ML20205P431
| ML20205P431 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 11/01/1988 |
| From: | Calvo J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20205P435 | List: |
| References | |
| NUDOCS 8811080129 | |
| Download: ML20205P431 (8) | |
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UNITED STATES 8
NUCLEAR REGULATORY COMMISSION B
WASHING TON. D. C. 20686 o....
HOUSTON LIGHTING & POWER COMPAfiY CITY PUBLIC SERVICE BOARD OF SAN ANTONIO CENTRAL POWER AND LIGHT COMPANY
.CJ,TY, p,F,3USTJL,JE),AS DOCKETNO.,5p,,49,8 59.V,TH,,T,E)3),PRpiE,CT, UNIT 1 AM E N Df 1 E N.T..T.O..F.A.C.I.L.11.Y..O.P.E R.A..T..I.N.G..L.I.C.E.N.S.E Amendment No. 2 License No. NPF-76
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1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for atiendcient by Pouston Lighting & Power Conpany (HL&P) dated 11 arch 8,1988 as suppicuented on itarch 26, 1908, ccrtlies with the standa'rds and requirements of the Atomic Energy Act of 1954, as ariended (the Act), and the Cottiission's rules and regulations set forth in 10 CFR Chapter I; I
D.
The facility will operate in confornity with the application, as atended, the provisions of the Act, and the rules and regulations of the Comission;
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C.
There is reascnable assurance:
(i) that the activities authorized by this atendrent can be conducted without endangering the health t
and scfety of the public, ar.d (ii) that such activities will be conducted in compliance with the Coccission's regulations-t D.
The issuance of this license amendment will not be inimical to the i
common defense and security or to the health and safety of the public; i
and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 5
of the Comission's regulations and all applicable requirements have been satisfied.
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L 8811080129 891101 L
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l 2.
Accordingly, the license is amended by chariges 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:
2.
,Te_c,hni ca,1, Sp,ec t fi ca tions e
ifi The Technical Specifications contained in Appendix A, as revi ed through Amendment No. 2, and the Er.vironmental 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 Enviror. mental Protection Plan.
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3.
The licent.e ac.endment is effective as of its date of issuance.
FOR THE HUCLEAR REdVLATORY C0ft.15510N
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,h Jose A. Ca v, Director Project Directorate - !Y Division of Reactor Projects - 111, IV, Y and Special Projects j
Office of Nuclear Reactor Regulation Attachrient:
Charses to the Technical l
Specificatiens l
Date of issuar.ce: November 1,1988 l
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ATTACHMENT TO LICENSE A11ENDl1EhT Li. 2 f A cJ,tJ Jy, pp Et,AJJ pp, LJ,C,E!@ E, Np,, fiff -?j 00CKET N0_.,5,0,,49p Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by Anendment nuttser and contain vertical lines indicating the areas of change. The corresponding overleaf paces are also provided to raintain document completeness.
Remoye Insert 5-6 5-6 5-7 5-7 5-9 i
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I SOUTH TEXAS - UNIT 1 5-5 l
I pESIGNFEATURES S.3 REACTOR 10g FUEL ASSEMBLIES 5.3.1 The core shall contain 193 fuel assemblies with sach fuel assembly con-tainint 264 fuel rods clad with Zircaloy-4.
Each fuel rod shall have a nominal active fuel length of 168 inches.
The initial core loading shall have a maxi-num enrichment of 3.5 weight percent U-235.
Peload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrichment of 3.5 weight percent U-235.
CONTROL R00 ASSEMBLIES 5.3.2 The core shall contain 57 full-length control rod assemblies. The full-length control rod assemblies shall contain a nominal 158.9 inches of absorber material.
The absorber material shall be hafnium.
All control rods shall be clad with stainless steel tubing.
5,4 REACTOR COOLANT SYSTEM t
I DESIGN PRESSURE AND TEMPERATURE s
5.4.1 The Reactor Coolant System is designed and shall be maintained:
a.
In accordance with the Code requirements specified in Section 5.2 of the FSAR, with allowance for normal degradation pu iuant to the l
applicable Surveillance Requirements, j
b.
For a pressure of 2485 psig, and c.
For a temperature of 650'F, except for the pressurizer which is 680'F.
VOLUME 5.4.2 The total water and steam volume of the Resctor Coolant System is 13,814
+ 100 cubic feet at a nominal T,yg of 561'F.
l 5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological towers shall be located as shown on Figure 5.1-1.
i 5.6 FUEL STORAGE i
CRITICALITY 5.f.!
The spent fuel storage racks are designed and shall be raintained l
with:
A k,ff equivalent to less than or equal to 0.95 when flooded with l
a.
unborated water, which includes a conservative allowance of
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SOUTH TEXAS - UNIT 1 56 Anendment No. 2 l
ffSIGN FEATURES 0.0185 Ak for Region 1 uncertainties and tolerances and 0.0259 ok for Region 2 uncertainties and tolerances.
b.
A nominal 10.95 inches center to center distance between fuel assemblies in Region 1 of the storage racks and a nominal 9.15 inches center to center distance between fuel assemblies in Region 2 of the storage racks.
c.
Neutron absorber (Boraflex) installed between spent fuel assemblies in the storage racks in Region 1 and Region 2.
d.
Region 1 of the spent fuel storage racks can be used to store fuel which has U-235 enrichment less than or equal to a nominal 4.5 weight percent.
Region 2 can be used to store fuel which has achieved sufficient burnup such that storage in Region 1 is not required.
The initial enrichment vs. burnup requirements of Figure 5.6-1 shall be met prior to storage af fuel assemblies in Region 2.
DRAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 62 feet-6 inches.
CAPACITY
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5.6.3 The spent fuel storage pool is desi ned and shall be maintained with a storage capacity limited to no more than 1 69 fuel assemblies.
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57 COMPONENT CYCLIC OR TRANSIENT LIMIT 5.7.1 The component: identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1.
l SOUTH TEXAS - UNIT 1 5-7 Amendment No. 2 l
4 TABLE 5.7-1 v.
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COMPONINT CYCLIC OR TRANSIENT LIMITS m
5 CYCLIC OR DESIGN CYCLE COMPDFENT TRANSIENT LIMIT OR TRANSIENT b
Reactor Coolant System 200 heatup cycles at < 100'F/h Heatup le - T"I from 1 200*F and 200 cooldewn cycles at to > 5
~< 100*F/h.
CooTdown cycle - T from
> 553*F to < 200*F*'I 200 pressurizer cooldown cycles Pressurizer cooldown cycle at < 200'F/h.
temperatures from > 650*F to
$ 200*F.
80 loss of load cycles, without
> 15% of RATED THERMAL POWER to isusediate Turbine or Reactor trip.
ifE of RATED THERMAL POWER.
40 cycles of loss-of-of fsite loss-of-offsite A.C. electrical A.C. electrical power.
ESF Electrical System.
80 cycles of loss of flow in one loss of only one reactor reactor coolant loop.
coolant pump.
400 Reactor trip cycles.
100% to UK of RATED THERMAL POWER.
10 auxiliary sprdy Spray water temperature differential actuation cycles.
> 621*F.
200 leak tests.
Pressurized to > 2485 psig.
10 hydrostatic pressure tests.
Pressorized to > 3110 psig.
Secondary Coolant System I steam line t>reak.
Break in a > 6-inch steam line.
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10 hydrostatic pressure tests.
Pressurized to > 1600 psig.
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40 l
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Acceptable i
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Unacceptable 20 I
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j 1.4 2.0 3.0 4.0 5.0 l
Initial Enrichment (w/o) i 4
i Figure 5.61 l
SOUTH TEXA5 PROJECT SPENT FUEL RACK 5 l
REGION 2 REQU!AED BURNUP A5 A FUNCTION OF INITIAL ENRICHMENT i
SOUTH TEXAS - UNIT 1 5-9 Amendment No. 2
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