ML20073D646
| ML20073D646 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 04/19/1991 |
| From: | Shelton D CENTERIOR ENERGY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| REF-GTECI-099, REF-GTECI-NI, TASK-099, TASK-99, TASK-OR 1925, GL-90-04, GL-90-4, NUDOCS 9104290159 | |
| Download: ML20073D646 (3) | |
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CENTEnton ENERGY Donald C. Shelton 300 Madison Avenue Vce Preddent Nudear Toledo, OH 436520X)1 Da h (419)249 2300 Docket Number 50-346 License Number NPP-3 Serial Number 1925 April 19, 1991 United States Nuclear Regulatory Commission Document Control Desk Vashington, D. C.
21555 Subj ec t :
Additional Response to Generic Letter 90-04: ' Status of Implementation of Generic Safety Issue (GSI) Number 99 Gentlemen:
The Nuclear Regulatory Commission (NRC) requested in Generic Letter 90-04 (Toledo Edison Log Number 3232), dated _ April 25, 1990, that Toledo Edison provide the status of the implementation of specific Generic Safety Issues (GSIs) at the Davis-Besse Nuclear Power Station (DBNPS), Unit 1.
In response to Generic Letter 90-04, Toledo Edison completed the table of GSIs (supplied as Enclosure 1 to Generic Letter 90-04) to provide a summary status of each GSI requirement or corrective action. The completed table was submitted to the NRC as an enclosure to Toledo Edison letter Serial Number 1818, dated June 29, 1990.
With respect to GSI 99 (MPA L817), Toledo Edison provided the present status in Serial Number 1818 as follows:
GSI/(MPA No.)
Title Applicability Status
- Comments 99(L817)
RCS/RIIR Suction All PVRs I
Outstanding Line Valve work; review Interlock on PVRs
' alarms and effectiveness for loss of decay heat e
removal and os$$
provide ggC.
additional oo information, if necessary,-
y by 12/91.
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gg "I" means change is necessary, but isn't complete.
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4 Docket Number 50-346 License Number NPF-3 Serial Number 1925 Page 2 Following Toledo Edison's response (Serial Number 1818) to this Generic Letter, the NRC subaltted a letter to Toledo Edison, dated December 7, 1990 (Toledo Edison Log Number 1-2406).
The enclosure to this NRC letter summarized the NRC Staff's understanding of the current status of those GSIs which remain unimplemented at DBNPS.
Vith respect to GSI 99, the NRC's status (Log 1-2406) was as follows:
GSI/(HPA No.)
Title Projected Implementation Comments Date 99/L817 RCS/RHR Suction 12/91 Interlocks Line Valve Interlock to be on PVRs removed at the end of the current fuel cycle (cycle 7)-
Tne information in the " comments" column has been changed significantly by the NRC Staff from that which Toledo Edison submitted in letter Serial Number 1818.
Subsequently, Toledo Edison has' discussed this change with the-NRC Staff and has been unable to determine the basis for.the NRC's information.
j The NRC's technical resolution of GSI.99 was achieved with the issuance of Generic Letter 88-17 (Loss of Decay Heat' Removal). Toledo Edison responded to Generic Letter Number 88-17 in Toledo Edison letters dated January 3, 1989 (Serial Number 1623) and February 1,-1989 (Serial Number 1631). Toledo Edison's GSI 99 status description to review alarms and-their effectiveness in indicating an approach to the loss of decay heat removal _by December, 1991 represents the latest-Toledo _ Edison projected completion date for actions recommended by Generic Let ter Number 88-17 and - thereby' bounds the overall completion of remaining vork to bez implemented for GSI 99..
Furthermore, in response to Generic Letter Number 87-12 (Loss of Residual Heat Removal While the Reactor Coolant System (RCS) Is Partially Filled),
Toledo Edison stated in letter Setial Number 1423,' dated September 23, 1987, that the interlocks associated with'the RCS boundary valves-that provide the.
suction flovpath for Decay Heat Removal-(DHR) operations (DH 11 and-DH-12)'
were not a problem for DHR operations. Technical Specifications-3/4.4.1.2 and 3/4.4.2 and plant proce'ures require the removal of_ control power from d
DH 11 and DH 12, once they are opened, to prevent their inadvertent. closure while the DHR system is in-operation. -Therefore, contrary to the NRC status for GSI 99 (Log Number 1-2406), Toledo Edison does not intend-to> remove:the interlocks associated with DHR suction valves DH 11~and DH'12.
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Docket Number 50-346 License Number NPF-3 Serial Number 1925 Page 3 Accordingly, Toledo Edison requests the difference between Toledo Edison's-j submittal (Serial Number 1818) and the NRC's letter (Log Number 1-2406,.
l dated December 7, 1990) on the status of GSI 99 be resolved by utilizing the
" comments" originally submitted by Toledo Edison letter Serial Number 1818.
If you have any questions, please contact Mr R. V. Schrauder, Manager -
l Nuclear Licensing, at (419) 249-2366.
i Very truly yours,
'I (f( ^x,$3' I
~
RAS /mmb cci P. M. Byron, DB-1 NRC Senior Resident Inspector i
A. B. Davis, Regional Administrator, NRC Region III J. R. Hall, NRC Senior Project Manager H. D. Lynch, NRC Senior Project Manager Utility Radiological Safety-Board f
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