0CAN098508, Responds to NRC Re Violation Noted in Insp Repts 50-313/85-19 & 50-368/85-20.Corrective actions:post-accident Sampling Sys Installed & Capabilities Functional & Isolation Valves Repaired
| ML20136H140 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 09/20/1985 |
| From: | Enos J ARKANSAS POWER & LIGHT CO. |
| To: | Denise R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| Shared Package | |
| ML20136H127 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-TM 0CAN098508, CAN98508, NUDOCS 8511250042 | |
| Download: ML20136H140 (3) | |
Text
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ARKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 UTTLE ROCK. ARKANSAS 72203 (501)371-4000 September 20, 1985 h
b OCAN098508 is Mr. Richard P. Denise, Director ort - 41985 Division of Reactor Safety and Projects U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011
SUBJECT:
Arkansas Nuclear One - Units 1 & 2 Docket Nos. 50-313 and 50-368 License Nos. DPR-51 and NPF-6 Response to Inspection Reports 50-313/85-19 and 50-368/85-20 Gentlemen:
The subject reports have been reviewed.
A response to the " Notice of Violation" is attached.
Ver truly yo s,
c
. Ted Enos Manager, Licensing JTE/MCS/sg Attachment cc:
Mr. Norman M. Haller, Director Office of Management & Program Analysis U. S. Nuclear Regulatory Commission Washington, DC 20555 Mr. Richard C. DeYoung Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, DC 20555 8511250042 851031 PDR ADOCK 05000313 G
PDR fY MEMBEA MiOOLE SOUTH UTILITsEs SYSTEM
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f NOTICE OF VIOLATION During an NRC inspection conducted on June 24-28, 1985, a violation of NRC requirements was identified.
The violation involved the inability to collect and analyze post-accident samples.
In accordance with the " General Statement of Policy and Procedures for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1985), the violation is listed below:
Inability to Collect and Analyze Post-Accident Samples In an " Order Confirming Licensee Commitments on Post-TMI Related Issues," dated March 14, 1983, and issued to Arkansas Power and Light, Arkansas Nuclear One, Units 1 & 2, the NRC ordered the licensee, to implement and maintain specific items described as complete in the Attachments to the Order. to the respective Order indicated that the installation of the post-accident sampling capability was complete.
Contrary to the above, on June 24, 1985, and July 12, 1985, NRC inspectors determined that the post-accident sampling capability was not implemented and maintained so that required samples and analyses of reactor coolant and containment atmosphere could be obtained and analyzed as specified in NUREG-0737, II.B.3.
This is a Severity Level IV violation (Supplement I).
(313/8519-01; 368/8520-01)
RESPONSE
The Post Accident Sampling System (PASS) was installed and the post accident capabilities were functional as described in our letter of December 6, 1982 (0CAN128201).
Problems with the operation of the system have been experienced and are normally corrected within a few days.
As stated in our letter of June 18, 1982 (0CAN068208),
NUREG-0737 requires a single PASS which, like all other non-safety related systems, is not required to be operable continuously.
The recent problems encountered when attempting to demonstrate operability for the NRC inspectors were corrected and sampling on both units was performed July 26, 1985.
As discussed in our letter of September 7, 1984 (0CAN098401), AP&L no longer takes credit for inline analysis of boron, chlorides and pH.
This is due to accuracy problems encountered with the inline equipment.
Instead, boron analysis is now accomplished onsight, utilizing a manual method.
Analysis for chlorides and pH will be performed at Oak Ridge National Laboratories as allowed by NUREG-0737, item II.B.3.
Information on the accuracy of the manual boron and chloride sampling methods was provided in our letters of July 15, 1985 (0CAN078510) and September 13, 1985 (0CAN098502).
)
Procedure changes have been completed requiring a monthly operational
. verification and provide a form for documenting this verification.
The procedure does not require the surveillance during cold shutdown but does specify that the surveillance will be performed within.seven days of criticality, if greater than one month since previously performed.
The surveillance procedure. requires notification of the NRC Resident Inspectors if PASS is out-of-service for more than seven consecutive days. -A preventive maintenance program is being developed for PASS and maintenance is receiving increased attention such that problems
- affecting operability will be corrected promptly.
The PASS is operable for post accident conditions.
However, one problem exists which causes some concern for the ability to obtain an
'ANO-1 containment sump sample.
This is because the ANO-1 sump sample pump casing has been over pressurized due to isolation valves that were leaking by their seats.
Although the pump is functional, it has a small casing leak which would add to the airborne activity in the reactor auxiliary building if a sample of the sump were taken.
The isolation valves are being repaired.
Parts are presently on order.
After-receipt and installation of these parts, the valves will be leak-tested.
If the results are satisfactory, the pump will be replaced with a new pump which is already on-site. With no unforeseen problems, these activities are estimated to be completed by October 15, 1985.