ML20004D462
| ML20004D462 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 05/13/1981 |
| From: | Madsen G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20004D460 | List: |
| References | |
| 50-313-81-11, 50-368-81-10, NUDOCS 8106090426 | |
| Download: ML20004D462 (3) | |
Text
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O V
Arkansas Power and Light Company Arkansas Nuclear One, Units 1 and 2 Occkets:
50-313; 50-368 Licenses:
OPR-51; NPF-6 NOTICE OF VIOLATION Based on the rescits of an NRC inspection conducted during the period of March 22 - April 21, 1981, and in accordance with the Interim Enforcement Policy, 45 FR 66754 (October 7, 1980), the following violations were identified:
1.
L' nit 2 Technical Specification 6.8.1 requires that, " Written procedures shall be established, implemented, and maintained covering... a.
The applicable procedures recommended in Appendix "A" cf Regulatory Guide 1.33."
Operating Procedure 2102.10, " Plant Shutdown and Cooldown" has been established in accordance with this Technical Specification.
Step 8.29 to this procedure establishes Low Temperature Overpressure (LTOP)protectionforgheReactorCoolantSystem(RCS)bystating,"When RCS temperature is 200 F, disable and lock out all HPSI Pumps, Contain-ment Spray Purps, and all but (1) Charging Pump, and caution tag HPSI and charging pump hand switches to preunt inadvertant operation as required for LTOP protection." Additionally, this procedure requires that each step be initialed by an operator to indicate its completion.
Contrarytgtheabove,onMarch 30, 1981, with RCS temperature approxi-mately 150 F and Step 8.29 to Procedure 2102.10 initialed complete, all three Charging Pump hand switches were found to be selected to the "AUT0" position instead of having at least two of the handswitches selected to the "STOP" position which would have disabled the Charging Pumps as required.
This constitutes a Severity Level V Violation (Supplement I.E.) (368/8110-1).
l 2.
Unit 2 Technical Specification 6.8.1 requires that, " Written procedures shall be established, implemented, and maintained covering... b. Refuel-inq operations."
Operating Procedure 2502.01, Refueling Shuffle, has been established in accordance with this Technical Specification.
Step 7.8 of this procedure contains the following note:
'810 6 0 0 0 N
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" CAUTION: WHEN INSERTING FUEL ASSEMBLIES INTO THE REACTOR CORE, NOTE COUNT RATE BEFORE AND AFTER INSERTION, OBSERVE PRECAUTION 4.24 AND LOG THE COUNT RATE IN THE BLANKS PROVIDED ON i
ATTACHMENT 0."
Contrary to the above, on April 21, 1981, the Control Room operator did not note and record neutron count rate when fuel assembly AKC 303 was insertad into core position A-8.
This constitutes a Severity Level V Violation (Supplement I.E.) 36a/8110-2).
3.
Unit 2 Technical Specification 3.7.10.2 requires that a continuous fire watch with backup fire suppression equipment be established within one hour if the Cable Spreading Room sprinkler is not operable.
The Unit 2 Cable Spreading Room sprinkler system was rendered incapable of automatic operation on March 30, 1981, when valve 2FS-61, the fire water supply to the room, was tagged shut to prevent inadvertent actuation of
+
the sprinkler during maintenance activities in the room.
Contrary to the above, although a fire watch had been previously stationed in accordance with the above Technical Specification, the fire watch was not continuous in that the NkC inspector found that no fire watch was stationec at 2:35 p.m. on April 2,1981.
This constitutes a Severity Level IV Violation (Supplement I.O. 2) (368/8110-3).
i 4.
Unit 1 Technical Specification 6.8.1 requires that, " Written procedures shall be astablished, implemented and maintained covering... a.
The applicable i
procedures recommended in Appendix "A" of Regulatory Guide 1.33."
Administrative Procedure 1000.13, Control of Station Modifications, has been established in accordance with this Technical Specification.
Step 6.4.2 of this procedure requires that upon issuance of the test copy of a Oesign Change Package (DCP), Plant Engineering shall mark the first generation sepf as of the plant drawings to indicate those portions of the i
drawings affected by the design change.
Affected areas are to be circled (bubbled) and "0CP No.
Pending" is to be entered in the revision block.
Drawings, thus revised, are to be distributed within the plant.
The intent of the procedures is that the revised drawings be distributed within several days after DCP test copy issuance.
j Contrary to the above, on March 25, 1981, the below listed plant drawings in the Unit 1 Control Room were not marked to indicate pending design changes, even though the design enanges had been completec by that cate:
l
3 Orawing No.
OCP No.
OCP Test Cooy Issue Date M204 79-1033 12/30/80
.M210 80-1135 1/24/81 M210 80-1180 1/28/81 M231 81-1011 2/14/81 M230 80-1004 1/14/81 This constitutes a Severity Level V Violation (Suppl'ement I.E.) (313/8111-1).
Pursuant to the provisions of 10 CFR 2.201, Arkansas Power and Light Company is hereby required to submit to this office within 25 days of the date of this Notice, a written statement or explanation in reply, including (1) the corrective steps which have been taken and the results achieved; (2) cor-
.rective steps which will be taken to avoid further violations; and (3) the date when full compliance will be achieved.
Under the authority of Section 182 of the Atomic Energy Act of 1954, as amended, this response shall be submitted under oath or affirmation.
As noted in paragraph 11 of the attached inspection report, no written response is required for Item 3 above, concerning failure to station a continuous fire watch.
When preparing the response to Item 2 above, concerning the failure to comply with the Refueling Shuffle procedure, pliase include _the commitment requested in paragraph 12 of the attached inspection report.
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Date_ h a l.0 l9 Sl
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b G. L. Maasen, Chief Reactor Projects Branch t
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