ML19254B070
| ML19254B070 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 08/23/1979 |
| From: | Parr O Office of Nuclear Reactor Regulation |
| To: | Proffitt W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| References | |
| NUDOCS 7909240040 | |
| Download: ML19254B070 (4) | |
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AUG 2 31979 Docket No: 50-338 Mr. W. L. Proffitt Senior Vice President - Power Virginia Electric and Power Company P. O. Box 26666 Richmond, Virginia 23261
Dear Mr. Proffitt:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING IE BULLETINS79-06A AND 79-06A, REVISION 1 We have reviewed your responses to IE Bulletins79-06A and 79-06A, Revision 1 for the North Anna Power Station, Unit 1 (North Anna 1) which were trans-mitted by letters dated April 26 and June 29, 1979. Our review of your responses has led us to believe that you have a general understanding of our concerns arising from the TMI-2 incident in relation to their implica-tions to the operation of the North Anna 1 plant. Nevertheless, we have discovered some deficiencies in your responses which must be resolved before we issue our safety evaluation for the North Anna 1 plant. The resolution of these deficiencies is contingent upon receiving complete and acceptable responses to the questions in Enclosure 1.
As a result of our continuing review of the TMI-2 incident, we may impose other corrective actions in addition to those in IE Bulletins79-06A and 79-06A, Revision 1.
In the interim if you need any clarification of the enclosed questions, please contact Mr. P. D. O'Reilly, the staff's assigned project manager for Bulletins and Orders involving W designed reactors.
Mr. O'Reilly may be reached on (301) 492-7745.
Your responses to the enclosed questions should be forwarded to us within 2 weeks from date of receipt of this letter.
Sincerely, let b. f O. D. Parr, CIef Light Water Reactors, Branch #3 Division of Project Management
Enclosure:
Request for Additional Information ec: See next page
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- 1373 cc: Honorable Frederick S. Fisher Mr. Peter S. Hepp Assistant 4torney General Executive Vice President Comonwalth of Virginia Sun Shipbuilding 4 Dry Dock Company 1101 East Broad Street P. O. Box 540 Richmond, Virginia 23219 Chester, Pennsylvania 19013 Michael W. Maupin, Esquire Hunton, Williams, Gay & Gibson P. O. Box 1535 Richmond, Virgi/ iia 23212 Mrs. June Allen 412 Owens Drive Nntsville, Alabama 35801 Mr. James Torson 501 Leroy Socorro, New Mexico 87801 Mrs. Margaret Dietrich Route 2, Box 568 Gordonsville, Virginia 22942 William H. Rodgers, Jr., Esquire Georgetown University Law Center 600 New Jersey Avenue, N. W.
Washington, D. C.
20001 Michael S. Kidd U.S. Nuclear Regula. tory Comission P. O. Box 128 Spotsivania, Virginia 22553 Clarence T. Kipps, Jr., Esquire 1700 Pennsylvania Avenue, N. W.
Washington, D. C.
20006 Carroll J. Savage, Esquire 1700 Pennsylvania Avenue, N. W.
Washington, D. C.
20006 c.,
N, REQUEST FOR ADDITIONAL INFORMATION AS A RESULT OF STAFF REVIEW OF RESPONSES TO BULLETINS79-06A AND 79-06A (REVISION 1)
NORTH ANNA POWER STATION, UNIT 1 DOCKET NO: 50-388 2.
Provide a complete response to this Bulletin item. You should clarify how operators will verify the margin to saturation conditions.
Indicate whether operators have been given aids (e.g., some type of saturation curve) to assist them in recognizing the degree of subcool-ing and the approach to saturation conditions.
Identify all instrumen-tation which might be used to recognize void formation in the primary system. Summarize the results of the review requested by this Bulletin item regarding the natural circulation mode of operation and any sub-sequent actions you have taken based on your review. Discuss the instrumentation available to the operator for confirmation that natural circulation is occuring. Identify the actions prescribed for operators to enhance natural circulation.
8.
Confirm that the proper position of all safety-related valves has been reviewed - both procedurally and actually. Our position on this matter is that all safety-related valves should be inspected, to the extent practical, on a periodic basis, to verify proper position. Confirm that you have reviewed plant procedures and have revised them as necessary to eneure that locked safety-related valves are subjected to periodic surveillance. Submit a summary of the results of this review.
9.
Your response does not identify all systems which are designed to transfer potentially radioactive fluids from the containment. Revise your response to provide the requested identification, for each system identified, provide the information regarding high radiation interlocks, containment isolation, and operability assurance requested by this Bulletin item.
10.
Confirm that you have reviewed and modified, as necessary, your maintenance and test procedures to ensure that they require (a) redundant safety-related systems are operable before a system is taken out of service, (b) safety-related systems are operable when returned to service, and (c) operators are made aware of the status of these systems. Provide a summary of this review and any action which you have taken based on its results.
Identify all safety-related equipment which cannot be tested without making it inoperable. Describe the actions which you have taken to solve this problem. Describe the method used for transferring information about the status of safety-related systems at shift change.
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Provide the date on which procedural revisions will be completed to incorporate the requirements of this Bulletin item.
12.
Sumarize the various operating modes that deal with hydrogen in the primary coolant system. Provide the schedule for completing operational
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procedures which incorporate these operating modes.
13.
Provide any proposed changes in Technical Specifications which are required as a result of your response to Item 2 through 12 of this Bulletin.
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