05000282/LER-2001-003-01, Nuclear Management Co., LLC, Supplement 1 Plant in Unanalyzed Condition Due to Flood Panel Deficiencies for April 2002
| ML021160306 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 04/12/2002 |
| From: | Nazar M Nuclear Management Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LER 01-003-01 | |
| Download: ML021160306 (6) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(x) |
| 2822001003R01 - NRC Website | |
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Committed to Nuclear Excellenca Nuclear Management Company, LLC Prairie Island Nuclear Generating Plant 1717 Wakonade Dr. East
- Welch MN 55089 April 12, 2002 10 CFR Part 50 Section 50.73 U S Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 LER 1-01 -03, Supplement 1 Plant in Unanalyzed Condition Due to Flood Panel Deficiencies Supplement 1 to the Licensee Event Report (originally submitted on September 10, 2001) for this occurrence is attached. Updated information is side-barred. In the report, we made no new NRC commitments. Please contact us if you require additional information related to this event.
Or~k. A Mano K. Nazar Site Vice Presi ent Prairie Island uclear Generating Plant c:
Regional Administrator - Region l1l, NRC NRR Project Manager, NRC Senior Resident Inspector, NRC James Bernstein, State of Minnesota Attachment
NRC FORM 366 U.S. NUCLEAR REGULATORY APPROVED BY OMB NO. 3150-0104 EXPIRES 6-30-2001 (1-2001)
COMMISSION
, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
FACILITY NAME (1)
DOCKET NUMBER (2)
PAGE (3) 05000 282 Prairie Island Nuclear Generating Plant Unit 1 1 OF 5 TITLE (4)
Plant in Unanalyzed Condition Due to Flood Panel Deficiencies EVENT IATE (5)
LER NUMBER (6
[
REP 7
ORT D
OTHER FACILITIES INVOLVED (8)
T FACILITY NAME DOCKET NUMBER MO DAY YEAR YEAR NUMBER ONO MO DAY YEAR Prairie Island Unit 2 05000 306 07 10 01 01 03 -01 04 12 02 FACILTY NAME DOCKET NUMBER OPERATING 1
THIS REPORT IS SUBMrITED PURSUANT TO THE REQUIREMENTS OF 10 CFR (Check all that apply) 011)
MODE (9) 20.2201(b) 20.2203(a)(3)(ii) 50.73(a)(2)(ii)(B)
B 50.73(a)(2)(ix)(A)
POWER 100 20.2201 (d) 20.2203(a)(4) 50.73(a)(2)(iii) 50.73(a)(2)(x)
LEVEL (10) 20.2203(a)(1) 50.36(c)(1)(i)(A) 50.73a)(2)(iv (A) 73.71 (a)(4) 20.2203(a)(2)(i) 50.36(c)(1)(fl)(A) 50.73 a)(2)(v) A 73 71(a)5) 20.2203 a)(2)(ii)
__50.3 c250.73 a (2 vBOTE 20.220 a 2 iii _
50.46 a 3)(i_
50.73(a Specify in Abstract below or in 20.220 a 50.732)(i) 50.73 a N2v (if more space is required, use additional copies of (if more space is required, use additional copies of (if more space is required, use additional copies of NRC Form 366A) (17) drawing additions, revisions, and deletions procedures (to require independent review of drawings and changes prior to issuance for use),
- design change procedures (to require walk-down of completed modification by responsible engineer prior to turnover),
Emergency Preparedness Program documents (to add a reference to the flood response procedure, so deficiencies are more likely to be identified in quality assurance audits of the Emergency Preparedness Program),
flood panel inspection/installation procedures (to strengthen inspection requirements and move the flood panel installation procedure to a separate procedure), and corrective action process procedures (to strengthen review and approval process).
In addition, the extent of the root causes identified is addressed in a number of related Condition Reports, which include assessments of:
adequacy of past inspections of plant structures,
- timeliness of corrective actions, independent verification of drawings, and effectiveness of past corrective actions.
- 2. The affected flood panels have been restored to compliance (improvements to flood panels will be evaluated as part of the site continuous improvement philosophy).
- 3. The steel panels in the D5/D6 Building have been seal welded.
FAILED COMPONENT IDENTIFICATION None.
PREVIOUS SIMILAR EVENTS
None.