ML17320A960

Requests Relief from Provisions of ASME Section XI - 1974, Table IWB-2500 Exam Categories B-L-1 & B-L-2 for Reactor Coolant Pump

ML17320A960
Person / Time
Site:	Cook
Issue date:	03/08/1984
From:	Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	Harold Denton Office of Nuclear Reactor Regulation
References
AEP:NRC:007OM, AEP:NRC:7OM, NUDOCS 8403160034
Download: ML17320A960 (8)

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REGULATO INFORMATION DISTRIBUTION TEM (RIDS)

ACCESSION NBR:8403160034 DOC ~ DATE: 84/03/08 NOTARIZED'O DOCKET FACIL;50 3i5 Donald C,

Cook Nuclear Power PlantE Un)t li Indiana 8

05000315 50 3i6 Donald CD Cook-Nuclear power Plantr Unit 2P Indiana 8

05000316 AUTH~ NAME" AUTHOR AFF II.IATION ALEXICHrM,P, Indiana 8 Michigan-Electric Co, RECIP ~ NAME>>

RECIPIENT AFFILIATION DENTON<H.R>

Office, of Nuclear Reactor Regulationi Director

SUBJECT:

Requests relief from provisions of ASME Section XI -

1974'able INB 2500 exam Categories B

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8 B

I-2 for reactor coolant

pump, DISTRIBUTION 'CODE:

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INDIANA8 MICHIGAN ELECTRIC COMPANY P.O. BOX 16631 COLUMBUS, OHIO 43216 March 8, 1984 LEP'NRC: 0070M Donald C.

Cook Nuclear Plant Unit Nos.

1 and 2

Docket; Nos. 50-315 and 50-316 License Nos.

DPR-58 and DPR-74 Inservice Inspection Program - Code Relief Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.

20555

Dear Mr. Denton:

This submittal is made pursuant to Title 10 of the code of Federal Regulations, Part 50.55a (g) (6) (1), and requests code relief from the provisions of ASME Section XI - 1974, Table IWB<<2500 examination cat~cries B<<L-1 and B-L-2 for the reactor coolant pump.

Section XI, category B-L-1, covers volumetric examination of 100$ of the pr essure-retaining welds and category B-L-2 oovers visual examination of the internal pressure boundary surfaces.

These examinations are r equ1red for at least one of a group of pumps performing similar functions in the system.

Section XI indicates that these examinations may be performed at or near t;he end of the inspection interval.

Indiana

& Michigan Electric Company requests relief from the above categories of exam1nations for the Donald C.

Cock Nuolear Plant.

The basis for requesting code relief is that the substant1al radiation exposure that the inspect1on personnel will incur and the substantial costs involved do not justify the possible informat1on that might be gained about the weld and adjacent base metal.

The pump casing is made from ASME SA-351, Grade CF-8M, a cast austenit1e stainless steel that has a long hist;ory of satisfactory serv1ce in handling fluids.

The casing was made in t;wo sect1ons to facilitate the casting process and the two sections are welded together with a matching filler mater1al.

fielding ease CF-8M mater1al to repair imperfections is a routine practice for almost all CF-8M castings, except those of simple configurat1on and small size.

The mater1al has good fracture toughness, and unlike ferr itic steels, is not subject to fraetur e prevention criteria.

Volumetr1c examination will require a substantial number of radiographic exposures that will require complete disassembly of the pump (Figure 1).

Disassembly of the pump, storage of the internals, and placement of f11m will expose personnel to substantial radiation.

From exper fence at other nuclear plants examining reactor coolant pumps, personnel exposure could be in the range of between 35 to 100 man-rem.

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Mr. Harold R.

De AEP: NRC: 0070M Based on cost incurred by other nuclear plants, this pump examination cost is estimated to be about

$500,000, which does not include costs associated with unit unavailability should th1s examination require extending an outage.

The examination will require d1sassembly of a pump under adverse conditions where there is=a possibility of causing damage to the pump internals.

-There is no other=reason to disassemble any of these pumps other than to perform these examinations.

This examination will also require handling"the reactor vessel upper internal assembly an addtional

time, as the -upper internals will have to be put back into the reactor vessel to minimize airborne radiation while the pump examination is per formed.

- Radiographic examination of similar welded reactor coolant pumps has been performed at a number of plants.

The radiography has been acceptable and the volumetric examinat1on has not shown any deterioration in the welds.

Me understand that code relief has been granted by the NRC from volumetric examinat1on for other reactor coolant pumps, and that this examination and its frequency is being studied by EPRI and the ASME BKPV Code gr oups.

As an alternate to the B-L-1 and B-L-2 examination, a visual examination will be performed on the external, surfaces 'of one pump dur1ng the hydrostatic pressure,.tests.

In,,addition',

a surface exam'ination will be performed on this pump on the accessible, external surface of the weld.

J If a pump has to be disassembled for ma1ntenance, a visual examination w111 be made of the internal surfaces to satisfy the'iB-L-2 code requirement and the volumetric exam1nation to the B-L-1 requir'ement reevaluated at that time.

Based on the foregoing,,we believe, that the radiation exposure and costs for this examination do not )ustify pe'rforming the volumetric exam1nation to meet the requirements of categories B-L-1 and B-1-2 and, therefore, we are requesting a code relief for the Coolant Pump weld

~ inspection.

This document has been prepared following Corporate procedures which incorporate a reasonable set of controls to insure its accuracy and completeness pr ior to signature by the undersigned.

Very truly yours, M. P.

A ex1ch Vice President MPA/cam cc:

John E. Dolan M. G. Smith, Jr. - Bridgman R.

C. Callen G. Charnoff E.

R. Swanson, NRC Resident Inspector - Br idgman

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AEP:NRC:0070M Center Line of Discharge Weld Figu e l Reactor coolant pump casing cross-section showing location of weld.

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