ML18064A791
| ML18064A791 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 05/19/1995 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML18064A790 | List: |
| References | |
| 50-255-95-04, 50-255-95-4, NUDOCS 9506050090 | |
| Download: ML18064A791 (3) | |
See also: IR 05000222/2004012
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Consumers Power Company
Palisades Nuclear Generating Facility
Docket No. 50-255
License No. DPR-20
During an NRC inspection conducted fro~ February 22 through April 12, 1995,
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:
1.
Palisades Plant Facility Operating License, Section 2.C.(3), requires,
in part, that the licensee shall implement and maintain in effect all
provisions of the approved fire protection program as described in the
Final Safety Analysis Report for the facility ..
a.
Administrative procedure 9.48, "Fire Protection Plan," Section
11.1, which is contained in the Fire Protection Program Report as
described in the Updated Safety Analysis Report, Section 9.6.1.2,
implements the requirements of Fire Protection Implementing
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Procedure, FPIP-7, "Fire Prevention Activities." FPIP-7,
Section 5 .1, requires' in part that stairways sha 11 be kept cl ear
of storage at all times.
Contrary to the above, from October 20, 1994, through March 08,
1995, the bottom of the stairwell leading to the safeguards rooms
was being used as a storage ar~a for various maintenance
activities. (255/95004-04a(DRS))
b.
The National Fire Protection Association Standard 10, Section 4-
4.1, which is implemented by the response to the BTP APCSP 9.5-1
and contained in the Fire Protection Program Report as described
in the Updated Safety Analysis Report, Section 9.6.1.2, requires,
in part, that annual maintenance be performed on all portable fire
extinguishers.
Contrary to the above, from February 1991 through March 1995, 89
portable fire *extinguishers maintained by the Project Management &
Modifications Group for use by fire watches during the performance
of hot work had not had the required annual maintenance.
(255/95004-04b(DRS))
This is a Severity Level IV violation (Supplement I).
2.
10 CFR 50, Appendix 8, Criterion III, Design Control, requires in part
that measures shall be established to assure that applicable regulatory
requirements and the design basis, as defined in paragraph 50.2 and as
specified in the license application, for those structures, systems, and
components to which this appendix applies are correctly translated into
specifications, drawings, procedures, and instructions. Also, design
control measures shall provide for verifying or checking the adequacy of
design, such as by the performance of design reviews.
9506050090 950519
ADOCK 05000255
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Contrary to the above, calculations EA-FC-954-02, "Low Pressure Suction
Trip on the Auxiliary Feedpump - Setpoint Change," and EA-C-PAL-95-
00538-01, Incorporation of a Higher Auxiliary Feedwater Pump Low Suction
Pressure Trip Setpoint into the T-2/T-81 Inventory Calculations Using
the RE.TRAN Program, did not adequately consider the design basis
condition for temperature. These calculations were part of Facility
Change (FC}, FC-954, Change P-88 Control From CV-0521 to CV-0522A, which
had been reviewed and was approved for installation on March 14, 1995.
(255/95004-02(DRS))
This is a Severity level IV violation (Supplement I).
3.
ImplemeRting license Condition No. 3.F to Facility Operating license No.
DPR-20 requires that the licensee maintain in effect and fully implement
all provisions of the physical security plan, including amendments and
changes made pursuant to authority of 10 CFR 50.54(p).
, Section 1.3.1 of the approved Palisades Security Plan requires, in part
that the licensee meet the requirements of 10 CFR 73.56, "Personnel
Access Authorization Requirements for Nuclear Power Plants" and
Regulatory Guide 5.66, June 1991, "Access Authorization Program for
Nuclear Power Plants". Palisades Nuclear Plant Policy/Procedure 1982-6,
titled "Atypical Behavior" requires, in part, that the employees are
required to report any observed atypical conduct to the Site Security
Manager.
Threats against personnel are an example of a reportable
atypical behavior.
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Contrary to the above, in July 1994, a physical altercation between a
security officer and a security supervisor was witnessed by numerous
security personnel and was not reported.* The altercation demonstrated
atypi~al behavior.
(255/95004-05(DRSS))
This is a Severity level IV violation (Supplement III).
Regarding violation number 3, the inspection showed that ~teps had been taken
to correct the identified violation and to prevent recurrence. Consequently,
no reply to the violation is required and we have no furthe~ questions
regarding this matter.
Regarding violations 1 and 2, pursuant to the provisions df 10 CFR 2.201,
Consumers Power 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.
Your
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response may reference or include previously docketed correspondence, if the
correspondence adequately addresses the required response.
If an adequate
reply is not received within the time specified in this Notice, an order or a
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 proper
should not be taken.
Where good cause is shown, consideration will be given
to extending the response time.
Dated at Lisle, Illinois this
19 day of May 1995 .