ML19257A538

Revised Auxiliary Feedwater Sys Tech Specs

ML19257A538
Person / Time
Site:	Prairie Island
Issue date:	12/31/1979
From:	NORTHERN STATES POWER CO.
To:
Shared Package
ML19257A535	List: ML19257A534 ML19257A537 ML19257A538
References
NUDOCS 8001040586
Download: ML19257A538 (7)

Text

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TS-i REV APPENDIX A TECHNICAL SPECIFICATIONS TABLE OF CONTENTS TS SECTION TITLE PAGE 1.0 Definitions TS.1-1 2.0 Safety Limits and Limiting Safety System TS.2.1-1 Settings 2.1 Safety Limit, Reactor Core TS.2.1-1 2.2 Safety Limit, Reactor Coolant System Pressure TS.2.2-1 2.3 Limiting Satety System Settings, Prot ec t ive TS.2.3-1 Instrumentation 3.0 Limiting Conditions for Operation TS.3.1-1 3.1 Reactor Coolant System TS.3.1-1 3.2 Chemical and Volume Control System TS.3.2-1 3.3 Engineered Safety Features TS.3.3-1 3.4 Steam and Power Conversion System TS.3.4-1 3.5 Instrumentation System TS.3.5-1 3.6 Containment System TS.3.6-1 3.7 Auxiliary Electrical Systems TS.3.7-1 3.8 Refueling and Fuel Handling TS.3.8-1 3.9 Radioactive Ef fluents TS.3.9-1 3.10 Control Rod and Power Distribution Limits TS.3.10-1 l 3.11 Core Surveillance Instrumentation TS.3.ll-1 3.12 Shock Suppressors (snubbers) TS.3.12-1 3.13 Control Room Air Treatment System TS.3.13-1 3.14 Fire Detection and Protection Systems TS.3.14-1 l 4.0 Surveillance Requirements TS.4.1-1 4.1 Operational Safety Review TS.4.1-1 4.2 Primary System Surveillance TS.4.2-1 4.3 Reactor Coolant System Integrity Testing TS.4.3-1 4.4 Containment System Tests TS.4.4-1 4.5 Engineered Safety Features TS.4.5-1 4.6 Periodic Testing of Emergency Power System TS.4.6-1 4.7 Main Steam Stop Valves TS.4.7-1 4.8 Steam and Power Conversion System TS.4.8-1 l 4.9 Reactivity Anomalies TS.4.9-1 4.10 Radiation Environmental Monitoring Program TS.4.10-1 4.11 Radioactive Source Leakage Test TS.4.ll-1 4.12 Steam Generator Tube Surveillance TS.4.12-1 4.13 Shock Suppressors (snubbers) TS.4.13-1 4.14 Control Room Air Treatment System Tests TS.4.14-1 4.15 Spent Fuel Pool Special Ventilation System TS.4.15-1 4.16 Fire Detection and Protection Systems TS.4.16-1 58%

1691 050 8o01o4o

TS.3.4-1 REV 3.4 STEAM AND POWER CONVERSION SYSTEM Applicability Applies to the operating status of the steam and power conversion system.

Objective To specify minimum conditions of steam-relieving capacity and auxiliary feed-water supply necessary to assure the capability of removing decay heat from the reactor, and to limit the concentration of activity that might be released by steam relief to the atmosphere.

Specification A. A reactor shall not be heated above 350 F unless the following conditions are satisfied:

1. Safety and Relief Valves

a. Rated relief capacity of ten steam system safety valves is available for that reactor, except during testing.

b. Both steam generator power-operated relief valves for that l reactor are operable.

2. Auxiliary Feed System

a. For single unit operation, the turbine-driven pump associated with that reactor plus one motor-driven pump are operable.

b. For two-unit operation, all four auxiliary feedwater pumps are operable,

c. Valves and piping associated with the above components i are operable except that during Startup Operation necessary changes may be made in motor-operated valve position. All such changes shall be under direct ad-ministrative control.

d. A minimum of 100,000 gallons of water is available in l the condensate storage tanks and A backup supply of river water is available through the cooling water system.

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, TS.3.4-2 REV

e. For Unit 1 operation motor operated valves MV32242 aad MV32243 l shall have valve position monitor lights operable and shall be locked in the open position by having the motor control center supply breakers manually locked open. For Unit 2, correspond-ing valve conditions shall exist.

f. Essential features including system piping, valves, and inter- l locks directly associated with the above components are operable.

g. Manual valves in the above systems that could (if one is im- l properly positioned) reduce flow below that assumed for acci-dent analysis shall be locked in the proper position for emergency l use. During power operation, changes in valve position will be under direct administrative control.

3. Steam Exclusion System Both isolation dampers in each ventilation duct that penetrates rooms containing equipment required for a high energy line rupture outside of containment shall be operable or at least one damper in each duct shall be closed.

4. Radiochemistry The iodine-131 activity of the water on the secondary side of either steam generator for that reactor does not exceed 0.30 uCi/cc.

B. If, during startup operation or power operation, any of the conditions of Specification 3.4. A. , except as noted below for 2.a or 2.b cannot be l

mat, startup operations shall be discontinued and if operability cannot be restored within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the af fected reactor shall be placed in the cold shutdown condition using normal operating procedures.

With regard to Specifications 2a or 2b, if a turbine driven AFW pump is not operable, that AFW pump shall be restored to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or the af fected reactor shall be cooled to less than 350 F within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. If a motor driven AFW pump is not operable, that AFW pump shall be restored to operable status within 7 days, or one unit shall be cooled to less than 350 F within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Basis A reactor shutdown from power requires removal of decay heat. Decay heat removal requirements are normally satisfied by the steam bypass to the con-denser and by continued feedwater flow to the steam generators. Normal feedwater flow to the steam generators is provided by operation of the turbine-cycle feedwater system.

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TS.3.4-3 REV The ten main stean safety valves have a total :ombined rated carability of 7,745,000 lbs/hr. The total full power steam flow is s ,094,000 lbs/hr; therefore, the ten main steam g total steam flow if necessary.gety valves will be able to relieve the In the unlikely event of complete loss of of tsite electrical power to either l or both reactors, continued removal of decay heat would be assured by avail-ability of either the steam-drivea cuxiliary feedwater pump or the motor-driven auxiliary feedwater pump associated with each reactor, and by steca discharge to the atmosphere through the main steam safety valves.

One auxiliary feedwater pump can supply suf ficient feedwater for removal of decay heat from one reactor. The motor-driven auxiliary feedwater pump for each reactor can be made available to the other reactor.

The minimum amount of water specified for the condensate storage tanks is sufficient to remove the decay heat generated by one reactor in the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of shutdown. Essentially unlimited replenishment of the condensate storage supply is available from the intake structures through the cooling water system.

The two power-operated relief valves located upstream of the main steam isolation valves are required to remove decay heat and cool the reactor down following a high energy line rupture outside containment (2). Isolation dampers l are required in ventilation ducts that penetrate those rooms containing equip-ment needed for the accident.

The secondary coolant activity is based on a postulated release of the contents of one steam generator to the atmosphere.(3) This could happen, for example, l as a result of a steam break accident combined with failure of a steam line isolation valve. The limiting dose for this case results from iodine-131 because of its low MPC, and because its long half-life relative to the other iodine isotopes results in its greater concentration in leakage fluid. The accident is assumed to occur at zero load when the steam generators contain maximum water. With allowance for plate-out retention of iodine in water droplets, one-tenth of the contained iodine is assumed to reach the site boundary. The maximum inhalation dose at the site boundary is then as follows:

Dose (rem) = C V

• B(t) X/Q DCF 10 Where: C = secondary coolant activity, 0.30 uCi/cc 3

V = water volume in one steam generator = 3510 ft = 99 M3

-4 B(t) = breathing rate, 3.47 x 10 g3 /sec X/Q = 9.8 x 10

-4 j,3 6

DCF = 1.50 x 10 rem /Ci I inhaled The resulting dose is 1.5 rem.

References -

(1) FSAR, Section 10.4 (2) FSAR, Appendix I (3) FSAR, Section 14 1691 053

TS.4.8-1 REV 4.8 STEAM AND POWER CONVERSION SYSTEMS Applicability Applies to periodic testing requirements of the auxiliary feedwater, steam generator power operated relief valves, and steam exclusion systems.

Objective To verify the operability of the steam and power conversion systems required for emergency shutdown cooling of the plant.

Specification A. Auxiliary Feedwater System

1. Each motor-driven auxiliary feedwater pump shall be started at intervals of one month and full flow to the steam generators shall be demonstrated once every refueling shutdown.

2. The steam turbine-driven auxiliary feedwater pump shall be started at intervals of one month and full flow to the steam generators shall be demonstrated once each year when steam from the steam generators is available.

3. The auxiliary feedwater pumps discharge valves shall be tested l by operator action at intervals of one month.

4. Motor-operated valves required to function during accident l conditions shall be tested at intervals of one month.

5. These tests shall be considered satisfactory if control board l indication and subsequent visual observation of the equipment demon-strate that all components have operated properly.

6. During power operation, for the manual valves outside containment, that could reduce AFW flow, if improperly positioned, to less than assumed in the accident analysis, monthly inspection are required to verify the valves are locked in the proper position required for emerency use.

7. After each cold shutdown and prior to exceeding 10% power, a test is required to verify the normal flow path from the primary AFW source to the steam generators. This test may consist of maintaining steam generator level during startup with the auxiliary feed pumps.

B. Power Operated Relief Valves Each power operated main steam relief valve shall be isolated and tested monthly.

1691 054

TS.4.8-2 REV C. Steam Exclusion System Isolation dampers in each duct that penetrates rooms containing equipment required for a high energy line rupture outside of con-t ainme nt shall be tested for operability once each month.

In addition, damper mating surfaces will be examined visually at each reactor refueling shutdown to assure that no physical change has occurred that could af fect leakage.

Basis Monthly testing of the auxiliary feedwater pumps, monthly valve inspections, and startup flow verification provide assurance that the AFW system will meet emergency demand requirements. The discharge valves of the pumps are normally open, as are the suction valves from the condensate storage tanks. Proper opening of the steam admission valve on each turbine-driven pump will be demonstrated each time a turbine-driven pump is tested. Ventilation system l isolation dampers required to function for the postulated rupture of a high energy line will also be tested.

Re ference FS AR, Sect ions 6.6,14, and Appendix I.

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