ML20012G486
| ML20012G486 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 12/18/1992 |
| From: | Shafer W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20012G485 | List: |
| References | |
| 50-282-92-22, 50-306-92-22, NUDOCS 9303030210 | |
| Download: ML20012G486 (2) | |
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NOTICE OF VIOLATION Northern States Power Company Docket Nos. 50-282, 50-306 Prairie Island Nuclear Generating Plant License Nos. DPR-42, DPR-60 During an NRC inspection conducted on October 19 through Novenber 20, 1992, a viclation of HRC requirements was identified.
In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C, the violation is listed below:
10 CFR 50, Appendix A, Criterion II, states, in part, that structures, systems anc components important to safety shall be designed to withstand the effects of natural phenomena such as earthquakes, tornadoes..., without loss of capability to perform their safety function.
10 CFR 50, Appendix B, Criterion III states, in part, that measures shall be established to assure that the design basis is correctly translated into specifications, drawings, procedures and instructions.
D5.06 Building and Building Support Systems Design Criteria, Eevision 2, dated February 28, 1991, paragraph 7.2.2.1.6, states "the 05/D6 Building and its foundation are physically separated from existing plant structures."
Fluor Daniel Final Report on 05/06 Building G-Row" Wall Construction Problems, dated October 23, 1991, Section 2.0, states, "A 1/2 inch cocpressible board was used between the turbine flood wall (up to elevation 705') and the "G" row wall of the 05/06 building to maintain the design separation between the two walls."
The Station Blackout / Electrical Safeguards Upgrade Project Design Report dated i
NoveT,ber 27, 1990, Section 4.3.2.2.1.f, states that the building and its foundation are physically separated from the existing plant and the gap filled with compressible material between the D5/D6 building and adjacent structures.
l Contrary to the above, the licensee failed to adequately translate design recuirements into applicable drawings. This resulted in the compressible r,
board not being installed between the walls and the subsequent degradation -of the seismic independence of the safety related 05/D6 generator building.
This is a Severity Level IV Violation (Supplement I.D.3).
t Pursuant to the provisions of 10 CFR 2.201, Northern States Pcwer Company is hereby required to submit a written statement or explanation to the U.S.
Nuclear Regulatory Commission, ATTN: Document Control Desk, MSHINGTON DC 20555 with a copy to the U.S. Nuclear Regulatory Commission, Eegien III, 799 Roosevelt Road, GLEN ELLYN IL 60137, and a copy to the NEC Resident Intpector at the Prairie Island Nuclear Generating Plant, within 30 days of the date of the letter transmitting this Notice of Violation (Notice). This reply should be clearly marked as a " Reply to a Notice of Violation" and should include:
(1) the reason for the violation, or, if contested, the basis for disputing the violation, (2) the corrective steps that hase been taken and the results achieved, (3) the corrective steps that will be taken to avoid further violations, and (4) the date when full compliance will be achieved.
If an adequate reply is not received within the time specifiec in this Notice, 9303030210 921218 PDR ADOCK 05000282 G
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an order or a demand for infor: nation may be issued as to why the license should not be modified, susperded, or revoked, or why such other action as may be proper should not be taken. Where good cause is shown, consideration will i
be given to extending the response time.
&'W Dated at Glen Ellyn, Illinois MV. D.1Mfer, Chief this 18th day of December, 1952.
/ Reactor Projects Branch 2 P
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