ML20024H311
| ML20024H311 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 05/23/1991 |
| From: | HOUSTON LIGHTING & POWER CO. |
| To: | |
| Shared Package | |
| ML20024H310 | List: |
| References | |
| ST-HL-AE-3756, NUDOCS 9105310175 | |
| Download: ML20024H311 (48) | |
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Attachment 1 Technical Specifications Affected and Description of Change A1/026,ts18 9105310175 910523 PDR fiDOCK 0500049E P PDR
Ml ACHMENT l ST-HL AE-3 75 6
- PAGE 8
._ 0F _A l
TECHNICAL SPECIFICATIONS AFFECTED BY PROPOSED l AMENDMENT AND BRIEF DESCRIPTION OF CHANGE PAGE TECHNICAL SPECIFICATION CHANGE DESCPIPTION 3/4 1 6 3,1,1,1 Moderator Temp- Relocates MTC Limits to the erature Coefficient COLR and corrects referetices 3/4 1-7 4.1.1. 3 MTC Surveillance Relocates MTC Limits to the Requirement COLR and corrects references 3/4 1-7a New Figure 3.1-2a, Maximum Retains upper !!TC Limit. MTC Limit Curve, MCT Required for positive MTC vs Power Level. Page Spec (future possibility). added to Tech Specs to Figure is also in COLR for accommodate it. T. S. 3.1.1.3 B3/4 1-2 3/4.1.1.3 Moderator Administrative Change. MTC Temperature Coefficient Limits have been relocated to the Bases the COLR. 3/4 1-16 3.1.3.1.b.2 Movable Administrative change. Control Assemblies- Removes reference to Group Height Figure 3.1-3, removed to the COLR in a previous amendment 3/4 1-17 3.1.3.1.c.1 Movable Administrative change. Removes Control Assemblies- reference to figure 3.1-3, removed Group Height to the COLR in a previous amendment. 3/4 1-22 3.1.3.5 Shutdown Rod Administrative change. Insertion Limit Clarifies that the fully withdrawn position for shutdown banks is specified in the COLR. 3/4 2-1 3.2.1.b Axial Flux Replaces references to Figure Difference 3.2-1, which is moved to the COLR 3/4 2-2 3.2.1.C Axial Flux Deletes the word "above" Difference twice in reference to Figure 3.2-1, 3/4 2-4 Figure 3.2-1 BLANK Figure moved to the COLR B3/4 2-1 3/4.2.1 Axial Flux Administrative change. The Fo Limit Difference Bases is removed to the COLR B3/4 2-2 3/4.2.1 Axial Flux Removes reference to Figure 3.2-1, I Difference Bases Figure 3.2-1 removed to the COLR Page 1 of 2 A1/626.N18
ATTACHMENT I - ST HL AE 37S6 PAGE A 0F 2 TECHNICAL SPECIFICATIONS AFFECTED BY PROPOSED AMENDMENT AND BRIEF DESCRIPTIOE OF CHANCE EAGE TECHNICAL SPECIFICATION CHANGE DESCRIPTION 3/4 2 5 3.2.2 Heat Flux Hot Relocates the Fo and K(Z) Channel Factor to the C01R. The numerical Fo limit is replaced with a function fo", which is to be specified in the COIR 3/4 2-6 Figure 3.2-2 BIANK Figure moved to the COLR 3/4 2-7 4.2.2.2.C.2 Heat Flux Hct Replaces the numerical part Channel Factor Surveil- power multiplier for F,y lance Requirements with a function PF,y, which will be specified in the COLR 3/4 2-8 4,2.2.2.e Heat Flux Hot Administrative Change Channel Factor Surveil- The Radial Peaking Factor lance Requirements Limits Report was replaced by che CO M in a previous amendment B3/4 2-5 3/4.2.2 and 3/4.2.3 Heat Administrative change. The Radial Flux Hot Channel Factor Peaking Factor Limits Report was and Nuclear Enthalpy Rise replaced by the CO M in a previous Hot Channel Factor Bases amendment 3/4 2-9 3.2.3 Nuclear Enthalpy Relocates the Fon to the Rise Hot Channel Factor COLR. The numerical values for the Fon limit and the part power multiplier are replaced with parameters fof, and PFon, which are to be defined in the COM 6-20 6.9.1.6 Core Operating Administrative change. Limits Report Expand the description of the COLR and its control. Spillover and T.S. 6.9.2 go onto new page 6-20a Page 2 of 2 A?/026.N18
Attachment 2 No Significant llazards Evaluation , A1/026.N18
r~jTTACHMENT 2 ST.HL AE- 3 75 6 PAGE I 0F _ 'I _. 4 NO SIGNIFICANT HAZARDS EVALUATION FOR CHANCES TO TECHNICAL SPECIFICATIONS DELETING CERTAIN CYCLE SPECIFIC PARAMETERS Backtround Generic Letter 88-16, dated October 4,1989,, was issued to encourage licensees to prepare changes to Technical Specifications related to cycle. specific parameters. These Technical Specification changes will relocate cycle-specific parameter limits from Technical Specifications to the Core Operating Limits Report (C0lR). These parameter limits in the South Texas Project Electrical Generating Station Technical Specifications are currently calculated using NRC approved methodologies. These limits are evaluated for every reload cycle, and may be revised periodically to reflect changes to cycle specific variables. This represents an administrative burden to both the NRC, and Houston Lighting & Power. The generic letter provided guidance to allow relocation of certain cycle-dependent core operating limits from the STP Technical Specifications. This would allow changes to the values of core operating limits without prior approval (i.e., license amendment) by the NRC, provided that an approved methodology was used for the paremeter limit. Thus, cycle specific changes to these limits will require a safety review in accordance with 10 CPR 50.59 instead of a prior submittal to the NRC. Toward this end, a previous license amendment created a COLR for the South Texas Project. The initial creation of this document relocated limits for control rod insertion, Fay, and axial flux difference. The proposed amendment expands on the document previously created, moving Moderator Temperature Coefficient, Heat Flux Hot Channel Factor, and Nuclear Enthalpy Rice Hot Chanc.cl Factor to the COLR. The COLR limits will continue to be calculated with NRC-approved methodologies, and the COLR itself will continue to be controlled as a unit-specific document. Proposed Chance The proposed technical specification changes concern the relocation of several cycle-specific core operating limits for the South Texas Project from the Technical Specifications to the COLR. The impacted Technical Specifications will be amended to note that the limit has been relocated to the COLR, and the COLR paragraph in the Administrative Controls Section will be expanded to provide more information than is currently present. The COLR will still be required to be submitted to the NRC to allow for continued trending of the cycle-specific parameters. l 4 A1/026.N18
ATTACHMENT A ST HL AE 375'6 PAGE - A_ ~~ OF 1'~~m The proposed changes will reference the COLR for specific parameters, and will ensure that cycle-specific parameters are maintained within the limits of the COLR. The cycle-specific parameter limits proposed for relocation to the COLR as part of this license amendment includes (a) 3.1.1.3 Modorator Temperature Coefficient l (b) 3.1.3.5 Shutdown Rod Insertion Limits (c) 3.2.1 Axial Flux Difference (d) 3.2.2 Heat Flux Hot Channel Factor (e) 3.2.3 Nuclear Enthalpy Rise Hot Channel Factor The proposed changes are consistent with the requirements of 10 CFR 50.36 and p the utaff's proposed policy for improving Technical Specifications, delineated in SECY-86-10, " Recommendations for Improving TS". The policy allows process variables such as core operational limits to be controlled by specifying them numerically in the Technical Specifications, or by specifying the method of calculating their numerical values if the staff finds that the correct limits ! will be followed in operation of the plant. The proposed revision references the NRC-approved methodologies. The proposed changes to the Technical Specifications are also considered to be improvements, and are consistent with the NRC stated policy for improving Technical Specifications (52 FR 3788, February, 1987).
- Safety EvaluatiQD f
The current Technical Specification method of controlling the above reactor physics parameters to assure conformance to 10 CFR 50.36 (which requires the lowest functtens1 levels acceptable for continued safe operation) is to specify the values determined to be within the acceptance criteria using an NRC-approved calculation methodology. As previously discussed, the methodologies for calculating these parameters have been approved by the NRC, and are consistent with the applicable limits in the Final Safety Analysis (. Report (FSAR). 1 I The removal of cycle-dependent variables from the Technical Specifications has i no impact upon plant operation or safety. No safety related equipment, safety I function, or plant operations will be altered as a result of this proposed change. Since applicable FSAR limits will be maintained, and the Technical Specifications will continue to require operation within the core operating limits calculated by the approved methodologies, this proposed change is administrative in nature, and does not affect the purpose of the Technical Specification involved. Appropriate actions to be taken if the limits are violated will remain in tha Technical Specifications. l This proposed change will control the cycle-specific parameters within the acceptance criteria and assure conformance to 10 CFR 50.36 by using the approved methodology instead of specifying Technical Specification values. A1/026.N18
ATTAClM5T A ST-HL AE 3 756 PAGE 3 _0F _ W The COLR will document the specific parameter limits resulting from NRC approved calculations, including mid cycle or other revisions to parameter values. Therefore, the proposed change is in conformance with the requirements of 10 CFR 50.36. Any changes to the COLR will be made in accordance with the requirements of 10 CFR 50.59, with a copy of the revised COLR sent to the NRC as required in Section 6,9.1.6 of the Technical Specifications. From cycle to cycle, the COLR will be revised such that the appropriate core operating limits for the applicable unit and cycle will apply. The Technical Specifications will not be changed. Determination of Significant Hazards Pursuant to 10 CFR 50.91, Houston Lighting 6 Power has determined that operation of the facility in accordance with the proposed license amendment request does not involve any significant hazards considerations as defined by NRC regulations in 10 CFR 50.92. The following discussion describes how the proposed amendment satisfies each of the three requiremente of 10 CFR 50,92(e).
- 1) The proposed change does not involve a significant increase in the probability or consequence of an accident previously evaluated.
The removal of cycle-specific core operating limits from the South Texas Proj ec t Technical Specifications has no influence or impact on the probability or consequences of any accident previously evaluated. The core operation limits, although not in the Technical Specifications, will be followed in the operation of the South Texas Project Electric Generating Station. The proposed amendment requires exactly the same actions to be taken if a core operating limit is exceeded that the current Technical Specificatione do. The cycle-specific limits in the COLR will continue to be controlled by the South Texas Project programs and procedures. Each accident cnalysis addressed in the South Texas Project FSAR will be examined with respect to changes in the cycle-dependent parameters, which are obtained from the use of NRC approved reload design methodologies, to ensure that the transient evaluation of new reloads are bounded by previously accepted analyses. This examination, which will be conducted per the requirements of 10 CFR 50.59, will ensure that future reloads will not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2) The proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
As stated earlier, the removal of the cycle specific variables has no influence or impact, nor does it contribute in any way to the probability or consequences of an accident. No safety-related equipment, safety function, or plant operation will be altered as a result of this proposed A1/026.N18
m snmen t .2 ST HL AE 37676 , PAGE 4 0F ~41 change. The cycle specific variables are calculated using the NRC approved methode, and submitted to the NRC to allow the staff to continue to trend the values of these limits. The Technical Specifications will continue to require operation within the core operating limits, and appropriate actions will be required if these limits are exceeded. Therefore, the proposed amendment does not in any way create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3) The proposed amendment does not result in a significant reduction in the margin of safety.
The margin of safety is not affected by the removal of cycle specific core operating limits from the Technical Specifications. The margin of safety presently provided by current Technical Specifications remains unchanged. Appropriate measures exist to control the values of these cycle specific limits. The proposed amendment continues to require operation within the core limits as obtained from the NRC approued reload dc11gn methodologies, and the actions to be taken if a limit is exceeded remains unchanged. The development of the limits for future reloads will continue to conform to those methods described in NRC-approved documentation. In addition, each future reload will involve a 10 CFR 50.59 safety review to assure that operation of the unit within the cycle specific limits will not involve a significant reduction in the margin of safety. Therefore, the proposed changes are administrative in nature, and do not impact the operation of the South Texas Project in a manner that involves a reduction in the margin of safety. Conclusion The Commission has provided guidance concerning the application of the standards for determining whether a significant hazards consideration exists. This guidance (51 FR 7750) includes examples of the type of amendments that are considered not likely to involve significant hazards considerations. The change proposed is similar to the examples of administrative changes in 51 FR 7750. Additionally, the proposed change is consistent with the NRC policy for improving Technical Specifications (52 FR 3788), and the proposed change is consistent with 10 CFR 50.36 and 10 CFR 50.59. In view of the preceding, the Houston Lighting & Power Company has determined that the proposed license amendment for the South Texas Project does not involve any significant hazards considerations. l A1/026.N18
0 4 Attachment 3 Marked-Up Technical Specification Pages A1/026.N18
~
ATTACHMENT 3 ~ JNDEX ST.HL. PAGE _J AE 0F
,3 _.
7W ')f__ LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION
'PAGE 3/4.0 APPLICABILITY................................................ 3/4 0-1
_3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL Shutdown Margin - T avg Greater Than 200*F................. 3/4 1-1 FIGURE 3.1-1 REQUIRED SHUTDOWN MARGIN VERSUS RCS CRITICAL BORON CONCENTRATION (MODES 1, 2, 3, AND 4)...................... 3/4 1-3 Shutdown Ma.rgin - T gg less Than or' Equal to 200'F. . . . . . . . 3/4 1-4 FIGURE 3.1-2 REQUIRED SHUTOOWN MARGIN VERSUS RCS CRITICAL BORON CONCENTRATION (MODE 5).................................... 3/4 1-5 f'lGOG 3.l-A Moderator Temperature 60L Meh+ur Tew.6t. C#4 Coefficient......................... ve ru be 3/4 1-6 l MinimumTemperatureforCrdq.a1cality....................... 3/4 l-hi 3/4 1-8 3/4.1.2 BORATION SYSTEMS Flow Paths - Shutdown.......... .......................... 3/4 1-9 Flow Paths - Operating.................................... 3/4 1-10 ( Charging Pumps - Shutdown................................. 3/4 1-11 Charging Pumps - Operating................................ 3/4 1-12 Borated Water Sources - Shutdown.......................... 3/4 1-13 Borated Water Sources - Operating......................... 3/4 1-14 3/4.1.3 MOVABLE CONTROL ASSEMBLIES Group Height.............................................. 3/4 1-16 { TABLE 3.1-1 ACCIDENT ANALYSES REQUIRING REEVALUATION IN THE EVENT OF AN INOPERABLE FULL-LENGTH R00. . . . . . . . . . . . . . . . . . . . 3/4 1-18 Position Indication Systems - Operating................... 3/4 1-19 Pos i tion I ndica tion Sys tems - Shutdown. . . . . . . . . . . . . . . . . . . . 3/4 1-20 Rod Drop Time............................................. 3/4 1-21 Shutdown Rod Insertion Limit.............................. 3/4 1-22 } Control Rod Inse rtion Limits. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 1-23 FIGURE 3.1-3 (Deleted) l SOUTH TEXAS - UNITS 1 & 2 iv Unit 1 - Amendment No. 9 Unit 2 - Amendment No.1
. ATTACHMENT 3
. ST HL AE 3'/Sfa PAGE 3 0F N INDEX LIMITING CONDil10NS FOR OPERATION AND SURVE]LLANCE REQUIREMENTS SECTION PAGE 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AX1AL FLUX OlFFERENCE.... ...... ......................... 3/4 2-1l - FIGURE 3.2-1 AX1 AL FLUX OlFFERENCE LIMITS AS A FUNCTION Of g\ded RATED THERMAL POWER.......... .. .. .................... s/424l 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR - F (Z)..................... /4 -5 l 9 FIGURE 3.2-2 K(Z) - NORMALIZED F (Z) q AS A FUNCTION OF CORE HEIGHT. 3, , c Gl 3/4.2.3 NUC LE AR ENTHALPY RISE HOT CHANNE L F AC10R. . . . . . . . . . . . . . . . . 3/42-9l 3/4.2.4 QUADRANT POWER TILT RATIO. . . . . ....... .. . ......... 3/4 2-10 3/4.2.5 DNB PARAMETERS. . . . . . . . .. 3/4 2-11 3/4.3 1N51RUMENTAT10N 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION. ... .. ... .. .. . 3/4 3-1 TABLE 3.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION. . .. . 3/4 3-2 TABLE 3.3-2 REACTOR TRIP SYSTEM INSTRUMENTAT10N RESPONSE TIMES. . 3/4 3-9 ( TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS. . . ... . . 3/4 3-11 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTAT10N. . ..... .... .... 3/4 3-16 TABLE 3.3-3 ENGINEERED SAFETY FEATURES ACTUAT10N SYSTEM INSTRUMENTATION... . . . .. . . . . . 3/4 3-18 TABLE 3.3-4 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENT ATION TRIP SEIP0lNTS. .. 3/4 3-29 TABLE 3.3-5 ENGINEERED SAFETY FEATURES RESPONSE TIMES. . . . 3/4 3-37 TABLE 4.3-2 ENGINELRED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTAT10N SURVElLLANCE REQUIREMENTS. . . . ..... .. . 3/4 3-42 3/4.3.3 MONITORING INSTRUMENTAT10N Radiation Monitoring for Plant Operations. ... ... . . 3/4 3-50 TABLE 3.3-6 RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS.......... ...... ..... ... . .. .. 3/4 3-51 TABLE 4.3-3 RADI ATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS SURVEILLANCE REQUIREMENTS.... .... . . 3/4 3-53 Movable incore Detectors.. ... . . . . 3/4 3-54 Seismic Instrumentation. .. . . ... . . . .... 3/4 3-55 TABLE 3.3-7 SEISMIC MONITORING INSTRUMENTATION. . . 3/4 3-56 SOUTH TEXA5 - UNITS 1 & 2 v
ATTACHMENT 3 INDEX ST.HL-AE 3?wr6 PAGE 2 0F 2V ADMINISTRATIVE CONTROLS
'CTION PAGE 6.5.2 NUCLEAR SAFETY REVIEW BOARD (NSRB) function................................................... 6-9 I
Composition................................................ 6-10 Alternates................................................. 6-10 Consultants................................................ 6-10 Heeting frequency.......................................... 6-10 Quorum..................................................... 6-10 Review..................................................... 6-10 Audits..................................................... 6 11 Records.................................................... 6 12 6.5.3 TECHNICAL REVIEW AND CONTROL Activities ..............................................., 6 6. 6 REPORTABLE EVENT ACTI0N..............r....................... 6-13 t ( *7 SAFETY LIMIT V10LAT10N....................................... 6-13 l l 6.8 PROCEDURES AND PR0 GRAMS...................................... 6-14 6.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE REP 0RTS............................................ 6-16 Startup Report............................................. 6 16 AnnualReports............................................. 6-17 ! Annual Radiological Environmental Operating Report. . . . . . . . . 6-17 Semiannual Radioactive Effluent Release Report............. 6-18 Monthly Ope ra ti ng Report s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-20 Core Ope ra ti ng Limi ts Report. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-20 \ l 6.9.2 SPECIAL REP 0RTS............................................ 6-20a { 6.10 RECORD RETENT10N............................................ 6-21 SOUTH TEXAS - UNITS 1 & 2 xix Unit 1 - Amendment No. 9 Unit 2 - Amendment No. I l
9
. i
- m.ar e ATTACHMENT 1 REACTIVITY CONTROL SYSTEMS gHf g__
[ MODERATOR TEMPERATURE COEfflCIENT LLM111NG_COMLT10M0LOMRAll@ 3.1.1. 3 The moderator temperature coef ficient (MIC) shall bei wi% % lid specpA i Apos4 Less 60phgh_ Mve t tia B '+(.cet&. 0 3t/f/ r er the all E red, mi- ,pc tim,+ non bt las A oc ep
,thdrawn, beginningfo O s6 ofnycie life (SOL), but zero TiiERMAT TOWERTUndition; and a p; 3,) g
- b. Lc ss .iegui,i ve then -W 10 4 okA / r rer the !, rods vi+hdr-awn, and of cycle li fe (10i), isAft0 iiiEiJiAL POWERMt. ion.
APPLICABILITY: Bgim;)c 5,,cif. a t i on 3.1.1.-3a..e4 Lk (got)
- MODES 1 andIWA 2* only**.
Spec i fication 3.1.1. 3b. - MODES 1, 2, and 3 only"*. ga .4 Lk ( EcQ );r;.} a. got., 5PM ck in &. CoLR3 With the MTC more positive than the Alimit of Specification 3.1.IJa. a% operation in MODES 1 and 2 may proceed provided: 1. Control rod withdrawal limits are established and maintained % BcL suf ficient to restore the MTC to less positive than 0 Ak/i/"F (;,;4 spda',J within 24 hours or be in HOT STANDBY within the next 6 hours. These withdrawal limits shall be in addition to the insertion gn g g,q limits of Specification 3.1.3.6;
- 2. The control rods are maintained within the withdrawal limits established above until a subsequent calculation verifies that the MTC has been restored to within its limit for the all rods withdrawn condition; and
- 3. A Special Report is prepared and submitted to the Commission, pursuant to Specification 6.9.2, within 10 days, describing the value of the measured MIC, the interim control rod withdrawal limits, and the predicted average core burnup necessary for restoring the positive MTC to within its limit for the all rods withdrawn condition.
b. EOL- sg6kb .. & COL 2 3 With the MTC more negative than thealimit of Specification 3.1.1.3b.
-etmve) be in HOT SHUTDOWN within 12 hours.
l l t i i l l
*With Kef f greater than or equal to 1. , **See Special Test Exceptions Specification 3.10.3.
SOUTH TEXAS - UNITS 1 & 2 3/4 1-6 l
ATTACHMENT 3 P.EACTIVITY C0t4 TROL SYSTEMS ST HL AE 375 6 PAGE 6 0F M (. S@VElLLAflCE REQUlMMENTS _. _ _ 4.1.1.3 The MTC shall be determined to be within its limits during each fuel cycle as follows: 5 ped hd b 41 col 2.
- a. The MlC shall be measured and compared to the BOL limit of-specifM cation 3.1.2.3c. , abovg prior to initial operation above 5% of '
RATED Tl!ERMAL POWER, af ter each fuel loading; and
- b. The MTC shall be measured at any THERMAL POWER and compared to -3.1 x-10" ak/k/^f (all rods withdrawn, RATED THERMAL POWER condition) within 7 EFPD af ter reaching an equilibrium boron concentration of 300 ppm. In the event this comparison indicates the MTC is more negative than -3.1 x 10 ' tAA#f, the HTC shall be remeasured, and compared t tw EOL MTC limit of Specimet' ' ' ' % , at least once per 4 EFP0 during the remainder the fuel cycle, s m sa -
k C-OL2.
-A Seo pfm * *' M bmA '.yptcNed. h 04 (CLR
(. 1 l l SOUTH TEXAS - UNITS 1 & 2 3/4 1-7 l
i. 0.7 l l 0.6 1 0.5 5 0.4 5 _n .. u is 0.3 oC
\7 {. C'
++ ,
g 0.2 g (1)
"x m 0.1 -
o 9o U NACCEPTABLE OPERATION , r- " a 2 0.0 a_ l
- 0.1 ACCEPTABLE OPERATION $
-0.2 hk
"'W M oik5
-0.3 b 0 20 40 60 80 100 %y$gW
% of RATED THERMAL POWER L t
I L=mL=-- -
.ri-.h.,
l ' l L QEC . MENT 3 RE AC11V11Y CON 1ROL SY51[H5 M HL AE 3?S% 3/4.1.3 HOVABlE CONTROL A",5[MPLlE5 -- PAGE 7 0F 1 GROUP HEIGHT Llfilj ngl 0NP1110R rourtRAT]py ..
..__.= _ _,_ ._ _ 7 _ _
3.1.3.1 All full-length shutdown and control rods shall be OPERABLE and - positioned within i 12 staps (indicated position) of their group step counter ucmand 00sition. APPLICABllliY: MODES l' and 2". AC1'qN:
- a. Wit h one or rnore f ull-length roc efable due to being immovable as a result of excessive f riction .:.nanical interference or known to be untrippable, determina that the SHUlDOWN MARGIN require-rent of Specification 3.1.1.1 is satisfied within I hour and be in HOI STANDBY within 6 hours,
- b. With one full-length rod trip.'able but inoperable due to causes other than addressed by ACi10N ., above, or misaligned from itt group step counter demana height by more than i 12 steps (indicated position), POW [R OPERAT10h may rontinue provided that within I hour.
- 1. The rod is restored to OPERABLE status within the above alignment requirements, or
- 2. The rod is declared inoperable and the remainder of the rods in the group with the inoperable rod a'e aligned to within i 12 steps of the inoperable rod while maintaining the rod sequence 05 sEc6ed a nd i ns e r t i on l imi t sof449 me-3-1-3. The THERMAL POWER level
** ~~~
shall be restricted pursuant to Specification 3.1.3.6 during Cpr u ti L: 4 5 subsequent operation, or 0 -
- 3. The md is declared inoperable and the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied. POWER OPERATION may then continue prcvided that; a) t reevaluation of .ach accident analysis of Table 3.1-1 le performed within a days; this reevaluation shall confirrt that the previously analyzed results of these accidents remain valid for the duration of operation under these conditions; b) 1he SHUIDCWN MARG'N requirement of Specification 3.1.1.1 is determined at least once per 12 hours;
'See Special Test Exceptions Specifications 3.10.2 and 3.10.3.
50VIH TEXA5 - UN115 1 & 2 3/4 1-16
ATTACHMENT 3 REAC11VITY C0fdROL SYSTEns ST HL AE37G J 0F M PAGE __2 i i G. O!.0 0_ _0. PIE 10.L _ _ . _ __ ACTlvN (Continued) c) A power distribution map is obtained f rom the inovable incore detectoir, and 9F (Z) and Fh are verified to be within their limits within 72 hours; and d) The THERMAL POWER level is reduced to less than or equal to 75% of RATED THERHAL POWER within the next hour and within the following 4 hours the High Neutron Flux Trip Setpoint is reduced to less than or equal to 85% of RATED THERMAL. POWER.
- c. With more than one rod trippable but inoperable due to causes other than addressed by ACTION a. above, POWER OPERATION may continue provided that:
- 1. Within 1 hour, the remainder of the rods in the bant(s) with the inoperable rods are aligned to within i 12 sicps of the inoperable rods while maintaining the rod sequence and insertion
" M"b 3.1-3. The THERMAL POWER level shall be A N C04 ~ limit %cf rigv v restricted pursuant to Specification 3.1.3.6 during subsequent operation, and
(
- 2. The inoperable rods are restored to OPERABLE status within 72 hours,
- d. With more than one rod misaligned from its group step counter demand height by more than i 12 steps (indicated position), be in HOT STANDBY within 6 hours.
}URVE LLLANCERQU]REMENIL__ _
4.1.3.1.1 The position of each full-length rod shall be determined to be within the group demand limit by verifying the individual rod positions at least once per 12 hours except during time intervals when the rod pnsition devi9 tion monitor is inoperable, then verify the group positions at least once per 4 hours. 4.1.3.1.2 Each full-length rod not fully inserted in the core shall be determined to be OPERABLE by movement of at least 10 steps in any one direction at least once per 31 days. l it. SOUTH TEXA5 - UN1151 & 2 3/4 1-17 . l
i4 . .n.4,5 ( 3 RlACTIVllY CON 1ROL SYS1[M5 bl ML AE 375% PAGE 9 0F W
./ SHUTOOWN ROD IN$tRT10N tlMli U Mj T INidO1D il] QN 10L0f( Rid} QfL___ _ , _ , _ , _ . _ _ , _
3.1. 3. 5 All shutdown rods shall be fully withdrawn b5 fg(sej in S 6 O'g, L;m,n f ADPt ICABillTY: MODES 1* and 2* **. k P/t (COLR). . ACTION: With a maximum of one shutdown rod not fully withdrawn, except for surveillance testing pursuant to Specification 4.1.3.1.2, within I hour either:
- a. f ully withdraw the rod, or
- b. Declare the rod to be inoperable and apply specification 3.1.3.1.
SUSVil E LM4CE _ PEiQlllREPENTS _ ._ ==== .__. _._._._ ,_. _ _ _ _ , 4.1.3.5 Each shutdown rod shall be determined to be f ully withdrawn:
- a. Withir. 15 minutes prior to withdrawal of sny rods in Contr4 Bank A, B, C, or D during an approach to reactor criticali .v, and
- b. At least once per 12 hours thereafter.
(
*See Special Test Exceptions Specifications 3.10.2 and 3.10.3.
( **With K ,7f greater than or equal to 1. SOUTH TEXA5 - UNITS 1 & 2 3/4 1-22
t ~ munmtm s
*
- ST.HL AE.97n,
- PAGE_/o 0F W 3/4.2 POWER Dl51RIBU110N llH115 ISI -Ob02
'3/4.2.1 AX1Al ftUX OlffERENCE LIE 1111LRMl_JA1.LOLOMAUOL__.
3.2.1 The indicated AX1AL' FLUX D!ffERENCE (AfD) shall be maintained within the target band (flux dif ference units) about the target flux dif ference as specified in the CORE OPERATING LIMITS REPORT,(cot.R), The indicated AfD may deviate outside the above required target band at greater . than or equal to 50% but less than 90% of RATED THERMAL POWER provided the indi-cated AfD is within the Acceptable Operation Limits of-4 VUN'd 9 ere-4rMand the cumu- i, 4tc lative penalty deviation time does not exceed I hour during the previous 24 hours. cogg The indicated AfD may deviate outside the above required target band at greater than 15% but less than 50% of RATED THERML POWER provided the cumulative penalty deviation time does not exceed I hour during the previous 24 hours. APPL!CABILITY: MODE 1, above 15% of RATED THERMAL POWER.* ACTION'
- a. With the indicated AfD outside of the: h required target band and with THERMAL POWER greater than or equal to 90% of RATED THERMAL POWER, within 15 minutes eithec::
- 1. Restore the indicated AFD to within the target band limits, or j
( /
- 2. Reduce THERHAL POWER to less than 90% of RATED THERMAL POWER.
- b. With the indicated AfD outside of the above required target band for more than I hour of cumulative penalty deviation time during the 3par d - previous 24 hours or outside the Acceptable Operation Limits +f k & Ccd . M9m-4-iH and with THERMAL POWER less than 90% but equal to or greater than 50% of RATED THERMAL POWER, reduce:
- 1. THERMAt POVER to less than 50% of RATED THERHAL POWER within 30 minutes, and
- 2. The Power Range Neutron flux * " - High Setpoint to less than or equal to 55% of RATED THERMAL POWER within the next 4 hours.
'See Special Test Exceptions Specification 3.10.2.
** Surveillance testing of the Power Range Neutron flux Channel may be performed pursuant to Specification 4.3.1.1 provided the indicated AfD is maintained within the Acceptable Operation Limits of449 ere-t2-1. A total of 16 hours operation may be accumulated with the AfD outside/of the above required target band during testing without penalty deviation. /
$ju2O h &
COLR SOUTH TEXA5 - UNITS 1 & 2 3/4 2-1 Unit 1 - Amendment No. 9 Unit 2 - Amendment No.1
ATTACHMENT 3 POWER 0151RIBui!0N LIMITS ST HL AE 375% PAGE il 0F M i yMJ TI!MJ0!!DWOU0101E!MT10F _ ACT10N (Continued)
- c. With the indicated AfD outside of the 4ede-required target band for k
. more than I hour of cumulative penalty deviation time during the previous 24 hours and with THERMAL POWER less than 50% but greater -
than 15% of RATED THERMAL POWER, the THERML POWER shall not be increased equal to or greater than 50% of RATED THERMAL POWER until the indicated AfD is within the shree required target band. I h M M LL MCl)1QM3f E1TS _ _ _ _ _ _ 4.2.1.1 1he indicated AfD shall be determined to be within its limits during POWER OPERATION above 15'4 of RATED THERMAL POWER by:
- a. Monitoring the indicated AfD for each OPERABLE excore channel:
- 1) At least once per 7 days when the AfD Monitor Alarm is OPERABLE, and
- 2) At least once per hour for the first 24 hours after restoring the AfD Monitor Alarm to OPERABLE status,
- b. Monitoring and logging the indicated AFD for each OPERABLE excore channel at least once per hour for the first 24 hours and at least
( once per 30 minutes thereaf ter, when the AfD Monitor Alarm is inoperable. The logged values of the indicated AfD shall be assumed to exist during the interval preceding each logging. I l 4.2.1.2 The indicated AfD shall be considered outside of its target band when two or more OPERABLE excore channels are indicating the AfD to be outside the target band. Penalty deviation outside of the above required target band shall be accumulated on a time basis of: l
- a. One minute penalty deviation for each 1 minute of POWER OPERATION outside of the target band at THERMAL POWER levels equal to or above 50% of RATED THERMAL POWER, and l b. One-half minute penalty deviation for each 1 minute of POWER OPERATION l outside of the target band at THERMAL POWER levels between 15% and 50% of RATED THERMAL POWER.
4.2.1.3 Th. .srget flux difference of each OPERABLE excore channel shall be l determined by measurement at least once per 92 Effective full Power Days, The provisions of Specification 4.0.4 are not applicchie. 4.2.1.4 The target flux dif ference shall be updated at least once per 31 Ef fective full Power Days by either determining the target flux dif ference ( SOUTH TEXA5 - UNITS 1 & 2 3/4 2-2 .
)
"Ah ACHMENT 3 ,
ST HL AE 375*6 i PAGE M - 0F a4 -- 1 Deickd
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IS O I I / ' 407 #0 10 O 10 20 \ O 40-50 FLUX DIFFERENCE (AI) FIGURE 3.2-1 IX] At FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER l SOUTH TEXA5 - UN]~51 & 2 3/4 2-4 Unit 1 - Amendment No. 4
g ATTACH!iENT 3 P0wfR DISTRIBUTION LIMll5 ST HL AE 3754 PAGE J3___0F 2!/___. g 3/4.2.2 HEAT flux HOT CHANNIL F ACIO -gf Q} j ljill]![G J OND LT ] 0!L f.0 R .0 P E R A110 N - - . . _ _ . , . , _ _ _ . _ . . _ _ _ _ _ m._ 3.2.2 f (Z) shall be limited by the following relationships: Q psiv ~ f g(Z) < 2. 50 [Kd f or P > 0. 5 0 - T - V y g(g).- s - RW gie f Q(Z) < 54-{4iH43 for P < 0. 5
~ ~
-\ %
1V{&) (a # N I* [q THERMAL POWER Wh*,/ P _~ RATWTEREAL POWER, and G4 R ATE D TH ERM 4L w,mA t ed eF ( N us a Q hos J bER (RTP) 5Fcihed K(Z) = the hmet4wsetametHrom-Mgure-h?-e-fw-4.-9 iwa core height beathm y N (x CWhg LARS P4pd (ce). N 3gcirn1d A & <_ 2' APPLICABillTY: MODE 1. ACil0N: With f q(2) exceeding its limit:
- a. Reduce THERMAL POWLR at least 1% f or each 1% qf (Z) exceeds the limit within 15 r:inutes and similarly reduce the Power
( Range Neutron flux Hicn Trip Setpoint within the next 4 hours; POWER OPERATION may proceed for up to a total of 72 hours; subsequent POWER OPERATION may proceed provided the Overpower AT Trip 5etpoint has been reduced at least 1% for each 1% Fg (Z) exceeds the limit.
- b. Identify and correct the cause of the out of-limit condition prior to increasing THERMAL POWER above the reduced limit re-quired by ACTION a. , above; THERMAL POWER may then be increased provided f q(Z) is demonstrated through incore mapping to be within its limit.
1 l SOUTH TEXA5 - UNITS 1 & 2 3/42-5 l 1
1 % ATTACHMENT 3 ST HL AE 375% PAGE _J.v___0F _dly_ l ggj ' - - 1.2 .
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cv . u, 1 / \i O 2 4 6 8 12 14 16 CORE HEIGHT (PT) = l l l, f1GURE 3.2-2 5(Z) - NORMAllZED F (Z) q AS A FUNCTION OF CORE HEIGHT SOUTH TEXAS UNITS 1 & 2 3/4 2-6 1
l d[8ChiiENT 3 POWER D15iRIBUT10N t1M115 ST HL AE 3764-
. PAGE .35_.__0F M WRYEILLMiCElEqVIRffiff3T5 . . .
4.2.2.1 The provisions of Specification 4.0.4 are not applicabic. 4.2.2.2 f xy shall be evaluated to determine if f (k) is within its limit by: q
- a. Using the movable incore detectors to obtain a power distribution map at any THERMAL POWER greater than 5% of RATED THERMAL POWER,
- b. Increasing the measured f xy component of the power distribution map by 3% to account for manufacturing tolerances and further increasing the value by 5% to account for measurement uncertainties,
- c. Comparing the f computed (f ) obtained in Specification 4.2.2.2b. ,
yy above to:
- 1) The f limits for RATED THERMAL POWER (fR P) for the appropriate x
measured core planes iO ven in Specification 4.2.2.2e. and f. , below, and
- 2) The relationship:
f-- Fy f xyL =f xy R7p (14-e(1-P)), ( Where f L is the limit for fractional THERMAL POWER operation l- express?dasafunctionofF RTP and P is the fraction of RATED THERMAL POWER at which f xy w measured.'f or WV F UN F P 4 :gQ k 4. Cot),
- d. Remeasuring F according to the following schedule:
- 1) When f is greater than the f R x
limit for the appropriate measured core plane but less than the f relationship, additional power distribution maps shall be taken df compared to f RTP x x and f x either: a) Within 24 hours af ter exceeding by 20% of RATED THERMAL C y,3 j,3g POWER or greater, the THERMAL POWER at which F*Y j determined, or b) At least once per 31 Ef fective full Power Days (EfPD), whichever occurs first. k 50VIH TEXA5 - UNITS 1 & 2 3/4 2-7
ATTACHMENT 3 ST HL AE 3756
, P0h'ER 015TRIBul:0N L1H1T5 PAGE 1L OF - 2 Y
( HEU1LELMMBEMRLffenthed _
- 2) When the F is less than or equal to the f,RTP limit for t b appropriate measured core plane, additional power distribution maps shall be take'n and f compared to f P and f at least -
x x x once per 31 EfPD.
- e. The F limits used in the Constant Axial Offset Control analysis
*Y for RATED THERMAL POWER (FRTP) shall be provided for all core planes as sect.if ei A in containing Bank "0" contro rodt, and all_unrodded core planes h
& Cot.t > hdia' Mm Fadv Unit hport per Specification 6.9.1.6;
- f. The F . limits of Specification 4.2.2.2e. , above, are not applicable in the following core planes regions as measured in percent of core height f rom the bottom of the fuel:
- 1) tower core region from 0 to 15%, inclusive,
- 2) Opper core region frem 85 to 100%, inclusive, Gric plane regions at 22.412%,34.212%,46.0
( _ 3) 69.512% and 81.3 ! 2%, inclusive, and 2%, 57.8 1 2%,
- 4) Core plane regions within i 2% of core height (1 3.36 inches) 600c; the bank demand position of the Bank "D" control rods.
9 With f ,C exceeding f , the effects of f on fg(Z) shall be yy evaluated to determine if9F (2) is within its limits. 4.2.2.3 When F (Z) is measured for other than f detenninations, an overall n xy measured F (2) shall be obtained from a power distribution map and increased 9 by 3% to account for manufacturing tolerances and further increased by 5% to account for measurement uncertainty.
- k l
SOUTH TEXA5 - UNITS 1 & 2 3/4 2-8
~
ATTACHMENT 3 POWER OlSTRIBUTION tlM115 ST.HL AE 3764
. PAGE_.D _0F _ Lq i 3/4.2.3 NL' CLEAR ENTHALPY R15E H01 CHANNEL _f_ ACTOR L 1 Ml MGJ0!!? lll.9LLOLO1Epil OL_____ _ _ _ _ _
3.2.3 i g shall be less than +.g[1.0 + -04 (1-P)) Ce pea - THERMAL POWER ere: P = RATTIFTi[RMAL POWER FrP
- F.a = & F*"* 6+ a RATeo vnawt ibecc mre) spo%J APPLICABILITY: MODE 1.
t^ N b O a<ab ACTION: y on f 3 lids 8 rt-F (CoLR) y N te Ic.c.tv Mulhelier (v F,g p, y c, & With F 6H exceeding its limit: g
- a. Within 2 hours reduce the THERMAL POWER to the level where the LIMlllNG COND1110t' FOR OPERATION is satisfied.
- b. Identify and correct the cause of the out-of-limit condition prior to increasing 1HERMAL POWER above the limit required by ACTION a.,
N above; THERMAL POWER may then be increased, provided F is demon-strated through incore mapping to be within its limit. g [MVElLLANCE PEQQJ1EMENTS m _ m., .._m____m.m_____ 4.2.3.1 The provisions of Specification 4.0.4 are not opplicable. 4.2.3.2 F q shall bc demonstrated to be within its limit prior to operation above 75% RATED THERMAL POWER af ter each fuel loading and at least once per 31 EfPD thereafter by:
- a. Using the movable incore detectors to obtain a power distribution map at any THERMAL POWER greater than 5% RATED THERMAL POWER.
- b. Using the measured value of f"g which does not include an allowance for measurement uncertainty.
50VIH TEXAS - UNITS 1 & 2 3/4 2-9
m %nMtNi J ST Hl. AE 3754 60MINIMAlIXEl0ER01.5. _ _ _ _ . -. sachjg.,_g;, ,3 5,EMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPOR1 (Cuntinued) (' The Semiannual Radioactive Ef fluent Release Reports shall also include the folloving: an explanation as to why the inoperability of liquid or gaseous ef fluent monitoring instrumentation was not corrected within the time specified - in Specification 3.3.3.10 or 3.3.3.11, respectively; and description of the l events leading to liquid holdup tanks or gas storage tanks exceeding the i limits of Specification 3.11.1.4 or 3.11.2.6, respectively. ' MONTHLY OPERATING REPORTS
- 6. 9. 3. 5 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORVs or safety valves, shall be submitted on a monthly basis to the Director, Of fice of Resource Management, ll.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a copy to the Regional Administrator of the Regional Office of the NRC, no.later than the 15th of each month following the calendar month covered by the report.
CORE OPERATING LIMITS REPORT 9 6.9.1.6 Core operating limits shall be established and documented in the OPERATING LIMITS REPORT before each reload cycle or any remaining a p;a 14f'CORf reload cycle. The CORE OPERATING LlHITS REPORT shall be main,tained available in the Control Room. The analytical methods used to det operating limits shall be those previously reviewedand'uaifie approved thebycore NRC in WCAP 8403, " Power Distribution and Load FoT1 vWfProcedures," 1974 and in WCAP-9273-A, " Westinghouse Reload Safety uation Methodology," 1985 (for #y @d}g Control Bank Insertion Limits). ,TWrore operating limits shall be determined # gl ( so that all applicable limits 41.g. , fuel thermal-mechanical limits, core hermal-hydraulic limitsrECCS limits, nuclear limits such as shutdown margin, and transient and actTdent analysis limits) of the safety analysis are met. The CORE OPJRATThG LIMITS REPORT, including any mid-cycle revisions or supplement's thereto, shall be provided within 30 days of their implementation,
,foriach reload cycle, to the NRC in accordance with 10 CFR 50.4.
SPECIAL REPORTS ) 6.9.2 Special reports shall be submitted to the Regional Administrator of the Regional Of fice of the NRC within the time period specified for each report.
)UTH TEXAS - UNITS 1 & 2 6-20 Unit 1 - Amendment No.9 f Unit 2 - Amendment No. I l
~ . - - - - - - .
LW4
- J ADMINISTRATIVE CONTROLS .
C_ ORE OPERATING LIMITS REPORT l PAGE 19 0F 19 6.9.1.6.a Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle, or any part of a reload cycle for the following:
- 1. Moderator Temperature Coefficient BOL and EOL limits, and 300 ppm surveillance limit for Specification 3/4.1.1.3,
- 2. Shutdown Bank Insertion Limit for Specification 3/4.1.3.5,
- 3. Control Bank Insertion LiLits for Specification 3/4.1.3.6,
- 4. Axial Flux Difference limits and target band ;sr Specification 3/4.2.1,
- 5. Heat Flux Hot Chaggg1 Factor, K(Z), Power Factor Multiplier, and F xy , for Specification 3/4.2.2, and
- 6. Nuclear Enthalpy Rise Hot Channel Factor, and Power Factor Multiplier for Specification 3/4.2.3 The COFs.1 OPERATING LIMITS REPORT shall be maintained availabic in the Control Room.
6.9.1.6.b The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in:
- 1. WCAP 9272-P-A, " WESTINGHOUSE RELOAD SAFETY EVALUATION-METHODOLOGY", July, 1985 (H Proprietary).
(Methodology for Specification 3.1.1.3 - Moderator Temperature Coefficient, 3.1.3.5 - Shutdown Rod Insertion Limit, 3.1.3.6 - Control Bank Insertion Limits, 3.2.1 - Axial Flux Difference, 3.2.2 - Heat Flux Hot Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor.)
- 2. WCAP 8385, " POWER DISTRIBUTION AND LOAD FOLLOWING PROCEDURES TOPICAL REPORT", September, 1974 (H l
Proprietary). (Methodology for Specification 3.2.1 - Axial Flux Difference l (Constant Axial Offset Control)) l l l I SOUTH TEXAS - UNITS 1&2 6-
'
- ATTACHMENT 3 .
ST HL AE 37S6 l PAGE 40 0F J'/ l
- 3. Westinghouse letter NS-TMA-2198, T. M. AnC4orson (Westinghouse) to K. Kniel (Chief of Core Performance Branch, NRC) January 31, 1980 - Attachmentt Operation and ;
Safety Analysis Aspects of an Improved Load Follow Package. > (Methodology for Specification 3.2.1 - Axial Flux Difference (Constant Axial Offset Control). Approved by NRC Supplement No. 4 to NUREG 0422 January, 1981 docket Nos. 50-369 and 50-370)
- 4. NUREG-n800, Standard Review Plan, U. S. Nuclear Regulatory Commit.uion, Section 4.3, Nuclear Design, July 1981. branch Technical Position CPB 4.3-1, Westinghouse Constant Axial Offset Control (CAOC) , Rev. 2, July 1981.
(Mothodology for Specification 3.2.1 - Axial Flux Dif ference (Constant Axial Offset Control).)
- 5. WCAP 9220-P-A, Rev.1, "WESTINGl!OUSE ECCS EVALUATION MODEL-1981 VERSION", February 1982 ()] Proprietary) .
(Methodology for Specification 3.2.2 - Heat Flux !!ot Channel Factor.)
- 6. WCAP 9561-P-A, ADD. 3, Rev.1, "BART A-1: A COMFUTER CODE FOR Tile BEST ESTIMATE ANALYSIS OF REFLOOD TRANSIENTS - SPECIAL REPORT: THIMBLE MODELING H ECCS EVALUATION MODEL", July, 1986, (H Proprietary).-
(Methodology for Specification 3.2.2 - Heat Flux flot Channel Factor.) 6.9.1.6.c The core operating limits shall be determined so that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met. 6.9.1.6.d The CORE OPERATING LIMITS REPORT, including any mid-E cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk, with copies to the Regional Administrator and Resident Inspector. l SOUTl! TEXAS - UNITS 1 & 2 6-
ATTAMMENT 3 s1.HL AE NS4 RE AC11V11Y CONTROL SYS1(MS PAGE ll 0F 2/- ( N 1 - u,===. - - m - m - m m m m _ _ - m - - - m m - m ,.. - MODERATOR 1EMPERATURE C0Ef flCIENT_ (Continued) The most negative MIC, value equivalent to the riost positive moderator density coef ficient (MDC), was obtained by incrementally correcting the HDC used in the f5AR analyses to nominal operating conditions. These corrections - involved subtracting the incremental change in the MDC associated with a core condition of all rods inserted (most positive MDC) to an all rods withdrawn , condition and, a conversion for the rate of change of rnoderator density with temperature at RATED _ THrRMAL POWER conditions. W"3 o This value of _the MDC _was _ then__,4 (og g _of-H~r10^tNk/*J. transiormed into represents the 1f6tIsiffi1C value 0 r10 '-6k/k/4.#ThQ1TC value cpq a conservative value (with corrections for burnup and soluble boron) at a core condition of 300 ppm equilibrium boron ypp concentration and is obtained by making these corrections to the limitin(QiiC NCd. va l ue, e f--4+riO-%knM . 60L j 3c0 y The Surveillance Requirements f or measurement of the MTC at the beginning sv ei wu and near the end of the fuel cycle are adequate to confirm that the MTC remains within its limits since this coef ficient changes slowly due principally to the reduction in RCS boron concentration associated with f uel burnup. 3/4.1.1.4 MINIMuli 1EMPERATURE f 0R CRillCAllTY g This specification ensures that the reactor will not be made critical ( with the Reactor Coolant System average temperature less than 561 f. This limitation is required to ensure: (1) the moderator temperature coefficient is within its analyzed temperature range, (2) the trip instrumentation is within its normal operating range, (3) the pressurizer is capable of being in an OPERABLE status with a steam bubble, and (4) the reactor vessel is above its minimum RT
- P"^ t "
ND1 3/4.1.2 BORAT10N SYSTEMS The Boron Injection System ensures that negative reactivity control is available during each rnode of f acility operation. The components required to perform this function include: (1) borated water sources, (2) charging pumps, (3) separate flow paths, (4) boric acid tran-fer pumps, and (5) an emergency power supply from OPERABLE diesel generators, With the RCS average temperature above 350 r, a minimum of two boron injection flow paths are required to ensure single functional capability in the event an assumed failure renders one of the flow paths inoperable. The boration capability of either flow path is suf ficient to provide a SHUIDOWN MARGIN f rom expected operating conditions of 3.75% ak/k af ter xenon decay and cooldown to 200 f. The maximum expected boration capability requirement occurs at EOL from full power equilibrium xenon conditions and requires i 27,000 gallons of 7000 ppm borated water f rom the boric acid storage system or 458,000 gallons of 2500 ppm borated water from the refueling water storage i tank (RWST). The RWST volume is an ECCS requirement and is more than adequate for the required boration capability. s SOUTH TEXA5 - UNITS 1 & 2 8 3/4 1-2
. . . - - -. .,- --- - _ . . -~-- -- - . -
ATTACHMENT 3 ST HL AE 37s*6 1 3/#.2 POWER D151R!Bul10N LlH115 j PAGE _21_. 0F ,W - fASE5 - - l The specifications of this section provide assurance of fuel integrity i during Condition 1 (Normal Operation) and II (Incidents of Moderate frequency) l events by: (1) maintaining the minimum DNBR in the core greater than or equal to 1.30 during normal operation andlin short-term transients, and (2) limiting . j the fission gas release, fuel pellet temperature, and cladding mechanical pro-perties to within assumed design criteria, in addition, limiting the peak linear power density during Condition I events provides assurance that the initial conditions assumed for the LOCA analyses are met and the ECCS accept-ance criteria limit of 2200'f is not exceeded. The definitions of certain hot channel and peaking factors as used in these specifications are as follows: ! f g(Z) Heat flux Hot Channel f actor, is defined as the maximum local heat flux on the surf ace of a fuel rod at core elevation Z divided by the average fuel rod heat flux, allowing for manuf acturing tolerances on fuel pellets and rods; F
'H Nuclear Enthalpy Rise Hot Channel f actor, is defined as the ratio of the integral of linear power along the rod with the highest integrated power to the average rod power; and Radial Peaking factor, is defined as the ratic of peak power density f,Y(2) to average power density in the horizontal plane at core elevation Z.
3/4.2.1 AX i '. ' FLUX OlffERENCE
% F. Wt The limits on AX]AL FLUX DIFFERENCE (AfD) assure that the f (2) upper i
bound envelope o *MO times the normalized axial peaking f actor is not exceed?d
+@ during either normal operation or in the event of xenon redistribution following gah% power changes.
Ms Weed 3.g Target flux dif ference is determined at equilibrium xenon conditions. The full-length rods may be positioned within the core in accordance with their respective insertion limits and shot.ld be inserted near their normal position for steady-state operation at high power levels. The value of the target flux dif ference obtained under these conditions divided by the fraction of RATED THERMAL POWER is the target flux dif ference at RATED THERHAL POWER for the associated core burnup conditions. Target flux dif ferences for other THERKAL POWER levels are obtained by multiplying the RATED THERMAL POWER value by the appropriate f ractional THERMAL POWER level. The periodic updating of the target flux difference value is necessary to reflect core burnup considerations.
/
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SOUTH TEXA5 - UN1151 & 2 8 3/4 2-1 I _ _ . _ ~ -
7tiACHMENT 3 POWER 015TRIBUT10N llH115 AGE '3 - ( L MSEE AX1AL FlVX OlFFERENCE (Continued) Although it is intended that the plant will be operated with the AFD within the target band required by Specification 3.2.1 about the target flux . difference, during rapid plant THERMAL POWER reductions, control rod motion will cause the AFD to deviate outside of the target band at reduced THERMAL POWER levels. This deviation will not af fect the xenon redistribution suffi-ciently to change the envelope of peaking factors which may be reached on a subsequent return to RATED THERMAL POWER (with the AFD within the target band) provided the time duration of the deviation is limited. Accordingly, a 1-hour penalty deviation limit cumulative during the previous 24 hours is provided for operation at THE0 MAL outside of the POWER levels target between 50% band butofwithin and 90% RATEDthe limits POWER. THERMAL of r!gure For3.0 *1 whileMf"' N ", THERMAL POWER levels between 15% and 50% of RATED THERMAL POWER, deviations of & COLR I the AfD outside of the target band are less significant. The penalty of 2 hours actual time reflects this reduced significance. l Provisions for monitoring the AFD on an automatic basis are derived from the plant process computer through the AfD Monitor Alarm. The computer deter-mines the 1-minute average of each of the OPERABLE excore detector outputs and provides an alarm message immediately if the AFD for two or more OPERABLE excore channels are outside the target band and the THERMAL POWER is greater C than 90% of RATED THERMAL POWER. During operation at THERMAL POWER levels between 50% and 90% and between 15% and 50% RATED THERMAL POWER, the computer outputs an alarm message when the penalty deviation accumulates beyond the limits of I hour and 2 hours, respectively. Figure B 3/4 2-1 shows a typical monthly target band. 3/4.2.2 and 3/4.2.3 HEAT FLUX HOT CHANNEL FACTOR and NUCLEAR ENTHALPY RISE R3T CHANhTL FAC10R The limits on heat flux bot channel factor and nuclear enthalpy rise hot channel factor ensure that: (1) the design limits on peak local power density and minimum DNBR are not exceeded and (2) in the event of a LOCA the peak fuel clad temperature will not exceed the 2200*F ECCS acceptance criteria limit. 1 Each of these is measurable but will normally only be determined periodically as specified in Specifications 4.2.2 and 4.2.3. This periodic surveillance is suf ficient to en:ure that the limits are maintained provided:
- a. Control rods in a single group move together with no individual rod insertion dif fering by more than 12 steps, indicated, from the group demand position;
- b. Control rod groups are sequenced with overlapping groups as described in Specification 3.1.3.6; lw l
i l SOUJH TEXA5 - UNITS 1 & 2 B 3/4 2-2 - I l
ATTACHMENO
, POWER 0151R1BU110N LIM 115 ST PAGE HL 114__AEOf 37S 4[---
i pay L __. _ HEAT FLUX HOT CHANNEL FACTOR and NUCLEAR ENTHALPY RISE HOT CHANNEL FAIT'OR (Continued) When an f g measurementistaken,anallowanceforbothexperimentall error _ and manufacturing tolerance must be made. An allowance of 5% is appropriate for a full-core map taken with the Incore Detector flux Mapping System, and a 3% allowance is appropriate for manufacturing tolerance. The Radial Peaking factor, fyy(Z), is measured periodically to provide assurance that the Hot Channel f actor,g f (Z), remains within its limit. The y c) g F,y limit for RATED THERMAL POWER (f ) as provided in the Sedia M eaking I4the-timi t Report per Speci fication 6.9.1.6 was determined f rom expected g gF power control manuevers over the f ull range of burnup conditions in the core. ( Cct R) 3/4.2,4 QUADRANT POWER T1LT RA110 The QUADRANI POWER llLT RATIO limit assures that the radial power distribu-tion satisfies the design values used in the power capability analysis. Radial power distribution measurements are made during STARIUP testing and periodically during power operation. The limit of 1.02, at which corrective action is required, provides DNB and linear hcat generation rate protection with x y plane power tilts. A limit of 1.02 was selected to provide an allowance for the uncertainty associated with the indicated power tilt. The 2-hour time allowance for operation with a tilt condition greater than 1.02 is provided to allow identification and correction of a dropped or misaligned control rod, in the event such action does not correct the tilt, the margin for uncertainty on f g is reinstated by reducing the maximum allowed power by 3% for each percent of tilt in excess of 1. For purposes of monitoring QUADRANT POWER TILT RATIO when one excore detector is inoperable, the moveable incore detectors are used to confirm that the normalized symmetric power distribution is consistent with the QUADRANT , POWER TILT RATIO. The incore detector monitoring is done with a full incore flux map or two sets of four symmetric thimbles. The two sets of four symmetric thimbles is a unique set of eight detector locati,ons. These locations are C-8, E-5, E- 11, H- 3, H-13, L-5, L-11, N-8. 3/4.2.5 DNB PARAMETERS ( The limits on the DNB-related parameters assure that each of the parameters are maintained within the normal steady-state envelope of operation assumed in the transient and accident analyses. The limits are consistent with the SOUTH TEXAS - UNITS 1 & 2 B 3/4 2-5 -
- _ _ _ - - - - _ . , - , , - - - - - - - - - - _ - - - - ~ - - - - _ - - - - - - -- - - . . , - - - - _ - - _ _ _ _ _
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I l i Attachment 4 t
- Sample Core Operating Limits Reports.
l l
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l \ l l l A1/026.R18
ATTACHMENT Y - ST HL AE 37r6 PAGE _L _0F --14 South Texas Unit 1 Cycle 3 1 CORE OPERATING LIMITS REPORT Thic Core Operating Limits Report for STPECS Unit 1 Cycle 3 has been prepared in accordance with the requirements of Technical Specification 6.9.1.6. The core operating limits have been developed usin6 the NRC approved methodologies specified in Technical Specification 6.9.1.6. The Technical Specifications affected by this report are:
- 1) 3/4.1.1.3 Moderator Temperature coefficient Limits
- 2) 3/4.1.3.5 Shutdovn Rod Insertion Limit
- 3) 3/4.1.3.6 Control Rod Insertion Limits
- 4) 3/4.2.1 AFD Limits
- 5) 3/4.2.2 licat Flux llot Channel Factor
- 6) 3/4.2,3 Nucicar Enthalpy Rise Hot Channel Factor 2 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented below.
2.1 MODERATOR TEMPERATURE _Q0 EFFICIENT (Specification 3.1.1.3) 2.1.1 The BOL, ARO, MTC shall be less positive than the limits shown in Figure 1. 2.1.2 The EOL, ARD, liFP, MTC shall be less negative than 4.0 x 10 ak/k/*F. 2.1.3 The 300 ppm, ARD, HFP, MTC shall be less negative than 3.1 x 10Ak/k/*F (300 ppm Surveillance Limit). l Where: BOL stands for Beginning of Cycle Life E0L stands for End of Cycle Life ARO stands for All Rods out llFP stands for llot Full Power (100% RATED TilERMAL POWER) 2.2 ROD INSERTION LIMITS (Specification 3.1.3.5 and 3.1.3.6) 2.?.1 The Concrol Rod Insertion limits are provided in Figure 2. 2.2.2 Fully withdrawn for-all Control and Shutdown Banks shall be 256 steps and above, but not exceeding 259 steps withdrawn. l 2.2.J All banks shall have the same fully withdrawn position. Page 1 of 7 l A1/026.N18
.- . . _ . . . , , . _ _ _ . . . . ~ . , _ . _..__,- - . _ - . . . _ . _ _ _. . _ . _
- i. , 4,.di/ENTV '
ST Hl. AE 376% PAGE n _ OF A 2.3 A&IAL FLUX DIFFERENCE (Specification 3.2.1) 2.3.1 AFD limits as required by Technical Specification 3.2.1 are determined by CAOC Operations with a Delta I allowable operating band of +3, 12t. 2.3.2 The AFD shall be maintained within the ACCEPTABl.E OPERATION portion of Figure 3, as required by Technical Specifications. 2.4 HEAT FLtrX ll(if CllANNEL FACTOR (Specification 3.2.2) 2.4.1 ifP-2.50. 2.4.2 K(Z> is provided in Figure 4. 2.4.3 The F,, limits for RATED TilTJtMAL F0VER within specific core planes shall be: 2.4.3.1 Iji'lessthanorequalto1.94forallcoreplanes containing Control Bank D rods, and 2.4.3.2 lij'lessthanorequalto1,64forallunroddedcore pianes. 2.4.3.3 P F,y - 0.2. These F,y limits were used to confirm that the heat flux hot channel factor Fo(z) will be limited by Technical Specification 3.2.2 assuming the most limiting axial power distributions expected to result for the insertion and removal of Control Bank ,. C and D during operation, including the accompanying variations l in the axial xenon and power distributions, as described in reference 3.2. Therefore, these F,, limits provide assurance that the initial conditions assumed in the IDCA analysis are j met, along with the ECCS acceptance criteria of 10CFR50.46, 2.5 ENTilALPY RISE liOT CllANNEL FACTOR (Specification 3.2.3) 2.5.1 f*g - 1.46, 2.5.2 PFa - 0. 3. Page 2 of 7 l A1/026.N18
/uienMENT4 , ST HL AE 37F6 PAGE 2 0F 14 3 REFERENCES 3.1 "Vestinghouse Reload Safety Evaluation Methodology," VCAP 9272 P A, July, 1985 3.2 " Power Distribution and Load Followin6 Procedures," VCAP 8385, September, 1974 3.3 NUREG 1346, Technical Specifications, South Texas Project Unit Nos. 1 and 2 l
l l l l Page 3 of 7 l l A1/026,N18
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Core Operating tiraits Report (Rev 9) 05/01/9') Page 5 of 7
ATTACHMENT 4
' ST HL AE 37S6 / PAGE G --_ 0F l '/ -
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4
. ATTACliMENT '/
ST HL AE 375% f PAGE 7 .0F /4 FIGURC 4 1.2 -
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ATTACHMENT (/ ST Hl. AE.37r6 South Texas Unit 2 Cycle 1 PAGE _ _P 0F / V 1 CORE OPERATIBO LIMITS REPORT This Core Operating Limits Report for STPECS Unit 2 Cycle 1 has been prepared in accordance with the requirements of Technical Specification 6.9.1.6. The core operating limits have been developed using the NRC approved methodologies specified in Tecnnical Specification 6.9.1.6. The Technical Specifications affected by this report are:
- 1) 3/4.1.1.3 Moderator Temperature Coefficient Limits
- 2) 3/4.1.3.5 Shutdown Rod Insertion Limit
- 3) 3/4.1.3.6 Control Rod Insertion Limits
- 4) 3/4.2.1 AFD Limits
- 5) 3/4.2.2 Heat Flux Hot Channel Factor
- 6) 3/4.2.3 Nuclear Enthalpy Rise llot Channel Factor 2 OPERATING LIMIII The cycle specific parameter limits for the specifications l'sted in.
Section 1.0 are preaented below. 2.1 MODERATOR TEMPERATURE COEFFICIENT (Specification 3.1.1.3) 2.1.1 The BOL, ARO, MTC shall be less pnsitive than the limits shown in Figure 1. 2.1.2 The EOL, ARD, itFP, MTC shall be less negative than -4.0 x 10 Ak/k/*T. 7.1.3 The 300 ppm, ARO, HTP, MTC shall be less negative- than -3.1 x - -- 10F*Ak/k/ F (300 ppm Surveillance Limir). Where: BOL stands for Beginning of Cycle Life EOL stands for End of Cycle Life ARO stands for All Rods Out HFP stands for llot Full Power (100% RATED TiiERMAL POWER) 2.2 ROD INSERTION LIMITS (Specifications 3.1.3.5 and 3.1.3.6) 2.2.1 The Control Rod Insertion limits are provided in Figure 2. 2.2.2 Fully withdrawn for all Control and Shutdown Banks shall be 256 steps and above, but not exceeding 259 steps withdra<n 2.2.3 All banks shall have the same fully withdrawn position. Page 1 of 7 A1/026.R16
ATTACHMENT y ST HL AE .57sw
. 2.3 AXIAL FLUX DIFFERENCE (Specification 3.2.1) 2.3.1 AFD limits as required by Technical Specification 3.2.1 are detertained by CAOC Operations with a Delta-I allowable operating band of +3, 12%.
2.3.2 The AFD shall 'oe snaintained within the ACCEPTABLE OPERATION portion of Figure 3, as required by Technical Specifications. 2.4 HEAT FLUX HOT CHANNEL FACTOR (Specification 3.2.2) 2.4.1 fTP n - 2.50. 2.4.2 K(Z) is provided in Figure 4 2.4.3 The F,, lital t:: for RATED THERMAL POWER within specific core plam s shall be: 2.4.3.1 fxf less than or equal to 1.78 for all core planes containing Control Bank D rods, and 2.4.3.2 Fjf less than or equal to 1.55 for all unrodded core planes. 2.4.3.3 P F,y - 0.2. These F,, limits were used to confirta that the heat flux hot channel factor Fn(z) will be limited by Technical Specification 3.2.2 assurning the most limiting axial power distributions expected to result for the insertion and removal of Control Bank C and D during operation, including the accompanying variations in the axial xenon and power distributions, as described in reference 3.2. Therefore, these F,y limits provide assurance that the initial conditions assumed in the IDCA analysis are met, along with the ECCS acceptance criteria of 10CFR50.46, 2.5 ENTHALPY RISE HOT CHANNEL FACTOR (Specification 3.2.3) 2.5.1 Fyf - 1.46, 2.5.2 PF3 s - 0. 3. Page 2 of 7 A1/026.N18
t- ATTACHMENT 4 ST HL AE-37re, 3 REFEREN,cn PAGE 10 0F /Y 3.1 "Vestinghouse Reload Lafety Evaluation Methodology," VCAP 9272-P-A, July, 1985 3.2 "I'onr Distribution and Load Fol',owing Procedures," VCAP 8385, September, 1974 3.3 "!!ouston Lighting 6 Power Company South Texas Project Units 1 and 2 Radial Peaking Factor Limit Report for South Texas Unit 2 Cycle 1," letter from H. A. Sinwell (Vestinghouse) to J. R. Vorden dated December 21, 1988. 3.4 NUREC-1346, Technical Specification , South Texas Project Unit Nos. 1 and 2 c Page 3 of 7 A1/026.N18
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- ATTACHMENT 4 ricune 2 ST HL A3 3756 C0!dROL ROD INSERTION L).*1115 YCRSUS P0;llR L[YR PAGE /A 0F /4 260: 4_ '23 ,259 79,259 1
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. 1 C SOUTH 1EX.A5 LN112 CYCLE' f
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w.. ATTACHMENT 'I ST HL AE 375%
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FICURE 3 I i 3
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~5 s (,4
- ATTACHMENT V
._,. . ST HL AE 3756 OF #
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