ML17279B004

Forwards Request for Addl Info Re Recirculation Pump Trip Sys & Alternate Rod Injection Sys to Complete Review

ML17279B004
Person / Time
Site:	Columbia
Issue date:	04/18/1988
From:	Samworth R Office of Nuclear Reactor Regulation
To:	Sorensen G WASHINGTON PUBLIC POWER SUPPLY SYSTEM
References
TAC-59158, NUDOCS 8804280539
Download: ML17279B004 (6)

Text

April 18, 1988 Docket No. 50-397 Mr. G.

C. Sorensen, Manager Regulatory Programs Washington Public Power Supply System P.O.

Box 968 3000 George Washington Way

Richland, Washington 99352

SUBJECT:

10 CFR 50.62 ATWS RULE (TAC NO. 59158)

On January 6,

1987 NRC requested that you submit sufficient information to demonstrate the adequacy of three specified systems.

We have reviewed your response dated April 13, 1987 and fitrd that the information which you provided on two of the systems is not adequate.

The enclosure to this letter identifies information which we will need on the recirculation pump trip system and the alternate rod injection system in order to complete our review.

Please provide the requested information within 30 days of receipt of this letter.

Sincerely, original signed by Robert B. Samworth, Project Directorate Division of Reactor IV, V and Special Senior Project Manager V

Projects - III, Projects Enclosure See next page Wanda Jones EButcher ACRS (10)

GPA/PA ARM/LFMB Region V (4)

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Mr. G.

C." Sorensen, Manager Washington Public Power Supply System WPPSS Nuclear Project No.

2 (WNP-2)

CC:

Nicholas S. Reynolds, Esq.

Bishop, Cook, Purcell I% Reynolds 1400 L Street NW Washington, D.C.

20005-3502 Mr. G.

E. Doupe, Esquire Washington Public Power Supply System P. 0.

Box 968 3000 George Washington Way Richland, Washington 99532 Mr. Curtis Eschels, Chairman Energy Facility Site Evaluation Council Mail Stop PY-ll Olympia, Washington 98504 Mr. P. L. Powell, Licensing Manager Washington Public Power Supply System P. 0.

Box 968, MD 956B Richland, Washington 99352 Mr. A. Lee Oxsen Assistant Managing Director for Operations Washington Public Power Supply System P. 0.

Box 968, MD 1023

Richland, WA 99352 Mr. R. B. Glasscock, Director Licensing and Assurance Washington Public Power Supply System P. 0.

Box 968, MD 280 Richland, Washington 99352 Mr. C.

M. Powers WNP-2 Plant Manager Washington Public Power Supply System P. 0.

Box MD 927M Richland, Washington 99352 Regional Administrator, Region V

U.S. Nuclear Regulatory Commission 1450 Maria Lane, Suite 210 Walnut Creek, Cali fornia 94596 Chairman Benton County Board of Commissioners

Prosser, Washington 99350

ENCLOSURE I REQUEST FOR ADDITIONAL INFORMATION ON ATWS REVIEW RELATED TO ALTERNATE ROD INJECTION (ARI) AND RECIRCULATION PUMP TRIP (RPT)

SYSTEMS WASHINGTON PUBLIC POWER SUPPLY SYSTEM NUCLEAR PLANT NO.

2 Provide the following design information as supporting documentation of your method of compliance with 10CFR50.62.

1.

Provide the electrical functional diagrams for the ARI and RPT systems from the sensors to the final actuated devices.

(Figures I and 3 in 4/13/87 submittal are not comprehensible.)

2.

Your submittal indicates that the ARI system has diversity from the existing reactor trip system (RTS).

Please identify the instrument sensor and trip model numbers for the ARI system and the RTS.

3.

Your 4/13/87 submittal Figure 4 indicates that both level and pressure channels have a delay timer in the circuit.

Please identify if this delay for the ATWS system to operate has been analyzed for the affects upon the ATWS system operation.

Please provide justification for the delay in the pressure and level channel trips.

Also identify how the reliability of this delay circuit will affect the ATWS trip requirements.

4.

Please describe how the ARI/RPT systems are reset upon the completion of the protective action.

Also describe the manual initiation capability and its protection from inadvertant operation.

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5.

Please provide the justification for the RPT design based upon the Safety Evaluqtion of Topical Report NEDE-31096-P section

7. 1 requirement for demonstration that; equivalent designs must be demonstrated to be functionally equivalent in their reliability of operation to the approved designs.

6.

Your submittal indicates that the logic configuration is a one-out-of-two for reactor water level and/or reactor pressure.

Please describe the system testabi lity at power and the status information available to the operator.

7.

Identify the power connections for the ARI system, verify independence from the RTS and the ability to perform its function with a loss of offsite power condition.

8.

Identify the actuation setpoints for the ARI and the RPT systems and demonstrate that these trip setpoints will not challenge the scram system.