ML031980607
| ML031980607 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 07/15/2003 |
| From: | Myers L FirstEnergy Nuclear Operating Co |
| To: | Dyer J NRC/RGN-III |
| References | |
| 1-1324 | |
| Download: ML031980607 (4) | |
Text
E Firstfnsrgy Nuclear Operating Company 5507 North State Route 2 Oak Harbor; Ohio 43449 Lew W. Myers Chief Operating Officer 4 79-32 1 - 7599 FaU: 419-321-7582 Docket Number 50-346 License Number NPF-3 Serial Number 1-1324 July 15, 2003 Mr. James E. Dyer, Administrator United States Nuclear Regulatory Commission Region I11 80 1 Warrenville Road Lisle, IL 60532-4351
Subject:
Notification of Information Provided to the Nuclear Regulatory Commission that May Not Be Complete and Accurate in All Material Respects
Dear Mr. Dyer:
The purpose of this letter is to notify the Nuclear Regulatory Commission (NRC) that some information provided by the Davis-Besse Nuclear Power Station (DBNPS) in four prior submittals may not be complete and accurate in all material respects as required by 10CFR50.9(a). It has been determined that none of the incomplete or inaccurate information has a significant implication for public health and safety or common defense and security, and these conditions are not being reported under 10CFR50.9(b). This letter informs the NRC of this matter in accordance with station procedures only.
The potentially incomplete or inaccurate information was discovered during our initial review of a sample of regulatory submittals to determine the extent of condition (EOC) to address the Davis-Besse 0350 Oversight Panel Restart Checklist Item 3.i, Process for Ensuring Completeness and Accuracy of Required Records and Submittals to the NRC. Checklist Item 3.i was added by NRC letter to FirstEnergy Nuclear Operating Company (FENOC) dated January 28,2003 (Reference Davis-Besse Letter Number Log 1-4336).
The initial reviews of submittals to the NRC are still underway, with an anticipated completion date of July 3 1,2003. In accordance with FENOCs plan governing this activity, FENOC will expand the scope of the sample of documents to be verified following the completion of the initial review on July 3 1.
The attached table provides a summary of the information provided to the NRC that may not be complete and accurate in all material respects. These issues have been documented in Condition Reports to determine appropriate corrective actions.
JUL 1 I 2003
Docket Number 50-346 License Number NPF-3 Serial Number 1-1324 Page 2 No commitments are identified in this letter or the attached enclosure.
If you have any questions or require further information, please contact Mr. Kevin L. Ostrowski, Manager - Regulatory Affairs, at (419) 321-8450.
Sincerely yours, GBDG Attachment Enclosure cc:
USNRC Document Control Desk J. B. Hopkins, DB-1 NRC/NRR Senior Project Manager C. S. Thomas, DB-1 Senior Resident Inspector Utility Radiological Safety Board
Docket Number 50-346 License Number NPF-3 Serial Number 1 - 1324 Attachment Page 1 of 1 COMMITMENT LIST The following list identifies those actions committed to by the Davis-Besse Nuclear Power Station (DBNPS) in this document. Any other actions discussed in the submittal represent intended or planned actions by the DBNPS. They are described only for information and are not regulatory commitments.
Please notify the Manager - Regulatory Affairs (419-321-8450) at the DBNPS of any questions regarding this document or associated regulatory commitments.
COMMITMENTS None DUE DATE NIA
Docket Number 50-346 License Number NPF-3 Serial Number 1 - 1324 Enclosure Summary of Information Provided to the NRC that May Not be Complete and Accurate in All Material Respects Submittal Licensee Event Report LER 99-003 Licensee Event Report LER 98-005 License Amendment Request No. 96-0008 Response to an NRC Request for Additional information regarding an inservice Inspection Relief Request Reference Letter NP-33-99-003-0 August 26, 1999 NP-33-98-005-0 July 11, 1998 FENOC Letter Serial 2397 July 28, 1999 FENOC Letter Serial 2736 Nov. 27,2001 Page 3 of3 4 of4 Att. 1 8 of 19 Att. 2 10 of 12 Statement in Submittal Within the last three years, there have been no Licensee Event Reports related to overcooling the Reactor Coolant System or the Pressurizer.
There have been no LERs in the previous three years involving operation of a component in the wrong train of a system.
This evaluation concluded that the equipment qualtfication tests demonstrate that the instruments required to monitor the course of an accident have a qualified lif. of approximately I year or greater, which is consistent with the Toledo Edison Design Criteria Manual.
Pipe sizes witli wall thickness less than 3/8 (including the group with wall thickness less than 1/5? range from 6 to 18 NPS.
Summary of Incomplete/lnaccurate Information A review of LERs three years prior to LER 99-003 identified another LER related to overcooling of the Reactor Coolant System. (LER 98-01 1 was reported to the NRC on November 13, 1998)
A review of LERs three years prior to LER 98-005 identified two additional LERs involving events where operation of a component in the wrong train of a system occurred. In addition, two other occurrences of a similar nature were found within the Davis-Besse Corrective Action Program but were not included in the Failure Data section of LER 98-005. This is contrary to guidance found in NUREG-1022, Revision 1 published in January 1998.
initial review identified at least one instrument that was qualified for about 0.58 years. The design requirement for the qualified life, applicable to this instrument at the time of the subject submittal, was one year.
Subsequent re-analysis has determined that this instrument is now qualified for one year with margin using current containment temperature profiles.
The range should have stated 6 to24 NPS.