ML20212C273
| ML20212C273 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 09/13/1999 |
| From: | Gramm R NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20212C277 | List: |
| References | |
| NUDOCS 9909210204 | |
| Download: ML20212C273 (21) | |
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4 UNITED STATES g
j NUCLEAR REGULATORY COMMISSION
,2 WASHINGTON, D.C. 20565 4001 49.....,o STP NUCLEAR OPERATING COMPANY DOCKET NO. 50-499 SOUTH TEXAS PROJECT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.104 License No. NPF 80 i
1.
The Nuclear Regulatory Commission (the Commission) has found that:
1 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 June 7,1999, complies with the standards and requirements of the Atomic 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 l
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.
l l
l 9909210204 990913 PDR ADOCK 05000498 P
I l 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 The Technical Specifications contained in Appendix A, as revised through Amendment No. 104, 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 and shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Lak /k 4"
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:
September 13, 1999 t
t
ATTACHMENT TO LICENSE AMENDMENT NOS.116 AND 104 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 INSERT 2-3 2-3 2-4 2-4 2-5 2-5 2-6 2-6 B 2-3 8 2-3 B 2-4 B 2-4*
3/4 3-15 3/4 3-15*
3/4 3-16 3/4 3-16 3/4 3-29 3/4 3-29 3/4 3-30 3/4 3-30 3/4 3-31 3/4 3-31 3/4 3-32 3/4 3-32 3/4 3-33 3/4 3-33 3/4 3-34 3/4 3-34 3/4 3-35 3/4 3-35 3/4 3-36 3/4 3-36 B 3/4 3-1 B 3/4 3-1 B 3/4 3-2 B 3/4 3-2 l
' Overleaf pages provided to maintain document completeness. No changes on these l
pages.
n 1
1 l
SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 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 channelin Table 3.3-1.
ACTION:
a.
With a Reactor Trip System Instrumentation or Interlock Setpoint less conservative than the value shown in the Trip Setpoint column but more conservative than the value shown in the Allowable Value column of Table 2.2-1, adjust the Setpoint consistent with the Trip Setpoint value.
b.
With the Reactor Trip System Instrumentation or Interlock Setpoint less conservative than the value shown in the Allowable Value column of Table 2.2-1, declare the l
channel inoperable and apply the applicable ACTION statement requirement of Specification 3.3.1 until the channel is restored to OPERABLE status with its Setpoint adjusted consistent with the Trip Setpoint value.
1 SOUTH TEXAS - UNITS 1 & 2 2-3 UNIT 1 - Amendment No.116 UNIT 2 - Amendment No.104 i
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F 2.2 LIMITING SAFETY SYSTEM SETTINGS BASES 2.2.1 REACTOR TRIP SYSTEM INSTRUMENTATION SETPOINTS The Reactor Trip Setpoint Limits specified in Table 2.2-1 are the nominal values at which the Reactor trips are set for each functional unit. The Trip Setpoints have been selected to ensure that the core and Reactor Coolant System are prevented from exceeding their safety limits during normal operation and design basis anticipated operational occurrences and to assist the Engineered Safety Features Actuation System in mitigating the consequences of accidents. The Setpoint for a Reactor Trip System or interlock function is considered to be adjusted consistent with the nominal value when the "as-measured" Setpoint is within the band allowed for calibration accuracy.
To accommodate the instrument drift assumed to occur between operational tests and the accuracy to which Setpoints can be measured and calibrated, Allowable Values for the Reactor Trip Setpoints have been specified in Table 2.2-1. Operation with Setpoints less conservative than the Trip Setpoint but within the Allowable Value is acceptable since an allowance has been made in the safety analysis to accommodate this error.
I The methodology to derive the Trip Setpoints is based upon combining all of the uncertainties in the channels. Inherent to the determination of the Trip Setpoints are the magnitudes of these channel uncertainties. Sensors and other instrumentation utilized in these channels are expected to be capable of operating within the allowances of these uncertainty magnitudes. Rack drift in excess of the Allowable Value exhibits the behavior that the rack has not met its allowance. Because there is a small statistical chance that this will happen, an infrequent excessive drift is expected. Rack or sensor drift, in excess of the allowance that is more than occasional, may be indicative of more serious problems and should warrant further investigation.
I l
SOUTH TEXAS - UNITS 1 & 2 B 2-3 Unit 1 - Amendment No.116 Unit 2 - Amendment No.104
)
l.
1
[
l LIMITING SAFETY SYSTEM SETTINGS RASES REACTOR TRIP SYSTEM INSTRUMENTATION SE7 POINTS (Continued)
The various Reactor trip circuits automatically open the Reactor trip l
breakers whenever a condition monitored by the Reactor Trip System reaches a preset or calculated level.
In addition to redundant channels and trains, the design approach provides a Reactor Trip System which monitors numerous system i
l variables, therefore providing Trip System functional diversity.
The functional l
capability at the specified trip setting is required for those anticipatory or l
diverse Reactor trips for which no direct credit was assumed in the safety analysis to enhance the overall reliability of the Reactor Trip System.
The Reactor Trip System initiates a Turbine trip signal whenever Reactor trip is initiated. This prevents tha reactivity insertion that would otherwise result i
from excessive Reactor Coolant System cooldown and thus avoids unnecessary actuation of the Engineered Safety Features Actuation System.
The Reactor Trip System includes manual Reactor trip capability.
Power Range, Neutron Flux l
In each of the Power Range Neutron Flux channels there are two independent i
bistables, each with its own trip setting used for a High and Low Range trip setting.
The Low Setpoint trip provides protection during suberitical and low power operations to mitigate the consequences of a power excursion beginning l
from low power, and the High Setpoint trip provides protection during power l
oparations to mitigate the consequences of a reactivity excursion from all j
pou r levels.
i The Low Setpoint trip may be manually blocked above P-10 (a power level of approximately 10% of RATED THERMAL POWER) and is automatically reinstated l
below the P-10 Setpoint.
i Power Range Neutron Flux, High Rates l
The Power Range Positive Rate trip provides protection against rapid flux increases which are characteristic of a rupture of a control rod drive housing.
Specifically, this trip complements the Power Range Neutron Flux High and Low trips to ensure that the criteria are met for rod ejection from mid power.
SOUTH TEXAS - UNITS 1 & 2 B 2-4 Unit 1 - Amendment No. 34 Unit 2 g n g n g o. 25 L
I TABLE 4.3-1 (Continued)
TABLE NOTATIONS (Continued) l (10)
Setpoint verification is not applicable.
(11)
The TRIP ACTUATING DEVICE OPERATIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip attachments of the Reactor Trip Breakers.
(12)
OPERABILITY shall be verified by a check of memory devices, input accuracies, Boron Dilution Alarm setpoints, output values, and software functions.
-(13)
(Not used)
(14)
The TRIP ACTUATING DEVICE OPERATIONAL TEST shall independently verify l
the OPERABILITY of the undervoltage and shunt trip circuits for the Manual Reactor Trip Function. The test shall also verify the OPERABILITY of the Bypass Breaker trip circuit (s).
(15)
Local manual shunt trip prior to placing breaker in service.
(16)
Automatic undervoltage trip.
(17)
Each channel shall be tested at least every 92 days on a STAGGERED TEST BASIS.
l (18)
The surveillance frequency and/or MODES specified for these channels in Table 4.3-2 are more restrictive and, therefore, applicable.
l l
SOUTH TEXAS - UNITS 1 & 2 3/4 3-15 Unit 1 - Amendment No. U,67 Unit 2 - Amendment No. 48,56 050 2 1 1991
1 j
l i
INSTRUMENTATION l
3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.2 The Engineered Safety Features Actuation System (ESFAS) instrumentation channels and interlocks shown in Table 3.3-3 shall be OPERABLE with their Trip Setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3-4 and with RESPONSE TIMES as shown in l
Chapter 16 in the UFSAR.
1 1
APPLICABILITY: As shown in Table 3.3-3.
ACTION:
1 With an ESFAS Instrumentation or Interlock Trip Setpoint trip less conservative than a.
I the value shown in the Trip Setpoint column but more conservative than the value shown in the Allowable Value column of Table 3.3-4, adjust the Setpoint consistent j
with the Trip Setpoint value.
l b.
With an ESFAS Instrumentation or Interlock Trip Setpoint less conservative than the value shown in the Allowable Value column of Table 3.3-4, declare the channel l
inoperable and apply the applicable ACTION statement requirements of Table 3.3-3 until the channel is restored to OPERABLE status with its Setpoint adjusted consistent with the Trip Setpoint value.
I c.
With an ESFAS instrumentation channel or interlock inoperable, take the ACTION shown in Table 3.3-3.
l i
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SOUTH TEXAS - UNITS 1 & 2 3/4 3-16 Unit 1 - Amendment No. 60.116 Unit 2 - Amendment No. 30,104 l
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TABLE NOTATIONS Time constants utilized in the lead-lag controller for Steam Line Pressure-Low are T, 2 50 seconds and t, s 5 seconds. CHANNEL CAllBRATION shall ensure that these time constants are adjusted to these values.
The time constant utilized in the rate-lag controller for Steam Line Pressure-Negative Rate-High is greater than or equal to 50 seconds. CHANNEL CAllBRATION shall ensure that this time constant is adjusted to this value.
Deleted l
- Deleted
i or vent for pressure control, ALARA and respirable air quality considerations for personnel
- entry, i
I SOUTH TEXAS - UNITS 1 & 2 3/4 3-36 Unit 1 - Amendment No. 64,116 Unit 2 - Amendment No. 60,104 L
3/4.3 INSTRUMENTATION BASES 3/4.3.1 and 3/4.3.2 REAOTOR TRIP SYSTEM and ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION The OPERABILITY of the Reactor Trip System and the Engineered Safety Features Actuation System instrumentation and interlocks ensures that: (1) the associated ACTION and/or Reactor trip will be initiated when the parameter monitored by each channel or combination thereof reaches its Setpoint, (2) the specified coincidence logic is maintained, (3) sufficient redundancy is maintained to permit a channel to be out-of service for testing or maintenance, and (4) sufficient system functional capability is available from diverse parameters.
The OPERABILITY of these systems is required to provide the overall reliability, redundancy, and diversity assumed available in the facility design for the protection and mitigation of accident and transient cond.tions. The integrated operation of each of these systems is consistent with the assumptions used in the safety analyses. The Surveillance Requirements specified for these systems ensure that the overall system functional capability is maintained comparable to the original design standards. The periodic surveillance tests performed at the minimum frequencies are sufficient to demonstrate this capability. Specified surveillance intervals and surveillance and maintenance outage times have been determined in accordance with WCAP-10271, " Evaluation of Surveillance Frequencies and Out of Service Times for the Reactor Protection Instrumentation System,"
supplements to that report, and the South Texas Project probabilistic safety assessment (PSA). Surveillance intervals and out of service times were determined based on maintaining an appropriate level of reliability of the Reactor Protection System instrumentation.
The Engineered Safety Features Actuation System Instrumentation Trip Setpoints specified in Table 3.3-4 are the nominal values at which the bistables are set for each functional unit. A Setpoint is considered to be adjusted consistent with the nominal value when the "as measured" Setpoint is within the band allowed for calibration accuracy.
SOUTH TEXAS - UNITS 1 & 2 B 3/4 3-1 Unit 1 - Amendment No.116 Unit 2 - Amendment No.104
INSTRUMENTATION BASES REACTOR TRIP SYSTEM and ENGINEF. RED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION (Continued)
The methodology to derive the Trip Setpoints is based upon combining all of the uncertainties in the channels. Inherent to the determination of the Trip Setpoints are the magnitudes of these channel uncertainties. Sensor and rack instrumentation utilized in these channels are expected to be capable of operating within the allowances of these uncertainty magnitudes. Rack drift in excess of the Allowable Value exhibits the behavior that the rack has not met its allowance. Being that there is a small statistical chance that this will happen, an infrequent excessive drift is expected. Rack or sensor drift, in excess of the allowance that is more than occasional, may be indicative of more serious problems and should warrant further investigation.
l The measurement of response time at the specified frequencies provides assurance that the Reactor trip and the Engineered Safety Features actuation associated with each channel is completed within the time limit assumed in the safety analyses. No credit was taken in the analyses for those channels with response times indicated as not applicable. Response time may be demonstrated by any series of sequential, overlapping, or total channel test measurements provided that such tests demonstrate the total channel response time as defined. Sensor response time verification may be demonstrated by either: (1) in place, onsite, or offsite test measurements, or (2) utilizing replacement sensors with certified response times.
The Engineered Safety Features Actuation System senses selected plant parameters and determines whether or not predetermined limits are being exceeded. if they are, the signals are combined into logic matrices sensitive to combinations indicative of various accidents, events, and transients. Once the required logic combination is completed, the system sends actuation signals to those Engineered Safety Features components whose aggregate function best serves the requirements of the condition. As an example, the following actions may be initiated by the Engineered Safety Features Actuation System to mitigate the consequences of a steam line break or loss-of-coolant accident: (1) Safety injection pumps start, (2) Reactor trip, j
(3) feedwater isolation,(4) startup of the standby diesel generators,(5) containment spray pumps start and automatic valves position, (6) containment isolation, (7) steam line isolation, (8) Turbine trip, (9) auxiliary feedwater pumps start and automatic valves position, (10) reactor containment fan coolers. start, (11) essential cooling water pumps start and automatic valves position, (12) Control Room Ventilation Systems start, and (13) component cooling water pumps start and automatic valves position.
I SOUTH TEXAS - UNITS 1 & 2 B 3/4 3-2 Unit 1 - Amendment No.116 l
Unit 2 - Amendment No.104 l
i