ML20248J238

Forwards Safety Evaluation Accepting Util Insp,Repairs & Mitigation of Welds Susceptible to IGSCC Performed During Spring 1988 Refueling Outage for Unit 2

ML20248J238
Person / Time
Site:	Quad Cities
Issue date:	10/03/1989
From:	Ross T Office of Nuclear Reactor Regulation
To:	Kovach T COMMONWEALTH EDISON CO.
Shared Package
ML20248J241	List: ML20248J238 ML20248J243
References
TAC-67016, NUDOCS 8910130163
Download: ML20248J238 (4)

Text

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,/ October 3,1989 p ....+

Docket No. 50-265 L

Mr. Thomas J. Kovach Nuclear Licensing Manager Commonwealth Edison Company Post Office Box 767 Chicago, Illinois 60690

SUBJECT:

. QUAD CITIES, UNIT 2 - IGSCC INSPECTION AND REPAIRS (TAC NO. 67016)

The NRC staff has com Edison Company.(CECO)pleted its review repairs regarding inspection, of documentation submitted and mitigation of welds by Commonweal susceptible to intergranular stress corrosion cracking (IGSCC) performed during the Spring 1988 refueling outage for. Unit 2. We determined that the. weld inspections, repairs, and litigations for IGSCC performed during this outage met the guidelines of Generic Letter 84-11, and that Quad Cities Unit 2 could be safely operoted for another 18-month fuel cycle. Our Safety Evaluation.

Report (SER) of the IGSCC welds . inspected and. repaired 'during the Unit 2 Spring

'1988 refueling outage is eiclosed. This SER also makes certain recommendations concerning the IGSCC inspection plan for upcoming (Unit 2) refueling outages.

Firstly, CECO should re-examine welds 02AS-56 and 02BS-F14 (28-inch recirculation system piping) during the Spring 1990 refueling outage. Secondly, Ceco should consider examining 50% of IGSCC welds treated with the Induction Heating Stress Improvement process during each of the next two refueling outages. And lastly, CECO should continue to implement an augmented leakage monitoring program for Unit 2 in accordance with NUREG-0313, Revision 2. Should Ceco decide any of

.these recommendations are inappropriate, notify us prior to the Spring 1990 refueling outage for Unit 2.

CECO responded to Generic Letter 88-01 with their future plans for piping replacment, inspection, repair and leakage detection. Our review of CECO's response is underway. When this review is completed, a separate SER will be issued, w

Thierry ass, Project Manager Project Directorate III-2 Division of Reactor Projects - III, IV, V, and Special Projects

Enclosure:

( /g As stated Gr cc w/ enclosure:

See next page 8910130163 891003 PDR ADOCK 05000265 O PDC

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[ October 3,1989 l Docket No. 50-265 Mr. Thomas J. Kovach f

Nuclear Licensing Manager Commonwealth Edison Company Post Office Box 767 Chicago, Illinois 60690

SUBJECT:

QUAD CITIES, UNIT 2 - IGSCC INSPECTION AND REPAIRS (TAC NO. 67016)

The NRC staff has completed its review of documentation submitted by Commonwealth Edison Company (CECO) regarding inspection, repairs and mitigation of welds susceptible to intergranular stress corrosion cracking (IGSCC) performed during the Spring 1988 refueling outage for Unit 2. We determined that the weld inspections, repairs, and litigations for IGSCC performed during this outage met the guidelines of Generic Letter 84-11, and that Quad Cities Unit 2 could be safely operated for another 18-month fuel cycle. Our Safety Evaluation Report (SER) of the IGSCC welds inspected and repaired during the Unit 2 Spring 1988 refueling outage is enclosed. This SER also makes certain recommendations concerning the IGSCC inspection plan for upcoming (Unit 2) refueling outages.

Firstly, Ceco should re-examine welds 02AS-56 and 02BS-F14 (28-inch recirculation system piping) during the Spring 1990 refueling outage. Secondly, CECO should consider examining 50% of IGSCC aelds treated with the Induction Heating Stress Improvement process during each of the next two refueling outages. And lastly, CECO should continue to implement an augmented leakage monitoring program for Unit 2 in accordance with NUREG-0313, Revision 2. Should CECO decide any of these recommendations are inappropriate, notify us prior to the Spring 1990 refueling outage for Unit 2.

CECO responded to Generic Letter 88-01 with their future plans for piping replacment, inspection, repair and leakage detection. Our review of CECO's response is underway. When this review is completed, a separate SER will be j issued. j j

Thierry M. Ross, Project Manager Project Directorate III-2 Division of Reactor Projects - III, IV, V, and Special Projects

Enclosure:

As stated l

cc w/ enclosure:

See next page DISTRIBUTION:

Docket file NRC & Local PDRs PDIII-2 r/f MVirgilio LLuther TRoss 0GC EJordan BGrimes ACRS(10) Plant file

• See previous concurrence f*f.

• PDIII-2 *PDIII-2 PDIII-2 TRoss:km LLuther PShemanski 10/02/89 10/02/89 10/3 /89 1

_ _ - - _ _ _ - _ I

Docket No. 50-265 Mr. Thomas J. Kovach ,-

Nuclear Licensing Manager ,/

Commonwealth Edison Company s Post Office Box 767 /

Chicago, Illinois 60690 /

Dear Mr. Kovach:

/

j i

SUBJECT:

QUAD CITIES, UNIT 2 - IGSCC INSPECTION AND REPAIRS (TAC NO. 67016)

TheNRCstaffhascompleteditsreviewofdocbmentationsubmittedbyCommonwealth Edison Company (CECO) regarding inspection ( repairs and mitigation of welds susceptible to intergranular stress corrosion cracking (IGSCC) performed during the Spring 1988 refueling outage for Unit 2. We determined that the weld inspections, repairs, and litigations,for IGSCC performed during this outage met the ' guidelines of Generic Letterj 84-11, and that Quad Cities Unit 2 could be safely operated for another 18-month fuel cycle. Our Safety Evaluation Report (SER) of the IGSCC welds inspected and repaired during the Unit 2 Spring 1988 refueling outage is enclosed. This SER also makes certain recommendations concerning the IGSCC inspection plan for upcoming (Unit 2) refueling outages.

Firstly, CECO should re-examine welds 02AS-56 and 02BS-F14 (28-inch recirculation system piping) during the Spring 1989 refueling outage. Secondly, CECO should consider examining 50% of IGSCC welds treated with the Induction Heating Stress Improvement process during'each of the next two refueling outages. And lastly, CECc should continue to implement an augmented leakage monitoring program for Unit 2 in accordance with NUREG-0313, Revision 2. Should CECO decide any of these recommendations.are inappropriate, notify us prior to the Spring 1990 refueling outage for, Unit 2.

I CEcorespondedtoGbnericLetter88-01withtheirfutureplansforpiping replacment, inspec' tion, repair and leakage detection. Our review of CECO's response is underway. When this review is completed, a separate SER will be issued. j j

/ 1

/ Thierry M. Ross, Project Manager 1

i 7 Project Directorate III-2 j

Division of Reactor Projects - III, IV, V, and Special Projects Enclos re:

As stdted l- cc w/ enclosure:

Seehextpage DISTRIBUTION:

l Docket tile NRC 8 Local PDRs PDIII-2 r/f MVirgilio j LLuther TRoss OGC EJordan l BGrimes ACRS(10) Plant file PDIII-2 -7 PDIII-2 PDIII-2 TRoss:km[ LLuthe PShemanski 10/ 2 /89 10/,2 /89 10/ /89

j.

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Mr. Thomas' J.. Kovach Quad Cities Nuclear Power Station Commonwealth Edison Company Units.I and 2 cc:

Mr. Stephen E. Shelton

.Vice President.

Iowa-Illinois Gas'and Electric Company-P. 0.. Box 4350 Davenport, Iowa 52808 Michael I. Miller, Esq.

Sidley and Austin One First-National Plaza Chicago, Illinois 60603 Mr. Richard Bax Station Manager Quad Cities Nuclear Power Station:

22710 206th Avenue North Cordova, Illinois 61242 Resident, Inspector U.' S. Nuclear Regulatory Commission 22712 .206th Avenue North

'Cordova, Illinois 61242 Chairman-Rock Island County Board of. Supervisors-1504 3rd Avenue Rock Island County Office Bldg.

Rock Island, Illinois 61201 Illinois Department of Nuclear Safety Office of Nuclear facility Safety 1035 Outer Park Drive Springfield, Illinois 62704 Regional Administrator, Region III U. S. ' Nuclear Regulatory Comission 799 Roosevelt Road, Bldg. #4 Glen Ellyn, Illinois 60137 I

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