ML20211B930
| ML20211B930 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 02/13/1987 |
| From: | Fay C WISCONSIN ELECTRIC POWER CO. |
| To: | Lear G NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| CON-NRC-87-17 VPNPD-87-68, NUDOCS 8702190607 | |
| Download: ML20211B930 (2) | |
Text
-
s; O
Wisconsin Electnc eom coumr 231 W. MICHIGAN P.O. BOX 2046, MILWAUKEE.WIS3201 (414)277-2345 VPNPD-87-68 NRC-87-17 February 13, 1987 Document Control Desk U.
S.
NUCLEAR REGULATORY COMMISSION Washington, D.
C.
20555
{
Attention:
Mr. George Lear, Project Director PWR Project Directorate 1 Gentlemen:
DOCKET NOS. 50-266 AND 50-301 APPENDIX R COMPLIANCE POINT BEACH NUCLEAR PLANT UNITS 1 AND 2 This is to confirm our notification to the PBNP resident inspec-tors on January 28, 1987 of two items related to Appendix R compliance which were discovered during review of fire protec-tion commitments in preparation for our upcoming NRC Appendix R inspection.
During 1986, we installed alternate source range instrumentation in both units to meet the commitments we made in our October 1983 Report, Alternate Shutdown Capability.
Since we could not procure and install the special electrical containment penetra-tions in accordance with the final design at that time, an alternate design was installed.
On January 28, 1987, we dis-covered that the normal 120 volt A.C. power supply cable for the pre-amplifiers of the source range instrumentation runs through the cable spreading room and could be destroyed by a fire in l
that room making the system inoperable, and that an alternate l
power supply was not provided.
Since the system is only I
required for cold shutdown, we issued a repair procedure for each unit on February 2, 1987 to describe the method of temporarily restoring power to the source range pre-amplifiers.
Additionally, we have begun the design of modifications to the existing system to provide a power supply in accordance with Appendix R requirements.
We expect to have these modifications completed during February, 1987.
8702190607 B70213 PDR ADDCK 05000266 h
G PDR p
g
i Document Control Desk February 13, 1987 Page 2 Our October 1983 Report also made a commitment to provide isola-tion provisions for the following cables which could affect the diesel generator start and operation from the local control panel:
1)
Auto Start Safeguard Circuit - Accident Auto Start 2)
Auto Start Safeguard Circuit - Undervoltage Auto Start We determined on January 28, 1987 that these modifications had not been completed as described.
We have initiated design modifications to provide means to isolate these cables and expect to have the modifications installed in March 1987.
In the interim, we have issued a Standing Order to Procedure AOP-10A, Control Room Inaccessibility, to provide instructions to_ operations personnel for disconnecting these cables if required.
If you have any questions or would like to discuss these items further, please contact me.
Very truly yours, f
C.
W.
Fay Vice President Nuclear Power Copy to Regional Administrator.- Region III i
l Resident Inspector i
j i
I
.. ~
,_,,,_ _