ML20198K134

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Corrected Tech Specs Pages to 980629 Application for Amend to License NPF-6
ML20198K134
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 12/17/1998
From:
ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20198K123 List:
References
NUDOCS 9812300343
Download: ML20198K134 (6)


Text

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REACTOR COOLANT SYSTEM

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SAFETY VALVES - SHUTDOWN LIMITING CONDITION FOR OPERATION l 3.4.2 A minimum of one pressurizer code safety valve shall be OPERABLE with a lift setting of 2500 PSIA i 3%*#. l APPLICABILITY: MODES 4 and 5.

1 ACTION:

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With no pressurizer code safety valve OPERABLE, inanediately susp6ao all operations involving positive reactivity changes and place an OPERABL3 shutdown cooling loop into operation.

SURVEILLANCE REQUIREMENTS 4.4.2 No additional Surveillance Requirements other than those required by Specification 4.0.5.

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  • The lift setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure. If found outside of a i 1% tolerance band, the setting shall be adjusted to within i 1% of the lift setting shown. ,

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  1. Equivalent relief capacity during MODE 5 satisfies the requirements of i this Specification. This allows both pressurizer code safety valves to be removed for testing and/or maintenance.

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9812300343 90121,*

PDR ADOCK 05000368 P PDR ;

I ARKANSAS - UNIT 2 3/4 4-3 Amendment No. M9,4M, i

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3/4.7 PLANT SYSTEMS BASES 1/4.7.1 TURBINE CYCLE 3/4.7.1.1 UAFETY CYCLES The OPEPABILITY of the main steam line code safety valves ensures that the secondary system pressure will be limited to within 110% of its design pressure of 1100 psia during the most severe anticipated system operational transient.

The maximum relieving capacity is associated with a turbine trip from 100% RATED THERMAL POWER coincident with an assumed loss of condenser heat sink (i.e., no steam bypass to the condenser) .

The specified valve lift settings and relieving capacities are in accordance with the requirements of Section III of the ASME Boiler and Pressure Code, 1971  ;

Edition. The "as-found" requirements are consistent with Section XI of the ASME Boiler and Pressure Vessel Code, 1986 Edition, and Addenda through 1987. The MSSV rated capacity passes the fulJ steam flow at 102% RATED THERMAL POWER (100%

+ 2% for instrument error) with the valves fully open. A minimum of 2 OPERABLE safety valves per steam generator ensures that sufficient relieving capacity is available for removing decay heat.

STARTUP and/or POWER OPERATION is allowable with safety valves inoperable within the limitations of the ACTION requirements on the basis of the reduction in secondary system steam flow and THERMAL POWER required by the reduced reactor ,

trip settings of the Power Level-High channels. The reactor trip setpoints are i determined from the most conservative value obtained from two methods. The I first method calculates setpoints based on the reduction in relieving capacity with the number of MSSVs inoperable and are derived as follows:

SP = (:X) - (Y) X ( Z% ) l X

where:

SP = Reduced reac' ;r trip setpoint in percent of RATED THERMAL POWER Z% = Total maximum safety valve relieving capacity of 102% power l steam flow X = Total relieving capacity of all safety valves per steam lint in lbs/ hour Y = Total maximum relieving capacity of the inoperable sarety valve (s ) in lbs/ hour. In each case, the valves with the greatest relieving capacity were assumed inoperable.

In the second method, the setpoint is detenmined from the Loss of Condenser Vacuum (LOCV) event. With + 3% MSSV tolerance, the LOCV event is analyzed with 1, 2, or 3 inoperable MSSVs on any steam generator, to determine the allowable initial power levels (and the trip setpoints) that yield acceptable results. For each of the inoperable MSSV conditions (1, 2, or 3 inoperable) in Table 3.7-1, the more conservative trip setpoint from the two analytical methods is selected.

ARKANSAS - UNIT 2 B 3/4 7-1 Amendment No. 4M,MO,M8,

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l- REACTOR COOLANT SYSTEM i SAFETY VALVES - SHUTDOWN LI)1ITING CONDITION FOR OPFJWfION 3.4.2 A minimum of one pressurizer code safety valve shall be OPERABLE with a lift setting of 2500 PSIA g_21tl,-3t*#, l l APPLICABILITY: MODES 4 and 5.

l ACTION:

With no pressurizer code safety valve OPERABLE, immediately suspend all 1

, operations involving positive reactivity changes and place an OPERABLE l- shutdown cooling loop into operation. ,

l SURVEILLANCE REQUIREMENTS I

I 4.4.2 No additional Surveillance Requirements other than those required l by Specification 4.0.5.

l j *The lift setting pressure-shall correspond to ambient conditions of the i

valve at nominal operating temperature and prsssure. If found outside of a i 1% tolerance band, the setting shall be adjusted to within i 1% of the

! lift setting shown.

l l # Equivalent relief capacity during MODE 5 satisfies the requirements of l this Specification. This allows both pressurizer code safety valves to be ,

removed for testing and/or maintenance.

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i ARKANSAS - UNIT 2 3/4 4-3 Amendment No. 449,444, s

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l REACTOR COOLANT SYOTEM i 1

i SAFETY VALVES - OPERATING LIMITING CONDITION FOR OPERATION l 1

3.4.3 All pressurizer code safety valves shall be OPERABLE with a lift setting 2500 peia 1,3+4 -4%*.

7 l l APPLICABILITY: MODES 1, 2 and 3.

ACTION:

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a. With one pressurizer code safety valve inoperabir, either restore l the inoperable valve to OPERABLE status within 15 minutes or be l in HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. j
b. The provisions of specification 3.0.4 may be suspended for one valve at a time for up to 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> for entry into and during operation in MODE 3 for the purpose of setting the pressurizer code safety valves under ambient (hot) conditions provided a preliminary cold setting was made prior to heatup.

SURVEILLNICE REQUIREMENTS l

4.4.3 No additional Surveillance Requirements other than those required by l Specification 4.0.5.

  • The lift setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure. If found outside of a 1 1% tolerance band, the setting shall be adjusted to within i 1% of the lift setting shown.

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} ARKANSAS - UNIT 2 3/4 4-4 Amendment No. 36,440, a

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3/4.7 PLANT SYSTEMS BASES 3'/ 4 . 7 .1 TURBINE CYCLE 3/4.7.1.1 SAFETY CYCLES The OPERABILITY of the main steam line code safety valves ensures that the secondary system pressure will be limited to within 110% of its design pressure of 1100 psia during the most severe anticipated system operational transient.

The maximum relieving capacity is associated with a turbine trip from 100% RATED THE" MAL PO9?F coincident with an assumed loss of condenser heat sink (i.e., no steam bypass to the condenser).

The specified valve lift settings and relieving capacities are in accordance with the requirements of Section III of the ASME Boiler and Pressure Code, 1971 Edition. The "as-found" requirements are consistenteoneeeve44ve with :::p::t t: l Section XI of the ASME Boiler and Pressure Vessel Code, 1986 Edition, and Addenda through 1987. The MSSV rated capacity oasses the full steam flow at 102% RATED Ther==1 Power (100% + 2% for instrument error) with the valves fully onen.8Phe tet:1 : li; ring ::;::ity f:: ;11 ." "'.' i: 10,000,000 lb/hr. Th; ?_'.'T 2 full ;;r :

(1000) st::: flex plu: OS f:: :::::: : tis i: 10,050,000 lb/hr. Th:: fere, the t:t:1 ;;li;;ing ::;;;ity ;f th; .""'.'; i: 110.32S ;f th; 1020 p;x;; ;t;;- fl;;

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A minimum of 2 OPERABLE safety valves per steam generator ensures that sufficient relieving capacity is available for removing decay heat.

STARTUP and/or POWER OPERATION is allowable with safety valves inoperable within the limitations of the ACTION requirements on the basis of the reduction in secondary system steam flow and THERMAL POWER required by the reduced reactor trip settings of the Power Level-High channels. The reactor trio setooints are determined from the most censervative value obtained fron two methods. The first haetooints based or the reduction in reLievina capacity with the nn=her of MSSVs inocerable and are c erived as follows:Th: ::::t:: trip ::tp: int eeelee46esw- ::: d::iv d :n th:

f;11;;ing h:::::

SP = (X) - (Y) x (J444v&G%,) l X

where SP = Reduced reactor trip setpoint in percent of RATED THERMAL POWER

= Total maximum safety valve relieving capacity of 102% power 1444v33% l steam flow X = Total relieving capacity of all safety valves per steam line in lbs/ hour Y = Total maximum relieving capacity of the inoperable safety valve (s) in lbs/ hour. In each case, the valves with the greatest relieving capacity were assr.med inoperable, i l

In the second method, the setooint is determined from the Loss of Condense r Vacuum (LOCV) event. With + 3% MSSV tolerance, the LOCV event is analyzec,with 1, 2. or 3 inonerable MSSVs on any steam aenerator, to determine the allowable l initial cower levels (and the trio setooints) that vield acceptable results. For each of the inoperable MSSV conditions (1, 2, or 3 inoperable) in Table 3.7-1, the more conservative trio setooint from the two analvtical methods is selected.

l ARKANSAS - UNIT 2 B 3/4 7-1 Amendment No. 440,449,448, a