ML20086F554
| ML20086F554 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 11/27/1991 |
| From: | Schuster T COMMONWEALTH EDISON CO. |
| To: | Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| TAC-M81019, TAC-M81020, NUDOCS 9112030281 | |
| Download: ML20086F554 (2) | |
Text
_ _ _ _ _ _ _ _ _ _. _ _ _
C:mm:nw alth Edison
) 1400 Opus Place Downers Grove, Illinois 6051$
November 27, 1991 Dr. Thomas E. Hurley, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 Attn: Document Control Desk
SUBJECT:
Byron Station Units 1 and 2 Response to Audit of Effectiveness of Safety-Related Check Valve Programs (TAC NOS. H81019 and H81020)
MRC_Docke tJosm50-A54_and.50-A55
REFERENCE:
A. Hsia letter to T. Kovach dated October 25, 1991
Dear Dr. Murley,
The referenced letter provided the results of an audit conducted by the Nuclear Regulatory Commission (NRC) from July 8 through 12, 1991, at Byron Station.
Based on the results of the audit, the NRC Staff concluded that the check valve programs at Byron Station appeared to be comprehensive, well thought out, and organized with management involvement.
The audit report did, however, identify several minor concerns regarding the Byron check valve program.
These five concerns were identified by the NRC Staff in Attachment 2.
Three of these concerns address issues which are programmatic in nature and can be summarized as follows:
1.
Six containment isolation valves greater than two inches (1/2RY8046 and 1/2WOOO7A&B) were in the IST program but not in the 50ER check valve program.
The NRC Staff recommended that these valves be reviewed by the licensee using the same c:iteria as applied to the valves in the check va've program to ensure consistent treatment and handling.
2.
Sixty-six other valves (two inches and under) were in the IST program, but not in the SOER check valve program.
The NRC Staff requested that Byron consider using additional criteria, such as system cleanliness, operational frequencies, and water chemistry for including safety significant valves in the SOER program.
3.
The Corporate Nuclear Operations Directive allowed the use of the IST program testing as an indicator of chect valve degradation in lieu of disassembly and inspection or diagnostic testing.
The NRC Staff requested justification for using the IST program for this purpose.
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Document Control Desk November 27, 1991 Because these three concerns may be considered programmatic in nature, CECO will review them from a generic standpoint to identify any required actions.
In order to properly respond to the programmatic concerns identified in the audit a comprehensive re-examination of the 50ER and lii programs with regard to these concerns will be performed.
This re-examination will require input from several corporate departments and all six CECO Stations.
A summary of that review describing any actions to be taken will be provided to the NRC by September 1, 1992.
The other two concerns identified on Attachment 2 of the audit report have been completed and the actions taken relative to the concerns are as follows:
1.
Attachment B to the Check Valve Preventative Maintenance Program, BVP 200-21Al, has been revised to include the RH pump discharge check valves 1/2RH8730A&B.
These valves had been inadvertently omitted from the procedure.
2.
The NRC was concerned that the pressure integrity of the diesel generator starting air system dryers could be lost during a seismic event based on preliminary information available during the audit.
It was requested that either documentation be provided to demonstrate that the dryers were capable of retaining pressure during c.nd af ter a seismic event, or begin pressure decay testing of the SA181 check valves since they would be depended upon to provide isolation.
Documentation was provided to the Byron Resident Inspector on July 19, 1991 and forwarded to Mr. D.
Danielson, Region III demonstrating that the dryers were capable of retaining pressure during and after a seismic event.
Respectfully, hfink b
hd Terence K. Schuster Nuclear Licensing Administrator cc: A.H. Hsia, Project Manager, NRR H. Kropp, Senior Resident Inspector A. Bert Davis, Regional Administrator
)
ZNLD/1350/2
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