ML18139A841

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Informs That Installation of Redundant safety-grade RCS Pressure Input to Core Subcooling Monitors Will Not Be Installed on Unit 2 Until Spring Maint Outage Currently Scheduled for May 1981
ML18139A841
Person / Time
Site: Surry  Dominion icon.png
Issue date: 11/18/1980
From: Sylvia B
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To: Harold Denton, Youngblood B
Office of Nuclear Reactor Regulation
References
TASK-2.F.2, TASK-TM 922, IEB-79-01B, IEB-79-1B, NUDOCS 8011210216
Download: ML18139A841 (1)


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RICHMOND,VIRGINIA 23261 November 18, 1980 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation Attn:

Mr. B. Joe Youngblood, Chief Licensing Branch No. 1 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C.

20555

Dear Mr. Denton:

Serial No. 922 NO/RWC:ms Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37 NUREG - 0578 (0660 AND 0737)

SURRY POWER STATION As previously identified to you in our letter dated July 7, 1980 (Serial No.

536) there are some post-TMI modifications that might not be fully implemented by the required implementation date of January 1, 1981 due to material deliv-ery problems.

The issuance of NUREG-0737 with revised implementation dates has alleviated this problem for all items identified except for one.

In a meeting with your staff at Surry Power Station on March 18, 1980 and a subsequent* letter dated April 1, 1980 (Serial No.

306) Vepco committed to install.a redundant safety grade reactor coolant system pressure input to the core subcooling monitors by January 1, 1981.

The original plant design has a single wide range reactor coolant pressure signal.

This system will not be installed on Surry Unit 2 until the spring maintenance outage currently scheduled for May, 1981.

The system will be installed on Surry Unit 1 prior to startup after the steam generator replacement outage.

The required electronics (P. 0. No. 45044 issued April, 1980) will not be available from the NSSS vendor until early 1981.

In addition, since trans-mitters qualified to IEEE-373-1974 are not available, transmitters qualified to the 1971 requirements will be installed and upgraded as part of our I.E.

Bulletin 79-0lB program.

Until that time the core subcooling monitors remain fully operati9nal with a single wide range reactor coolant pressure input and the process co_mputer as backup.

Should you need more information, please contact us.

cc:

Mr. James P. O'Reilly Very truly yours, (fl(~k B. R. Sylvia Manager - Nuclear Operations and Maintenance