ML20096F485
| ML20096F485 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 05/06/1992 |
| From: | Black S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20096F491 | List: |
| References | |
| NUDOCS 9205210197 | |
| Download: ML20096F485 (13) | |
Text
_ _ _ _ - _ _ _ _ _ _.
4
[
'o UNITED STATES l'
T,j NUCLEAR REGULATORY COMMISSION 3%
wAsm Not oN. o. c. rosss
\\'
/
HOUSTON LIGHTING & POWER COMPANY CITY PUBLIC SERVICE BOARD OF SAN ANTONIO CENTRAL POWER AND LIGHT COMPANY CITY OF AUSTIN. TEXAS DOCKET NO. 50-498
.5_0VTH TEXAS PROJECT. UNIT 1 q
AMENDMENT TO FACillTY OPERATING LICENSE Amendment No. 36 License No, NPF-76 1.
The Nuclear Regulatory Commission (the Commission) has found 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 Ani.onio (CPS), Central Power and Light Company (CPL), and City of Austin, Texas (C0A) (the licensees) dated August 23, 1991, as supplemented by letter dated January 24, 1992, complies with the tandards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regu W ions set forth in 10 CFR Chapter I; B.
The facility wi'il operate in conformity with the application, as i
amended, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance:
(1) 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 +.he 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.
- Houston Lighting & Power Company is autherized to act for the City Public Servu.e Board of San Antonio Cencral Power and Light Company and City of Austin, Texas and has exclusive respo. -ibility and control over the physical-construction, operation and maintenance of the facility.
9205210197 920506 l
PDR ADOCK 0D000498 P
k
- 2.
Accordingly, the license is amended by changes to the Technical Specifi--
cations as indicated in the atthcht ant to this license amendment and Paragraph 2.C.(2) of !acility Operating License No. NPF-76 is hereby amended to read as follows:
2.
Technical Soecifications The Technical Specification: contained in Appendix A, as revised through Amendment No. 36 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 licente amendment is effective as of its date of issuance and to be implemented within 7 days of its issuance, j
FOR THE NUCLEAR REGULA10RY COMMISSION--
l empsL 5
Suzanne. Black, Director Project Direcit rate IV-2 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: May 6, 1992 r
t w
= --
e -r6
-,--r-f w 1
![ge aso v
'o, UNITED STATES
+
) vu ',f NUCLEAR REGULATORY COMMISSION n
WASHINGTON, D C. 20555
/
HOUSTON LIGHTING & POWER COMPANi CITY PUBtIC SERVICE BOARD OF SAN ANTONIO CENTRAL POWER AND LIGHT COMPANY CITY Qf_ AUSTIN. TEXAS DOCKET NO. 50-499 SOUTH TEXAS PROJECT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE i
Amenument No. 27 License No NPF-80 i
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Houston Lighting & Power Company
- l (HLF) acting on behalf of itself and for the City Public Service Boata of San Antonio (CPS), Central Power rnd Light Company (CPL), and Ci+y of Austin, Texas (C0A) (the licensees) dated August 23, 1991, as supplemented by letter dated January 24, 1992, 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 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 Commirsion'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.
- Houston Lighting & Power Company is acumrized to act for the City Public Service Board of San Antonio, Central Power'and Light Company and City of Austin, Texas and has exclusive re:,ponsibility and control over the physical construction, operation and maintenance of the facility.
m
]
1
' 2.
Accordingly, the license is amended by changes to the Technical Specifi-l cations as indicated in the attachment to this license amendment and i
Paragraph 2.C.(2) of Facility Operating License No. NPF-80 is hereby amended to read as follows:
2.
Igchnical Specifications i
The Technical Specifications contained in Appendix A, as revised through Amendment No. 27, and the Environmental Protection Plan contained in Appendix B, are hereby in.orporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
The license amendrent is effective as of its date of issuance and to be implemented within 7 days of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION l
'A% o b. h cd Suzanne
. Bl'ck, Director Project Directorate IV-2 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation Attachmen+:
Changes to the Technical Specifications Date of Issuance: May 6,1992 l
V ATTACHMENT TO LICENSE AMENDMENT N05. 36 AND 27 f_A[J11TY OPERATING LI[11(SL1!QS. NPF-76 AND :4PF-80 A
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 centain vertical lines indicating the areas of change.
The corresponding overleaf p ges are also provided to maintain document completene,s.
REMOVE INSERT viii viii 3/4 4-3:
3/4 4-31 3/4 4-34 B 3/4 4-8 8 3/4 4-8 B 3/4 4-15 83/44-15 l
i i
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR 000LANI LOOPS AND COOLANT CIRCULATION Startup and Power O Hot Standby........peration.....:........................
3/4 4-1 Hot Shutdown..........................................
3/4 4-2 3/4 4-3 Cold Shutdown - Loc;; filied............................
3/4 4-5 Cold Shutdown - Loops Not Filled.........................
3/4 4 6 3/4.4.2 SAFETY VALVES Shutdown..............
Operating....................
3/4 4-7 3/4 4-8 3/4.4.3 PRESSURIZER..............................................
3/4 4-9 3/4.4.4 f.ELIEF VALVES............................................
3/4 4-10 3/4.4.5 STEAM GENERATORS.........................................
3/4 4-12 TABLE 4.4-1 HINIMUM NUMBER OF STEAM GENERATORS TO B, INSP DURING INSERVICE INSPEC7 ION.....................ECTED 3/4 4-17 TABLE 4.4-2 STEAM GENERATOR TUBEINSPECTION........................
3/4 4-18 3/4.4.t REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems.............
3/4 4-19 Operational Leakage...................
3/4 4-20 TABLE 3.4-1 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES..
3/4 4-22 3/4.4.7 CHEMISTRY................................................
3/4 t-23 TABLE 3.4-2 REACTOR COOLANT SYSTEl' CHEMISTRY LIMITS..............
3/4 4-24 TABLE 4.4-3 REACTOR COOLANT SYSTEM CH REQUIREMENTS................EMISTRY LIMITS SURVEILLANCE 3/4 4-25 3/4.4.8 SPECIFIC ACTIVITY........................................
3/4 4-26 FIGURE 3.4-1 DOSE EQUIVALENT I-131 REACTOR COOLANT SPECIFIC ACTIVITY LIMIT VERSUS PERCENT OF RATED THERMAL' POWER WITH "HE REACTOR COOLANT SPECIFIC ACTIVITY >l pCi/ gram DOSE EQUIVALENT I-131....................................
3/4 4-26 TABLE 4.4-4 REACTOR COOLANT SPECIFIC AC PR0 GRAM..................,.....TIVITY SAMPLE AND ANALYSIS 3/4 4-29 3/4.4.9 PRESSURE /TEliPERATURE LIMITS Reactor Coolant System...................................
3/4 4-31 FIGURE 3.4-2 REACTOR COOLANT SYSTEM HEATUP LIMITATIONS -
APPLICABLE UP TO 32 EFPY.................................
3/4 4-32 SOUTH TEXAS - UNITS 1 & 2 vii
9 ifffl LIM] TING COND1110NS FOR OPERATION At40 SURVElll ANCE REQUIREMENTS SECTION P_AE FIGURE 3.4-3 REACTOR COOLANT SYSTEM C00LDOWri LIMITATIONS -
APPLICABLE UP TO 32 EFPY 3/4 4-33 TABLE 4.4-5 (This table number not used) 3/4 4-34 Pressurizer.................
3/4 4-35 Overpressure Protection Systems.......
3/4 4-36 FIGURE 3.4-4 110MINAL MAXIMUM ALLOWABLE PORV SETPoll1T FOR THE COLD OVERTRESSURT SYSTEM 3/4 4-38 3/4.4.10 STRUCTURAL INTEGRITY 3/4 4-39 3/4.4.11 REACTOR VESSEL HLAD VEf1TS...........
3/4 4-40 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ACCUMULATORS 3/4 5-1 3/4.5.2 ECCS SUBSYSTEMS - T,,, GREi,.. ' THAN OR EQUAL TO 350*F 3/4 5-3 3/4.5.3 ECCS SUBSYSTEMS - T,,,LESS THAN 350*F 3/4 5-6 ECCS SUBSYSTEMS - T,, LESS thall OR EQUAL TO 200*F 3/4 5-8 3/4.5.4 (This specification number is not used)....
3/4 5-9 3/4.5.5 REEUELING WATER STORAGE TANK 3/4 5-10 3/4.5.6 RESIDUAL HEAT R MOVAL (RHR) SYSTEM 3/4 5-11 3/4.6 C0t4TAINMENT SYSIOS 3/4.6.1 PRIMARY CONTAINMENT Containment Integrity.............
3/4 6-1 Containment Leakage..............
3/4 6-2 Containment Air Locks.............
3/4 6-5 Internal Pressure...............
3/4 6-7 Air Temperature................
3/4 6-8 Containment Structural Integrity 3/4 6-9 Containment Ventilation System 3/4 6-12 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS Containment Spray System 3/4 6-14 Spray Additive System......
3/4 6-15 Containment Cooling System 3/4 6-17 o
SOUTH TEXAS UNITS 1 & 2 viii Unit 1 - Amendment No. 36
'i Unit 2 - Amendment No. 27
~
REACTOR COOLANT SYSliti 3/4.4.9 PRESSURE /TEMPERATVRE LIMlU REAC'9R COOLANT SYSTEM LIM 111NG CONDITION FOR OPERATION 3.4.9.1 The Reactor Coolant System (except the pressurizer) temperature and pressure shall be limited in accordance with the limit lines shown on Figures 3.4-2 and 3.4-3 during heatup, cooldown, criticality, and inservice leak and hydrostatic testing with:
- a. A maximum heatup of 100*F in any 1-hour period,
- b. A maximum cooldown of 100*F. in any 1-hour period, and
- c. A maximum tenperature change of less than or equal to 10*F in any 1-hour period during inservice hydrostatic and leak testing operations-above the heatup and cooldown limit curves.
api'llCABILITT: At all times.
ACTION:
With any of the above limits exceeded, restore the temperature and/or pressure to within the limit within.30 minutes; perform an engineering evaluation to determine the effects of the out-of-limit condition on the structural in-tegrity of the Peactor Coolant System; determine that the Reactor Coolant System remains acceptable for continued operation or be in at.least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and reduce the RCS T and pressure tt. less than 200*F and 500 psig, respectively, within the folTowing 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE RE0VIREMENTS 4.4.9.1.1 The Reactor Coolant System temperature and pressure shall ba determined to be within the limits at least once per 30 minutes during system heatup, cooldown, and inservice leak and hydrostatic. testing conditions.
l 4.4.9.1.?
The reactor vessel materialtirradiation surveillance specimens shall be removed and examined, to determine changes in material' properties, as l
required by 10 CFR Part 50,, Appendix H.
The results of.these examinations.
l-shall be used to update Figures 3.4-2 and 3 4-3.
l-l l
)
SOUTH TEXAS - UNITS 1 & 2 3/4 4-31 Unit-l' - Amendment No. 36 Unit 2 - Amendment No. 1
MATERIAL Pf40PERTY BASIS _
CONTROLLING MATERIAL - RV RTNDT INITIAL: lO'T INTERHEDIATE SHELl.. R-1606-3 RTNDT AFTER 32 EFPY COPPER CONTENT CONSERVATIVELY 1/4 91'F ASSUMED AS 0.10 VTX 3/4T, 64*F l
CURVE APPLICABLE FOR HEATUP RATES UP TO IOO'/FR FOR THE SERVICE PERIDO UP TO 32 EFPY AND CONTAINS MARGINS OF 1O'F AND 60 PSIG FOR POSSISLE INSTRUMENT ERRORS 3000 5
i f
[
LEAK TEST LIMIT --+=
I
~
2000 u
)
)
/ /
~
u
/
/
( )<
a C) 1000 s
/
/
l s/
-eu!!c^'2" c
EASED ON INSERVICE HYDROSTATIC TEST W.ATLP MATES aJ TDPERATtstE (242')
FOR
{!CE L.P TO 100'rnet 32 EP*
I t t 1
-t t tA O
O
- 100, 200
'300 400 INDICATED TEMPERATURE (*F)
I i
FIGURE 3.4-2 REACTOR COOLANT SYSTEM HEATUP LIMITATIONS - APPLICABLE UP TO 32 EFPY SOUTH TEXAS - UNITS 1 &~2 3/4 4-32.
-y%'
MATERIAL PROPERTY SASIS CONTROLLING MATERIAL - RV RTg y INITIAL: lO'F INTERNECIATE SHELL R-1606-3 RT AFTER 32 EPPY COPPER CONTENTS: CONSERVATIVELY E T
/4, A9SUMEO AS 0.10 VTX gl'F 3/47, 64'V SINGLE CURVE APPLICABLE FOR COOLDOWN RATES UP TO s
THE SERVICE PERIOD UP TO 32-EFPY. A2 CONTAINS MARGIN 1.
' AND 60 PSIG Fort POSSIBLE INSTRUMENT ERRORS 3000-f r
LD r
. )
t
~
~ 2000
. 1
~
f.
b l
Lf)
[
}
S Q
1000
/
O C00LDonN RATE *F/Wt 3
(621'PSIS)M t
y
~
g32V 800#. l ( tao'F}
I-O
-O
'I00-200-301 INDICATEDLTEMPERATURE;(?F)
FIGURE-3.4-3 REACTOR'C00LANT SYSTEM COOLDOWN LIMITATIONS - APPLICABLE UP TO 32
' SOUTH.TEXAST _VNITS l'& 2:
3/4.4-33
,_,..m.-.._
.., _., ~...
JMjf 4.4-5 I
(This table number not used) f I
l i
SOUTH TEXAS - UNITS 1 & 2 3/4 4-34 Unit 1 - Amendment Ho. 36 Unit 2 - Amendment No. 27
l l
RExCTOR COOLANT SYSTEM BASES PRESSURE TEMPERATURE LIMITS (Continued)
Allowable combinations of pressure and temperature for specific a.
temperature change rates are below and to the right of the limit lines shown.
Limit lines for cooldown rates between those presented may be obtained by interpolation; and b.
Figures 3.4-2 and 3.4-3 define limits to assure prevention of non-ductile failure onl For normal operation, of her inherent plant characteristics, e.g., y. pump heat addition and pressurizer heater capacity, may limit the heatup and cooldown rates that can be achieved over certain pressure-temperature ranges.
2.
These limit lines shall be calculated periodically using methods provided
- below, 3.
The secondary side of the steam generator must not be pressurized above 200 psig if the temperature of the steam generator is below 70 F, 4.
The pressurizer heatup and cooldown rates shall not exceed 100 F/h and 200 F/h, respectively.
The spray shall not be used if the temperature difference between the pressurizer and the spray fluid is greater than 621'F, a'nd 5.
System preservice hydrotests and inservice leak and hydrotests shall be performed at pressures in accordance with the requirements of ASME Boiler and Pressure Vessel Code,Section XI.
The fracture toughness properties of the ferritic materials in the' reactor vessel are determined in accordance with the NRC Standard Review Plan, ASTM E185-73, and in accordance with additional reactor vessel requirements.
These properties are then evaluated in accordance with Appendix G of the 1976 Summer Addends to Section III of the ASME Boiler and Presst.a Vessel Code and the calculation methods described in WCAP-7924-A, " Basis for Heatup and Cooldown Limit Curves," April 1975.
Heatup and cocidown limit curves are calculated using-the most limiting value of the nil-ductility reference temperature, RTNOT, at the end of 32 effec-tive full power years (EFPY) of service life.
The 32 EFPY service life ~ period is chosen such that the limiting RTNDT at the 1/4T: location in the core region is greater than the RT f the limiting unirradiated material.
The selection NDT of such a limiting RTNDT. assures that,all components in-the Reactor Coolant System will be operated conservatively in accordance with applicable Code requirements.
The reactor vessel materials have been tested to determine their initial RTNDT; the results of these tests are shown in Tables B 3/4.4-la and B 3/4.4-lb.
l Reactor operation and resultant fast neutron (E greater than 1 MeV) irradiation l
SOUTH TEXAS - UNITS 1 & 2 B 3/4 4-7 Unit 1 - Amendment No. 4
l i
l BASES l
ERESSURE/TEMPEE QVRE LIMITS (Continued) i can cause an increase in the RT,33 Therefore, an adjusted reference tempera-ture, based upon the fluence, copper content, and phosphorus content of the material in question, can be predicted using Figure B 3/4.4-1 and the value of l
6RT,3,ts on Predicted Radiation Damage to Reactor Vessel-Materials." computed b Elemen The t
heatup and cooldown limit curves of-Figures 3.4-2 and 3.4-3 include predicted adjustments for this shift in RT at the end of 32 EFPY as well as adjust-
[
ments for possible errors in the,37 pressure and temperature sensing instruments.
i Values of 4RT determined in-this manner may be_used until the results from the material,33 surveillance program, evaluated according to ASTM-E185,'are i
available.
Capsules will be removed in accordance with the requirements of-AS1H ElBS-73 and 10 CFR Part 50, Appendix H.-
The results obtained from the i
surveillance specimens can be used to predict future radiation damage-to the i
reacter vessel material by_ using the lead factor and the withdrawal time' of 4
the capsule.
The heatup and cooldown curves must be recalculated when the j
i 6RT,3,he equivalent capsule radiation exposure. determined from the surveillance ca for t i
l Allowable pressure-temperature relationships for various heatup and i'
cooldown rates are calculated using methods derived from Appendix G-in Section 111 of the ASME Doiler and Pressure Vessel Code as required by Appendix G-to 30 CFR part 50, and these methods are discussed in detail in WCAP-7924-A.
t-Ihe general, method for calculating heatup and cooldown limit' curves is-based upon.the principles of the linear elastic fracture mechanics ~(LEFM)
L technology, in the calculation procedures a semielliptica11 surface defect with a _ depth of one-quarter of the wall thickness, T, and a length of 3/2T is assumed to exist at the inside of the vessel-wall as well:as at-the outside of-the vessel wall. The dimensions of this postulated crick, referred to in-Appendix'G of ASME Section 111 as the reference flaw, amply' exceed the current capabilities of inservice inspection techniques..Therefore, the reactor operation limit' curves feveloped for this'referenc'e crack are conservative-and provido sufficient safety margins,for protection against;nonductile failure.
To assure that the radiation embrittlement effects are accounted for in the' calculation M the limit curves, the'most limiting value of the nil-ductility is'used and this includes the-radiation-induced-D refe,ence inperature, RT,31,to the end of the period for:whichtheatup :and-shif t, 4RT,33,. corresponding' cooldown curves.are generated.
The' ASME approach: for calculating the -allowable limit curves for1various~
heatup;and.coolde rates specifies thatLthe total stress intensityLfactor, Kh, for the combined thermal-and pressure' stresses at any= time during;heatup or cooldown cannot-be greater-than;the reference stress intensity factor, K..
m for the metal. temperature at thatt time.
K is obtained from the reference a
SOUTH TEXAS ' UNITS 1 1 2 B 3/4f4-8 Unit)1 - Amendment: No. 36 Unit 2 -: Amendment!No.;27-4
REACTOR COOLANT SYSTEM BASES LOW TEMPERATURE OVERPRESSURE PROTECTION (Continued) overshoot beyond the PORY Setpoint which can occur as a result of time delays in signal processing and valve opening, instrument uncertainties, and single failure.
To ensure that mass and heat input transients more severe than those assumed cannot occur, Technical Specifications require lockout of all high head safety injection pumps while in MODE 5 and MODE 6 with the reactor vessel head on. All but one high head safe injection pump are required to be locked out in MODE 4.
Technical Specifications also require lockout of the positive displacement pump and all but one charging pump while in MODES 4, 5, and 6 with the reactor vessel head installed and disallow start of an RCP if secondary temperature is more than 50*F above primary temperature.
lhe Maximum Allowed PORV Setpoint for the COMS will be updated based on the results of examinations of reactor vessel material irradiation surveil-lance specimens performed as required by 10 CFR Part 50, Appendix H.
3/4.4.10 STRUCTURAL INTEGRITY The inservice inspection and testing programs for ASME Code Class 1, 2 and 3 components ensure that the structural integrity and operational readi-ness of these components will be maintained at an acceptable level throughout the life of the plant.
These programs are in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as recuired by 10 CFR 50.55a(g) except where specific written relief has been grantet by the Commission pursuant to 10 CFR 50.55a(g)(6)(1).
Components of the Reactor Coolant System were designed to provide access to permit inservice inspections in accordance with Section XI of the ASME Boiler and Pressure Vessel Code, 1974 Edition and Addenda through Winter 1975.
3/4.4.11 REACTOR VESSEL HEAD VENTS Reactor vessel. head vents are provided to exhaust noncondensible gases and/or steam from the Reactor Coolant System that' could inhibit natural circulation core cooling.
The OPERABILITY of at least two reactor vessel head vent paths ensures that the capability exists to perform this function.
The vaive redundancy of the reactor vessel head vent paths serves to minimize the probability of inadvertent or irreversible actuation while ensuring that a single failure of.a vent _ valve, power supply, or control-system does not prevent isolation of the vent path.
The function, capabilities, :Nd testing requirements of the reactor vessel head vents are consistent with tk requirements of Item II.B.I'of NUREG-0737,
" Clarification of TMI Action Plan Requirements," November'1980.
l SOUTH TEXAS - UNITS 1 & 2 B 3/4 4-15 Unit 1 - Amendment-No. 4, 36 L
. Unit 2 - Amendment No.- 27 l
.