ML20237D322

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Forwards Parameter List Used at Incident Response Ctr,Per 850513 Request.List Developed for Implementation of Automated Data Transmission Sys.Data Points Represented by List Will Vary Depending on Design of Plant in Question
ML20237D322
Person / Time
Issue date: 05/23/1985
From: Perkins K
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
To: John Miller
Office of Nuclear Reactor Regulation
Shared Package
ML20235G519 List: ... further results
References
FOIA-87-737 NUDOCS 8712230190
Download: ML20237D322 (3)


Text

{{#Wiki_filter:' MAY 2 ? 1985 HEMORANDUM FOR: James R. Miller, Chief Operating Reactors Branch #3 Division of Licensing Q Nuclear Reactor Regulations FROM: Kenneth E. Perkins, Chief Incident Response Branch Division of Emergency Preparedness and Engineering Response Office of Inspection and Enforcement

SUBJECT:

PARAMETER LIST FOR INCIDENT RESPONSE l Your May 13, 1985 memo requested the list of 67 variables used at the incident response center. Enclosed are the parameter lists to which you were referring. Please be aware of two aspects regarding these lists. First, the exact number of data points represented by the lists will vary depending on the specific design of the plant in question. For example, the number of radiation monitor values transmitted to the operations center will vary from plant to plant. , Second, these data lists were developed specifically for the implementation of an automated data transmission system from the plant sites. The data that is currently acquired verbally over p' hone lines is a subset of these lists which is requested of the licensee at the time of the event. Should you have any ques'tions please contact John Hickman at X24155. - O Kenneth E. Perkins, Chief Incident Response Branch l Division of Emergency and Preparedness ' l and Engineering Response Office of Inspection and Enforcement Enclosures *

1. TABLE 1, PWR PARAMETER LIST
2. TABLE 2, BWR PARAMETER LIST cc: DCS DEPER R/F IRB R/F 2h t HickmansLEn R. F. Priebe, IE K. E. Perkins, IE JBHickman R/F O

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MAY 9 91985 , TABLE 1 PWR PARAMETER LIST O Primary Coolant Pressure System Temperatures - hot leg Temperatures - cold leg

l Temperatures - core exit thermocouple l Subcooling margin 1 Pressurizer level
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Reactor vessel level (when available)  ; Reactor coolant flow Neutron flux - startup range Secondary Coolant Steam generator levels System Main feedwater flows Auxiliary / Emergency.feedwater flows Safety Injection High pressure safety injection flows ,, , Low pressore safety injection flows Safety injection flows (Westinghouse) Borated water storage tank level l Containment Containment pressure

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