ML20112A534

Eighth Interim Deficiency & Part 21 Rept,Item 41 Re Failure of Westinghouse Reactor Protection Sys Following Secondary High Energy Line Break.Initially Reported on 800707.Design Changes Issued.Next Rept by 850430

ML20112A534
Person / Time
Site:	Harris
Issue date:	02/26/1985
From:	Parsons R CAROLINA POWER & LIGHT CO.
To:	Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
CON-NRC-329, REF-PT21-85, REF-PT21-85-103-000 41, PT21-85-103, PT21-85-103-000, NUDOCS 8503180346
Download: ML20112A534 (4)

Text

_ __

i *, i CD&L

2L?A w a P. O. Box 101, New Hill, N C 27562 February 26,1985 i

Dr. J. Nelson Grace NRC-329 United States Nuclear Regulatory Commission Region II

! 101 Marietta Street, Northwest (Suite 2900) y Atlanta, Georgia 30323 4

CAROLINA POWER & LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT 1986 - 900,000 KW - UNIT I -

POTENTIALLY SIGNIFICANT FAILURE OF THE REACTOR PROTECTION SYSTEM FOLLOWING A 4

SECONDARY HIGH ENERGY LINE RUPTURE (STEAM GENERATOR REFERENCE LEG HEATUP)-ITEM 41

Dear Dr. Grace:

Attached is our eighth interim report on the subject item which was deemed reportable per the provisions 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 April 30,1985.

Thank you for your consideration in this matter.

Yours very truly, R. M. Parsons Project General Manager Completion Assurance Shearon Harris Nuclear Power Plant i RMP/sae A ttachment cc Messrs. G. Maxwell /R. Prevatte (NRC-SHNPP)

Mr. R. C. DeYoung (NRC) 00 S PDR ggg i

OmCIAL COPY sel/I - . . - _ - . - . - -

I CAROLINA POWER & LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 EIGHTH INTERIM REPORT POTENTIAL SIGNIFICANT FAILURE OF THE REACTOR PROTECTION SYSTEM FOLLOWING A SECONDARY HIGH ENERGY LINE RUPTURE (STEAM GENERATOR REFERENCE LEG HEATUP)

ITEM 41 FEBRUARY 28, 1985 REPORTABLE UNDER 10CFR50.55(e)

{ '. . . 1 l

l

SUBJECT:

10CFR50.55(e) Reportable Item Shearon Harris Nuclear Power Plant Unit i Potential Significant Failure of the Reactor Protection System Following a Secondary High Energy Line Break (Steam Generator Reference Leg Heatup)

ITEM: 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 system 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.

CP&L letter dated March 30, 1984, R. M. Parsons to J. P. O'Reilly transmitting a fourth interim report.

CP&L letter dated July 30, 1984, R. M. Parsons to J. P. O'Reilly transmitting a fifth interim report.

CP&L letter dated October 1, 1984, R. M. Parsons to J. P. O'Reilly transmitting a sixth interim report.

CP&L letter dated November 30, 1984, R. M. Parsons to J. P. O'Reilly transmitting a seventh interim report.

( l J '- . .

SCOPE OF PROBLEM: Unit I steam generators (three per unit).

SAFETY IMPLICATIONS: An erroneous indication of the steam generator water level could result in delayed signals to the reactor protection system.

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. Corrective action will be achieved by the issuance of design changes that incorporate insulation of the steam generator reference legs.

FINAL REPORT: A final report will be issued when the corrective action has been completed. This is now anticipated to be April 30, 1985

- -.