ML20248B948
| ML20248B948 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 07/31/1989 |
| From: | Hebdon F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20248B954 | List: |
| References | |
| NUDOCS 8908090381 | |
| Download: ML20248B948 (18) | |
Text
,
1 1
ff og UNITED STATES y
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p, NUCLEAR REGULATORY COMMISSION
$ 3',*
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o, p(/ 1 WASHINGTON. D. C. 20555 s *..+p HOUSTON LIGHTING & POWER COMPANY CITY PUBLIC SERVICE BOARD OF SAN ANTONIO l
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CENTRAL POWER AND LIGHT COMPANY CITY OF AUSTIN, TEXAS DOCKET NO. 50-498 SOUTH TEXAS PROJECT, UNIT 1 AMENDRENT TO FACILITY OPERATING LICENSE Amendment No. 9 License No. NPF-76 2.
The Nuclear Regulatory Comission (the Commission) has fcund that:
A.
The application for amendment by Houston Lighting & Power Company * (HL&P) acting on behalf of itself and for the City Public Service Board of San Antonio (CPS), Central Power and Light Ccmpany (CPL), and City of Austin, Texas (C0A) (the licensees) dated June 1,1989, 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 20 CFR Chapter I; B.
The facility will operate in conformity with the application, as arrended, the provisions of the Act, and the rules and regulations l
of the Comission; 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 ectordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
B90B090381 890731 P"
PDR ADOCK 0500049s[F P
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- Houston Lighting & Power Company is authorized to act fcr the City Public Service Board of San Antonio, Central Power and Light Company and City of Austin, Texas and has exclusive responsibility and centrol over the physical construction, operation and maintenance of the facility.
o
[* i 1
2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. NPF-76 is hereby amended to read as follows:
j 2.
Technical Specifications l
The Technical Specifications contained in Appendix A, as revised i
through Amendment No. 9, 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 end the Environmental Protection Plan.
3.
The license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSIDH nNdx<
b-Frederick J. He don, Director Project Directorate - IV Division of Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
July 31, 1989
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UNITED STATES j
NUCLEAR REGULATORY COMMISSION t
j WASHINGTON, D. C. 20555 l
HOUSTON LIGHTING 3 POWER COMPANY
)
CITY PUBLIC SERVICE BOARD OF SAN ANTONIO CENTRAL POWER AND LIGHT COMPANY l
CITY OF AUSTIN, TEXAS DOCKET NO. 50-499 i
SOUTH TEXAS PROJECT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment Ho. 1 i
License No. NPF-80 1
l '.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Houston Lighting 8 Pcwer Company * (HL&P) acting on behalf of itsclf and for the City Public Service Board of San Antonio (CPS), Central Power and i
Light Company (CPL), and City of Austin, Texas (C0A) (the j
licer. sees) dated June 1,1989, complies with the standards and 1
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 provisions of the Act, and the rules and regulations of the Commissior.;
i C.
TL2 ~ is reasonable assurance:
(1) that the activities authorized by this amendment can be conducted without endangering the health l
and safety of the public, and (ii) th3t 59th activities will be l
ccnducted in compliance with the Crnmission's regulations; l
D.
Thc issuance of this license amendment will not be inimical to the ennmon defense and security or to the health and safety of the public; q
and j
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 I
L of the Commission's regulations and all applicable requirements have been satisfied.
1 l
- Houston Lighting & Power Company is authorized to act for the City Public l
Service Board of San /atenio, Central Power and Light Company and City of 4
Aust%, Texas and has cyclusive responsibility and control over the physical construction, cpration and maintenance of the facility.
q L
J
' 2.-
Accordingly, the license is amended by changes to the Technical Specifi-cations 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 Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 1
, and the Env honmental Protection Plan 1
contained in Appendix D, t hereby incorporated in the license.
The licensee shall operate the facility in accordance with the l'
Technical Specifications and the Environmental Protection Plan.
3.
The license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY C0!iMISS10t!
[b.
Frederick J. Hebdon, Director Project Directorate - IV Division of Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reector Regulation
Attachment:
Changes to the Technical SpecifictLions Date of Issuance:
July 31, 1989
__-..--._-_-.-._a__-_--__-
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l
' ATTACHMENT TO LICENSE AMENDMEfr. NGS. 9 AND 1 l
FACILITY OPERATING LICENSE N05. NPF-76 AND NPF-80 l
)
DOCKET NOS. 50-498 AND 50-499 Replace the following pages of the Appendix A Technical Specifications with
'the attached pages. The revised pages are identified by Amendment number and contain vertical lines. indicating the areas of change. The corresponding overleaf pages are also provided to maintain document completeness.
Remove Insert i
i iv iv XiX XiX 1-2 1-2 3/4 1 '23 3/4 1-23 3/4 1-24 3/4 2 3/4 2-1 6-20 6-20 kmw__-,-,----------__
___-._a-,
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f;'
Je" ' '.
y I:
3 INDEX
.1.0 DEFINITIONS j '
SECTION PAGE 11 f
1.1' ACTI0N........................................................
1-1 1.2 ACTUATION LOGIC TEST...........................................
1-1 1.3
' ANALOG CHANNEL OPERATIONAL TEST..............................
1-1 1.4 AXIAL FLUX DIFFERENCE...............................
1-1 1.5. CHANNEL CALIBRATION..........................................
1-1.
1.6', CHANNEL. CHECK.................................
1 -
1~ 7 CONTAINMENT INTEGRITY.........................................
1-2
- 1. 8 CONTROLLED LEAKAGE............................................
~1-2 1.S~
CORE ALTERATIONS......................-........................
1-2
- 1. 9a CORE OPERATING LIMITS REP 0RT..................................
1-2 1.10.~ DIGITAL CHANNEL OPERATIONAL TEST...................
1-2' 1.11 DOSE EQUIVALENT.I-131..........................................
1.
1.12 E-AVERAGE DISINTEGRATION ENERGY...............................
1-3
. 1. 3 ENGINEERED SAFETY FEATURES RESPONSE TIME......................
1-3 3.14 FREQUENCY N0TATION............................................
1-3 1.15' GASEOUS WASTE PROCESSING SYSTEM...............................
1-3 1.16 IDENTIFIED LEAKAGE............................................
1-3 1.17 MASTER RELAY, TEST.............................................
1-4 1.18: MEMBER (S) DF THE PUCLIC..................
1-4 1.19 0FFSITE DOSE CALCULATION MANUAL...............................
1-4 1.20 'OP E RAB L E - OPE RABI LITY.......................................
1-4 1.21 OPERATIONAL MODE - M0DE..................................
1-4 1.22 PHYSICS TESTS.................................................
1-4 1.23 PRESSURE BOUNDARY LEAKAGE.....................................
1-4 1.24 PROCESS CONTROL PR0 GRAM.....................
1-5
' 1.25 PURGE - PURGING...............................................
1-5 1.26 QUADRANT POWER TILT RATI0.....................................
1-5 1.27 RATED THERMAL P0WER...........................................
1-5 SOUTH TEXAS - UNITS 1 & 2 i
Unit I - Amendment No. 9 Unit 2 - Amendment foo. I h__mm.m._.m
_-______u-.u.
INDEX DEFINITIONS SECTION L.
PAGE 1
l 1.28 REACTOR TRI) SYSTEM RESPONSE TIME.............................
1-5 1.29 REPORTABLE EVENT..............................................
1-5 1.30 SHUTDouN MARGIN....................t..........................
1-5 l
1.31 SITE B0VNDARY..................................................
1-6 1.32 SLAVE RELAY TEST..............................................
1-6 1.33 SOLIDIFICATION................................................
1-6 l
-1.34 SOURCE CHECK..................................................
1-6 1.35 STAGGERED TEST BASIS..........................................
1-6 1.36 THERMAL P0WER............................................
1-6 1.37 TRIP ACTUATING DEVICE OPERATIONAL TEST........................
1-6 1.38 UNIDENTIFIED LEAKAGE..........................................
1-6 1.39 UNRESTRICTED AREA.............................................
1-7 1.40 VENTING.......................................................
1-7 TABLE 1.1 FREQUENCY N0TATION.......................................
1-8 TABLE 1.2 OPERATIONAL M0 DES........................................
1-9 a
l I
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i SOUTH TEXAS - UNITS 1 & 2 11 l
^
INDEX 2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS-SECTION' PAGE 2.1 SAFETY LIMITS 2.1.1 ~ REACTOR C02E..................................................
2-1 2.1.2 REACTOR COOLANT SYSTEM PRESSURE...............................
2-1 FIGURE 2.1-1 REACTOR CORE SAFETY LIMIT - FOUR LOOPS IN OPERATION....
2-2 2.2 LIMITING SAFETY SYSTEM SETTINGS 2.2.1 REACTOR TRIP SYSTEM INSTRUMENTATION SETP01NTS.................
2-3 TABLE 2.2-1 REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS......
2-4 BASES SECTION PAGE 2.1 SAFETY LIMITS 2.1.1 REACTOR C0RE.................................................
B 2-1 2.1.2 REACTOR COOLANT SYSTEM PRESSURE..............................
B 2-2 P
2.2 LIMITING SAFETY SYSTEM SETTINCS 2.2.1 REACTOR TRIP SYSTEM INSTRUMENTATION SETPOINTS................
2 2-3 SOUTH TEX 83 - UNITS 1 & 2 iii
i i
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION
_PAGE 3/4.0 APPLICABILITY................................................
3/4 0-1 3/4.1 REACTIVITY C04 TROL SYSTEMS 3/4.1.1 B0 RATION 40NTROL Shutdown Margin - T,yg 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 Margin - T,yg Less Than or Equal to 200 F........
3/4'l-4' FIGURE 3.1-2 REQUIRED SHUTDOWN MARGIN VER5US RCS CRITICAL BORON CONCENTRATION (MODE S)...............
3/4 1-5 Moderator Temperature Coefficient.........................
3/4 1-6 Minimum Temperature for Criticality.......................
3/4 1-8 3/A 1. 2 B0 RATION SYSTEMS Flow Paths - Shutdown.....................................
3/4 1-9 clow Paths - Operating....................................
3/4 1-10 Chart,'ng Pumps - Shutdown.................................
3/4 1-11 Charging Pumps - Operating.......................
?/4 1-12 Borated Water Sources - Shutdown..........................
3/4 1-13 Borated Water Sources - Operating........................
3/4 1-14 1
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 R0D....................
3/4 1-18 Position Indication Systems -
Operating...................
3/4 1-39 Position Indication Systems - Shutdown...................
3/4 1-20 Rod Drop Time................
3/4 1-21 i
Shutdown Rod Insertion Limit..............................
3/4 1-22 Control Rod Insertion 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.I
)
i.i INDEX ADMINISTRATIVE CONTROLS i
1 4
l SECTION PAGE i
6.5.2~ NUCLEAR SAFETY REVIEW BOARD (NSRB)
H Function...................................................
6-9 Composition............................
6-10 Alternates...........................
6-10 Consultants................................................
6 Meeting Frequency..........................................
6 Quorum.....................................................
6-10 Review.....................................................
6-10 Audits.....................................................
6 '
Records....................................................
6-12
' 6. 5. 3 TECHNICAL REVIEW AND CONTROL Activities................................................
6-12 6.6 REPORTABLE EVENT ACTI0N......................................
6-13 i
6.7 SAFETY LIMIT VIOLATION.......................................
6-13 6.8 PROCEDURES AND PR0 GRAMS......................................
6-14 1
6.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE REP 0RTS............................................
6-16 Startup Report.............................................
6-16 Annual Reports.............................................
6-17 j
Annual-Radiological Environmental Operating Report.........
6-17 Semiannual Radioactive Effluent Release Report.............
6-18 j
Monthly Operating Reports..................................
6-20 Core Operating Limits Report...............................
6-20 i
1 6.9.2 SPECIAL REP 0RTS............................................
6-20 j
6.10 RECORD RETENTION............................................
6-21 1
I i
SOUTH TEXAS - UNITS 1 & 2 xix Unit 1 - Amendment No. 9 Unit 2 - Amendment No. 1 l
E' Y
1 e
INDEX ADMINISTRATIVE CONTROLS SECTION PAGE.
6.11 RADIATION PROTECTION PR0 GRAM................................
6-22
- 6.12 HIGH-RADIATION AREA........................................
6-22 6.13 PROCESS CONTROL PROGRAM (PCP)...............................-
6-23 6.14 0FFSITE DOSE CALCULATION MANUAle (0DC,Q.................. c...
6-23
- 6.15 MAJOR CHANGES T0 LIQUID,-GASEGUS, AND SOLID RADWASTE TREATMENT SYSTEMS..................................
6-24
- SOUTH TEXAS - UNITS 1 & 2 xx
l.
t l
e 1.0 DEFINITIONS i_
The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications.
ACTION I
1.1 ACTION shall be that part of a Technical Specification that prescribes remedial measures required under designated conditions.
ACTUATION LOGIC TEST 1.2 An ACTUATION LOGIC TEST shall be the application of various simulated input combinations in conjunction with each possible interlock logic state and verification of the required logic output.
The ACTUATION LOGIC TEST shall include a continuity check, as a minimum, of output devices.
ANALOG CHANNEL OPERATIONAL TEST 1.3 An ANALOG CHANNEL OPERATIONAL TEST shall be the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY of alarm, interlock and/or trip functions.
The ANALOG CHANNEL OPERATIONAL TEST shall include adjustments, as necessary, of the alarm, inter-lock and/or Trip Setpoints so that the Setpoints are within the required range and accuracy.
AXIAL FLUX DIFFERENCE 14 AXIAL FLUX DIFFERENCE shall be the difference in normalized flux signals between the top and bottom halves of a 2-section excore neutron detector.
CHANNEL CALIBRATION 1.5 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel so that it responds within the required range and accuracy to known values of input.
The CHANNEL CALIBRATION shall encompass the entire channel including the sensors and alarm, interlock, and/or trip functions and may be performed by any series of sequential, overlapping, or total channel steps i
so that the entire channel is calibrated.
1 CHANNEL CHECK
- 1. 6 A CHANNEL CHECK shall be the qualitative assessment of channel behavior i
during operation by observation.
This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.
l 1
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SOUTH TEXAS - UNITS 1 & 2 1-1 i
DEFINITIONS CONTAINMENT INTEGRITY 1.7 CONTAINMENT INTEGRITY shall exist when:
All penetrations required to be closed during accident conditions a.
are either:
1)
Capable of being closed by an OPERABLE containment automatic isolation valve syste:n, or 2)
Closed by manual valves, blind flanges, or deactivated automatic valves secured in their closed positions, except as provided in Specification 3.6.3.
b.
All equipment hatches are closed and sealed, Each air lock is in compliance with the requirements of Specifica-c.
tion 3.6.1.3, d.
The containment leakage rates are within the limits of Specific'a-tion 3.6.1.2, and The sealing mechanism associated with each penetration (e.g., welds, e.
bellows, or 0-rings) is OPERABLE.
CONTROLLED LEAKAGE 1.8 CONTROLLED LEAKAGE shall be that seal water flow supplied to the reactor coolant pump seals.
1.9 CORE ALTERATIONS shall be the movement or manipulation of any component within the reactor pressure vessel with the vessel head removed and fuel in the vessel.
Suspension of CORE ALTERATION shall not preclude completion of movement of a component to a safe conservative position.
CORE OPERATING LIMITS REPORT 1.9a The CORE OPERATING LIMITS REPORT is the unit-specific document that provides core operating limits for the current operating reload cycle. These cycle-specific core operating limits shall be determined for each reload cycle i
in accordance with Specification 6.9.1.6.
Plant operation within these core operating limits is addressed within the individual Specifications.
DIGITAL CHANNEL OPERATIONAL TEST 1.10 A DIGITAL CHANNEL OPERATIONAL TEST shall consist of injecting simulated process data where available or exercising the digital computer hardware using I
data base manipulation to verify OPERABILITY of alarm, interlock, and/or trip functions.
I DOSE EQUIVALENT I-131 1.11 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcurie / gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, 1~132, 1-133, I-134, and I-135 actually present.
The thyroid dose conversion factors.used for this calculation shall be those listed in Teble E-7 of NRC Regulatory Guide 1.109, Revision 1, October 1977.
SOUTH TEXAS - UNITS 1 & 2 1-2 Unit 1 - Amendment No. 9 i
Unit 2 - Amendment No.I
p
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REACTIVITY CONTROL SYSTEMS CONTR,0L ROD INSERTION LIMITS LIMITING CONDITION FOR OPERATION 3.1.3.6 The control banks shall be limited in physical insertion as specified I
in the CORE OPERATING LIMITS REPORT.
l APPLICABILITY:
MODES 1* and 2* **.
ACTION:
With the control banks inserted beyond the above insertion limits, except for surveillance testing pursuant to Specification 4.1.3.1.2:
Restore the control banks to within the limits within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, or a.
b.
Reduce THERMAL POWER within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to less than or equal to that fraction of RATED THERMAL POWER which is allowed by the bank posi-tion using the insertion limits specified in the CORE OPERATING LIMITS REPORT, or c.
Be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SUM EI1LM CE RE0VIREMENTS 4.1.3.6 The position of each control bank shall be determined to be within the insertion limits at least once per 12 haurs except during time intervals when the rod insertion limit monitor is inoperable, then verify the individual rod positions at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
- See Special Test Exceptions Specifications 3.10.2 and 3.10.3.
- With K,ff greater than or equal to 1.
SOUTH TEXAS - UNITS 1 & 2 3/4 1-23 Unit I - Amendment No. 9 Unit 2 - Amendment No.1 i
i 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE LIMITING C0]DITION FOR OPER4] ION j
l 3.2.1 The indicated AXIAL FLUX DIFFERENCE (AFD) shall be maintained within the
{
target band (flux difference unitr,) about the target flux difference as specified in the CORE OPERATING LIMITS REPORT.
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 Operatien Limits of Figure 3.2-1 and the cumu-lative penalty deviation time does not exceed I hour during the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
1 The indicated AFD may deviate outside the above required target band at greater than 15% but less than 50% of RATED THERMAL POWER provided the cumulative penalty deviation time does not exceed 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> during the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
APPLICABILITY:
MODE 1, above 15% of RATED THERMAL POWER.*
ACTION:
\\
a.
With the indicated AFD outside of the above required target bar i and with THERMAL POWER greater than or equal to 90% of RATED THERMAt.
)
POWER, within 15 minutes either:
{
1 1.
Restore the indicated AFD to within the target band limits, or i
l 2.
Reduce THERMAL POWER to less than 90% of RATED THERMAL POWER.
b.
With the indicated AFD outside of the above required target band for more than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of cumulative penalty deviation time during the j
previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or outside the Acceptable Operation Limits of Figure 3.2-1 and with THERMAL POWER less than 90% but equal to or greater than 50% of RATED THERMAL POWER, reduce:
1.
THERMAL POWER to less than 50% of RATFD THERMAL POWER within 30 minutes, and 2.
The Power Range Neutron Flux * ** - High Setpoint to less than or l
equal to 55% 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 />, l
- See Special Test Exceptions Specification 3.10.2.
- Surveillance testing of the Prwer 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 of Figure 3.2-1.
A total of 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> operation i
may be accumulated with the AFD outside of the above required target band during testing without penalty deviation.
SOUTH TEXAS - UNITS 1 & 2 3/4 2-1 Unit 1 - Amendment No. 9 Unit 2 - Amendment No.1
POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION y
ACTION (Continued) c.
With the indicated AFD outside of the above required target band for i
more than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of cumulative penalty deviation time during the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and with THERMAL POWER less than 50% but greater than 15% of RATED THERMAL POWER, the THERMAL POWER shall not be increased equa! to or greater than 50% of RATED THERMAL POWER until the indicated AFD is within the above required target band.
SURVEILLANCE REbgIREMENTS I
4.2.1.1 The indicated AFD shall be determined to be within its limits during POWER OPERATION above 15% of RATED THERMAL POWER by:
a.
Monitoring the indicated AFD for each OPERABLE execre 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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and at least once per 30 minutes thereafter, 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.
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:
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 b.
One half minute penalty deviation for each 1 minute of POWER OPERATION outside of the target band at THERMAL POWER levels between 15% and 50% of RATED THERMAL POWER.
4.2.1.3 The target flux difference of each OPERABLE excore channel shall be determined by measurement at least once per 92 Effective Full Power Days.
The provisions of Specification 4.0.4 are not applicable.
4.2.1.4 The target flux difference shall be updated at least once per 31 Effective Full Power Days by either determining che target flux difference SOUTH TEXAS - UNITS 1 & 2 3/4 2-2
l l
ADMINISTRATIVE CONTROLS SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT (Continued) in Appendix B shall be supplemented with three additional categories:
class of solid wastes (as defined by 10 CFR Part 61), type of container (e.g., LSA, I
Type A, Type B, Large Quantity) and SOLIDIFICATION agent or absorbent (e.g.,
cement, urea formaldehyde).
The Semiannual Radioactive Effluent Release Report to be submitted within 60 days after January 1 of each year shall include an annual summary of hourly meteorological data collected over the previous year.
This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured),
or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability.* This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents re_ leased from the unit or station during the previous calendar year.' This same. report shall also include an assessment of the radiation doses from radioactive.
liquid and gaseous effluents to HEMBEP.S OF THE PUBLIC due to their activities inside the SIiE BOUNDARY (Figures 5.1-3 and 5.1-4) during the report period.
All assumptions used in making these assessments, i.e., specific activity, exposure time, and location shall be included in these reports.
The meteorological conditions concurre,nt witn the time of release of radioactive materials in gaseous effluents, as determined by sampling frequency and measurement, shall be used for determining the gaseous pathway doses.
The assessment of radiation doses shall-be performed in accordance with the methodology and parameters in I
the OFFSITE DOSE CALCULATION MANUAL (0DCM).
The Semiannual Radioactive Effluent Release Report to be submitted within 60 days after January 1 of each year shall also include an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation, for the previous calendar year to show conformance with 40 CFR Part 190, " Environmental Radiation Protection Standards for Nuclear Pcwer Operation." Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1, 0:.tober 1977.
The Semiannual h3diosctive Effluent Release Reports shall include a list and description of unplanned releases from the site to UNRESTRICTED ARCAS of radioactive materials in gaseous and liquid effluents made during the reporting period.
The Semiannual Radioactive Effluent Release Reports shall include any changes made during the reporting period to the PROCESS CONTROL PROGRAM and the ODCM, pursuant to Specifications 6.13 and 6.14, respectively, as well as any major change to Liquid, Gaseous, or Solid Radwaste Treatment Systems 3
pursuant to Specification 6.15.
It shall also include a listing of new loca-1 tions for dose calculations and/or environmental monitoring identified by the i
Land Use Census pursuant to Specification 3.12.2.
- In lieu of submission with the Semiannus1 Radioactive Effluent Release Report, f
the licensee has the option of retaining this summary of required meteoro-logical data on site in a file that shall be provided to the NRC upon request.
I SOUTH TEXAS - UNITS 1 & 2 6-19 i'
w i
ADMINISTRATIVE CONTROLS SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT (Continued)
The Semiannual Radioactive Effluent Release Reports shall also include the followinn:
an explanation as to why the inoperability of liquid or gaseous effluent 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 events leading to liquid holdup tanks or gas storage tanks exceeding the limits of Specification 3.11.1.4 or 3.11.2.6, respectively.
MONTHLY OPERATING REPORTS
- 6. 9.1. 5 Routine reports of operating statistics and shutdown experience, 1
including documentation of all challenges to the PORVs or safety valves, shall be submitted on a monthly basis to the Director, Office of Resource Management, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a copy to the Regional Administrator of the Regional Office of the NRC, no.later then the 15th of each month following the calendar month covered by the report.
CORE OPERATING LIMITS REPORT 6.9.1.6 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle.
The CORE OPERATING LIMITS REPORT shall be maintained available in the Control Room.
The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by NRC in WCAP-8403, " Power Distribution and Load Following Procedures," 1974 and in WCAP-9273-A, " Westinghouse Reload Safety Evaluation Methodology," 1985 (for 1
Control Bank Irsertion Limits).
The core operating limits shall be determined so that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydrau'.ic limits, ECCS limits, nuclear limits such as shutdown margin, and transient an-t accident analysis limits) of the safety analysis are met.
The CORE OPERATINb !IMITS REPORT, including any mid-cycle revisions or supplements thereto, snali ba provided within 30 days of their implementation, for each reload cycle, to the N E in accordance with 10 CFR 50.4.
SPECIAL REPORTS 6.9.2 Special reports shall be subaiitted to the Regional Administrator of the Regional Office of the NRC within the time period specified for each report.
SOUTH TEXAS - UNITS 1 & 2 6-20 Unit I - Amendment No.9 Unit 2 - Amendment No.I