Text

Technical Specifications, Best Estimate Analyzer for Core Operations-Nuclear
	ML060950451
Person / Time
Site:	South Texas
Issue date:	03/31/2006
From:	; Plant Licensing Branch III-2
To:	;
	Thadani M
Shared Package
ML060760523	List: ML060760501; ML060950451;
References
	TAC MC8224, TAC MC8225
	Download: ML060950451 (12)
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REACTIVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION ACTION (Continued)

-~N c) A core power distribution measurement is obtained and F0 (Z) and l-NH are verified to be within their limits within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; and I d) The THERMAL POWER level is reduced to less than or equal to 75% of RATED THERMAL POWER within the next hour and within the following 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 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 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , the remainder of the rods in the bank(s) with the inoperable rods are aligned to within +/- 12 steps of the inoperable rods while maintaining the rod sequence and insertion limits as specified in the COLR. The THERMAL POWER level shall be restricted pursuant to Specification 3.1.3.6 during subsequent operation, and

2. The inoperable rods are restored to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

d. With more than one rod misaligned from its group step counter demand height by more than + 12 steps (indicated position), be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS 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 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except during time intervals when the rod position deviation monitor is inoperable, then verify the group positions at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

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.

SOUTH TEXAS - UNITS 1 & 2 3/4 1-17 Unit 1 - Amendment Nlo. 2 175 Unit 2 - Amendment No. 4- 163

REACTIVITY CONTROL SYSTEMS POSITION INDICATION SYSTEMS - OPERATING LIMITING CONDITION FOR OPERATION 3.1.3.2 The Digital Rod Position Indication System and the Demand Position IndicatiDn System shall be OPERABLE and capable of determining the control rod positions within +/- 12 steps.

APPLICABILITY: MODES 1 and 2.

ACTION:

-R. With a maximum of one digital rod position indicator per bank inoperable either:

1. Determine the position of the nonindicating rod(s) indirectly by the movable incore detectors or a core power distribution measurement at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and immediately after any motion of the nonindicating rod which exceeds 24 steps in I one direction since the last determination of the rod's position, or

2. Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

b. With a maximum of one demand position indicator per bank inoperable either:

1. Verify that all digital rod position indicators for the affected bank are OPERABLE and that the most withdrawn rod and the least withdrawn rod of the bank are within a maximum of 12 steps of each other at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , or

2. Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

SURVEILLANCE REQUIREMENTS 4.1.3.2 Each digital rod position indicator shall be determined to be OPERABLE by verifying that the Demand Position Indication System and the Digital Rod Position Indication System agree within 12 steps at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except during time intervals when the rod position deviation monitor is inoperable, then compare the Demand Position Indication System and the Digital Rod Position Indication System at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

SOUTH TEXAS - UNITS 1 & 2 3/4 1-19 Unit 1 - Amendment No. 175 Unit 2 - Amendment No. 163

POWER DISTRIBUTION LIMITS 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR - Fn (Z)

LIMITING CONDITION FOR OPERATION 3.2.2 Fa(Z) shall be limited by the following relationships:

F.(Z) < (FTP/P)* K(Z) for P > 0.5 Fo(Z) < (FRTP/OS)* K(Z) for P < 0.5 Where: FTP = the FQ limit at RATED THERMAL POWER (RTP) specified in the Core Operating Limits Report (COLR).

THERMAL POWER and P = RATED THERMAL POWER K(Z) = the normalized Fo(Z) as a function of core height specified in the COLR.

APPLICABILITY: MODE 1.

ACTION:

With Fc(Z) exceeding its limit:

a. Reduce THERMAL POWER at least 1% for each 1% Fa(Z) exceeds the limit within 15 minutes and similarly reduce the Power Range Neutron Flux-High Trip Setpoint within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; POWER OPERATION may proceed for up to a total of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; subsequent POWER OPERATION may proceed provided the Overpower AT Trip Setpoint has been reduced at least 1% for each 1% Fa(Z) exceeds the limit.

Is. Identify and correct the cause of the out-of-limit condition prior to increasing THERMAL POWER above the reduced limit required by ACTION a., above; THERMAL POWNER may then be increased provided Fa(Z) is demonstrated through core power distribution measurement to be within its limit.

SOUTH TEXAS - UNITS 1 & 2 3/4 2-5 Unit 1 - Amendment No. 2 175 Unit 2 - Amendment [lo. 4-7 163

POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS 4.2.2.1 The provisions of Specification 4.0.4 are not applicable.

4.2.2.2 FXY shall be evaluated to determine if FQ(Z) is within its limit by:

a. Obtaining a core power distribution measurement,

b. Increasing the measured F.y by the applicable manufacturing and measurement uncertainties as specified in the COLR,

c. Comparing the F,,y computed (F.? ) obtained in Specification 4.2.2.2b., above to:

1) The FXY limits for RATED THERMAL POWER (F-RTP) for the appropriate measured core planes given in Specification 4.2.2.2e. and f., below, and

2) The relationship:

FL = 1T1[j+pFxy(1-p)]'

Where FL is the limit for fractional THERMAL POWER operation expressed as a function of FXTP, PFXY is the power factor multiplier FXY specified in the COLR, and P is the fraction of RATED THERMAL POWER at which Fxy is measured.

d. Remeasuring Fxy according to the following schedule:

1) When F- is greater than the FRTP limit for the appropriate measured core plane but less than the FLt relationship, additional core power distribution measurements shall be taken and Fc compared to F.RTP and Fx, either:

a) Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after exceeding by 20% RATED THERMAL POWER or greater, the THERMAL POWER at which FXCY was last determined, or b) At least once per 31 Effective Full Power days (EFPD), whichever occurs first.

SOUTH TEXAS - UNITS 1 & 2 3/4 2-7 Unit 1 - Amendment Ngo. 2- 175 Unit 2 - Amendment Ngo. 4- 163

POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued)

2) When FXCis less than or equal to the FF.'TP limit for the appropriate measured core plane, additional core power distribution measurements shall be taken and FXGY compared to FgRP and FL- at least once per 31 EFPD.

e. The Foxy limits used in the Constant Axial Offset Control analysis for RATED THERMAL POWER (FR-TP ) shall be provided for all core planes containing bank "D" control rods and all unrodded core planes as specified in the COLR per Specification 6.9.1.6;

f. The Fy limits of Specification 4.2.2.2e, above, are not applicable in the following core planes regions as measured in percent of core height from the bottom of the fuel:

1) Lower core region from 0 to 15%, inclusive,

2) Upper core region from 85 to 100%, inclusive,

3) Grid plane regions at 22.4 + 2%, 34.2 + 2%, 46.0 + 2%, 57.8 + 2%, 69.5 + 2%

and 81.3 + 2%, inclusive, and

4) Core plane regions within + 2% of core height (+/- 3.36 inches) about the bank demand position of the bank "D" control rods.

9. With Fib exceeding Fy, the effects of F,,, on Fo(Z) shall be evaluated to determine if Fa(Z) is within its limits.

4.2.2.3 When FQ(Z) is measured for other than F,, determinations, an overall measured F((Z) shall be obtained from a core power distribution measurement and increased by the applicable manufacturing and measurement uncertainites as specified in the COLR.

SOUTH TEXAS - UNITS 1 & 2 3/4 2-8 Unit 1 - Amendment Njo. 27175 Unit 2 - Amendment No. 47 163

POWER DISTRIBUTION LIMITS 3/4.2.3 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR LIMITING CONDITION FOR OPERATION 3.2.3 F~,shall be less than FUP [1.0 +PFAH (1-P)]

Where: Fr}T = the Fm Limit at RATED THERMAL POWER (RTP) specified in the Core Operating Limits Report (COLR).

PFAH = the Power Factor Multiplier for Fig specified in the Core Operating Limits Report (COLR).

p THERMAL POWER RATED THERMAL POWER APPLICABILITY: MODE 1.

ACTI ON:

With FR exceeding its limit:

a. Within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months reduce the THERMAL POWER to the level where the LIMITING CONDITION FOR OPERATION is satisfied.

b. Identify and correct the cause of the out-of-limit condition prior to increasing THERMAL POWER above the limit required by ACTION a., above; THEFRMAL POWER may then be increased, provided FN is demonstrated through core power distribution measurement to be within its limits.

SURVEILLANCE REQUIREMENTS 4.2.3.1 The provisions of Specification 4.0.4 are not applicable.

4.2.3.2 FN shall be demonstrated to be within its limit prior to operation above 75% RATED THERMAL POWER after each fueling loading and at least once per 31 EFPD thereafter by:

a. Obtaining a core power distribution measurement.

b. Increasing the measured value of F,, by the applicable measurement uncertainty as specified in the COLR.

SOUTH TEXAS - UNITS 1 & 2 3/4 2-9 Unit 1 - Amendment No. 2a 175 Unit 2 - Amendment No. 14 163

POWER DISTRIBUTION LIMITS 3/4.2.4 QUADRANT POWER TILT RATIO LIMITING CONDITION FOR OPERATION 3.2.4 The QUADRANT POWER TILT RATIO shall not exceed 1.02.

APPLICABILITY: MODE 1, above 50% of RATED THERMAL POWER*.

ACTION:

With the QUADRANT POWER TILT RATIO determined to exceed 1.02:

a. Within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months reduce THERMAL POWER at least 3% from RATED THERMAL POWER for each 1% of indicated QUADRANT POWER TILT RATIO in excess of 1 and similarly reduce the Power Range Neutron Flux-High Trip Setpoint within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

b. Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and every 7 days thereafter, verify that Fo(Z) (by F<,, evaluation) and at are within their limits by performing Surveillance Requirements 4.2.2.2 and 4.2.3.2. THERMAL POWER and setpoint reductions shall then be in accordance with the ACTION statements of Specifications 3.2.2 and 3.2.3.

SURVEILLANCE REQUIREMENTS 4.2.4.1 The QUADRANT POWER TILT RATIO shall be determined to be within the limit above 50% of RATED THERMAL POWER by:

a. Calculating the ratio at least once per 7 days when the alarm is OPERABLE, and

b. Calculating the ratio at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during steady-state operation when the alarm is inoperable.

4.2.4.2 The QUADRANT POWER TILT RATIO shall be determined to be within the limit when above 75% of RATED THERMAL POWER with one Power Range channel inoperable by measuring core power distribution to confirm indicated QUADRANT POWER TILT RATIO at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by using:

a. The Power Distribution Monitoring System (PDMS), or

b. The movable incore detectors by either:

1. Using the four pairs of symmetric thimble locations, or

2. Using the movable incore detection system to monitor the QUADRANT POWER TILT RATIO with a full incore map.

See Special Test Exceptions Specification 3.10.2.

SOUTH TEXAS - UNITS 1 & 2 3/4 2-10 Unit 1 - Amendment No. 4167 175 Unit 2 - Amendment No. 456 163

REACTOR COOLANT SYSTEM COLD SHUTDOWN - LOOPS NOT FILLED LIMITING CONDITION FOR OPERATION 3.4.1.4.2

a. At least two residual heat removal (RHR) loops shall be OPERABLE* and at least one RHR loop shall be in operation**, and

b. Each valve or mechanical joint used to isolate unborated water sources shall be secured in the closed position.

APPLICABILITY: MODE 5 with reactor coolant loops not filled.

ACTION:

a. With less than the above required RHR loops OPERABLE, immediately initiate corrective action to return the required RHR loops to OPERABLE status as soon as possib'e.

b. With no RHR loop in operation, suspend all operations that would cause introduction into the RCS of coolant with boron concentration less than required to meet SHUTDOWN MARGIN of LCO 3.1.1 and immediately initiate corrective action to return the required RHR loop to operation.

^. With a valve or mechanical joint used to isolate unborated water sources not secured in the closed position, immediately suspend all operations that would cause introduction into the RCS of coolant with boron concentration less than required to meet SHUTDOWN MARGIN specified in the Core Operating Limits Report (COLR) and initiate action to secure the valve(s) or joint(s) in the closed position and within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months verify boron concentration is within limits specified in the COLR. The required action to verify the boron concentration within limits must be completed whenever ACTION c is entered. A separate ACTION entry is allowed for each unsecured valve or mechanical joint.

SURVEILLANCE REQUIREMENTS 4.4.1.4.12.1 At least one RHR loop shall be determined to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

4.4.11.4.2.2 Each valve or mechanical joint used to isolate unborated water sources shall be verified closed and secured in position at least once per 31 days.

Two RHR loops may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing provided the other RHR loop is OPERABLE and in operation.

- The RHIR pump may be deenergized for up to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months provided: (1)no operations are permitted that would cause introduction into the RCS of coolant with boron concentration less than that required to meet SHUTDOWN MARGIN of LCO 3.1.1, and (2)core outlet temperature is maintained at least 10OF below saturation temperature.

SOUTH TEXAS - UNITS 1 & 2 3/4 4-6 Unit 1 -Amendment No. -128, -49 175 Unit 2 - Amendment No. 11447, 1437 163

REACTOR COOLANT SYSTEM OVERPRESSURE PROTECTION SYSTEMS SURVEILLANCE REQUIREMENTS 4.4.9.3.1 Each PORV shall be demonstrated OPERABLE by:

a. Performance of an ANALOG CHANNEL OPERATIONAL TEST on the PORV actuation channel, but excluding valve operation, within 31 days prior to entering a condition in which the PORV is required OPERABLE and at least once per 31 days thereafter when the PORV is required OPERABLE;

b. Performance of a CHANNEL CALIBRATION on the PORV actuation channel at least once per 18 months; and

c. Verifying the PORV block valve is open at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months when the PORV is being used for overpressure protection.

4.4.9.3.2 The RCS vent(s) shall be verified to be open at least once per 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months s4 when the vent(s) is being used for overpressure protection.

4.4.9.3.3 The positive displacement pump shall be demonstrated inoperable5 at least once per 31 days, except when the reactor vessel head is removed or when both centrifugal charging pumps are inoperable and secured, by verifying that the motor circuit breakers are secured in the open position.

4.4.9.3.4 Verify at least once every 31 days that only one centrifugal charging pump is capable of injecting into the RCS 5, except when the reactor vessel head is removed, by verifying that the motor circuit breakers are secured in the open position.2 4.4.9.3.5 Verify at least once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months that each ECCS accumulator is isolated.

SPECIFICATION NOTATIONS 1 ECCS accumulator isolation is required only when ECCS accumulator pressure is greater than or equal to the maximum RCS pressure for the existing RCS cold leg temperature allowed by Figures 3.4-2 and 3.4-3.

2 An inoperable centrifugal charging pump(s) and/or positive displacement charging pump may be energized for testing or pump switching provided the discharge of the pump(s) has been isolated from the RCS by a closed isolation valve with power removed from the valve operator, or by a manual isolation valve secured in the closed position. Reactor coolant pump seal injection flow may be maintained during the RCS isolation process.

3 This ACTION may be suspended for up to 7 days to allow functional testing to verify PORV operability.

During this test period, operation of systems or components which could result in an RCS mass or temperature increase will be administratively controlled. During the ASME stroke testing of two inoperable PORVS, cold overpressurization mitigation will be provided by two RHR discharge relief valves associated with two OPERABLE and operating RHR loops which have the auto closure interlock bypassed [or deleted]. If one PORV is inoperable, cold overpressure mitigation will be provided by the OPERABLE PORV and one RHR discharge relief valve associated with an OPERABLE and operating RHR loop which has the auto closure interlock bypassed [or deleted].

4 Except when the vent pathway is provided with a valve that is locked, sealed, or otherwise secured in the open position, then verify these valves open at least once per 31 days.

SOUTH TEXAS - UNITS 1 & 2 3/4 4-38 Unit 1 - Amendment No. 441-8 175 Unit 2 - Amendment No. 4-06 163

6.0 ADMINISTRATIVE CONTROLS 6.2 Organization 6.2.1 Offsite and Onsite Organizations Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting the safety of the nuclear power plant.

a. Lines of authority, responsibility, and communication shall be defined and established throughout highest management levels, intermediate levels, and all operating organization positions. These relationships shall be documented and updated, as appropriate, in organization charts, functional descriptions of departmental responsibilities and relationships, job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements, including the plant-specific titles of those personnel fulfilling the responsibilities of the positions delineated in these Technical Specifications, shall be documented in the UFSAR and/or the Operations Quality Assurance Plan.

b. The plant manager shall be responsible for overall safe operation of the plant and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.

,. A specified corporate officer shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.

d. The individuals who train the operating staff, carry out radiation protection functions, or perform quality assurance functions may report to the appropriate onsite manager; however, these individuals shall have sufficient organizational freedom to ensure their independence from operating pressures.

6.2.2 Unit Staff The unit staff organization shall include the following:

a. A total of three non-licensed operators for the two units is required in all conditions. At least one of the required non-licensed operators shall be assigned to each unit. When a unit is operating in MODES 1, 2, 3, or 4, two non-licensed operators are required to be assigned to that unit.

b. The shift crew composition may be one less than the minimum requirements of 'I0 CFR 50.54(m)(2)(i) and Specifications 6.2.2.a and 6.2.2.f for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence of on-duty shift crew members, provided immediate action is taken to restore the shift crew composition to within the minimum requirements.

(continued)

SOUTH TEXAS - UNITS 1 & 2 6-2 Unit 1 - Amendment No. 3, 93, 151 175 Unit 2 - Amendment No. 88r4 3 9 163

6.0 ADMINISTRATIVE CONTROLS 6.9 Reporting Requirements 6.9.1.6a (Continued)

8. Heat Flux Hot Channel Factor, K(Z), Power Factor Multiplier, FRTP, and F0(Z) manufacturing and measurement uncertainties for Specification 3/4.2.2,

9. Nuclear Enthalpy Rise Hot Channel Factor, Power Factor Multiplier, and FAH measurement uncertainties for Specification 3/4.2.3, and

10. DNB related parameters for Reactor Coolant System Tavg Pressurizer Pressure, and the Minimum Measured Reactor Coolant System Flow for Specification 3/4.2.5.

The COLR shall be maintained available in the Control Room.

b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

1. WCAP 9272-P-A, "Westinghouse reload safety evaluation methodology" July 1985 (W Proprietary).

(Methodology for Specification 3.1.1.1 - Shutdown Margin, 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 Diffarence, 3.2.2 - Heat Flux Hot Channel Factor, 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor, and 3.2.5 - DNB Parameters.)

2. WCAP 12942-P-A "safety evaluation supporting a more negative eol Moderator temperature coefficient technical specification for the south texas projec: electric generating station units 1 and 2."

(Methodology for Specification 3.1.1.3 - Moderator Temperature Coefficient)

3. WCAP 8745-P-A, "Design Basis for the Thermal Overpower AT and Thermal Overtemperature AT Trip Functions," September 1986 (Westinghouse Proprietary Class 2).

(Methodology for Specification 2.1 - Safety Limits and 2.2 - Limiting Safety System Settings)

4. WCAP 8385, "power distribution and load following procedures topical report,"

September, 1974 (W Proprietary)

(Methodology for Specification 3.2.1 - Axial Flux Difference (Constant Axial Offset Control)

(continued)

SOUTH TEXAS - UNITS 1 & 2 6-15 Unit 1- Amendment No.14-5,150,411 175 Unit 2 - Amendment No.403,138,439 163

6.0 ADMINISTRATIVE CONTROLS 6.9 Reporting Requirements 6.9.1.6b (continued)

5. Westinghouse Letter NS-TMA-2198, T. M. Anderson (Westinghouse) to K.

Kniel (Chief of Core Performance Branch, NRC) January 31, 1980 -

Attachment:

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.)

6. NUREG-0800, Standard Review Plan, U. S. Nuclear Regulatory Commission, Section 4.3, Nuclear Design, July, 1981. Branch Technical Position CPB 4.3-1, Westinghouse Constant Axial Offset Control (CAOC),

Rev. 2, July 1981.

(Methodology for Specification 3.2.1 - Axial Flux Difference (Constant Axial Offset Control).)

7. WCAP 10266-P-A, Rev. 2, WCAP 11524-NP-A, Rev. 2, "The 1981 Version of the Westinghouse ECCS Evaluation Model Using the BASH Code,"

Kabadi, J. N., et al., March 1987; including Addendum 1-A, "Power Shape Sensitivity Studies," December, 1987 and Addendum 2-A, "BASH methodology Improvements and Reliability Enhancements," May 1988.

(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor)

8. WCAP 12610-P-A, "Vantage+ Fuel Assembly Reference Core Report," April 1995 (W Proprietary)

(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor)

9. CENPD-397-P-A, Revision 01, "Improved Flow Measurement Accuracy Using Crossflow Ultrasonic Flow Measurement Technology," May 2000.

(Methodology for operating at a RATED THERMAL POWER of 3,853 Mwt)

10. WCAP 13749-P-A, "Safety Evaluation Supporting the Conditional Exemption of the Most Negative EOL Moderator Temperature Coefficient Measurement," March 1997 (W Proprietary).

(Methodology for Specification 3.1.1.3 - Moderator Temperature Coefficient)

11. WCAP 12472-P-A, "BEACON Core Monitoring and Operations Support System," August 1994 (W Proprietary)

(Methodology for Specification 3.2.1 - Axial Flux Difference, 3.2.2 - Heat Flux Hot Channel Factor, 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor)

(continued)

SOUTH TEXAS - UNITS 1 & 2 6-16 Unit 1 - Amendment No. 4-38, 151 175 Unit 2- Amendment No. *27, 1.9 163

v t e Letter Sequence Other
TAC:MC8224, (Open) TAC:MC8225, (Open)
Initiation Request Acceptance... Administration Questions Answers Results Approval... Other: ML060760501, ML060950451
MONTHYEAR2005-08-30 [Table View]

ML060950451

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