L-79-145, Forwards Addl Response to IE Bulletin 79-06
| ML17206A899 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 05/29/1979 |
| From: | Robert E. Uhrig FLORIDA POWER & LIGHT CO. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| L-79-145, NUDOCS 7907130415 | |
| Download: ML17206A899 (3) | |
Text
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FLORIDA POWER II LIGHT COMPANY May pg, 1979 L-79-145 Mr. James P. O'Reilly, Director, Region II Office of Inspection and Enforcement U. S. Nuclear Regulatory Comnission 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303
Dear Mr. O'Reilly:
Re:
RII:JPO 50-335 IE Bulletin 79-06,79-06B The attached information is submitted to supplement Responses 6(c) and 10 of our letter L-79-79 dated April 24, 1979.
Very truly yours,
+ Robert E. Uhrig Vice President Advanced Systems 5 Technology REU/NS/cph~
cc:
Harold Reis, Esquire V907180$ IS q
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ATTACHMENT Re:
RII:JPO 50-335 IE Bulletin 79-06,79-06B Res onse 6 c Su lement The following information is provided to supplement our response to item no.
6 of I 8
E Bulletin 79-06B regarding operation of reactor coolant pumps (RCP's ).
While operation of the RCP's is not required to conform with analyzed accident results presented in the
- FSAR, FPL does agree to operation of the RCP's under certain transient conditions to met the intent of the Bulletin.
FPL has provided instructions to the St. Lucie operators to operate one RCP per loop during a small break loss of coolant transient (with outside power available) as long as the RCP is providing forced flow through the core.
The instructions further state that if continued pump operation is judged to be a
potential cause of further degradation of the reactor coolant system, RCP operation shall be terminated.
In order to provide continued operation of the RCP's, it will be necessary for the operator to manually override the SIAS close signal for valves in the Component Cooling Water System that provide cooling flow to the RCP's.
This manual override can be accomplished by manually positioning the control switches for these valves to the "open" position.
Appropriate instructions regarding this item have been included in the instructions mentioned above.
Res onse 10 Su lement The following instructions have been issued at St. Lucie:
Within one hour following a significant release of radioactivity or an uncontrolled or unexpected condition which poses a threat to the health and/or safety of the general public, the NRC shall be notified and an open comuni ca-tion channel established and maintained to the extent possible.
If appropriate supervisors or the duty call supervisor are not or cannot be on site to perform this function within the required time, the Nuclear Watch Engineer is designated to communicate with:
a)
Ted Webster - Office 404/221-5549 Home 404/939-6127 b)
Region II Duty Officer - 404/221-4503 After additional people arrive on site a meeker of the plant staff, technically qualified to address plant concerns, will man the phone continuously with the NRC.
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