ML20207B232

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Forwards Insp Repts 50-317/88-17 & 50-318/88-17 on 880627- 0713.Violations Noted.On 880604,voltage Regulator for Diesel Generator Improperly Placed in Manual Mode.On 880704, Improper Adjustment Made to Differential Temp Indication
ML20207B232
Person / Time
Site: Calvert Cliffs  
Issue date: 07/21/1988
From: Kane W
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To: Tiernan J
BALTIMORE GAS & ELECTRIC CO.
Shared Package
ML20207B237 List:
References
NUDOCS 8808020279
Download: ML20207B232 (3)


See also: IR 05000317/1988017

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4 1 1 1988

DOCKET / LICENSE:

50-317/0PR-53

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50-318/0PR-69

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Baltimore Gas and Electric Company

ATTN: Mr. J. A. Tiernan

Vice President, Nuclear Energy

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Calvert Cliffs Nuclear Power Plant

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MD. Rts. 2 and 4, P. O. Box 1535

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Lusby, Maryland 20657

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Gentlemen:

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Subject: NRC:RI Special Inspection Report Nos. 50-317/88-17, 50-318/88-17

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The enclosed report transmits the findings of the June 27 - July 13,1988

special inspection concerning two operational events at the Calvert Cliffs

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facility. These findings were discussed with Mr. L. Russell and members of

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your staff.

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On June 4,1988, the voltage regulator for #21 diesel generator was improperly

placed in the manual mode.

This rendered the diesel generator inoperable

for a 48-hour period.

Technical Specifications (TS) require a minimum of two

diesel generators to be operable during Modes 1, 2, 3 or 4.

The related action

statement allows one diesel generator to be inoperable for a maximum of 72

hours provided the operability of remaining AC power sour.ces is demonstrated.

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The operability of remaining AC sources was not demonstrated during the above

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48-hour period. This caused a TS Limiting Condition for Operation

and its related action statement to be rxceeded and is therefore an apparent

violation.

During a startup on Unit 1, on July 4,1988, an improper adjustment was made

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to the differential temperature (delta T) power indications which are inputs to

the reactor protection system (RPS). This action introduced an error into

power indication which may have altered TS limiting safety system settings. An

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evaluation is in progress to determine the impact of the error on the settings,

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The altering of limiting safety systen settings in a non-conservative direction

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would constitute a TS violation.

In addition, the failure to follow existing

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procedures is an apparent violation.

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Perhaps of more significant concern are underlying weaknesses highlighted by

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these events and by a March 30, 1988, event in which Operations personnel

allowed pressurizer / pressurizer spray line differential temperature to exceed

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a TS limit (detail 3 of Inspection Report 50-317/88-05,318/88-06). All point

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to the lack of a questioning attitude by Operations personnel and a willingness to

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pursue the solution to a given abnormal situation without first obtaining the

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required level of technical review and without assuring consistency with

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approved procedures.

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0FFICIAL RECORD COPY

IR CC 88-17 - 0001.0.0

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0800020279 000721

11/29/80

PDR

ADOCK 05000317

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Baltimore Gas and Electric Company

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Accordingly, we have scheduled an En 'orcement Conference on August 8,1988 to

discuss these events with you in the NRC Region I Office in King of Prussia,

Pa. We will forward an appropriate notification of enforcement action af ter

the Enforcement Conference.

During the Enforcement Conference, please be prepared to address the

'o11owing:

safety significance of both events,

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the impact of the power error on RPS limiting safety system

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settings,

root cause evaluations,

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factors that worsened or mitigated these events,

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broader implications of these events,

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actions to prevent recurrence, and

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matters listed in section III of the enclosed report.

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Your cooperation with us is appreciated.

Sincerely,

%ed Byg

William F. Kane, Director

Division of Reactor Projects

Enclosure: NRC:RI Special Inspection Report Nos. 50-317/83-17, 50-318/88-17

cc w/ enc 1:

J. Lippold, Genersl Supervisor, Technical Services Engineering

T. iiagette, Administrator, Nuclear Evaluations

Public Document Room (LPDR)

Local Public Document Room (LPDR)

Nuclear Safety Information Center (NSIC)

NRC Resident Inspector

State of Maryland (2)

0FFICIAL RECORD COPY

IR CC 83-17 - 0002.0.0

11/29/80

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Balt'inore Gas and Electric Company

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JUL 211988

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bec w/ encl:

Region I Docket Room (with concurrences)

Management Assistant, ORMA (w/o enclosure)

ORP Section Chief

S. McNeil, LPM, NRR

R. Capra, POI-1, NRR

D. Holody, Enforce >nent Of ficer, Region 1

R. Gallo, Region 1

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Tripp

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0FFICIAL RECORD COPY

IR CC 88-17 - 0003.0.0

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