ML17309A618

Provides Addl Info to Assist NRC in Exam of RCP Flywheel Insp Interval Change.Revised ISI Program Document Section XI Rev 1 Contains Updated RCP Requirements

ML17309A618
Person / Time
Site:	Ginna
Issue date:	07/08/1997
From:	Mecredy R ROCHESTER GAS & ELECTRIC CORP.
To:	Vissing G NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17264A947	List: ML17264A946 ML17309A618
References
NUDOCS 9707170007
Download: ML17309A618 (15)

Text

I gal CATEGORY 1 REGULATORY INFORMATION DISTRIBUTION TEM (RIDE)

ACCESSION NBR:9707170007 DOC.DATE: 97/07/08 NOTARIZED:

NO FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G

At tH,NAME AUTHOR AFF I.'>IATION MECREf)Y,R.C.

Rochester Gas

& Electric Corp.

RECIV.NAME RECIPIENT AFFILIATION VISS'.NG,G.

DOCKET I

'05000244 g~ce~+

SUBJECT:

Provides addi info to assist in exam of 970318 ltr to NRC re "Reactor Coolant Pump Flywhell Insp Interval Change."

Also forwardsSection XI,rev 0

& revised Section XI,rev 1

C which contains updated RCP requirements 6

exams performed.

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(

4ND ROCHESTER GASANDELECTRIC CORPORATION ~ 89 EASTAYENUE, ROCHESTER, N. Y Idhf9-0001 AREA CODE716 54rS-2700 ROBERT C. MECREDY Vice President Nodeor Operotions U.S. Nuclear Regulatory Commission Document Control Desk Attn:

Guy Vissing Project Directorate I-1 Washington, D.C.

20555 July 8, 1997

Subject:

Reactor Coolant Pump Flywheel Inspection Interval Change Additional Information R.E.

Ginna Nuclear Power Plant Docket No. 50-244 Ref.(a):

Letter from Robert C. Mecredy, (RG&E), to Guy S. Vissing, (NRC), "Reactor Coolant Pump Flywheel Inspection Interval Change,"

dated March 18, 1997.

Dear Mr. Vissing:

The purpose of this letter is to provide additional information to assist you in the examination of the referenced transmittal.

The reactor coolant pump (RCP) flywheel inspection was not part of the previous R.E. Ginna Technical Specifications.

As such, it has not been carried into the Improved Technical Specifications.

The previous Inservice Inspection (ISI) program document related to RCP flywheel inspections isSection XI Revision 0.

The revised ISI program

.document isSection XI Revision 1

which contains the updated RCP requirements.

Copies of these two documents are enclosed.

In addition, a copy of the examinations performed during the second period of the third interval are enclosed.

Should you have any questions, please call George Wrobel at (716) 724-8070.

Very truly yours, Robert C. Mecredy Enclosures REJi470 9707f 70007 tt70708 't l,

PDR ADQCK",05000244 t

e PDaLI llllllllllllllllllllllllllllllilllllllll

xc:

Mr. Guy Vissing (Mail Stop 14B2)

Project Directorate I-1 Washington, D.C.

20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector

9707170007 ADDIT,IONAL PROGRAM SECTION 11 Revision 0 Page 1 of 9

1.0 General

The purpose of this section is to provide information and clarification on additional inspection programs being performed at R.

E.

Ginna Nuclear Power Plant.

These inspection programs may be due in part to ASME Section XI program requirements or to other commitments made by Rochester Gas and Electric.

The following list identifies additional inspection programs being performed at R.

ED Ginna Nuclear Power Plant:

Steam Generator Tube Inspection Program Reactor Coolant Pump Flywheel Program Reactor Vessel Augmented Program, Category B-A 2.0

2.1 General

2.1.1 The Steam Generator Tube Inspection Program incorporates the requirements of ASME Section XI Code, under'ategory B-Q, Item Number B16.20.

The Code requires that Steam Generator tubing in U-Tube Design be volumetrically (Eddy.Current) examined to the extent and frequency governed by the plant Technical Specifications.

In accordance with this Code requirement and R.

E.

Ginna Station Technical Specifications, eddy current examinations shall be performed.

Steam Generator Tubing shall be examined their full length, at least once every five years.

ADDITIONAL PROGRAM-SECTION t 1 Revision 0 Page 2 of 9 2 '

The Steam Generator Tube Inspection Program also incorporates the requirements of USNRC Regulatory Guide 1.83, Revision 1, dated July,

1975, "Inservice Inspection of Pressurized Water Reactor

. Steam Generator Tubes" and the recommendations of the Electric Power Research.

(EPRI)- PWR Steam Generator Inspection Guidelines, X'8t885~8gpxevkPgx'8li8xCiag 2.2 Xasyectx'cek"'pxogram~

2.2.1 The program for each Xeegeet'y'en'may'C9~8 of the five-years shall

include, as a

minimum,

.the following requirements:

2.'.

A rotating random sampling of 20%

of all operational tubes for their full length.

g'h'S'Surrngi~lllR~!'PO<'.'~O@iuh'e!e jg8ha'3'"'3'Fp+!he-'*',;.+OnRP'3;:O'te'd A rotating, random sample of. 20-. 'of each type of.

sleeved inlet tube for their full

length, including the sleeve from the upper end through the expanded transition of the lowex end.-

All operational tubes that had a

previously identified SerOPee:;::.:candu'Oei degradation of greater than 20'; through wall to the extent of previously identified degradation.

However, if after two (2) consecutive inspections these tubes have not had greater than 10-. further penetration, the inspection frequency on these tubes may be extended to 40 months.

ADDITlONAL, PROGRAM SECTlON 11 Revision 0 Page 3 of 9 2.2..2 Other tubes may be added

.to the program each i'aspic'Ct'xoQ~@CpC3le as necessary to meet other concerns and are classified as "owner elected".

"Owner Elected" examinations are not mandatory and may be performed as determined by the owner.

2.2.3 The Ginna Steam Generator Reliability Committee may change the aforementioned plan to meet outage schedules, provided that the changes meet the requirement of Regulatory Guide 1.83 and Supplement 1

it! f!': i.::,i': ll" W,:.- 'i:;::,:,,',ll: '::!1'

'i,:,

2.3 Examination Method:

2.3.1 Eddy Current (Volumetric) Examination techniques shall be employed to perform the required examinations on Steam Generator tubes.

2.4 Precpxency of Examinations:

2.4.1 Examinations shall be performed every -$!esp'e'Cp'ee'::,';:.,",;,O'JJ',.C3!8 to the extent required and specified within 2.2, as a

minimum.

2.5 Examination Evaluation:

2.5.1 Eddy Current evaluation shall be performed in accordance with('8gpdeVe'5;,'-p'Wo'ee5~8'e.

ADDITIONAL PROGRAM SECTlON

'1 't Revision 0 Page4of 9 2.6

Repair, Replacement and Testing Requirements 2.6.1

-Repair criteria for steam generato'r tubes is-based on the requirements of Regulatory Guide 1.121, "Bases for Plugging Degraded PWR Steam Generator Tubes".

2.6.1.1 Steam generator tubes that have imperfections greater than 40 percent through-wall as indicated by eddy current, shall be 'repaired by plugging or sleeving..

2.6.1.2 Steam generator sleeves that have imperfections greater than 30 percent through wall as indicated by eddy current shall be repaired by plugging.

2.6.2 Repairs by welded plugs and sleeves shall be performed in accordance with 88Cti'Op<@32:.

2.7 2.7.1

'I Scheduling:

Eddy Current examination schedules of 'Steam Generator,'ubes shall be established within Supplement 1,~/@he

%%8'8~r'Vi'C8'.":."INO'C.t'ACE ~jP~NC'gX8N>~P3,"cN 2.8 Reports and Records:

2.8.1 Applicable records shall be maintained as specified within Section 1 and Se'C'tk<ML3,,'2::.

2.8.2

.Within 15 days following the completion of the evaluation of each inservice inspection of steam generator

tubes,

,the number of tubes required by Paragraph 2.6.1 above to be plugged or sleeved in each steam generator shall be reported to the NRC in a

Special Report.

t e

ADDITIONAL PROGRAM SECTION 11 Revision 0 Page 5 of 9 The complete results of the steam generator tube inservice inspection shall be submitted to the BRC in RRNÃk$

a Special Report within 12 months following the completion of the inspection.

This Special Report shall include:

(a)

Number of tubes inspected and extent to which inspected.

(b)

Location and percent penetration for each imperfection, and of wall-thickness indication of an (c)

Identification of tubes plugged or sleeved.

If the number of tubes in a generator falling into categories (a) or (b). below exceeds the criteria, then results of the inspection shall be considered a

Reportable Event pursuant to 10 CFR 50.73.

Oral notification to the NRC Staff shall 'be accomplished'ithin 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, but no sooner than the next normal working day after the final review of the eddy current results.

A written follow up report shall provide a description of investigations conducted to determine the cause of the tube degradation and corrective measures taken to preclude recurrence.

Categories (a) and (b) are:

(a)

More than 10 percent of the total tubes inspected are degraded (imperfections greater than 20 percent of the nominal wall thickness).

However, previously degraded tubes must exhibit at least 10 percent further wall penetration to be included in this calculation.

C 0

ADDITIONAL PROGRAM SECTION 11 Revision 0 Page 6 of 9

'b)

Nore than 1 percent of the total tubes inspected are degraded (imperfections greater than the repair limit).

3.0

3.1 General

The augmented inservice inspection program for Reactor Coolant Pump Flywheels incorporates the requirements of the USNRC Regulatory Guide 1.14, Revision 1, dated August 1975, entitled "Reactor Coolant Pump Flywheel Integrity".

3.2 Examination Requirements:

3.2

~ 1 "Examinations shall be performed on all active Reactor Coolant Pump Flywheels and Anti-Rotation, Pawls.

3.3 Examination Method,:

3.3.1 Reactor Coolant Pump Flywheels shall be examined using Ultrasonic and Surface examination techniques.

3.3.2 Reactor Coolant Pump Anti-Rotation Pawls shall be examined using Surface examination techniques.

3

~ 3.3 Ultrasonic and Surface examinations shall conform to and be performed in accordance with Section 1 of this program.

'C ADDITlONAL PROGRAM SECT1ON 11 Revision 0 Page 7 of 9 3.4 Frequency of Examinations:

3.4.1 Examinations shall be performed on all operating Reactor Coolant Pump Plywheel and Anti-Rotation Pawls once each period.

1 3.5 Examination Evaluation:

3.5.1 Examination evaluations shall be performed in accordance with Section 1 of this program.

3.5.2 Unacceptable examinations shall be report'ed.

for evaluation,and appropriate corrective action.

3.6

Repair, Replacement and Testing Requirements 3.6.1 Repairs and Replacements shall be performed in accordance with ~88Ct'ieli~g!3',

as applicable.

3.7 Scheduling

3.7.1 Examination schedules shall be established within SuPPiement Z.,

.themezne'etS,i'Ce@znSPeetacn<<PX'Ogtem-:.:X',1:an.

3.8 Reports and Records:

3.8.1 Applicable records shall be maintained as specified in Section i: ade:;-:,: e Sticoin'2

ADDITlONAL PROGRAM SECTION 11 Revision 0 Page 8 of 9 General:

As specified within the Federal Register, 10 CFR Part 50, Vol. 57, No.

152 dated August 6,

1992, a specific augmented examination program is required for ASNE Section XI Category B-A, Shell Welds of "Pressure Retaining Welds in Reactor Vessel".

Examination Recpxirements:

Examinations shall be performed on all ASNE Section XI Category B-A, Item B1.0, Shell Welds of "Pressure Retaining Welds in Reactor Vessel" that are not required by the Code.

Examination Method.:

Ultrasonic examinations shall conform and be performed in accordance with Section 1 of this program.

Frequency of Examinations:

Examinations shall be peri ormed once during the Inspection Interval.

ExaminationEva1uation:

Examination Evaluations shall be performed in accordance with Section 1 of this program.

' w~

AD D1TIONAL PROGRAM SECT!ON 11 Revision 0 Page 9 of 9 Unacceptable examinations shall be reported for evaluation and appropriate corrective action.

Repair, Replacement and Testing Recpxirements (4. 6. 1 Repairs and Replacements shall be performed in accordance with Sect'a'o~ti;,;:1'2:,

as applicable.

Scheduling:

Examination schedules shall be established within Supplement 1,::,t58FX's'eptlXC8~sXgfSy'O'CdiCXf..":.":PX'agxlaN:;,;Plan@

Reports and Records:

4!. 8. 1 Applicable'ecords shall, be maintained's specified within Section 1 and 8'8~C54~On's"'42:,.