ML20049J282

Forwards Request for Addl Info Re Inservice Insp Program. Response within 45 Days Requested

ML20049J282
Person / Time
Site:	Pilgrim
Issue date:	02/22/1982
From:	Vassallo D Office of Nuclear Reactor Regulation
To:	Morisi A BOSTON EDISON CO.
References
NUDOCS 8203120390
Download: ML20049J282 (4)

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Docket No. 50-293 Y

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fir. A. Victor Horisi, Manager Nuclear Operations Support Department p

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Dear fir. Morisi:

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L M' We are continuing our review of your submittals islated to the inservice inspection program for the Pilgrim Nuclear Power Station and have identified the need for additional information.

Accordingly, please provide the information requested in the Enclosure within 45 days of receipt of this letter.

The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.

Please contact your NRC Project Manager should you have any questions.

Sincerely, ORIGINALS 103 Domenic B. Vassallo, Chief Operating Reactors Branch #2 Divisiu of Licensing

Enclosure:

Distribution:

Request for Additional MDocket File G. Jotnson Infomation NRC PDR D. Chtney Local PDR K. Eccleston cc: w/ enclosure ORB #2 Reading See next page D. Eisenhut 0 ELD IE-1 J. Van Vliet S. Norris NSIC ACRS-10 Gray file N

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Mr. A. Victor Morisi Boston Edison Company cc:

Mr. Richard D. Machon Pilgrim Station Manager Boston Edison Company RFD #1, kocky Hill Road Plymouth, Massachusetts 02360 i

Henry Herrmann, Esquire Massachusetts Wildlife Federation 151 Tremont Street Boston, Massachusetts 02111 i

Plymouth Public Library

• fiorth Stre.et' Plymouth, Massachusetts 02360 Resident Inspector c/o U. S. NRC P. O. Box 867 Plymouth, Massachusetts 02360 Ms. JoAnn Shatwell Office of the Attorney General Environmental Protection Division 1 Ashburton Place 19th Floor Boston, Massachusetts 02108 Ronald.C. Haynes Regional Administrator, Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 0

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.e ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION INSERVICE INSPECTION PROGRAM PILGRIM #1 1.

Code Relief #2 This code relief request applies to a total of 15 pipe welds of category B-J, item B4.5, in the following systems:

Main Steam Reactor Core Isolation Coolant Feed Water Core Spray Residual Heat Removal High Pressure Coolant Ir.jection

- Reactor Water Cleanup The ASME Boiler and Pressure Vessel Code,Section XI,19.74 Edition tnrough the Summer 1975 Addenda, requires that these Class I welds be volumetrically examined.

Relief is requested.from volumetrically examining these 15 pipe welds bpcause they are located in triple-flued heads and are inaccessible.

At the time of design there vere no examination requirements for these welds. These 15 pipe welds are part of 495 pipe welds of category B-J, item B4.5, in the above systems, and all of the other pipe welds are inspected as part of the Inservice Inspection Program.

The following additional information is requested:

(a) Please clarify in the program table where this particular code relief is requested.

For the Residual Heat Removal System, the lines as identified in code Relief #2 description do not totally agree with the table.

(b) Describe the 'eak detection systems that would serve, and their proximity to, the areas in which these 15 pipe welds are located.

(c)' Discuss the capability of the bellows sleeve to withstand the full dynamic effects of a longitudinal or circumferential break of the enclosed process pipe, including jet impingement, pipe whip impact, and environmental effects.

If previously discussed in submittals to NRC, document by reference.

(d) Do any of the 15 pipe welds involve the welding of dissimilar metals?

2.

Code Reli'ef #5 This code relief request applies to the calibration block used in the per-formance of ultrasonic examinations of the reactor vessel.

Relief is requested from changing standards from the present unciad calibration block to clad bl ocks.

The following additional information is requested:

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5 (a) What experimental evidence will support the premise that the use of an unciad calibration does not significantly affect the validity -of the examination results?

(b) Identify in program table by Section XI category number and by Section XI item number, where this relief is requested.

3.

Code Relief #6 This code relief request applies to the calibration blocks used in the performance of ultrasonic examinations.

Relief is requested form machined notches in the calibration block.

The following additional informa,tipn,is re, ques _t.e.d:

(a) Identify in program table by 'Section XI category number and by Section XI item number, where this relief i.s requested.

(b) Discuss your capability to detect planar and near surface flaws.

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Code Ex'emption #1 This code exemption applies to pressure retaining welds and support com-ponents, categories B-0,. B-J, and B-K-2, pursuant to IWB-122dj}1) (Summer 1975 Addenda), in the following systems:

Reactor Pressure Vessel Main Steam Reactor Recirculation Stand-by Liquid Control Exemption from exsmination for line sizes 3-inches and upder is claimed'.

The following additional information is requested:

Pursuant to IWB-1220 (1), show that under the postulated conditions of loss of coolant from the component (for which exemption is claimed) during normal reactor operation, the reactor can be shut down and cooled down in an order-ly manner assuming makeup is provided by the reactor cool. ant makeup system

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only, and the. makeup system is using onsite power.

If previously discussed in submittals to NRC, document by reference.

REFERENCE:

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-s Submittal, Boston Edison Company letter #75-153, " Pilgrim duclear Power Station Unit #1 - Weld Inspection Program: to T. A. Ippolito (NRC) from G. C. Andognini (BE Co), July 24, 1979.

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