ML20155C675

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Responds to Generic Ltr 88-05 Re Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components.Program Not Considered Applicable Based on Discussion Re Factors Contributing to High Rate of Boric Acid Corrosion
ML20155C675
Person / Time
Site: Crane Constellation icon.png
Issue date: 06/02/1988
From: Standerfer F
GENERAL PUBLIC UTILITIES CORP.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
4410-88-L-0088, 4410-88-L-88, GL-88-05, GL-88-5, NUDOCS 8806140288
Download: ML20155C675 (3)


Text

,i GPU Nuclear Ccrporation

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Middletown, Pennsylvania 17057 0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Number:

(717) 948-8461 June 2, 1988 4410-88-L-0088/0392P US Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555

Dear Sirs:

Three Mile Island Nuclear Station, Unit 2 (TMI-2)

Operating License No. DPR-73 Docket No. 50-320 NRC Generic Letter 88-05 NRC Generic Letter 88-05 addresses boric acid corrosion of carbon steel reactor pressure boundary components in PWR plants. The generic letter requested assurance that a program has been implemented consisting of systematic measures to ensure that boric acid corrosion does not lead to degradation of the reactor coolant pressure boundary integrity. Based on the following discussion, GPU Nuclear considers that the program specified in Generic Letter 88-05 is not applicable to TMI-2.

Three (3) major factors contribute to a high rate of boric acid corrosion o

low alloy steel:

1.

High temperature; 2.

Reactor coolant leakage; and 3.

Low alloy steel surface wetting.

The TMI-2 Reactor System Coolant Limiting Conditions for Operatien require that temperature be maintained less than 200 F and that the system remain open to building atmosphere. Operating experience shows that reactor coolant temperature is maintained less than 850F, The ongoing defueling operation requires that the Reactor Vessel head is removed, which ensures that the Reactor Coolant System (RCS) remains open to building atmosphere. This greatly reduces the pressure in the RCS; thus, the force for leakage is minimized and continuous surface wetting is avoided. This combination of actual TMI-2 reac".or coolant temperature and pressure ensures that:

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Document Control Desk June 2,-1988 4410-88-L-0088 1.

Trw possibility of reactor coolant leakage is minimized, and 2.

The corrosion rate _of, low alloy steel resulting.from a solution of boric acid is minimized.

Therefore, due to the. unique conditions of.TMI-2, the program identified in Generic Letter 88-05 does not appear applicable and THI-2 should be exempted Lfrom establishing the specific program identified therein.

Sincerely, l@' k's s

F,. Standerfer Director, THI-2 t

EDS/ emf Attachment cc: Senior Resident Inspector, TNE - R. J. Conte Regional Administrator, Region 1 - W. T. Russell Director, Plant Directorate IV - J. F. Stolz Systems Engineer, TMI Site - L. H. Thonus i

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ATTACHWNT-4410-88-L-0088 ETROPOLITAN EDISON COWANY JERSEY CENTRAL POWER AND LICHT COW ANY PENNSYLVANIA ELECTRIC COW ANY-GENERAL PUBLIC UTILITIES NUCLEAR CORPORATION Three Mile Island Nuclear Station, Unit.2 (TMI-2)

Operating License No. DPR-73 Docket No. 50-320 NRC Generic Letter 88-05 This letter is submitted in support of the Nuclear Regulatory Commission request concerning the March 17, 1988, letter transmitting NRC Generic Letter 88-05, "Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR Plants." All statements contained in this response have been reviewed, and all such statements made and matters set forth therein are true and correct to the best of my knowledge, information, and belief.

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r v F. R. 'Standerfer g Director, TMI-2 Signed and sworn before me this

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