ML20198C936
| ML20198C936 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 10/10/1985 |
| From: | Watson R CAROLINA POWER & LIGHT CO. |
| To: | Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| CON-NRC-393, REF-PT21-85, REF-PT21-85-468-000 215, HO-850218-(O), NBI-OSI, PT21-85-468, PT21-85-468-000, NUDOCS 8511120225 | |
| Download: ML20198C936 (4) | |
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So-Yo o CP&L Carolina Power & Light Company NN l
~ ia a g; 3 7 SilEARON HARRIS NUCLEAR PROJECT P.O. Box 165 New Hill, North Carolina 27562 0'T 10 W J
File Number:
SHF/10-13510 Letter Number: HO-850218 (0)
-x Dr. J. Nelson Crace United States Nuclear Regulatory Commission Region II 101 Marietta Street, Northwest (Suite 2900)
Atlanta, Georgia 30323 CAROLINA POWER & LICllT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT 1986 - 900,00 KW - Unit 1
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WESTINCHOUSE SAFETY CRADE CORE EXIT
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THERMOCOUPLES, ITEM 215 Dear Dr. Gracet Attached is our second interim report on the subject item, which was deemed reportable per the provisions of 10CFR50.55(e) and 10CFR, Part 21 on May 28, 1985. CP&L is pursuing this matter, and it is currently projected that corrective action and submission of the final report will be accomplished by January 1, 1986.
Thank you for your consideration in this matter.
Yours very truly,
[
R. A. Watson Vido President Shearon liarris Nuclear Power Plant MWijsb Attachment cet Messrs. C. Maxwell (NRC-SHNPP).'
J. M. Taylor (NRC) 8511120225 851010 PDR ADOCK 05000400
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l CAROLINA POWER & LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT NO. 1 SECOND IhTERDi REPORT WESTINCHOUSE SAFETY CRADE CORE EXIT THERMOCOUPLES ITDi 215 OCTOBER 4, 1985 g
6 REPORTABLE UNDER 10CFR50.55(e) AND 10CFP21 4
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SUBJECT:
Shearon Harris Nuclear Power Plant - Unit No. I 10CFR50.55(e) and 10CFR21 Reportable Deficiency. Testing of various components of the Safety Grade Core Exit T/C System indicates that the thermocouple signal will be maintained although some errors could be experienced during HELB.
This potential error could exceed the allowance for certain systems using the thermocouple system.
ITEM:
Safety Grade Core Exit Thermocouples
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SUPPLIED BY:
NATURE OF I
DEFICIENCY:
As part of qualification testing done by Westinghouse during the WCAP 8587 Program, some errors were experienced in the thermocouple signal. These errors are postulated to be caused by a combination of moisture ingression and thermal expansion in the thermocouples, connectors, potting adapters, splices, and the reference junction box.
The thermocouple signal is used in three areas at Shearon Earris; Reactor Coolant System (RCS) subcooling margin and the detection of Inadequate Core Cooling (ICC), and temperature compensation of the Westinghouse Reactor Vessel Level Indication System (RVLIS).
DATE PROBLEM OCCURR ED:
CP&L was notified May 10, 1985.
DATE PROBLEM REPORTED:
On May 28, 1985, CP&L (N. J. Chiangi) notified the NRC (Mr. A. Hardin) that the item was reportable under the provisions of 10CER50.55(e) and 10CFR, Part 21.
(Note:
CP&L Interim Report dated June 26, 1985 stated in error that CP&L notified the NRC on March 28, 1985.)
SCOPE OF PROBLEM:
These potential errors affect the RCS subcooling margin calculation and the Inadequate Core Cooling detection.
The RVLIS temperature compensation is not adversely affected.
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SAFETY EHPLICATION:
CP&L has not fully completed its evaluation of the potential errors and their effect due to ongoing Westinghouse investigation. With current information available, potential for errors could result in consequences more severe than currently described in plant final safety analysis.
REASON DEFICIENCY IS REPORTABLE:
This is reportable as a design error since, as presently designed, the error in the thermocouple signal could be greater than that assumed in the present analysis.
CORRECTIVE ACTION:
Westinghouse is to establish cause and recommendations on modifications necessary to correct problem.
Westinghouse continues to test subject equipment with a scheduled report to be issued to CP&L by November 30, 1985. Results will be evaluated before corrective action is implemented.
FINAL REPORT:
The final report on this item is pending completion of the corrective actions described above.
It is currently projected that the final report will be issued by January 1, 1986.
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