ML20058E681

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Provides Addl Info Re Reactor Bldg Purge Sys in Order to Resolve Generic Item B-24 & NUREG-0737,Item II.E.4.2.5, Containment Isolation Dependability
ML20058E681
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 07/26/1982
From: Baynard P
FLORIDA POWER CORP.
To: Stolz J
Office of Nuclear Reactor Regulation
References
REF-GTECI-B-24, REF-GTECI-ES, RTR-NUREG-0737, RTR-NUREG-737, TASK-2.E.4.2, TASK-B-24, TASK-B-24-.2, TASK-OR, TASK-TM
  1. 3F-782-19, 3F-0782-19, 3F-782-19, NUDOCS 8207300149
Download: ML20058E681 (2)


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M Power CO m ro n a i eoss July 26,1982

//3F-0782-19 File: 3-0-26 Mr. John F. Stolz, Chief Operating Reactor Branch //4 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72 NUREG-0737, item II.E.4.2 Containment isolation Dependabillity

Dear Mr. Stolz:

Pursuant to Florida Power Corporation's (FPC) and NRC's collective efforts to resolve Generic Item B-24 and TMI Action Plan item II.E.4.2.5 as they related to Crystal River Unit 3 (CR-3), FPC hereby provides additional information concerning the Reactor Building Purge System and its future operation. This information supplements submittals made to you by our letters dated June 2,1982, and July 8,1982.

On July 23,1982, the purge valves will be closed to begin our thirty (30) day assessment of the impacts upon operation. During this period, data will be collected regarding Reactor Building activity increases, and the rate of decrease to acceptable levels when purging is reinstated intermittently. Based on this data collection and its reduction, limited purging -

times can be defined.. This is in keeping with the staff's position that purging / venting should be minimized.

As noted in our June 2 letter, FPC has provided information to demonstrate the purge valves are capable of being closed against LOCA induced forces when the valves are blocked at a partially open position.

This information was produced by the valve manufacturer and, as indicated in the report, full consideration was given to the OYb 8207300149 820726 PDR ADOCK 05000302 P

PDR General Office 3201 inirty fourin street soutn. P O Box 14042, St Petersburg. Florida 33733 e 813-866-5151

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Mr. John F. Stolz July 26,1982 Page 2 provisions of the staff's " Guidelines for Demonstrating Operability of Pur'ge and Vent' s

Valves." Since no written comments were received by FPC, we have been unable to -

determine the staff's specific concens on the manufacturer's report. Upon receipt of their comments, FPC will respond in a timely manner. While FPC remains committed to efforts to justify continued use of the existing 48" Pratt butterfly valves for purging operations, FPC hereby commits to also explore other feasible alternatives.

FPC has previously committed to install debris screens on the innerside of the inboard purge valves. As indicated in our letter dated July 8,1982, design and installation-schedules will be submitted to your office by August 31,1982.

Finally, as discussed in the July 15 meeting, FPC hereby commits to submit appropriate requests for technical specification amendments in a timely manner. These amendments will address concerns which include a purge valve test program, time limit on purging, changes in RCS leak detection systems response due to a more severe containment environment, the necessary increase in the use of respirators for containment entry, and a necessary decrease in the number of entries into the containment due to ALARA considerations.

y; This letter is intended to address all outstanding issues relating to the CR-3 purge valves.

Should you have any questions or comments, please contact us.

Very truly yours, dpr\\d4d ZZu 3

Dr.

Y. Bayn d Assistant to the Vice President Nuclear Operations s

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cc:

Mr. 3. P. O'Reilly, Regional Administrator Office of Inspection & Enforcement U.S. Nuclear Regulatory Commission 101 Marietta Street N.W., Suite 3100 Atlanta, GA 30303 1

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