ML17265A395
| ML17265A395 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 08/06/1998 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Vissing G NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9808120301 | |
| Download: ML17265A395 (6) | |
Text
CATEGORY 1 REGULA'1 Y INFORMATION DISTRIBUTIO SYSTEM (RIDS)
A'CCESSION NBR:9808120301 DOC.DATE: 98/08/06 NOTARIZED: NO DOCKET ¹ FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
05000244 AUTH.'NAME AUTHOR AFFILIATION MECREDY,R.C.
Rochester Gas S Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION VISSING, G. S.
SUBJECT:
Recpxests approval for use of relief recpxest 35 re use of AMSE Section ZI Code,1995 Edition,1996 Addenda,to develop licensee fourth 10-yr interval ISI program on class 1,2
& 3 components.
DISTRIBUTION CODE:
A007D COPIES RECEIVED: LTR i ENCL I
SIZE:
Q TITLE: OR Submittal: Inservice/Testing/Relief from ASME Code - GL-89-04 A
T NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72) 05000244 E G
RECIPIENT ID CODE/NAME PD1-1 LA VISSING,G.
INTERNAL: AEOD/SPD/RAB NRR/DE/ECGB OGC/HDS3 RES/DET/EMMEB COPIES LTTR ENCL 1
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1 RECIPIENT ID CODE/NAME PD1-1 PD E CENTER 01 NUDOCS -ABST CT RES/DET/EIB COPIES LTTR ENCL 1
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1 EXTERNAL: LITCO ANDERSON NRC PDR 1
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N NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD)
ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED:
LTTR 13 ENCL 12
ROCHESTER GAS ANDELECTRIC CORPORATION 89 EASTAVENIIE, ROCHESTER, N.V. 14649-0001 AREA CODE 716-546-2700 ROBERT C. MECREDY Vice President Nvcteor Operotions August 6, 1998 U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Guy S. Vissing Project Directorate I-1 Washington, D.C.
20555
Subject:
Inservice Inspection Program ASME Section XI Required Examinations Fourth 10-Year Interval Request for Relief Regarding Request No.
35 R.E. Ginna Nuclear Power Plant Docket No. 50/244
Dear Mr. Vissing:
The purpose of this letter is to seek approval for the use of Relief Request number 35 concerning the use of ASME Section XI
- Code, 1995
- Edition, 1996
- Addenda, which has not been endorsed within 10 CFR 50.55a.
This code will be used to develop our Fourth 10-Year Interval ISI Program on Class 1,
2 and 3 components, with
'he exception of Containment requirements of IWE and IWL.
This Relief is requested pursuant to the provisions of 10 CFR 50.55a(a)(3)(i),
the use of a
later ASME Section XI Code.
Justification is included in the attachment to this letter. It is requested that this relief request be expedited and NRC reply obtained before September 1998 in order for it to be utilized at R.E. Ginna Nuclear Power Plant for preparation of the submittal of our Fourth Interval Program.
As required by 10 CFR 50.55a, our Fourth Interval Program needs to be submitted to the NRC six (6)months prior to the end of our Third Interval, which ends December 31, 1999.
Very ly yours, JSM/mab:504 Attachment
'Robert C. Mecre y
.'.,(. U v v 3 ttt80812030i
'tt8080b PDR ADQCK 05000244 8
xc:
Mr. Guy S. Vissing (Mail Stop 14B2)
Project Directorate.I-1 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 U.S.
NRC Ginna Senior Resident Inspector
ATTACHMENT Rochester Gas and Electric Corporation Ginna Station Docket No. 50/244 Fourth 10-Year Interval Request for Relief No.= 35 ASME Code Section XI Alternative for the Fourth Interval ISI Program System/Component(s) for Which Relief is Requested:
This Relief Request is requested for Inservice Inspection of all ASME Class 1, Class 2 and Class 3 components in accordance with the rules provided in ASME Section XI Code, Division 1.
II.
Code Requirement:
10 CFR 50.55a specifies the ASME Section XI
- Code, 1989 Edition, that has been endorsed for owners to utilize in the preparation and use for their ASME Section XI Inservice Inspection Program as well as their Repair and Replacement Program.
Later ASME Section XI Codes may be utilized only if approved by the NRC.
III. Code Requirement from Which Relief is Requested:
R.E.
Ginna Nuclear Power Plant is requesting relief from utilizing the ASME Section XI Code, 1989
- Edition, and is requesting permission for the use of ASME Section XI Code, 1995 Edition with the 1996 Addenda for Class 1,
2, and 3
components for our Fourth Interval ISI Program instead of the 1989 Edition Code Edition as identified within the current 10 CFR 50.55a.
This Relief Request does not address Containment (IWE/IWL and applicable IWA) requirements.
The Containment requirements shall be performed to ASME Section XI Code, 1992 Edition with the 1992 Addenda.
This year and edition of ASME Section XI Code is the basis for the EPRI/Industry Guideline which will be used to develop and implement our Containment Inspection Program.
Request for Relief No.
35 Page 1 of 3
~ t IV.
Basis for Relief:
Relief is requested pursuant to the provisions of 10 CFR 50.55a(a)(3)(i),
request for approval to use a later ASME Section XI Code.
The proposed alternative will provide an acceptable level of quality and safety.
On December 3,
1997, the NRC issued a proposed change in the Federal Register to amend 10 CFR 50.55a for Inservice Inspection.
The proposed rulemaking endorsed the use of ASME Section XI Code, 1995 Edition with the 1996 Addenda for the Inservice Inspection as well as for Repair or Replacement of Class 1, 2, and 3 components.
The use of this later code is clearer and provides much needed clarification to those requirements specified within the current approved Code (1989 Section XI Code).
By utilizing the later Section XI Code for Inservice Inspection as well as Repair and Replacement of Class 1, 2, and 3 components, would minimize the number of needed relief requests that the NRC would be required to process.
It is requested that ASME Section XI Code, 1995 Edition with the 1996 Addenda be utilized to develop R.
E. Ginna Nuclear Power Plant Fourth Interval Program.
V.
Alternate Examinations:
R.E.
Ginna Nuclear Power Plant requests that our Fourth Interval Inservice Inspection (ISI) Program as well as our Repair and Replacement Program shall conform to ASME Section XI Code, 1995 Edition with the 1996 Addenda for Class 1,
2 and 3 Components including supports.
The Fourth Interval Section XI Inservice Testing (IST) Program for R.E.
Ginna Nuclear Power Plant shall conform to 10 CFR 50.55(a) which implements ASME 'Section XI Code, 1989 Edition.
VI.
Justification for the Granting of Relief:
On December 3,
1997, the NRC issued a proposed change in the Federal Register to amend 10 CFR 50.55a for Inservice Inspection.
The proposed rulemaking endorsed the use of ASME Section XI Code, 1995 Edition with the 1996 Addenda for the Inservice Inspection as well as for Repair or Replacement of Class 1, 2, and 3 components.
1 Request for Relief No.
35 Page 2 of 3
The use of the 1995 code is clearer and provides much needed clarification to those requirements specified within the current approved Code (1989 Section XI Code).
NRC approval to utilize the later Section XI Code for Inservice Inspection, as well as Repair and Replacement of Class 1,
2, and 3
components, would minimize the number of needed relief requests that the NRC would be required to process.
VII. Implementation Schedule:
Examinations will be performed during the Fourth 10-year Interval.
Request for Relief No.
35 Page 3 of 3