ML20206A343
| ML20206A343 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 04/19/1999 |
| From: | Gramm R NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20206A348 | List: |
| References | |
| NUDOCS 9904280138 | |
| Download: ML20206A343 (10) | |
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- 4 UNITED STATES f",
j NUOLEAR REGULATORY COMMISSION o
R WASHINGTON, D.C. eamaa anni s.,...../
STP NUCLEAR OPERATING COMPANY DOCKET NO. 50-498 SOUTH TEXAS PROJECT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.108 License No. NPF-76 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by STP Nuclear Operating Company
- acting on behalf of itself and for Houston Lighting & Power Company (HL&P), the City Public Service Board of San Antonio (CPS), Central Power and Light Company (CPL), and City of Austin, Texas (COA) (the licensees), dated August 6,1997, as supplemented by letters dated September 4 and 18,1997, December 9, 1997, and February 4,1999, complies with the standards and requirements of
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the Atomic Energy Act of 1954, as amended (the Act), and the Commission's I
rufes and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- STP Nuclear Operating Company is authorized to act for Houston Lighting & Power Company (HL&P), the City Public Service Board of San Antonio, Central Power and Light Company and City of Austin, Texas and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.
9904280138 990419 PDR ADOCK 05000498 P
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. 2.
Accordir. gly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Facility l
Operating License No. NPF-76 is hereby amended to read as follows:
2.
Technical Soecifications
)
The Technical Specifications contained in Appendix A, as revised through Amendment No. 108, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and j
the Environmental Protection Plan.
]
3.
The license amendment is effective as of its date of issuance to be implemented within 7 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION l
A bh Robert A. Gramm, Chief, Section 1
)
Project Directorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical J
Specifications I
Date of issuance: April 19. 1999 l
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UNITED STATES p
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NUCLEAR REGULATORY COMMIS810N j
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STP NUCLEAR OPERATING COMPANY DOCKET NO. 50-499 SOUTH TEXAS PROJECT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 95 License No. NPF-80 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by STP Nuclear Operating Company
- acting on behalf of itself and for Houston Lighting & Power Company (HL&P), the City Public Service Board of San Antonio (CPS), Central Power and Light Company (CPL), and City of Austin, Texas (COA) (the licensees), dated August 6,1997, as supplemented by letters dated September 4 and 18,1997, December 9, 1997, and February 4,1999, complies with the standards and requirements of the AtomJc Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; and
]
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the.
Commission's regulations and all applicable requirements have been satisfied.
- STP Nuclear Operating Company is nuthorized to act for Houston Lighting & Power Company (HL&P), the City Public Service Board of San Antonio, Central Power and Light Company and City of Austin, Texas and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.
r
. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. NPF-80 is hereby amended to read as follows:
2.
Technical Soecifications j
The Technical Specifications contained in Appendix A, as revised through Amendment N;. 95, and the Environmental Protection Plan contained
.in Appendix B, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
]
3.
The license amendment is effective as of its date of issuance to be implemented' within 7 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION l
h W
Robert A. Gramm, Chief, Section 1 Project Directorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: April 19, 1999
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ATTACHMENT TO LICENSE AMENDMENT NOS.108 AND 95 FACILITY OPERATING LICENSE NOS. NPF-76 AND NPF-80 DOCKET NOS. 50-498 AND 50-499 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Inig_r1 2-3 2-3*
2-4 2-4 3/4 2-11 3/4 2-11 B 3/4 2-5 B 3/4 2-5*
B 3/4 2-6 B 3/4 2-6
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I
- Overleaf pages provided to maintain document completeness. No changes contained on these pages.
i SAFFTY [fMITS AMD tfMITINC EAFFTY KYSTEM EFTTfNGS 2.2 LIMITING SAFETY SYSTEM SETTINGS REACTOR TRIP SYSTEM INSTRUMENTATION SETPOINTS 2.2.1 The Reactor Trip System Instrumentation and Interlock Setpoints shall be set consistent with the Trip setpoint values shown in Table 2.2-1.
APPLICABILITY: As shown for each channel in Table 3.3-1.
ACTION:
With a Reactor Trip System Instrumentation or Interlock Setpoint a.
less conservative than the value shown in the Trip setpoint column but more conservative than the value shown in the f'lowable Value column of Table 2.2-1, adjust the Satpoint cons?
.t with the Trip
. Setpoint value.
b.
With the Reactor Trip System Instrumentation or Into 'ock Setpoint less conservative than the value shown in the A11swable Value column of Table 2.2-1, either:
1.
Adjust the Setpoint consistent with the Trip setpoint value of Table 2.2-1 and determine within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> that Equation 2.2-1 was satisfied for the affected channel, or 2.
Ceclare the channel inoperable and apply the applicable ACTION statement requirement of Specification 3.3.1 until the channel I
is restored to OPERABLE status with its Setpoint adjusted consistent with the Trip 5etpoint value.
Equation 2.2-1 2 + R + 5 i TA Where:
Z = The value from Column 2 of Table 2.2-1 for the affected channel, R = The "as measured" value (in percent span) of rack error for the affected channel, S = Either the "as-measured" value (in percent span) of the sensor error, or the value from Column S (Sensor Error) of Table 2.2-1 for the affected channel, and TA = The value from Columh TA (Total Allowance) of Table 2.21 for the affected channel.
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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 Tg, s 598'F (or s 595'F with reduced RCS flow of 3.2.5.c) b.
Pressurizer Pressure, > 2189 psig*
c.
Reactor Coolant System Flow,2 392,300 gpm" (or 2380,500 gpm" with reduced RCS T, of 3.2.5.a) 4 AP_PLICABILITY: 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 flowis 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 290% RTP.
4.2.5.3 The RCS total flow rate shall be determined by precision heat balance or elbow tap AP l
measurements at least once per 18 months. The provisions of Specification 4.0.4 are not applicable.
i
- Limit not applicable during either a Thermal Power ramp in excess of 5% of RTP per minute or a Thermal Power step in excess of 10% RTP.
J
" Includes a 2.8% flow measurement uncertainty.
SOUTH TEXAS - UNITS 1 & 2 3/4 2-11 Unit 1 - Amendment No. 6+;97,108 Unit 2 - Amendment No. 50;04,95 j
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P_0VER DISTRIBUTION LIMITS RAtts HEAT FLUX HOT CHANNEL FACTOR and NUCLEAR ENTRALPY RISE HOT CHANNEL FALTOR (Continued)
When an F measurement is taken, an allowance for both experimental error g
and manufacturing tolerance must be made. An allowance of 5% is appropriate for a full-core map taken with the Incore Detector Flux Mapping Systes, and a 3% allowance is appropriate for manufacturing tolerance.
The Radial Peaking Factor, F (Z), is sensured periodically to provide assurancethattheHotChannelFa,ctorgq(2),remainswithinitslimit.
The F
limit for RATED THERMAL POWER (F
) as provided in the Core Operating L lts Report (COLR) per Specificati 6.9.1.6 was determined from expected power control manuevers over the full range of burnup conditions in the core.
3/4.2.4 OUADRANT POWER TILT RATIO The QUADRANT POWER TILT 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 STARTUP testing and periodically during power operation.
The limit of 1.02, at which corrective action is required and linear heat generation rate protection with x y plane power, provides DNS tilts. A limit of 1.02 was selected to provide an allowance for the uncertainty associated with the indicated power tilt.
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l The 2-hour time allowance for operation with a tilt condition greater i
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 sargin for uncertainty on F i
g s 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 incere detectors are used to confire that the normalized symmetric power distribution is consistent with the QUADRANT POWER TILT RATIO. The incere detector monitoring is done with a full incore flux sap or two sets of four s tric thimbles. The two sets of four symmetric thimbles is a unique set of el ht detector locations.
These locations are C-8 E-5, E-11, H-3, H-13 L-5, L-11, N-8.
3/4.2.5 DNB PARAMFTgt),
The limits on the DNS-related parameters assure that each of the parameters are maintained within the normal staa -state envelope of operation assumed in
~
the transient and accident analyses.
he limits are consistent with the SOUTH TEXAS - UNITS 1 & 2 8 3/4 2-5 Unit 1 - Amendment No. 27 Unit 2 - Amendment No. 37 et Ws +
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4 POWER DISTRIBUTION LIMITS BASES 3/4.2.5 DNB DARAMETERS (Continued) initial FSAR assumptions and have been analytically demonstrated adequate to maintain a minimum DNBR of greater than or equal to the design limit throughout each analyzed transient.
The T.,, value of 598'F and the pressurizer pressure value of 2189 psig are analytical values.
The readings from four channels will be averaged and then adjusted to account for measurement uncertainties before comparing with the required limit. The flow requirement (392,300 gpm) includes a measurement uncertainty of 2.8%
Technical Specificatbn 3.2.5 provides for an alternate minimum measured Reactor Coolant System flow limit consistent with plugging up to 10% of steam generator tubes and Departure from Nucleate Boiling requirements. When using the alternate minimum flow limit, the T., limit is reduced to 595'F for Reactor Coolant System flow no less than 380,500 gpm.
Setpoint and cc.nstant values for OPAT and OTAT are also revised accordingly when this alternate mode of operation is entered.
The RCS flow measurement uncertainty of 2.8% bounds the precision heat balance and the elbow tap Ap measurement methods. The c' bow tap Ap measurement uncertainty presumes that elbow tap Ap measurements are obtained from either ODPS or the plant process computer. Based on instrument uncertainty assumptions, RCS flow measurements using either the precision heat balance or the elbow tap Ap measurement methods are to be performed at greater than or equal to 90% RTP at the beginning of a new fuel cycle. The elbow tap Ap RCS flow measurement methodology is described in ST-HL-AE-5707, " Proposed Amendment to Technical Specification Table 2.2-1 and 3/4.2.5 for Reactor Coolant System Flow Monitoring - Revised," dated August 6,1997, and in ST-HL-AE-5752," Amended Response to Request for Additional Information on the Proposed Elbow Tap Technical Specification Change (Table 2.2-1 and Section 3/4.2.5)," dated September 18,1997.
The 12-hour periodic surveillance of these parameters through instrument readout is sufficient to ensure that the parameters are restored within their limits following load changes and other expected tmnsient operation.
SOUTH TEXAS - UNITS 1 & 2 B 3/4 2-6 Unit 1 - Amendment No. 6tr97,108 Unit 2 - Amendment No. 5@e495
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