ML19324A032
| ML19324A032 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 04/18/1980 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Pilant J NEBRASKA PUBLIC POWER DISTRICT |
| References | |
| NUDOCS 8006200115 | |
| Download: ML19324A032 (1) | |
Text
bec to DAC:ADM:
.A!?fTRAL FILES f,,# "*%gJ,;
UNITED STATES POR:HQ NUCLEAR REGULATORY COMMISSION LPOR Reason iv O
611 RYAN Pt.AZA oRIVE. SulTE 1000 IIC 3_
,/
r*
April 18,1980 STATE Nebraska Public Power District A1TI:
J. H. 211 ant,. Director Licensing & Quality Assurance Post Offica Box 499 Columbus, Nebraska 68601 Gentlemen:
The enclosed II Circular No. 80-08 is forwarded to you.for infor=ation.
No written response is required.
Should you have any questions related to your understanding of the recommendations on this matter, please contact this office.
l 1
Sincerely, I
a
. r1 7. Seyfri?
/
Director Regio'
Enclosures:
1.
II Circular No. 80-08 2.
List of Recently Issued II Circulars cc:
L. C. Lessor, Superdntendent Cooper Nuclear Station Post Office Sox 98 e
3rowuv411a, Nebraska.
68321 I
p 800s:00 u s
{
o SSINS No.: o830 Accession No.:
UNITED STATES 8002280651 NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT T"D"%
WASHINGTON, D.C. 20555 g
IE Circular No. 80-08 April 18, 1980 Page 1 of 1 BWR TECHNICAL SPECIFICATION INCONSISTENCY - RPS RESPONSE TIME Description of Circumstances:
i 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 i
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.
i Our followup indicates that GE BWR facilities which have Technical
- Specifications similar to those 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 Specifications 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, IS will inspect licensee corrective action.
If you require additional information regarding this matter, contact the Director of the appropriate NRC Regional Office.
d J
e w
-,-m_,e-
.,n--
. ~ -
,-,-,,m e,,
.,,.g.w,-,_,-_.w,.s v w n v. w,y,
,wgw-w,,y m,w w w
r IE Circular No. 80-08 April-18, 1980 RECENTLY ISSUED IE CIRCULARS Circular Subject Date Issued To No.
Issued 80-02 Nuclear Power Plant Staff 2/1/80 All holders of Reactor Work Hours Operating Licenses (OLs),
including research and test reactors, and 1
Construction Permits (cps) 80-03 Protection from Toxic Gas 3/6/80 All holders of a power Hazards reactor Operating License (OL) 80-04 Securing of Threaded 3/14/80 All holders of a power Locking Devices on Safety-reactor Operating License Related Equipment (OL) or Construction Permit (CP) 80-05 Emergency Diesel-Generator 4/1/80 All holders of a power Lubricating Oil Addition reactor Operating License (OL) and Onsite Supply or Construction Permit (CP) 80-06 Control and Accountability 4/14/80 Medical licensees in Systems for Implant Categories G and G1 Therapy Sources 80-07 Problems with HPCI Turbine 4/3/80 All holders of a power Reactor Operating Licenses (OL) or Construction Permit (CP) h
- - - ~
... -