ML20215J095

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Forwards EGG-NTA-7443, Technical Evaluation Rept of Crystal River Nuclear Generating Station Unit 3 Response to NRR Generic Ltr 83-37, Interim Rept
ML20215J095
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 02/23/1987
From: Obenchain C
EG&G IDAHO, INC., IDAHO NATIONAL ENGINEERING & ENVIRONMENTAL LABORATORY
To: Carrington M
Office of Nuclear Reactor Regulation
Shared Package
ML20215J098 List:
References
CON-FIN-D-6022 GL-83-37, OBEN-27-87, TAC-54527, TAC-57602, NUDOCS 8705070222
Download: ML20215J095 (2)


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Idaho National Engineermg laboratory February 23, 1987 Mr. Mayo Carrington, Project Manager U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Technical Assistanco Management Branch Planning and Program Analysis Staff 7920 Norfolk Avenue Bethesda, MD 20014 TRANSMITTAL OF INTERIM TER FOR EVALUATION OF CRYSTAL RIVER UNIT 3 RESPONSE TO GENERIC LETTER 83-37 (TAC N0s. 54527 AND 57602) (06022) - Oben-27-87

Dear Mr. Carrington:

The enclosed material is transmitted in fulfillmont of the interim review for Crystal River Unit 3 of Project VI for the 06022 4RC form 189. This work was conducted under the technical direction o' Mr. F. R. Allonspach of the Of fice of Nuclear Reactor Regulation, Fdilities Operations Branch-Division of PWR Licensing-B.

The Licensee has proposed changes to Technical Specifications (TSs) that provide acceptablo responses for the following items:

Postaccident Sampling (!!.B.3)

Long Term Auxiliary Feodwater System Evaluation (ll.E.1.1)

Noble Gas Effluent Monitors (ll.F.1.1)

Sampling and Analysis of Plant Effluents (!!.F.1.2)

Containment High-Rango Radiation Monitor (!!.F.1.3)

Containment Pressure Monitor (ll.F.1.4)

Containment Water Lovel Monitor (!!.F.1.5)

The Licensee is not in compliance with the Gotoric Letter for the following items:

Containment Hydrogen Monitor (ll F.1.6)

Instrumentation for Determination of Inidoquate Core Cooling (!!.F.2)

Control Room Habitability Requirements (!!!.D.3.4) 1 i

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  • s Mr. Mayo Carrington February 23, 1987 Oben-27-87 Page 2 Item !!.B.1, Reactor Coolant Vents is being reviewed by the NRC Staff (TAC Nos. 54387 and 57602).

The enclosed report is an interim review of the Crystal River Unit 3 l

response to the Generic Letter 83-37 requirement for Technical Specifications for certain TM1 action items.

A final Technical Evaluation Report will be issued upon receipt of further responses from the Licensee for the items judged to not meet the requirements of the Generic Letter.

Very truly yours,

/O'91Idf$b*

U C. F. Obenchain, Manager NRR and !&E Support EVM:ggo

Enclosure:

As Stated cc:

J. F. Stolz, NRC-PB06 F. R. Scholl, NRC-ORBW H. Silver, NRC-P006 G. L. Jones, 00E-10 P. E. Litteneker, 00E-ID F. R. Allonspach, NRC-PliF0 J. O. Zane, EG&G Idaho Iw/o Enclosure)

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