ML20212F514
| ML20212F514 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 10/30/1997 |
| From: | Grobe J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Graesser K COMMONWEALTH EDISON CO. |
| Shared Package | |
| ML20212F518 | List: |
| References | |
| 50-454-97-13, NUDOCS 9711040319 | |
| Download: ML20212F514 (3) | |
See also: IR 05000454/1997013
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October 30,-1997
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Mr. K. Graesser
Site Vice President -
Byron Nuclear Power Station
Commonwealth Edison Company '
4450 North German Church Road
Byron,-lL 61010
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SUBJECT:
NRC STEAM GENERATOR REPLACEMENT INSPECTION REPORT
50J44/97013(DRS) AND NOTICE OF VIOLATION
Dear Mr. Graesser:
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On September 18,1997, the NRC completed an inspection at your Byron Nuclear Power
Station. The purpose of the inspection was to review the engineering and planning efforts for
the upcoming Unit 1 steam generainr replacement project. The enclosed report presents the
results of this inspection.
Overall, your steam generator replacement initiative demonstrated a good engineering effort
focused on safety. In particular, we noted that the replacement stenm generator (RSG) design
changes and material upgrades represented significant improvemeats over the original steam
generators. Further, we concluded that the steam generator replat ement prtgram complied
- with the American Society for Mechanical Engineers (ASME) Code Section XI requirements.
However, we are concemed with two aspects of your RSG program. In particular, the scope of
the RSG safety evaluation appeared limited and the control of design basis inpots for
calculations supporting the RSG replacement wananted improvement.
One violation was identified, with two examples, for failure to fully consider the impact of the
RSGs on safety related systems affected by this modification. The inspectors identified that the
RSG modification wnuld likely impact the design basis plant cooling performance of the residual
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heat removal system and this had rsot_been evaluated by your staff. Additionally, the effects of
a main steamline break and a main feedline break on containment sump and pH levels
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(potentially impacted by the RSG modification) had not been evaluated. We consider these
errors to indicate a less than rigorous engineering staff effort for evaluation of the scope of
effected systems impacted by the RSG modification.
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Another violation was identified, with two examples, for failure to fully ensure design basis
inputs had been incorporated into calculations supporting the RSG modification, inspectors
identified ' hat input errors had been made in determining the reactor coolant volume change
associated with the RSG modification, which affected several other analysis. Of particular
concem, was a design basis heat load input missing from the calculation supporting the
minimum condensate storage tank water volume inventory, which appeared to invalidate your
staffs conclusions documented in the RSG safet/ evaluation. These errors indicated a lack of
attention to detail for control of design basis inputs in calculations supporting the RSG
modification.
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ADOCK 05000454
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- K. Graesser.
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October 30, 1997L
The violations are cited in thts enclosed Notice of Violation (Notice) and the associated :
' circumstances are described in detail in the enclosed report.' Please note that your are required
to respond to this letter and should follow the instructions specified in the enclosed Notice when
i preparing your response. The NRC will use your response, in part, to determine whether
further enforcement action is necessary to ensure compliance with regulatory requirements, in -
accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter and its .
enclosures will be placed in the NRC Public Document Room.
iWe will gladly discuss any questions you have concerning this inspection.
Sincerely,
-original signed by J. A. Grobe-
. John A. Grobe, D' actor.
,
- Division of Read %fety
Docket No.-50-454 -
- License No.- NPF-37-
Enclosures:
1. Notice of V!olation
2.: Inspection Report 50-454/97013(DRS) -
cc w/ encl:
R. J. Manning, Executive Vice President, Generation
M, Wallace, Senior Vice President, Corporate Services
H. G. Stanley, Vice President, PWR Operations
Liaison Officer, NOC-BOD '
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- D. A. Sager, Vice President, Generation Support
D. Farrar, Nuclear Regulatory Services Manager
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I. Johnson, Licensing Operations Manager
Document Control Desk - Licensing -
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K. Kofron; Station Manager
D. Brindle, Regulatory Assurance Supervisor
Richard Hubbard.
Nathan Schloss, Economist, Office of the Attomey General .
State Liaison Officer
State Liaison Officer, Wisconsin
. Chairman, Illinois Commerce Commission
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See Attached Distribution:
DOCUMENT NAME: ~ G:DRS\\BYR97013.DRS
. To eoceive a co py of this document, Indicate in the box 'C' = Copy w/o attach /end *E' = Co)y w/ attach /enct *N* = No copy
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10M/97
10/n/97l1
10lofl97
10/7'/97
OFFICIAL RECORD COPY
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K. Graesser-
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October 30, 1997
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Distribution:
- Docket File w/ encl- _
SRI, Byron w/enci
TSS w/ encl
PUBLIC IE-01 w/enci
LPM, NRR w/enci
CAA1 w/enci
OCFO/LFARB w/encI
A. B. Beach, Rill w/enci
- DOCDESK w/enct
DRP w/enci -
J. L Caldwell, Rlli w/enci
' DRS wlenci
Rlli Enf. Coordinator w/enci
Rill PRR w/ encl
R. A.~ Capra, NRR w/enci
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