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Category:FUEL CYCLE RELOAD REPORTS
MONTHYEARML20211B7351999-05-31031 May 1999 Cycle 7 Colr ML20206E2971999-04-30030 April 1999 Rev 1 to Millstone Nuclear Power Station,Unit 2 COLR - Cycle 13 ML20084K7441995-03-13013 March 1995 COLR for Cycle 6 Operation ML20078N4921995-01-31031 January 1995 COLR Cycle 13, Rev 0 ML20059L2641993-08-31031 August 1993 Cycle 5 Colr ML20106E3311992-10-30030 October 1992 Rev 5 to Millstone Unit 2 Cycle 12 Colr ML20091A5481992-03-23023 March 1992 Rev 4 to Millstone Unit 2,Cycle 11 Core Operating Limits Rept ML20087B4721992-01-31031 January 1992 Revised Millstone Nuclear Power Station Unit 3,Startup Test Rept,Cycle 4 ML20086T2581991-12-24024 December 1991 Revised Tables to Core Operating Limits Rept for Cycle 4 Operation, Consisting of Control Rod Bank Insertion Limits Vs Thermal Power four-loop Operation & three-loop Operation ML20085L1121991-10-31031 October 1991 Rev 3 to Millstone Unit 2,Cycle 11 Core Operating Limits Rept ML20077H0421991-06-30030 June 1991 Rev 2 to Millstone Unit 2 Cycle 11 Core Operating Limits Rept ML20070Q1771991-03-21021 March 1991 Core Operating Limits Rept for Cycle 4 Operation, Addressing Both Three & Four Loop Operation ML20065N6041990-11-30030 November 1990 Rev 1 to Millstone Unit 2 Cycle 11 Core Operating Limits Rept ML20065K0821990-11-30030 November 1990 Rev 0 to Millstone Nuclear Power Station,Unit 2 Cycle 11 Core Operating Limits Rept ML20058E6341990-10-31031 October 1990 Rev 0 to Millstone,Unit 2 Cycle 11 Core Operating Limits Repts ML20011F4361990-02-28028 February 1990 Rev 0 to Millstone Unit 3 Cycle 3 Core Operating Limits Rept. ML20247N0741989-05-31031 May 1989 Rev 1 to, Reload Safety Evaluation for Millstone Unit 3 Cycle 3 ML20244B4821989-04-30030 April 1989 Reload Safety Evaluation,Millstone Unit 3,Cycle 3 ML20155J4711988-10-31031 October 1988 Cycle 10 Sar ML20155G5911988-10-0404 October 1988 Small Break LOCA Analysis ML20153F8271988-08-31031 August 1988 Large Break Loca/Eccs Analysis ML20235R4491987-07-31031 July 1987 Errata & Addenda 1 to 23A4845, Supplemental Reload Licensing Submittal for Millstone Unit 1,Reload 11 ML20214L6861987-05-21021 May 1987 Rev 0 to Supplemental Reload Licensing Submittal ML20215N8271986-09-30030 September 1986 Rev 2 to Reload Safety Evaluation,Millstone Nuclear Power Station,Unit 2 Cycle 8 ML20134K4241985-08-31031 August 1985 Rev 0 to Supplemental Reload Licensing Submittal for Millstone Unit 1,Reload 10 ML20126J1811985-06-30030 June 1985 Cycle 7 Final Reload Safety Analysis ML20073M2451983-04-30030 April 1983 Reload Safety Analysis 1999-05-31
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217P5391999-10-25025 October 1999 Rev 0,Change 1 to Millstone Unit 1 Northeast Utils QA Program ML20217C8721999-10-0606 October 1999 Rev 21,change 3 to MP-02-OST-BAP01, Nuqap Topical Rept, App F & G Only B17896, Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 1.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 1.With B17894, Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 2.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 2.With B17898, Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 3.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 3.With ML20216J4341999-09-24024 September 1999 Mnps Unit 3 ISI Summary Rept,Cycle 6 ML20211N8401999-09-0202 September 1999 Rev 21,change 1 to Northeast Utils QA TR, Including Changes Incorporated Into Rev 20,changes 9 & 10 B17878, Monthly Operating Rept for Aug 1999 for Mnps,Unit 1.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Mnps,Unit 1.With B17874, Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 3.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 3.With ML20216F5141999-08-31031 August 1999 Rept on Status of Public Petitions Under 10CFR2.206 B17879, Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 2.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 2.With ML20211G9631999-08-30030 August 1999 SER Accepting Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20211A6561999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 2 B17858, Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 3.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 3.With B17856, Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 1.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 1.With ML20210J0311999-07-21021 July 1999 Rev 20,Change 10 to QAP 1.0, Organization ML20210E5931999-07-19019 July 1999 Revised Page 16 of 21,to App F of Northeast Util QA Program Plan ML20210C5911999-07-15015 July 1999 Revised Rev 20,change 10 to Northeast Util QA Program TR, Replacing Summary of Changes ML20210A0411999-07-15015 July 1999 Rev 20,change 10 to Northeast Util QA Program Tr B17814, Special Rept:On 990612 B Train EDG Failed to Restart within 5 Minutes Following Completion of 18 Month 24 H Endurance Run Required by TS 4.8.1.1.2.g.7.Caused by Procedural inadequacy.Re-performed Hot Restart Via Manual Start1999-07-12012 July 1999 Special Rept:On 990612 B Train EDG Failed to Restart within 5 Minutes Following Completion of 18 Month 24 H Endurance Run Required by TS 4.8.1.1.2.g.7.Caused by Procedural inadequacy.Re-performed Hot Restart Via Manual Start ML20209D1881999-07-0101 July 1999 Rev 20,change 9 to Northeast Util QA Program Tr ML20196J2191999-06-30030 June 1999 SER Concluding That Licensee USI A-46 Implementation Program,In General,Met Purpose & Intent of Criteria in GIP-2 & Staff Sser 2 for Resolution of USI A-46 ML20211A6751999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Millstone Nuclear Power Station,Unit 2,providing Revised Average Daily Unit Power Level & Operating Data Rept ML20196A8451999-06-30030 June 1999 Post Shutdown Decommissioning Activities Rept ML20209J0541999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Millstone Unit 2 B17830, Monthly Operating Rept for June 1999 for Millstone Nuclear Power Station,Unit 3.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Millstone Nuclear Power Station,Unit 3.With ML20196K1791999-06-30030 June 1999 Addendum 6 to Millstone Unit 2 Annual Rept, ML20196J1821999-06-30030 June 1999 Rev 21,Change 0 to Northeast Utilities QAP (Nuqap) Tr B17833, Monthly Operating Rept for June 1999 for Millstone Power Station,Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Millstone Power Station,Unit 1.With ML20195H1011999-06-11011 June 1999 Rev 20,change 8 to Northeast Utilities QAP (Nuqap) TR ML20207G6411999-06-0303 June 1999 Safety Evaluation Supporting Amends 105,235 & 171 to Licenses DPR-21,DPR-65 & NPF-49,respectively ML20211A6631999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for Millstone Nuclear Power Station,Unit 2,providing Revised Average Daily Unit Power Level,Operating Data Rept & Unit Shutdowns & Power Reductions B17808, Monthly Operating Rept for May 1999 for Millstone Nuclear Power Station,Unit 3.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Millstone Nuclear Power Station,Unit 3.With ML20211B7351999-05-31031 May 1999 Cycle 7 Colr B17804, Monthly Operating Rept for May 1999 for Mnps,Unit 2.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Mnps,Unit 2.With B17807, Monthly Operating Rept for May 1999 for Mnps,Unit 1.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Mnps,Unit 1.With ML20209J0661999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for Millstone Unit 2 ML20206M4631999-05-11011 May 1999 Safety Evaluation Supporting Alternative Proposed by Licensee to Perform Ultrasonic Exam on Inner Surface of Nozzle to safe-end Weld ML20206J8351999-05-0707 May 1999 Rev 20,Change 7 to QAP-1.0, Northeast Utls QA Program (Nuqap) Tr ML20206G6221999-05-0404 May 1999 SER Accepting Util Request to Apply leak-before-break Status to Pressurizer Surge Line Piping for Millstone Nuclear Power Station,Unit 2 B17782, Monthly Operating Rept for Apr 1999 for Millstone Nuclear Power Station,Unit 1.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Millstone Nuclear Power Station,Unit 1.With ML20205R3531999-04-30030 April 1999 Addendum 4 to Annual Rept, B17775, Monthly Operating Rept for Apr 1999 for Millstone Nuclear Power Station Unit 3.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Millstone Nuclear Power Station Unit 3.With ML20205K6141999-04-30030 April 1999 Non-proprietary Version of Rev 2 to Holtec Rept HI-971843, Licensing Rept for Reclassification of Discharge in Millstone Unit 3 Spent Fuel Pool ML20206E2971999-04-30030 April 1999 Rev 1 to Millstone Nuclear Power Station,Unit 2 COLR - Cycle 13 B17777, Monthly Operating Rept for Apr 1999 for Millstone Unit 2. with1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Millstone Unit 2. with ML20205Q5891999-04-0909 April 1999 Rev 20,change 6 to QAP-1.0,Northeast Utils QA Program TR ML20205R8751999-04-0909 April 1999 Provides Commission with Staff Assessment of Issues Related to Restart of Millstone Unit 2 & Staff Recommendations Re Restart Authorization for Millstone Unit 2 ML20206T3991999-03-31031 March 1999 First Quarter 1999 Performance Rept, Dtd May 1999 B17747, Monthly Operating Rept for Mar 1999 for Millstone Nuclear Power Station,Unit 1.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Millstone Nuclear Power Station,Unit 1.With 1999-09-30
[Table view] |
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l MILLSTONE UNIT NO. 3 .l CYCLE 3 ,
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CORE OPERATING LIMITS REPORT
- l. d l-REVISION 0 ;
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6 FEBRUARY 1990
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i MILLSTONE UNIT NO. 3 -
, CYCLE 3 CORE OPERATING LIMITS REPORT ,
1.0 : CORE ~0PERATING LIMITS REPORT This Core. Operating Limits Report (COLR) for Millstone Unit No. 3, Cycle 3, has been prepared in, accordance with the requirements of Techni-cal Specification 6.9.1.6. i;
~ The Technical Specifications affected by this report are listed below:
3/4.1.1.3 Moderator Temperature Coefficient 3/4.1.3.5- Shutdown Rod Insertion Limit '!
3/4.1.3.6 Control Rod Insertion Limits (Four Loop and Three Loop) i 3/4.2.1.1 Axial Flux Difference--Four Loop, 3/4.2.1.2 Axial Flux Difference--Three Loop ,
'3/4/2.2.1 Heat Flux Hot Channel Factor--Four Loop 3/4.2.2.2 Heat Flux Hot Channel Factor--Three Loop .;
3/4.2.3.1 RCS Flow Rate and Nuclear Enthalpy' Rise Hot Channel Factor--Four Loop 3/4.2.3.2 RCS Flow Rate and Nuclear Enthalpy Rise Hot Channel ,
Factor--Three Loop- -
2.0 OPERATING LIMITS i The- cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the following subsections. These limits have been developed using the NRC-approved methodologies specified in .c Technical -Specification 6.9.1.6.
2.1 Moderator Temnerature Coefficient (Soecification 3/4.1.1.3) ,
t 2.1.1 The moderator temperature coefficient (MTC) limits are:
The BOL/AR0/0%-70% RTP--MTC shall be less positive than p' +0.5 x'10 4 Ak/k/'F. Above 70% RTP the MTC limit is a linear ramp to 0 Ak/k/*F at 100% RTP.
l The E0L/AR0/RTP--MTC shall be less negative than
-4.75 x 10 4 Ak/k/*F.
L l Page 1, Revision 0 3
e c o 2.1.2 The MTC surveillance' limit is:
The 300 ppm /AR0/RTP--MTC should be less negative than or equal to -4.0 x 10 4 Ak/k/'F.
Where: BOL stands for beginning of cycle life ARO stands for all rods out HZP stands for hot zero power EOL stands for end of-cycle life RTP stands for rated thermal power 2.2 Shutdown Rod Insertion Limit (Soecification 3/4.1.3.5)
The shutdown rods shall be fully withe.rawn.
2.3 Control Rod insertion limits (Specification 3/4.1.3.6) ;
The control rod banks shall be limited in physical insertion as shown in Figure 1 for four loop operation and Figure 2 for three-loop operation.
2.4 Axial Flux Difference--Four looo Operation (Soecification 3/4.2.1.1) 2.4.1 The axial flux difference (AFD) target band is +5%, -5%
for core average accumulated burnup 5 3000 MWD /MTV.
2.4.2 The AFD target band is +3%, -12% for core average accumu-lated burnup 2 3000 MWD /MTV.
i Where: MWD /MTV stands for megawatt days / metric ton of ;
initial uranium metal.
2.4.3 The AFD acceptable operation limits are provided in Figure 3. I 2.5 Axial Flux Difference--Three-looo Operation (Specification 3/4.2.1.2) 2.5.1 The AFD target band is +5%, -5%.
2.5.2 The AFD acceptable operation limits are provided in i Figure 4. ;
1 2.6 Heat Flux Hot Channel Factor (Four Loops Operating)--F (Z) i 0
I (Specification 3/4.2.2.1) p RTP Q
F0 (Z) 1
Page 2, Revision 0
e s .;. .
p RTP {
Q Fg (Z) s
0.5 ;
Thermal Power Where:- P= -
Rated Thermal Power 2.6.1 FlTg2.32 2.6.2 K(Z) is provided in Figure 5.
2.6.3 See Figure 6 for a plot of [Ff . PRel) versus exial core height..
Fxyl,pRTP , (3 , pp ,(3,p))
RTP
2.6.4 Where
F*# - 1.67 for unrodded core planes 1.79 for core planes containing Bank D control rods 2.6.5 PF xy = 0.2 2.7 Heat Flux Hot Channel Factor (Three Loops Operating)--F (Z) n (Snecification 3/4.2.2.2) p RTP Q
F0 (Z) s
p RTP Q
F(Z)s g
- K(Z) for P s 0.325 Thermal Power Where: P=
Rated Thermal Power Page 3, Acv sion 0
e, .
t 2.7.1 FhTg1.69 j Note. Since maximum power in three-loop operation is 65%,FhTP represents the theoreticalg F limit if power were at 100%. j 2.7.2 K(Z) is provided in Figure 7. ,
2.7.3 See Figure 8 for a plot of [Ff . PRel) versus axial core height.
l F
xy -F 65 RTP * (1 + My *[0.65P)) .
2.7.4 Where
F*RTP - 1,69 for unrodded core planes .
- 1.81 for core planes containing Bank D '
control rods 2.7.5 Mp - 0.281 ;
2.8 Nuclear Enthalpy Rise Hot Channel Factor (Four Loops Operating)--F"H A (Soecification 3/4.2.3.1) r I
RTP , (3 , pp g ,[3,p))
FAH s FAg Thermal Power Where: P-Rated Thermal Power 1
2.8.1 FRTP , 3,49 A
2.8.2 PFAH - 0.3 l
l Page 4, Revision 0
s h'
0 '
s 4 ,
2.9 Hgelear Enthalov Rise Hot Channel Factor (Three loops Operating)--FAH(Specification 3/4.2.3.2)
Ffg5FRTP . (3 , pp , [3,pg Thermal Power Where: P=
Rated Thermal Power RTP 2.9.1 F A
= 1.351 2.9.2 PFAH = 0.43 Page 5, Revision 0 j
-., o (FULLY WITHDRAWN) .
(028.228) (0.78.228) 228 200 /
SANK B (1.0,164)
(0.Q164) t 150 e /
n.
/
BANK C
/
k BANK 0 (0.0,50)
/
(028,0) 0 o 0.2 0.4 0.6 0.8 1.0 (FULLY INSERTED) FRACTION OF RATED THERM AL POWER ;
FIGURE 1 R0D BANK INSERTION LIMITS VERSl1S THERMAL POWER FOUR LOOP OPERATION MILLSTONE - UNIT 3
i
,e '
I l
(FOLLY WITHDRAWN) j (007228) (0 57 228) /
/ BANK B l
( 0,212) 200
/
5 MSANK C e / (0.65,132) 5 8 100
,( 0,0.98) ,
, -SANK D 50 (0 07,0) '
0 O 02 04 06 0.8 10 (FULLY INSERTED) FRACTION OF RATED THERMAL POWER k
l FIGURE 2 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER THREE LOOP OPERATION j
1 i
l MILLSTONE - UNIT 3
.. \
. 1
[ .c.' , ;
E
$ h
, 1 b l
. w Y 5 ,
i 40 0 I I I I l- 1 I I -
UNACCEPTABLE ( 11,9 0) (11. 9 0 )
OPERATION UNACCEPT ABL E '
OPERATION 60 -
/ ' '
\
ACCEPTABLE OPERATION 60
\
. /
/
\
( 31. 5 0) (31. 5 0 )
40 e '
20 0
50 40 30 20 10 0 20 30 10 40 50 i
FLUX DIFFERENCE (6I)'/.
FIGURE 3 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER (FOURLOOPSOPERATING) l l
l l MILLSTONE - UNIT 3 ~
O N, e E
S
- 2 5 Y Is W
10 0 80 UNACCEPTABLE ( 8,65) (8.65) UNACCEPTABLE OPERATION OPERATION I I '
So I \ '
ACCEPTABLE OPERATION L
4 ; I I \
/ \
( 24 5,32) (24 5,32) 20
\
l 0
50 40 30 20 10 0 10 20 30 40 50 i, FLUX OtFFERENCE (61)*f.
I FIGURE 4 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER (THREELOOPSOPERATING)
MILLSTONE - UNIT 3
~
, !6 g- e. .
1.50 1.25 - -
o 1.00 e
T T*'
3 O.75 - -
2.320 2 CORE HEIGHT K(2) 0.000 1.000 a O.50 - - 5ON 1 000 t! 10.000 0.94 0 5
12.000 0.647 0.25 - ,
0.00 ! ! ! !
O 2 4 6 8 10 12 CORE HEIGHT (FT)
> FIGURE 5 K(Z)-NORMALIZEDF(Z)ASAFUNCTIONOFCOREHEIGHT n
FOR POUR LOOP OPERATION MILLSTONE - UNIT 3 i
f
_ 0,0,2.321 I .0 2.321 li '
pW
-- --- --- ,, 10.8m 2.18 2.fS -p %q K
4 5 . *****$ 1 ++ ..
f t, t
[ '4' '*,
_4a.
I L
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m J vf +4
+;
i g a ' '
l l s' 12.0. 1.60 '
g o ,I ,, a
, 1 ll ,
x 1.25 , i
< l 3 , ,
I l f I 1.00 ',,
i + .
l l c" i
.no i'
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.500 0 2 4 4 8 10 12 l sorrow COREHEIGHT(FEET) top l
l t
FIGURE 6 T
MAXIMUM F g
P ggt VERSUS AXIAL CORE HEIGHT DURING NORMAL CORE F0VR-LOOP OPERATION MILLSTONE - UNIT 3
I. !
'o ,
i mm.
- 1. 2 5' - -
i C
[o 1.00 .
8 3 0.75 - - TOTAL
< 2.60o -
CORE HEIGHT M(Z) 2 0.000 1.000 a O.50 - - e.ooo i.ooo 5
" 10.Soo 0.940 12.000 0.577 0.25 - - t 0.00 ! !
O 2 4 6 8 10 12 CORE HEIGHT (FT)
FIGURE 7 K(Z) - NORMALIZED F g(Z) AS A FUNCTION OF CORE HEIGHT FOR THREE-LOOP OPERATION I
MILLSTONE - UNIT 3
. _ . . _ - . . - - - - _ . . . . . . . - _ . . . . ~ - . - - . - . . ~ . . ~ . . . - . . - - . . . .. ..-. . .
l'
+.
6O i.F 2.00 t 1
$ t 1 IS 0.0. 1.600 6.0 i!
1.690rj w mm%
-- sc,.6. 1.sai :
e a l.S0 - i ,e +, l N b, ++4 / *I.\ l
,p ** " t 7 '+ ,I 5, 1.25 i
g t ,
> g O r O
6 .
v
2 1*00 E 12.CI. 0.975 -
l .o s
l 1 '
s 4l
.750
' i i ,
8 10 12
. 500 ,' 2 4 6 l
COREHEIGHT(FEET) TOP 90Tf0W i
FIGUPE 8 T
MAXIMUM F P ggt VERSUS AXIAL CORE HEIGHT g
I DURING NORMAL CORE THREE-LOOP OPERATION J
MILLSTONE - UNIT 3 L. __._.______.__._._______U