ML19253A615
| ML19253A615 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 08/10/1979 |
| From: | Moody D CONNECTICUT YANKEE ATOMIC POWER CO. |
| To: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| WMY-79-79, NUDOCS 7909100451 | |
| Download: ML19253A615 (2) | |
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ENGINEERING OFFICE WESTBORO, MASSACHUSETTS 01581 617-366-9011
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B.3.2.1 WMY 79-79 August 10, 1979 United States Nuclear Regulatory Commission Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406 Attention: Office of Inspection and Enforcement Mr. Boyce H. Grier, Director
References:
(a) License No. DPR-36 (Docket No. 50-309)
(b) I & E letter to MYAPC dated April 14, 1979 (c) MYAPC letter to I & E dated April 25, 1979 (d) MYAPC letter to I & E dated May 4, 1979 (e) I & E letter to MYAPC dated July 26, 1979
Dear Sir:
Subjec t:
Additional Information Regarding IE Bulletin 79-06B Relative to your request fer additional infor=ation regarding IE Bulletin 79-06B, as requested in reference (e), the following information is provided.
4 It>m 2.a With regard to the additional parameters identified for determining the possibility of core voiding (i.e. RCS flow indications, incore temperature monitors, source range instruments and water saturation curves), the following actions have been in. tiated.
Maine Yankee has prepared and implemented water saturation curves for the operators' use and incorporated references to these curves in appropriate procedures.
A review is currently being performed by the appropriate departments within the Nuclear Services Division of the Yankee Atomic Electric Company to:
(1) deter:aine if the range of presently installed incore temperature monitors can be expanded.
(2) establish applicability of source range instrumeritation output as another means for the identification of a core voiding condition.
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.9 mmo n 79o9100 6 /-
' United States Nuclear Regulatory Commission Page 2 August 10, 1979 The evaluations are at this time incomplete and therefore, the use of these parameters as evidence of core voiding is not presently being utilized.
The subject of RCS flow during small break LOCA's is at present being analyzed by Combustion Engineering.
Recently issued instructions included in IE Bulletin No.79-06C require the tripping of all reactor coolant pumps under certain LOCA conditions.
Until such time as the analyses have been completed and the effects of stopping or starting reactor coolant pumps during LOCA conditions has been evaluated, it is felt that references in operating procedures to RCS flow indications for the purpose for determining core voiding would be inappropriate.
Following the completion of the evaluations of the above items Maine Yankee will, where appropriate, incorporate these additionally identified parameters into the existing procedures which address the possibility of core voiding.
As previously discussed, a procedure which addresses the issue of natural circulation has been prepared.
It is at this time being reviewed by the Plant Operations Review Committee.
It is anticipated that this review and approval process will be completed during late August, at which time this procedure will be issued for implementation.
Item 9.b As stated in Reference (d) the Maine Yankee Maintenance Request and Tagging Rules forms have been revised to provide adequate documentation relative to the concerns of Ite=s 9.a, b, and c of Reference (b).
The revised forms were reproduced by a local contractor, have been received and are presently being utilized.
Item 9.c Step 3.1.9 of the Operator Relief procedure requires the transmittal of information relative to the status of safeguards equipment (i.e.:
removal or return to service).
We trust this information is satisfactory.
Should additional information be required, please contact us.
Very truly yours, MAINE YANKEE ATOMIC POWER COMPANY D. E. Moody Manager of Operatione de9 G '! c" s v'.
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