ML13312A725

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Forwards Insp Repts 50-206/93-29,50-361/93-29 & 50-362/93-29 on 930902-1006.No Violations Noted.Concerns Noted Re Apparent Failure to Perform Adequate Safety Evaluation Prior to Commencing pre-outage Work in Unit 3
ML13312A725
Person / Time
Site: San Onofre  Southern California Edison icon.png
Issue date: 11/04/1993
From: Vandenburgh C
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To: Ray H
SOUTHERN CALIFORNIA EDISON CO.
Shared Package
ML13312A726 List:
References
NUDOCS 9312030076
Download: ML13312A725 (3)


See also: IR 05000206/1993029

Text

UNITED STATES

-A

NUCLEAR REGULATORY COMMISSION

REGIONV

1450 MARIA LANE

WALNUT CREEK. CAUFORNIA 94596-5368

NOV 04

Docket Nos. 50-206, 50-361, 50-362

Southern California Edison Company

Irvine Operations Center

23 Parker Street

Irvine, California 92718

Attention: Mr. Harold B. Ray, Senior Vice President, Power Systems

SUBJECT:

NRC INSPECTION REPORT NOS. 50-206, 361, 362/93-29

This refers to the routine inspection conducted by J. f.

Russell,

D. L. Solorio, F. R. Huey, and T. R. Meadows of this office, and C. M. Regan,

of the Office of Nuclear Reactor Regulation, on September 2 through October 6,

1993, of activities authorized by NRC License Nos. DPR-13 NPF-1 and NPF-15

and to the discussion of our findings held by the inspectors with

Mr. R. W. rieger and other members of the Southern California Edison Company

staff at the conclusion of the inspection.

Areas examined during this inspection are described in the enclosed inspection

report. Within these areas, the inspection consisted of selective

examinations of procedures and representative records, interviews with

personnel, and observations by the inspectors.

No violations of NRC requirements were identified within the scope of this

inspection. However, the NRC is concerned with the apparent failure to

perform an adequate safety evaluation prior to conmencing pre-outage work in

the Unit 3 safety equiInment building. The safety analysis appeared inadequate

because it failed to consider the effects of design basis flooding accidents.

We considered that an unqerlying reason for this apparent violation appears to

be an inadequate program to control watertight doors and plugs in the context

of their role to prevent flooding, and the ensuing lack of procedural

guidance. This issue is unresolved pending your submission of an evaluation

of the safety consequences of this condition. We will review your evaluation

and deterfine whether additional NRC actions are warranted. We are continuing

to evaluate the large amount of construction activities which were evident in

the emergency core cooling system rooms while Unit 3 was in power operations.

During this inspection we reviewed your Nuclear Safety Concerns Program and

interviewed various plant personnel regarding the Nuclear Safety Concerns

Program. Two issues of note were observed as a result of the interviews. We

noted that some contractor employees were not aware of the Nuclear Safety

Concerns Program and some were worried about possible discrimination if they

went to the Nuclear Safety Concerns Program. In addition , some maintenance

personnel lacked confidence in going first to their supervisor with a concern

and some also lacked confidence in the Nuclear Safety Concerns Program. We

9312030076 931104

PDR ADOCK 05000206

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request that you inform us what, if any, actions you plan to take address this

issue.

We also noted several loose parts and vibration monitor alarms occurred

associated with the Unit 3 steam generators during this inspection period. We

understand that you consider these alarms to be due to noises external to the

steam generators and not-due to a loose part. We will review the results of

steam generator base plate inspections that you will be performing during the

upcoming Unit 3 cycle VII outage.

Finally, we observed the actions of the Unit 2 control room staff during a

dropped control element assembly event. We considered their actions in

mitigating the ensuing reactor power and reactor coolant system temperature

perturbations a-strength.

In accordance with 10 CFR 2.790(a), a-

copy of this letter and the enclosure

will be placed in the NRC Public Document Room.

Should you have any questions concerning this inspection, we will be pleased

to discuss them with you.

Sincerely,

C. A. VanDenburgh, Chief

Reactor Projects Branch

Enclosure:

Inspeetion Report Nos. 50-206/93-29

50-361/93-29

and 50-362/93-29

cc w/enclo-sure:

Mr. Edwin A. Guiles, Vice President Engineering & Operations, San Diego Gas

and Electric Co.

T. E. Oubre, Esq., Southern California Edison Company

Chairman, Board of Supervisors, County of San Diego

Mr. Sherwin Harris, Resource Project Manager, Public Utilities Department

Mr. Charles B. Brinkman, Manager, ABB Combustion Engineering Nuclear Power

Mr. R. W. Krieger, Vice President, Nuclear Generating Station, Southern

California Edison Company

Mr. Don J. Womeldorf, Chief, Environmental Management Branch

Mr. Thomas E. Bostrom, Project Manager, Bechtel Power Corporation

Mr. Robert G. Lacy, San Diego Gas and Electric

Mr. Steve Hsu, Radiologic Health Branch

Mayor, City of San Clemente

0II

3

Docket File

G. Cook

S. Richards

B. Faulkenberry

J. Sloan

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