ML18057A528

Proposed Tech Specs Re Description of Primary Coolant Sys

ML18057A528
Person / Time
Site:	Palisades
Issue date:	10/04/1990
From:	CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML18057A527	List: ML18057A526 ML18057A528
References
NUDOCS 9010170109
Download: ML18057A528 (7)

Text

ATTACHMENT I Consumers Power Company Palisades Plant Docket 50-255 PROPOSED TECHNICAL SPECIFICATION PAGE CHANGE October 4, 1990 I Page

5.2 CONTAINMENT DESIGN FEATURES (Cont'd) 5.2.2 Penetrations

a. All penetrations through the steel-lined concrete structure for electrical conductors, pipe, ducts, air locks and doors are of the double-barrier design.

b. The automatically actuated containment isolation valves are designed to close upon high radiation or high pressure in the containment structure. No single component failure in the actuation system will prevent the isolation valves from functioning as designed.

5.2.3 Containment Structure Cooling Systems

a. The containment air cooling system includes four separate self-contained units which cool the containment air during normal operation and limit the pressure rise in the event of a design accident. Three units, each with a cooling water flow of 4875 gpm with an inlet temperature of 75°F, will remove 229 x 10 6 Btu/hr of heat.

b. The containment spray system is capable of removing 233 x 10 6 Btu/hr (two pumps) from the containment atmosphere at 283°F by spraying the water from the 270,000-gallon SIRW tank.

Recirculation of spray water from the containment sump through heat exchangers into the. containment atmosphere is also provided.

Under this mode of operation, the heat removal capability is 167 x 10 6 Btu/hr based upon 4000 gpm of component cooling water flow with 114°F inlet temperature through the heat exchanger and 1420 gpm of spray water flow at 283°F inlet temperature.

5.3 NUCLEAR STEAM SUPPLY SYSTEM (NSSS) 5.3.1 Primary Coolant System Design Pressure and Temperature The primary coolant system is designed, and shall be maintained:

a. In accordance with the Code requirements specified in Section 4.2 of the FSAR with allowance for normal degradation pursuant to the surveillance requirements,

b. For a pressure of 2500 psia,

c. For a temperature of 6-50°F' except the pressurizer which shali be 700°F, and

d. With a volume of approximately 10,900 cubic feet.

5-2 Amendment No.

TSPR5-2

ATTACHMENT 2 Consumers Power Company Palisades Plant Docket 50-255 MARKED UP TECHNICAL SPECIFICATION PAGES October 4, 1990 1 Page

• 5.2 5.2.2 CONTAINMENT DESIGN.FEATURES (Contd) -

Penetrations

a. *All penetrations through the steel-lined concrete structure for electrical conductors, pipe, ducts, air locks and doors are of the double-barrier design.

b. The autamati~a.lly actuated containment isolation valves are designed to cJ.ose upon high radiation or high pressure in the containment structure.

• No single component fail.ure in the actuation system will prevent the isolation valves from functioning as designed.

Containment Structure Cooling Systems

a. The containment air cooling system includes four separate self-contained units vhich cool the containment air during normal opera-tion and limit the pressure rise in the event of a design accident.

Three units, each with a cooling water flow of 4875 gpm with an 6

inlet temperature of 75°F, will remove 229 x 10 Btu/hr of heat.

b. The contairnnent spr&Y' system is capable of removing 233 x io 6 Btu/hr (two pumps} from the containment atmosphere at 283°F by sp~ the

• water from the 270, 000-gallon SIRW tank. Recirculation of spr&Y"

• water. from the containm8nt sump through heat exchangers into. the

.containment atmosphere is al.so provided.

Under this mode of operation, the heat. removal capability is 6

167 x 10 Btu/hr based upon 4oOO gpm ot component cooling vater flow vi th U4 °F inJ.et temperature through the heat exchanger and 1420 gpm of spr&Y' water flow at 283°F inl.et temperature.

5.3 NUCLF.AR STF.AM SUPPLY SYSTEM (NSSS.}.

5.3.1 eo *. 'mie pl'1m""'¥. eeele.nt ey&tem eh'JJ be aeei.889d ead eeastl"l:letea ia aeeerdsnee wUh *ae ASMB Beiler- aad Pressure Veeeel Gede, See=

tioa III, Rq:;es toz eonstI tzeticm ot !uclesr YeHela, inelttcliftg a:il*

addenda th:roi:gb the winter ot ~965, and the ASA Oode. tor Preestare Fiptng B31. l:'.

'b. '&e pri:mary eeelaa11 s,.a1:1em e&all ee aesigaed ter a pl'eeeve at 25ee paia and a tempezseue ot 650°¥ except tor the preHom-her w&ieh sas 11 B:a¥e a aea:l:gn 'bemper&'btsre of 100°F.

e. !he

• l'Clmne of the prima::ry eeelaa11 system s88:ll ee app!'elWllSitl eJ:y 10,900 elihie teet'*

ATTACHMENT 3 Consumers Power Company Pa 1i sades Pl ant Docket 50-255 DRAFT FINAL SAFETY ANALYSIS REPORT PAGE CHANGE October 4, 1990 2 Pages

1. 200 cycles of loss of turbine lo~d from 100% power

2. 200 cycles of total loss of reactor coolant flow when at 100% power

3. 2 cycles of loss of secondary system pressure 4.2.3 DESIGN SERVICE LIFE CONSIDERATIONS The major Primary Coolant System components are designed considering a 40-,year service life. In order to achieve this, the strict quality control assurance staridards as outlined in Subsections 4.5.4 and 4.5.S were followed.

Component design has also considered environmental protection, adherence to established operating procedures and irradiation 'effects on the material.

The reactor vessel is the only component of the Primary Coolant System which is exposed to a significant level of neutron irradiation. The irradiation surveillance program is outlined in Subsection 4.5.3. To com-pensate for any ins,rease in the NDTT shift caused by irradiation, the Plant

. operating procedures for the pressure-temperatu*re relationship during heatup and cooldown will be periodically r'evised to stay within the stress limits.

The design of the Primary Coolant System components allows for adequate inspection techniques to be applied over the lifetime o-f the Plant. All reactor internals are designed to be removable for inspection and to allow reactor vessel internal inspection. Insulation panels are ~emovable for external inspection of selected highly stressed areas.

4.2.4 CODES ADHERED TO AND COl1PONENT CLASSIFICATION The design, fabrication, construction, inspection, testing and clas~ifi cation of all reactor coolant system components are in accordance with the ASME Boiler and Pressure Vessel Code,Section III, 1965 edition, including all addenda through Winter.1965 (ASHE B&PV Code, Section'lII, 1965, W65a),

and the Code for Pressure Piping, ASA B31.1, 1955. ..,.....,..-: °"A

_J-NSE:l(1 IT The codes adhered tq and component classifications Tab~e 4-2.

4.2.S SAFETY CONSIDERATIONS OF DESIGN PARAMETERS Design Pressure After establishin-g the normal opera-ting pressure conditions of the Primary Coolant System, a minimum design pressure was determined which exceeds the normal operating pressure and anticipated operating transient pressure changes.*

Major considerations employed in the determination of this selected minimum design pressure include: :normal operating pressure, instrumentation and control response, reactor core thermal lag, coolant transport time, system fs0981-0492a-09-72 4.2-2 Rev 0

Insert "A" Replacement parts and components will satisfy the requirements of the original Plant construction code in a manner that is consistent with 10 CFR 50.55a, and the rules and requirements specified in ASME B&PV Code,Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components", Article IWA-7000.