ML18092A993

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Forwards Response to Draft Technical Evaluation Rept Re Salem ATWS Item 1.2 (Generic Ltr 83-28),confirming 860110 Telcon.Part 21 Related
ML18092A993
Person / Time
Site: Salem  
Issue date: 01/20/1986
From: Corbin McNeil
Public Service Enterprise Group
To: Varga S
Office of Nuclear Reactor Regulation
References
REF-PT21-86-032-000 GL-83-28, NLR-N86008, PT21-86-032-000, PT21-86-32, NUDOCS 8601270003
Download: ML18092A993 (4)


Text

Public Service Electric and Gas Company Corbin A. McNeill, Jr.

Vice President -

Public Service Electric and Gas Company P.O. Box236, Hancocks Bridge, NJ 08038 609 339-4800 Nuclear January 20, 1986 NLR-N86008 Off ice of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, MD 20014 Attention:

Mr. Steven A. Varga, Director PWR Project Directorate #3 Division of PWR Licensing A

Dear Mr. Varga:

DRAFT TECHNICAL EVALUATION REPORT FOR SALEM ATWS ITEM 1.2 (GENERIC LETTER 83-28)

SALEM GENERATING STATION UNITS 1 AND 2 DOCKET NOS. 50-272 AND 50-311 Attached is PSE&G's response to the subject Draft Technical Evaluation Report which conf irrns our telephone conversation with Mr. Joel Kramer of the NRC on January 10, 1986.

If you require additional information, please let us know.

Attachment C Mr. Donald C. Fischer Licensing Project Manager Mr. Thomas J. Kenny Senior Resident Inspector Sincerely,

  • AIJ - *J*. Knighr(l,-\\ir.;.;.1yJ --~. * -

EB (BALLARD)

EICSB (ROSA)

PSB (GAMMILL), *

  • RSB (BERLINGER)-

FOB (BENAROYA)

RESPONSE TO DRAFT TECHNICAL EVALUATION REPORT FOR SALEM ATWS ITEM 1.2 (GENERIC LETTER 83-28)

SALEM GENERATING STATION -

UNITS l AND 2 DOCKET NOS. 50-272 AND 50-311 Item No. 1 Parameter Recorded:

Attached is a Table of the PWR Parameters available for Post Trip Review at Salem.

We have included an additional column for the SPDS parameters to supplement the SOE and Time History Recorders.

The SPDS has fourteen (14) hours data storage capability with an option to permanently store the data on disc or tape.

Hard copy printout is also available.

The SPDS System is scheduled for operation in December 1986.

The NRC recommended parameters for the SOE which are not included in the Salem SOE, Containment Isolation, Control Rod Position, Containment Radiation, MSIV Position, AC and DC System Status and PORV Position are all included on the SPDS with the exception of the AC System Status.

Control Rod Position is also included on a Time History Recorder.

For the recommended Time History Recorder parameters, Primary System Flow and Steam Generator Pressure are excluded at Salem.

The Steam Generator Pressure parameter is included on the SPDS.

Primary System Flow was not included because it is not a Reg.

Guide 1.97 requirement.

In summation between the three sources of Post Trip Review data, all parameters with the exception of AC Systems Status has been included on at least one source.

AC System Status is not a Reg. Guide 1.97 requirement; therefore its exclusion.

Item No. 2 Item No. 3 Item No. 4 Item No. 5 anl9 SOE Recorders Performance Characteristics:

No comment, original response satisfactory.

Time History Recorders Performance Characteristics:

The Time History Recorders at Salem are Texas Instruments Inc. manufacture, Tigraph 100 Model.

Performance characteristics:

Accuracy:

+ 0.5% full scale Resolution:

0.25% of full scale Prime Rate Print:

5 lines per second Chart:

15 days at a speed of 0.3 inch per hour.

Data Output Format A.

SOE -

No comment, original response satisfactory B.

Time History Recorder -

Strip Chart includes time, channel (parameter) identification by letter and Parameter label identification on the individual recorder.

C.

SPDS -

Hard copy and disc or tape permanent storage includes time, parameter identification and description.

Data Retention Capability Per Salem Operations Administrative Directive (AD-3) Post Trip Review data is stored for the life of the plant.

SALEM PWR PARAMETERS FOR POST TRIP REVIEW SOE Time History Recorder Recorder SPDS Parameter/Signal x

x Reactor Trip x

Safety Injection x

Containment Isolation x

Turbine Trip x

x Control Rod Position x

x x

Neutron Flux, Power x

x x

Containment Pressure x

Containment Radiation x

x Containment Sump Level x

x x

Primary System Pressure x

x x

Primary System Temperature x

x x

Pressurizer Level x

x Reactor Coolant Pump Status x

Primary System Flow x

x Safety Inj., Flow, Pump/Valve Status x

MSIV Position x

x Steam Generator Pressure x

x x

Steam Generator Level x

x x

Feedwater Flow x

x x

Steam Flow x

x Auxiliary Feedwater System, Flow, Pump/Valve Status x

DC System Status (Bus Voltage) x x

Diesel Generator Status (Start/Stop, On/Off) x PORV Position GH3/l 4