ML18139C341

Submits Schedule for Replacement or Mod of safety-related Equipment for Environ Qualification Per 10CFR50.49(g) Criteria.Master List of Equipment Encl

ML18139C341
Person / Time
Site:	Surry
Issue date:	05/20/1983
From:	Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	Harold Denton, Varga S Office of Nuclear Reactor Regulation
References
085F, 85F, NUDOCS 8305260232
Download: ML18139C341 (3)

Text

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e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261

w. L. STEWART VICE PRESIDENT NUCLEAR OPERATIONS May 20, 1983 Mr. Harold R. Denton, Director Serial No. 085F Office of Nuclear Reactor Regulation PSE/JEW:jdm:0478C Attention: Mr. Steven A. Varga, Chief Docket Nos.: 50-280 Operating Reactors Branch No. 50-281 Division of Licensing License Nos.: DPR-32 U.S. Nuclear Regulatory Commission DPR-37 Washington, DC 20555 Gentlemen:

ENVIRONMENTAL QUALIFICATION OF SAFETY-RELATED ELECTRICAL EQUIPMENT SURRY POWER STATION UNITS l AND 2 This letter is in response to 10 CFR Part 50, paragraph 50.49(g) which requires each holder of an operating license to identify the electrical equipment important to safety and submit a schedule for qualification or replacement of such equipment. Vepco has developed a master list of equipment covered by 10 CFR Part 50, paragraph 50.49(b) (1) and (3) (Attachment 1).

Using the status column of this list, the qualification status of each piece of equipment can be determined. For all equipment identified in the status column as scheduled for replacement (R) or modification (M), the schedule for this activity is as follows:

Unit l: Replacement or modification is scheduled for the Cycle 7-8 refueling outage, which is presently scheduled to start in the third quarter of 1984. This is consistent with the requirements of 10 CFR 50.49(g).

Unit 2: Replacement or modification is scheduled for the Cycle 7-8 refueling which is presently scheduled to start in the first quarter of 1985. This is consistent with the requirements of 10 CFR 50.49(g).

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s3o526-0fl32 830520 PDR ADOCK 05000280 P PDR

e VIRGINIA ELECTRIC AND POWER COMPANY TO In response to 10 CFR Part 50, paragraph 50.49(b) (2), Vepco is developing criteria to address this equipment. It is anticipated the equipment in this category, if any, and the methodology used to identify this equipment will be provided to you on or before November 16, 1983. Additionally, any corrective actions required to qualify or replace equipment identified for compliance will be completed on a schedule consistent with the requirements of 10 CFR Part 50, paragraph 50.49.

Attachment 2 provides the justification for continued operation (JCO) for equipment not qualified as requested in your letter of January 26, 1983 and amended by your letter of April 4, 1983. Additionally, JCO information was provided by our letters of March 9, 1983, (SN-085C) and May 11, 1983, (SN-085E). All other JCO's previously submitted have been reviewed and determined to be applicable, or the equipment has been replaced with qualified equipment.

This completes the response requirements of the January 26, 1983 and April 4, 1983 letters and 10 CFR Part 50, paragraph 50.49(g).

Attachments cc: Mr. James P. O'Reilly w/attachments Regional Administrator Region II 101 Marietta Street, Suite 2900 Atlanta, Georgia 30303 Mr. D. J. Burke w/attachments NRC Resident Inspector Surry Power Station Mr. J. Don Neighbors w/attachments NRC Project Manager - Surry Operating Reactors Branch No. 1 Division of Licensing U.S. Nuclear Regulatory Commission Washington, DC 20555

ATTACHMENT 2 VEPCO LETTER OF MAY 20, 1983 SERIAL NUMBER 085F TECHNICAL EVALUATION REPORT ENVIRONMENTAL QUALIFICATION OF SAFETY-RELATED ELECTRICAL EQUIPMENT SURRY POWER STATION UNITS l AND 2 RESPONSE TO NRC LETTERS OF JANUARY 26, 1983 AND APRIL 4, 1983 Charging Pump Component Cooling Water Pump Motors l-CC-P-2A l-CC-P-2B 2-CC-P-2A 2-CC-P-2B JUSTIFICATION FOR CONTINUED OPERATION These motors will be replaced within the schedule established by 10 CFR 50.49. For interim operation, Appendix D of the TER indicates that additional~

justification should be provided for charging pump operation more than one hour after assumed CCW pump failure. That justification follows.

• The charging pump component cooling water pumps provide seal and cooling water for the charging pumps. The flow from the component cooling water pumps cools the charging pumps while they are in their safety mode of safety injection.

In the event of a cooling water pump failure, the manufacturer has determined that the charging pumps can operate indefinitely in normal ambient conditions without seal water coolant as long as. the pumped fluid is less than 115°F. There is no HELB that can simultaneously render both the charging pump and CCW pump environments harsh.

• In the safety injection mode the suction of the charging pumps is diverted from the normal source, at the volume control tank, to the refueling water storage tank by the safety injection signal. The water in the refueling water storage tank is cooled by Tech Spec requirement to a temperature of slightly below 45°F, which ensures that the charging pumps can operate in the event of any "HELB that might cause failure of the CCW pump motors.

It is concluded that the failure of the component cooling water pumps will not hinder the safety mode of safety injection, and will have no impact on~

• plant safety.