ML14192A151

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Responds to 770425 & 0823 Ltrs Re Proposed Mods to Controls for Certain Critical ECCS Motor Operated Valves.Mods to Valve Motor Control Circuits Are Acceptable.Requests Valve Surveillance Requirements Per Encl Tech Spec
ML14192A151
Person / Time
Site: Robinson 
Issue date: 03/09/1981
From: Varga S
Office of Nuclear Reactor Regulation
To: Jackie Jones
Carolina Power & Light Co
Shared Package
ML14192A153 List:
References
NUDOCS 8103160143
Download: ML14192A151 (3)


Text

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UNITED STATES f

NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 March 9, 1981 Docket No. 50-261 Mr. J. A. Jones Senior Vice President Carolina Power & Light Company 336 Fayetteville Street Raleigh, North Carolina 27602 Co

Dear Mr. Jones:

By letters dated April 25 and August 23, 1977, concerning H. B. Robinson Steam Electric Plant, Unit No. 2, you proposed modifications to the con trols for certain critical ECCS motor operated valves.

The proposed modifications are designed to eliminate operator actions outside of the control room, to preclude single failure involving spurious valve operation, and to avoid any unintended operator action that would result in loss of cooling capability. The modifications to the valve con trols include: (1) the addition of a separate control power lockout switch; (2) valve position indication that is not deenergized by control power lockout; and (3) redundant valve position indication. The control power lockout scheme conforms to the single failure criterion. Therefore, the design of the valve control satisfies the requirements of EICSB BTP 18 of the Standard Review Plan.

The following valves were identified as being required for eme gency long-term cooling of the core and as not satisfying the single failure criterion.

1. Valves 862 A & B RHR Suction from RWST
2. Valves 863 A & B RHR Discharge to RWST
3. Valves 864 A & B SI Supply from RWST
4. Valves 866 A & B Hot Leg SI
5. Valve 869 Hot Leg SI In the event of a loss-of-coolant accident, the valves identified in items one through four must change position during the switchover from injection to recirculation flow.1 The controls for these valves were to be modified.

The licensee also proposed to modify the controls for the valve identified in item five to eliminate the need for operator action outside of the con trol room in the event this valve has to be operated.

810 3 1 6 0 /0

Mr. J. A. Jones

-2 Based on our review, we find that the modifications to the valve motor control circuits satisfy the single failure criterion. We, therefore, conclude that the design is acceptable.

Your letter dated September 26, 1980 proposed changes to the Technical Specifications for the valves discussed in 1 through 4 above. However, you have not provided surveillance requirements for these valves.

We request that you, propose surveillance requirements for these valves (See the enclosed Standard Technical Specification for guidance).

Please provide your response within 45 days of receipt of this letter.

ncerely, S

arga,Chi f Operating Reactors B nch #1 Division of Licensi

Enclosure:

Standard Technical Specification cc w/enclosure See next page

Mr. J..A. Jones Carolina Power and Light Company cc: G. F. Trowbridge, Esquire Shaw, Pittman, Potts and Trowbridge 1800 M Street, N.W.

Washington, D. C. 20036 Hartsville Memorial Library Home and Fifth Avenues Hartsville, South Carolina 29550

-U. S. Nuclear Regulatory Commission Resident Inspector's Office H. B. Robinson Steam Electric Plant Route 5, Box 266-1A Hartsville, South Carolina 29550 Michael C. Farrar, Chairman Atomvic Safety and Licensing Appeal Board Panel U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Richard S. Salzman Atomic Safety and Licensing Acceal Board Panel U. S. Nuclear Regulatory Commission Washington, D. C..20555 Dr. V. Reed Johnson Atomic Safety and Licensing Appeal Board Panel U. S. Nuclear Regulatory Commission Washington, D. C. 20555