ML17352A834

Proposed TS 3/4.7.1.1 & Associated Bases,Addressing Max Allowable Reactor Thermal Power Operation W/Inoperable MSSVs

ML17352A834
Person / Time
Site:	Turkey Point
Issue date:	10/20/1994
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17352A833	List: ML17352A832 ML17352A834
References
NUDOCS 9410260330
Download: ML17352A834 (9)

Text

ATTACHMENT 3 PROPOSED TECHNICAL SPECIFICATIONS Marked-up Technical Specification Pages:

3/4 7-1 3/4 7-2 B 3/4 7-1 Inserts A and B Insert for BASES 3/4.7.1.1 9410260330 941020 PDR ADDCK 05000250 PDR

3/4.7 PLANT SYSTEMS 3/4.7. 1 TURBINE CYCLE SAFETY VALVES LIMITING CONDITION FOR OPERATION

3. 7. 1. 1 All main steam line Code safety valves associated with each steam generator shall be OPERABLE with lift settings as specified in Table 3.7-2.

APPLICABILITY: MODES 1, 2, and 3.

ACTION: l<s<gT'A5- ke~

With (3) reactor coolant oops an assoc~a ed steam generators in oper with one or more main steam line Code safety valves inopera MODES 1, 2, and 3 may proceed provided, that wi operable valve is restored to OPERA

'urs, ration in either the in-s or the Power Range Neutron Flux High Trip Setpoint is re able 3.7"1; otherwise, be in at least HOT STANDBY withi ext 6 hours and in COLO SHUTDOWN within the following 30 h (O<t rwE)

SURVEILLANCE RE UIREMENTS 4.7. 1. 1 No additional requirements other than those required by Specification l~5<g~ ( 8 ke~~

TURKEY POINT - UNITS 3 8 4 3/4 7-1 AMENDMENT NOS.I37AND 132

L-94-223 Insert A With (3) reactor coolant loops and associated steam generators in operation and with one or more main steam line Code safety valves inoperable, and a ~ with a positive Moderator Temperature Coefficient, operation in MODES 1 and 2 may continue provided, that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, either=

the inoperable valve(s) is restored to OPERABLE status or reduce the Power Range Neutron Flux High Tzip Setpoint to the maximum allowable percent of RATED THERMAL POWER listed in Table 3.7-1; otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, or

b. with a negative or zero Moderator Temperature Coefficient, operation in MODES 1, 2, and 3 may continue provided, that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, either the inoperable valve(s) is restored to OPERABLE status or reduce power to less than or equal to the maximum allowable percent of RATED THERMAL POWER listed in Table 3.7-1; otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Insert B The provisions of Specifications 4.0.4 are not applicable foz entry into MODE 3.

TABLE 3.7-1 HAXIMUM ALLOWABLE POWER WITH INOPERABLE STEAM LINE SAFETY VALVES DURING THRE L OP OPERATION HAXIHUH NUMBER OF INOPERABLE MAX UM ALLOWAB P WE {tAH&E SAFETY VALVES ON ANY OPERATING STEAM GENERATOR PE ATEO T HAL POWER TABLE 3.7-2 STEAM LINE SAFETY VALVES PER LOOP ORIFICE SIZE VALVE NUMBER LIFT SETTING 21K " S UARE INCHES

~Loo A ~Loo B ~Loo C

1. RV1400 RV1405 RV1410 1085 psig 16

2. RV1401 RV1406 RV1411 1100 psig

3. RV1402 RV1407 RV1412 1115 psig 16

4. RV 1403 RV1408 RV1413 1130 psig 16 "The lift setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.

TURKEY POINT -, UNITS 3 Ec 4 3/4 7-2 AMENDMENT NOS.137 AND 132

p 4 e r r ~ i 4n w f

'p ~ ~ NV.iJ ',

e fA e8A mtwr 4 c = 1

~ <<) (. ) q~~

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3/4. 7 PLAHT SYSTEMS BASES 3/4. 7. 1 TURBINE CYCLE 3/4. 7. l. 1 SAFETY VALVES The OPERABILITY of the main steam line Code safety valves ensures that the Secondary System pressure will be limited to within 110K (1193. 5 psig) of its design pressure of 1085 psig during the most .severe anticipated system opera-tional transient. The maximum relieving capacity is associated with a Turbine trip from lOOX 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 VIII of the ASME Boiler and Pressure 'Code, 1971 Edition. The total relieving capacity for all valves on all of the steam lines is 10,670,000 lbs/h which is 111K of the total secondary steam flow of 9,600,000 lbs/h at 100K RATFD THERMAL POWER. A minimum of one OPERABLE safety valves per steam generator ensures that sufficient relieving capaci is avai lable for the allowable THERMAL POWER restriction in Table 3.7 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 Coolant System steam flow and THEltMAL POWER required by the reduced Reactor trip settings of the Power Range Neutron Flux channels. The Reactor Trip Setpoint reductions are derived on the following bases:

SP .. x (109) FP~l C wlwH Where:

l~ sCRv'P Reduced Reac r Trip Setpoint in percent of RATED THE L POWE Maximum nu er of inoperabl safety valv per ste line, 09 = Power R ge Neutron Flux- gh Trip Set int, X Total elieving capacit of all safe valves p r steam line in lbs/hour, and M imum relieving c acity of any one safety valve in bs/hour 3/4. 7. 1. 2 AUXILIARY FEEOWATER SYSTEM The OPERABILITY of the Auxiliary Feedwater System ensures that the Reactor Coolant System can be cooled down to less than 3504F from normal operating conditions in the event of a total loss-of-offsite power. Steam can be TURKEY POINT - UNITS 3 4 4 B 3/4 7-1 AMENDMENT NOS.137 AND 132

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p c<)

L-94-223 INSERT FOR TS BASES 3 4.7.1.1 (w h N)

Hi g = (100/Q)

K where:

Hi Reduced THERMAL POWER for the most limiting steam generator expressed as a percent of RTP Q Nominal Nuclear Steam Supply System (NSSS) power rating of the plant (including reactor coolant pump heat), Mwt K ~5 Conversion factor; 947.82 (Btu/sec)/Mwt ws Minimum total steam flow rate capability of the operable MSSVs on any one steam generator at the highest MSSV opening pressure (including tolerance and accumulation) (Lbm/sec) ~ For example, if maximum number of inoperable MSSVs on any one steam the generator is one, then ws should be a summation of the capacity of the operable MSSVs at the highest operable MSSV operating pressure, excluding the highest capacity MSSV. If the maximum number of inoperable MSSVs per steam generator is three, then ws should be a summation of the capacity of the operable MSSV at the highest opezable MSSV operating pressure, excluding the three highest capacity MSSVs.

hfg Heat of vaporization for steam at the highest MSSV opening pressure (including tolezance and accumulation) (Btu/ibm)

N Number of loops in plant The values calculated from this algorithm must then be adjusted lower for use in TS 3.7.1.1 to account for instrument and channel uncertainties.

Operation with less than all four MSSVs OPERABLE for each steam generator is permissible, if THERMAL POWER is proportionally limited to the relief capacity of the remaining MSSVs. This is accomplished by restricting THERMAL POWER so that the energy transfer to the most limiting steam generator is not greater than the available relief capacity in that steam generator.

0 N r