ML18057A714

Proposed Tech Specs Re Pressurizer Safety Valve Setpoint

ML18057A714
Person / Time
Site:	Palisades
Issue date:	01/17/1991
From:	CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML18057A713	List: ML18057A712 ML18057A714
References
NUDOCS 9101290048
Download: ML18057A714 (3)

Text

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ATTACHMENT Consumers Power Company Palisades Plant Docket 50-255 TECHNICAL SPECIFICATIONS CHANGE REQUEST PRESSURIZER SAFETY VALVE SETPOINT ADDITIONAL INFORMATION Proposed N~w Pages January 17, 1991 2 Pages

04R 91011 7

• 9101290 ~ 05000255 pt,1R p

1 ADOCK PDR- \. .

3.1 PRIMARY COOLANT SYSTEM (contd)

The oxygen and halogen limits specified are at least an order of magnitude below concentration which could result in damage to the materials found in the primary coolant system even if maintained for an extended period of time.<~ Thus, the period of eight hours to initiate corrective action to restore individual concentrations within the limits, or 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to restore both concentrations has been established.

If the corrective action has not been effective at the end of the 24-hour period, then the reactor will be brought to the hot shutdown condition and the corrective action will continue. If, at the end of a

• further 24-hour period, the corrective action has not been effective,

• long-term corrective action could be required and the reactor will be brought to the cold shut down condition.*

References (1) FSAR, Section 4.3~11, 4.3.13.

(2) FSAR, Section 9.10.

(3) Corrosion &Wear Handbook, O.J.DePaul, ~ditor 3~J.7 Primary.and Secondary Safety Valves Specifications

a. The reactor shall not be mada critical unles~ all three -

pressurizer safety valves are operable with their lift settings maintained between 2500 . psia and 2580 psia .

(t 3%).

b. ~ minimum of one operable safety valve shall be installed on the pressurizer wh~never the reactor head is on the vessel.

c. Whenever the reactor is in power operation, a minimum of 23 secondary system safety valves shall be operable with their lift settings between 985 psig (+/- 30 psig) and 1025 (+/- 3%) psig.

3-24 Amendment No. ~J, JJ,, JJ~,

TSPR9017

3.1 PRIMARY COOLANT SYSTEM (Contd)

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sas-1-s---- ---------- -------------------- ------- -------------- ------ ------ -- ----- -- ------ --:-----

The primary and secondary safety valves pass sufficient steam to limit .

the primary system pressure to 110 percent of design (2750 psia) following a complete loss of turbine generator load w1thout simultaneous reactor trip while operating at 2650 MWt. <1 >

• The reactor is assumed to trip on a "Hi~h Primary Coolant System Pressure" si~nal. To determine the maximum steam flow, the only other pressure relieving system assumed operational is the secondary system

~afety valves. Conservative values for all system parameters, delay times and core moderator coefficient are assumed. Overpressure protection is provided to the portions of the primary coolant system

• which are at the highest pressure considering pump head, flow pressure drops and elevation heads. .

If no residual heat were removed by any of the means available, the

• amount of steam which could be generated* at safety valve lift pressure*

would be less than half of o~e valve's- capacity. One valve, therefore, provides adequate defense against overpressurization when the reactor is subcritical. .

• The total 6 relief capacity of the 24 secondary system safety valves is 11.7 x 10 lb/h. Jhis is based on a steam flow equivalent to an NSSS power level_ of 2650 MWt at the nominal lOQO psia valve lift pressure.

At the power rating of 2530 MWt, a relief capacity of less than 11.2 x 106 lb/h is required to prevent overpressurization bf the secondary system of loss of load conditions, and 23 valves provide 1

relieving capabtlity of 11.2 x 106 lb/h.< ~>. * -

The overRressurization analysis for the loss of load event< 2 > for Cycle 8< supports the specified secondary safety valve lift pressure tolerance. 3The overpressurization analysis for the Loss of Load event*

for Cycle 9< > supports the specified primary safety valve lift pressure tolerance of +3% and accounts for the new Steam Generators. ASME B&PV Code, 1986 edltion, Section x1 subsection IWV-3500i s~ecifies ANSl/ASME OM-1-1981 requirements which a1low the specified to erances in the lift pressures of the safety valves.

• l l.

-- Refer-ences , - - - - -- - -- - -

Updated FSAR, Section 4.3.4 and 4.3.9.4 , .

!2 3

ANF-87-150(NP), Volume 2, Section 15.2.1 Advanced Nuclear Fuels Corporation Report ANF 90-078 "Palisades Cycle9: Analysis of Standard Review Plan Chapter 15 Events September 25, 1990 3-25 Amendment No. ~J, lJ~, JJ~,

- TSPR9017