ML20050A351

Forwards Addl Info Re Preservice Insp.Info Clarifies Seven Questions Posed by M Humm During 820309 Meeting

ML20050A351
Person / Time
Site:	Perry
Issue date:	03/25/1982
From:	Davidson D CLEVELAND ELECTRIC ILLUMINATING CO.
To:	Schwencer A Office of Nuclear Reactor Regulation
References
NUDOCS 8204010171
Download: ML20050A351 (8)

Text

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TH E CLEV EL A N D E L E CTitl0 IL L UldiN ATIN G CO M P AN Y P o. Box 5000 m CLEVELAND, ohio 44101 e TELEPHONE (216) 622-9800 e ILLUMINATING BLOG. e 55 PUBLIC SoVARE Daiwyn R. Davidson arving The Best Location in the Nation VICE PRESIDENT SYSTEM ENGINEERING AND CONSTRUCTION gg s

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March 25, 1982 , ,

.g i m MR31;gggw Mr. A. Schwencer ED iCM9etg{prI)s Chief, Licensing Branch No. 2 Division of Licensing }b/e o

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U. S. Nuclear Regulatory Commission f.

Washington, D. C. 20555 t 8d Perry Nuclear Power Plant Docket Nos. 50-M0; 50-W1 Preservice Inspection

Dear Mr. Schwencer:

As a result of a meeting held with members of the Materials Engineering Branch on March 9, 1982, Mr. Martin Humt requested clarification on seven questions. The purpose of this letter is to provide additional information concerning these seven questions. Additionally, the procedures used for UT examination arc being provided to Mr. Humm.

Very Truly Yours, b

Dalwyn R. Davidson Vice President System Engineering and Construction DRD: mlb cc: Martin Humm John Stefano Jay Silberg, Esq.

Max Gildner A y p. ?'{f Ss t i

8204010171 820305 PDR ADOCK 05000440 C PDR

4 Item 1 Describe CEI's philosophy for determining which welds are to be examined (i.e., sampling philosophy) for both ASME Code Class I and II welds. Identify any IWB 1220/IWC1220 exclusions.

Response

For Class 1, all welds not exempt will be scheduled for examination.

For Class 2, the welds will be scheduled based on +he selection criteria of the 1974 Section XI including the Summer 1975 addenda paragraph IWC-2411 and Table IWC-2520 Category C-F and C-G. Where a system is a Category C-G (50% of the welds selected) or has multiple streams, the welds selected will be representative of the different sizes and geometries. Etception to this may be made where an access problem exists. Where possible, these '.relds would not be scheduled out the proper percentage of welds examined would be maintained.

The exemptions that will be considered in the preparation of the PSI Program Plan are as follows:

a) Class 1 -

-IWB-1220(a) S'78 addenda - Make up criteria. The criteria are 2 36 ID for water and 3.0 ID for steam.

-IWB-1220(b) S'78 addenda - 1" pipe and smaller

-IWB-1220(c) S'78 addenda - 2" and smaller on vessel head made inaccessible by CRD penetrations.

b) Class 2

-IWC-1220(a) S'75 addenda - less than 75 psig and 200 F design pr.rameters .

IWC-1220(c) S'78 addenda - 4" pipe and smaller i

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Item 2 Provide justifications for the exclusion identified in the General Reference Text on pg. Ih, paragraph 3.3.1 (steam service Line 4.72" ID).

Response

CEI has reviewed this exclusion.' As a result of our review, an exclusion of 3 00" ID will be requested instead of the 4.72" ID. Justification of this exclusion will be based on available normal make up flow as required by IWB 1220.

Item 3 Discuss CEI's plans for examination of this wall pipe.

Response

CEI plans to review the systems which contain thin wall large bore piping (Wall thickness less than .5 in). The purpose of this review will be to determine if augmented examination of certain piping would be desirable.

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- Item 4 Describe the RW examination program including the

,- i percentage of welds which will be examined. Address Reg. Guide 1.150 in'your responae.  ;

Response

The reactor pressure vessel examinations will be performed using a .;

combination of automated and manual ultrasonic techniques. ' Manual-examina.tions will be performed on the accessible portions 'of the bottom ,

head area up to and including the bottom head to shell weld. The closure head as well as RW shel.1 and nozzle welds above the biological shield will also be performed manually.

r Automated examinations will be performed on the balance of RW longitudinal and circumferential welds within the shield wall. This will t be accomplished utilizing a fixed track system mounted inside the cavity

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insulation. A moveable arm assembly carrying the required transducer assemblies is mounted on the fixed tracks to accomplish the required examinations. It is estimated that approximately 5% of the circum-ferential welds and 5% of the longitudinal welds in this area will not be ftilly examined utilizing this system.

Nozzle to shell weldy and inner radius areas on the RW will also be l'

-examined usitg both manual and automated methods. The areas examined with automated hchniques will depend on radiation and access factors.

The device used is a removeable saddle device requiring no permanent ,

- tracks. -Cavity design provides reasonable access for manual examination.  !

of the remaining nozzles.

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The provisions of RegtJ.atory Guide 1.150 will be addressed and reflected ~  !

in developing the ultrt.nonic examination procedures for the reactor pressure vessel.. ,

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Item 5 Discuss the techniques CEI plans to use for bolting examinations.

Response

The procedures used for ultrasonic examination of bolting will address the need to detect service induced defects.

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Item 6 Discuss CEI's intent to comply with ASME Section .

] XI, Subsection IWF.

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Response

i t Component Support Exams will be scheduled in accordance with the 1977 .

Section XI with addenda through 1978, Categories B-H, B-K-1, B-K-2, C-C, ,

C-E, D-A, D-B, and D-C as appropriate. . Subsection IWF was first included in the Winter 1978 addenda of the Code and is not specifically addressed in the 1977 Edition of Section XI through Suramer 1978 addenda.

Subsection TJF will be addressed in the IST Program prepared under a separate contract. '

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Item 7 Provide a schedule for completion of examinations.

Response

Completion of Unit 1 piping examinations is currently scheduled for December 31, 1982.

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