ML20087P219
| ML20087P219 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 03/30/1984 |
| From: | Parsons R CAROLINA POWER & LIGHT CO. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| CON-NRC-202, REF-PT21-84-241-000 41, PT21-84-241, PT21-84-241-000, NUDOCS 8404060172 | |
| Download: ML20087P219 (4) | |
Text
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O CP&L Q R{y$ ""4Iggight company a
,,.~ xxz-a P. O. Box 101, New Hill, N. C. 27562 March 30,1984 Mr. James P. O'Reilly N RC-202 United States Nuclear Regulatory Commission Region II 101 Marietta Street, Northwest (Suite 2900) l Atlanta, Georgia 30303 l
CAROLINA POWER & LIGIIT COMPANY SHEARON HARRE NUCLEAR POWER PLANT 1986 - 900,000 KW - UNIT 1 PROTECTION SYSTEM FOLLOWING A SECONDARY HIGH ENERGY LINE RUPTURE (STEAM GENERATOR REFERENCE LEG HEATUP)-ITEM 41
Dear Mr. O'Reilly:
Attached is our fourth interim report on the subject item which was deemed reportable per the providions of 10CFR50.55(e) on July 7,1980. CP&L is pursuing this matter, and it is currently projected that corrective action and submission of the final report will be accomplished by July 31,1984.
Thank you for your consideration in this matter.
Yours very truly, l
W
. M. Parsons l
Project General Manager Shearon Harris Nuclear Power Plant RMP/sh l
Attachment l
cc:
Messrs. G. Maxwell /R. Prevatte (NRC-SHNPP)
Mr. R. C. DeYoung (NRC)
OFFICIAL COPY 8404060172 840330 gl g PDR ADOCK 05000400 g
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4 CAROLINA POWER & LICHT COMPANY-SHEARON HARRIS NUCLEAR POWER PLANT 4
I-UNIT 1 FOURTH INTERIM REPORT 4
-POTENTIAL SIGNIFICANT FAILURE OF THE REACTOR PROTECTION SYSTEM FOLLOWING A SECONDARY HICH ENERGY LINE RUPTURE (STEAM CENERATOR REFERENCE LEC HEATUP) 4 ITEM'41 k
MARCH 30, 1984 1
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i REPORTABLE UNDER 10CFR50.55(e).
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SUBJECT:
10CFR50.55(e) Reportable' Item Shearon Harris Nuclear Power Plant Potential Sf gnificant Failure of the Reactor Protection System Following a Secondary High Energy Line Break (Steam Generator Reference. Leg Heatup)
ITEti:
Steam Generator Level Measurement for SHNPP Unit 1 SUPPLIED BY:
Westinghouse Water Reactor Division NATURE OF DEFICIENCY:
Westinghouse notified the NRC under 10CFR21 in June 1979 of a potentially significant failure of the reactor protection system following a secondary high energy line break.
Such a break within containment could result in the heatup of the steam generator level measurement reference leg. A heatup of the reference leg would result in severe density changes which would give erroneous indication of steam generator water level.
DATE PROBLEM WAS CONFIRMED TO EXIST:
Westinghouse Letter CQL-5801 dated March 20, 1980, received March 28, 1980.
PROBLEM REPORTED:
N. J. Chiangi notified the NRC (Mr. J. Bryant) that this item was reportable under 10CFR50.55(e) on July 7,1980.
CP&L letter dated July 8,1980 - N. J. Chiangi to J. P. O'Reilly transmitting an interim report.
CP&L letter dated December 23, 1981 - N. J. Chiangi to J. P. O'Reilly transmitting a second interim report.
CP&L letter dated June 1,1983 - R. M. Parsons to J. P. O'Reilly transmitting a third interim report.
SCOPE OF PROBLEM:
Unit I steam generators (three per unit).
SAFETY IMPLICATIONS: An erroneous indication of the steam generator water icvel could result in delayed signals to the reactor protection system.
.~
c REASON PROBLEM:
IS REPORTABLE: Delayed reactor protection signals could lead ~ to a
- degraded safety condition.
CORRECTIVE ACTION:
Westinghouse has now adopted insulation of the steam generator reference leg as a permanent solution to the heatup concern. Since containment piping insulation is not yet scheduled, corrective action will be achieved by implementing design changes to incorporate insulation of the steam generator reference legs. Design changes will be made as soon as the instrument tubing layout has been f inalized.
I FINAL REPORT: A final report will not be available until the corrective action has been completed, which is expected to be, July 31, 1984 for Unit 1.
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