
TRS 3.3.7.1, TRS 3.3.7.2, and TRS 3.3.7.3 Verification of the movement of each of the four high pressure turbine control valves, six low pressure turbine combined intermediate valves (composed of 6 intermediate stop valves and 6 intercept valves), and four high pressure turbine stop valves ensures the OPERABILITY of each valve and that it will be able to close in the event of a turbine trip condition. The 92 day Frequency is based upon current surveillance practice as recommended by the turbine vendor and described in the FSAR (Ref. 3).
(continued)
SUSQUEHANNA - UNIT 1 TRM / B 3.3-14b SUSQEHANA-NIT TRM/
B3.314bEFFECTIVE DATE 11/04/2015
Main Turbine Overspeed Protection System Rev. 2 B 3.3.7 B 3.3.7 Main Turbine Overspeed Protection System BASES TRS TRS 3.3.7.4 (continued)
This TRS is for the performance of a CHANNEL CALIBRATION of the required main turbine overspeed protection instrumentation. The calibration is a complete check of the instrument channel from the sensing device to main turbine trip initiation. The Frequency of 24 months is a typical refueling cycle and considers channel reliability.
TRS 3.3.7.5 The disassembly and inspection of the valves referenced ensures that abnormal wear is not occurring which could result in the valves inability to close upon receipt of a close signal. The Frequency is such that only one of each type valve (i.e., high pressure turbine stop; high pressure turbine control; and low pressure turbine combined intermediate), is required to be inspected within a 40 month period. If unacceptable flaws or excessive corrosion are found in a valve, all valves of its type are inspected (Ref. 3).
Valve bushings are inspected and cleaned, and bore diameters are checked for proper clearance.
REFERENCES 1. FSAR Section 7.7:1.5
- 2. FSAR Section 10.2.2.6.
- 3. FSAR Section 10.2.3.6.
SUSQUEHANNA-UNIT1 TRM / B 3.3-14c SUSQEHANA
-UNITI TR
/ 3.314cEFFECTIVE DATE 11/04/2015
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TECHNICAL REQUIREMENT FOR OPERATION (TRO) APPLICABILITY & SURVEILLANCE (TRS)
APPLICABILITY TEXT 3.1.1 1 11/09/2007
Title:
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Title:
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Title:
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Title:
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Title:
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Title:
OPEN INSTRUMENTATION CONFIGURATION TEXT 3.3.10 1 12/14/2004
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~SES MANTJAIJ Manual Namue: TRMI Manual
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TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.4.1 1 04/26/2006
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Title:
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Title:
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Title:
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Title:
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Title:
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Title:
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Title:
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Title:
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SSES MANUJAL Manual Name : TE*I 21:Manual
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Title:
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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:
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Title:
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Title:
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PLANT SYSTEMS CONTROL STRUCTURE HVAC TEXT 3.7.10 1 12/14/2004
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PLANT SYSTEMS SPENT FUEL STORAGE POOLS (SFSPS)
TEXT 3.7o11 0 04/16/2009
Title:
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CONTINUOUS TEXT 3.8.2.2 2 12/14/2004
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Title:
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Title:
MISCELLANEOUS INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)
TEXT 3.10.4 2 04/17/2008
Title:
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... TEXT 3.11.2.1 3 04/26/2006
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Title:
RADIOACTIVE EFFLUENTS DOSE - IODINE, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM TEXT 3.11.2.4 0 11/18/2002
Title:
RADIOACTIVE EFFLUENTS GASEOUS RAD WASTE TREATMENT SYSTEM TEXT 3.11.2.5 4 07/03/2013
Title:
RADIOACTIVE EFFLUENTS VENTILATION EXHAUST TREATMENT SYSTEM TEXT 3.11.2.6 5 04/28/2015
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RADIOACTIVE EFFLUENTS RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION ac* TEXT 3.11.3 1
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RADIOACTIVE EFFLUENTS TOTAL DOSE 04/26/2006 Report Date: 11/11/15 Page *:i~ of of 16 I_66 Report Date: 11/11/15
SSES MANUAL Manual Name : TRMI Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT 3.11.4.1 5 03/05 /2015
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RADIOACTIVE EFFLUENTS MONITORING PROGRAM TEXT 3.11.4.2 2 04/26 /2006
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RADIOACTIVE EFFLUENTS LAND USE CENSUS 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 POOL 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 0
Title:
LOADS CONTROL PROGRAM LIGHT LOADS REQUIREMENT TEXT 4.1 0 08/31/1998
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ADMINISTRATIVE CONTROLS ORGANIZATION TEXT 4.2 0 08/31/1998
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ADMINISTRATIVE CONTROLS REPORTABLE EVENT ACTION TEXT 4.3 0 08/31/1998
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ADMINISTRATIVE CONTROLS SAFETY LIMIT VIOLATION TEXT 4.4 1 12/18/2008
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ADMINISTRATIVE CONTROLS PROCEDURES & PROGRAMS TEXT 4.5 0 08/31/1998
Title:
ADMINISTRATIVE CONTROLS REPORTING REQUIREMENTS TEXT 4.6 0 08/31/1998
Title:
ADMINISTRATIVE CONTROLS RADIATION PROTECTION PROGRAM 16Reprt Dte:11/1/1 Page8.a Page of 16 Report Date: 11/11/15
SSES MANUJAL
. 1-- Manual Name: TECHNICAL Manual
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TRMI REQUIREMENTS MANUAL UNIT 1 TEXT 4.7 0 08/31/1998
Title:
ADMINISTRATIVE CONTROLS TRAINING TEXT B3.0 5 03/05/2015
Title:
APPLICABILITY BASES TECHNICAL REQUIREMENT FOR OPERATION (TRO) APPLICABILITY TEXT B3.1.1 2 04/29/2014
Title:
REACTIVITY CONTROL SYSTEMS BASES ANTICIPATED TRANSIENT WITHOUT SCRAM ALTERNATE ROD INJECTION (ATWS-ARI) INSTRUMENTATION TEXT B3.1.2 0 11/19/2002
Title:
REACTIVITY CONTROL SYSTEMS BASES CONTROL ROD DRIVE (CRD) HOUSING SUPPORT TEXT B3.1.3 3 03/31/2006
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REACTIVITY CONTROL SYSTEMS BASES CONTROL ROD BLOCK INSTRUMENTATION TEXT B3.1.4 0 11/19/2002
Title:
REACTIVITY CONTROL SYSTEMS BASES CONTROL ROD SCRAM ACCUMU/LATORS INSTRUMENTATION AND CHECK VALVE TEXT B3.2.1 0 11/19/2002
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CORE OPERATING LIMITS BASES CORE OPERATING LIMITS REPORT (COLR)
TEXT B3.3.1 1 01/31/2014
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INSTRUMENTATION BASES SEISMIC MONITORING INSTRUMENTATION TEXT B3.3.3 3 12/18/2008
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INSTRUMENTATION BASES METEOROLOGICAL MONITORING INSTRUMENTATION TEXT B3.3.4 5 10/14/2015
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INSTRUMENTATION BASES TEN POST ACCIDENT MONITORING (PAM) INSTRUMENTATION
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- Manual Name: TRMI
=iManual
Title:
TECHNICAL REQUIREM'cENTS MANUAL UNIT 1 TEXT B3.4.6 2 04/25/2013
Title:
REACTOR RECIRCULATION SINGLE LOOP OPERATION SLO FLOW RATE RESTRICTION 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 2 04/17/2008
Title:
CONTAINMENT BASES SUPPRESSION POOL ALARM INSTRUMENTATION TEXT B3o6.4 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 TEXT B3.7.3.1 3 06/15/2010
Title:
PLANT SYSTEMS BASES FIRE SUPPRESSION WATER SUPPLY SYSTEM
- TEXT B3.7.3.2 2 04/26/2006 W.
Title:
PLANT SYSTEMS BASES SPRAY AND SPRINKLER SYSTEMS Page 1_1 of i__66 Report Date: 11/11/15
SSES MANUAL Manual Name: TRMI SManual Title* TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.7.3.3 0 11/19/2002
Title:
- PLANT SYSTEMS BASES C02 SYSTEMS TEXT B3.7.3.4 3 04/29/2014
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 STEXT B3.7.3.8 3 09/27/2012
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 TEXT B3.7.6 4 06/04/2013 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 Report Date: 11/11/15 Page 1/2 Page 12 of of 16 16 Report Date: 11/11/15
SSES MANTJAI~
Manual Name : TPR41 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.7.8 4 01/31/2 014
Title:
PLANT SYSTEMS BASES SNUBBERS TEXT B3.7.9 2 12/08/2011 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 1 04/14/2010
Title:
STRUCTURAL INTEGRITY TEXT B3.8.1 2 03/10/2010
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 1 11/14/2013
Title:
ELECTRICAL POWER BASES DEGRADED VOLTAGE PROTECTION TEXT B3.8.6 2 12/08/2011
Title:
ELECTRICAL POWER BASES EMERGENCY SWITCHGEAR ROOM COOLING TEXT B3.8.7 2 06/04/2013
Title:
BATTERY MAINTENANCE AND MONITORING PROGRAM Report Date: 11/11/15 Page i~
Page 13 of of ii 16 Report Date: 11/11/15
S.~ES MM~AL
<?=Manual Name: TRMI
"*Manual Titles° TECHNICAL REQUIREMENTS MANUAL UNIT 1 0 TEXT B3.9.l 0 11/19/2002
Title:
REFUELING OPERATIONS BASES DECAY TINE TEXT B3.9.2 0 11/19/2002
Title:
REFUELING OPERATIONS BASES COMM4UNICATIONS TEXT B3.9.3 0 11/19/2002
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 03/31/2006
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 B3.10.4 1 04/17/2 008
Title:
MISCELLANEOUS BASES LEADING EDGE FLOW METER (LEFM)
TEXT B3.ii.ioi 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES LIQUID EFFLUENTS CONCENTRATION TEXT B3ol.11Io2 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES LIQUID EFFLUENTS DOSE TEXT B3.ii.i.3 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES LIQUID WASTE TREATMENT SYSTEM TEXT B3.11.I.4 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES LIQUID RADWASTE EFFLUENT MONITORING INSTRUMENTATION TEXT B3.11.I.5 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES RADIOACTIVE LIQUID PROCESS MONITORING INSTRUMENTATION Report Date: 11/11/15 Page 14 Page 14 of of ~i* Report Date: 11/11/15
SSES MANUJAI O Manual Name: TRMI
... Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 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 - NOBLE GASES TEXT B3.11.2.3 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES DOSE - IODINE, TRITIUM, AND RADIONUCLIDES IN SPARTICULATES FORM TEXT B3.11.2.4 0 11/19/2002
Title:
RADIOACTIVE EFFLUENTS BASES GASEOUS RADWASTE TREATMENT SYSTEM TEXT B3.11.2.5 5 07/03/2013
Title:
RADIOACTIVE EFFLUENTS BASES VENTILATION EXHqAUST 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 5 03/05/2015
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 TEXT B3.12.2 1 12/03/2010
Title:
LOADS CONTROL PROGRAM BASES HEAVY LOADS REQUIREMENTS Report Date: 11/11/15 Page i~.
15 of of 16 I__66 Report Date: 11/11/15
SSES MANUJAL
- - Manual Name: TRN1
- Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 1 TEXT B3.12.3 0. 11/19/2002
Title:
LOADS CONTROL PROGRAM BASES LIGHT LOADS REQUIREMENTS Report Date: 11/11/15 Page 1616 of of 16 16 Report Date: 11/11/15
SUSQUEHANNA STEAM ELECTRIC STATION Rev. 64 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Titl__ee Effective Date TOC TABLE OF CONTENTS 04/23/2015 1.0 USE AND APPLICATION Page TRM / 1.0-1 10/04/2002 Page TRM / 1.0-2 01/21/2014 Page TRM / 1.0-3 10/04/2002 2.0 PLANT PROGRAMS Page TRM / 2.0-1 04/23/2015 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 01/21/2014 Page TRM / 2.0-6 03/27/2008 Page TRM / 2.0-7 05/15/2008 Pages TRM / 2.0-8 and TRM / 2.0-9 01/07/2011 Page TRM / 2.0-10 02/02/2010 Page TRM / 2.0-11 11/15/2004 Page TRM / 2.0- 12 03/27/2008 Pages TRM / 2.0-13 and TRM / 2.0-1* 11/15/2004 Page TRM / 2.0-15 11/15/2005 3.0 PI"I"LI*.jp?.DILI I I Pages TRM / 3.0-1 and 02/19/2015 Page TRM / 3.0-3 03/15/2002 Page TRM / 3.0-4 02/19/2015 REACTIVITY CON 3.1 Page TRM / 3.* 10/3112007 Pages TRM an 08/31/1998 Pages 3. 5 08/31/1998 Page TR 03/22/2006 04/07/2009 03/27/2008 3.1-9 and TRM / 3.1,9a 02/18/1999
.1-10 02/18/1999 3.2 iERATING LIMITS REPORT 07/07/1999 Pages TRM / 3.2-2 through TRM / 3.2-63 11/04/2015 3.3 INSTRUMENTATION Pages TRM / 3.3-1 through TRM / 3.3-3 07/16/1999 Page TRM / 3.3-4 and TRM / 3.3-5 10/31/2007 Page TRM / 3.3-6 03/10/2011 SUSQUEHANNA-UNIT1 TRM / LOES-1 SUSQEHANA UNT I RM LOS-1EFFECTIVE DATE 11/04/2015
SUSQUEHANNA STEAM ELECTRIC STATION Rev. 84 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date Page TRM / 3.3-7 10/31/2007 Page TRM / 3.3-8 08/31/1998 Page TRM / 3.3-9 10/07/2015 Page T'RM / 3.3-9a 06/30/2010 Page TRM / 3.3-10 10/31/2007 Page TRM /3.3-11 10/07/2015 Page TRM / 3.3-11a 10/07/2015 Page TRM I 3.3-12 03/30/2001 Page TRM / 3.3-13 01/07/2011 Page TRM / 3.3-14 12/1 4/1 998 Page TRM / 3.3-15, 04/11/2014 Page TRM I 3.3-16 01/07/2011 Page TRM / 3.3-17 11/04/2015 Page TRM / 3.3-17a 11/04/2015 Page TRM / 3.3-18 10/31/2007 Pages TRM / 3.3-19 through TRM / 3.3-21 10/22/2003 Page TRM / 3.3-22 03/27/2008 Page TRM / 3.3-22a 11/15/2004 Pages TRM / 3.3-22b through TRM / 3.3-22d 03/22/2006 Page TRM / 3.3-23 12/03/2004 Pages TRM / 3.3-24 and TRM I 3.3-25 05/16/2003 Page, TRM / 3.3-26 10/22/2003 Page TRM / 3.3-27 02/19/2015 Page TRM / 3.3-28 04/07/2009 3.4 REACTOR COOLANT SYSTEM Page TRM / 3.4-1 03/31/2006 Pages TRM / 3.4-2 through TRM / 3.4-5 10/23/11998 Pages TRM / 3.4-6 through TRM / 3.4-8 04/01/2009 Page TRM / 3.4-9 08/31/1998 Page TRM / 3.4-10 10/31/2007 Page TRM / 3.4-11 08/31/1998 Page TRM / 3.4-12 03/27/2008 Page TRM / 3.4-13 03/31/2006 Pages TRM / 3.4-14 and TRM / 3.4-15 04/25/2013 3.5 EMERGENCY CORE COOLING AND RCIC Page TRM / 3.5-1 01/28/2005 Pages TRM / 3.5-2 and TRM / 3.5-3 08/31/1998 Pages TRM / 3.5-4 and TRM / 3.5-5 10/31/2007 Pages 3.5-6 and 3.5-7 08/31/1998 SUSQUEHANNA- UNIT 1 TRM / LOES-2 LOS-2EFFECTIVE I RM UNT SUSQEHANADATE 11/04/2015
SUSQUEHANNA STEAM ELECTRIC STATION Rev. 84 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date 3.6 CONTAI NMENT Page 3.6-1 08/31/1998 Pages TRM / 3.6-2 and TRM I 3.6-2a 04/16/2014 Page 3.6-3 08/31/1998 Page TRM / 3.6-4 01/07/2002 Page 3.6-5 08/31/1998 Pages TRM / 3.6-6 through TRM / 3.6-8 12/31/2002 3.7 PLANT SYSTEMS Pages 3.7-1 through 3.7-3 08/31/1998 Page TRM / 3.7-4 03/31/2006 Pages 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 12/29/1999 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 04/07/2 009 Page TRM / 3.7-24 03/31/2006 Page TRM / 3.7-25 08/02/1999 Page TRM / 3.7-26 09/25/2012 Page TRM / 3.7-27 11/24/2011 Pages TRM / 3.7-28 through TRM / 3.7-34a 09/25/2012 Page TRM / 3,7-35 03/31/2006 Pages TRM / 3.7-36 and TRM / 3.7-37 02/01/1999 Page TRM / 3.7-38 02/19/2015 Page TRM / 3.7-39 08/31/1998 Page TRM / 3.7-40 03/31/2006 Page TRM / 3.7-41 05/24/2012 Pages TRM / 3.7-41a through TRM / 3.7-41c 05/24/2012 Page TRM / 3.7-42 09/04/2008 Page TRM / 3.7-43 08/31/1998 Page TRM / 3.7-44 02/19/2015 Pages TRM / 3.7-45 and TRM / 3.7-46 10/05/2006 Page TRM / 3.7-47 06/07/2007 TRM / LOES-3 EFFECTIVE DATE 11/04/2015 SUSQUEHANNA-UNITI SUSQUEHANNA-UNIT1 TRM / LOES-3 EFFECTIVE DATE 11/04/2015
SUSQUEHANNA STEAM ELECTRIC STATION Rev. 84 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date Page 10/05/2006 Page TRM TRM II 3.7-48 3.7-49 06/07/2007 Pages TRM / 3.7-49a and TRM / 3.7-49b 10/05/2006 Page TRM / 3.7-50 01/21/2014 Page TRM / 3.7-51 08/16/2006 Page TRM / 3.7-52 12/03/2004 Page TRM / 3.7-53 04/15/2003 Page TRM / 3.7-54 07/29/1999 Pages TRM / 3.7-55 through TRM / 3.7-57 04/01/2009 3.8 ELECTRICAL POWER Page TRM / 3.8-1 04/02/2002 Page TRM / 3.8-2 01/28/2005 Pages TRM / 3.8-3 and TRM /3.8-4 03/25/2010 Pages TRM / 3.8-5 and TRM / 3.8-6 04/02/2002 Page TRM / 3.8-7 10/31/2007 Pages TRM / 3.8-8 through TRM / 3.8-10 12/03/2004 Page TRM /3.8-11 09/03/2004 Page TRM / 3.8-12 12/03/2004 Page TRM / 3.8-13 02/19/2015 Page TRM / 3.8-14 08/31/1998 Pages TRM / 3.8-15 through TRM / 3.8-17 04/02/2002 Page 3.8-18 08/31/1998 Page TRM / 3.8-19 04/02/2002 Page 3.8-20 08/31/1998 Pages TRM / 3.8-21 and TRM / 3.8-22 06/06/1999 Page TRM / 3.8-23 11/07/2013 Pages TRM / 3.8-24 and TRM / 3.8-25 11/30/2011 Page TRM / 3.8-26 05/28/2009 Page TRM / 3.8-27 11/29/2006 Pages TRM / 3.8-28 and TRM / 3.8-29 05/28/2009 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 TRM / 3.10-2 and TRM / 3.10-3 08/31/1998 Page TRM / 3.10-4 08/01/2006 Pages TRM / 3.10-5 and TRM / 3.10-6 03/22/2006 Page TRM / 3.10-7 06/10/2010 Page TRM / 3.10-8 03/27/2008 SUSQUEHANNA - UNIT 1 TRM / LOES-4 SUSQEHANA UNT I RM LOS-4EFFECTIVE DATE 11/04/2015
SUSQUEHANNA STEAM ELECTRIC STATION Rev. 84 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date 3.11 RADIOACTIVE EFFLUENTS Page TRM / 3.11-1 03/31/2006 Pages TRM / 3.11-2 and TRM / 3.11-3 08/31/1998 Page TRM / 3.11-4 03/31/2006 Page TRM / 3.11-5 08/31/1998 Page TRM / 3.11-6 03/31/2006 Pages TRM / 3.11-7 and TRM / 3.11-8 08/31/1998 Pages TRM / 3.11-9 and TRM / 3.11-10 10/09/2012 Pages TRM / 3.11-11 and TRM / 3.11-12 08/31/1998 Page TRM /3.11-13 02/19/2015 Page TRM / 3.11-14 12/03/2004 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 Page TRM / 3.11-22 04/02/2002 Page TRM / 3.11-23 11/14/2006 Page TRM / 3.11-24 06/18/2013 Page TRM / 3.11-25 04/12/2007 Pages TRM / 3.11-26 and TRM / 3.11-27 01/21/2004 Page TRM /3.11-28 09/08/2009 Page TRM / 3.11-29 12/03/2004 Pages TRM / 3.11.30 and TRM / 3.11.31 01/21/2004 Page TRM / 3.11.32 04/23/2015 Page TRM / 3.11-33 03/31/2006 Page TRM / 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 Page TRM / 3.11-40 02/19/2015 Pages TRM / 3.11-41 through TRM / 3.11-43 08/31/1998 Page TRM / 3.11-44 08/01/2006 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 4.0-1 through 4.0-3 08/31/1998 Page TRM / 4.0-4 12/11/2008 Pages 4.0-5 through 4.0-8 08/31/1998 SUSQUEHANNA-UNIT1 TRM/LOES-5 SUSQEHANA UNT I RM LOS-5EFFECTIVE DATE 11/04/2015
SUSQUEHANNA STEAM ELECTRIC STATION Rev. 84 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 02/19/2015 Page TRM / B 3.0-4a and TRM / B 3.0-4b 02/19/2015 Page TRM / B 3.0-5 02/19/2015 Page TRM I B 3.0-6 08/31/1998 Page TRM I B 3.0-7 04/12/2007 Pages TRM / B 3.0-8 through TRM I 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 through TRM / B 3.0-15 02/19/2015 B 3.1 REACTIVITY CONTROL SYSTEMS BASES Page TRM / B 3.1-1 07/13/1999 Page TRM / B 3.1-2 04/16/2014 Page TRM /B 3.1-3 10/31/2007 Page B 3.1-4 08/31/1998 Page TRM / B 3.1-5 11/15/2005 Pages TRM I B 3.1-6 and TRM / B 3.1-7 03/22/2006 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 01/21/2014 Page TRM / B 3.3-2 03/10/2011 Page TRM / B 3.3-2a 10/31/2007 Page TRM / B 3.3-3 12/11/2008 Page TRM / B 3.3-3a 10/31/2007 Page TRM / B 3.3-4 06/30/2010 Page TRM / B 3.3-5 10/07/2015 Page TRM I B 3:3-6 06/30/2010 Page TRM I B 3.3-7 10/07/2015 Page TRM / B. 3.3-8 06/30/2010 Page TRM I B 3.3-9 10/31./2007 Pages TRM / B 3.3-10 through TRM I B 3.3-12 01/07/2011 Page TRM / B 3.3-13 01/21/2014 Page TRM / B 3.3-14 06/25/2002 Page TRM / B 3.3-14a 11/04/2015 Page TRM I B 3.3-14b 11/04/2015 Page TRM / B 3.3-14c 11/04/2015 Pages TRM / B 3.3-15 and TRM I B 3.3-16 10/22/2003 Page TRM / B 3.3-17 03/22/2006 Pages TRM / B 3.3-17a through TRM / B 3.3-17c 03/22/2006 Page TRM / B 3.3-17d 03/27/2008 TRM / LOES-6 EFFECTIVE DATE 11/04/2015 SUSQUEHANNA-UNITI SUSQUEHANNA - UNIT 1 TRM / LOES-6 EFFECTIVE DATE 11/04/2015
SUSQUEHANNA STEAM ELECTRIC STATION Rev. 84 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date TRMI IBB3.3-19 Pages TRM / B 3.3-17e andTRM 3.3-17f 03/22/2006 Pages TRM / B 3.3-18 and 08/03/2010 Page TRM / B 3.3-20 10/22/2003 Page TRM / B 3.3-21 05/16/2003 Pages TRM / B 3.3-22 and TRM / B 3.3-23 04/07/2009 B 3.4 REACTOR COOLANT SYSTEM BASES Page B 3.4-1 08/31/1998 Pages TRM / B 3.4-2 and TRM / B 3.4-3 04/01/2009 Pages TRM 1 B 3.4-4 and TRM / B 3.4-4a 10/31/2007 Page TRM / B 3.4-5 10/1 5/1 999 Page B 3.4-6 08/31/1998 Pages TRM / B 3.4-7 and TRM / B 3.4-8 04/25/2013 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 through 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 03/27/2008 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 Page TRM/IB 3.7-3 06/10/2010 Page 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 Page TRM / B 3.7-6 03/3"1/2006 Pages TRM / B 3.7-7 and TRM / B 3.7-7a 08/02/1999 Page TRM / B 3.7-8 O5/2 9/2013 Page TRM / B 3.7-9 04/11/2014 Page TRM / B 3.7-10 08/02/1999 Page TRM / B 3.7-I0a 03/31/2006 Page TRM / B 3.7-11 08/02/1999 Page TRM / B 3.7-11a 03/31/2006 Pages TRM / B 3.7-12 and TRM / B 3.7-13 08/02/1999 Pages TRM / B 3.7-14 and TRM / B 3.7-14a 09/25/20 12 EFFECTIVE DATE 11/04/2015 SUSQUEHANNA SUSQUEHANNA-UNIT1
- UNIT I TRM // LOES-7 TRM LOES-7 EFFECTIVE DATE 11/04/2015
SUSQUEHANNA STEAM ELECTRIC STATION Rev. 84 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date Page TRM / B 3.7-14b 11/24/2011 Pages TRM / B 3.7-15 and TRM I B 3.7-16 0210111999 Pages B 3.7-17 through B 3.7-20 08/31/1998 Page TRM I B 3.7-21 05/29/2013 Pages TRM / B 3.7-21a through TRM / B 3.7-21d 05/24/2012 Pages TRM / B 3.7-21e through TRM / B 3.7-21g 05/29/2013 Page TRM / B 3.7-22 and TRM / B 3.7-23 01/30/2008 Page TRM / B 3.7-24 10/05/2006 Page TRM / B 3.7-25 01/21/2014 Pages TRM / B 3.7-26 through TRM / B 3.7-28 10/05/2006 Pages TRM / B 3.7-29 and TRM I B 3.7-30 06/07/2007 Page TRM / B 3.7-30a 10/05/2006 Page TRM / B 3.7-30b 01/21/2014 Page TRM / B 3.7-31 11/30/2011 Page TRM / B 3.7-32 03/09/2001 Page TRM / B 3.7-33 04/15/2003 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 3.7-39 04/01/2009 Page TRM / B 3.7-40 04/08/2010 ELECTRICAL POWER BASES B 3.8 Page TRM / B 3.8-1 04/02/2002 Page TRM / B 3.8-2 01/28/2005 Page TRM / B 3.8-2a 03/01/2010 Page TRM / B 3.8-3 04/02/2002 Page TRM / B 3.8-3a 04/02/2002 Page TRM / B 3.8-4 09/03/2004 Page TRM / B 3.8-4a 04/02/2002 Page B 3.8-5 08/31/1998 Pages TRM / B 3.8-6 through TRM / B 3.8-15 04/02/2002 Page TRM / B 3.8-16 11/07/2013 Page TRM / B 3.8-17 11/30/2011 Pages TRM / B 3.8-17a and TRM / B 3.8-17b 11/30/2011 Pages TRM / B 3.8-18 through TRM / B 3.8-20 05/29/2013 Pages TRM / B 3.8-21 and TRM I B 3.8-22 05/28/2009 Page TRM I B 3.8-23 05/29/2013 Page TRM / B 3.8-24 05/28/2009 B.3.9 REFUELING OPERATIONS BASES Pages B 3.9-1 through B 3.9-7 08/31/1998 TRM / LOES-8 EFFECTIVE DATE 11/04/2015 SUSQUEHANNA - UNIT UNIT 1I TRM / LOES-8 EFFECTIVE DATE 11/04/2015
SUSQUEHANNA STEAM ELECTRIC STATION Rev. 84 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MAN UAL)
Section Title Effective Date B 3.10 MISCELLANEOUS BASES Page B 3.10-1 08/31/1998 Pages TRM / B 3.10-2 and TRM / B 3.10-3 03/22/2006 Pages TRM / B 3.10-4 and TRM / B 3.10-5 08/23/1999 Page TRM / B 3.10-6 03/27/2008 B 3.11 RADIOACTIVE EFFLUENTS BASES Pages B 3.11-1 through B 3.11-9 08/30/1998 Page TRM / B 3.11-10 02/01/1999 Pages TRM/B 3.11-11 and TRM/B 3.1 1-11a 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 / B3.11-15 02/01/1999 Pages B 3.11-16 through B 3.1 1-19 08/30/1998 Page TRM / B 3.11-20 04/02/2002 Page TRM / B 3.1 1-20a 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 Pages TRM / B 3.1 1-23a and TRM / B 3.1 1-23b 06/18/2013 Pages TRM / B 3.11-24 and TRM / B 3.11-25 01/21/2004 Pages B 3.11-26 and B 3.11-27 08/30/1998 Page TRM / B3.11-28 11/30/2005 Page TRM / B 3.11-29 02/19/2015 Pages TRM / B3.1 1-30 and TRM / B 3.11-31 05/29/2013 Page TRM /B 3.11-32 08/30/1 998 Page TRM / B 3.11-33 06/30/2010 Pages B 3.11-34 and B 3.11-35 08/30/1998 Page TRM / B 3.11-36 02/12/1999 B.3.12 LOADS CONTROL PROGRAM BASES Page TRM / B3.12-1 09/19/2007 Page TRM / B 3.12-2 11/29/2010 Page TRM / B 3.12-3 02/05/1999 TRM1 text LOES 11/4/2015 SUSQUEHANNA - UNIT 1 TRM / LOES-9 SUSQEHANA UNT I RM LOS-9EFFECTIVE DATE 11/04/2015
Core Operating Limits Report (COLR)
Rev. 16 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.
APPLI(CABILITY: SPecified in the referenced Technical Specifications.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME" A. Core Operating Limits not A,1 Perform action(s) described Specified in met. in referenced Technical referenced Specification. Technical Specifications.
TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE FREQUENCY
NOTE-.......... ............. .. N/A No associated Surveillances. Surveillances are implemented in the applicable Technical Specificatiorns.
SUSQUEHANNA-UNIT1 TRM / 3.2-1 SUSQEHANA
-UNI 1 TM/32-1EFFECTIVE DATE 0710711999
Rev. 16 PL-NF-14-001 Rev. 2 Page "i of 62 Susquehanna SES Unit I Cycle 19 CORE OPERATING LIMITS REPORT Nuclear Fuels Engineering September 2015 SUSQUEHANNA UNIT1 TRM!3.2-2 SUSQEHANA UNT I RM/32-2EFFECTIVE DATE 11/0412015
Rev. 16 PL-NF-14-001 Rev. 2 Page 2 of 62 CORE OPERATING LIMITS REPORT REVISION DESCRiPTiON INDEX Rev. Affected ,
No. Sections Description/Purpose of Revision 0 ALL Issuance of this COLR is in support of Unit I Cycle 19 operation.
1 ALL New COLR required due to Power/Flow Map revision.
2 ALL New COLR required for the inclusion of operating limits regarding a Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) closure event.
~J. J FORM NFP-QA-008-2, Rev. 1 SUSQUEHANNA UNIT 1 TRM/3.2-3 TRM/.2-3EFFECTIVE DATE 11/04/2015
Rev. 16 PL-NF-14-00i Rev. 2 Page 3 of 62 SUSQUEHANNA STEAM ELECTRIC STATION Unit I Cycle 19 CORE OPERATING LIMITS REPORT Table of Contents
1.0 INTRODUCTION
............................................................................ 4 2.0 DEFINITIONS................................................................................6 3.0 SHUTDOWN MARGIN ....................................................................... 6 4.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR).................. 7 6.0 MINIMUM CRITICAL POWER RATIO (MCPR)............................................ 9 6.0 LINEAR HEAT GENERATION RATE (LHGR) ...................................... ....... 27 7.0 ROD BLOCK MONITOR (RBM) SETPOINTS AND OPERABILITY REQUIREMENTS ............................................................................ 38 8.0 RECIRCULATION LOOPS - SINGLE LOOP OPERATION............................... 40 9.0 POWER I FLOW MAP .............................................. :......................... 58 10.0 OPRM SETPOINTS.......................................................................... 60
11.0 REFERENCES
................ ................................................................ 61 SUSQUEHANNA UNIT 1 TRM/3.2-4 SUSQEHANA NITTR/3..-4DATE 11/04/2015 EFFECTIVE
Rev. 16 PL-NF-14-0O1 Rev. 2 Page 4 of 62 1.0 iNTRODUCTION This CORE OPERATING LIMITS REPORT for Susquehanna Unit t Cycle 19 is prepared in accordance with the requirements of Susquehanna Unit 1, 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 1 TRM/3.2-5 UNT I RM/32-5 SUSQEHANA EFFECTIVE DATE 11/04/2015
Rev. 16 PL-NF- 14-001 Rev. 2 Page 5 of 62 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 LHGRFACT is a multiplier applied to the LHGR limit when operating at less than 108 Mlbm/hr core flow. The LHGRFAC1 multiplier protects against both fuel centerline melting and cladding strain during anticipated system transients initiated from core flows less than 108 Mlbmlhr.
2.5 LHGRFACp is a multiplier applied to the LHGR limit when operating at less than RATED THERMAL 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 I hr, below which the OPRM RPS trip is activated.
SUSQUEHANNA UNIT 1 TRM/3.2-6 SLJSUEHNNAUNITI EFFECTIVE TMI32-6 DATE 111/0412015
Rev. 16 PL-NF-1 4-001 Rev. 2 Page 6 of 62 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 (BOG) SHUTDOWN MARGIN (SDM) tests must also account for changes in core reactivty during the cycle. Therefore, the SUM 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 8DM) during the operating cycle and the calculated BOG core reactivity. If the value of "R" is zero (that is, BOG is the most reactivepoint in the cycle) no correction to the BOG 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 t TRM/3.2-7 SUSQEHANA UNTI RM/32-7 EFFECTIVE DATE 11104/2015
Rev. 16 PL-NF-14-O01 Rev. 2 Page?7 of 62 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 ATRIUMT'-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 1 TRM/3.2-8 SUSQEHANA UNT I RM/32-8 EFFECTIVE DATE 11/04/20 15
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AVERAGE AVERAGE PLANAR LINEAREXPOSURE PLANAR HEAT GENERATION RATE LIMIT VERSUS
-TWO LOOP OPERATION Coz ATRIUMTM-10 FUEL C:'(D7 FIGURE 4.2-1
Rev. 18 PL-NF-14-001 Rev. 2 Page 9 of 62 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 Technical Requirements Manual Reference Technical Requirements Manual 3.3.7 5.3 Description The MOPR 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-1O) shall be the greater of the Flow-Dependent or the Power-Dependent MOPR, depending on the applicable equipment operability status.
a) Main Turbine Bypass I EOO-RPT I Backup Pressure Regulator Operable Figure 5.2-1: Flow-Dependent MCPR value determined from BOO to EDOC Figure 5.2-2: Power-Dependent MOPR value determined from BOO to EGOC b) Main Turbine Bypass lnoperable Figure 6.2-3: Flow-Dependent MCPR value determined from BOO to EDOC Figure 5.2-4: Power-Dependent MOPR value determined from BOO to EGOC c) EOC-RPT Inoperable Figure 5.2-5: Flow-Dependent MCPR value determined from BOO to EOC Figure 5.2-6: Power-Dependent MCPR value determined from BOG to EOO d) Backup Pressure Regulator Inoperable Figure 5.2-7: Flow-Dependent MCPR value determined from BOO to EDOC Figure 5.2-8: Power Dependent MCPR value determined from BOG to EDOC e) One Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) Closed Figure 5.2-0: Flow-Dependent MCPR value determined from BOO to EGG Figure 5.2-1 O:Power-Dependent MCPR value determined from BOO to EDO SUSQUEHANNA UNIT 1 TRM/3.2-10 SUSQEHANA UITTRM3.2I EFFECTIVE 0DATE 11/04/2015
Rev. 16 PL-NF-1 4-001 Rev. 2 Page 10 of 62 The MCPR limits in Figures 5.2-1 through 5.2-10 are valid for Two Loop operation.
The MCPR limits for Single Loop operation are provided in Section 8.0.
5.4 Averauqe Scram Time Fraction Ifthe 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 UNIT1 TRM/3.2-11 SUSQEHANA UITTRM3.21 EFFECTIVE IDATE 11104/2015
Rev. i6 PL-NF-14-O01 Rev. 2 Page Iiof 62 Main Turbine Bypass I EOC-RPT I Backup Pressure Regulator Operable SUSQUEHANNA UNIT 1 TRM/3.2-12 NITTR/32I 2DATE 1110412015 EFFECTIVE SUSQEHANA
C' SSES UNIT 1 CYCLE 19 C 2.2 c,
2,1 z
z 2.0 z
1.9
._E 1.8 1.7 CD k* 0.
CA 0o 1.6 <)
1.5 m 1.4 Ill C)
H 1.3 rn ci 1.2 H 30 40 50 60 70 80 90 100 110 Total Core Flow (MLBIHR)
-o "o n, I Ill (.Q0 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS 1 EOC-RPT I BACKUP PRESSURE REGULATOR OPERABLE TWO LOOP OPERATION (BOC TO EOC)
FIGURE 5.2-1 * -< 0
. . .. . . . .. .... . .. ..... ...... .... .... .. . ... ... . . . . .. . . . . .. . . .... . .. ........ ,... .. .. .. .. . .. .. ,,,,,.. .. .. . . . . . ... ... .. 1... .. . . . .. . .. . .... ... . .. . . .. . . . .. . I J . .. .... . ,J , , =. .. ... .
cj SSES UNIT 1 CYCLE 19 0
z z
C z
1J H 0.
0 m
0 20 30 40 50 60 70 80 90 100 Core Power (% RATED)
"13 -O
- , I-MCPR OPERATING LIMIT VERSUS CORE POWER 0" MAIN TURBINE BYPASS I EOC-RPT I BACKUP PRESSURE REGULATOR OPERABLE TWO LOOP OPERATION (BOO TO EOC) (3 "
n Ii --.
FIGURE 5.2-2
Rev. 16 PL-NF- 14-001 Rev. 2 Page 14 of 62 Main Turbine Bypass Inoperable SUSQUEHANNA UNIT1 TRM/3.2-15 UITTRM3.2l EFFECTIVE SUSQEHANA 5DATE 1 1/04/2015
0 SSES UNIT 1 CYCLE 19 2.2 03 C
2.1 LEGENDA
MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME
-CURVE CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME z
C 2.0 z
-1 1.9 I INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 1.8 H. '1.7 0J o-01 1,6 1.5
-I"I 1.4
--- I EEENCE:_T.S. 3.7.6 and 3.2.2 ___________ __________
'1.3 m
Hr iii 1.2 30 40 50 60 70 80C I0 100 110 Total Gore Flow (MLB/H-R)
--t "D "
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS INOPERABLE TWO LOOP OPERATION (BOC TO EOC)
FIGURE 5.2-3 ,.-4 <
Q)"*
0
CI, SSES UNIT 1 CYCLE 19 C 3.6 Ci, C
mR c
Z
-t
.E_
-H 0
$o O.
-.4
-11 "51 m
z3
-H
<m Fi 20 30 40 50 60 70 80 90 100 Core Power (% RATED)
(73 -U 51 MCPR OPERATING LIMIT VERSUS CORE POWER CD CD-
- MAIN TURBINE BYPASS INOPERABLE Z TWO LOOP OPERATION (BOC to EOC) 77 FIGURE 5.2-4 -- h 0)
Rev. 16 PL-NF-14-001 Rev. 2 Page 17 of 62 EOC-RPT Inoperable SUSQUEHANNA UNIT 1 TRM/3,2-18 SUSQEHANA UITTRM3.2I EFFECTIVE 8DATE 11/04/2015
CD SSES UNIT 1 CYCLE 19 2.2 03 LEGEND C
m 2.1 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM
=
INSERTION TIME 2.0 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME C
z 1.9 4. SAFETY* ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2
-H E I I IJ 1.8 L.
USED INDETER[MIN1NG MFLCPR I
-4. 1.7 0.
C0 o CD 1.6 -3.
C) 1.5
-rr 1.4
REFERENCE:
T.S. 3.3.4.1 and 3.2.2
--Il
<r m 1.3 m
1.2 30 40 50 60 70 80 90 100 110 U Total Core Flow (MLBIHR)
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW EOC-RPT INOPERABLE *QcD TWO LOOP OPERATION (BOC TO EOC)
FIGURE 5.2-5 0""
ci SSES UNIT 1 CYCLE 19 C
I z
z z
E 0
(D 0
C) m n-I 0
H m
0 50 60 90 H* 20 30 40 Core Power (% RATED) 70 80 100 n-MCPR OPERATING LIMIT VERSUS CORE POWER *(D Z EOC-RPT INOPERABLE TWO LOOP OPERATION (BOC to EQO) O-" -1 FIGURE 5.2-8 (O1*--
Rev. 16 PL-NF-14-0O1 Rev. 2 Page 20 of 62 Backup Pressure Regulator Inoperable SUSQUEHANNA UNIT 1 TRM/3.2-21 NIT TR/3.-21 DATE 11/04/2015 EFFECTIVE SUSQEHANA
SSES UNIT 1 CYCLE 19 Cn 2.2 LEGEND m
2.1 _____________ -CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME z
C 2.0 ________ -CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME z
1.9 _______ _______ - SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 1.8 I-1.7 r*o 0 A BI
- 10. 0, 1.6 1.5 m
"1 1.4 rri 0
IREFERENCE:
TS. 3.7.8 and 3.2.2~
1.3 I-~ { 4 1 ~~-f 108, 1.221 m 1.2 30 40 50 60 70 80 90 100 110 Total Core Flow (MVLB/HR)
"-D "-
0 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW BACKUP PRESSURE REGULATOR INOPERABLE "'.)
0 o', TWO LOOP OPERATION (BOC TO EQO)
FIGURE 5.2-7 "*' <c 0 0)"
SSES UNIT I CYCLE 19 60 C
z 0,
.2
-Il CD C
-3.
0)
'i,,
100,1.35 m
20 30 40 50 60 (% RATED) 70 Core Power 80 90 100 o1 T1 T1
-L
- Q2 Z~
MCPR OPERATING LIMIT VERSUS CORE POWER BACKUP PRESSURE REGULATOR INOPERABLE TWO LOOP OPERATION (BOO to EOC)
FIGURE 5.2-8 -,h . 0 0)' ,C
Rev. 16 PL-NE-14-001 Rev. 2 Page 23 of 62 One TSV. or TCV Closed SUSQUEHANNA UNIT 1 TRM/3.2-24 SUSQEHANA UIT ITR IS.-24 EFFECTIVE DATE 11104/2015
SSES UNIT 1 CYCLE 19 2.2 I LEGEND 2,1 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 2.0 _______
_______ -CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME
-r" 1.9 130, 1.831 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES NJ I ARE OPERABLE PER SR 3.7.5.1 AND 3.7.6.2 U' .4-1.8
- _ USED IN DETERMINING MFLCPR E2 1.7 C., 1.6 CD 1.5 m
-I-1 1.4 m
REFERENCE:
T.S. 3.2.2 and TRM 3.3.71 0
I-4 1.3
_ _ I _ I_ _ _ _ _ _ _ _ _ _
1.2 m
30 40 50 60 70 80 90 100 110 Total Core Flow (MLBIHR) 0 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW CD Z N)
TWO LOOP OPERATION (BOC TO EOC) - ,-<
FIGURE 5.2-9 0
cj SSES UNIT 1 CYCLE 19 C
m z
C z
S 0.-
-I 0m
- 0 CD m
-n m
m C)
-9 20 30 40 50 60 70 80
- Core Power (% RATED)
MCPR OPERATING LIMIT VERSUS CORE POWER
FIGURE 5.2-10
Rev. 16 PL-NF-14-O01 Rev. 2 Page 26 of 62 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 - oo70 3.440 Average Scram Realistic Maximum Insertion Time Allowable SUSQUEHANNA UNIT 1 SUQEAN NTITRM/3.2-27 EFFECTIVE DATE 11/0412015
- 1. . . .1 I * ... A... . . - -- a L.~cgaa. . .. .. * .1 L. * -- . .*... ..&. aaau I 1S a. . .... aJ L&...aa......a..n.
Rev. 16 PL-NF- 14-001 Rev. 2 Page 27 of 62 6.0 LINEAR HEAT GENERATION RA*TE (LHGR) 6.1 Technical Specification Reference Technical Specification 3.2.3, 3.3.4.1, 3.7.6, and 3.7.8 6.2 Technical Requirements Manual Reference Technical Requirements Manual 3.3.7 6.3 Description The maximum LHGR for ATRIUMTZ-I 0 fuel shall not exceed the LHGR limit determiined 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 in the following figures:
a) Main Turbine Bypass Operable Figure 6.2-2: Flow-Dependent LHGR Uimit Multiplier Figure 6.2-3: Power-Dependent LHGR Limit Multipiier b) Main Turbine Bypass Inoperable Figure 6.2-4: Flow-Dependent LHGR Limit Multiplier Figure 6.2-5: Power-Dependent LHGR Limit Multiplier c) One Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) Closed Figure 6.2-6: Flow-Dependent LHGR Limit Multiplier Figure 6.2-7: Power-Dependent LHGR Limit Multiplier
- The LHGR limits and LHGR limit multipliers in Figures 6.2-2 and 6.2-3 are applicable to EOC-RPT Operable and Inoperable and Backup Pressure Regulator Operable and Inoperable.
- The LGHR limits and LHGR limit multipliers in Figures 6.2-1 through 6.2-7 are valid for both Two Loop and Single Loop operation.
SUSQUEHANNA UNIT 1 TRM/3.2-28 SUSQEHANA EFFECTIVE NITTRI3.-28 DATE 11/04/2015
C,)
SSES UNIT 1 CYCLE 19 C 16.0 Ii Ii II ii i iI ii ii a ili a iI l Ii i !i Co a a la a a l la l a l 0 a a
a a
a a I I I I El 11111 ' I* I I
C I !
m lala al ala a alalala alIlal al a la aa a a a a L +/- Z .... L 1 - - .....t....J......-
= -
z '14.0 0.,3.---- f=--I--+ I 900 ,-I--S-I--..
4 ..J- REFERENCE; T.S 3.2.3 z L- i- - - I I I a a a. a . . a . .a . .a . .a . I & a 1 a a a a I a I a. I. ~ alala IaI-aI I I IaIaI l aI IaI a Ial al l lalal lala C
a[
a a
a aI la a al ia I Ia a a a ia a I alalalala I a la alaa a a a a
a la a
l n
a .a .a a l la aal . . . . 1I t. t. .1 I .. . .. . .. ..... .. .
4" z La-Ial lal la"1a1 aI 1ajj ~ I i jII !i i l 12.0 al a lala alalal aI a i l a a /aaa a a1 1 a a1 2 a . .a. a. a a a a, a a Iaf a a I a at aIa aI a a.a.a. a. a aIa a ala aIalal lii l al al l al a l 0
Cu ~II I I II Ia I I I I I Ia 1 1 11 1 11 1 ~I I Ia I aaI a I I a
I l
aaI Ia a. I a a I
al I a I I II a
H C a I l lall l la iala lalala al aialaIa a
'a" 10.0 Cu a- ta l al la a al
-- al-- aI a 4aIaa a- a- a aIaI a aI a--a a- a a-- a- a a aI IIaa a a IIaI I aa aIa a4 - I * -
0 aa a a a a a a a aia a aIa a Iaaatai i iiaa a a ,aaa a a a ,aaa aa a Il
, , CD a Ia a la a alalI a a a a a a a a a a a a a l a a a Ialal .a . .a.aa .a .a a a a a a a a a a a a Ia aIa a aI aI .a a .a.. a a N) V aI a al i lalalala a a alal aI a a1 C I l l l l l1-Ta-TaII l l I I-I I-yi rw- l l l- . . .
N) CD a a i a a lalala a la a a a a a al a
la.
a"a a
a a
a ai a a alal a
a a
a a
a a
a a
l a
ia a a l la la a
a la l
a l
a la a
l i
4-a Co 0 aI a I Ia I Ia I a a Ia a Ia a a a la a a l la l la a a al Ia a la a la a a a l 0) 0 I- 8.0 0 I I I Ill I I I a I iII Ia Il I *l lll ali C
Ial a lI ll l a 1 l i l lI l . a. al
.a. l 1 l 7 l iI al~
l l l l1l l l lal lal l lanl l l i mm I I I II I I I I I I I I I I I I I I
-I- 6.0 rn .a.. .a.. a a j , , I a , , t , ,I a a ,iI, a a I !
H 11 11 1 1 11 1111 ai lal a all a a al a aI 1 I a I a a a C 4.0 0 10000 20000 30000 40000 50000 60000 70000 80000 H
Pellet Exposure (MWDIMTU) rr T-0 "
-I- UNEAR HEAT GENERATION RATETMLIMIT VERSUS PELLET EXPOSURE ATRIUM -10 FUEL FIGURE 6.2-1 Oco a-0")' 0
Rev. 16 PL-NF-'I4-001 Rev. 2 Page 29 of 62 Main Turbine Bypass Operable SUSQUEHANNA UNIT 1 TRM/3.2-30 SUSQEHANA NITTR/3.-30 DATE 11/04/2015 EFFECTIVE
C,,
SSES UNIT 1 CYCLE 19 Co 1.10 1.00 z
z 0.90
-I--
0.80
-I ._1
('3 0.70 a, <D
('3
._)
0.60 0,50
-n r-n m 0.40 m
0.30
-I 30 40 50 60 70 80 90 100 110 m: Total Core Flow (MLB/hr)
- 0) FLOW DEPENDENT LHGR LIMIT MULTIPLIER NJ MAIN TURBINE BYPASS OPERABLE (03 ATRIUMT*-10 FUEL FIGURE 8.2-2
SSES UNIT 1 CYCLE 19 1.10 L I & "" 'U"' ........... * " '
- m L 4 4 *
- A A i C
m3 LEGEND
.. " ' '
- t I " I I i
I ii Fji o T ---- ,-------~.------.I-------, 9 CURVE A: BASE CURVE 1.00 CURVE B: CORE POWER __26% AND CORE FLOW <_.0 MLBM1HR
- I TI rS I 1 31 1 --- I - . ..- j. a .I - * -- -
0.90 I I I I a I i I I
"-I II l l* i I [ aI I li l i k I I
I
.1_J IIS
_ _ J. _
I
. 1 IJ ;
1 _1 J LI z
I--
0.80 I I I I I 1 1 5 I I I I I 1 I I I I I
,.I I l ARE OPRAL PE SR ANI37lI...
0.70 . . ..._
- 1*. 1. * * ._ ._ . . . . . . . . .
C) /II I I 1 I ___ _ _ ___ ___ __ ___ ___ _
1_-
H 0.
0 0.60
__..,. . IL.__J._.I * ..- 1 REOERABENCE: TSR 3.2.3,1 3.A4N 3.7.6 an 8 I I
iH i _ 1i_
- /
0.50 -
03 iL I yr i I" '-- "" ' "- - ! . .. .... .. . . .. .-. -- - '- - -l . - - * - * - ; ' .. . .
l 26 04 N,3 0.40 23 I -" -
0.0.
I I...
II -'-I....
I
.. F - I-'
, ~l, I-
- I I * --I - - - - -l-I
, , I
-- - It - -
3I - *
/ - f - I- -
I ,
-I - d - -
i I I I I I I I I I I I
! ,, IJ, J I I I I I r I I I I I I I - 3 I I 0 0.30 I I II I r I I 1 2,0 30 40 50 Core Power 60 (% RATED) 70 80 90 100 POWER DEPENDENT LHGR LIMIT MULTIPLIER MAIN TURBINE BYPASS OPERABLE o ,z AT*iUMTM-10 FUEL FIGURE 6.2-3
Rev. 16 PL-NF-14-O01 Rev. 2 Page 32 of 62 Main Turbine Bypass Inoperable SUSQUEHANNA UNIT I TRM/3.2-33 SUSQEHANA NITTR/3.-33 DATE 11t10412015 EFFECTIVE
SSES UNIT 1 CYCLE 19 Co 1.10 I
z 1.00 C:
Z 0.90 0.
0.80
.-I "-J C;, ._ 0.70 C;o 0,
C),. 0) 03 0.60 0o Ct 0.50 m
C)
-H m1 0.40 0
H-1 m] 0.30 30 40 50 60 Total Core Flow 70 80 90 100 110 (MLB/HR)
"0 "-
nD FLOW DEPENDENT LHGR LIMIT MULTIPLIER C.D z MAIN TURBINE BYPASS INOPERABLE 01 ATRIUMTMea-t FUEL -Il 0O FIGURE 6.2-4 0
CO, SSES UNIT 1 CYCLE 19 C 1.10 03 m
=
z z
C z
a..
.5.
.5 0
--I -I a,
1'3 a, oD 0
I..
a) 0 0.
m m
0
.-I m
0 4> 20 30 40 50 60 (% RATED) 70 Core Power 80 90 100
--I, 01" POWER DEPENDENT LH-GR LIMIT MULTIPLIER MAIN TURBINE BYPASS INOPERABLE Co C? ATRIUMTM.-10 FUEL FIGURE 6.2-,5 0"C*
Rev. 16 PL-NF-14-00l Rev. 2 Page 35 of 62 One TSV or TCV Closed SUSQUEHANNA UNIT 1 TRM/3.2-36 NITTR/3.-36DATE 11/04/2015 EFFECTIVE SUSQEHANA
0 O SSES UNIT 1 CYCLE 19 1.10 C
i"1 1.00 C
z 0.90 a,
-H1 0.80
-_J 0.70 CD CD
",4 0.60 U..
0.50
-T1
-IT 0.40 m
m 0.30 0 30 40 50 60 Total Core 70Flow (MLB/hr) 80 90 100 110 rl3 FLOW DEPENDENT LHGR LIMIT MULTIPLIER 0 ONE TSV OR TCV CLOSED* 0-" 0 ATRIUMTM-t10 FUEL D' I, -=
FIGURE 6.2-6
- 75% rated power.
n ,, n
C',
SSES UNIT 1 CYCLE 19 C
03 m
C z
13
{.i
--I ,-J
.1_
C,)
0 cc 0L 0) mT "rn ml 0
m1 H3 20 30 40 50 (% RATED)
Core Power 60 70 80 rn
-I POWER DEPENDENT LHGR LIMIT MULTIPLIER CD Z ONE TSV OR TCV CLOSED ATRIUMTM-10 FUEL *i-- n FIGURE 6,2-7 c0*
Rev. 16 PL-NF-14-OO1 Rev. 2 Page 38 of 82 7.0 ROD BLOCK MONITOR (RBM SETFOINTS AND OPERABILITY 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, d) Low Power Range - Upscale, e) Intermediate Power Range - Upscale, and I) 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. Ifthe 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.
SUSQUEHANNA UNIT 1 TRM/3.2-39 NITTRIS.-39 DATE 11/04/2015 SUSQEHANA EFFECTIVE
Rev. 16 PL-NF-14-001 Rev. 2 Page 39 of 62 Table 7.2-I RBM Setpoints Allowable Nominal Trip Function Value( 1 ) 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 117.4 117.0 High Power Range - Upscale 107.6 107.2 (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)
> 28 andc<90 < 1.76
~90 and <95 <1.47
>_95 < 1.70 (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.
SUSQUEHANNA UN]T 1 TRMI3.2-40 SUSQEHANA NITTRI3.-40 DATE 11/04/201 5 EFFECTIVE
Rev. 18 PL-NF-1 4-001 Rev. 2 Page 40 of 62 8.0 REGIRCULATION 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 Technical Req~uirements Manual Reference Technical Requirements Manual 3.3.7 8.3 Description APLHGR The APLHGR limit for ATRlUMTM-I 0 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 (ATRIUM TM-10) shall be the greater of the Flow-Dependent or the Power-Dependent MCPR, depending on the applicable equipment operability status.
a) Main Turbine Bypass I 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 [noperable 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 IEOC c) EOC-RPT Inoperable Figure 8.2-6: Flow-Dependent MCPR value determined from BOG to EOC Figure 8.2-7: Power-Dependent MCPR value determined from BOC to EOC SUSQUEHANNA UNIT 1 TRMI3.2-41 NIT TRI3.-41EFFECTIVE SUSQEHANA DATE 11/04/2015
Rev. 18 PL-NF-14-OO1 Rev. 2 Page 4l of 62 d) Backup Pressure Regulator Inoperable Figure 8.2-8: Flow-Dependent MCPR value determined from BOO to EGOC Figure 8.2-9: Power-Dependent MCPR value determined from BOO to EDO e) One Turbine Stop Valve (TSV) or Turbine Control Valve (TCV) Closed Figure 8.2-1O:Flow-Dependent MOPR value determined from BOO to EDO Figure 8.2-11 :Power-Dependent MOPR value determined from BOO to EOC The MOPR limits in Figures 8.2-2 through 8.2-1 1 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 andOperabilityRequirem~ents The RBM setpoints and operability requirements for Single Loop Operation are defined in Section 7.0.
SUSQUEHANNA UNIT 1 TRM/3.2-42 NITTRI3.-42 DATE 1110412015 EFFECTIVE SUSQEHANA
C 16.0 T T T r T ~ T ~ u 1 1 ~ I r QI I I ' I I l Il l t I I la 1 l l 9 i0 1 '
I E lI I I Ii l l l llI lI l
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1o 1 11 1111 1 Il liIljlIlIIIIIl l l ll II l l l Illl I l l I I Il l 4.0 L U' i41-- LI4l2 M - -L -- ~L- AJ-J L..L
........... ... -- , I , ,. , I 0.0 l1000. l 2000.0 ll 000. 4000.08000.06000.07000.
-L~l l l l l l l lI l l i l l Averag PlanalEpour MWIMTU)l o = a l l l l l l l l2l l l i t l l A ' I I I I l * . . Ca AVRAEPLNR INA HA GENERATION RAELMITlERSUtll o AERAE PANA EPOSRE..SIGL.LOP.OERAIO ATRIUMTMAOll FUELll l l owlll FIGURE 8.2-1ll l l l l l l lI I
...... , , J2J***
..... . . . .. . .. .... .....*.. ....................... . ..... ..... ..... .......... ... * . .... .......... ... ... ................. ...... ................... ......... ....... . ..... . .. .. r*, i, . ... .. ... . .. ... .... .. .
Rev. 16 PL-NF.-14-001 Rev. 2 Page 43 of 62 Main Turbine Bypass I EOC-RPT/I Backup Pressure Regulator Operable SUSQUEHANNA UNIT 1 TRM/3.2-44 UITTRM3.2-44 SUSQEHANA EFFECTIVE DATE 11/0412.015
9 SSES UNIT 1 CYCLE 19 3.6 I I I LEGEND m 3.4 4. a- CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM z INSERTION TIME z 3.2 + I 4-C CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME z
3.0 t 1--i.
m I II II . . I H0 4-.
D.1 o~
2.8 2.6 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES L
ARE OPERABLE PER SR 3.7.6.t AND 3.7.6.2 I I Ii USED INDETERMINING MFLCPR K
0, 2.4 0
2.2 2.0 i'1
-m '.8 rI,
REFERENCE:
" T.S. 3.4.1 and 3.2.21 108, 1.49' 1.6 H
-m 0 '1.4 1N1 70 80 90 100 110 0 30 40 50 60 Total Core Flow (MLB/HR)
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW Co MAIN TURBINE BYPASS 1 EOC-RPT / BACKUP PRESSURE REGULATOR OPERABLE SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8.2-2
9 0 SSES UNIT I CYCLE 19 4.6 o0 4.4 ___ LEGEND 4.2
________CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM
____INSERTION TIME z 4.0 ____________CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME
~-CURVE C: CORE POWER _<26% AND coRE FLOW
- 50 MLBM/HR 3.6 S 3.4
--fl!SAFETY ANALYSES ASSUME THAT F~OUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 3.2 Ho 03 3.0 _____USED IN DETERMINING MFLCPR 1.
N)
CD 0 2.8 0);
0) 2.6 2.4 2.2 f 140. 2.08!
,4 0A-B-BT*
4 -.-------- ~ I "t100, '
2.0 F *, ... .. . .. .
-Iil m
t 1.8 0 REEEC: T.S. 3.4.1 and 3.2.2 "Z 1.6 Hr o 1.4 20 100 mn 2040 50co 60*( RAE70 80 90 "0 "
MCPR OPERATING LIMIT VERSUS CORE POWER CD MAIN TURBINE BYPASS I EOC-RPT I BACKUP PRESSURE REGULATOR OPERABLE SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8.2-3 °< I
"* O 0)' C
Rev. 16 PL-NF-14-OO1 Rev. 2 Page 46 of 62 Main Turbine Bypass Inoperable SUSQUEHANNA UNIT1 TRM/3.2-47 SUSQEHANA NITTR/3.-47 DATE 1110412015 EFFECTIVE
C' SSES UNIT 1 CYCLE 19 4.2 I I II C-
________ ________ LEGEND 4.0 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 3.8 - INSERTION TIME z
z
________________CURVE B: REALISTIC AVERAGE SCRAM iNSERTiON TIME 3.6 z
3.4
- SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS -
,4D 3.2 VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 o* 3.0 H0 0
CD co3 0) 2.4.
2.2 m 2.0 "I1 m .
1.8 -1
REFERENCE:
T.S. 3.4.1, 3.7.6,, and22 -- _,118 0
m 1.6 _ _ _ _ _I _ _ _-_-_-_
1.4 m
30 40 50 60 Total Core 70 80 90 t00 110 Flow (MLB/HR) 0 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW CD Z
-J. MAIN TURBINE BYPASS INOPERABLE SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8,2-4 0 o)"
C, SSES UNIT I CYCLE 19 4.2 123,4A41 * =* *l "1 I " m l C-Cin I LEGEND 4.0 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM F INSERTION TIME z 3.8 z CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME
~, 3,61 ____________ 4-Z
-I 3.6 CURVE C: CORE POWER_*26% AND CORE F~LOW _<50 MLBMIHR
.t-l 3.4 I m
.1.a 1I~Z~38 I--.*- 4. I-I E
-I Cu 3.2 ISAFETY VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6,2 ANALYSES ASSUME THAT TWO OR MORE BYPASS w 3.0 USED IN DETERMINING MFLCPR I-0.
1~oi C~) 0
.41 CD N)
- a. 2.8 CO 0 ______ _ ________ 0) 2.6 2.4 2,2 m
2.0 0r
REFERENCE:
T.S. ,3.4.1, 3.7.6, and 3.2.2 ..
-I 1.8 20 30 40 6060 Power (%o o70RATED) 80 90 100 50Core "0 "T CD MCPR OPERATING LIMIT VERSUS CORE POWER Com I N) MAIN TURBINE BYPASS INOPERABLE .CD SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8,2-5 ow.
- h. h< .-
Rev. 16 PL-NF-14-O0l Rev. 2 Page 49 of 62 EOC-RPT Inoperable SUSQUEHANNA UNIT 1 TRM/3.2-50 SUSQEHANA NIT TR/3.-5OEFFECTIVE DATE 11/0412015
p SSES UNIT 1 CYCLE 19 4.0 LEGEND m 3.8 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM~
z 3.6 ________________INSERTION TIME z
C CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.4 z
3,2 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVESl E 3.0 - ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2
,U
-1 I-2,8 USED IN DETERMINING MFLCPR 4,
0.
2.6 0
N, 0I 2.4 0) 2.2 2.0 m 1.8 0
REFERENCE:
T.S 3..,.341 and 3.2.2 _ "_-_-_-[_08t" 1.6 1.4 m 30 40 50 60 70 80 9t0 100 110 Total Core Flow (MLB/HR)
- , ,I-0 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW 4* EOC-RPT INOPERABLE -Q* .:
SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8.2-6
C*
SSES UNIT 1 CYCLE 19 Cb 0*
z
.-I C.'
CD C.,
N)
C,' 0)
'-I"1
['11
-IT m
1-1 20 30 40 5060 Power' (% RATED) 70 80Core 80 90 100 m -U -D MCPR OPERATING LIMIT VERSUS CORE POWER Co z EOC-RPT INOPERABLE 0,-
SINGLE LOOP OPERATION (BOC to EOC) ,C FIGURE 8.2-7 ow' 0
Rev. 15 PL-NF-14-OO1 Rev. 2 Page 52 of 62 Backup Pressure Regulator Inoperable SUSQUEHANNA UNIT 1 TRM/3.2-53 SUSQEHANA NITTRIS.-53 DATE 11/04/2016 EFFECTIVE
C',
SSES UNIT I CYCLE 19 CO 4.0 I I I I m 3.8
- MAXIMUM ALLOWABLE AVERAGE SCRAM z
3.6 INSERTION TIME V
I .
C I: REALISTIC AVERAGE SCRAM INSERTION TIME z 3.4 4 4.-
3.2 f , , .. ,I.,,.I,, I , " "
S C
3.0 2,8 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 USED IN DETERMINING MFLCPR 2
H* C) a.
0 2,6 CD 0~
C, 2.4 2,2 2.0 r-n
-n' rni 1.8 A-
__---_ _ _ ___ __ B
REFERENCE:
T.S. 3.4.1, 3.7.8, and 3.2.2[ ____.__ .. _. _ _ .J._108, 1.48 1.6 m
1,4 30 40 50 60 70 80 90 100 110 Total Core Flow (MLBJHR) w r 0*
MOPR OPERATING LIMIT VERSUS TOTAL CORE FLOW BACKUP PRESSURE REGULATOR INOPERABLE 01 SINGLE LOOP OPERATION (BOC to EGOC)
FIGURE 8.2-8 0O" 0
' I * . ...... .... ....... ".............. ... ...... . ... . .. ... . . . ............ ...... .............. ......................... ................. ................. .. .. * .. . . =. . ... * " *LZ*:* I* *,.,. L*** ............ .....
CD SSES UNIT 1 CYCLE 19 C " 'I-0*
C 4.4 ---- LEGEND m UM ALLOWABLE AVERAGE SCRAM
-i- 4.2 CURVE A: MAXIM z ____
___ ___INSERi nION TIME z
C 4.0 CURVE B: REALI*
STIC AVERAGE SCRAM INSERTION TiME 3._____,_.__1CURVE C: CORE POWER < 26% AND CORE FLOW < 60 MLBMIHR I
I I rY ANALYSES ASSUME THAT FOUR BYPASS VALVES l---
ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 3.0 26.01, 2.90 E
USED IN DETERMINING MFLCPR CD 0.= 2.6 A *1*
0)
O- 60, 2.18 U* 4 4 1100 "
2.2 1 m
2.0 m
1.8
REFERENCE:
T.S. 3.4.1, 3.7.8, and 3.2.2J11ii 1.4
.-I 20 30 40 60 ... ... 60 ... .. .. 70 80 90 100 m uore r'ower rio KAIi )uJ MCPR OPERATING LIMIT VERSUS CORE POWER CD J\) BACKUP PRESSURE REGULATOR INOPERABLE "11 0J SINGLE LOOP OPERATION (BOO to EOC)
FIGURE 8.2-9 (:I' .Q DO O--
Rev. 16 PL-NF-14-001 Rev. 2 Page 55 of 62 One TSV or TCV CloSed SUSQUEHANNA UNIT 1 TRM/3.2-56 NITTR/3.-56 DATE 11/04/2015 EFFECTIVE SUSQEHANA
S SSES UNIT 1 CYCLE 19 3,6 0o C
-i- 3.4 z
z 3.2 z
3.0 2.8 E
0.
2.6
-*1 2.4 k* *0 0-C, 2.2 2.0 rri "11 1.8 m
1.6 m
1.4 r'ri 110 30 40 50 60 70 80 90 100 Total Core Flow (MLB/HR)
C 0* MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW o ,-n ONE TSV OR TCV CLOSED*
cj SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8.2-10 o~
1'r%-h*
0 oi)
SSES UNIT 1 CYCLE 19 4.6I I I I 4.4 LEGEND m
4.2 ______ CURVE *: MAXIMUM ALLOWABLE AVERAGE SCRAM z INSERTION TIME z 4.0 CURVE E3: REALISTIC AVERAGE SCRAM INSERTION TIME C
z 23 .61 23,3.7 CURVE c.: CORE POWER < 26% AND CORE FLOW < 50 MLBM/HR 3.6
"* 26, 3.56-"
C......SAFETY ANALYSES ASSUMEtt THAT FOUR BYPASS VALVES t 3.4 26,C 3.33 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 3.2
-- ___________USED IN DETERMINING MFLCPR 3.0 C,i CJ1 2.8 CD 0) 2.6
___ _ _ __ _ _ _ __ _ _ _ _6,19 2.4 2.2 _________ 6.01, 2.40_____ _________ - 519 2.0 n
1.8 1.6 m
1.4 20 30 40 50 60 70 80 Core Power (%RATED)
-0 7ci MCPR OPERATING LIMIT VERSUS CORE POWER w"I-ONE TSV OR TCV CLOSED 01 SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8.2-11 0)'
- i jq L. . ... *....... . . ..... . ... . . .......... . . .. .......... ........ T.. .. ............. .... ...... * * * * * ... ... .... -:-.!
.. ... .=
Rev. 16 PL-NF-14-OO1 Rev. 2 Page 58 of 62 9.0 POWERI/FLOW MAP 9.1 Technical Specification Reference Technical Specification 3.3.1.1 9.2 Description Monitor reactor conditions to maintain THERMAL POWER / core flow outside of Stability Regions I and II of the Power/IFlow map, Figure 9.1.
Ifthe 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 perT"S 3.3.1.1, Region I of the Power!
Flow map is considered an immediate sca region.
Region Ilof the Power!/Flow map is considered an immediate exit region regardless of the operability of the OPRM Instrumentation.
SUSQUEHANNA UNIT1 TRM/3.2-59 SUSQEHANA NITTR/3.-59 DATE 11104/2015 EFFECTIVE
Rev. 16 PL-NF-14-O01 Rev. 2 Page 59 of 62 120
Purpose:
- 120 110*
InitialI/Date: " I 1100 100 9o. 90 80 70 L.
60 0
fi-50 40 If 30 201 10
-H-I-I-4--]l- 0*-
0 10 20 30 40 50 50 70 80 90 100 110 Total Core Flow (Mlbmlhr)
(for SLO <75% Pump Speed Use Form GO-100-009-2)
Figure 9.1 SSES Unit 1 Cycle 19 Power/IFlow Map SUSQUEHANNA UNIT 1 TRM/3.2-60 SUSQEHANA NITTR/3.-60 DATE 11104/2015 EFFECTIVE
Rev. 16 PL-NF-14-001 Rev. 2 Page 60 of 62 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 fisted below:
SF = 1.11 Np = 15 Fp = 60OMlbm /hr SUSQUEHANNA UNIT ! TRM/3.2-61 UNT SUSQEHANA DATE 11/04/20 15 I RM/32-61EFFECTIVE
Rev. 16 PL-NF-14-001 Rev. 2 Page 61 of 82
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 I and 2, "RQDEX2 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, "ATRlUMW-10: Appendix K Spray Heat Transfer Coefficients," Siemens Power Corporation, September 2000.
- 4. XN-NF-84-105(P)(A), Volume 1 and Volume I Supplements 1 and 2, lJXCOBRA-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 I 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, t' 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 1 and 2, "Advanced Nuclear Fuels Corporation Critical Power Methodology for Boiling Water Reactors1 "
November 1990.
- 11. NE-092-001A, Revision 1, "Licensing Topical Report for Power Uprate With increased Core Flow," Pennsylvania Power & Light Company, December 1992 and NRC SER (November 30, 1993).
- 12. ANF-89-98(P)(A) Revision 1 and Supplement 1, "Generic Mechanical Design Criteria for BWR Fuel Designs," Advanced Nuclear Fuels Corporation, May 1995.
SUSQUEHANNA UNiT1 TRM/3.2-62 EFFECTIVE DATE 11/04/2015
Rev. 16 PL-NF-14-001 Rev. 2 Page 62 of 62
- 13. EMF-22O9(P)(A), Revision 3, "SPCB Critical Power Correlation," AREVA NP, September 2009.
- 14. EMF-85-74(P)(A), Revision 0, Supplement 1(P)(A) and Supplement 2(P)(A),
"RQDEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model,"
Siemens Power Corporation, February 1998.
- 15. EMF-2168(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 t Revision I 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-1 358(P)(A), Revision 3, "The Loss of Feedwater Heating Transient in Boiling Water Reactors," Framatome ANP, September 2005.
SUSQUEHANNA UNIT1 TRM/3.2-63 SUSQEHANA EFFECTIVE NITTR/3.-63 DATE 11/04/2015
Main Turbine Overspeed Protection System Rev. 2 3.3.7 3.3 Instrumentation 3.3.7 Main Turbine Overspeed Protection System TRO 3.3.7 One Main Turbine Overspeed Protection System shall be OPERABLE.
APPLICABILITY: MODES I and 2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Two of eight stop valves A.1.1 Close one of the inoperable 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and control valves valves.
AND A.1 .2 Limit THERMAL POWER 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> following
< 75% RTP. closure of the inoperable valve AND A.1.3 Apply the following limits for a 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> following closed Turbine Stop Valve or closure of the Turbine Control Valve as inoperable valve specified in the COLR:
OR A.2 Isolate main turbine from the 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> steam supply.
(continued)
SUSQUEHANNA-UNIT1 TRM / 3.3-17 SUSQEHANA-UITITRM 3.-17EFFECTIVE DATE 11/04/2015
Main Turbine Overspeed Protection System Rev. 2 3.3.7 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME B. Two of twelve intercept B.1 Close either the intercept 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> valves and intermediate valve or the intermediate stop stop valves inoperable, valve within one of the affected combined intermediate valves.
OR 8.2 Isolate main turbine from the 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> steam supply.
C. Turbine Overspeed C.1 Isolate main turbine from the 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Protection System steam supply.
inoperable for reasons other than Condition A or B.
SUSQUEHANNA-UNIT1 TRM / 3.3-17a SUSQEHANA
-UNI I RM DATE 11/04/2015 I3.317aEFFECTIVE
Main Turbine Overspeed Protection System Rev. 2 3.3.7 TECHNICAL REQUIREMENT SURVEILLANCE
~NOTE---- --------
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 up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the redundant overspeed trip device is OPERABLE.
SURVEILLANCE FREQUENCY
-- NOTE--..........----......
The provisions of TRS 3.0.4 are not applicable TRS 3.3.7.1 Cycle each high pressure turbine control valve from the 92 days running position and observe valve closure.
-- -- NOTE--...............................
The provisions of TRS 3.0.4 are not applicable TRS 3.3.7.2 Cycle each low pressure turbine combined intermediate 92 days valve from the running position and observe valve closure.
NOTE---------------------.....
The provisions of TRS 3.0.4 are not applicable TRS 3.3.7.3 Cycle each high pressure turbine stop valves from the 92 days running position and observe valve closure.
TRS 3.3.7.4 Perform a CHANNEL CALIBRATION of main turbine 24 months overspeed protection instrumentation.
TRS 3.3.7.5 Disassemble one of each type valve identified in 40 months on a TRS 3.3.7.1, TRS 3.3.7.2, and TRS 3.3.7.3, perform a STAGGERED TEST visual and surface inspection of valve seats, disks and BASIS stems and verify no unacceptable flaws or corrosion.
SUSQUEHANNA-UNIT1 TRM / 3.3-18 SUSQEHANA UNT I RM3.-18EFFECTIVE DATE 10/31/2007
Main Turbine Overspeed Protection System Rev. 2 B 3.3.7 B 3.3.7 Main Turbine Overspeed Protection System BASES TRO The Main Turbine Overspeed Protection System is designed to protect the main turbine from excessive overspeed by initiating a turbine trip by fast closure of the turbine control valves and closure of the intercept valves to essentially secure all steam flow to the turbine (Ref. 1).
To protect the turbine generator from overspeed conditions, two trip devices are provided. Either device, when initiated, will close the main stop valves, control valves, and combined intermediate valves thus isolating the turbine (Ref. 2).
These two trip devices are as follows:
- A mechanical overspeed trip which is initiated ifthe turbine speed reaches approximately 10% above rated speed, and o An electrical overspeed trip which serves as a backup to the mechanical trip and is initiated at approximately 12% above rated speed.
OPERABILITY of at least I of the 2 overspeed protection systems is required for the Turbine Overspeed Protection System to be considered OPERABLE.
Main Turbine Overspeed Protection System (MTOPS) OPERABILITY is also based upon the ability of the valves that control steam flow to the turbine to close following the receipt of a closure signal. The 4 stop valves, 4 control valves, 6 intermediate stop valves, and 6 intercept valves make up a system of 20 valves. A single failure to any one of the above system of 20 valves will not prevent a turbine trip (Ref. 2). Hence, if 19 of the 20 noted valves are OPERABLE, the MTOPS is OPERABLE. Note that for this statement to be true, the intermediate stop valves and intercept valves are considered separate valves. Overspeed protection is only disabled on a CIV failure if both valves within a CIV are inoperable. Failure of only one valve in a CIV does not prevent an overspeed trip, and does not affect operability. Actions to close one inoperable valve if two valves are inoperable maintain the unit within the analysis in Ref. 2. However, redundancy is reduced and repairs should be completed in accordance with the corrective action program.
Excessive turbine overspeed could generate potentially damaging missiles that could present a personnel and equipment hazard. MTOPS is not necessary to provide adequate protection of the public health and safety and is not required to obviate the possibility of an abnormal situation or event giving rise to an immediate threat to the public health and safety.
(continued)
SUSQUEHANNA - UNIT 1 TRM / B 3.3-14 SUSQEHANA
-UNI I TM
/BDATE 3.-14EFFECTIVE 06/25/2002
Main Turbine Overspeed Protection System Rev. 2 B 3.3.7 B 3.3.7 Main Turbine Overspeed Protection System BASES (continued)
ACTIONS The Actions are defined to ensure proper corrective measures are taken in response to the inoperable components.
A.1.l, A.1.2, A.1.3 and A.2 If two of eight stop valves and control valves are inoperable, action must be taken to restore at least one of the valves to OPERABLE status in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
This action ensures steam isolation to the turbine in the event of an overspeed condition, and maintains the unit within the bounds of the FSAR analysis. The 72-hour Completion Time provides a reasonable time to troubleshoot the problem, make repairs, and reduce power in an orderly manner if required without challenging plant systems. The required action if the problem is not resolved is to close one of the inoperable valves, or to isolate the main turbine from the steam supply. If one of the inoperable valves is closed, then limit thermal power to less than or equal to 75% of rated power, and apply Minimum Critical Power Ratio (MCPR) and Linear Heat Generation Rate (LHGR) limits as specified in the COLR within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Restricting thermal power to less than or equal to 75% of rated power eliminates possible shock loads to the turbine blades that could occur from a non-uniform circumferential steam flow distribution entering the HP turbine for this configuration. If the MCPR and LHGR limits are not in compliance with the applicable requirements at the end of this period, the ACTIONS required by the applicable specifications must be implemented.
This time is provided to stabilize operation with a closed Turbine Stop Valve or Turbine Control Valve.
B.1 and B.2 If two of twelve intercept valves and intermediate stop valves are inoperable, action must be taken to restore at least one of these valves to OPERABLE status in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. This action ensures steam isolation to the turbine in the event of an overspeed condition. The 72-hour Completion Time provides a reasonable time to troubleshoot the problem, make repairs, and reduce power in an orderly manner ifrequired without challenging plant systems.
The required action ifthe problem is not resolved is to close either the intercept valve or the intermediate stop valve within one of the affected combined intermediate valves, or to isolate the main turbine from the steam supply.
(continued)
SUSQUEHANNA-UNIT1 TRM / B 3.3-14a SUSQEHANA-NITI TR
/ 3.314aEFFECTIVE DATE 11/04/2015
Main Turbine Overspeed Protection System Rev. 2 B 3.3.7 B 3.3.7 Main Turbine Overspeed Protection System BASES ACTIONS C.1 (continued)
If the MTOPS is inoperable for reasons other than conditions A or B, then action must be taken to isolate the main turbine from the steam supply.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> allows a reasonable amount of time to complete the plant shutdown associated with isolating the main turbine from the steam supply.
TRS The TRSs are performed at the specified Frequency to ensure that the turbine overspeed protection function is maintained OPERABLE.
The TRSs are modified by a Note to indicate that 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 the redundant overspeed trip device is OPERABLE. Upon completion of the Surveillance, or expiration of the 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> allowance, the channel must be returned to OPERABLE status or the applicable Condition entered and Required Actions taken. This Note is based on the average time required to perform channel Surveillance. The 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> testing allowance does not significantly reduce the probability that the Main Turbine Overspeed Protection System will function when necessary.
TRS 3.3.7.1, TRS 3.3.7.2, and TRS 3.3.7.3 Verification of the movement of each of the four high pressure turbine control valves, six low pressure turbine combined intermediate valves (composed of 6 intermediate stop valves and 6 intercept valves), and four high pressure turbine stop valves ensures the OPERABILITY of each valve and that it will be able to close in the event of a turbine trip condition. The 92 day Frequency is based upon current surveillance practice as recommended by the turbine vendor and described in the FSAR (Ref. 3).
(continued)
SUSQUEHANNA - UNIT 1 TRM / B 3.3-14b SUSQEHANA-NIT TRM/
B3.314bEFFECTIVE DATE 11/04/2015
Main Turbine Overspeed Protection System Rev. 2 B 3.3.7 B 3.3.7 Main Turbine Overspeed Protection System BASES TRS TRS 3.3.7.4 (continued)
This TRS is for the performance of a CHANNEL CALIBRATION of the required main turbine overspeed protection instrumentation. The calibration is a complete check of the instrument channel from the sensing device to main turbine trip initiation. The Frequency of 24 months is a typical refueling cycle and considers channel reliability.
TRS 3.3.7.5 The disassembly and inspection of the valves referenced ensures that abnormal wear is not occurring which could result in the valves inability to close upon receipt of a close signal. The Frequency is such that only one of each type valve (i.e., high pressure turbine stop; high pressure turbine control; and low pressure turbine combined intermediate), is required to be inspected within a 40 month period. If unacceptable flaws or excessive corrosion are found in a valve, all valves of its type are inspected (Ref. 3).
Valve bushings are inspected and cleaned, and bore diameters are checked for proper clearance.
REFERENCES 1. FSAR Section 7.7:1.5
- 2. FSAR Section 10.2.2.6.
- 3. FSAR Section 10.2.3.6.
SUSQUEHANNA-UNIT1 TRM / B 3.3-14c SUSQEHANA
-UNITI TR
/ 3.314cEFFECTIVE DATE 11/04/2015