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Category:FUEL CYCLE RELOAD REPORTS
MONTHYEARML20196L2081999-04-19019 April 1999 Rev 01-07-00 to RE-21, Cycle 7 Colr ML20197H3781997-12-10010 December 1997 Rev 2 to RE-21, Cycle 6 Colr ML20141C8191997-06-18018 June 1997 1 to Cycle 6 Colr ML20141C8091997-06-0707 June 1997 0 to Cycle 6 Colr ML20140F1411997-04-22022 April 1997 Rev 5 to Cycle 5 Colr ML20137X7191997-03-31031 March 1997 Rev 4 to Cycle 5 Colr ML20116J3701996-08-0101 August 1996 Rev 1 to Cycle 5 Colr ML20101R0871996-03-28028 March 1996 Cycle 5 Colr ML20095L0081995-12-12012 December 1995 Rev 1 to Cycle 5 Colr ML20094M8221995-11-10010 November 1995 Rev 01-05-00 to Cycle 5 Core Operating Limits Rept ML20071H9021994-07-11011 July 1994 Rev 01-04-00 to Cycle 4 Colr ML20059D2691993-12-24024 December 1993 RE-21 Colr,Cycle 3, Rev 01-03-03 ML20115A3001992-10-0606 October 1992 COLR Seabrook Station Unit 1,Cycle 3 ML20094N5321992-03-31031 March 1992 Core Operating Limits Rept Seabrook Station Unit 1 Cycle 2 ML20082B7451991-07-0909 July 1991 Cycle 2 Radial Peaking Limit Rept 1999-04-19
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217H2841999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Seabrook Station. with ML20212D1461999-09-17017 September 1999 SER Accepting Request to Use Proposed Alternative to Certain Weld Repair Requirements in ASME Boiling & Pressure Vessel Code ML20216F5141999-08-31031 August 1999 Rept on Status of Public Petitions Under 10CFR2.206 ML20212B8671999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Seabrook Station. with ML20210Q7581999-08-11011 August 1999 SER Approving Proposed Merger of CES & Bec,Which Will Create New Parent Company of Canal ML20210R9781999-08-0606 August 1999 ISI Exam Rept of Seabrook Station, for RFO 6,period 3 ML20210J8681999-08-0303 August 1999 SER Approving License Transfer from Montaup Electric Co to Little Bay Power Corp & Approval of Conforming Amend for Seabrook Station Unit 1 ML20210R6001999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Seabrook Station, Unit 1.With ML20210H1151999-06-30030 June 1999 Naesc Semi-Annual Fitness-for-Duty Rept for 990101-0630 ML20209H1371999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Seabrook Station, Unit 1.With ML20195G5391999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Seabrook Station, Unit 1.With ML20195C0491999-05-25025 May 1999 Offshore Intake Seal Deterrent Barrier Design ML20206E4761999-04-30030 April 1999 LER 99-S01-00:on 990408,contractor Employee Was Granted Temporary Unescorted Access to Seabrook Station Protected Area.Caused by Failure of Contractor Employee to Provide Accurate Info.Individual Access Revoked.With ML20206N1751999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Seabrook Station, Unit 1.With ML20196L2081999-04-19019 April 1999 Rev 01-07-00 to RE-21, Cycle 7 Colr ML20205K5441999-03-31031 March 1999 Decommissioning Update ML20205L8141999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Seabrook Station. with ML20205C1981999-03-24024 March 1999 Safety Evaluation Concluding That Proposed Relief Request IR-8,Rev 1,provides Acceptable Alternative to ASME Code Requirements.Recommends Authorization of Proposed Alternative Pursuant to 10CFR50.55a(a)(3)(i) ML20207F4941999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Seabrook Station. with ML20199E6731998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Seabrook Station, Unit 1.With ML20198P1831998-12-31031 December 1998 LER 98-S01-00:on 981214,incomplete pre-employment Screening Records Was Noted.Caused by Failure of Contractor Employee to Provide Accurate Info.Subject Contractor Employees Employment Was Terminated.With ML20202E8241998-12-31031 December 1998 Naesc Semi-Annual Fitness-for-Duty Rept for 980701-981231 ML20196F5741998-12-0202 December 1998 Safety Evaluation Concluding That Licensee Has Established Acceptable Program to Verify Periodically design-basis Capability of safety-related MOVs at Seabrook ML20198B8661998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Seabrook Station, Unit 1.With ML20195D0311998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Seabrook Station, Unit 1.With ML20154H5291998-10-0808 October 1998 Special Rept:On 980928,meteorological Monitoring Instrumentation Channel Inoperable for Period Greater than 7 Days.Caused by Vendor to Follow Std Industry Practice for Calibr of Instrumentation.Instruments Installed ML20154M8421998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Seabrook Generating Station,Unit 1.With ML20151V5951998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Seabrook Station, Unit 1.With ML20237B4501998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Seabrook Station ML20236R1781998-06-30030 June 1998 Naesc Semi-Annual Fitness-for-Duty Rept for 980101-0630 ML20236M3591998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Seabrook Station, Unit 1 ML20237A4871998-06-0303 June 1998 North Atlantic Seabrook Station 1998 Exercise on 980603 ML20248M2951998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Seabrook Station, Unit 1 ML20247G2641998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Seabrook Station ML20247H3171998-04-27027 April 1998 Rev 1 to Seabrook Station SGs B & C Isi,May/June 1997 ML20216F8891998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Seabrook Station 05000443/LER-1998-002, Re Potential Safety Injection Pump Runout Conditions Identified on 980113.LER 98-002-00 Retracted1998-03-20020 March 1998 Re Potential Safety Injection Pump Runout Conditions Identified on 980113.LER 98-002-00 Retracted ML20216H9211998-03-13013 March 1998 Fitness for Duty Program Performance Data Personnel Subject to 10CFR26 ML20248L2811998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Seabrook Station, Unit 1 ML20197A7531998-02-27027 February 1998 Safety Evaluation Accepting License Request for Relief from ASME Code,Section IX Requirements Re Inservice Insp of RHR Heat Exchanger Nozzle Welds & Reactor Vessel Closure Head Nuts ML20202G3701998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Seabrook Station ML20198G0271997-12-31031 December 1997 Commonwealth Energy Sys 1997 Annual Rept ML20248L7711997-12-31031 December 1997 Western Massachusetts Electric 1997 Annual Rept. Supporting Info,Encl ML20198G1021997-12-31031 December 1997 Baycorp Holdings 1997 Annual Rept ML20198N7021997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Seabrook Station, Unit 1 ML20198G0351997-12-31031 December 1997 Eastern Edison Co 1997 Annual Rept ML20198G0681997-12-31031 December 1997 Taunton Municipal Lighting Plant 1997 Annual Rept ML20248L7671997-12-31031 December 1997 North Atlantic 1997 Annual Rept ML20198F9511997-12-31031 December 1997 United Illuminating Co 1997 Annual Rept ML20236M9561997-12-31031 December 1997 Amended Public Service of New Hampshire 1997 Annual Rept 1999-09-30
[Table view] |
Text
..
C North Atlantic :
December 29,1993 - .j i
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ENCLOSURE TO NYN-93173 ;
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'i 9401070095 931229 PDR
[i ADOCK 05000443 ti P PDR h
3 RE-21 CORE OPERATING LIMITS REPORT P
CYCLE 3 COLR L
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F RE DEPT SUPER VISOR [4Y! hM'* I2llb3 SIGNATURE ' W.
DATE OPERATIONS MANAGER 9]I ,y bic, yyjpy3 h j SIGNATURE DATb ;
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REVISION 01-03-03 i
RE-21
~
1.O? CSRE LOPERATING fMTTS REPORT -
Rev. 0103 03 :
Page 1 of 7 This Core Operating Limits Report for Seabrook Station. Unit 1. Cycle 3 has been prepared in accordance with the requirements of Technical Specification 6.8.1.6. '
The Technical Specifications affected by this report are: ,
- 1) 3.1.1.1 Shutdown Margtn Limit for MODES 1. 2. 3. 4
- 2) 3.1.1.2 Shutdown MargLn Limit for MODE 5
- 3) 3.1.1.3 Moderator Temperature CoefHelent
- 4) 3.1.3.5 Shutdown Rod Insertion Limit
- 5) 3.1.3.6 Control Rod Insertion Limits .
- 6) 3.2.1 Axial Flux Difference
- 7) 3.2.2 Heat Flux Hot Channel Factor ,
- 8) 3.2.3 Nuclear Enthalpy Rise Hot Channel Factor 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in section 1.0 are .
presented in the following subsections. These limits have been developed using the NRC-approved methodologies specified tr. 'rechnical Specification 6.8.1.6.
~
2.1 Shutdown Margin Ilmit For MODES 1,2,3, and 4: (Specification 3.1.1.1) .
A) The Shutdown Margin shall be greater than or equal to 1.3 % AK/K in MODES 1, .
2, and 3. .
B) The Shutdown Margin shall be greater than or equal to'1.8 % AK/K in MODE 4.
2.2 Shutdown Margin Ilmit For MODE 5: (Specification 3.1.1.2) .
The Shutdown Margin shall be greater than or equal to 1.8 % AK/K.
m.<-m -- ,w . - .
RE-21 2.3 Mod: rat:r Temperature Coeff1':isct: (Specificati:n 3.1.1.3)
Rcv. 01-03-03 Page 2 of 7 2.3.1 The Moderator Temperature CoefIlcient (! SIC) shall be le'ss positive than 0 AK/K/*F for Beginning of Cycle Life (BOL). All Rods Out (ARO) Hot Zero Thermal Power conditions.
2.3.2 MTC shall be less negative than -4.2 x 10-* AK/K/'F for End of Cycle Life (EOL). ARO. Rated Thennal Power conditions.
2.3.3 The 300 ppm ARO. Rated Thermal Power M'IC shall be less negative than
-3.3 x 10-4 AK/K/'F (300 ppm Surveillance Limit) 2.4 Shutdown Rod Insertion Limit: (Specification 3.1.3.5) 2.4.1 The shutdown rods shall be fully withdrawn. The fully withdrawn position is defined as the intenal within 225 steps withdrawn to the mechanical fully withdrawn position inclusive.
2.5 Control Rod Insertion Ilmits: (Specification 3.1.3.6) 2.5.1 The control rod banks shall be limited in physical hisertion as specifled in Figure 1, 2.6 Axial Fluz Difference: (Specification 3.2.1) 2.6.1 The Axial Flux Difference (AFD) Target Band is + 3 %. - 12 %.
2.6.2 The indicated AFD may deviate outside the required band specified in 2.6.1 (above) at greater than or equal to 50 % but less than 90 % of RATED.
THERMAL POWER provided the indicated AFD is within the Acceptable-Operation Limits as specified in Figure 2.
2.7 Heat Fluz Hot Channel Factor: (Specification 3.2.2) -
2.7.1 F"o = 2.32
. -~ '
2.7.2 K(Z) is specified in Figure 3. ":RE-21 -
Rov."01-03-03
'Page 3 of 7 s 2.7.3 PFu = 0.2 -
2.7.4 The Fw limits for Rated Thermal Power within specific core planes shall ber -
2.7.4.1 ,
Fu (RIP) less than or equal to 1.850 for all planes containing banks D + C control rods; 2.7.4.2 Fu (RTP) less than or equal to 1.800 for all planes containing bank D control rods;
2.7.4.3 Fu (RTP) less than or equal to 1.640 for all unrodded planes for cycle burnup from 0 up to 1,000 MWD /MTU; :
2.7.4.4 Fu (RTP) less than or equal to 1.670 for all unrodded planes'for cycle-burnup from 1.000 up to 2,000 MWD /MTU: 6 2.7.4.5 Fu (RTP) less than or equal to 1.680 for all unrodded planes for cycle' ;
burnup from 2.000 up through 8.000 MWD /MIU; '
2.7.4.6 Fu (RTP) less' than or equal to 1.630 for all unrodded planes. for cycle _ j burnup from 8,000 up through 12,000 MWD /MTU; - I 2.7.4.7 Fu (RTP) fess than or equal to 1.620 for all unrodded planes for cycle burnup from 12.000 MWD /MTU onward; and 2.7.4.8 See Figure 4 for a plot of F g(Z) x P(REL) versus axial core height.
2,8 Nuclear Enthalpy Rise Hot Channel Facter. (Specification 3.2.3) -
t 2.8.1 F ",,' = 1.490 for the movable incore detector system F"' = 1.488 for the fixed incore detector system ,
2.8.2 PF3 = 0.2 1
t . .
t
~ . RE-21 Rev 0103 03 -
Page;4 of 7 >
.i M3%
CYCLE 3 COLR* FIGURE 1 ROD BANK INSERTION LIMITS VS. THERMAL POWER :
(Steps Withdrawn) (Fractional Power) . l 6
225 FULLY WITHDRAWN = 225 to 232 faciustre. 't
/- '
/__.__.__
(0.286,225)l '(0.830,125),/
200 --
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o !
d (0.0,164) yga _._ . . _ . . . . _ _ _ ,_ __ _ _ _ _ . . _ . . . _ . . _ . _ _ . _ , . ;
B ~ ~ ~ ~~~
, _ /. i (1.0,146)y .
- if n
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120 - - - . - - 4 /. ,
l ~
l i/i s l BANK C . ,
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~t _. - . . - _ . . -. - .. - . - ._ - - - . . .-. - .-__ _ .-
e .
p _..- -.-. - .. - . - - - - . - . . . -
s ,
80 -~--
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cif !a, f! ! !
i ! l /i i lL1 t y
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40 (0.0, n) l /[ BANK Dl ,
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4 i i io -
- 0. 0 0.2 0.4 0. 6 0.8 1:0 Fractional Rated Thermal Po'wer- .i i
Bank A must be FULLY WITHDRAWN prior to power operation. i
,e,
.p g_3, Rev. 01-03-03 Page 5 of' 7 L
CYCLE 3 COLR FIGURE 2 120 100 Unacceptable operation Unacceptable operation
- i i,ii g (-11,90) 7 g- (11,90) 1 80 E / \
/ \
S Acceptable operation
.g eo
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(g 40
(-31,50) (31,50)-
20 l l l l 40 20 -10 0 10 20 30 40 50 Flux Difference (AI)%
AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF-RATED THERMAL POWER
F F ^RE 1-
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- Rev. 01 03 03 Page 6 of 7
- 1. -
L- CYCLE 3 COLR FIGURE 3 1.2
- (0.0,1.0) . (6.0,1.0) 1.0 . (10.8,0.94) _
4 N \
h 0.8 18 \
._u 3
E 0.6 ( .0,0.65) _
g .I z
e
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N y 0.4 0.2 1
0.0 0 2 4 6 8 10 -12 Core Height (ft)
K(Z) - NORMALIZED Fg(Z)
AS A FUNCTION OF CORE-HEIGHT
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- ..- RE-21 CYCLE 3 COLR FIGURE 4 ##"' ##~8##
Page 7 of 7
- t. 2.4 . . . .
- (0.0,2.32) (6.0,2.32) ---
2'3 -- 8'
.+ '"'
.21 +2 _ '% % _ (10.8,2.18)
+
D- ^
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+
1.9 = -
r 0e 1.8 F
o , .
LL 1,7 __+
E a 1.6 .
h m 1.5 -
(12.0,1.51) -
2 %
- 1.4 -
1.3 -
+
1.2-7 1.1 - '
4 1.0 - - -- LIMIT '
.9 - -- + MAX Fo
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0 2 4 6 8 10 -12 Bottom Top -
Axial Core Height (ft) 7 MAXIMUM Fo - Ps VERSUS CORE HEIGHT