ML20148K028
| ML20148K028 | |
| Person / Time | |
|---|---|
| Issue date: | 05/20/1997 |
| From: | Gallo R NRC (Affiliation Not Assigned) |
| To: | Kipp C GENERAL ELECTRIC CO. |
| Shared Package | |
| ML20148K008 | List: |
| References | |
| REF-QA-99900003 99900003-97-01, 99900003-97-1, NUDOCS 9706170341 | |
| Download: ML20148K028 (2) | |
Text
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UNITED STATES j
NUCLEAR REGULATOF.Y COMMISSION o
2 WASHINGTON, D.C. 20665-0001 I
k.....,d May 20, 1997 Mr. Craig P. Kipp Plant Manager General Electric Nuclear Energy P.O. Box 780 Wilmington, NC 28402-0780
SUBJECT:
NRC INSPECTION REPORT 99900003/97-01 AND NOTICE OF NONCONFORMANCE
Dear Mr. Kirp:
On March 14, 1997, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at the General Electric (GE) Nuclear Energy facility.
The enclosed report presents the results of that ins.rction.
The inspection was conducted to assess GE's design interface with licensees that implemented the average power range monitor-rod block monitor-technical specification (referred to as ARTS) modification, that allowed licensees to bypass the rod block monitor (RBM) for a rod withdrawal error (RWE) event if the core had sufficient minimum critical power ratio margin.
The inspectors assessed RBM operability and related technical specifications actions with respect to protecting the fuel cladding in the boiling water reactor cores of ARTS plants for an RWE event. The inspectors also assessed GE's monitoring of the effectiveness of its design control program.
During the inspection, the inspectors determined that GE did not adequately inform ARTS licensees of the need to consider the fuel cladding plastic strain limits and the associated mechanical overpower (M0P) limits in addition to the minimum critical power ratio limits when considering RBM operability for potential RWE events.
This inadequate interface between GE and ARTS licensees contributed to (1) the failure of licensees to ensure through their technical specifications that the RBM was operable to protect fuel cladding at applicable plants, and (2) occasions during certain operational cycles of the Fermi, Hatch, Brunswick, and Duane Arnold nuclear plants when, based on GE's RWE analyses, the fuel cladding had exceeded its M0P limits and had the potential of exceeding its plastic strain limits.
The inspectors determined that GE modified certain design parameters used in the RWE analysis without procedures or other documented basis, and did not assess the overall effectiveness of GE's design control program after Detroit Edison Company (DECO) identified deficiencies in design adequacy.
Based on the above, the inspectors concluded that the implementation of GE's quality assurance program did not meet certain NRC requirements imposed on GE by its customers.
9706170341 970611 PDR QA999 EMVGENE 99900003 PDR
C. Kipp These issues are cited in the enclosed Notice of Nonconformance (NON), and the circumstances surrounding them are described in detail in the enclosed report.
You are requested to respond to the nonconformances and should follow the instructions specified in the enclosed NON when preparing your response.
In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter and its enclosures sill be placed in the NRC's Public Document Room.
Sincerely, t
Original signed by Robert M. Gallo, Chief Special Inspection Branch-Division of Inspection and Support Programs Office of Nuclear Reactor Regulation Docket No. 99900003 i
Enclosures:
1.
Notice of Nonconformance 2.
Inspection Report 99900003/97-01
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