ML20072G223
| ML20072G223 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 06/21/1983 |
| From: | Pilant J NEBRASKA PUBLIC POWER DISTRICT |
| To: | Vassallo D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-TM GL-82-33, LQA8300161, NUDOCS 8306280386 | |
| Download: ML20072G223 (2) | |
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GENERAL OFFICE
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LQA8300161 June 21,1983 Director of Nuclear Reactor Regulation Attention: Mr. Domenic B. Vassallo, Chief Operating Reactors Branch No. 2 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Vassallo:
Subject:
Post-Accident Sampling System, Item II.B.3,
Reference:
1)
Letter from J. M. Pilant to D. B. Vaasallo dated April 22, 1983, "NPPD Response to Request for Additional Information per Reference 1" 2)
Letter from D. B. Vassallo to J. M. Pilant dated February 15, 1983, " Review of Post-Accident Sampling System, NUREG-0737, Item II.B.3" In a telephone conversation May 31, 1983, the Staff requested that the District document clarification of two of the items which were responded to in Reference 1.
This letter is written to provide the requested information.
In Attachment 1 of Reference 2 the following statements are made:
"In addition to the radionuclide measurements, other plant indicators may be available which can aid in estimating core damage.
These include incore temperature indicators, total quantity of hydrogen released from zirconium degradation and containment radiation monitors.
When providing an estimate of core damage the information available from all indications should be factored into the final estimate (i.e. if the incore temperature indicators show fuel overheat and the radionuclide concentration indicate no damage, then a recheck of both indications should be performed)."
Cooper Nuclear Station Procedure 8.4.1.1.a will be revised by July 15,1983, to consider indications specified above in the final estimation of core damage.
It should be noted that CNS does not have incore temperature indicators. These indicators are not required per Regulatory Guide 1.97. - Rev. 3, May 1983, and g
generic letter 82-33 Supplement 1 to NUREG 9737.
8306280386 830621 1
PDR ADOCK 05000298 D
P PDR 1
Pega 2.
Juns 21,1983 The accuracy of the following analyses are provided:
Reactor Coolant Total Gas i20%
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=
50%
Reactor Coulant Ph 2.0%
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=
Containment Atmosphere flydrogen =
0.2%
It is understood that the above accuracles are acceptable since they are based upon " state of the art" methodologies.
Based upon the discussion with the Staff, the District believes that the above supplementary information adequately addresses all of the Staff's concerns related to Reference 1.
Sincerely, M
M.. Pflant Division Manager of Licensing &
Quality Assurance JMP/jdw:rt21/5(C1)
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