ML19323J377
| ML19323J377 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 04/18/1980 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Rich Smith VERMONT YANKEE NUCLEAR POWER CORP. |
| References | |
| NUDOCS 8006200075 | |
| Download: ML19323J377 (1) | |
Text
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UNITED STATES 8
NUCLEAR REGULATORY COMMISSION o
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REGION I g
631 PARK AVENUE L
KING OF PaUSSIA, PENNSYLVANIA 19406
- ,d April 18,1980 Docket No. 50-271 Vermont Yankee Nuclear Power Corporation ATTN:
Mr. Robert L. Smith Licensing Engineer 25 Research Drive Westborough, Massachusetts 01581 Gentlemen:
The enclosed IE Circular No. 80-05, "BWR Technical Specification Inconsistency-RPS j
Response Time," is forwarded to you for information.
No written response is I
required.
If you desire additional information regarding this matter, please contact this office.
- incerely, Vid. 02t~
H. Grier c
irector
Enclosures:
1.
IE Circular No. 80-08 2.
List of Recently Issued IE Circulars CONTACT:
E. Greenman (215-337-5267) cc w/encls:
Mr. Warren P. Murphy, Plant Superi:itendent Ms. J. Abbey, Technical Secretary Mr. J. E. Griffin, President Mr. L. H. Heider, Vice President 8006200075',
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ENCLOSURE 1 SSINS No.: 6830 Accession No.:
UNITED STATES 8002280651 NUCLEAR REGULATORY COMMISSION
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- D 0FFICE OF INSPECTION AND ENFORCEMENT "O
WASHINGTON, D.C. 20555 IE Circular No. 80-08 Date:
April 18, 1980 Page 1 of 1 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 relay 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 Specifica-tions 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 Office.
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ENCLOSURE 2 IE Circular No. 80-08 Date:
April 18, 1980 Page 1 of 1 RECENTLY ISSUED IE CIRCULARS Circular Subject First Date Issued To No.
of Issue 79-22 Stroke Times for Power 11/16/79 All Power Reactor Licensees Operated Relief Valves with an Operating License (OL) or Construction Per-mit (CP) 79-23 Motor Starters and Con-11/26/79 All Power Reactor Licensees tactors Failed to Op-with an OL or CP erate 79-24 Proper Installation and 11/26/79 All Power Reactor Calibration of Core Facilities with an OL or j
Spray Pipe Break CP Detection Equipment on BWRs 80-01 Service Advice for GE 1/17/80 All Power Reactor Faci-Induction Disc Relays lities with an OL or CP 80-02 Nuclear Power Plant 2/1/80 All Power and Research Staff Work Hours Reactors with an OL or CP 80-03 Protection from Toxic 3/6/80 All Power Reactor Facil-Gas Hazards ities with an OL a
80-04 Securing Threaded Lack-3/14/80 All Power Reactor Facil-ing Devices on Safety-ities with an OL sr CP
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Related Equipment 80-05 Emergency Diesel Gen-4/1/80 All Power Reactor Facil-erator Lubricating Oil ities with an OL or CP Addition and Onsite Supply 80-06 Control and Account-4/14/80 Medical Licensees in ability Systems for Categories G and G1 Implant Therapy Sources 80-07 Problems with HPCI 4/3/80 All Power Reactor Facil-Turbine Oil System ities with an OL or CP