ML18079A250

Forwards Updated Listings of Items,Including Preoperational Tests Which May Not Be Completed Until After Initial Fuel Loading.Requests Deferral of Incomplete Test Items

ML18079A250
Person / Time
Site:	Salem
Issue date:	05/04/1979
From:	Mittl R Public Service Enterprise Group
To:	Parr O Office of Nuclear Reactor Regulation
References
NUDOCS 7905090308
Download: ML18079A250 (6)

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PS~G Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 Phone 201 /430-7000 May 4, 1979 Director of Nuclear Reactor Regulation

u. S. Nuclear Regulatory Commission Washington, D.C.

20555 Attention:

Gentlemen:

Mr. Olan D. Parr, Chief Light Water Reactors Branch 3 Division of Project Management REQUEST FOR DEFERMENT INCOMPLETE ITEMS NO. 2 UNIT SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-311 Public Service Electric and Gas Company hereby transmits updated listings of items including pre-operational tests which may not be complete until after initial fuel loading.

This updates and supersedes our letter of April 9, 1979.

Safety evaluations are provided illustrating that the incomplete-ness of these items at the time of plant readiness.for initial fuel loading will have no adverse effect of the health and safety of the general public or station personnel.

The lists designated as Attachments 1 and 2 identify those items which will be completed prior to and after initial criticality, respectively.

We have concluded that the items in the attachments do not involve an unreviewed safety question and will have no effect on the safe operation and reliability of the plant.

Should you have any questions in this regard, please do not hesitate to contact us.

Enclosure

?1ili1s, R. L. Mittl General Manager -

Licensing and Environment Engineering and Construction Department 7 905 0 90 3og

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95-2001 (200M) 2-78

ATTACHMENT #1 (Revision #3)

DESCRIPTION

1.

System:

Condenser Air Removal and Priming The operational testing of the crosstie with Unit 1 will not be completed.

2.

Valve 24MSl5 (Main Steam Safety)

Valve was gagged during HFT.

3.

Radiation Monitoring The following radiation monitoring channels will not be operational until after core load, but will be in service prior to initial criti-cality:

ITEMS TO BE COMPLETED PRIOR TO INITIAL CRITICALITY SAFETY EVALUATION Page 1 The Condenser Air Removal and Priming System is not safety related.

The Unit 1 crosr.tie does not affect operation of the system, but is installed for operational flexibility and serves no safety function.

The valve will be repaired prior to core load.

Valve testing will require Main Steam System partial pressure; the remaining portion of system pressure will be simulated by mechanical assist.

Therefore, the valve will not be untested before the system reaches its maximum pressure.

This procedure, coupled with the other safety valves in the line, adequately ensures over-pressurization protection.

This will not detrimentally affect system function or plant safety.

These deferred radiation monitors are utilized for the detection of potential radioactivity introduced in the process systems and are not required until after initial criticality.

The containment monitor (2R21) has high range capability and is not required until power opera-tion.

The deferment of these items will not endanger personnel, plant safety and public safety.

Sufficient monitoring capabilities exist for core load and all activities up to initial criticality through the follow-ing monitors which will be operational:

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ATTACHMENT #1 (Revision 3)

DESCRIPTION 2Rl9A No. 21 Stm. Gen. Blowdown 2Rl9B No. 22 Stm. Gen. Blowdown 2Rl9C No. 23 Stm. Gen. Blowdown 2Rl9D No. 24 Stm. Gen. Blowdown 2R21 Containment 2R31 Letdown Line 2R35 Stm. Gen. Blowdown Discharge 2Rl5 Condenser Air Ejector 2R40 Condensate Polishing 2Rl6 Plant Vent (Gross)

4.

System:

Emergency Diesel Generator The 23 consecutive start tests for diesels 2b and 2c will not be com-pleted until prior to initial criticality.

The 23 consecutive start tests have been euceeefully completed for diesel ?a.

ITEMS TO BE COMPLETED PRIOR TO INITIAL CRITICALITY SAFETY EVALUATION 2RlA Control Room 2RlB Control Room Intake Duct 2R2 Containment 2R5 Fuel Handling Bldg.

2R7 Incore Seal Table 2R9 Fuel Storage Area 2RlOA Perso~nel Hatch El. 100' 2RlOB Personnel Hatch El. 130' 2RllA Containment Sampling - Particulate 2Rl2A Containment Sampling -

Gaseous 2Rl2B Containment Sampling -

Iodine 2R32A Fuel Handling Crane 2R32B Cask Handling Crane 2R41A Plant Vent Sampling -

Particulate 2R41B Plant Vent Sampling -

Iodine 2R41C Plant Vent Sampling -

Gaseous 2R34 Penetration Area 2R4 Charging Pump Room 2Rl3A No. 21 Fan Coil Unit Cooling 2Rl3R No. 22 & 24 ~an Coil Unit Cooling

?Rl3C No. 23 & 25 Fan Coil Unit Cooling 2Rl7A Component Cooling Loop 21 2Rl7B Component Cooling Loop 22 2R29 Spent Fuel Pit Skimmer Filter Page 2 In addition, health physics personnel will perform radiation surveys to verify that no radiation hazards exist.

The 2Rl6 Monitor is re-dundant to 2R41C which is in service and will have no effect on system operations.

Diesel generator testing and demonstration of increased reliability are now underway.

All testing will be completed prior to Core Load except the 23

~onsecutive starts per diesel for diesels 2b and 2c.

These tests, as delineated in Regulatory Guide 1.108, will be completed prior to initial criticality.

These diesel generators have demonstrated their reliability in previous component and system tests.

These units are not prototypes, and are.

identical to ~hose used in No. 1 Unit, which have shown a high degree of reliability.

Consequently, completion of these tests prior to initial criticality will have no effect upon the safe operation of the plant.

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ATTACHMENT #2 (Revision 3)

ITEMS TO BE COMPLETED PRIOR TO INITIAL CRITICALITY Page 1

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S_A_FJo: TY EV A LU A TI ON

1.

System:

Radiation Monitoring All monitors will be installed prior to initial criticality.

The following monitors will be operational as required for public safety and to support activities from initial criti-cality through commercial operation.

These monitors are:

a.

2Rl8 Liquid Waste Disposal 2R36 Evaporator and Feed Preheater Condensate

b.

2R42A Gas Decay Tank 21 2R42B Gas Decay Tank 22 2R42C Gas Decay Tank 23 2R42D Gas Decay Tank 24 These monitors will be completed to support radwaste system operation and prior to liquid waste discharges in accordance with the Environmental Tech. Specs.

These monitors are utilized for gross indication of radiation levels in the gas decay tanks.

Until these monitors are operational, health physics surveys will be performed to check radiation levels.

The tanks are adequately shielded and protected from personnel and present no safety hazard.

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ATTACHMENT #2 (Revision 3)

DESCRIPTION

c.

2R24A, B Seal Water Injection Filter 2R25 Seal Wnter Filter 2R~6 Reactor Coolant Filter 2R~7 Liquid Waste Filter 2R33 Ion Exchanger Filter 2RJ8 Steam Generator 8lowdown Filter

d.

2R28 Spent Fuel Pit Filter 2R30 Refueling Water Purification Filter

e.

Display Functions

2.

System:

Circulating Water The operational tests of circulators 218, 228, and 23A will not be completed.

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ITEMS TO BE COMPLETED PRIOR TO INITIAL CRITICALITY Page 2 These monitors are utilized to provide indication of filter concentrations, until these monitors are operational, health physics surveys will be performed to check radiation levels.

The filters are adequately shielded and protected from personnel and present no safety hazard.

These monitors are utilized for spent fuel storage and handling operations and will be completed prior to handling spent fuel, thereby presenting no safety hazard.

Radiation monitoring display functions required for operator information on radiation levels and alarms will be operational prior to initial criticality.

Miscellaneous display functions for operator convenience will not be operational until after initial criticality.

These functions have no effect on plant operations or public safety.

The operation of the Circulating Water System is not a safety related function.

Three of the six circulators have been tested and accepted and are available for Mode I operation.

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ATTACHMENT //2 (Revision 3)

DESCRIPTION

3.

SUP 50.~o, Initial Synchronization of Generator, will not be performed until after Initial Criticality.

4.

Waste Disposal -

Liquid SUP 16.2 -

Liquid Wnste Processin~

Waste Evaporator will not be completed until after Initial Criticality.

I I'l'EMn *rn 1n: COMPLETED AVT~R INrTIAL CRITICALITY SAFETY EVALUATION

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The Generator was run at 1800 RPM during !lot Functional Testing, but was not synchronized.

Synchronization after Initial Criticality will not affect the safe operation of* reliability of the system.

The operation of Salem Unit No. 2 without an available Liquid Waste Evaporator prior to power operation will have no affect upon the safe operation of the plant for the following reasons:

1.

The radioactivity levels in the plant from initial core load up through zero power testing are very low.

Operation of the waste evaporator during this period would not be required to meet ALARA criteria for radioactive releases.

2.

The Unit No. 2 evaporator will be operational prior to going beyond zero power testing (prior to Mode I)

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