ML19305E348

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Discusses 800317 Ltr Re Request for Change in Tech Spec 3.7.E.1 Value for Drywell Suppression Chamber Differential Pressure from 1.47 Psid to 1.1 Psid.Requests Another Change to Tech Spec to Value of 1.0 Psi
ML19305E348
Person / Time
Site: Cooper Entergy icon.png
Issue date: 04/18/1980
From: Pilant J
NEBRASKA PUBLIC POWER DISTRICT
To: Ippolito T
Office of Nuclear Reactor Regulation
References
NUDOCS 8004230457
Download: ML19305E348 (2)


Text

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April 18, 1980 Director, Nuclear Reactor Regulation Atta: Mr. Thomas A. Ippolito, Chief Operating Reactors Branch No. 3 Division of Operating Reactors U.S. Nuclear Regulatory Commission Washington, DC 20555

Subject:

Drywell-Suppression Chamber Differential Pressure Technical Specification Change Request Cooper Nuclear Station NRC Docket No. 50-298, DPR-46

Reference:

1) Letter from J. Pilant to T. Ippolito Dated March 17, 1980, Same Subject

Dear Mr. Ippolito:

Reference 1 transmitted a request for a change in the Technical Specifi-cation 3.7.E.1 value for Drywell-Suppression Chamber Differential Pres-sure from the present 1.47 psid to 1.1 psid. Discussions relating to this change conducted with the staff on April 16, 1980 have prompted NPPD to request that Specification 3.7.E.1 be revised to a differential pressure value of 1.0 psi. This value is consistent with the value used in various plant unique testing programs and final load definitions to be used in the Mark I Containment Program analyses for Cooper Nuclear Station.

The District has considered the effect of varying the two parameters associated with this Technical Specification change (i.e. downcomer sub-margence and drywell-suppression chamber differential pressure) and has confirmed that the torus support system and the torus attached piping will continue to meet all of the Mark I Containment Short Term Program requirements following the modification. Downcomer modification and associated Technical Specification changes are part of the long term modifications necessary to resolve the Long Term Mark I Containment Program.

The present refueling outage is currently expected to be concluded approx-imately May 31, 1980; therefore, approval of all outage related Technical Specification changes are respectfully requested prior to May 15, l'80.

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Thomas A. Ippolito April 18, 1980 Page 2 Should you have any questions or require additional information, please do not hesitate to contact me.

Sincerely yours, V ugm:f.+

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. Pilant Director of Licensing and Quality Assurance JDW/cmk

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