ML20003C828

Responds to NRC Info Request 121.27 Re Preservice Insp Program Plan.Discusses Program Status Re Piping & Vessel Welds,Components & Supports on Reactor Coolant Pressure Boundary

ML20003C828
Person / Time
Site:	Shoreham File:Long Island Lighting Company icon.png
Issue date:	03/16/1981
From:	Novarro J LONG ISLAND LIGHTING CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
SNRC-543, NUDOCS 8103180526
Download: ML20003C828 (2)

Text

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~ 74*F C W W W SHOREHAM NUCLEAR POWER STATION P 0. BOX 604, NORTH COUNTRY ROAD e WADtNG RNFR, N.Y.11792 March 16, 1981 SNRC-543

$ N Mr. Harold R. Denton e g Di'.ector of Nuclear Reactor Regulation f(

U. S. Nuclear Regulatory Commission 9i Washin-Jton, D. C. 20555 ..gf. 1 q $ @[

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.s' Preservice and Inservice Inspection Progr A Shoreham Nuclear Power Station - Unit 1 4'f '

Docket No. 50-322 ' ' ' ' -

Dear Dr. Denton:

In response to NRC Information Request 121.27, information regarding the Shoreham Nuclear Power Station Preservice Inspec-tion (PSI) Program Plan was provided.

The purpose of this letter is to provide the current status -

of the PSI Program. As yo'.1 are aware, the intent of this program is to meet the requirements of Section XI of the ASME Boiler and Pressure Vessel Code, " Rules for Inservice Inspection of Nuclear Reactor Coolant Systems", 1971 Edition including the 1972 Summer Addenda. The scope is to include piping, components and s'ipports on the Reactor Coolant Pressure Boundary, identified as Quality Group Classification A in Table 3.2.1-1 of the FSAR.

As far as the present status of the program is concerned, the following has been determined:

a. Piping Welds - Approximately 90% of the welds have been examined to date. Thus far, only eight cases have been identified as inaccessible or partially inaccessible for examination in accordance with the present PSI program.

Modifications are being investigated which might render these welds accessible,

b. Vessel Welds - An estimated 15% of the welds have been examined to date, with no anticipated interferences for PSI. Certain welds will require utilization of test reports of inspections performed prior to setting of the vessel. Examination of the remaining Reactor Vessel Welds is wheduled to be completed by 1/82. Of S

8103180526

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Mr. Harold R. Denton SNRC-543 March 16, 1981 Page 2

c. Pipe Supports - No problems are anticipated with the visual inspection of pipe supports. Completion is scheduled by 9/81.

Based on current information and suitable resolution of "a" above, we do not anticipate that any significant number of additional requests for relief from the requirements of the ASME Code will be necessary. However, it is expected that there will be some additional exemptions (as permitted by Section XI) beside those already stipulated in the PSI Program Plan.

With regard to the Inservice Inspection (ISI) Program, the initial draft for the first 40 month inspection interval for Shoreham is being developed based on the Summer 1978 Edition and Addenda of ASME Section XI as stated in our response to NRC Information Request 121.30. However, in accordance with the provision of 10CFR50.55a (g), inservice examinations conducted during the first 40 months must comply with the require-ments in the editions of the code and addenda in effect no more than 6 months prior to the date of start of operation. There-fore, it may be necessary to comply with a later Edition of the ~

ASME Code and issuance of the Inservice Inspection Plan will be withheld until a firmer definition of the Code requirement is available.

If additional information is required, please contact this office.

Very t' ly yours, A

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J. P. Nov rro Project Manager Shoreham Nuclear. Power Station-RWG:mp cc: Mr. J. Higgins l

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