ML19326B564
| ML19326B564 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 04/16/1978 |
| From: | David Williams ARKANSAS POWER & LIGHT CO. |
| To: | Madsen G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| Shared Package | |
| ML19326B556 | List: |
| References | |
| 1-048-3, 1-48-3, NUDOCS 8004160347 | |
| Download: ML19326B564 (3) | |
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ARKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 UTTLE ROCK. ARKANSAS 72203 (501)3714000 April 6, 1978 1-048-3 Mr. G. L. t!adsen Reactor Construction & Operation Branch U. S. Nuclear Regulatory Commission Office of 7.aspection & Enforcement Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76012 SUILTECT: Arkansas Nuclear One - Unit One Docket No. 50-313 License No. DPR-51 IE Inspection Report 50-313/78-04 (File:
0232) l y/
Gentlemen:
The subject inspection report identified three violations of our tech-nical specifications and one violation of Criterion II of Appendix B to 10 CFR 50.
In response to the Notice of Violation, provided'below..is our reply to the four infractions:
(1) As corrective action for failure to record the neutron flux level after insertion of a fuel assembly into the core and prior to sub-sequent loading, the following sequence of events occurred:
(A)
Immediately upon notification by the inspector, the operator commenced recording the neutron count rate before and after each core geometry change.
(B) A special meeting of the Plant Safety Committee wa's called by the Plant Manager on February 15, 1978, to discuss this information and to determine the action to be taken to achieve compliance.
(C) During the time span 1830-2100 hours on February 15, 1978, Refueling Operations were discontinued and the refueling shuf-fle procedure (OP 1502.04) was reviewed in detail with all operators involved with fuel handling.
8004200 347 l
i Mr. G. L. Madstr April 6, 1978 s
In order to assure that the neutron count rate will be recorded following loading of each fuel assembly into the core and prior to subsequent loading, we will add a blank space on the chronological log for recording the count rate.
Procedure 1502.04 (Fuel Shuffle) will be revised prior to core cycle four (4) fuel load on ANO-Unit 1.
.It is our opinion that we were in full compliance with procedure 1502.04 at 2100 hours0.0243 days <br />0.583 hours <br />0.00347 weeks <br />7.9905e-4 months <br /> on February 15, 1978.
(2) We are of the opinion that this is an isolated case.
We feel that our procedures and method of training are adequate. We attribute this incident to human error.
In spite of the human involvement, we strive to make our procedures and instructions as complete and detailed as possible.
The refueling operator in the control room did not understand why he had lost the counter scaler; consequently, he did inform the operator in the reactor building who in turn informed the Senior Reactor Operator in charge of fuel handling that the counter scaler was not working and refueling activities were stopped.
As corrective action for this incident, the following sequence of events occurred:
(A)
The source range channel was re-energized in approximately two (2) minutes after it was de-energized.
(B) A special meeting of the Plant Safe,ty Committee was called by the Plant Manager to review this incident and to determine action to be taken.
(C) Refueling operations were discontinued from 1830-2100 hours on February 15, 1978, and the refueling shuffle procedure was reviewed with all operators involved with fuel handling.
(D)
Caution cards were placed in the source range channels in the RPS cabinets to caution personnel agninst de-energizing the source range instrumentation during fuel shuffle operations.
-(E) An alarm was placed in the plant omputer to alert the operator in_ case of an inoperable source range channel.
The next revision of procedure 1502.04 (Fuel Shuffle) will incluja a provision for adding caution cards to the source range channels in.
_the RPS cabinets prior to fuel shuffle commencing.
Procedure 1502.04 is revised prior to each fuel cycle.
We are of the opinion. that we were in compliance with Technical l
Specification 3.8.2 at 2100 hours0.0243 days <br />0.583 hours <br />0.00347 weeks <br />7.9905e-4 months <br /> on February 15, 1978.
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^ Mr. G. L. Mrdscn April 6, 1978 (3)
It is our belief that procedure 1103.13 (Reactor Coolant System s_
Leak Rate Determination) is conservative as written in that we do not take allowance for evaporative losses, relief valve leakage, makeup pump seal leakage and other miscellaneous items.
We will revise procedure 1103.13 to include such items as evaporative losses and other measurable leakage, however, we feel that procedure 1103.13 will be rendered less conservative.
Procedure 1103.13 will be. revised by May 1, 1978.
(4)
Procedure 1304.70 (Reactor Building Isolation Valve Stroke Test.
Quarterly) was written and approved in April of 1974. At that time Valve CV-1065 was required to be open to supply flushing water to the reactor coolant pump seal standpipes. Subsequent to April 1974, the requirement for flush water to the r eactor coolant pump seal standpipes was deleted and Valve CV-106.* became a normally closed valve.
Procedure 1304.70 has been reviewed several times since it was. issued, but this valve has been overlooked.
We have made an initial review of our procedures and find no other remotely operated reactor building isolation valves which are not being stroke tested as required by Technical Specification 4.4.1.4.
We will make a detailed review of our procedures to assure compliance with Technical Specification 4.4.1.4 and revise procedure 1304.70 to include valve CV-1065 and any other remotely operated reactor building isolation valves by April 19, 1978.
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Sincerely, DHJ:LA:ce Daniel H. Williams Manager, Licensing i
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