ML17223B166
| ML17223B166 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 04/17/1991 |
| From: | FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17223B165 | List: |
| References | |
| NUDOCS 9104240026 | |
| Download: ML17223B166 (29) | |
Text
ATTACHMENT I ST ~ LUCIE UNIT 1 TECHNICAL SPECIFICATIONS MARKED UP PAGES FOR F~y DELETION T
Pages:
Ia IV 1-7 3/4 2-2 3/4 2-6 3/4 2-7 3/4 2-8 3/4 2-11 3/4 10-2 B 3/4 2-1 B 3/4 2-2 9104240026 9104i7 PDR ADOCK 05000335 P-PDR
INDEX DEFINITIONS SECTION PAGE 1.23 Process Control Pr ogram (PCP).........,..........,...
~ 24 Purge
+ Purging o ~
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l.
1-5
.25 Rated Thermal Power....................,.........,.........
l.
1-6 1.26 Reactor Trfp System Response Time........................,...
1 6
.27 Reportable Event.......................,..........,..........
l.
1-6 1.28 Shield Sufldfng Integrity............,......,....
.29 Shutdown Margin...................,...,........,,...,.,
1 1-6
.30 Site Soundary................................................
1.
1-6
.31 Source Check..........-. "".................................
1 1-6 1.32 Staggered Test Hasfs..................................-.......
1-7
.33 Thermal Power................................................
1 1-7 1.34 Unfdentfffed Leakage.........................................
1-7 1.35 Unrestrfcted Area............................................,
1-7 1.36 Unrodded Integrated Radial Peaking Factor Fro ~ ~ ~ ~ ~ ~ ~ ~ ~
~ ~ ~ ~ ~ 1-7 1.37 ded nar fal eakfn F
or-
. 1-7 j
OKLETE ST.
LUCIE - UNIT 1
Ia Amendment No.
$$,N>69
INDEX LIMITING CONDITIONS FOR OPERATION ANO SURVEILLANCE RE UIREMENTS SECTION 3 4.2 POWER DISTRIBUTION LIMITS PAGE 3/4.2.1 LINEAR HEAT RATE.... ~...........................,....
3/4 2-1 3/4.2.2 TOTAL NAR R
PEAK ACTOR-
~
~
~
~
~
~
~
~
~
o 3/4 2
6 3/4.2.3 TOTAL INTEGRATED RADIAL PEAKING FACTOR - F..........
3/4 2-9 3/4.2.4 AZIMUTHAL POWER TILT - T q
3/4.2.5 ONB PARAMETERS
..............,3/4 2-11
~ ~ ~ ~
~
~
~ o
~
~ ~ ~ ~ ~ 3/4 2
13 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTIVE INSTRUMENTATION...................
3/4 3-1 3/4.3.2 ENGINEEREO SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION......................................
3/4 3-9 3/4 3-21 3/4 3-21 3/4 3-25 3/4 3-27 3/4 3-30 3/4 3-33 3/4 3-37 3/4 3-41.
3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring.................................
Incore Detectors..............,......................
Seismic Instrumentatfon..............................
Meteoro1ogfca1 Instrumentatfon...............-..
Remote Shutdown Instrumentatfon..................
Fire Oetectfon Instrumentation.......................
Accident Monitoring Instrumentatfon............,.
Radfoactfve Liquid Effluent Monitoring Instrumentatfon.................................
~ ~ ~ ~ ~
..... 3/4 3-45 Radf oactf ve Gaseous Effluent Monitorfng Instrumentatfon......................................
3/4 3-50 3 4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS ANO COOLANT CIRCULATION.......- 3/4 4-1 3/4.4.2 SAFETY VALVES -
SHUTDOWN.............................
3/4 4-2 3/4.4.3 SAFETY VALVES - OPERATING............................
3/4 4-3 ST.
LUCIE - UNIT 1 IV Amendment No. 27, 37,
$7,5 g
'4 0
DEFINITIONS STAGGERED TEST BASIS 1.32 A STAGGERED TEST BASIS shall consist of:
a.
A test schedule for n systems, subsystems, trains or-other designated components obtained by dividing the specified test interval into n equal subintervals, and b.
The testing of one system, subsystem, train or other designated component at the beginning of each subinterval.
THERNL POWER 1.33 THERtOL POWER shall be the total reactor core heat transfer rate to the reactor coolant.
!1.34 UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED LEAKAGE or CONTROLLED LEAKAGE, UNRESTRICTED AREA 1.35 An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.
UNRODDED INTEGRATED RADIAL PEAKING FACTOR - Fr 1.36 The UNRODDED INTEGRATED RADIAL PEAKING FACTOR is the ratio of the peak pin power to the average pin power in an unrodded core, excluding tilt.
UNROODED NAR RADIAL AKING FACT Fxy 7
The UNRO D PLANAR RA L PEAKING CTOR i the maximu ratio of e
pea to average p
er density the indiv al fue ods in an of the unrod d horizontal lanes.
excl ing tilt.
DEL rE ST. LUCIE - UNIT 1 1-7 Amendment No. N 06g
POWER OISTRIBUTION LIMITS SURVEILLANCE RE UIREMENTS (Continued c ~
Veri fying that the AXIAL SHAPE INOEX is maintained within the allowable limits of Figure 3.2-2, where 100 percent of maximum allowable power represents the maximum THERMAL POWER allowed by the following expression:
where:
1, M is the maximum allowable THERMAL POWER level for the existing Reactor Coolant Pump combination.
2.
N is the maximum allowable fraction of RATEO THERMAL POWER as det ined by the / curve of Fi ure 3.2-3.
p,on f~
~
C~iere 4.2.1.4 Incore Oetec or Monitorin S stem
- The incore detector monitor-ing system may be used for monitoring the core power distribution by verifying that the incore detector Local Power Oensity alarms:
a.
Are adjusted to satisfy the requirements of the core power distribution map which shall be updated at least once per 31 days of accumulated operation in MOOE l.
b.
Have their alarm setpoint adjusted to less than or equal to the limits shown on Figure 3.2-1 when the following factors are appropriately included in the setting of these alarms:
2.
3.
A measurement-calculational uncertainty factor of 1.07, An engineering uncertainty factor of 1.03, A THERMAL POWER measurement uncertainty factor of 1.02.
SIf the core system becomes inoperable, reduce power to M x N within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and monitor linear heat rate in accordance with Specification 4.2.1.
ST.
LUCIE - UNIT 1 3/4 2-2 Amendment No. J7, 87, PR,SP@~70
POWER DISTRIBUTION LIMITS TOTAL PLA RADIAL PEAKING FACTOR FT LIMITING CONDI N
FOR OPERATION
>2.2 The calculated lue of FTy shall be li ted to 1.70.
APPL B ILITY:
MODE 1>>.
ACTION:
With FTy
> l.
within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> eith a.
b.
Reduce T
POWER to bring t combination of THE L POWER and F'o
'thin the limits of ure 3.2-3 and withdr the full Qngth C
to or beyond the L
Term Steady State Insertion Limits f Specification 3.1.
6; or Be n
HOT STANDBY.
SU E ILLANCE REQUI ENTS 4.2.2.1 e provisions o
Specification 4.0.
re not applicable.
4.2.2.2 FTx al'I be calcula by the expression Fxy(1+T
) when calcula8d w
h a non-full c power distribution~ nalysis c3de and sha 1 be calculat as Ffy ~ Fxy w n calculations are rformed with a full re power dis ibution analys code.
FT>> shall be termined to be within ts limit at t following inte als:
a.
ior to operat n above 70 pere t of RATED THERMAL P R
af r
each fuel 1
- ding, b.
At lea once per 31 s of accumulat operation in MODE 1, and c.
Within four urs if the AZ HAL POWER TIL Tq) is
~ 0.03.
Special Test-xception 3.1 ST.
LUCIE - UNIT 1
3/4 2-6 Amendment No. 27, 32,
NLRB"
~ q 1
'1 I
POWER OISTRIBUTION LIMITS SU EILLANCE RE REMENTS Co tinued 4.2.2.3 shall be d termined ea time a
c culation o
F is T
Xy uired by ing the inc e detectors -to obtain power dist 'bution map ith all 1 length C
at or above the Long erm Steady ate Inser on Limit qr the existigg Reactor Ceolant Pum combination.
This determi tion shalgbe limited'.to core planing between X and 85K o full care eight and'shall excluberegians influenced by rid effects V
4.
2.4 T
s ll be determined each time a cele&latino of T
is made using nan full're powergistribution,ana lysi's code.
The v
ue of Tg used in t s case to etermineVTy shall b
the measured value of DELETE ST.
LUCIE - UNIT 1
3/4 2-7 Amendment No. V, 55
1.1 1.0 1.7, 1.0)
UHACCEPThBI.E OPERA! ION REG lON 0.9 (l.78, O
0.8 CJ hCCEPTADLE OPERATION REGION 0.7 0.6 1..70 1.71.
1.72 1.73 1.74 5
Heasured F<
F
'T T
1.76 1.77 1.78 FIGURE 3.2-3 hllouable Combinations Of Tbcnaal Power And F DELET E
POWER DISTRIBUTION LIMITS AZIMUTHAL POWER TILT - T LIMITING CONDITION FOR OPERATION 3.2.4 The AZIMUTHAL'OWERTILT (T ) shall not exceed 0.03.
APPLICABILITY:
MODE 1*
ACTION:
a a b.
With the indicated AZIMUTHAL POWER TILT determined to be
>.030 but ( 0.10, either correct the power tilt within two hours or determine within th u
a d t e
s per subsequent 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, that T
A PL A
P P
the TOTAL INTEGRATED RADIAL PEAKING FACTOR (Fr) within the limits,of Specificatio 3.2.3.
l5 I
With the i cated AZIMUTHAL POWER TILT determined to be
> 0.10 ~
operation may proceed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> provided that the TOTAL ~
AKING FACTOR (Fn) fl PAL/f~A CI IN F
TlR)I F
)
w'n the limits of Specificationg 3 2p 3.2.3.
Subseque operation for the purpose of I
measurement and to identify the cause of the tilt is allowable provided the THERMAL POWER level is restricted to <'205 of the maximum allowable THERMAL POWER level for the existing Reactor Coolant Pump combination.
SURVEILLANCE RE UIREMENT I
4.2.4.1 The provisions of Specification 4.0.4 are not applicable.
4.2.4.2 The AZIMUTHAL POWER TILT shall be determined to be within the limit by:
a.
Calculating the tilt at least'once per 7 days when the Subchannel Deviation Alarm is OPERABLE,
- See Special Test Exception 3.10.2.
ST.
LUCIE - UNIT 1 3/4 2-11 Amendment No.
32
SPECIAL TEST EXCEPTIONS GROUP HEIGHT INSERTION ANO POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION 3.10.2 The group height, insertion and power distribution it of Specfffcations
- 3. 1. 1.4, 3. 1.3. 1, 3. 1.3.2, 3. 1.3.5, 3. 1.3. 6.
.2.3 and 3.2.4 may be suspended during the performance of PHYSICS provided:
a.
The THERMAl. POWER is restricted to the test power plateau which shall not exceed 85% of RATED THERMAL POWER, and b.
The limits of Specification 3.2. 1 are maintained and deter-mfned as specified in Specification 4.10.2.2 below.
APPLICABILITY:
MODES 1 and 2.
ACTION:.
With any require 3.1.3.6,
'a ~
of the limits of Specification 3.2.1 being exceeded while the f Specifications 3.1.1.4. 3.1.3.1, 3.1.3.2, 3.1.3.5,
~
~
~
p 3.2.3 and 3.2.4 are suspended, either:
L.ETK Reduce THE OQER sufffcfently to satisfy the requirements of Specification 3.2.1. or b.
Be fn HOT STANDBY wfthfn 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE RE UIREMENTS DuxWK 4.10.2.1 The THERMAL POWER shall be dete ed at least once per hour during PHYSICS TESTS fn which the re nts of Specifications 3.1.1.4, 3.1.3.1, 3.1;3.2, 3.1.3.5, 3.1.3.6, 3.2.3 or 3.2.4 are suspended and shall be verified to be within the est power plateau.
4.10.2.2 The lfnear heat rate shall be determined to be wfthfn the lfmfts of Specfffcatfon 3.2.1 by monitoring ft continuously with the Incore Detector Monftorfng System pursuant to the requirements of Specifications 4.2.1.3 and 3.3.3.2 durfng PHYSICS TESTS above 5X of RATED THERMAL POWER in which the re nts of Specifications 3.1.1.4, 3.1.3.1. 3.1.3.2, 3.1.3.5, 3.1.3.6 3.2.3 or 3.2.4 are suspended.
ozaa~a ST. LVCIE - UNIT 1 3/4 10-2 Amendment No.
(p
.r e
3/4.2 POWER OISTRIBUTION LIMITS.
BASKS 3/4.2.1 LINEAR HEAT RATE t
The limitation on linear heat rate ensures that in the event of a
- LOCA, the peak temperature of the fuel cladding will not exceed 2200'F.
Either of the two core power distribution monitoring systems, the Kxcore Oetector Monftorfng System and the Incore Oetector Monftoring System, provides adequate monitoring of the core power distrfbutfon and is capable of verifying that the linear heat rate does not exceed its limits.
The Kxcore Oetector Monitoring System performs this function by continuously monitoring the AXIAL SHAPE INOEX with the OPERABLE quadrant symmetric excore neutron flux detectors and verifying that the AXIAL SHAPE INOEX fs maintained within the allowable limits of figure 3.2-2.
In conjunction with the use of the excore monitoring system and in establishing the AXIAL SHAPE INOEX. limits, the following assump-tions are made:
I) the CEA insertion limits of Specifications 3.1.3.5 and 3.1.3s6 are satisfied,
- 2) the AZIMUTHAL POWER TILT restrictions of Specifica-t1on 3.2.4 are sat1sfsed, and 3) the TOTAL RAOIAL PEAKING FACTOR does not exceed the limits of Speci Aoo:
9, c,9.
Acg; gTEQRATE'>
The Incore Oetector Monitorfng System continuo y prov des a direct measure of the peaking factors and the alarms which have been established for the individual fncore detector segments ensure that ffle peak linear heat rates will be maintained within the allowable limits of figure 3.2-1.
The setpoints for these alarms include allowances, set fn the conservatfve directions. for I) a measurement-calculatfonal,uncertainty factor of 1.07,
- 2) an engineering uncertaincy factor of 1.03, 3) a THERMAL POWER measurement uncertainty factor of 1.02.
~be LESE Er.6TG 3 4.2.3 and 3/4.2.4 TOTAL INTKGRATEO RAOIAL PEAKING "
FACTOR)-
F ANO EL,EIE The limftatfons on tions used in the analys Local Power Oensfty-Hf h
op rat n a var us imf tfo s o F
d T AZIMUTHAL POWER TILT - T F~'n T
are provided to ensure that the assump-q s for establfshfng the inear Heat Rate and LCOs and LSSS set ofnts em in ali dur n
0 gr up n
r on imi s.
h ar pr vf d
e u
t at he s
t ns AOb'-
ST.
LUCIE - UNIT I B 3/4 2-1 Amendment No. )7/,p,pspb 70
PQQER OISTRIBUTION LIMITS BASES FT an are es ~f FT a
each provides Pl STE CO EE
'T LET arglyp1s es b
the ONB Ma f
CO, and Thermal Margin/Low Pressure L
S se po n s remain va id durin eration at the various allowable CEA group insertion limits. If FT or T exceed their basic I
limitations, operation may continue under addftfon31 restrictions imposed by the ACTION statements since these additional restrictions provide adequate provisions to assure that the assumptions used fn establfshing the Linear Heat Rate, Thermal Margin/Low Pressure and Local Power Oensity - High LCOs and LSSS setpoints remain valid.
An AZIMUTHAL POMER TILT ) 0.10 is not expected and if ft should occur, subsequent operation would be restricted to only those operations requi red to identify the cause of this unexpected tfIt.
ceo: F EL T T
Gg r
requiremen at measured value (I+Tq) be mul tiplied by the alculate~lu@ of Fr to determine is applicable only when Fr a!4 calculated wi a
on-full core distribution analysis.
full core power distribution analysis code the azimuthal tilt is explicitly accounted for as part of the radial power distribution used to cal cul ate x
Fr.
o LETE I
ELK%
The surveillance requirements for verifying that I
within their limits provide assurance that the actu I
and T do not exceed the assumed values.
Verffyfn 1
fuel loading preen Co exceedfng 755 of RATEO THERMAL addftional assurance that the core was properly Ioade 3 4.2.5 ONB PARAMETERS The lfmfts on the ONB related parameters assure that each of the parameters are maintained within the normal steady state envelope of opera-tion assumed. in the transient and accident analyses.
The limits are consis-tent with the safety analyses assumptions and have been analytically demon-strated adequate to maintain a minimum ONBR of ~ 1.22 throughout each analyzed transient.
The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> periodic surveillance of these parameters through instrument readout fs sufffcfent to ensure that the parameters are restored within their limits fo11owfng load changes and other expected transient operation.
The 18 month periodic measurement of the RCS total flow rate is adequate to detect flow degradatfon and ensure correlation of the flow indication channels with measured flow such that the indicated percent flow will provide sufficient verfffcation of flow rate on a
12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> basis.
ST.
LUCIE - UNIT I B 3/4 2-2 Amendment No. g7, g8, 53,
ATTACHMENT II SAFETY ANALYSIS INTRODUCTION - BACKGROUND This is a request to delete the St. Lucie Unit 1 Technical Speci-fication 3/4.2.2 "Total Planar Radial Peaking Factor Fxy and all of its associated references.
Advanced Nuclear Fuels Corporation (ANF) previously performed the setpoint analysis for St. Lucie Unit 1 reloads ANF-1 through 4
using Axial Power Distributions (APDs) generated by using a one-dimensional core simulator model which required the presence of T
an Fxy limit (Reference 1).
For the ANF-5 reload (current reload),
and future reloads, the APDs were and will be generated by using a three-dimensional (3-D) core model (Reference 2).
The use of the APDs from the 3-D core model obviates the need for the T
Fxy parameter because a synthesis of the 1-D axial power shapes and the 2-D radial power distribution is no longer performed.
The NRC has determined that the use of the 3-D core model does not constitute a methodology change (Reference 3).
Thus, the deletion of the Fxy Technical Specification limit is possible because ANF's 3-D power distribution methodology does not require it.
II.
SAFETY ANALYSIS (continued)
DESCRIPTION OF TECHNICAL SPECIFICATION CHANGES The detailed description of the proposed changes related to the deletion of the Fxy limit are presented below:
1.
Item:
Page Ia Action:
Reference to the "Unrodded Planar Radial Peaking Factor Fxy" is deleted from the Index of Definitions.
Discussion:
This change is needed due to the deletion of the Definition 1.37 (which defines the "Unrodded Planar Radial Peaking Factor Fxy ).
2.
Item:
Page IV Action:
Reference to the Technical Specification 3/4.2.2 is deleted from the Index of Limiting Conditions for Operation and Surveillance Requirements.
Discussion:
This change is needed due to the deletion of Technical Specification 3/4.2.2.
3.
Item:
Page 1-7 Action:
The definition 1'7 "Unrodded Planar Radial Peaking Factor Fxy" is deleted.
Discussion:
The deletion of Technical Specification 3/4.2.2 obviates the need to have a
definition for Fxy.
4.
Item:
Page 3/4 2-2 Action:
The term "Fxy" in Surveillance Requirements 4.2.1.3 Item c. is replaced with the term tlF ltr
~
Discussion:
When the LHR is monitored by excore detectors the allowable core power distribution was based on the Total Planar Radial Peaking Factor Fxy.
Due to the revision in the setpoint methodology, assurance that LHR limits are not exceeded is provided by adherence to Technical Specification 3/4.2.3 limit on "Total Integrated Radial Peaking Factor Fr".
5.
Item:
Pages 3/4 2-6, 3/4 2-7 Action:
The "TOTAL PLANAR RADIAL PEAKING FACTOR Fxy Limiting Condition for Operation 3. 2. 2 and Surveillance Requirements 4.2.2.1, 4.2.2.2, 4.2.2.3 and 4.2.2.4 are deleted.
Discussion:
This change is needed because ANF's setpoint methodology does not require the Planar Radial Peaking Factor Fxy to determine the maximum total core peaking factor.
6.
Item:
Action:
Page 3/4 2-8 Reference to FxyII is deleted from Figure 3.2-3.
Additionally the term "Flii is deleted Discussion:
The deletion of the "Fxy" term from Figure 3.2-3 is needed due to the deletion of Technical Specification 3/4.2.2 (which defines the limits of the peaking factor Fzy).
The term "Fl" in the title "Measured Fr( Fj is a T
T T
typographical error.
The term should have been "Fxy" which is being deleted.
7.
Item:
Page 3/4 2-11 Action:
References to the "Total Planar Radial Peaking Factor, Fxy" and to the limits of Specification 3.2.2 are deleted from the Technical Specification 3/4.2.4.
Revised text accounts for the deletions.
Discussion:
These changes are based on the deletion of Technical Specification 3/4.2.2.
8.
Item:
Page 3/4 10-2 Action:
References to the Technical Specification 3.2.2 are deleted from the Technical Specification 3/4.10.2.
Discussion:
These changes resulted due to the deletion of Technical Specification 3/4.2.2.
9.
Item:
Page B 3/4 2-1 Action:
In the Technical Specification Bases for 3/4.2.1 for Linear Heat Rate, the word "PLANAR" is replaced with the word "INTEGRATED" and the reference to Technical Specification "3.2.2" is replaced with Il3 2
3 II Discussion:
When the LHR is monitored by excore detectors the allowable core power distribution was based on the Total Planar Radial Peaking Factor Fxy Due to the revision in the setpoint methodology, assurance that LHR limits are not exceeded is provided by adherence to Technical Specification 3/4.2.3 limit on "Total Integrated Radial Peaking Factor Fr".
10.
Item:
Pages B 3/4 2-1, B 3/4 2-2 Action:
Technical Specification Bases for 3/4.2.2 is deleted.
The text is corrected to account for the deletion of the Fxy limit.
Additionally, the term "Fr" is being added to the text after the word "determine" in the second line of the second paragraph of Page B 3/4 2-2.
Discussion:
With the deletion of Technical Specification
/
3/4.2.2 the need to have a basis for Fxy is obviated.
The term "Fr" was omitted from the original text and is being added to technically correct the text.
SAFETY ANALYSIS (continued)
TECHNICAL DISCUSSION The Technical Specification limit on Planar Radial Peaking Factor Fxy enters into the setpoint analyses for the Local Power Density (LPD) Limiting Safety System Settings (LSSS),
and LPD Limiting Conditions for Operation (LCO).
The LPD LSSS setpoint is established to produce a reactor trip during any plant Condition II transient to prevent exceeding the 21 kw/ft LPD or Linear Heat Rate (LHR)limit which coincides with fuel centerline melt.
The LPD LCO is an operational limit on reactor power (currently 15 kw/ft for Unit 1) to assure that the calculated peak cladding temperature will not exceed the regulatory limit of 2200'F during a Large Break Loss of Coolant Accident (LOCA).
The'PD LCO also provides monitoring requirements in the event in-core detectors are inoperable and it protects against penetration of the 15 kw/ft LPD limit.
The LPD limit shown in Technical Specifications is essentially the locus of the limiting values of core power level versus Axial Shape Index (ASI).
ASI is defined as the difference between the core power in the bottom half of the core and the top half divided by the sum of the top and bottom halves.
These limiting values are correlated to provide allowable power level as a function of axial shape index.
In the analyses for the LPD LSSS and LCO a large number of Axial Power Distributions (APDs) are examined to establish bounding values of the Total Power Peaking Factor (F~), versus ASI.
The peak linear heat rate occurs at the position of the maximum total peaking factor (F~).
The axial power distributions used in the
e
- J
~. a lp f
setpoint analyses for St.
Lucie Unit 1 reloads ANF-1 through 4
(Cycle 6 through
- 9) were generated using an axial one-dimensional (1-D) core simulator model together with a two-dimensional power distribution.
In this synthesis technique, the total peaking factor(
FQ) is determined by:
F~
= Fzy x Fz where F~
= core maximum surface heat flux factor Fzy
= ratio of maximum surface heat flux in an axial core plane to the average surface heat flux in that plane Fz
= Core average axial power (heat flux) distribution.
When synthesizing a
core maximum F~
from a one-dimensional Fz distribution and a separate 2-D peaking factor, assurance that the resultant F~ is not exceeded is obtained by limiting the maximum value of Fzy at which the core can operate.
The Axial Power Distributions (APDs) used in the setpoint analyses for St. Lucie Unit 1 ANF-5 (current cycle) and future ANF reloads were and will be generated using a three-dimensional core simulator model.
ANF has demonstrated that the use of the 3-D APD generation without an Fzy limit provides an F~ value that is not significantly different from the value obtained from the 1-D methodology with an Fzy limit.
Therefore, the resu its for the setpoints will not. be significantly different.
In the 3-D APD generation, the core maximum surface heat flux factor F~ is calculated directly from the XTGPWR 3-D core model.
The need for an Fzy Technical Specification limit is eliminated since F~ is calculated directly and is limited by adherence to the Fr Technical Specification limit.
SAFETY ANALYSIS (continued)
REFERENCES 1.
Exxon Report, XN-NF-507, "ENC Setpoint Methodology for CE Reactors",
dated July 1980.
2.
Advanced Nuclear Fuels Report, ANF-507 (P)
Addendum 1
"Advanced Nuclear Fuels Corporation Setpoint Methodology for CE Reactors:
Three Dimensional Axial Power Distribution Generation",
dated June 1988.
3.
NRC Letter, M.W. Hodges (NRC) to R.A. Copeland (ANF),
"ANF 3-dimensional Setpoint Methodology for Combustion Engineering Reactors",
dated July 8, 1988.
ATTACHMENT III DETERMINATION OF NO SIGNIFICANT HAZARDS The standards used to arrive at a determination that a request for amendment involves no significant hazards consideration are included in the Commission s regulation 10 CFR 50.92, which states that no significant hazards considerations are involved if the operation of the facility in accordance with the proposed amendment would not (1) involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety.
Each standard is discussed as follows:
(1)
Operation of the facility in accordance with the proposed amendment would not involve a significant increase in the probability or consequences of an accident previously evaluated.
The LPD LSSS and LPD LCO setpoints ensure that the core thermal limits are not exceeded.
The setpoint analysis utilizes the total core peaking factor, Fg and radial I
peaking factory Fry to establish the operational limitations.
The planar power peaking factor,
- Fxy, limitation was utilized in the synthesis of the total core peaking factor F~.
Improved physics methodology for core modeling to generate three-dimensional axial power distributions (APDs) obviates the need for the Fxy factor since it permits the direct calculation of F~ using the peak assembly Axial Power Distribution (APD).
The dependence of the LPD setpoint methodology on the Technical Specification Fxy limit is replaced with an equivalent dependence on the Fr Technical Specification limit.
Therefore, adherence to the Fr Technical Specification effectively limits core F~,
and assures that the LPD setpoint methodology results will bound reactor operation.
With the exception of the replacement of Fr for Fxy there T
T has been no change to the input or acceptance criteria used in the safety analysis.
No FSAR safety limits have been exceeded based on the proposed Technical Specifica-tion change.
The FSAR conclusion that the design basis acceptance criteria are met for the Condition II events remain valid.
Therefore, it can be concluded that the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
(2)
Operation of the facility in accordance with the proposed amendment would not create the possibility of a new or different kind of accident from any accident previously evaluated.
The proposed change does not affect any active hardware involving plant operation nor does it alter the mode of operation of the plant.
The limitation of the Planar Radial Peaking Factor Fxyp is replaced with the equivalent limitation of the Total Integrated Radial T
Peaking Factor Fr as a result of the improved core modeling in the setpoint methodology.
The proposed change creates no new accident initiators.
Therefore, it can be concluded that the proposed changes will not create the possibility of a new or different kind of accident from any previously evaluated.
(3)
Operation of the facility in accordance with the proposed amendment would not involve significant reduction in a margin of safety.
The deletion of the Fzy limit has been reviewed for the impact upon the current licensed safety analyses.
Assumptions in the accident consequences remain valid.
The changes caused by the proposed Technical Specification change are bounded by the assumptions in the accident analyses.
Therefore, it can be concluded that. the proposed changes do not involve a significant reduction in a margin of safety.
Based on the above, it has been determined that the proposed amendment does not (1) involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety.