ML17256A489
| ML17256A489 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 02/09/1983 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Maier J ROCHESTER GAS & ELECTRIC CORP. |
| Shared Package | |
| ML17256A490 | List: |
| References | |
| TASK-04-03, TASK-06-02.D, TASK-4-3, TASK-6-2.D, TASK-RR IEB-80-04, IEB-80-4, LSO5-83-02-024, LSO5-83-2-24, NUDOCS 8302160261 | |
| Download: ML17256A489 (4) | |
Text
February 9, 1983 Docket No. 50-244 LS05-83-02-024 Mr. John E. Maier, Vice President Electric and Steam Production Rochester Gas and Electric Corporation 89 East Avenue Rochester, New York 14649
Dear Mr. Maier:
SUBJECT:
MiAIN STEAM LINE BREAK MITM CONTINUED R.
E.
GINNA NUCLEAR POHER PLANT DISTRIBUTION
- II'"'
NRC PDR Local PDR ORB Reading NSIC OCrutchfield MSmith GOick ETouri gny OELD ELJordan JMTaylor ACRS (10)
SEPB FEEOMATER ADOITIOW-Your letters of April 30, 1980 and February 1, 1982 concerning the Systematic Evaluation Program (SEP) topics VI-2.D "Mass and Energy Release for Possible Pipe Breaks Inside Containment,"
and IV-3 "Contain-ment Pressure and Heat Removal Capability" were evaluated along with other pertinent information regarding Ginna as the response to IE Bulletin 80-04 dated February 8, 1980.
The bulletin was issued as a
result of deficiencies identified in the original Main Steam l.ine Break (t)SLB) analysis for three facilities.
The deficiencies concerned the continued addition of water to the affected steam generator in the event of a MSLB and the resultant over-pressure of the containment.
Your responses were evaluated by our contractor, the Franklin Research Center.
Their Technical Evaluation Report as well as our Safety Evaluation Report are enclosed.
He have concluded that there is no potential for containment overpressurization resulting from a NSLB with continued feed-
~ water addition at Ginna because:
- 1) the main feedwater system is automatically
~~ g j isolated and the auxiliary feedwater system limits flow to the affected DS<
steam generator; g) the auxiliary feedwater pumps are protected from the effects of runout flow and therefore can be expected to carry out their intended function during the MSLB event; and 3) all potential water sources were identified and, although a reactor return-to-power is predicted, there is no violation of the specified acceptable fuel design limits; Therefore the Exxon Nuclear MSLB reactivity increase ana1ysis remains valid i<e find the above conclusions acceptable.
No further action is required by you regarding this subject.
8302i6026i 83020'g)
PDR AD00la 05000244 P
PDR Sincerely, Original signed by/
Dennis M. Crutchfield, Chief Operating Reactors Branch
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/83 OFFICEti SURNAMElp DATEP Enclosure 0 ~
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NRC FORM 818 (10-80) NRCM 0240 OFFICIAL RECORD COPY USGPO: 1981-335.960
I'/
t
ter. John E. Hai er February 9, 1983 CC Harry H. Yoigt, Esqui re
- LeBoeuf, Lamb, Leiby and t1acRae 1333 New Hampshire Avenue, N.
W.
Suite 1100 Washington, D. C.
20036 ter. Michael Slade 12 Trailwood Circle Rochester, New York 14618 Ezra Bialik Assistant, Attorney General Environmental Protection Bureau New York State Department of Law 2 World Trade Center Hew York, Hew York 10047 U. S. Environmental Protection Agency Region II Office ATTN:
Regional Radiation Representative 26 Federal Plaza Hew York, New York 10007 Herbert Grossman, Esq.,
Chairman Atomic Safety and Licensing Board U. S. Nuclear Regulatory Commission Washington, D. C.
20555 I
Ronald C. Haynes, Regional Administrator Nuclear Regulatory Commission, Region I 631 Park Avenue King of Prussia, Pennsylvania 19406 Resident Inspector R. E. Ginna Plant c/o V. S.
NRC 1503 Lake Road
- Ontario, Hew York 14519 R
Director, Bureau of Nuclear Operations'tate of Hew York Energy Office.
Agency Building 2 Empire State Plaza
. Albany, New York 12223 Supervisor of the Tov(n of Ontario 107 Ridge Road West
- Ontario, Hew York 14519 Dr. Emmeth A. Luebke Atomic Safety and Licensing Board U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Dr. Richard F. Cole Atomic Safety and Licensing Board
.U. S. Nuclear Regulatory Commission Washington, D. C.
20555
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