ML14190A514

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Responds to & Forwards Request for Addl Info Re Degraded Grid Voltage
ML14190A514
Person / Time
Site: Robinson Duke Energy icon.png
Issue date: 07/02/1979
From: Schwencer A
Office of Nuclear Reactor Regulation
To: Jackie Jones
Carolina Power & Light Co
References
NUDOCS 7908100579
Download: ML14190A514 (4)


Text

T97l50-2 ACRS (16) 2 197 9 JULY N R Local PDR NRR Rdg ORBI Rdg D. Eisenhut Docket No. 50-261 B. Grimes W'. Gammil l A. Schwencer' Mr. J. A. Jones D. Neighbors Senior Vice President C. Trammell Carolina Power and Light Company C. Parrish 336 Fayetteville Street P. Kreutzer Raleigh, North Carolina 27602 I&E (3)

OELD

Dear Mr. Jones:

TERA J. Buchanan We are reviewing your letter of January 24, 1979, which submitted the H. B. Robinson Unit No. 2 "System Design Basis for Degraded Grid Voltage and Emergency Power System Modification" report. We have.

determined that the additional information requested in the enclosure Is necessary in order to complete our review.

Your letter stated that it appears no Technical Specifications changes are required. However, the enclosure identifies changes that will be required.

To enhble us-to maintain a review schedu))e consistent with our objective of resolving this issue by the end of 1979, please submit the requested information and Technical Specification changes within 90 days of receipt.

We appreciate your cooperation on this issue.

Sincerely, Original Signed By A. Schwencer, Chief Operating Reactors Branch #1 Divisionof Operating Reactors

Enclosure:

Request for Additional Information cc: w/enclosure See next page DO :

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oC UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 July 2, 1979 Docket No.

50-261 Mr. J. A, Jones Senior Vice President Carolina Power and Light Company 336 Fayetteville Street Raleigh, North Carolina 27602

Dear Mr. Jones:

We are reviewing your letter of January 24, 1979, which submitted the H. B. Robinson Unit No. 2 "System Design Basis for Degraded Grid Voltage and Emergency Power System Modification" report. We have determined that the additional information requested in the enclosure is necessary in order to complete.our review.

Your letter stated that it appears no Technical Specifications changes are required. However, the enclosure identifies changes that will be required.

To enable us to maintain a review'schedule consi'stent with our objective of resolving this issue by the end of 1979, please submit the requested information and Technical Specification changes within 90 days of receipt.

We appreciate your cooperation on this issue.

Sincerely, A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors

Enclosure:

Request for Additional Information cc:

w/enclosure See next page

Mr. W. L. Proffitt Virginia Electric and Power Company 2 -

July 2, 1979 cc:

Mr. Michael W. Maupin Hunton and Williams Post Office Box 1535 Richmond, Virginia 23213 Swem Library College of William and Mary Williamsburg, Virginia -23185 Donald J. Burke U. S. Nuclear Regulatory Commission Region II Office of Inspection and Enforcement 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303

REQUEST FOR ADDITIONAL INFORMATION H. B. ROBINSON PLANT, UNIT 2 DEGRADED GRID VOLTAGE

1.

Provide the voltage trip point on the 4160V side for the second level voltage protection monitors.

It is stated as 86 percent on the 480 volt bus with a time delay of 10 seconds. A Technical Specification Change is required to incorporate this set point and time delay.

2. Describe the load shedding sequence showing the interaction of onsite power with the load shed feature. Refer to Position 2 (NRC letter, "Safety Evaluation and Statement of Staff Positions Relative to Emer gency Power Systems for Operating Reactors", dated 6/2/77).
3. It is required that the Technical Specifications include a test require ment to demonstrate the full functional operability and independence of the onsite power sources at least once every 18 months during shutdown.

Refer to Position 3 (NRC letter, Safety Evaluation and Statement of.

Staff Positions Relative to Emergency Power Systems for Operating Reactors",

dated 6/2/77).

State the frequency of checks, calibration, functional tests, and operating surveillance modes.

Provide proposed Technical Specifications addressing testing.