ML20071B038
| ML20071B038 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 02/18/1983 |
| From: | James Knubel GENERAL PUBLIC UTILITIES CORP. |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.1, TASK-TM NUDOCS 8302250297 | |
| Download: ML20071B038 (3) | |
Text
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4 GPU Nuclear
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100 Interpace Parkway Parsippany, New Jersey 07054 201 263-6500 TELEX 136-482 Writer's Direct Dial Number:
February 18, 1983 Mr. Dennis M. Crutchfield, Chief Operating Reactors Branch #5 Division of Licensing Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, DC 20555
Dear Mr. Crutchfield:
SUBJECT:
Oyster Creek Nuclear Generating Station Docket No. 50-219 Nureg 0737, Item II.F.1 Attachment #1 to this letter provides justification for the l
Oyster Creek Schedule for completing NUREG 0737, Item II.F.1, " Additional Accident-Monitoring Instrumentation".
It should be noted that Oyster Creek is presently in a Refueling Outage and plans to complete five of the six modifications re uired prior to startup. The last modification (Containment Hi Range Monitor) will be completed during the next refueling outage.
If you have any further questions, please contact me at (201) 299-2264.
Very truly your 3 I
J mes Knubel anager BWR Licensing f-4 l lf 1
JK:bif Attachment 8302250297 830218 yDRADOCK 05000219 PDR GPU Nuclear is a part of the General Public Utilities System
O ATFACHMENT #1 NUREG ITEM REASON FOR DELAY COMPENSATORY MEASURES 1.
II.F.1.1 Final accomplishment of this iten can
' thera presently exists nobel gas effluent monitors, Noble Gas only be acccmplished during a refueling however, these monitors do not meet the range re-Effluent Monitor outage. The current refueling outage quirements specified by Nureg 0737.
It is felt that which began on February 12, 1933 is these monitors would be acceptable for all but the most the first availabic outage of sufficien1.
severe accidents in which case Emergency Response duration which has occurred since the recommendations to local agencies would be based upon issurance of Nureg 0737.
Plant Parameters (i.e., reactor water IcVel, containment pressure, Plant area radiation levels, etc.) and the input from offsite monitoring teams.
- 2. II.F.1.2 SAME AS #1 The presently exists charcoal filters in the stack Continuous sampling gas monitoring system. However, for a severe accident of Plant effluent they would not be accessible due to high radiation levels.
It has been concluded that recommendations to local agencies could be accomplished based upon plant parameters and input from offsite monitoring teams.,
- 3. Containment Hi-Final accomplishment of this will be The following instrumentation which is presently in-Range Monitor in the next scheduled refueling outage stalled or will be installed prior to operation in II.F.1.3 which is currently anticipated to occur cycle 10 will provide diverse indication of a severe in 1985. This is felt to be justified accident:
based upon the large number of other a.
Reactor water level pare _neters inside containment that i) lo-lo water level wil1 provide indication of a major ii) lo-lo-lo water level Occident.
iii) Reactor fuel zone monitor b.
Containment Pressure c.
Torus Water level d.
Drywell Oxygen Concentration c.
Drywell Hydrogen Concentration f.
Containment Particulate Monitor j
g.
Core Spray initiation h.
Containment Temperature Monitor
- i. Containment Spray Initiation
ATTACilMENT #1 NUREG ITEM REASON FOR DELAY COMPENSATORY MEASURES 9
- 4. Containment SAME AS # 1 There presently exists instrumentation to monitor Pressure this parameters, however, it does not have the range II.F.1.4 required by Nureg 0737. Other indications of Containmes liigh Pressure would be the detection of higher than anticipated radiation levels in the Secondary Containment and Plant gaseous effluents.
- 5. Containment SAME AS # 1 There presently exists instruments to monitor this Water Level parameter, however, the range of these instruments II.F.1.5 does not meet the requirements of Nureg 0737.
Since Oyster Creek has a Bh'R Mark I Containment the con-tainment cannot be flooded, just due to a LOCA, there would need to be the introduction of a large amount of water from some other source. This could be detected and stopped by the plant operators Also, since the most accident monitoring instrumentation is located outside primary containment the plant is very insensitive to flooding inside containment.
- 5. Containment SAME AS # 1 Oyster Creek has an Nitrogen inerted BWR bhrk I Ilydrogen Monitor Containment. This coupled with the fact that Oxygen is monitored would provide nssurance that an explosive post accident environment did not develop.
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