ML20045G253
| ML20045G253 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 07/02/1993 |
| From: | Greenman E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20045G250 | List: |
| References | |
| 50-341-93-11, NUDOCS 9307130096 | |
| Download: ML20045G253 (3) | |
Text
,
NOTICE OF VIOLATION Detroit Edison Company Docket No. 50-341 Fermi 2 License No. NPF-43 During an NRC inspection conducted from May 4 through June 3,1993, a i
violation of NRC requirements was identified, In accordance with the " General i
Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, i
Appendix C, the violation is listed below:
1.
10 CFR Part 50, Appendix B, Criterion V, requires, in part, that l
activities affecting quality be prescribed by documented instructions, j
procedures, or drawings of a type appropriate to the circumstances, and j
be accomplished in accordance with these instructions, procedures, or drawings.
It further requires that instructions, procedures, or drawings shall include appropriate quantitative or qualitative
-acceptance criteria for determining that important activities have been satisfactorily accomplished.
i i
A.
Section 5.2.6 of NPP-OPI-12, " Tagging and Protective Barrier i
System," specified that independent verification shall be required i
when isolating components and upon restoration of components to service.
Independent verification of component position shall-be i
performed in accordance with NPP-OPI-08, " Control of Equipment."
Section 5.3 of NPP-OPI-08 stated that independent verification i
should be done in a timely manner.
i Contrary to the above, these procedures were not appropriate to the circumstances to ensure that an i Mer' dent verification for i
an abnormal valve lineup required fc
. nt evoluti6n was l
accomplished prior to the evolution. An Abnormal Lineup Sheet was performed on February 10, 1993, to isolate three control rod i
hydraulic control units prior to a planned reactor trip.
The i
independent verification was performed approximately four hours j
after the reactor trip.
j!
B.
Section 4.5.5.17 of Fermi Management Directive (FMD) CT-1,
" Calibration, Testing, and Surveillance," requires, in part, that I
appropriate procedures, checklists, data sheets, and operator rounds sheets used to perform calibrations, checks, tests, and surveillances shall require independent verification of the installation and removal of jumpers and lifted leads and for systems important to safety, the return of the system to normal 3
configuration following the calibration or test.
[
t Contrary to the above, as of February 1,1993, Instrumentation &
Control Surveillance Procedures 44.020.212 (HPCI Steam Line i
Pressure Calibration), 44.020.203 (HPCI Steam Line Flow l
Calibration), 44.220.403 (MSIV Leakage Control System Control Air Pressure Calibration), 44.020.262 (HPCI Steam Line Flow Response i
Time Test), 44.030.257 (Reactor Vessel Water Level Calibration),
j and 44.030.218 (RHR Pump B Discharge Pressure (ADS Permissive) l Calibration) all failed to contain independent verification i
requirements as required by FMD-CT1. (341/930ll-Olb) 9307130096 930702 a
I PDR ADOCK 05000341 O
PDR l
~-
I
1 j
l i
C.
Fermi Surveillance Procedure 44.120.001, " Accident Monitoring, Reactor Vessel Pressure, Division 1, Channel Calibration," was l
used to ensure equipment operability.
Contrary to the above, on April 29, 1993, Procedure 44.120.001 was not appropriate to the circumstances in that its provisions failed to ensure equipment operability of Division 1, Post-Accident Monitoring Pressure recorder B21-R623A. (341/930ll-01c) l This is a Severity Level IV violation (Supplement I).
.j 11.
Fermi Technical Specification 6.8.1.a requires that written procedures shall be established, implemented, and maintained covering the applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978.
Section 1.g of Appendix A to this regulatory guide revision requires, in part, that shift and rrlief turnover be covered by written procedures.
Fermi Administrative Procedure NPP-0PI-05, " Shift Turnover," requires the control room operators to perform shift turnovers, walkdown the control boards, and i
be aware of the status of any off-normal conditions.
Contrary to the above, on April 29, 1993, during two consecutive shift turnovers, the control room operators failed to be aware of the abnormal status of the Division 1, Post-Accident Monitoring Pressure recorder-(B21-R623A), namely that it was inoperable and reading zero instead of approximately 1,000 psi. The recorder strip chart was stamped by an operator at each shift turnover. (341/93011-03)
This is a Severity Level IV violation (Supplement I).
Pursuant to the provisions of 10 CFR 2.201, Detroit Edison Company 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 III, and a copy to the NRC Resident Inspector at the facility that is the subject of this Notice, within 30 days of the date of the 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) the reason for the violation, 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 order or a Demand for Information may be issued to show cause why the license should not be modified, suspended, or revoked, or why such other action as may be-proper should not be taken.
Where good cause is shown, consideration will be given-to extending the response time.
flotice of Violation 3
i 1
Under the authority of Section 182 of the Act, 42 U.S.C. 2232, this response shall be submitted under oath or affirmation.
Dated at Glen Ellyn, IL (fun +A this & day op ut x, 1993 Edward G. Greenman, Director
(/
Division of Reactor Projects 1
l t
i r
i 1
l l
l