ML20209B582
| ML20209B582 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse |
| Issue date: | 06/24/1999 |
| From: | Campbell G CENTERIOR ENERGY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 2604, 50-346-97-201, 50-346-98-03, 50-346-98-3, NUDOCS 9907070231 | |
| Download: ML20209B582 (4) | |
Text
m I
" 4 E
S50 S
R 2
5 Oak Harbor, ohio 43449-0760 Quy G. Campbell 41 % 21-8688
. Vwe PresMent Nudeer Fac 419-321-8337 Docket Number 50-346 License Number NPF-3
- Serial Number 2604
-June 24, 1999 United States Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555-0001
Subject:
Change to Commitment for Inspector Follow-up Item 50-346/97-201-10 Ladies and Gentlemen:
By letter dated November 7,1997, the Davis-Besse Nuclear Power Station, Unit 1 (DBNPS) submitted a response (letter Serial Number 2498) to the Nuclear Regulatory Commission (NRC)
Inspection Report (IR) Number 50-346/97-201 (DBNPS Log Number 5122, dated September 4, 1997), Davis-Besse Design Inspection. Letter Serial Number 2498 detailed the DBNPS commitments and associated completion dates for the inspection follow-up and unresolved items identified in IR 50-346/97-201. Inspection Report Number 50-346/98-003 (DBNPS Log Number 1-3949, dated March 10,1998) presented the results of the follow-up NRC inspection to the Davis-Besse Design Inspection which was completed on February 26,1998. Inspection Report Number 50-346/98-003 identified three (3) inspection follow-up items which would remain open, and cited updated commitment completion dates for the items. Attachment I to this letter provides justification for revision to the completion date for one of the inspection follow-up items cited in Inspection Report Number 50-346/98-003, designated as Inspector Follow-up Item 50-346/97-201-10.
In accordance with the Nuclear Energy Institute's " Guideline for Managing NRC Commitments,"
and as accepted in NRC SECY-95-300, the DBNPS is informing the NRC of this change. No NRC approval is required or requested.
I I
[/
'pI27o7o231 990Mt4" 4
anoca osoooa46 a
FDR2 1
)
r Docket Number 50-346 License Number NPF-3 Serial Number 2604 -
Page 2 Should you have any questions or require additional information, please contact Mr. James L.
Freels, Manager-Regulatory Affairs at (419) 321-8466.
Very truly yours, M
ns i
RMC/dic
' Attachments cc:
J. E. Dyer, Regional Administrator, Region III S. N. Bailey, NRC/NRR Project Manager K. S. Zellers, DB-1 Senior Resident Inspector Utility Radiological Safety Board
~
j
=
t Docket Number 50-346 License Number NPF-3 Serial Number 2604 Page1of1 JUSTIFICATION FOR CHANGE TO COMPLETION DATE FOR INSPECTOR FOLLOW-UP ITEM 50-346/97-201-10, HIGH CONTAINMENT PRESSURE (SFAS LEVEL 3) ACTUATION SETPOINT Toledo Edison Regulatory Management System (TERMS) Tracking Number 18944 The NRC Inspection Team noted inconsistencies in the calculation documentation for the Safety Features Actuation System (SFAS) Level 3 containment high pressure trip setpoint and the lack of supporting documentation for instrument loop inaccuracies. Technical Specification (TS)
Table 3.3-4, " Safety Features Actuation System Instrumentation Setpoints," provides a trip setpoint of 18.4 psia with an allowable value of 18.52 psia. A DBNPS letter (Serial Number 685) dated January 30,1981, addressed revising the setpoint in accordance with NUREG-0737, "TMI Action Plan,Section II.E.4.2.5, Containment Isolation Dependability." This letter documented an 18.24 psia setpoint and an 18.39 psia allowable value. The letter stated that the current TS values were acceptable and required no changes because they compared very closely to the new calculated values. Subsequently, DBNPS Calculation C-ICE-048.01-001 was performed utilizing a new methodology to improve operational margins and resulted in an instrument string uncertainty of 1.5 psi which, when applied to the analytical limit, would result in a setpoint of approximately 19.08 psia. A License Amendment Request (LAR) was submitted on February 17,1993 (DBNPS Serial Number 2025) to propose,in part, a revision of the containment high pressure setpoint. However, this portion of the LAR was later withdrawn on February 10,1995 (DBNPS letter Serial Number 2276), due to plans to change the setpoint methodology and extend the operating cycles to 24 months. The NRC Design Inspection Team identified the calculation inconsistencies and instrument loop inaccuracies as a weakness in IR 97-201. The DBNPS agreed to update Calculation C-ICE-048.01-001 and submit a LAR by June 30,1999. This commitment was further documented in IR 98-003.
' The previous commitment will not be met because of competing internal priorities. However, the calculation update has recently been completed and the LAR has been drafted. The LAR will be submitted to the NRC no later than September 30,1999. It should be noted that the existing setpoint is conservative with respect to the newly calculated setpoint; therefore, the change in the commitment date does not affect nuclear safety.
. =
Docket Number 50-346 License Number NPF-3
,, Serial Number 2604 Page1ofI COMMITMENT LIST The following list identifies those actions committed to by the Davis-Besse Nuclear Power Station in this document. Any other actions discussed in the submittal represent intended or planned actions by Davis-Besse. They are described only as information and are not regulatory commitments. Please notify the Manager - Regulatory Affairs (419-321-8466) at Davis-Besse of any questions regarding this document or associated regulatory commitments.
COMMITMENTS DUE DATE The previous commitment [to update the TS SFAS Containment 9/30/99 High Pressure Trip Setpoint] will not be met because of competing internal priorities. However, the calculation update has recently been completed and the LAR has been drafted. The LAR will be submitted to the NRC no later than September 30, 1999.
i i
i Commitment List, page 1 of 1 l