ML18101A743
| ML18101A743 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 05/24/1995 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML18101A742 | List: |
| References | |
| 50-272-95-07, 50-272-95-7, 50-311-95-07, 50-311-95-7, NUDOCS 9506010119 | |
| Download: ML18101A743 (3) | |
See also: IR 05000323/2005006
Text
Enclosure 1
APPENDIX A
Public Service Electric and Gas Company
Salem Nuclear Generating Station
Docket Nos: 50-272; 50-311
Units 1 and 2
During an NRC inspection conducted on March 23, 1995 - May 6, 1995,
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.
Technical Specification 3.7.6 for Salem Unit 2 requires that control
room emergency air conditioning shall be operable in all modes with at
least two operable isolation dampers in each outside air intake duct.
The Tech~ical Specification 1.18 definition of operability requires
that, in order for a component to be considered capable of performing
its intended function, all auxiliary equipment that is required for the
component to perform its function is also capable of performing its
related support function.
The design of the control room emergency air
conditioning dampers requires that either radiation monitor 2R1A or 2R1B
be capable of initiating isolation of the dampers on high radiation in
the control room emergency air conditioning ventilation intake duct.
With no operable dampers, the licensee shall meet the requirements of
Technical Specification 3.0.3, which requires that the licensee shall
within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> take actions to place the unit in at least hot standby
within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, at least hot shutdown within the following 6
hours, and at least cold shutdown within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ..
Contrary to the above, from 9:20 a.m. on April 4, 1995, to 3:24 a.m. on
April 5, 1995, with Salem Unit 2 in mode 1, the licensee blocked
actuation of both 2R1A and 2R1B on high radiation in the control room
air conditioning ventilation intake duct rendering the isolation dampers
incapable of isolating on high radiation, and failed to take the actions
required by Technical Specification 3.0.3.
This is a Severity Level IV violation (Supplement I) .
9506010119 950524
ADOCK 05000272
G
I
2
B.
Technical Specification 6.8.1 requires, in part, that written procedures
be established, implemented and maintained covering the applicable
procedures recommended in Appendix "A" of Regulatory Guide 1.33,
Revision 2, February 1978.
Regulatory Guide 1.33 requires that
maintenance that can affect the performance of safety related equipment
be properly preplanned and performed in accordance with written
procedures, documented instructions, or drawings appropriate to the
circumstances.
Licensee Procedure NC.NA-AP.ZZ-0009, step 5.1.1.a
requires procedures to control safety related activities and maintenance
on security equipment, and step 5.7.1 requires that individuals perform
work in accordance with the established work package; and procedure
NC.NA-AP.ZZ-0023, Scaffolding and Transient Loads Control, provides
instructions for controlling the erection and storage of scaffolding in
safety related areas and requires that scaffolding in safety related
areas have adequate clearances, cross-braces, restraints, and variance
approval, and be removed in a timely manner following completion of
maintenance.
Contrary to the above:
On April 26, 1995, plant staff performed hot spot flushing which
affected the safety-related Refueling Water Storage Tank (RWST) and
safety injection system without a procedure to control the activity;
On May 4, 1995, plant staff performed work on the safety-related no. 23
service water pump without a procedure or a work package;
On April 18, a security guard corrected a malfunctioning security door
without a procedure or a work package;
On April 26,
scaffolding installed in the vicinity of the no. 11
auxiliary feedwater pump (AFP) and the room cooler for the Salem unit 1
motor-driven AFPs did not have the required clearance, cross-bracing,
restraints, or variance approval; and,
On May 1, scaffolding around the Salem Unit 2 containment fan cooler
unit service water piping was not removed in a timely manner following
completion of the work on January 25, 1995.
This is a Severity Level IV violation (Supplement I).
C.
10 CFR 50.59 requires that changes to the plant, as described in the
Updated Final Safety Analysis Report (UFSAR), be evaluated to determine
that they do not constitute an Unreviewed Safety Question (USQ), and
that records of changes must include a written safety evaluation which
provides the bases for the determination that the change does not
involve an USQ.
3
Contrary to the above:
A 10 CFR 50.59 applicability review, dated April 7, 1995, failed to
provide an adequate basis for the determination that a degraded 1A-
125VDC battery cell (no. 35) post seal did not constitute an Unresolved
Safety Question;
A Safety Evaluation, dated April 3, 1995, failed to provide the basis
for the determination that use of a Service Water Intake area exhaust
fan motor, used to replace a fan motor in the no. 22 RHR room cooler
unit did not constitute an Unreviewed Safety Question.
This is a Severity Level IV violation (Supplement I).
Pursuant to the provisions of 10 CFR 2.201, Public Service Electric and Gas
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 I, 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 response may reference or
include previous 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 .
DatedAa.}King of Prussia, Pennsylvania
this ~
day of May 1995