ML20137B578
| ML20137B578 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 12/27/1985 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML20137B567 | List: |
| References | |
| GL-83-28, NUDOCS 8601150575 | |
| Download: ML20137B578 (2) | |
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_ SAFETY EVALUATION REPORT.FOR t
_ GENERIC LtIIER 83-28. ITEM 4.1 k
_ REACTOR TRIP SYSTEM RELIABILITY
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_ARKANSA5 NUCLEAR ONE - UNIT 1~
_ DOCKET NO: 50-313 t
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_ INTRODUCTION i
On February 25, 1983, Sales Nuclear Power Plant failed to open upon an auto signal from the reactor protection system.
the plant startup and the' reactor was_ tripped manually by the opera{
i about 30 seconds after the initiation of the automatic trip signal.
failure of the circuit breakers has been determined to be The sticking of' the under voltage" trip attachment.
t 22, 1983, Prior to this incident, on February trip signal was generated based on steam generator low j
plant startup.
In this case, the. reactor was tripped manually by the operator almost coincidentally with the automatic trip.
incidents, on February 28, 1983, Following these j
Operations (EDO), directed the staff tothe NRC Executive Director for generic implications of these occurrence. investigate and report on the Power Plant.
The results of the staff's inquiry into the generics at Unit 1 of th implications of the Salem unit incidents are reported in NUREG-1000
" Generic Implications of ATWS Events at the Salem Nuclear Power Pla As a result of this investigation, the Commission (NRC t
Generic Letter 83-28 dated July 8,1983) all licensees)of operating requested (by reactors, applicants for an operating license, and holders of construction permits to respond to certain generic concerns.
i concerns are categorized into four areas:
These (1) Post-Trip Review, Testing, and (4) Reactor Trip System Reliability Im j
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consists of Action Item 4.1, " Reactor Trip System l
(Vendor-Related Modifications),"
Reactor Trip Breakers)," Action Item 4.3, " Rea 1
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Reliability Westinghouse (and B&W Plants) "' Action Item 4.4 Automatic Actuation of Shunt Trip Attachments for i
Reliability (Improvements in Maintenance ~and Test Procedures for i
B&W Plants)" and' Action Item 4.5, " Reactor Trip System Reliability i
(System Functional Testing)."
addresses Action Item _4.1 only.-This safety evaluation report (SER) t t
II. REVIEW GUIDELI'ES i
N The following review guidelines were used to evaluate the response from i
the licensee to item 4.1 of Generic Letter 83-28:
8601150575 851227
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.The licensee or applicant shall subrit a statement that he has and determined that (1) each modification has, in fa not implementing a modification exists. implemented; or (2)
III. EVALUATION AND CONCLUSION By letter dated April 23, 1985 the licensee of. Arkansas Nuclear One -
Unit 1 provided information regarding vendor recommended modification the reactor trip system.
the review guidelines as described in Se: tion It; 'A brief de the licensee's response and the staff's evaluation of the response aga the review guidelines is provided below:
v The licensee stated that the gcneric response of the B&W owners group has been implemented concerning the modifications to the reactor trip breakers.
A program has been implemented to bearings lubricated with Mobil 28 lubricant. systematically r been completed for the Arkancas Nuclear One, Unit I reactor tripT breakers.
Based on our review, we conclude that the licensee's response to vendor recommended modifications to the reactor trip system for the Arkansas Nuclear One - Unit 1 is acceptable.
Principal NRC Contributor:
J. Bess i
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