ML20137N483
| ML20137N483 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 01/17/1986 |
| From: | Opeka J, Opeka J J NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES |
| To: | Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| 974A, F0974A, F974A, SD-57, NUDOCS 8602030252 | |
| Download: ML20137N483 (2) | |
Text
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NORTHEAST UTIUTIES
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L January 17, 1936 Docket No. 50-423 F097t4A Dr. Thomas E. Murley Regional Administrator Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406
References:
(1)
W. G. Counsil letter to T. E. Murley, F0570A, dated July 5, 1984.
(2)
W.
G. Counsil letter to T. E.
Murley, F0583A, dated September 19,1934.
(3)
- 3. F. Opeka letter to V. Noonan, Evaluation of Environmental Effects of Main Steam Line Break Outside Containment, dated December 20,1985.
(4)
- 3. F. Opeka letter to V. Noonan, Evaluation of Environmental Effects of Main Steam Line Break Outside Containment, dated January 7,1986.
(5)
- 3. F. Opeka !ctter to V. Noonan, Evaluation of Environmental Effects of Main Steam Line Break Outside Containment, dated January 14, 1936.
Dear Dr. Murley:
Millstone Nuclear Power Station, Unit No. 3 Reporting of Potential Significant Deficiencies in Accordance with 10CFR50.55(e):
High Energy Line Breaks Outside Containment (SD-57)
In a Junc 5,1984 telephone conversation between your Mr. T. Rebelcwski and our Mr. R. R. Viviano, Northcast Nuclear Energy Company (NNECO), reported a potential significant deficiency in the construction of Millstone Unit No. 3 as required by 10CFR 50.55(e).
The potential significant deficiency involved two potential safety issues. One of the issues, the number of reactor coolant pumps which need to be operating in Mode 3, was determined not to be a significant deficiency for Millstone Unit No. 3 (see Reference (1)). The other potential safety issue, high energy line breaks outside of containment, required additional review.
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~. 3 Reference (2) noted that the safety issue concerned the potential impact of superheated steam on the environmental qualification of equipment outside cf containment following a high energy line break.
In Reference (3), NNECO provided the Staff information regarding the impact of release of superheated steam from a postulated main steam line break (MSLB) on environmental qualification of equipment located outside containment.
Specifically, Reference (3) included the following information:
o Description of design basis for postulated breaks o
Temperature and pressure profiles development criteria o
Temperature and pressure profiles and results in Reference (4), NNECO submitted additional information concerning environmental effects on equipment required to safely shutdown the plant and maintain it in a safe shutdown condition.
Representatives from NNECO met with the Staff on January 3,1936 to discuss the Staff's concerns regarding our Reference (4) submittal.
In Reference (5), NNECO submitted clarifying information concerning the margin and responses to the Staff's questions that were raised at the January 3, 1936 meeting.
As such, we consider the information provided in the above references sufficient to close SD-57 as well as satisfy License Condition 2.6(3) MSLB Outside Containment.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY E F GJ-
- 3. F. Opeks' Senior Vice President cc:
Mr. 3. M. Taylor, Director Division of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C. 20555