ML20108C717

Part 21 & Sixth Interim Deficiency Rept,Item 41 Re Failure of Reactor Protection Sys Following Secondary High Energy Line Rupture.Initially Reported on 800707.Westinghouse Steam Generator Ref Leg Insulated.Final Rept by 841130

ML20108C717
Person / Time
Site:	Harris
Issue date:	10/01/1984
From:	Parsons R CAROLINA POWER & LIGHT CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
CON-NRC-276, REF-PT21-84 41, NUDOCS 8411190042
Download: ML20108C717 (4)

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' Caro lina Power & Light Company .

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' l La j P. O. Box 101, New Hill,-NC .27562 October 1, 1984 S.

Mr. James P. O'Reilly NRC-276 United States Nuclear Regulatory Commission Regic". 11 101 M etta'Streeet,' Northwest (Suite 2900)

Atlanta,. Georgia .30323~ '

CAROLINA' POWER & LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT -

1986 - 900,000 KW - UNIT 1 POTENTIALLY-SIGNIFICANT FAILURE OF THE REACTOR PROTECTION SYSTEM FOLLOWING A

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

Dear Mr. O'Reilly:

Attached is our sixth 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 November 30, 1984.

Thank you for your consideration in this matter.

Yours very truly, R. M. Parsons Project General Manager Shearon Harris Nuclear Power Plant

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Attachment t

ec: Messrs. G. Maxwell /R. Prevatte (NRC-SHNPP)

Mr. R. C. DeYoung-(NRC)

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8411190042 841001 PDR ADOCK 05000400 OFFICTAL COPY

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

ITEM 41-

-SEPTEMBER 28, 1984 4

REPORTABLE UNDER 10CFR50.55(e) i i

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110CFR50.55(e)' Reportable Item

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SUBJECT:

Shearon' Harris' Nuclear Power-Plant Unit l'

- ' Potential;Significant Failure offthe~Reactorf Protection System Following a SecondaryLHigh Energy Line-Break-(Steam-GeneratorLReference' Leg Heatup)

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- ITEM: Steam Generator Level Measurement for SHNPP Unit il-

-SUPPLIED BY: Westinghouse Water-Reactor Division! <

- NATURE OF4

. 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 heatu9 of.the system generator level measurement reference leg. LA-heatup;of the' a

reference leg would result:in severe density. changes

. whichL would give erroneous -indication of. steam generator: water leveli '

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 123, 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.

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.

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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

- generat.or reference leg as.a permanent solution to- ,

the heatup concern. . Corrective action will.be-

- achieved by 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 November- 30, 1984.

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