ML19324A037
| ML19324A037 | |
| Person / Time | |
|---|---|
| Issue date: | 04/25/1980 |
| From: | Carroll D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Wright G ILLINOIS, STATE OF |
| References | |
| NUDOCS 8006200123 | |
| Download: ML19324A037 (1) | |
Text
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UNITED STATES
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,o GLEN ELLYN, ILLINOIS 60137 APR25gggg State of Illinois Department of Public Health ATTN:
Mr. Gary N. Wright, Chief Division of Nuclear Safety 535 West Jefferson Street Springfield, IL 62761 Gentlemen:
The enclosed IE Circular No. 80-08 titled "BWR Technical Specification Inconsistency - RPS Response Time" was sent to the following licensees on April 18, 1980, for information.
Commonwealth Edison Company Dresden 1, 2, 3 (50-10, 50-237, 50-249)
Quad-Cities 1, 2 (50-254, 50-265)
Consumers Power Company Big Rock Point (50-155)
Iowa Electric Light and Power Company Duane Arnold (50-331)
Northern States Power Company Monticello (50-263)
Sincerely, dh
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LL.d f o othy E.
arroll, Acting Chief Administrative Branch
Enclosure:
IE Circular No. 80-08 cc w/ encl:
Mr. D. W. Kane, Sargent & Lundy Central Files Reproduction Unit NRC 20b Local PDR NSIC TIC 8006200f.2)
SSINS No.: 6830 Accession No.:
UNITED STATES 8002280651 NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C. 20555 f
April 18, 1980 IE Circular No. 80-08 BWR TECHNICAL SPECIFICATION INCONSISTENCY - RPS RESPONSE TIME Description of Circumstances:
On March 10, 1980, Vermont Yankee (VY) notified the NRC that the reactor protection system (RPS) response time of 100 milliseconds (from sensor contact opening to and including scram solenoid reiay contact opening) specified in the Technical Specification is inconsistent with the value of 50 milliseconds used in the safety analysis. VY verified that actual response times have been below 50 milliseconds since initial plant operation and initiated a Technical Specification change request and plant procedure changes.
VY reported that a letter from General Electric Company (GE) informed them of the inconsistency and that the problem may be generic.
Our followup indicates that GE BWR facilities which have Technical Specifications similar to that discussed above may be affected.
Based on RPS design and test results, actual RPS response times are expected to be less than 50 milliseconds.
For GE BWR's, we request that you take the following corrective action promptly after receipt of this Circular: (1) verify that the actual RPS response time in the most recent test is less than the value specified in the safety analysis, (2) observe the RPS response time value specified in the safety analysis until a Technical Specification change (if necessary) is approved, and (3) take appropriate actions to make Technical Specification on RPS response time consistent with the RPS response time used in the safety analysis.
If a value less than that currently in the Technical Specifications is proposed, the licensee will be expected to provide the basis for that value, including the validity of tests and methods.
No written response to this Circular is required, however, IE will inspect licensee corrective action.
If you require additional information regarding this matter, contact the Director of the appropriate NRC Regional Off::e.
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IE Circular No. 80-08 Enclosure April 18, 1980 RECENTLY ISSUED IE CIRCULARS Circular Subject Date of Issued to No.
Issue 80-07 Problems with HPCI Turbine 4/3/80 All holders of a power Oil System reactor OL or CP 80-05 Control and Accountability 4/14/80 Medical licensees in Syttems for Implant Therapy Categories G and G1 Sources
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80-05 Emergency Diesel-Generator 4/1/80 All holders of a power Lubricating Oil Addition and reactor OL or CP Onsite Supply 80-04 Securing of Threaded Locking 3/14/80 All holders of a power Devices on Safety-Related reactor OL or CP Equipment 80-03 Protection from Toxic Gas 3/6/80 All holders of a Hazards power reactor OL.
80-02 Nuclear Power Plant Staff 2/1/80 All hoiders of Reactor Work Hours OLs, including research and test reactors, and cps 80-01 Service Advice for GE 1/17/80 All licensees of Induction Disc Relays nuclear power reactor operating facilities and holders of nuclear power reactor cps 79-25 Shock Arrestor Strut 12/20/79 All licensees and Assembly Interference holders of power reactor cps 79-24 Proper Installation and 11/26/79 All Holders of a Calibration of Core Spray Power Reactor OL or Pipe Break Detection CP Equipment on BWRs.
79-23 Motor Starters and 11/26/79 All Power Reactor and Contactors Failed Operating Facilities tc Operate and Holders of Reactor cps
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