ML20101G700

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Proposed TS Deleting TS Table 5.7-1 Re Component Cyclic or Transient Limits
ML20101G700
Person / Time
Site: South Texas  STP Nuclear Operating Company icon.png
Issue date: 06/16/1992
From:
HOUSTON LIGHTING & POWER CO.
To:
Shared Package
ML20101G699 List:
References
NUDOCS 9206260245
Download: ML20101G700 (7)
v • d • e


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ATTACHMENT 2 MARK-UPS OF PROPOSED CilANGES TO "

TECilNICAL SPECIFICATIONS t'

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.9206260245 920616 PDR ADOCK 05000498 i P PDR TSC\91 259.001 ,

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{' A1TACHMENT 2 INDEX ST HL AE- 4 os 'T PAGE 1 0F 4

! DESIGN FEATURES i SECTION PAGE

!; 5.1 SITE 4

a 5.1.1 EXClVS10ffAREA. .... .. . . .. ..... ...... . .. ........ .. 5-1 l 5.1.2 LOW POPULA110N ZONE.. .............. .......... ........ .... . 5-1 i 5.1. 3 MAP DEf1NING UNRESTRICTED AREAS AND SITE BOUNDARY FOR l RADI0 ACTIVE GASE0US AND LlQUID EFFLUENT 5....................... 5-1

- 5. 2 C0t!1AINMENT I

5.2.1 CONilGURAT10N............................. .................. 5-1 ~

5.2.2 DESIGN PRESSURE AND TEMPERATURE................................ 5-1

flGURE 5.1-1 EXCLUSION AREA.... . ..................... ............ 5-2 '

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flGURE 5.1-2 -LOW POPULATION ZONE.... . .......................... ... 5-3 l FIGURE 5.1-3 UNRE51RICTED AREA AND 51TE BOUNDARY FOR RAD 10 ACTIVE l l GA5E005 EFFLUEN15.

.. .. . ... .. .. . ..... .. .. 5-4 i . .

4 flGURE 5.1-4 UNRESTRICTED AREA AND 51TE BOUNDARY FOR RAD 10 ACTIVE' l LIQU10 EffLVEN15 . ................. . ....... .. .. 5-5 l

i 5.3 REAC10R CORE i

5.3.1 FUEL ASSEMBLIES.... . . .... ........... ...... .. ..,..... 5-6 i

5.3.2 CONTROL' ROD'A55EMBL1ES... .... ... . .... . ..... ... . .... 5-6 5.4 REACTOR COOLANT SYSTEM l

s 5.4.1 DESIGN PRESSURE AND TEMPERAlVRE.... . ..... . . . .. ... . 5-6.

t l 5.4.2 VOLUMt. ... . .. ...................... ........ . .. ... 5-6 t

l 5. 5 METEOROLOGICAL TOWER LOCATION........... ... .. .... ... .. . 5-6 1

l- 5. 6 fuel STORAGE l 5.6.1. CRITICAllTY. ................................ ................. 5-6

5.6.2 DRAINAGE.......................................... ..... ...... 5-7

! 5.6.3 CAPACITY...... ...... .. .................................. ... 5-7 5.7 COMPONENT-CYCLIC OR TRANSIENT LIMIT.. ....... ............ 5 FIGURE 5.6-1 SOUTH TEXA5 PROJECT SPENT FUEL RACKS - REGION 2 HEQUIRED BURNUP.AS A FUNCTION Of INITIAL ENRICHMEN1.. 5-8 n _a_J b ( 0"f'ON Ead4.u.4-n e i RARE ! E rd _t-mW > .

l-SOUTH TEXA5 - UNITS 1 & 2 xvii: Unit'1 - Amendmerit nn.

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ATTACHMENT 4 PLS10!LL[AIURES ST.HL AE-405 7

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0.0185 ok for Re ion 1 uncertainties and tolerances and 0.0259 ok for Re ton 2 uncertainties and tolerances.

b.

A nominal 10.95 inches center to center distance between fuel i

assemblies in Region 1 of the storage racks.and a nominal 9.15 inches center to center distance between fuel assembifes ,in Region 2 of the storage racks.

c. Heutron absorber (Boraflex) installed between spent fuel assemblics in the storage rat...s in Region 1 and Region 2.
d. Region 1 of the spent fuel storage racks can be used to store fuel which has a U i weight percen.-235
t. Region cnrichment less 2 can be than used or equal to store fuelto a nominal which has 4.5 achieved required. sufficient burnup such that storage 1.n Region 1 is not The initial enrichment vs. burnup requirements of Figure 5.6.1 shall be met prior to storage of fuel assembifes in
Region 2.

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DRAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maintained tb prevent inadvertent draining of the pool below elevation 62 feet-6 inches.

CAPACITY i

5.6.3 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1969 fuel assemblies.

(

h 5. 7 COMPONENT CYCLIC OR TRANSIENT LIMIT

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8 5.7.1 The components of the reactor coolant system are

  • designed and shall be maintained within limits j addressed in the Component cyclic and Transient Limit i 4

Program as required by specification 4.8.3f.

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SOUTH TEXAS - UNITS 1 & 2 5-7 l

Uni.t 1 - Amendment No. 2

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. TABLE 5.7-1 0 -

COMPONENT CYCLIC OR TRANSIENT LIMITS

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[\

R _

> CYCLIC OR DESIGN CYCLE

- TRANSIENT LIMIT OR TRANSIENT 7 COMPONENT

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E Reactor Coolant tem 200 heatup cycles at < 100*F/h Heatup cycle - Tavg from <-

-4 and 200 cooldown cycles at to > 550*F.

<~100*F/h. CooTdown cycle - Ta m

> 550*F to < 200'F e.

" pressurizer cooldown cycles Pressurizer down cycle at 00'F/h. temperat from > 650*F to

< 200' 80 loss of cycles, without  % of RATED THERMAL POWER to immediate Turb or Reactor trip. of RATED THERMAL POWER.

. 40 cycles of loss-o fsite Loss-of-offsite A.C. electrical A.C. electrical power. ESF Electrical System. .

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80 cycles of loss of in Loss of only one reactor

. reactor coolant 1 . . coolant pump.

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400 Reactor p cycles. 100% to 0% of RATED THERMAL POWER.

10 au ~ ary spray Sp water temperature differential i a _ior, cycles. > 62 Y -

200 leak tests. Pressurize > 2485 psig., 1 l

g mu231 cu l 10 hydrostatic pressure tests.

Pressurized to > 0 psig.'. hy!

r c>t Okj\

y ,

Break in a > 6-inch sti:am

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- Secondary ant System- 1 steam line break. i o

- -4 {

a 10 hydrostatic pressure tests. Pressurized to > 1600 psig... Qk i

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. l l ADidifd51RA]J1Lf0ER0t5 ATTACHMFNT 2 ST HL-AE-4 0 59

. PROCEDURES AND PROGRAMS (Continueq PAGE 4 0F i

e. Accident Monitoring Instrumentation A program which will ensure the capability to monitor plant variables and systems operating status during and following an accident. This program shall in:1ude those instruments provided to indicate system .

operating status and furnish information regarding the release of '

radioactive materials (Category 2 and 3 instrumentation as defined in Regulatory Guide 1.97, Revision 2) and provide the following:

1) Preventive maintenance and periodic surveillance of instrumen-tation,
2) Pre planned operating procedures and backup instrumentation to be used if one or more monitoring instruments become inoperable, and

. 3) Administrative procedures for returning inoperable instruments TSERT A ] to OPERABLE status as soon as practicable.

6.9 REPORTING REQUIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Regional Administrator of the Regional Office of the NRC unless otherwise noted.

STARTUP REPORT

6. 9.1.1 A summary report of plant startup and power escalation testing shall be submitted following: (1) receipt of an Operating License, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4). modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the' unit.

The Startup' Report shall address each of the tests identified in the Final Safety Analysis Report and shall include a description of the measured values of the operating conditions or . characteristics obtained during the test program a

'and a comparison of these values with design predictions and specifications.

Any corrective actions that were required-to obtain satisfactory operation shall also be described. Any additional specific details required in license condi-tions based on other commitments shall be included in this report.

Startup Reports shall_ be submitted within: (1) 90 days following completion of the Startup Test Program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e. , initial criticality, completion of Startup Test Program, and resumption or commencement of commercial operation), supplementary reports shall be sub-nitted at least every 3 months until all three events have been completed.

SOUTH TEXAS - UNITS 1 & 2 6-16 -

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!' ATTACHMENf1 1

  • ST HL AE 40.51 4

PAGE s 0F G, t@ M liTRAT]VE_t00ROL1 _ , _ _ _ -s i ,

1 6.10 RECORD RETENTION

! 6.10.1 In addition to the applicable record retention requirements of Title-10,  !

Code of Federal Regulations, the following records shall be retained for at
least the minimum period indicated.

6.10.2 The following records shall be retained for at least 5 years:

I a. Records and logs of unit operation covering time interval at each i power level; j b. Records and logs of principal inaintenance activities, inspections, y repair, and replacement of principal items of equipment related to j nuclear safety; l c. All REPORTABLE EVENT 5; 4

i d. Records of surveillance activities, inspections, and calibrations .

l required by these Technical Specifications;

! e. Records of changes made to the procedures required by j Specification 6.8.1;

f. Records of radioactive shipments;
g. Records of sealed source and fission detector leak tests and results; and

! h. Records of annual physical inventory of all sealed source material 1 of record.

6.10.3 The following records shall be retained for the duration of the unit-Operating License:

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l a. Records and drawing changes reflecting unit design modifications '

made to systems and equipment described in the final Safety Analysis j Report;

b. Records of new and irradiated fuel inventory, fuel transfers, and i assembly burnup histories; l
c. Records of radiation exposure for all individuals entering radiation control areas;

} d. Records of gaseous and liquid radioactive material released to the environs; l e. Records of transient or operational cycles for those unit components identified-in i 4 5. 7-1; the- U F147 3

f. Records of reactor tests and experiments;
g. Records of training and qualification for current members of the j unit staff; I h. Records of inse.vice inspections performed pursuant to these % hnical

[ Specifications;

i. Records of quality assurance activities required by the Operational Quality Assurance Plan;

! SOUTH TEXAS UNITS 1 & 2 6-21 .

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- ATTACHMENT A ST HL AE 4 05 "i PAGE f, _0F G IllSERT A f.

COMPO! LENT CYCLIC or TRANSIDIT LIMIT

Th COMPollEllT CYCLIC or TRA11SIDIT LIMIT PROGRAli__pr.ovl<les-contro ack the reicwwMFwu< Table 3.9-8 cyclic / transient nocu es ncure that components are

.mainberivitrd Vitiiin the design linits.

7 The Ct.mponent Cyclic and Transient Lirnit Program provides controls to track cyclic / transient plant conditions to assure that the cumulative fatigue usage factor does not exceed 1.0 for those components for which fatigue analysis was perforrned in accordance with Section III of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code. The cyclic and transient limits used in the design are identified in the Updated Final Safety Analysis Report, i

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