ML20009C225

Forwards LER 81-046/01T-0.Detailed Event Analysis Encl

ML20009C225
Person / Time
Site:	McGuire
Issue date:	05/07/1981
From:	Parker W DUKE POWER CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20009C226	List: ML20009C225 ML20009C231
References
NUDOCS 8107200390
Download: ML20009C225 (3)

Text

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OPPICI,1L C opy * ,

Dtrxi: POWER CO>IPANY - '

PowEn BUH. DING 422 SouTu ChuHcu STREET, CHAHLOTTE, N. C. 20242 Il'A'(;; ay, g WI L LI AM O. PA R M E R, J R.

e pacs.or~r May 7., 1981 rcte.-o~c: 4 c. 70 Sicane PmCOvCHON 373-4o83 f/.-65 3 63D Mr. J. P. O'Reilly, Director U. S. Nuclear Regulatory Conm.ission p ,

Region II '

101 Marietta Street, Suite 3100 q p

Atlanta, Georgia 30303 ,

' _ ' JUL 1719815 Re: McGuire Nuclear Station Unit 1 Docket No. 50-369

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Dear Mr. O'Reilly:

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Please find attached Reportable Occurrence Report R0-369/81-46. This report concerns an inspection / leak detection program being considered applicable to Loop 10-inch Accumulator Injection line contrary to the existing Licensing agreenent.

This incident was considered to be of no significance with respect to the health and safety of the public.

Very truly yours,

/d k O.

William O. Parker, Jr.

RWO:dj s l cc: Director Mr. Bill Lavalee Office of Management and Program Analysis Nuclear Safety Analysis Center U. S. Nuclear Regulatory Commission Post Office Box 10412 Washington, D.C. 20555 Palo Alto, California 94303 Mr. Harold R. Denton, Director M. J. Graham Office of Nuclear Reactor Regulation Resident Inspector McGuire Nuclear Station l &ll l

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MCGUIRE NUCLEAR STATION UNIT 1 REPORT NO: Incident No. 81-46 REPORT DATE: May 5, 1981 FACILITY: McGuire Nuclear Station, Unit 1 IDENTIFICATION OF DEFICIENCY: Inspection / Leak Detection Program Considered Applicable To Loop B 10-inch Accumulator Injection Line, Contrary To Existing Licensing Agreement.

INITIAL REPORT: On April 23, 1981, Mr. Jack Bryant of NRC Region II, Atlanta, Georgia was notified of this deficiency by Mr. A. P. Cobb, Jr. and Mr. Morris Sample of Duke Power Company, Charlotte, North Carolina, 28242.

DESCRIPTION OF DEFICIENCY: A deficiency occurred in implementation of the existing licensing agreement for pipe rupture protection, whereby inspection / leak detection measures were assumed fer postulated breaks in Loop B 10-inch Accumulator Injection line in lieu of providing structural restraints or barriers to prevent unacceptable interactions. As such, protection for jet impingement interactions with two 1-inch Nuclear Sampling lines, one 3/4-inch Nuclear Sampling line, and one 2-inch Steam Generator Blowdown line, and an electrical cable supplying power to a containment isolation valve, has not been provided in accordance with requirements. The deficiency occurred as a result of not updating a design document to reflect the firal licensing agreements reached with the NRC staff as specified in the February 9, 1979 letter from R.S. Boyd to W.O. Parker.

Unit 2 work in this area has not progressed sufficiently to have encountered this problem; however, documentation changes are required to prevent its occurrence.

ANALYSIS OF SAFETY DTPLICATION: Loss of integrity of the 3/4-inch or 1-inch Nuclear Sampling or 2-inch Stera Generator Blowdown line could result in propagation of the postulacad injection line break to other loop (s) of the i Reactor Coolant System, or to the Secondary Side piping, or both. Loss of functional integrity of these components, or the electrical cable providing power to the walve, in conjunction with other simultaneously postulated events

' could result in loss of containment integrity. Loss of the Nuclear Sampling or Steam Generator Blowdown lines as a result of the Accumulator Injection line break has been enveloped by previous analyses.

CORRECTIVE ACTION: Duke will formally implement the inspection / leak detection program for postulated pipe ruptures on the affected Loop B 10-inch Accumulator Injection lines (Loops A, C, & D). These censist of the following:

(1) Examination of welds in accordance with frequency requirements of ASME Section XI.

(2) Performance of additional surface examination for each weld while the system is under pressure.

(3) Performance of volumetric examination of each weld while the system is under pressure.

(4) Performance of hydrostatic pressure test as required by ASME Section XI.

(5) Continuous monitoring of postulated break locations with acoustic leak detection devices to provice instant indication of any through-wall leakage (visual & audible alarm in Control Room).

The Electrical cable will be rerouted to preclude jet impingement due to postulated pipe ruptures inside Containment. Also, the design document will be revised co reflect use of inspection / leak detection program on all 10-inch Accumulator Injection lines and other applicable licensing agreements.

SCHEDUIE:

The schedule for completing the above corrective action is as follows:

ITEM COMPLETION DATE Initial Criticality Implement Leak Detection-Loop B Initial Criticality Re-route Cable Revise Document 6/15/81 Currently initial criticality is scheduled for May 28, 1981.

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