ML20080S744

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Responds to 831006 Request for Addl Info Re Changes to Emergency & Abnormal Procedures Following Review of Preliminary Safety Concern 22-82, Potential for Pressurized Thermal Shock
ML20080S744
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 10/14/1983
From: Westafer G
FLORIDA POWER CORP.
To: Deyoung R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
REF-GTECI-A-49, REF-GTECI-RV, TASK-A-49, TASK-OR 3F-1083-11, NUDOCS 8310180473
Download: ML20080S744 (2)


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M Power C O ft P O es A Y e 0 8s October 14, 1983 3F-1083-11 Mr. Richard C. DeYoung, Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555

Subject:

Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72 Preliminary Safety Concern 22-82 Potential for Pressurized Thermal Shock

Dear Sir:

On September 22, 1983, Florida Power Corporation (FPC) forwarded the results of our review of the subject preliminary safety concern (PSC). On October 6,1983, the NRC Project Manager for Crystal River Unit 3 (CR3) requested that FPC submit more of the details of the changes to the CR-3 emergency and abnormal procedures (E & AP's) that resulted from this review.

The E & AP's have recently been revised to be symptom-oriented in conjuction with the Anticipated Transient Operating Guidelines (ATOG) for CR-3. This revision was implemented on July 26, 1953.

Actions for the small break operating guidelines (SBOG's) were included in this procedure revision.

The initial SBOG's were misinterpreted by some of the user utilities including FPC.

This misinterpretation was corrected and the correction included in our July 26, 1983 implementation of the E & AP's.

The Pressurized Thermal Shock (PTS) Operating Region is between 50 and 100 degrees subcooled. If CR-3 has experienced a cooldown of greater than 1000F per hour and ended up with a Reactor Coolant System (RCS) temperature less than 5000F, an overview of the guidelines to be followed are:

1.

If the RCS temperature and pressure are within the PTS Operating Region, CR-3 must remain in the region for three (3) hours before continuing to cool down.

2.

If the RCS temperature and pressure are above the PTS Operating Region, RCS pressure will be reduced until the RCS temperature and pressure are within the PTS Operating Region. A three (3) hour hold will then ensue before continuing to cool down.

8310180473 831014 iL 1 0 PDR ADOCK 05000302 P

PDR General Office 32o1 initty-fourin stex4 sourn. P O Box 14042. St. Petersburg. Fienda 33733 e 813-866-5151

9 October 14,1983 3F-1083-11 Page 2 3.

If the RCS temperature and pressure are below the PTS Operating Region, CR-3 pressure will be increased via the high pressure injection pumps until the RCS temperature and pressure are within the PTS Operating Region. (This increase in pressure is acceptable since the region below the PTS Operating Region may be indicative of

, inadequate core cooling.

This must be overcome first before Pressurized Thermal Shock is considered.) A three hour hold in the PTS Operating Region will ensue before continuing cool down.

Sincerely, f'

12 7 G.R Westafer Manager Nuclear Operations Licensing and Fuel Management RMB:jcf cc:

Mr. James P. O'Reilly Regional Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta Street N.W., Suite 2900 Atlanta, GA 30303 s

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