ML20212B906
| ML20212B906 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 10/16/1997 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20212B902 | List: |
| References | |
| 50-302-97-13, NUDOCS 9710280282 | |
| Download: ML20212B906 (2) | |
Text
-
r i
l NOTICE OF VIOLATION Florida Power Corporation Docket No. 50-302 Crystal River Unit 3 License No. DPR 72 i
During NRC ins >ections conducted on August 17 through September 20. 1997.
violations of iRC requirements were identified, in accordance with the
" General Statement of Policy and Procedure for NRC Enforcement Actions." NUREG 1600 the violations are listed below:
}
A.
10 CFR 50. Appendix B. Criterion 111. Design Control, requires that measures be established to assure that appropriate quality standards are r
specified in documents and that deviations from such standards are controlled.
The design control measures shall provide for verifying or checking the adequacy of design, such as by the performance of design reviews.
l Contrary to the above, the scaffolding control program, as defined in licensee Administrative Instruction (Al) 1803. Safety Standard for Ladders.-Scaffolds, and Ancillary Equipment. Revision 11. does not contain measures to assure 1 5t deviations from the design quality standard for the safety n9a1C mipment installed in the plant are adequately controlled.
SMr uWly. the procedure does not require a documented review of impact on un plant by the installation of scaffolding in the vicinity of safety related systems.
On August 26 1997 unrestrained and unanalyzed scaffolding was observed-in the vicinity of the main control board and both trains of 4160 volt engineered safeguard switchgear cabinets.
This is a Severity Level IV Violation (Supplement 1).
B.
Technical S)ecification 5.6.1.1 Procedures, requires that written procedures )e established and implemented covering the applicable 2
3rocedures recommended in Regulatory Guide 1.33. Revision 2. Appendix A, i
r bruary 1978.
This includes procedures for equipment control.
e Licensee Compliance Procedure (CP) 115. Nuclear Plant Tags and Tagging 4
Orders. Revision 75. step 4.5.9.3 states that all breakers outside of a cubicle are to have their wheels chocked.
Contrary to the above, on August 26. 1997, the inspector's examination of the A '4160V Engineered Safeguards switchgear room revealed that six breakers were removed from cubicles without their wheels being chocked 4
and that three additional breakers were chocked in such a manner as to be unable to restrain motion of-the breakers.
This 1s a Severity Level IV Violation (Supplement 1).
Pursuant to the provisions of 10 CFR 2.201. Florida Power Corporation is hereby required to submit a written statement or explanation to the U.S.
Nuclear Regulatory Commission. ATTN: Document Control Desk. Washington, DC 20555. with a copy to the Regional Administrator. Region 11. and a copy to the NRC Resident-Inspector, at Crystal River, within 30 days of the date of the Q-a *Mit Wh e
PDR i
2 letter transmitting this Notice of Violation (Notice).
This reply should be clearly marked as a " Reply to a Notice of Violation" and should include for each violation:
(1) tne reason for the violation or. If contested, the basis for disputing the violation. (2) the corrective steps that have been taken and i
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.
Your response may reference or include previous docketed correspondence. if the correspondence adequately addresses the required res)onse. if an adequate i
reply is not received within the time specified in this lotice, an order or demand for information may be issued as to why the license should not be modified, suspended. or revoked. or why such other action as may be
) roper should not be taken.
Where good cause is shown consideration will )e given to extending the response time.
-Because your res)onse will be placed in the NRC Public Document Room (PDR) to the extent possi)le, it should not include any personal privacy. 3roprietary.
or safeguards information so that it can be placed in the PDR willout redaction.
If personal privacy or proprietary information is necessary to provide an acceptable response. then please provide a bracketed copy of your response that identifies the information that should be protected and a redacted copy of your response that deletes such information.
If you request withholding of such material, you must s)ecifically identify the portions of your response that you seek to have withleld and provide in detail the bases for your claim of withholding (e.g., explain why the disclosure of information will create an unwarranted invasion of personal privacy or provide the information required by 10 CFR 2.790(b) to support a request for withholding confidential commercial or financial information).
If safeguards information is necessary to provide an acreptable response, please provide the level of protection described in 10 CFR 73.21.
Dated at Atlanta, Georgia this 16th day of October 1997 l
i U.S. NUCLEAR REGULATORY COMMISSION REGION 11 t
Docket No:
50-302 License No:
DPR-72 Report No:
50 302/97-13 Licensee:
Florida Power Corporation Facility:
Crystal River 3 Nuclear Station Location:
15760 West Power Line Street Crystal River. FL-34428-6708 Dates:
August 17 through September 20. 1997 Inspectors:
S. Cahill. Senior Resident Inspector T. Cooper. Resident Inspector S. Sanchez. Resident inspector D. Billings. Resident Inspector. Oconee. section E8.5 J. Lenahan. Reactor Inspector, sections E3.1. E8.4 M. Miller Reactor Inspector, section 07.1 T. Ross. Senior Resident inspector, Farley, sections 08.4. 08.5 R. Schin. Reactor Inspector, sections 07.1. 08.1.
08.2. E8.1. E8.2, E8.3 H. Thomas. Reactor inspector, section 07.1 F. Wright. Senior Radiation Specialist, sections R1.1 through R1,4. R3.1. R3.2 R5.1. R6.1 Approved by:
K. Landis. Chief. Projects Branch 3 DivisionofReactorProjects
._