ML20248B879

Forwards Safety Evaluation Concluding That Insps,Repairs & Mitigations Performed During Reload 9/Cycle 10 Outage Met Guidelines of Generic Ltr 84-11.Util Should Incorporate Weld Repairs & Exams in Unit Igssc Insp Plan

ML20248B879
Person / Time
Site:	Quad Cities
Issue date:	06/06/1989
From:	Ross T Office of Nuclear Reactor Regulation
To:	Kovach T COMMONWEALTH EDISON CO.
Shared Package
ML20248B883	List: ML20248B879 ML20248B891
References
GL-84-11, TAC-66529, NUDOCS 8906090193
Download: ML20248B879 (4)

Text

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% UNITED STATES Q 3 .g NUCLEAR REGULATORY COMMISSION 7n ( WASHINGTON, D. C. 20555

[I k *s w [j June 6,1989 l Docket No. 50-254 Mr. Thomas J. Kovach Nuclear Licensing Manager Consnonwealth Edison Company Post Office Box 767 Chicago, IL 60690

SUBJECT:

SAFETY EVALUATION OF THE QUAD CITIES, UNIT 1, IGSCC INSPECTION

' PLAN AND REPAIRS (TAC NO. 66529)

RE: (a) Letter from I. Johnson (CECO) to T. Murley (NRC) dated, December 10, 1987 (b) Letter from I. Johnson (Ceco) to T. Murley (NRC) dated, December 17, 1987

.' (c) Letter from T. Ross (NRC) t L. Butterfield (CECO) dated, December 18, 1987 (a) Letter from T. Ross (NRC) to L. Butterfield (Ceco) dated, April 13, 1988 *

(e) Letter from I. Johnson (CECO) to T. Mur1ey (NRC). dated, May 31, 1988 (f) Letter from W. Morgan (CECO) to T. Murley (NRC) dated, July 29,1988 ,

In reference (a), Commonwealth Edison Company (CECO) submitted their final report detailing the results of the Quad Cities (Unit 1) augmented inspection p(rogram IGSCC) pursuantfor piping to welds susceptible General Letter (GL) to Intergranular 84-11. This reportStress Corrosion provided Cracking descriptions of flaws, along with analyses and repair actions conducted during the Reload 9/

Cycle 10 Refueling Outage for Quad Cities, Unit 1. In addition to their final report, CECO committed (reference (b)) to upgrade two particular weld repairs and reevaluate another weld during the next refueling outage, and institute an ,

augmented leakage monitoring program in accordance with GL 84-11 during Cycle 10.  !

Based determined upon in areference preliminary (review of the aforementioned documentation, wec), that the should not preclude restart. However, in reference (d), we requested additional information from Ceco inorder to satisfactorily complete our safety evaluation l Ceco responded to this oftheIGSCCinspectionp)lanresultsandrepairs.

request with reference (e .

Enclosed is the final. NRC Safety Evaluation for the IGSCC inspection program conducted at Quad Cities, Unit 1, during the Reload 9/ Cycle 10 Refueling Outage. We have concluded that the inspections, repairs, and litigations performed during this outage met the guidelines of GL 84-11 and Quad Cities Unit I can continue to operate safely 1or at least an 18-month fuel cycle (Cycle 10) in its present configuration.

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1 CECO's plans for inspection and/or modification of the recirculation system piping, and any other piping systems susceptible to IGSCC, during the next refueling outage must now follow the guidelines in Generic Letter 88-01.

Ceco did already respond to Generic Letter 88-01 in reference (f) regarding their IGSCC program for future outages related to piping replacement, ,

inspection, repair and leakage detection. However, we have not completed our evaluation of this response because additional information is needed. When our

. review is completed, a separate safety evaluation will be forthcoming.

With regard to the specific IGSCC inspection plan of the upcoming Unit I refueling outage (scheduled to begin September 1989), CECO should incorporate the additional weld repairs and examinations recommended in our SER or provide detailed justification for not doing so. These recommendations include previous Ceco connitments identified by reference (b).

Should you have any particular ' questions concerning our conclusions and' ,

recommendations contained in the enclosed SER, please do not hesitate to contact me.

Thierry 4 Ross, Project Manager Project Directorate III-2 Division of Reactor Projects III, IV, V, and Special Projects

Enclosure:

. As stated cc w/ enclosure:

See next page

_ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ i

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Mr. Thomas J. KovachL Quad Cities Nuclear Power Station

. Connonwealth Edison Company Units 1 and 2 cc:

.Mr. Stephen E. Shelton Vice President Iowa-Illinois Gas and

' Electric Company

'P. O. Box 4350 Davenport, Iowa 52608 Michael I. Miller, Esq.

Sidley and Austin

_One First National Plaza Chicago, Illinois 60603 Mr. Richard Bax-Station Manager Quad Cities huclear Power Station 22710 '206th Avenue North Cordova, Illinois 61242 Resident Inspector U. S. Nuclear Regulatory Connission 22712 206th Avenue North Cordova, Illinois 61242-Chhtraan Rock Island County Board

.of Supervisors 1504 3rd Avenue Rock Island County Office Bldg.

Rock Island, Illinois 61201 Mr. Michael E. Parker, Chief Division of Engineering Illinois Department of Nuclear Safety 1035 Outer Park Drive, Springfield, Illinois 62704 Regional. Administrator, Region III U. S. Nuclear Regulatory Commission 799 Roosevelt Road, Bldg. f4 Glen Ellyn, Illinois 60137

June 6,1989 -

Ceco's plans for inspection and/or modification of the recirculation system l piping, and any other piping systems susceptible to IGSCC, during the next

! refueling outage must now follow the guidelines in Generic Letter 88-01.

CECO did already respond to Generic Letter 88-01 in reference (f) regarding their IGSCC program for future outages related to piping replacement, l inspection, repair and . leakage detection. However, we have not completed our l evaluation of this response because additional information is needed. When our review is completed, a separate safety evaluation will be forthcoming.

l With regard to the specific IGSCC inspection plan of the upcohiing Unit I refueling outage (scheduled to begin September 1989), CECO should incorporate the additional weld repairs and examinations recommended in our SER or provide detailed justification for not doing so. These recommendations include previous Ceco commitments identified by reference (b).

Should you have any particular questions concerning our conclusions and recommendations contained in the enclosed SER, please do not hesitate to contact me.

1 i

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

Enclosure:

As stated i cc w/ enclosure:

See next page l

l DISTRIBUTION:

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