|
---|
Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217G4341999-10-14014 October 1999 Rev C to Proposed TS Change Re Conversion to Improved Standard TSs ML20217G5121999-10-14014 October 1999 Revised Page 285 to TS Re Allowed Containment Leakage Rate, Changing Rev 0 to Rev 1 ML20216J3871999-09-29029 September 1999 Proposed Tech Specs Pages,Extending LCO Allowable Out of Service Time for RHRSW Sys from 7 Days to 11 Days with Special Conditions to Allow for Installation of Mod to Division a RHRSW Strainer ML20196F6071999-06-22022 June 1999 Proposed Tech Specs Re pressure-temp Limits ML20195B8831999-06-0101 June 1999 Proposed Tech Specs,Converting to Improved Std TS ML20206U1421999-05-19019 May 1999 Proposed Tech Specs Revising AOTs for Single Inoperable EDG ML20205K1091999-04-0505 April 1999 Proposed Tech Specs,Removing Position Title of General Manager from Sections & Will State That If Site Executive Officer Is Unavailable,Responsibilities Will Be Delegated to Another Staff Member,In Writing ML20199H3611999-01-15015 January 1999 Proposed Tech Specs Table 4.1-2 Re Local Power Range Monitor (LPRM) Signal Calibr ML20198M8321998-12-30030 December 1998 Proposed Tech Specs Page 258f Re Configuration Risk Mgt Program ML20197G6181998-12-0303 December 1998 Proposed Tech Specs Reducing Size of Spent Fuel Rack Assembly N3 from 8x13 Cells to 8x12 Cells & Deleting Proposed Inclusion of Fuel Pool Water Level Inadvertent Drainage Into Amend ML20154M7181998-10-16016 October 1998 Proposed Corrected Tech Specs Section 3/4.6.C,relocating Portions of Reactor Coolant Sys - Coolant Chemistry ML20236X8041998-08-0303 August 1998 Proposed Tech Specs Section 1.1.A Re SLMCPR to Be Applicable During Cycle 14 ML20236M6231998-07-10010 July 1998 Proposed Tech Specs Pages Re Amend to Relocate TS 3/4.6.C, RCS - Coolant Chemistry, from TS to UFSAR & Applicable Plant Procedures Controlled by 10CFR50.59 Process ML20249B1631998-06-16016 June 1998 Proposed Tech Specs Re Relocation of Safety Review Committee Review & Audit Requirements ML20236L2931998-06-0707 June 1998 Proposed Tech Specs Section 3.5.b.1 Re Main Condenser Steam Jet Air Ejector & Table 3.10-1 Re Radiation Monitoring Sys That Initiates &/Or Isolates Sys ML20217K0391998-03-30030 March 1998 Proposed Tech Specs Changing Interval of Selected LSFT from Semiannually to Once Per 24 Months & Revising Definition for LSFT to Be Consistent w/NUREG-1433 ML20247F7981998-02-26026 February 1998 Proposed Tech Specs Re Allowed Containment Leakage Rate ML20202G8841998-02-0606 February 1998 Revised Proposed TS Pages,Revising Allowed Outage Times for 4kV Emergency Bus Trip Functions & Replace Generic Actions for Inoperable Instrument Channels w/function-specific Actions ML20202D4021998-02-0606 February 1998 Proposed Tech Specs Revising RPS Normal Supply Electrical Protection Assembly Undervoltage Trip Setpoint as Result of Reanalysis Based on Most Limiting Min Voltage Requirements of Applied Loads ML20202D5621998-02-0606 February 1998 Proposed Tech Specs Allowing RCS Pressure Tests to Be Performed While Remaining in Cold Shutdown Mode ML20203J6971997-12-12012 December 1997 Proposed Tech Specs,Revising Administrative Controls for Normal Working Hours of Plant Staff Who Perform Safety Related Functions ML20217J0021997-10-14014 October 1997 Proposed TS Pages Re Changes to Design Features Section, Including Revised Limits for Fuel Storage ML20217G3071997-10-0808 October 1997 Proposed Tech Specs Re Distribution of Inoperable Control Rods ML20211H0801997-09-26026 September 1997 Revised Proposed TS Changes to ASME Section XI, Surveillance Testing ML20236N7061997-09-0909 September 1997 Proposed Tech Specs,Describing Licensee'S Configuration Risk Mgt Program Which Supports Rev of Allowed out-of-svc Times for Single Inoperable EDGs to Accommodate on-line Maint of EDGs ML20140D8131997-04-14014 April 1997 Proposed Tech Specs Re SRC Audit Requirements & Mgt Title Change ML20135B1921996-11-26026 November 1996 Proposed Tech Specs,Requesting That Snubber Operability, Surveillance & Records Requirements in TS Be Relocated to Plant Controlled Documents ML20134M1751996-11-20020 November 1996 Proposed Tech Specs Reflecting Interposed Amend That Was Issued,Updating References to Repts on TS Pp & Changing Rev Bars on Previously Submitted Update Pp Which Were Erroneously Positioned on Pp ML20149L7191996-11-0808 November 1996 Proposed Tech Specs Re Min Critical Power Ratio Safety Limit ML20129G0091996-10-23023 October 1996 Proposed Tech Specs Re Page 134 Deleted Under Amend 236 & Remain Deleted ML20128Q7441996-10-11011 October 1996 Proposed Tech Specs Re Extension of Instrumentation & Miscellanous Surveillance Test to Accommodate 24 Month Cycles ML20115G0641996-07-12012 July 1996 Proposed Tech Specs Re Cycle 12 Min Critical Power Ratio Safety Limit ML20113B6511996-06-20020 June 1996 Proposed Tech Specs Re Option B to 10CFR50,App J for Primary Containment Leakage Rate Testing Program ML20112D1531996-05-30030 May 1996 Proposed Tech Specs,Revising Minimum Critical Power Ratio Safety Limit & Associated Basis ML20112D5711996-05-30030 May 1996 Proposed Tech Specs,Eliminating Selected Response Time Testing Requirements ML20112D2721996-05-30030 May 1996 Proposed Tech Specs Re ATWS Recirculation Pump Trip Instrumentation Requirements JPN-96-023, Proposed Tech Specs Re Deletion of Requirement for PORC to Review Fire Protection Program & Implementing Procedures. Addl Deletion of Insp & Audit Requirements of Specs 6.14.A & 6.14.B1996-05-16016 May 1996 Proposed Tech Specs Re Deletion of Requirement for PORC to Review Fire Protection Program & Implementing Procedures. Addl Deletion of Insp & Audit Requirements of Specs 6.14.A & 6.14.B ML20108D1171996-04-24024 April 1996 Proposed Tech Specs,Supporting Adoption of Primary Containment Lrt Requirements of Option B to 10CFR50,App J & Clarifying Numerical Value of Allowable Containment Leakage Rate as 1.5% Per Day ML20107M4511996-04-24024 April 1996 Proposed Tech Specs 3.11.B/4.11.B Re Crescent Area Ventilation ML20101H6741996-03-27027 March 1996 Proposed Tech Specs,Supporting Adoption of Primary Containment Lrt Requirements of Option B to 10CFR50,App J at Plant & Clarifies Numerical Value of Allowable Containment Lrt as 1.5% Per Day ML20101H3821996-03-22022 March 1996 Proposed TS Table 3.2-2 Re Core & Containment Cooling Sys Initiation & Control Instrumentation Operability Requirements ML20101F8411996-03-22022 March 1996 Proposed Tech Specs,Implementing BWROG Option I-D long-term Solution for Thermal Hydraulic Stability ML20097A2271996-02-0101 February 1996 Proposed Tech Specs,Allowing RCS Pressure Tests to Be Performed While Remaining in Cold Shutdown Mode ML20100C2991996-01-25025 January 1996 Proposed Tech Specs Re EDGs Surveillance Testing ML20097J6691996-01-25025 January 1996 Proposed Tech Specs Re Extension of Instrumentation & Miscellaneous Surveillance Test Intervals to Accommodate 24- Month Operating Cycles ML20095F7091995-12-14014 December 1995 Proposed Tech Specs,Incorporating IST Requirements of Section XI of ASME Boiler & Pressure Vessel Code ML20094R6981995-11-30030 November 1995 Proposed Tech Specs,Extending Surveillance Test Intervals for SLC Sys to Support 24 Month Operating Cycles ML20094B6641995-10-25025 October 1995 Proposed Tech Specs Extending Containment Sys Surveillance Test Intervals to Accommodate 24 Month Operating Cycles ML20092H5401995-09-15015 September 1995 Proposed Tech Specs Extending Surveillance Test Intervals for Auxiliary Electrical Sys to Support 24 Month Operating Cycles ML20086P6561995-07-21021 July 1995 Proposed Tech Specs Re Replacement of title-specific List of PORC Members W/More General Statement of Membership Requirements 1999-09-29
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217G5121999-10-14014 October 1999 Revised Page 285 to TS Re Allowed Containment Leakage Rate, Changing Rev 0 to Rev 1 ML20217G4341999-10-14014 October 1999 Rev C to Proposed TS Change Re Conversion to Improved Standard TSs ML20217D9961999-10-13013 October 1999 Risk-Informed ISI Program Plan for Ja Fitzpatrick ML20216J3871999-09-29029 September 1999 Proposed Tech Specs Pages,Extending LCO Allowable Out of Service Time for RHRSW Sys from 7 Days to 11 Days with Special Conditions to Allow for Installation of Mod to Division a RHRSW Strainer ML20196F6071999-06-22022 June 1999 Proposed Tech Specs Re pressure-temp Limits ML20195B8831999-06-0101 June 1999 Proposed Tech Specs,Converting to Improved Std TS ML20206U1421999-05-19019 May 1999 Proposed Tech Specs Revising AOTs for Single Inoperable EDG ML20205K1091999-04-0505 April 1999 Proposed Tech Specs,Removing Position Title of General Manager from Sections & Will State That If Site Executive Officer Is Unavailable,Responsibilities Will Be Delegated to Another Staff Member,In Writing ML20204B6321999-03-21021 March 1999 Plant Referenced Simulation Facility Four Year Performance Testing Rept ML20199H3611999-01-15015 January 1999 Proposed Tech Specs Table 4.1-2 Re Local Power Range Monitor (LPRM) Signal Calibr ML20206P0541998-12-31031 December 1998 Rev 3.2 to EDAMS/RADDOSE-V ML20198M8321998-12-30030 December 1998 Proposed Tech Specs Page 258f Re Configuration Risk Mgt Program ML20197G6181998-12-0303 December 1998 Proposed Tech Specs Reducing Size of Spent Fuel Rack Assembly N3 from 8x13 Cells to 8x12 Cells & Deleting Proposed Inclusion of Fuel Pool Water Level Inadvertent Drainage Into Amend ML20154M7181998-10-16016 October 1998 Proposed Corrected Tech Specs Section 3/4.6.C,relocating Portions of Reactor Coolant Sys - Coolant Chemistry ML20155E7831998-09-15015 September 1998 Rev 2 to Ja FitzPatrick NPP IST Program for Pumps & Valves Third Interval Plan ML20236X8041998-08-0303 August 1998 Proposed Tech Specs Section 1.1.A Re SLMCPR to Be Applicable During Cycle 14 ML20236M6231998-07-10010 July 1998 Proposed Tech Specs Pages Re Amend to Relocate TS 3/4.6.C, RCS - Coolant Chemistry, from TS to UFSAR & Applicable Plant Procedures Controlled by 10CFR50.59 Process ML20249B1631998-06-16016 June 1998 Proposed Tech Specs Re Relocation of Safety Review Committee Review & Audit Requirements ML20236L2931998-06-0707 June 1998 Proposed Tech Specs Section 3.5.b.1 Re Main Condenser Steam Jet Air Ejector & Table 3.10-1 Re Radiation Monitoring Sys That Initiates &/Or Isolates Sys ML20217K0391998-03-30030 March 1998 Proposed Tech Specs Changing Interval of Selected LSFT from Semiannually to Once Per 24 Months & Revising Definition for LSFT to Be Consistent w/NUREG-1433 B110073, Rev 1 to GE-NE-B1100732-01, FitzPatrick Reactor Pressure Vessel Surveillance Matls Testing & Analysis Rept of 120 Degree Capsule at 13.4 Efpy1998-02-28028 February 1998 Rev 1 to GE-NE-B1100732-01, FitzPatrick Reactor Pressure Vessel Surveillance Matls Testing & Analysis Rept of 120 Degree Capsule at 13.4 Efpy ML20247F7981998-02-26026 February 1998 Proposed Tech Specs Re Allowed Containment Leakage Rate ML20202G8841998-02-0606 February 1998 Revised Proposed TS Pages,Revising Allowed Outage Times for 4kV Emergency Bus Trip Functions & Replace Generic Actions for Inoperable Instrument Channels w/function-specific Actions ML20202D4021998-02-0606 February 1998 Proposed Tech Specs Revising RPS Normal Supply Electrical Protection Assembly Undervoltage Trip Setpoint as Result of Reanalysis Based on Most Limiting Min Voltage Requirements of Applied Loads ML20202D5621998-02-0606 February 1998 Proposed Tech Specs Allowing RCS Pressure Tests to Be Performed While Remaining in Cold Shutdown Mode ML20199G5921998-01-0707 January 1998 Rev 0 to JAF-ISI-0003, Third ISI Interval,Ten-Yr ISI Plan ML20199G5661998-01-0606 January 1998 Rev 0 to JAF-ISI-0002, Third ISI Interval,Isi Program. W/28 Oversize Drawings ML20203J6971997-12-12012 December 1997 Proposed Tech Specs,Revising Administrative Controls for Normal Working Hours of Plant Staff Who Perform Safety Related Functions ML20217J0021997-10-14014 October 1997 Proposed TS Pages Re Changes to Design Features Section, Including Revised Limits for Fuel Storage ML20217G3071997-10-0808 October 1997 Proposed Tech Specs Re Distribution of Inoperable Control Rods ML20217K5841997-09-30030 September 1997 Rev 1 to Ja FitzPatrick Nuclear Power Plant IST Program for Pumps & Valves,Third Interval ML20211H0801997-09-26026 September 1997 Revised Proposed TS Changes to ASME Section XI, Surveillance Testing ML20236N7061997-09-0909 September 1997 Proposed Tech Specs,Describing Licensee'S Configuration Risk Mgt Program Which Supports Rev of Allowed out-of-svc Times for Single Inoperable EDGs to Accommodate on-line Maint of EDGs ML20149G2571997-07-14014 July 1997 JAFNPP ISI Program Relief Requests for 2nd Ten-Yr Interval Closeout ML20140D8131997-04-14014 April 1997 Proposed Tech Specs Re SRC Audit Requirements & Mgt Title Change ML20198G7211997-04-0303 April 1997 Hot Rolled XM-19 Stainless Steel Core Shroud Tie-Rod Matl - Crevice Corrosion Investigation ML20136H3771997-03-11011 March 1997 Rev 0 to Power Uprate Startup Test Rept for Cycle 13 ML20135B1921996-11-26026 November 1996 Proposed Tech Specs,Requesting That Snubber Operability, Surveillance & Records Requirements in TS Be Relocated to Plant Controlled Documents ML20134M1751996-11-20020 November 1996 Proposed Tech Specs Reflecting Interposed Amend That Was Issued,Updating References to Repts on TS Pp & Changing Rev Bars on Previously Submitted Update Pp Which Were Erroneously Positioned on Pp ML20149L7191996-11-0808 November 1996 Proposed Tech Specs Re Min Critical Power Ratio Safety Limit ML20129G0091996-10-23023 October 1996 Proposed Tech Specs Re Page 134 Deleted Under Amend 236 & Remain Deleted ML20128Q7441996-10-11011 October 1996 Proposed Tech Specs Re Extension of Instrumentation & Miscellanous Surveillance Test to Accommodate 24 Month Cycles ML20135D0311996-07-31031 July 1996 Rev 4 to Radiological Effluent Controls & Offsite Dose Calculation Manual ML20115G0641996-07-12012 July 1996 Proposed Tech Specs Re Cycle 12 Min Critical Power Ratio Safety Limit ML20113B6511996-06-20020 June 1996 Proposed Tech Specs Re Option B to 10CFR50,App J for Primary Containment Leakage Rate Testing Program ML20112D1531996-05-30030 May 1996 Proposed Tech Specs,Revising Minimum Critical Power Ratio Safety Limit & Associated Basis ML20112D2721996-05-30030 May 1996 Proposed Tech Specs Re ATWS Recirculation Pump Trip Instrumentation Requirements ML20112D5711996-05-30030 May 1996 Proposed Tech Specs,Eliminating Selected Response Time Testing Requirements JPN-96-023, Proposed Tech Specs Re Deletion of Requirement for PORC to Review Fire Protection Program & Implementing Procedures. Addl Deletion of Insp & Audit Requirements of Specs 6.14.A & 6.14.B1996-05-16016 May 1996 Proposed Tech Specs Re Deletion of Requirement for PORC to Review Fire Protection Program & Implementing Procedures. Addl Deletion of Insp & Audit Requirements of Specs 6.14.A & 6.14.B ML20108D1171996-04-24024 April 1996 Proposed Tech Specs,Supporting Adoption of Primary Containment Lrt Requirements of Option B to 10CFR50,App J & Clarifying Numerical Value of Allowable Containment Leakage Rate as 1.5% Per Day 1999-09-29
[Table view] |
Text
.-.a - - . . .. . . . - - . -_ --
't ATTACHMENT I t-PROPOSED TECHNICAL SPECIFICATION CHANGES RELATED.TO MCPR OPERATING LIMITS 4
i I
u POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT ;
DOCKET NO. 50-333 DPR-59 4
4 8304040433 720220 p DR ADOCK 05000333 i PDR
O 3.1 (Cont!d) JAFNPP
- MTR Operating Limit for Incremental C. MCPR shall be determined daily during j Cycle Cbre Average Exposure reactor power operation at ) 25% of rated tier-am1. power and following any change in power Fuel Type DOC to BOC-lGHD/t to level or distribution that would cause 1GWD /t before EOC EOC operationwith a limiting control rod pattern as described in the banan for At 11DM trip level setting S = 0.66 W + 394 -
Specification 3.3.D.5.
8x8 1.24 1.26 D. When it is detennined that a, channel has 3
8x8R 1.24 1.25 failed in the unsafe condition, the
- P8x0R 1.25 1.28 other 11PS channelar that monitor the
- came variable shall be functionally At HDM trip level setting S = 0.66W + 40% tested inmediately before the trip
. system containing the failure is tripped.
2 8x8 1.24 1.26 'the trip systan containing the unsafe bx8R 1.24 1.26 failure may be placed in the untripped i P8x8R 1.25 1.28 cxrdition during the period in which surveillance testing is being perfonned At HDM trip level setting S = 0.66 W + 41% on the other RPS channels 8x8 1.27 1.27 E. Verification of the limits set forth
- 8x0R 1.27 1.27 in specification 3.1.D. shall be perfonned l l Pax 0R 1.27 1.28 as follows:
At UDM trip level setting S = 0.66 W + 42t 1. 'Ihe average scran time to notch I
8x8 position 38 shall bes t,' ,i tg 1.31 1.31 8x0R 1.31 1.31 2. 'ihe average scran dme to notch Pax 0R 1.31 1.31 position 38 is determined as follows:
n n TMt='
N1 Y1 Ni'
. i=1 i=1
~
where: n = matjer of surveillance testa performed to date in the cycle, Ni =
ntatjer of active rods measured in Ament! ment flo.g 1
l l
1
1 .
FIGURE 3.1-2a
~
Operating Limit MCPR Vez: 4as [ (Section 4.1.E)
For 8X8 Fuel Types 1.40--
v (V
1.35_ g,3 0 a:
m O
SO
.d e 1.30_, 0' 9
$ 90 86.l.29 3 - (0
'.j '
e goc -
O U
a-(O s s8 soc.to 1.25_
(0,1*
l.20_
i l I I I ~'s l I I I i 0 .1 .2 .3 .4 .5 .6 .7 .8 .9 1.0 1 '
L Option B: E=0 Option A:I = 1 47b Amendment No. [
FIGURE 3.1-b Operating Limit MCPR- Versus T (Section 4.1.E) -
For 8X8 R Fuel Types 1.40 _,
3 3 ,s -
ed 1.35 ~ Q 'g .3 c:
x v 96I y 1.30__, go (0 qg6< l'2 s o A C,\ s tn SO
.n j to EOC -
u g ,1 *9,6T goc o 1.25 _
(0 e l*24) 1.20 _,
r l l l l l l 1 l l l l 0 .1 .2 .3 .4 .5 .6 .7 .8 .9 J.0 Y
l l Option B: 'C = 0
, Option A: I =1 i
I Amendment No. fd 47c
FIGURE 3.1-2c Operating Limit MCPR Versus T (Section 4.1.E)
For P8X8 R Fuel Types i
1 gOT 1.40-.
(si (1,1 3 1.35-a:
n.
U z
C 29O v $0' j 1.30_. (0.661 ' g ,
w SO
. . (0 ' SOE
- BOc go u t ai 4
. o 1.25- 0 l
(0.l*2 1.20__
, L l
i I
l l l l l l l 1 l
0 .1 .2 .3 .4 .5 .6 .7 .3 .9 1.0 Y
f Option B: E =0 Option A: T! =l l
Amendment No. 47d 1
~ . , . .. _ _ . . . ~ -
. - ... .. . - .- . . . - . . . . . . = .- . .- ~-.
- ATTACHMENT II PROPOSED TECHNICAL SPECIFICATION CHANGES RELATED TO
^ '
MCPR OPERATING LIMITS t
r 4
4 8
F i
t l'
t i
1 i
POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT
- , DOCKET NO. 50-333 DPR-59 i
r k
.?
. . - = _ _ _ _ _ . __. _ ,___ , _ - _.-
. DESCRIPTION OF THE CHANGES LThe table of Minimum 1ritical PoJer Ratio (MCPR) Operating Limits in Section 3.1.B.1 cui page 31 is corrected as follows.
(Uncorrected MCPR limits are indicated with parentheses.)
TABLE I COMPARISON OF UNCORRECTED AND CORRE0TEP, VALVES.
MCPR-OPERATING-LIMITS FOR INCREMENTAL ~ CYCLE CdRE AVERAGE EXPOSURE BOC TO 1 GWD/t EOC - 1 GWD/t FUEL TYPE BEFORE EOC TO EOC ,
At RBM trip level setting S = 0.66W + 39%
8X8 1.24 (1.22) 1.26 (1.23) 8 X 8R 1.24'(1.22) >
1.26 (1.23)
P8 X 8R 1.25 (1.22) 1.28 (1.25)
At RBM trip level setting S =-0.66W + 40%
8X8 '1.24 (1.24)- 1.26 (1.24) 8 X 8R 1.24 (1.24) 1.26 (1.24)
- P8 X 8R 1.25 (1.24)- 1.28 (1.25) r At RBM trip level setting S = 0.66W + 41%
8X8 1.27 (1.27) 1.27 (1.27)
- 8 X 8R 1.27 (1.27) 1.27 (1.27)
, P8 X 8R 1.27 (1.27) 1.28 (1.27)
,At RBM trip level setting S = 0.66W + 42%
! 8X8 1.31 (1.31) 1.31 (1.31)-
8 X 8R 1.31 (1.31) 1.31.(1.31)
P8 X 8R 1.31 (1.31) 1.31 (1.31) "
. Accordingly, figures 3.1-2a, 3.1-2b and 3.1-2c (pages 47 b, c and d),
depicting MCPR operating limit versus scram time ratio (as defined <
in section 4.1.E), are changed to reflect the new limits. Both corrected and uncorrected curves are plotted for each fuel-type on the.following pages.
h 3
,,--r - . < - ---,,-,~~e-m'-- ,. .---eJ.---- - - + - - - - - < - . - . ~,----+,-...--,---- - - . - --,-4
Comparison of Corrected anc Uncurrected Limits Operating Limit MCPR Versus f (Section 4.1.E)
For 8X8 Fuel Types
= Corrected limits
= Uncorrected limits
- 1. 4 0__ ,
h
& 's-O 's.h .
' 0 1.35 -
./
- f @'9
/
Rh /
W s e -
N 19 @ *3 0T A
! 1.30 _. s g,oV f l O' tn
/
.9 s *T goc '
e (0 / /
M n
/
0 /
h~ <
/ qh2) 1.25 - (0 1 ,
, '\g .69 7'
,/
/
g ,s -
$ q,,
30c, ? 6,ge1 ' s.21T 1I 0.1 l . 2 0._
(O.g.2 I I I I i i I I J i 0 .1 .2 .3 .4 .5 .6 .7 .8 .g 1.0 L
-- ~~ -- _ . _ _ _ _ _ _ , ,, _
I
Comparicon of Correct ct and Uncorrected Limits Operating Limit MCPR Veruus T (Section.4.1.E) -
For 8X8R Fuel Types
= Corrected Limits
= Uncorrected Limits 1.40 -
9 0 *v
@'v$<A 0
- 1. 3 5__ ,. @ '% 3 s'
/
/
/
l
% /
0<
E /
O 'g .
.$ 1.30_. C A / f E gO / f
'j goge goc" p,
/
0 D '
g6T 0-
.; <e .s - .Oc js.,,,,1.2se, a4 c /
- s. -
1.25_ ,-
- c., -
(0 e 1* B.9 O
- g.12u 1.20_.
l l l l l l l 1 l l 0 .1 .2 .3 .4 .5 .6 .7 .8 9 1.0
Compcricon of Corrected and Uncorrected Limits Operating Limit MCPR Versus E (Section 4.1.E)
For P8X8R Fuel Types
= Corrected limits
= Uncorrected limits (1,10 1.40-.
(1,1.3
/
1.35_ /
(1e 13 4I 0 /- /
40 e ,' /
S % Soc - , '296) 6/ /
1.30 f
.a o (0.66)'
/
1 a /
./
/ -
0 T- (o,12 / / 2561
/ BOC / (0.600, 1, M / j i
o 1.25 / ,-
S -
(0 e l* goc'h '
3,e-0C
/(O.{.22) .
1.20 __
l l l l 1 I I I i I I I l 0 .1 .2 .3 .4 .5 .6 .7 .8 .9 1.0
[
, . ~ -- - , - - - .- , .,.
I..-PURPOSE OF THE CHANGES-
~
-Cycle'5 MCPR operating limits given in Section 3.1.B and in Figures 3.1-2 a,-b'and--c have been revised to account for-a nonconservative' error in. computer. calculations of the reactor's response to pressurization transients.: These calculations were originally' submitted in support of Cycle 5 operation by letter dated November 18,'1981 (Reference 1).
~
By telephone and letter. dated February 2, 1983.(Reference.2),.
the General > Electric' Company' informed the Authority of an error discovered in'the carryunder fraction used in input data.for its ODYN computer code. The ODYN' code is used to calculate plant response to transients, and:the results of ODYN analyses are used to
- - ' calculate MCPR operating limits for the cycle. Carryunder fraction is defined as,the weight fraction of steam bubbles entrained in recirculating' reactor water.(i.e.,. steam not separated out and sent to the turbine). The.carryunder fraction originally used was that value used~previously-in REDY analyses of pressurization transients.
The correct fraction should have been the lower value used in
< qualification'of the ODYN code as a_ licensing tool'(Reference 3).
~
In analyses of postulated pressurization transients, a lower
~ carryunder fraction leads to a greater ZiCPR for each fuel type, due primarily to an increase in the rate of pressuri'zation of the
'reactorEvessel. Hence, MCPR operating limits must be raised so that the MCPR values for each fuel type would not fall below fuel safety limits, should a_ pressurization transient occur.
'The' changes required in the MCPR-operating limits of Section 3.1.B were^ determined using results of analyses of the same-
- pressurization events for the upcoming Cycle 6 as those analyzed for r Cycle 5. . GETAB initial conditions and calculated-/SCPR's.using the erroneous carryunder fraction were compared for Cycle 5 and Cycle
- 6. In.all cases, the initial CPR's and the calculated 21CPR's for Cycle 6 were greater than-or equal'to those for Cycle 5. Therefore, the changes in /SCPR calculated for. Cycle 6 using the correct-carryunder fraction bound the changes for, Cycle 5 using the correct fraction.
The largest additional reduction in CPR for pressurization transients in' Cycle 6 using the correct fraction was determined to 1 be 0.03. For conservatism, new MCPR limits for Cycle 5 were thus determined?by adding an increment'of 0.03 to each calculated CPR
- value: tabulated for' pressurization transients, as shown in Table II'.
1he accepted methods-given in the NRC's Safety Evaluation Report on the ODYN code (Reference 4) were then applied to determine the Option A ( C = 1) and Option B ( t = 0) MCPR operr.U ng limits.
b~ <
. . -- l TABLE II CYCLE"6 ACPR FOR CORE-WIDE PRESSURIZATION TRANSIENTS With Erroneous' With Correct Exposure Carryunder Carryunder Transient Range (GWD/t) - Fraction Fraction 8X8R/P8X8R 8X8R/P8X8R
.22/.25 .24/.27
~
Load Rejection EOC-1 to EOC
.Without Bypass BOC to_EOC-1 .20/.22 1 .21/.24 l Feedwater.
! Controller EOC-1 to EOC .19/.21 .21/.23 Failure BOC to EOC-1 .15/.16 .17/.19 i
CYCLE 5 ACPR FOR CORE-WIDE PRESSURIZATION TRANSIENTS With Erroneous With Correct Exposure Carryunder Carryunder Transient Range (GWD/t) Fraction- Fraction 8X8 & 8X8R/P8X8R 8X8& 8X8R/P8X8R Load Rejection EOC-1 to EOC .22/.24 .25/.27 Without Bypass BOC to EOC-1 .18/.21 .21/.24 Feedwater Controller EOC-1 to EOC .17/.19 .20/.22 '
Failure BOC to EOC-1 .15/.16 .18/.~19 1 -
t -- t- -
-u- y-y -w -g._,
III. IMPACT OF THE CHANGES
--Since the MCPR operating limits calculated for pressurization events with.the corrected carryunder fraction were not limiting and are not expected to be limiting at any time during Cycle 5 operation, the proposed changes to the Technical Specifications have no impact-on plant operation. If scram-time surveillance determines that current-operation under Option B is no longer justified, then the corrected MCER operating limits will apply.
IV. IMPLEMENTATION OF THE CHANGES Implementation of the changes, as proposed, will not impact the ALARA or Fire Protection programs at FitzPatrick. Moreover, the changes will not impact the environment.
V. CONCLUSION The incorporation of these changes: a) will not increase the probability or the consequences of an accident or malfunction of equipment important to safety as previously evaluated in the Safety Analysis Report; b) will not increase the possibility for an accident or malfunction of a type other than that evaluated previously in the Safety Analysis Report; c) will not reduce the margin of safety as defined in the basis for any Technical Specification .and d) does not constitute an unreviewed safety question.
VI. REFERENCES
- 1. PASNY letter, J. P. Bayne to T. A. Ippolito, dated November 18, 1981 (JPN-81-92).
- 2. General Electric letter, C.M. Richards to J. M. Clabby (PASNY), dated February 2, 1983.
-3. NRC memorandum, D.G. Eisenhut to all BWR licensees, dated November 4, 1980 ([[::JAF-80-196|JAF-80-196]]).
- 4. Safety Evaluation of the ODYN Computer Code, issued with NRC Generic Letter No. 81-08, dated January 29, 1981.
- 5. FitzPatrick Prompt Reportable Occurrence Report, Corbin A.
McNeill, Jr. to Director of Regulatory Operation - Region I, dated February 3, 1983.
- 6. FitzPatrick Licensee Event Report No. 83-008/0lT-0, dated February 9, 1983 (JAFP-83-0167).
- 7. General Electric Thermal Analysis Basis (GETAB),
NEDO-10958-A, January 1977.
- 8. General Electric Standard Application for Reactor Fuel (GESTAR), NEDO-240ll-A-4, January 1982.