ML18079A547
| ML18079A547 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 07/06/1979 |
| From: | Mittl R Public Service Enterprise Group |
| To: | Parr O Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7907170028 | |
| Download: ML18079A547 (3) | |
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PS~G Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 Phone 201 /430-7000 July 6, 1979 Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission
~ashington, D. c.
20555 Attention:
Mr. Olan D. Parr, Chief Light Water Reactors Branch 3 Division of Project Management Gentlemen:
REQUEST FOR DEFERMENT INCOMPLETE ITEMS NO. 2 UNIT SALEM NUCLEAR GENERATING DOCKET NO. 50-311 STATION 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 May 4, l979.
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 Attaclunents 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 The Energy People
?{j:;r;ors, R. L. Mittl General Manager -
Licensing and Environment Engineering and Construction
~°£' 1/1 i907170D<f 95-2001 (400M) 9-77
ATTACHMENT #1 (Revision #4)
DESCRIPTION
- l.
- 2.
Valve 24MS15 (Main Steam Safety)
Valve was gagged during HFT.
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:
2Rl6
- 2R21 2R31 2R40 Plant Vent (Gross)
Containment (High Range)
Letdown Line (Failed Fuel)
Condensate Polishing EAL:kd 7/5/79 ITEMS TO BE COMPLETED PRIOR TO n:rrIAL CRITICALH'Y SAFETY EVALUATION The valve has been repaired.
Valve testing will require Main Steam System par~ial pressure; the remaining pcrticn of s:;stem 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 overpressurization protection.
This will not detrimentally affect system function or plant safety.
'l'hese deferred radiation monito:::-s are utilized for the detection of potential radioactivity introduced in the process systems and are not required until after initial criticality.
The contain-ment monitor (2R21) has high range capability and is not required until power operation.
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 following monitors which will be operational:
2RlA 2RlB 2R2 2R4 2i:5 2R7 2R9 2Rl0A 2RllA 2Rl2A 2Rl2B 2Rl3A 2Rl3B 2Rl3C 2Rl5 2Rl7A 2Rl7B 2Rl9A 2Rl9B 2Rl9C 2Rl9D 2R26 2R27 2R29 2R32A 2R32B 2R33 2R34 2R35 2R36 2R38 2.R41A 2:RCB 2R41C 2R42A 2R42B 2R42C 2R42D Control Room Control Room Intake Duct Containment Changing Pum~ Room Fuel Handling Building Incore Seal Table Fuel Storage Area Personnel Hatch El. 100' Containment Sampling - Particulate Containment Sampling -
Gaseous Containment Sampling - Iodine No. 21 Fan Cooler Cooling No. 22 and No. 24 Fan Cooler Cooling No. 23 and No. 25 Fan Cooler Cooling Condenser Air Ejector Component Cooling Loop 21 Component Cooling Loop 22 No. 21 Steam Generator Blowdown No. 22 Steam Generator Blowdown No. 23 Steam Generator Blowdown No. 24 Steam Generator B~owdown Reactor Coolant Filter Liquid Waste Filter Spent Fuel Pit Skimmer Filter Fuel Handling Crane Cask Handling Crane Ion Exchange Filter Penetration Area Steam Generator Blowdown Discharge Evap and Feed Preheater Condensate Steam Generator Blowdown Filter Plant Vent Sampling - Particulate Plant Vent Sampling -
Iodine Plant Vent Sampling -
Gaseous No. 21 Gas Decay Tank No. 22 Gas Decay Tank No. 23 Gas Decay Tank No. 24 Gas Decay Tank In addition, health physics personnel will perform radiation surveys to verify that no radiation hazards exist.
The 2Rl6 Monitor is redundant to 2R41C which is in service and will have no effect on system operations.
. ATTACHMENT # 2 (Revision 4)
DESCRIPTION
- 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
- b.
2R24A, B*seal Water Injection Filter 2R25 Seal Water Filter
- c.
2R28 2R30 Spent Fuel Pit Filter Refueling Water Purification Filter
- d.
Display Functions
- 2.
System:
Circulating Water The operational tests of circulators 21B, 22B and 23A will not be completed.
- 3.
SUP 50.20, Initial Synchronization of Generator, will not be performed until after Initial Criticality.
EAL:kd 7/5/79 ITEMS TO BE COMPLETED AFTER I!UTIAL CRITICALITY SAFETY EVALUATION This monitor will be completed to support radwaste system operation and prior to liquid waste discharges in accordance with the Environmental Technical Specifications.
These monitors are utilized to provide indication of filter concentrations.
Until these monitors are operational, health physics surv~ys will be performed to check radiation l'vels.
The filters are adequately shielded and protected from personnel and pres*ent 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.
Tqese 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.
The Generator was run at lBOO RPM during* Hot Functional Testing, but was not synchronized.
Synchronization after Initial Criticality will not affect the safe operation of reliability of the system.