ML20085K892

Proposed Tech Specs,Deleting Section 5.7-1 Re Component Cyclic or Transient Limit

ML20085K892
Person / Time
Site:	South Texas
Issue date:	10/25/1991
From:	HOUSTON LIGHTING & POWER CO.
To:
Shared Package
ML20085K890	List: ML20085K892 ST-HL-AE-3884, Application for Amends to Licenses NPF-76 & NPF-80,deleting Tech Spec Table 5.7-1, Component Cyclic or Transient Limits Which Is Implemented by Plant Procedure Per Requirements in Updated FSAR
References
NUDOCS 9111010137
Download: ML20085K892 (5)

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ATTACHMENT 2 MARK UPS OF PROPOSED CHANCES TO TECHNICA!. SPECIFICATIONS r

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TSCl91-239.001 9121010137 911023 FDR ADOCK 05000492

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f ATTACHMENT 2 1 010tL{EA1UREJ _

,_S" HL AE-3d '/ q mit i _ ur 0.0185 ok for Region 1 ur> certainties and tolerances and 0.0259 ok for Region 2 uncertaintics and tolerances.

b, A nominal 10.95 inches center to center distance between foal asserrblies in Region 1 of the storage racks.and a nominal 9.15 inches Region center 2 of the to center storage racks. distance between fuel assembifes .in c.

Heutron in the storage absorber racks in Reg (Boraflex) ion 1 and Region 2 installed bet

d. Region 1 of the spent fuel storage ra ts can be used to store fuel which has a U weight percen,-235 cnricha,ent less than or equal to a nominal 4.5

t. Region 2 can be used to sture fuel which has achieved sufficient burnup required. The initial enrichment such that storage fn Region 1 is not vs. burnup requirement 9 of rigure 5.6.1 shall be met prior to storage of fuel assemblies in Region 2.

DRA1HACE 5.6.2 The spent fuel storage pool is designed and shali be maintained to' prevent inadvertent draining of the pool below elevation 62 feet-6 inches.

_ CAPACITY 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.

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5. 7 COMPONENT Cyclic OR TRANSIENT LtHIT '

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5.7.1 The components of the reactor coolant hystem are [

designed and shall be maintained within limits -

J addressed in the Component cyclic and Transient Limit i

,,  ; Program as required by specification 6.8.3f. l

• , b SOUTH TEXAS - UNITS 1 & 2 5-7 Unit 1 - Amendment No. 2

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TABLE 5.7-1 .

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COMPONENT CYCLIC CR TRANSIENT LIMITS b

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CYCLIC OR DESIGN CYCLE COMPONENT TRANSIENT LIMIT OR TRANSIENT E Reactor Coolant . tem 200 heatup cycles at < 100*F/h Heatur cycle - T from < '

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

" -< 100'F/h. CooTdown cycle - T =

c- > 550'F to < 200*F a pressurizer cooldown cycles Pressurize:- down cycle at - 00'F/b. temperat- from > 650*F to

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< 200' 80 loss of cycles, without A % of RATED THERM POWER to ircediate 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 w in Loss of only one reactor reactor coolant 1 . coolant pump.

[e 400 Reactor p cycles. 100% to 0% of RATED THERML POWER.,

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- 10 au ' ary spray Sp. water temperature differential i

a, .fon cycles. > 621 N

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200 leak tests. Pressurize > 2485 psig.

i E 2i l 10 hydrostatic pressure tests. Pressurized to > 'O psig. - Sj??.' I

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Secondary f v@

ant System 1 steam line break. Break in a > 6-inch steam ' e.

10 hydrostatic pressure f.ests. Pressurized to > 1600 psig. . .

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@Dil(15]MUYLCONIROL5___ _ _ _ _ _ _ _ _ - - - -

REM _ DE Y PROCEDURES AND PROGRAMS (Continued)

e. Accident Monitoring Instrumentation A program which will ensure the capability to monitor plant variables and systems operating status dering and following an accident. This program shall include 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 instrucen-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 inoperabic instruments GNSERT A q to OPERABLE status as soon as practicable.

6.9 REPORTING REQUIREMENTS

. ROUTINE REPORTS 6.9.1 In addition to the appilcable reporting requirements of Title 10, Code of Federal Regulatians, 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 Icvel, (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 Repert 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

'cnd 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, r6tartup 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 commerc}al operation), supplementary reports shall be sub-aitted at least every 3 months until all three events have been completed.

SOUTH. TEXAS - UNITS 1 & 2 6-16 -

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f. CottPONENT CYCLIC AND TRAN8IENT LIKTT PROGRAM l

The cotsponent cyclic and Transient, Limit Progrsa provides controls - to track cyclio/ transient occurrences j to ensure that components-of the reactor coolant syntaa il are not subjected to conditions that are more severe d than those which have been considered in the fatigue analysis that was performed to comply with the f requirements of section III of the ASME B&P7 Code. The program nhall include the component ayalio and J; transient limits that are identified in the speftst.

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