ML20065P717
| ML20065P717 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 04/21/1994 |
| From: | Opeka J NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES SERVICE CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| B14825, NUDOCS 9404290252 | |
| Download: ML20065P717 (5) | |
Text
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- g##//Jg7 Utilities Systen' w e e w e,w com,m P.O. Box 270 llartford, CT 06141-0270 (203) 665-5000 April 22, 1994 Docket No. 50-423 B14825 U.S.
Nuclear Regulatory Commission Attention:
Document Control Desk Washington, DC 20555 Millstone Nuclear Power Station, Unit No. 3 Inspection Report No. 50-423/93-81 Schedule for Resolution of Unresolved Items In a letter dated February 16, 1994,0) the NRC Staff transmitted Inspection Report No. 50-423/93-81 to Northeast Nuclear Energy Company (NNECO).
The inspection report provided the results of an electrical distribution system functional inspection conducted during the period between October 18 and November 5,
1993.
In the inspection
- report, the NRC Staff requested that NNECO
- provide, in
- writing, within 60 days after receipt of the inspection
- report, a
schedule for the resolution of the unresolved items identified in the report and an itemization of the actions taken or planned to enhance the functionality of the electrical distribution system.
In Inspection Report 50-423/93-81, the NRC Staff identified four unresolved items. provides NNECO's schedule for resolution of the four unresolved items, on behalf of Fillstone Unit No.
3.
1 Additionally, the actions taken or planned to enhance the functionality of the electrical distribution system are described in Attachment 1 of this submittal, 2)and in our reply to the notice of violation dated March 18, 1994.(
(1)
J.
T.
Wiggins letter to J.
F.
Opeka, " Notice of Violation, NRC Inspection Report No. 50-423/93-81," dated Februar.y'16, 1994.
(2)
J.
F.
Opeka letter to the U.S.
Nuclear Regulatory Commission, " Millstone Nuclear Power Station, Unit No.
3, t
Reply to a
Notice of Violation, Inspection Report No.
50-423/93-81," dated March 18, 1994.
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IJ. S. Nuclear Regulatory Commission B14 82 5/Pago. 2 April 22, 1994 We trust that you will find this information satisfactory.
We remain available to answer any questions you may havo.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY f.tAl-
- x. -
J. F. dpdha 1
Executive Vice President cc:
T. T.
Martin, Region I Administrator V.
L. Rooney, NRC Project Manager, Millstone Unit No. 3 P.
D.
Swotland, Senior Resident Inspector, Millstone Unit Nos.
1, 2,
and 3
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Docket No. 50-423 B14825 1
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Millstone Nuclear Power Station, Unit No. 3 Inspection Report 50-423/93-81
- 1 Schedule for Resolution of Unresolved Items
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a April 1994
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Millstorie Nuclear Power Station, Unit No. 3 Inspection Report 50-423/93-81 Schedule for Resolution of Unresolved Items DESCRIPTION OF UNRESOLVED ITEM UNRESOLVED ITEM #
COMPLETION DATE m
)
1.
Maximum Grid Voltage (1) 50-423/93-81-04 12/31/94 2.
Degraded Grid Relay 50-423/93-81-05 7/29/94 Sotpoints (2) 3.
Capacity of Transformer 50-423/93-81-06 COMPLETE Supply Cables (3) 4.
Battery Service Tests 50-423/93-81-07 COMPLETE Profile (4)
(1) a.
Revice Specification SP-EE-269, titled
" Electrical Design Criteria," Calculation No. NL-024, titled "Short Circuit Calculation for Individual Containment Electrical Penetration Circuits," Calculation No. NL-
- 038, titled
" Station Service Studies Voltage i
Profiles," and Calculation No. 177E, titled "120 ' Volt System Short Circuit Study."
b.
Evaluate the feasibility of installing a transformer to
'l enhance design basis grid voltage stability, c.
Revised Calculation No. NL-051, titled "MP3 6.9 kV'&
4.16 kV System Short Circuit Studies."
(2)
Calculation No.
NL-042GE, titled "MP3 Degraded Voltage Protection Scheme Relay Settings," has been revised, and a i
technical specification change request -is currently being processed.
A proposed revision to the Millstone Unit No. 3 Technical Specifications will be submitted to the NRC Staff for review and approval by the completion date noted in the table.
(3)
Calculation No.
91-019-556E3, titled "Ampacity of RSST &
NSST Secondary Cables and SBO Diesel Cen.
Emergency Generator Leads Installed in Ductbanks," shows that the
.j transformer secondary feeders are adequately sized for the present station service load as identified in Calculation No.
NL-026, titled
" Reserve and Normal Station Service Transformer Load Study. "
Therefore, the issue of adequate capacity for the transformer supply cable supply plant load i
an U. S '. Nuclear Regulatory Commission B14825/Attachmenc 1/Page 2 April 22, 1994 is resolved.
However, Calculation Mo. 91-019-556E3 will be revised to reflect actual field conditions for such items as ground temperature, concrete temperature, etc., In order to reduce some of the conservative engineering judgement utilized for these parameters.
By revising the calculation to reflect actual field conditions, the transformer 1
secondary feeders should more closely match the transformer ratings.
(4)
Millstone Unit No. 3 Station Procedure No. SP 3712NB, titled
" Battery Surveillance Discharge Testing," has been revised.
to reflect the latest loading cycle provided in Calculation l
No.
188E,. titled " Battery Size Calculations and Battery Charger Size Calculations."
In addition, Millstone Unit No.
j 3 Technical Support and Plant Maintenance Departments have been added to the distribution of revisions associated'with Calculation No.
188E to ensure the System Engineer is
-I cognizant of any calculation change so that the related-surveillance procedure can be revised appropriately.
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