ML18078B107
| ML18078B107 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 03/28/1979 |
| From: | Mittl R Public Service Enterprise Group |
| To: | Parr O Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7903300257 | |
| Download: ML18078B107 (8) | |
Text
Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 Phone 201 /430-7000 March 28, 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 In accordance with the requirements of 10CFRSO.SS(d) of the Commission's regulations, PSE&G hereby transmits a listing of incomplete preoperational tests and other items for which deferment until after initial fuel loading is anticipated.
A review of our FSAR commitments has identified a small number of balance of plant or safety related items that will not be completed prior to plant readiness for initial fuel loading.
We have evaluated these items and have determined that the incomplete status of these items at the time of plant readiness for initial fuel loading will have no adverse effect on the health and safety of the general public or station personnel.
Attachments 1 and 2 identify those items which will be completed prior to and after initial criticality, respectively.
The lists include our safety evaluation of the deferment of completion of the items.
We have concluded that the items identified in the attachments do not involve an unreviewed safety question and will have no effect on the safe operation and reliability of the plant.
7 9 0 3 30 0 251 The Energy People 95-2001 (400M) 9-77
Director of Nuclear Reactor Regulation Mr. Olan D. Parr, Chief March 28, 1979 Page 2 Should you have any questions in this regard, please do not hesitate to contact us.
Enclosure Very truly yours,
- t:/fL~
R. L. Mittl General Manager -
Licensing and Environment Engineering and Construction
ATTACf-:.~:~T #1 (Revis ion #1)
ITEMS*TO BE CONPLETED PRIOR TO INITIAL CRITICALITY
- C.ESCRIFTION
- l.
Waste Disposal The following tests will not be completed until after core load.
16.l - Liquid Waste Receipt and
. Storage (portions only) 16.6 - Gaseous Waste Processing
- 2.
Valve 24MS15 (Main Steam Safety)
Valve was gagged during HFT.
- 3.
Radiation Monitoring The following radiation monitoring channels will not be operational until after core load:
2RllA-Containment Sampling Particulate 2Rl2A-Containment Sampling Gaseous 2Rl2B-Containment Sampling Iodine 2RlA-Control Room SAFETY EVALUATION These systems are riot required for safe shutdown of the plant, and no r~dioactive waste is generated until after initial criticality.
Functionai testing of these system~
can therefore be deferred until after core load e
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.
Therefo~e, 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 monitors perform redundant functions to units that will be in service prior to core load.
The Control *room monitoring is provided by monitor 2RlB, Control Room In-take Vent Duct.
Containment Ventilation releases would be monito.red by the Plant Vent Sampling System Chann~~
2R41A, B and c.
The following additional monitors w~
also be in service for core load:
2R2 Containment Area 2R5 Fuel Handling Area 2R7 Incore Seal.Table 2R9 Fuel Storage Area 2RlOA Personnel Hatch 2RlOB Personnel Hatch El.100, El.130
(Revision #1)
- C.ESCRIPTION ITEMS TO DE COMPLETED PRIOR TO INITIAL CRITICALITY SAFETY EVALUATION The above monitors *provide sufficient monitoring for personnel, plant safety and public safety during core load and all activities up to i'riitial criticality.
In addition, h~alth physics personnel will perform radiation surveys to verify that no.radiation hazards exist.
1-.':'Ii-.C~:!*::=!;T #2
. (Revis io!'l 1)
ITEMS TO BE COI*::PLETED AFTER INITIAL CRITICALITY DESCRIPTimJ
- 1.
System:
Radia'tion Monitoring**
All monitors will be installed prior to initial criticality.
Those monitors which are needed for operations and public safety will be tested and placed in operation prior to.initial criticality.
The remaining monitors will be completed as required to support activities from initial criticality through commercial operation.
These monitors are:
- a.
- b.
- o.
- d.
2Rl5 2R40 2Rl8 2R36 2Rl6 2R42A 2R42B 2R42C 2R42D Condenser Air Ejector Condensate Polishing Area Liquid Waste Disposal Evaporator and Feed Preheater Condensate Plant Vent (Gross)
Gas Decay Tank 21 Gas Decay Tank 22 Gas Decay Tank 23 Gas Decay Tank 24 SAFETY EVALUATION These monitors are concerned with radiation levels in the secondary side {steam) systems and will be completed for power acension testing.
These monitors will be completed to support radwaste system operation and prior to liquid waste discharges in accordance witn the Environmental Tech. Specs.
This monitor is redundant to monitor Channel 2R41C, Plcl:
Vent-Gaseous, which will be in s~~v~oe qnd has no effect on system operations.
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.
- e.
- f.
(Revision 1)
.ITEMS TO BE COMPLETED JffTER INITIAL CRITICALITY
~*
\\
D:: SC?. IP TI m!
SAFETY EVALUATION
- 2R24A, 2R25*
2R26 2R27 2R33 2R38 2R28 2R29 2R30 2R32A 2R32B B
Seal Water Injection Filter Seal Water Filter.
Reactor Coolant Filter Liquid Waste Filter Ion Exchanger Filter Steam Generator Blowdown Filter Spent Fuel Pit Filter Spent Fuel Pit Skinuner Filter Refueling Water Purification Filter Fuel Handling Crane Cask Handling Crane 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.f.uel storag'e9 and handling operations and will be completed prior to handling spent fuel, thereby presenting no safety hazard.
- g.
Display Functions
- Radiation monitoring display functions required for operator information on radiation.levels and alarms will
- 2.
system:
Condenser Air Removal and Priming The operational testing of the crosstie with Unit 1 will not be completed.
- 3.
System:
Circulating *water The operational tests of circulators 21B, 22B and 23A will not be completed.
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 Condenser Air Removal and Priming System is not saf.
related.
The Unit 1 crosstie does not affect operation of the &yatem, but is installed for operational flexibility and serves no safety function.
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 1 operation.
ITEMS TO BE cor-~PLETED' AFTER INITIAL CRITICALITY
- -\\
(Revis ion 1)
\\
DES C?- IP'!'IO~!
SAFETY EVALUATION
- 4.
System:
.The 23 consecutive start tests will not be completed until the completion of the zero power physics tests.
- 5.
SUP 50.20, Initial Synchronization of Generator, will not be performed until after Initial Criticality.
- 6.
Waste Disposal - Liquid SUP 16.2 - Liquid Waste Processing Waste Evaporator will not be completeduntil after Initial Criticality.
Diesel generator testing and demonstration of increased reliability*are now underway.
All testing will be com-pleted prior to Core Load except the 23 consecutive starts per diesel.
These tests; as delineated in -
Regulatory Guide 1.108, will be completed prior to pro-ceeding beyond the Zero Power Physics Test Program.
These diesel generators have demonstrated their reliability in previous component and system tests.
These units are not prototypes, and are identical to those.9 used in No. 1 Unit, which have shown a high degree of reliability.
Consequently, completion.of these tests prior to departure from the Zero Power Physics Test Pro-gram will have no effect upon the safe operation of Salem No. 2 Unit.
The Generator was run at 1800 RPM during Hot Functional Testing, but was not syschronized.
Synchronization after Initial Criticality will not affect the safe operation or reliability of the system.
The operation of Salem Unit No. 2 without an available Liquid Waste Evaporator at the beginning of plant life will have no affect upon the safe operation of the plant for the following reasons:
- 1.
The radioactivity levels in the plant for the fiI--
several months of plant life.are very low.
The amount of radioactive liquid waste that would be released to the environment would be only a small fraction 0£ the all6wable limits.
Operation of the waste evaporator during initial periods of operation would not be required to meet ALARA criteria for radioactive releases and would not result in any appreciable radioactive releases when compared to allowable release limits.
- 6.
A':'lhC?J*:I:!;T #2
{Revision 1)
DE SC?- IP'!' Im~
(Continued)
ITEMS TO BE COMPLETED AFTER INITIAL CRITICALITY Sli.FETY EVALUl\\TION
. l
- 2.
The Unit 2 evaporator will be operational prior to entering the first refueling outage.
Waste evaporation requirements prior to that time can be fulfilled by the Unit 1 waste processing system via the crosstie between units.
- 7.
System:
Control Air The Control Air System as installed insures sufficient redundancy during design basis events.
Changeover to Final checkout of #2 Emergency Control Air Compressor using permanent No. 2 Unit power supply.
Compressor is now connected to Unit 1 vital power.
Unit 2 power supply can be deferred without jeopardizing49 plant safety, since the compressor is presently connected to the Unit 1 vital power supply.
The changeover to Unit 2 vital power supply will be made prior to June.l, 1979.