ML17342B421: Difference between revisions

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{{#Wiki_filter:Florida   Power and Tur'key Point Plant Light Company 0  ~ENCLOSURE 1 0
{{#Wiki_filter:ENCLOSURE 1
Docket No. 50-250 License No. DPR-31 EA 89-47 During the Nuclear Regulatory Commission (NRC) inspection conducted on January 17-20, 1989, a violation of NRC requirements was identified.               In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1988), the violation is listed below:
0~
Criterion   V of Appendix 8 to 10 CFR Part 50, as implemented by the licensee's   accepted Quality Assurance Program (FPL QAR-1-76A, dated June 10, 1987), requires that activities affecting quality be in accordance with approved procedures.
0 Florida Power and Light Company Tur'key Point Plant Docket No. 50-250 License No.
Section 5.4.8 of Procedure       QP 5. 1 (Revision 3) of the licensee's Quality Assurance   Manual requires     that procedures     be developed to implement the Plant Emergency Plan.
DPR-31 EA 89-47 During the Nuclear Regulatory Commission (NRC) inspection conducted on January 17-20,
Emergency Procedure   20101   (Duties of the Emergency Coordinator) specifies an Alert declaration   upon   determination of Reactor Coolant System (RCS) leakage exceeding 50 gpm,     followed by notification to the State of Florida within 15 minutes and the     NRC within 60 minutes.
: 1989, a violation of NRC requirements was identified.
In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions,"
10 CFR Part 2, Appendix C (1988),
the violation is listed below:
Criterion V of Appendix 8 to 10 CFR Part 50, as implemented by the licensee's accepted Quality Assurance Program (FPL QAR-1-76A, dated June 10, 1987),
requires that activities affecting quality be in accordance with approved procedures.
Section 5.4.8 of Procedure QP 5. 1 (Revision
: 3) of the licensee's Quality Assurance Manual requires that procedures be developed to implement the Plant Emergency Plan.
Emergency Procedure 20101 (Duties of the Emergency Coordinator) specifies an Alert declaration upon determination of Reactor Coolant System (RCS) leakage exceeding 50 gpm, followed by notification to the State of Florida within 15 minutes and the NRC within 60 minutes.
Contrary to the above, on January 7, 1989, the licensee failed to promptly classify an event involving Unit 3 RCS leakage greater thah 50 gpm and to make timely notification to the State of Florida and the NRC.
Contrary to the above, on January 7, 1989, the licensee failed to promptly classify an event involving Unit 3 RCS leakage greater thah 50 gpm and to make timely notification to the State of Florida and the NRC.
This is a Severity Level IV violation (Supplement         VIII).
This is a Severity Level IV violation (Supplement VIII).
Pursuant to the provisions of 10 CFR 2.201, Florida Power and Light Company is hereby required to submit a written statement or explanation to the Director, Office of Enforcement, U.S. Nuclear Regulatory Commission, within 30 days of the date of this Notice. This reply should be clearly marked as a "Reply to a Notice of Violation" and should include: ( 1) admission or denial of the violation, (2) the reasons for the violation           if   admitted, (3) the corrective steps that have been taken and the results achieved, (4) the corrective steps which will be taken to avoid further violations, and (5) the date when full compliance will be achieved.       If   an adequate reply is not received within the time specified in this Notice, an order may be issued to show cause why the 8903090099 890224 PDR   ADOCN, 05000250 G                   PNU
Pursuant to the provisions of 10 CFR 2.201, Florida Power and Light Company is hereby required to submit a written statement or explanation to the Director, Office of Enforcement, U.S.
Nuclear Regulatory Commission, within 30 days of the date of this Notice.
This reply should be clearly marked as a "Reply to a Notice of Violation" and should include:
( 1) admission or denial of the violation, (2) the reasons for the violation if admitted, (3) the corrective steps that have been taken and the results
: achieved, (4) the corrective steps which will be taken to avoid further violations, and (5) the date when full compliance will be achieved.
If an adequate reply is not received within the time specified in this Notice, an order may be issued to show cause why the 8903090099 890224 PDR ADOCN, 05000250 G
PNU


Florida Power and Light Company                     Docket Nos. 50-250, 50-251 Turkey Point Plant                                    License Nos. DPR-31, DPR-41 license should not be modified, suspended,   or revoked or why such other action as may be proper should not be taken.
Florida Power and Light Company Turkey Point Plant Docket Nos.
FOR THE NUCLEAR REGULATORY COMMISSlON lgo m L    rnst cting Regional Administrator Dated at Atlanta, Georgia this     day of           1989}}
50-250, 50-251 License Nos.
DPR-31, DPR-41 license should not be modified, suspended, or revoked or why such other action as may be proper should not be taken.
FOR THE NUCLEAR REGULATORY COMMISSlON Dated at Atlanta, Georgia this day of 1989 lgo m
L rnst cting Regional Administrator}}

Latest revision as of 11:49, 7 January 2025

Suffolk County First Set of Interrogatories & Request for Production of Documents to NRC Staff Re Emergency Broadcast Sys.* Certificate of Svc Encl.Related Correspondence
ML17342B421
Person / Time
Site: Shoreham File:Long Island Lighting Company icon.png
Issue date: 03/03/1988
From: Mark Miller
KIRKPATRICK & LOCKHART, SUFFOLK COUNTY, NY
To:
NRC OFFICE OF THE GENERAL COUNSEL (OGC)
References
CON-#188-5755 OL-3, NUDOCS 8803090099
Download: ML17342B421 (4)
v • d • e


Text

ENCLOSURE 1

0~

0 Florida Power and Light Company Tur'key Point Plant Docket No. 50-250 License No.

DPR-31 EA 89-47 During the Nuclear Regulatory Commission (NRC) inspection conducted on January 17-20,

1989, a violation of NRC requirements was identified.

In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions,"

10 CFR Part 2, Appendix C (1988),

the violation is listed below:

Criterion V of Appendix 8 to 10 CFR Part 50, as implemented by the licensee's accepted Quality Assurance Program (FPL QAR-1-76A, dated June 10, 1987),

requires that activities affecting quality be in accordance with approved procedures.

Section 5.4.8 of Procedure QP 5. 1 (Revision

3) of the licensee's Quality Assurance Manual requires that procedures be developed to implement the Plant Emergency Plan.

Emergency Procedure 20101 (Duties of the Emergency Coordinator) specifies an Alert declaration upon determination of Reactor Coolant System (RCS) leakage exceeding 50 gpm, followed by notification to the State of Florida within 15 minutes and the NRC within 60 minutes.

Contrary to the above, on January 7, 1989, the licensee failed to promptly classify an event involving Unit 3 RCS leakage greater thah 50 gpm and to make timely notification to the State of Florida and the NRC.

This is a Severity Level IV violation (Supplement VIII).

Pursuant to the provisions of 10 CFR 2.201, Florida Power and Light Company is hereby required to submit a written statement or explanation to the Director, Office of Enforcement, U.S.

Nuclear Regulatory Commission, within 30 days of the date of this Notice.

This reply should be clearly marked as a "Reply to a Notice of Violation" and should include:

( 1) admission or denial of the violation, (2) the reasons for the violation if admitted, (3) the corrective steps that have been taken and the results

achieved, (4) the corrective steps which will be taken to avoid further violations, and (5) the date when full compliance will be achieved.

If an adequate reply is not received within the time specified in this Notice, an order may be issued to show cause why the 8903090099 890224 PDR ADOCN, 05000250 G

PNU

Florida Power and Light Company Turkey Point Plant Docket Nos.

50-250, 50-251 License Nos.

DPR-31, DPR-41 license should not be modified, suspended, or revoked or why such other action as may be proper should not be taken.

FOR THE NUCLEAR REGULATORY COMMISSlON Dated at Atlanta, Georgia this day of 1989 lgo m

L rnst cting Regional Administrator

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