ML20127C989: Difference between revisions

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APPEN0lX A                                  '
NOTICE Of VIOLATION                              j Gulf States Utilities                                                    Docket: 50-458            f River Bend Station                                                      License: NPF-47 St. Francisville, Louisiana During an NRC inspection conducted on November 8 through December.19, 1992,                        I three violations of NRC requirements were identified.                        In accordance with the
                        " General Statement of Policy and Procedure for NRC Enforcement Actions,"
10 CFR Part 2, Appendix C, the violations are listed below:
A.            Failure to Meet a Limiting Condition for Operation Technical Specification 3.0.4 states, " Entry into an OPERATIONAL CONDITION or other specified condition shall not be made when the conditions for the Limiting Condition for Operation are not met and the associated ACTION requires a shutdown if they are not met within a specified time interval."
Technical Specification 3.7.3, " Limiting Conditions for Operation,"
states that the reactor core isolation cooling system shall be operable with an operable flow path capable of automatically taking suction from the suppression pool and transferring the water to the reactor pressure vessel. This specification is applicable in Operational Conditions 1, 2, and 3, with reactor steam dome pressure greater than 150 psig. The                -
associated action statement requires a shutdown if the system is not restored within 14 days.
Contrary to the above, on November 25, 1992, the licensee entered a specified condition when the Limiting Conditions for Operation were not met, in that reactor pressure was increased to greater than 150.psig with the reactor core _ isolation cooling system inoperable.
This is a Severity level IV violation.              (Supplement. 1) (458/92034-1)
: 8.            failure to Perform Action Statement Requirements Technical Specification 3.3.1, Table 3.3.1-1, requires at least three channels of the intermediate range monitors to be operable in each trip system with the plant in Operational Condition 3 and 4, otherwise, within I hour, verify all insertable control rods to_ be inserted in the core and lock the reactor mode in the shutdown position.
Technical Specification 3.3.7.6-requires-at least_two channels of-the source range monitors to be operable with the plant in Operational Conditions 3 and 4, otherwise, within I hour, verify all insertable control rods to be inserted in the core and lock the reactor mode switch in the shutdown position.
9301150052 930108 PDR            ADOCK 05000458                                                                    ,
G                                      PDR
 
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Contrary to the above, on December 6, 1992, the reactor operator failed to lock the reactor mode switch in the shutdown position af ter entering into Operational Condition 3, with all channels of 4
the intermediate range and source range monitors inoperable.
This is a Severity Level IV violation. (Supplement I) (458/92034-2)
C. Failure to identif_y a Condition Adverse to Oualit_y 10 CFR Part 50, Appendix B, Criterion XVI states, in part, that measures shall be established to assure that conditions adverse to quality are promptly identified and corrected.                                  .
Contrary to the above, from April 15,-1991, through December 4, 1992,
;                                        measures had not been established to identify the degradation of the safety-related high pressure core spray pump room unit cooler. As a result, the filter elements of the unit cooler had deteriorated to the point that they were breaking down and clogging the cooling coils.                                                                                                          .
This is a Severity Level IV violation.                                (Supplement 1) (458/92034-3)                                                                          ;
Pursuant to the provisions of 10 CFR Part 2.201, Gulf States Utilities is hereby required to submit a written statement or explanation to the U. S.
Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, D.C.
20555 with a copy to the Regional Administrator, Region IV, and a copy to the NRC Resident inspector, within 30 days of the date of the letter transmitting this Notice of Violation (Notice). This reply should clearly he marked as a
                                  " Reply to a Notice of Violation" and should include for each violation:
(1) the reason for the v'iolation, or, if contested, the basis for disputing the violation, (2) the corrective steps that have been taken and the results achieved, (3) the corrective steps that will be taken to avoid further violations, and (4) the date when full compliance will be achieved. -If an-adequate reply is not received within the time specified in this Notice, an-I                                order or demand for information may-be issued as to why the license should not i                                be modified, suspended, or revoked, or why such other action as may be proper j                                should not be taken. Where good cause is shown, consideration will be given to extending the response time.
Dated at Arlington, Texas, this 8th day of January 1992 l
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Latest revision as of 18:54, 23 July 2020

Notice of Violation from Insp on 921108-1219.Violation Noted:On 921125,licensee Entered Specified Condition When LCO Not Met,In That Reactor Pressure Increased to Greater than 150 Psig W/Rcics Inoperable
ML20127C989
Person / Time
Site: River Bend Entergy icon.png
Issue date: 01/08/1993
From:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20127C974 List:
References
50-458-92-34, NUDOCS 9301150052
Download: ML20127C989 (2)


Text

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l '

APPEN0lX A '

NOTICE Of VIOLATION j Gulf States Utilities Docket: 50-458 f River Bend Station License: NPF-47 St. Francisville, Louisiana During an NRC inspection conducted on November 8 through December.19, 1992, I three violations of NRC requirements were identified. In accordance with the

" General Statement of Policy and Procedure for NRC Enforcement Actions,"

10 CFR Part 2, Appendix C, the violations are listed below:

A. Failure to Meet a Limiting Condition for Operation Technical Specification 3.0.4 states, " Entry into an OPERATIONAL CONDITION or other specified condition shall not be made when the conditions for the Limiting Condition for Operation are not met and the associated ACTION requires a shutdown if they are not met within a specified time interval."

Technical Specification 3.7.3, " Limiting Conditions for Operation,"

states that the reactor core isolation cooling system shall be operable with an operable flow path capable of automatically taking suction from the suppression pool and transferring the water to the reactor pressure vessel. This specification is applicable in Operational Conditions 1, 2, and 3, with reactor steam dome pressure greater than 150 psig. The -

associated action statement requires a shutdown if the system is not restored within 14 days.

Contrary to the above, on November 25, 1992, the licensee entered a specified condition when the Limiting Conditions for Operation were not met, in that reactor pressure was increased to greater than 150.psig with the reactor core _ isolation cooling system inoperable.

This is a Severity level IV violation. (Supplement. 1) (458/92034-1)

8. failure to Perform Action Statement Requirements Technical Specification 3.3.1, Table 3.3.1-1, requires at least three channels of the intermediate range monitors to be operable in each trip system with the plant in Operational Condition 3 and 4, otherwise, within I hour, verify all insertable control rods to_ be inserted in the core and lock the reactor mode in the shutdown position.

Technical Specification 3.3.7.6-requires-at least_two channels of-the source range monitors to be operable with the plant in Operational Conditions 3 and 4, otherwise, within I hour, verify all insertable control rods to be inserted in the core and lock the reactor mode switch in the shutdown position.

9301150052 930108 PDR ADOCK 05000458 ,

G PDR

1

\

Contrary to the above, on December 6, 1992, the reactor operator failed to lock the reactor mode switch in the shutdown position af ter entering into Operational Condition 3, with all channels of 4

the intermediate range and source range monitors inoperable.

This is a Severity Level IV violation. (Supplement I) (458/92034-2)

C. Failure to identif_y a Condition Adverse to Oualit_y 10 CFR Part 50, Appendix B, Criterion XVI states, in part, that measures shall be established to assure that conditions adverse to quality are promptly identified and corrected. .

Contrary to the above, from April 15,-1991, through December 4, 1992,

measures had not been established to identify the degradation of the safety-related high pressure core spray pump room unit cooler. As a result, the filter elements of the unit cooler had deteriorated to the point that they were breaking down and clogging the cooling coils. .

This is a Severity Level IV violation. (Supplement 1) (458/92034-3)  ;

Pursuant to the provisions of 10 CFR Part 2.201, Gulf States Utilities is hereby required to submit a written statement or explanation to the U. S.

Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, D.C.

20555 with a copy to the Regional Administrator, Region IV, and a copy to the NRC Resident inspector, within 30 days of the date of the letter transmitting this Notice of Violation (Notice). This reply should clearly he marked as a

" Reply to a Notice of Violation" and should include for each violation:

(1) the reason for the v'iolation, or, if contested, the basis for disputing the violation, (2) the corrective steps that have been taken and the results achieved, (3) the corrective steps that will be taken to avoid further violations, and (4) the date when full compliance will be achieved. -If an-adequate reply is not received within the time specified in this Notice, an-I order or demand for information may-be issued as to why the license should not i be modified, suspended, or revoked, or why such other action as may be proper j should not be taken. Where good cause is shown, consideration will be given to extending the response time.

Dated at Arlington, Texas, this 8th day of January 1992 l

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