ML20084J983

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Proposed Tech Specs,Reflecting Relocation of TS 3/4.1.2.1 to 3/4.1.2.6 & 3/4.4.2.1 to Technical Requirements Manual
ML20084J983
Person / Time
Site: South Texas  STP Nuclear Operating Company icon.png
Issue date: 05/31/1995
From:
HOUSTON LIGHTING & POWER CO.
To:
Shared Package
ML20084J958 List:
References
NUDOCS 9506060347
Download: ML20084J983 (18)


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ATTACHMENT 2 MARKUPS OF PROPOSED CHANGES i

TO TECHNICAL SPECIFICATIONS AND ASSOCIATED BASES 9506060347 950531 PDR ADOCK 05000498 P PDR Tsc.9545toooot

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ST-HL-AE-5092 Attachment 2 Page 8 of 11 l

EEACTIVITY CONTROL SYSTEMS BASES l l

l MODERATOR TEMPERATURE COEFFICIENT (Continued)

The most negative MTC value, equivalent to the most positive moderator density coefficient (MDC), was obtained by incrementally correcting the MDC used in the FSAR analysis to nominal operating conditions.

These corrections involved: (1) a conversion of the MDC used in the FSAR analysis to its equivalent MTC, based on the rate of change of moderator density with temperature at RATED THERMAL POWER conditions, and (2) subtracting from this value the largest differences in MTC oiaerved at EOL, all rods withdrawn, RATED TilERMAL POWER conditions, and those most adverse conditions of moderator temperature and pressure, rod insertion, axial power skewing, and xenon concentration that can occur in nominal operation and lead to a significantly more negative EOL MTC at RATED TIIERMAL POWER. These corrections transformed the MDC values used in the FSAR analysis into the limiting EOL MTC value specified in the CORE OPERATING I

LIMITS REPORT (COLR). The 300 ppm surveillance MTC value specified in the COLR represents a conservative value (with corrections for burnup and soluble boron) at a core condition of 300 ppm equilibrium boron concentration, and is obtained by making these corrections to the limiting MTC value.

The Surveillance Requirements for measurement of the MTC at the beginning and near the end of the fuel cycle are adequate to confirm that the MTC remains within its limits since this coefficient changes slowly due principally to the reduction in RCS boron concentration associated with fuel burnup.

3/4.1.1.4 MINIMUM TEMPERATURE FOR CRITICALITY l l

This specification ensures that the reactor will not be made critical with the Reactor Coolant System average temperature less than 561 F. This limitation is required to ensure: (1) the moderator temperature  !

coellicient is within its analyzed temperature range, (2) the trip instrumentation is within its normal operating range, (3) the pressurizer is capable of being in an OPERABLE status with a steam bubble, and (4) the reactor vessel is above its minimum RTm temperature.

F! 1.2 39RMION SYRTFMc BAcre i

The4kme-injeetion-System-enstwes tha: negative-eentrohr,-twailable during each mode of facility opemtion. The ewnponentwequirwl-to-perfonn4hi runctian inc!ude: (!) borated uter scarce:., (2) charging l pump +,-9)-sepamte41ew-pathsH4)4wie-eekt-transfer pumps, and (5) an emergeaey pc ser supply-from l OPMAHie-diewl-genemters-Whh-the-RC4everage4empemttwe abo;e 350 F, :ninimm ef t" e borer, njection Oe" paths are required-tensure+ ingle-ftmetional-eapaintity-in-the e ent an asm.med failure renders one of-the 0^" paths inopemble-4hlwathm-eapabilitp4-either Sc; path 49-sufficier te provide a FHUTDO'"F MARGIN from espeeted-opemting+mditie:. of ! 3% (delta)kA-efter xenca deca; and cuc!do" .. ic 200 F The mammtm>

apeeted4walke-sapability-+eepdre: 27,000 gallen: er "00 ppm-bomted-water-fronHhe beric acid "crage system-et-4-58,000 gallemf 2300 ppm 4wated va:er fronHhe refueling "a:er ::erage tank (R\"SB. The R"/ST c!mne . . . ECCF requirement-mw! :: wre :han-adequate-for-the-requival4eration capatnlip SOUTil TEX Ab -% NITS 1 & 2 B 3/41-2 Unit 1. Amendment No. 27,35, 51, 5!, 61 Unit 2 - Amendment No. I', 26,!0,13,50 nemm mi

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Y f ! ,, 1 p. 7 TSC.9595100.001 # 1 - , uvuu awaus v uno a m a

ST-HL-AE-5092 Attachment 2 Page 11 of 11 3/4.4 REACTOR COOLANT SYSTEM BASES (Continued) 3/4.4.1 REACTOR COOLANT I OOPS AND COOLANT CIRCULATION The restrictions on starting an RCP with one or more RCS cold legs less than or equal to 350 F are provided to prevent TCS pressure transients, caused by energy additions from Secondary Coolant System, which could exceed the limits of Appendix G to 10 CFR Part 50. The RCS will be protected against overpressure transients and will not exceed the limits of Appendix G by restricting starting of the RCPs to when the secondary water temperature of each steam generator is less than 50 F above each of the RCS cold I leg temperatures.

3/4.4.2 SAFETY VALVES The pressurizer Code safety valves operate to prevent the RCS from being pressurized above its Safety limit I of 2735 psig. Each safety valve is designed to relieve 504,950 lbs per hour of saturated steam at the valve setpoint of 2500 psia. -The relief capacity of a single-safety valve is adequate to relieve any ever pre =ne eemdition-whieh could cecur durin;; ;hutdown In the event that nc safety valves are OPERABLE, an l operating-RHR-leep, ecanected ic RCS, providesererptessure relief capability and -i!! prevent RCS l 1

overpreswriimtion--4n-taldition r4he Overpressure Protection System provide; a diverse means of protectica against-RCS cverpressurization a: !c.c temperatures.

During Modes 1,'.2, and 3, operation, all pressurizer Code safety valves must be OPERABLE to prevent the RCS from being pressurized above its Safety Limit of 2735 psig. The combined relief capacity of all of these valves is greater than the maximum surge rate resulting from a complete loss-of-load assuming no Reactor trip until the first Reactor Trip System Trip Setpoint is reached (i.e., no credit is taken for a direct Reactor trip on the turbine trip resulting from loss-of-load) and also assuming no operation of the power-operated relief valves or steam dump valves.

Demonstration of the safety valves' lift settings will occur only during shutdown and will be performed in accordance with the provision of Section XI of the ASME Boiler and Pressure Code.

1 I

B 3/4 4-1 South Texas - Units 1 & 2 ucm % m mi B 3/4 4-2 June 27,1990

e l

(

l ATTACHMENT 3 l

TECHNICAL SPECIFICATION SCREENING l EVALUATION BASED ON THE FINAL POLICY STATEMENT CRITERIA I

1 l

i i

I TSC-95 95-100 001

- ST-HL-AE-5092 Attachment 3 Page 1 of 5

. (1) TECIINICAL SPECIFICATION STP T.S. LOCATION / NUMBER 3/4.1.2.1 to 3/4.1.2.6 (2) EVALUATION BASED ON FINAL POLICY STATEMENT CRITERIA Is the Technical Specification applicable to:

YES N_O O e (1) Installed instrumentation that is used to detect, and indicate in the control room, a significant abnormal degradation of the reactor coolant pressure boundary?

O e (2) A process variable, design feature, or operating restriction that is an initial condition of a Design Bases Accident or Transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier?

O e (3) A structure, system, or component that is part of the primary success path and which functions or actuates to mitigate a Design Bases Accident or Transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier?

O e (4) A structure, system, or component which operating experience or probabilistic safety assessment has shown to be significant to the pubic health and safety?

If the answer to any one of the above questions is "YES", then the Specification shall be included in the Technical Specifications.

If the answer to all four criteria is "NO", then the Specifications may be relocated to Licensee-controlled documents.

i TSC 9L95-100 001

ST-HL-AE-5092 Attachment 3 Page 2 of 5 Technical Specification Screening Form Q) Discussion The purpose of the boration subsystem of the Chemical and Volume Control System, as addressed by Technical Specifications 3/4.1.2.1 through 3/4.1.2.6 is to provide for negative reactivity control during each mode of facility operation. As stated in Technical specification 3/4.1.2, Boration Systems - Bases:

  • With the Reactor Coolant System average temperature above 350 F, a minimum of two boron inject'on flow paths are required to ensure single functional capability in tic event an assumed failure renders one of the flow paths inoperable. The boration capability of either flow path is sufricient to provide a shutdown margin from expected operating conditions of 1.3%

(delta)k/k after xenon decay and cooldown to 200 F.

  • With the Reactor Coolant System temperature below 350 F, one boron injection flow path / source is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the additional restrictions prohibiting core alterations and positive reactivity changes in the event the single boron injection flow path / source becomes inoperable.
  • The operability of one Boron Injection System during refueling ensures that this system is available for reactivity control while in Mode 6.

Ilowever, continued negative reactivity control is ensured through other Technical Specifications not affected by this change.

The boration subsystem of the Chemical and Volume Control System, including the flow paths, charging pumps, and borated water sources, is not installed instrumentation that is used to detect, and indicate in the control room, a significant abnormal degradation of the reactor coolant pressure boundary. Therefore, the boration subsystem of the Chemical and Volume Control System does not meet Criterion 1.

nc.e m mi

l ST-HL-AE-5092 Attachment 3 Page 3 of 5 The boration subsystem of the Chemical and Volume Control System, including the flow paths, charging pumps, and borated water sources, is not a process variable, design feature, i or operating restriction that is an initial condition of a Design Basis Accident or Transient I analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier. Shutdown Margin is a process variable which is an initial condition of various Design Basis Accidents and Transient Analyses. However, operability of the ,

Chemical and Volume Control System is not. Limitations on Shutdown Margin are established and maintained by other Technical Specifications (e.g.,3/4.1.1) that are not affected by this proposed change. Therefore, the boration subsystem of the Chemical and Volume Control System does not meet Criterion 2.

l The boration subsystem of the Chemical and Volume Control System, including the flow paths, charging pumps, and borated water sources, is not a structure, system or component that is part of the primary success path and which function or actuates to mitigate a Design Basis Accident or Transient that either assumes the failure of or presents a challenge to the l integrity of a fission product barrier. Control and maintenance of the boron concentration in I the Reactor Coolant system by the Chemical and Volume Control System is not a part of the primary success path for mitigation of a Design Basis Accident or Transient. This function is provided either by the Emergency Core Cooling System (for some accidents or transients) or through maintenance of the Shutdown Margin, as established by specifications not affected by the proposed change, which is adequate to provide for the required safety function for other transients and postulated design basis accidents. Therefore, the boration subsystem of the Chemical and Volume System Control does not meet Criterion 3.

The boration subsystem of the Chemical and Volume Control System, including the flow paths, charging pumps, and borated water sources, is not a structure, system, or component which operating experience or probabilistic safety assessment has shown to be significant to the public health and safety. Boration paths are not modeled on the probabilistic safety assessment of the South Texas Project except for borated water injected via the Refueling Water Storage Tank. Leakage through the Reactor Coolant Pump seals due to loss of seal injection 'oy the charging pumps is included in the probabilistic safety assessment, but the contribution to Core Damage Frequency is not significant. Operating experience is included in the probabilistic safety assessment. Therefore, the boration subsystem of the Chemical and

\Hume Control System does not meet Criterion 4.

l (4) CONCLUSION O This Specification should be included in Technical Specifications.

a This Specification may be relocated to a Licensee-controlled Document.

acm-wm

ST-HL-AE-5092 Attachment 3 Page 4 of 5 (1) TECIINICAL SPECIFICATION - Safety Valves - Shutdown STP T.S. LOCATION / NUMBER 3/4.4.2.1 (2) EVALUATION HASED ON FINAL POLICY STATEMENT CRITERIA Is the Technical Specification applicable to:

YES NLQ O E (1) Installed instrumentation that is used to detect, and indicate in the control room, a significant abnormal degradation of the reactor coolant pressure boundary?

O a (2) A process variable, design feature, or operating restriction that is an initial condition of a Design Bases Accident or Transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier?

O E (3) A structure, system, or component that is part of the primary success path and which functions or actuates to mitigate a Design Bases Accident or Transient that either assumes the failure of or presents a challenge to the integrity of e ' m product barrier?

O e (4) A structure, . a or component which operating i experience or probabilistic safety assessment has shown to be significant to the pubic health and safety? l l

If the answer to any one of the above questions is "YES", then the Specification shall be included in the Technical Specifications. I I

If the answer to all four criteria is "NO", then the Specifications may be relocated to l Licensee-controlled documents.

l

'13C 0$.95-100 001

ST-HL-AE-5092 Attachment 3 Page 5 of 5 Technical Specification Screening Form (3) Discussion The purpose of Technical Specification 3/4.4.2.1, Safety Valves - Shutdown, is to ensure that sufficient capability is available to prevent the Reactor Coolant System from being pressurized above its safety limit of 2735 psig. Ilowever, below Mode 3, overpressure protection is provided by the low temperature overpressure protection requirements so that the pressurizer safety valves are not assumed to function to mitigate a design basis accident or transient under those conditions.

The pressurizer Code safety valves are not installed instrumentation that is used to detect, and indicate in the control room, a significant abnormal degradation of the reactor coolant pressure boundary. The pressurizer Code safety valves do not meet Criterion 1.

The pressurizer Code safety valves in Modes 4 and 5 are not a process variable, design i feature, or operating restriction that is an initial condition of a Design Basis Accident or l Transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier. The limitations and restrictions established for the Overpressure Protection Systems provide the design feature in Modes 4 and 5, which the pressurizer Code I safety valves provide for operations in Modes 1,2 and 3. Therefore, the pressurizer Code safety valves do not meet Criterion 2 in Modes 4 and 5.

The pressurizer Code safety valves in Modes 4 and 5 are not a structure, system or component j that is part of the primary success path and which functions or actuates to mitigate a Design liasis Accident or Transient that either assumes the failure of or presents a challenge to the ,

integrity of a fission product barrier. The limitations and restrictions established for the l Overpressure Protection Systems provide the design feature in Modes 4 and 5, which the pressurizer Code safety valves provide for operations in Modes 1,2 and 3. Therefore, the pressurizer Code safety valves do not meet Criterion 3 in Modes 4 and 5.

The pressurizer Code safety valves in Modes 4 and 5 are not a structure, system, or component which operating experience or probabilistic safety assessment has shown to be significant to the public health and safety. Rev.ews , hat have been performed are only applicable to operating modes. The pressurizer Code safety valves do not meet Criterion 4 in l Modes 4 and 5.

1 (4) CONCLUSION a This Specification should be included in Technical Specifications.

s This Specification may be relocated to a Licensee-controlled Document.

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