ML032120197

Tech Spec Pages for Amendment Nos. 154 & 142, Deleting Information Differentiating Between Unit 1 & Unit 2 Specific to Model E Steam Generators

ML032120197
Person / Time
Site:	South Texas
Issue date:	07/21/2003
From:	NRC/NRR/DLPM/LPD4
To:
Thadani M, NRR/DLPM, 415-1476
Shared Package
ML032130048	List: ML032120197 ML032130046
References
TAC MB5158, TAC MB5159
Download: ML032120197 (11)

Text

(1)

STPNOC pursuant to Section 103 of the Act and 10 CFR Part 50, to possess, use and operate the facility at the designated location in Matagorda County, Texas, in accordance with the procedures and limitations set forth in this license; (2)

Texas Genco, LP, the City Public Service Board of San Antonio (CPS), Central Power and Light Company (CPL), and the City of Austin, Texas (COA), pursuant to the Act and 10 CFR Part 50, to possess the facility at the designated location in Matagorda County, Texas, in accordance with the procedures and limitations set forth in this license; (3)

STPNOC, pursuant to the Act and 10 CFR Part 70, to receive, possess and. use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; (4)

STPNOC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5)

STPNOC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (6)

STPNOC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility authorized herein.

C. This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1)

Maximum Power Level STPNOC is authorized to operate the facility at reactor core power levels not in excess of 3853 megawatts thermal (100% power) in accordance with the conditions specified herein.

Amendment No. 427Tt3g,'iX42

1.0 DEFINITIONS 1.24 Not Used PURGE - PURGING 1.25 PURGE or PURGING shall be any controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

QUADRANT POWER TILT RATIO 1.26 QUADRANT POWER TILT RATIO shall be the ratio of the maximum upper excore detector calibrated output to the average of the upper excore detector calibrated outputs, or the ratio of the maximum lower excore detector calibrated output to the average of the lower excore detector calibrated outputs, whichever is greater. With one excore detector inoperable, the remaining three detectors shall be used for computing the average.

RATED THERMAL POWER 1.27 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 3,853 Mwt.

REACTOR TRIP SYSTEM RESPONSE TIME 1.28 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its Trip Setpoint at the channel sensor until loss of stationary gripper coil voltage. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured. In lieu of measurement, response time may be verified for selected components provided that the components or methodology for verification have been previously reviewed and approved by the NRC.

REPORTABLE EVENT 1.29 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 of 10 CFR Part 50.

SHUTDOWN MARGIN 1.30 SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming all full-length rod cluster assemblies (shutdown and control) are fully inserted except for the single rod cluster assembly of highest reactivity worth which is assumed to be fully withdrawn.

SOUTH TEXAS - UNITS I & 2 1-5 Unit 1 - Amendment No. 4384,156,154 Unit 2-Amendment No. 27, 139, 142

I)

-I 0) z C,,

TABLE 2.2-1 (Continued REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS U'

FUNCTIONAL UNIT

13. Steam Generator Water Level Low-Low

14. Undervoltage -

Reactor Coolant Pumps

15. Underfrequency -

Reactor Coolant Pumps

16. Turbine Trip

a.

Low Emergency Trip Fluid Pressure

b.

Turbine Stop Valve Closure

17. Safety Injection Input from ESFAS TRIP SETPOINT 2 20.0% of narrow range instrument span 2 10,014 volts 2 57.2 Hz 257.1 Hz ALLOWABLE VALUE 2 18.0% of narrow range instrument span 2 9339 volts 2 1245.8 psig 2 1114.5 psig C C SW I

- -a I I Pp

< Fully closed N.A.

Fully closed N.A.

POWER DISTRIBUTION LIMITS 3/4.2.5 DNB PARAMETERS LIMITING CONDITION FOR OPERATION 3.2.5 The following DNB-related parameters shall be maintained within the limits following:

a. Reactor Coolant System T., < the limit as specified in the Core Operating Limits Report

b. Pressurizer Pressure, > the limit as specified in the Core Operating Limits Report

c.

Thermal Design Reactor Coolant System Flow, 2 392,000 gpm APPLICABILITY:

MODE 1.

ACTION:

With any of the above parameters exceeding its limit, restore the parameter to within its limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce THERMAL POWER to less than 5% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.2.5.1 Each of the parameters shown above shall be verified to be within its limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. The provisions of Specification 4.0.4 are not applicable for verification that RCS flow is within its limit.

4.2.5.2 The RCS flow rate indicators shall be subjected to a channel calibration at least once per 18 months.

NOTE SR 4.2.5.3 is required at beginning-of-cycle with reactor power > 90% RTP.

4.2.5.3 The RCS total flow rate shall be determined by precision heat balance or elbow tap AP measurements at least once per 18 months. The provisions of Specification 4.0.4 are not applicable.

SOUTH TEXAS - UNITS 1 & 2 3/4 2-11 Unit 1 -Amendment No. 146, 117,154 Unit 2 - Amendment No. 403. 105.142

CD, 0C-I x

--I C

z

-4 a,

90 TABLE 3.3-4 (Continued)

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT

5. Turbine Trip and Feedwater Isolation (Continued)

d. Deleted

e. Safety Injection

f. Ta

- Low Coincident with Reactor Trip (P4)

(Feedwater Isolation Only)

6. Auxiliary Feedwater

a. Manual Initiation

b. Automatic Actuation Logic

c. Actuation Relays

d. Steam Generator Water Level--

Low-Low

e. Safety Injection TRIP SETPOINT ALLOWABLE VALUE c;

-S See Item 1. above for all Safety Injection Trip Setpoints and Allowable Values.

2 5740F

> 571.70 F N.A.

N.A.

N.A.

N.A.

N.A.

N.A.

2 20.0% of narrow range 2 18.0% of narrow range instrument span instrument span See Item 1. above for all Safety Injection Trip Setpoints and Allowable Values C a S+ S CD Q z z 0 0ii

4. rlu r\\) -P.

REACTOR COOLANT SYSTEM 3/4.4.5 STEAM GENERATOR LIMITING CONDITION FOR OPERATION 3.4.5 Each steam generator shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION:

With one or more steam generators inoperable, restore the inoperable generator(s) to OPERABLE status prior to increasing T.

above 2000F.

SURVEILLANCE REQUIREMENTS 4.4.5.0 Each steam generator shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.5.

4.4.5.1 Steam Generator Sample Selection and InsDection - Each steam generator shall be determined OPERABLE during shutdown by selecting and inspecting at least the minimum number of steam generators specified in Table 4.4-1.

4.4.5.2 Steam Generator Tube Samnle Selection and Inspection - The steam generator tube minimum sample size, inspection result classification, and the corresponding action required shall be as specified in Table 4.4-2. The inservice inspection of steam generator tubes shall be performed at the frequencies specified in Specification 4.4.5.3 and the inspected tubes shall be verified acceptable per the acceptance criteria of Specification 4.4.5.4. The tubes selected for each inservice inspection shall include at least 3% of the total number of nonplugged tubes in all steam generators; the tubes selected for these inspections shall be selected on a random basis except:

a. Where experience in similar plants with similar water chemistry indicates critical areas to be inspected, then at least 50% of the tubes inspected shall be from these critical areas;

b. The first sample of tubes selected for each inservice inspection (subsequent to the preservice inspection) of each steam generator shall include:

1) All nonplugged tubes that previously had detectable wall penetrations (greater than 20%),

2)

Tubes in those areas where experience has indicated potential problems, and SOUTH TEXAS - UNITS I & 2 3/4 4-12 Unit I - Amendment No. 90-4 07,154 Unit 2 - Amendment No. 7-7, 4, 142

REACTOR COOLANT SYSTEM STEAM GENERATORS SURVEILLANCE REQUIREMENTS (Continued)

3) A tube Inspection (pursuant to Specification 4.4.5.4a.9) shall be performed on each selected tube. If any selected tube does not permit the passage of the eddy current probe for a tube inspection, this shall be recorded and an adjacent tube shall be selected and subjected to a tube inspection.

c.

The tubes selected as the second and third samples (if required by Table 4.4-2) during each inservice inspection may be subjected to a partial tube inspection provided:

1) The tubes selected for these samples include the tubes from those areas of the tube sheet array where tubes with imperfections were previously found, and

2) The inspections include those portions of the tubes where imperfections were previously found.

The results of each sample inspection shall be classified into one of the following three categories.

Category Inspection Results C-1 Less than 5% of the total tubes inspected are degraded tubes and none of the inspected tubes are defective.

C-2 One or more tubes, but not more than 1% of the total tubes inspected are defective, or between 5% and 10% of the total tubes inspected are degraded tubes.

C-3 More than 10% of the total tubes inspected are degraded tubes or more than 1% of the inspected tubes are defective.

Note: In all inspections, previously degraded tubes must exhibit significant (greater than 10%) further wall penetrations to be included in the above percentage calculations.

82, 83, 90, 96, 107, 115,154 SOUTH TEXAS - UNITS I & 2 3/4 4-13 Unit I - Amendment No.

Unit 2 - Amendment No.

77, 83, 91,111, 133,142

REACTOR COOLANT SYSTEM STEAM GENERATORS SURVEILLANCE REOUIREMFNTS (Continued) 4.4.5.4 Acceptance Criteria

a.

As used in this specification:

1) Tube means that portion of the tube which forms the primary system to secondary system pressure boundary;

2)

Imperfection means an exception to the dimensions, finish, or contour of a tube from that required by fabrication drawings or specifications. Eddy-current testing indications below 20% of the nominal tube wall thickness, if detectable, may be considered as imperfections;

3)

Degradation means a service-induced cracking, wastage, wear, or general corrosion occurring on either inside or outside of a tube;

4)

Degraded Tube means a tube containing imperfections greater than or equal to 20% of the nominal wall thickness caused by degradation;

5)

% Degradation means the percentage of the tube wall thickness affected or removed by degradation;

6)

Defect means an imperfection of such severity that it exceeds the plugging limit A tube containing a defect is defective;

7)

Plugging Limit means the imperfection depth at or beyond which the tube shall be removed from service and is equal to 40% of the nominal tube wall thickness:

8)

Unserviceable describes the condition of a tube if it leaks or contains a defect large enough to affect its structural integrity in the event of an Operating Basis Earthquake, a loss-of-coolant accident, or a steam line or feedwater line break as specified in Specification 4.4.5.3c., above;

9)

Tube Inspection means an inspection of the steam generator tube from the point of entry (hot leg side) completely around the U-bend to the top support of the cold leg;

10) Preservice Inspection means an inspection of the full length of each tube in each steam generator performed by eddy current techniques prior to service to establish a baseline condition of the tubing. This inspection shall be performed prior to initial POWER OPERATION using the equipment and techniques expected to be used during subsequent inservice inspections.

SOUTH TEXAS - UNITS 1 & 2 3/4 4-15 Unit 1 - Amendment No. 83, B0, 96, 107, 1 54 Unit 2-Amendment No. 77,83,94, 142

REACTOR COOLANT SYSTEM STEAM GENERATORS SURVEILLANCE REOUIREMENTS (Continued)

b.

The steam generator shall be determined OPERABLE after plugging all tubes exceeding the plugging limit and all tubes containing through-wall cracks required by Table 4.4-2.

4.4.5.5 Reports

a.

Within 15 days following the completion of each inservice inspection of steam generator tubes, the number of tubes plugged in each steam generator shall be reported to the Commission in a Special Report;

b.

The complete results of the steam generator tube inservice inspection shall be submitted in a Special Report within 12 months following the completion of the inspection. This Special Report shall include:

1) Number and extent of tubes inspected,

2) Location and percent of wall-thickness penetration for each indication of an imperfection, and

3) Identification of tubes plugged.

c.

Results of steam generator tube inspections which fall into Category C-3 shall be reported in a Special Report within 30 days and prior to resumption of plant operation. This report shall provide a description of investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence.

I I

SOUTH TEXAS - UNITS I & 2 3/4 4-16 82, 83, 80, 96, 107, 145,44',154 Unit I - Amendment No.

Unit 2 - Amendment No 77,83,9,111, 13,439,142

Table 4.4-2 STEAM GENERATOR TUBE INSPECTION 1st SAMPLE INSPECTION 2nd SAMPLE INSPECTION 3rd SAMPLE INSPECTION Sample Size Result Action Required Result Action Required Result Action Required A minimum of S C-1 None N.A.

N.A.

N.A.

N.A.

Tubes per SG.

C-2 Plug defective tubes C-1 None N.A.

N.A.

and Inspect additional 2S tubes in this SG.

C-2 Plug defective tubes C-1 None and inspect additional 4S tubes in this SG C-2 Plug defective tubes C-3 Perform action for C-3 result of first sample C-3 Perform action for N.A.

N.A.

C-3 result of first sample.

C-3 Inspect all tubes in this All other N.A.

N.A.

SG, plug defective SGs are C-1 None tubes and inspect 2S tubes in each other Some SGs Perform action for C-2 N.A.

N.A.

SG.

C-2 but no result of second sample additional Notify NRC pursuant to SG are C-3 1 OCFR50.72(b)(3)(ii)

Additional Inspect all tubes In each N.A.

N.A.

SG is C-3 SG and plug defective tubes.

Notify NRC pursuant to 10CFR50.72(b)(3)(ii)

I I

5=3-%

n where N is the number of steam generators in the unit, and n Is the number of steam generators inspected during an inspection.

SOUTH TEXAS - UNITS 1 & 2 3/4 4-18 Unit 1 - Amendment No. 90,-146,154 Unit 2 - Amendment No.77, 114,133, 142

TABLE 3.7-1 MAXIMUM ALLOWABLE POWER RANGE NEUTRON FLUX HIGH SETPOINT WITH INOPERABLE STEAM LINE SAFETY VALVES DURING 4 LOOP OPERATION MAXIMUM NUMBER OF INOPERABLE SAFETY VALVES ON ANY OPERATING STEAM GENERATOR MAXIMUM ALLOWABLE POWER RANGE NEUTRON FLUX HIGH SETPOINT (PERCENT OF RATED THERMAL POWER) 1 61 43 2

3 26 SOUTH TEXAS - UNITS I & 2 3/4 7-2 Unit 1 - Amendment No. 448, 154 Unit 2 -Amendment No. 42, 142