IR 05000237/1991021
| ML17174A778 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Byron, Braidwood, Quad Cities, Zion, LaSalle  |
| Issue date: | 07/02/1991 |
| From: | Schumacher M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML17174A777 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737 50-237-91-21-MM, 50-249-91-21, 50-254-91-16, 50-265-91-12, 50-295-91-16, 50-304-91-16, 50-373-91-14, 50-374-91-14, 50-454-91-17, 50-455-91-17, 50-456-91-18, 50-457-91-16, NUDOCS 9107110066 | |
| Download: ML17174A778 (4) | |
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U.S. NUCLEAR REGULATORY COMMISSION REGION I II Reports No. 50-456/91018(DRSS); 50-457/91016(DRSS)
50-454/91017(DRSS); 50-455/91017(DRSS)
50~237/91021(DRSS); 50-249/91021(DRSS)
50-373/91014(DRSS); 50-374/91014(DRSS)
50-254/91016(DRSS); 50-264/91012(DRSS)
50-295/91016(DRSS); 50-304/91016(DRSS)
Docket Nos: 50-456; 50-457 50-454; 50-455 50-237; 50-249 50-373; 50-374 50-254; 50-265 50-295; 50-304 Licensee:
Commonwealth Edison Company Opus West II I 1400 Opus Place Downers Grove, IL 60515 Licenses No. NPF-72; NPF-77 NPF-37; NPF-66 DPR-19; DPR-25 NPF-11; NPF-18 DPR-29; DPR-30 DPR-39; DPR-48
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Facility Name: *Braidwood Nuclear Power Station, Units 1 and 2 Byron Nuclear Power Station, Units 1 and 2 Dresden Nuclear Power Station, Units 2 and 3 LaSalle County Station, Units 1 and 2 Quad Cities Nuclear Power Station, Units 1 and 2 Zion Nuclear Power Station, Units 1 and 2 -
Meeting At:
Dresden Site, Morris, Illinois Meeting Conducted:
June 13, 1991 Approved By:
Meeting Summary Meeting on June 13, 1991 (Reports No. 50-456/91018(DRSS); 50-457/91016(DRSS),
50-454/91017(DRSS); 50-455/91017(DRSS), 50-237/9102l(DRSS);
50-249/91021(DRSS), 50-373/91014(DRSS); 50-374/91014(DRSS),
50-254/91016(DRSS); 50-265/91012(DRSS), 50-295/91016(DRSS);
50-304/91016(DRSS))
Ar~as Discussed:
A special management meeting was conducted at the request of the licensee to discuss the results of a self-assessment of the post-accident sampling system (PASS) at the six nuclear ~lants in comparison to NUREG-0737 requirements and NRC commitment PDR ADOCK 05000237 G
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Results:
Of 207 specific items reviewed by the licensee, 204 satisfied the requirements of NUREG-073 Three items of relatively minimal safety significance did not ~nd ~ction plans have been developed to correct the An additional 17 items were identified where current practices or methods were not consistent with original NRC'commitments. *Revisions have been or will be made to.. the stations* Updated Final Safety Analysis Reports
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(UFSARs) to indicate the changes from the commitment The self-assessment represented a good effort by.the license * Meeting Attendees Commonwealth Edison Company DETAILS D. Farrar, General.Manager, Nuclear Services D. Miller, Chemistry Services K. Miedlar, Chemistry Services J. Burns, Chemistry Services J. Bates, Nuclear Licensing Nuclear Regulatory Commission C..E. Norelius, Director, Division of Radiation Safety and Safeguards L. R. Greger, Chief, Reactor Programs Branch M. C. Schumacher, Chief, Radiological Controls and Chemistry Section A. G. Januska, Senior Radiation Specialist M. A. Kunowski, Senior Radiation Specialist N. Shah, Radiation Specialist Meeting Summary The licensee presented resuits of a self-assessment it undertook in response to internal concerns and several recent NRC inspections at Braidwood (Inspection Reports No. 50-456/90009(DRSS); 50-457/90009(DRSS)
and 50-456/90005(DRSS); 50-457/90005(DRSS)) regarding the post-accident sampling system (PASS) at the six station The assessment included discussions with key personnel that run or maintain PASS, and a review of selected surveillance procedures, diagrams, training records, system descriptions, UFSAR sections, and NRC inspection report The goals of the self-assessment were to determine if all NUREG-0737 PASS requirements and commitments were met at the six stations and to correct any identified problem Of 207 items that were reviewed, only three items were identified that did not satisfy the requirements. These are the improper location of a post-accident reactor coolant dissolved oxygen monitor at LaSalle and Zion, and the lack of a demonstration of accuracy of the in-line ion chromatograph for post-accident boron analysis at Dresde For LaSalle, the licensee estimated that the modification to correct the problem will be completed around October 199 For Zion, a similar modification is scheduled to be completed around August 199 And for Dresden, the demonstration of the accuracy of the boron analysis should be completed by July 1991. These items will be reviewed during future inspections (Open Items No. 373/91014-0l(DRSS), 295/91016-0l(DRSS),
237/91021-0l(DRSS)).
Until these corrective actions are completed, the licensee has contracted with an off-site vendor to provide compensatory dissolved oxygen and boron analysis capability.
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In addition to the three requirements that were not met, 17 discrepancies were identified between current practices or methods and commitments made i*n the !llany correspondence between the 1 i censee and the NR The licensee has determined that none of the discrepancies involved an unreviewed safety question and will update -or has updated the UFSAR to reflect the change from previous commitment These updates are subject to review during future NRC inspection At the conclusion of the presentation, the licensee stated that approximately 0.5 person-year of effort went into the assessment and that another assessment is planned for effluent monitor The NRC representatives acknowledged the licensee's statements and requested to be informed of the results of the effluent monitor assessmen The licensee did not identify any material presented at the meeting as proprietary.
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