ML18079A571
| ML18079A571 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 04/05/1979 |
| From: | Ebneter S, Finkel A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML18079A569 | List: |
| References | |
| 50-311-79-12, NUDOCS 7907230023 | |
| Download: ML18079A571 (5) | |
See also: IR 05000311/1979012
Text
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U.S. NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
.port No.
50-311/79-12-
50-311
Region I
Docket No. ------
License No.
CPPR-53
Priority ------
- licensee: Public Service Electric and G~s Company
80 Park Place
Newark, New Jersey 07101
Facility Name:
Salem Nuclear Generating Station, Unit 2
Inspection at: Hancocks Bridge, New Jersey
Inspection conducted:
February 13-14, 1979
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- inspectors:
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.
A. E. Finkel, Reactor Inspector
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Approved by: . _5_* ........
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S. o: Ebneter, Chief, Engineering Support
Section No. 2, RC&ES Branch
Inspection Summary:
Category ___ B ___ _
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date s'i g ned
date signed
date signed
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7date signed
Inspection on February 13-14, 1979 (Report No. 50-311/79-12)
Areas Inspected:
Routine, unannounced inspection by a regional based inspector.
The inspection consisted of the review of the radiation monitoring system instal-
lation and safety-related cable and tray installation. The ,inspection involved
13 inspector-hours ,on site by one NRC regional based inspector *. ** .. - <-~>::. * -, .. -
_
Re'sults: Of t_he,~w~ ar_el1~_ 1n~pe~ted, ng *1J~ni$,Qf nqncq111pliance* wet~: ideritifjed~*-,.:
in ~n~ area ;_:_,one apparerrt"'item-*of *noncomplfance wa's *ide'ntiffed* fn "'one area*. (In~ -.:
.
fraction ~ failure to maintain 1nsta1 ted cable trays in accordance with procedures,
paragraph 2. a).
Region I Form 12
(Rev. April 77)
/ ..
DETAILS
1.
Persons Contacted
Public Service Gas and Electric Company.
P. Bailey, Electrical Field Engineer
- J. Brady, Electric Field Engineer
- S. Chawaga, Project Quality Contra l E_ng i neeri ng
- L. Corleto, Controls Engineer
- J. Destefano, Site Quality Engineer
R. Griffith, Site Quality Assurance Engineer
- E. Meyer, Project Quality Assurance Engineering
- D. Mclaughlin, Senior Construction Erigineer
United Engineering and Construction, Incorporated
- R. Cheyne, Project Superintendent
W. Copeland, Quality Control Supervisor, Electrical I and C
- E. Walsh, Assistant Field Superintendent - QC
- denotes those present at the exit interview
- phone call from site to Newark, New Jersey
2.
Radiation Monitoring System
The inspector reviewed the documentation and examined the installa-
tion of the Radiation Monitoring System equipment as listed below
in i terns (a ) and ( b ) :
a.
Documentation.
The insp~ctor examined the records associated
with the foll owi_ng radiation monitoring systems:
- * Egu i pment No.
2RlA
2RlB
2R11A
2Rl2A
2Rl2B
2R21
2R41A
Name
Area Monitor
Process Monitor
Process Monitor
Process Monitor
Process Monitor
Area Monitor
Process Monitor
Location
Control Room
Control Room
Int~ke Duct
Containment Sampling
Particulate
Containment Sampling Noble
Gas
Containment Sampling Iodine
24
11 .Steam Generator Slowdown
Plant Vent Sampling
Particulate *
}.
2R41B
2R41C
.3
Process Monitor
Process Monitor
Plant Vent Sampling
Particulate
Plant Vent Sampling
Noble Gas
The records included factory acceptance test data, nondestructive
tests, certification of conformance, storage and maintenance
_records, installation inspection records, and data identifying
calibration data.
Reviewing the factory test data for the 2RlB, 2Rl3A, 2Rl3C and
2Rl5 monitor power supplies, the inspector determined the
power supply voltage position O for the above radiation monitors
was out of the specification voltage range on the high end of
the setting. .The range for the 0 setting was listed as +500
VOC to +1200 VOC +50 VOC. In the five monitors listed above,
all 0 setting for-the high end of the voltage range were over
+1500 VOC.
The licensee stated that the design of this setting
is being changed and a new voltage level will be established
by engineering for all radiation monitors listed on drawing
244150-A-1642-3.
This matter is considered to be unresolved and will be reviewed
by an NRC inspector during a subsequent inspection (311/79'.'"12-
01).
b. * *installation
The inspector examined the installation of the following
radiation monitoring equipment:
Radiation Monitoring Cabinet No. 236 A and B, drawing
242788-A- 1644.
The inspector examined and verified the
cabinet location, installation and the fire sealing of
the cables entering the cabinet.
The No. 235 cabinet was
installed in accordance with the engineering documentation *
and verified by quality control.
2RlA Area Control Room Monitor and 2R21 Area Containment
Post Accident Monitor equipments were not yet installed
in the control room panel nor was the 2R21B monitor or
2RlA monitor installed in its drawing location.
The
inspector did verify that the mounting locations were in
accordance with the drawings.
The installation and quality control inspection of the entire*
radiation monitor system has not progressed to the point where
complete system inspection can be performed by the licensee.
Therefore, the total system installation will be examined by .
an NRC inspector during a subsequent inspection.
,J;
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3.
Cable and Tray Installation
During a random inspection of safety-related cables and trays, the *
inspector identified the following safetyjrelated cable trays with
bent side rails and bent bottom cross bars in the south penetration
area of the Auxiliary Building.
Tray 2P027
Tray 2P066
Tray 2P037
\\
The licensee had identified Cable Tray 2P027 as having this problem
on Deficiency Report {DR) No. 4479, dated October 19, l.976.
The
tray was replaced May 1978 and the crafts were re-instructed as to
the requirements that safety related cable trays shall comply_with
and the DR closed on October 2, 1978. It appears that the replaced
. tray, 2P027 has been damaged to the same condition that originally
was identified iri DR No. 4479.
While the inspector was inspecting the trays in the south penetra-
tion area, elevation 78 feet, he observed craft personnel walking
on safety related cables in tray 2P037.
The craft supervisor was
informed of the problem and the craft personnel were taken off the
cable tray. The inspector also identified metal shavings on top of
and between cables in tray 2P027.
The licensee was informed by the inspector that positive corrective
action was required immediately due to additional potential damage
that may occur to installed safety-related cables and trays by
craft personnel working in the area during painting and cleanup,
that is presently being performed at Salem Unit 2.*
The licensee's Detail Construction Procedure (DCP) 2205, dated
August 24, 1978, Revision 9, paragraphs 4.23 and 4.24, states in
part "No craft personnel shall walk in trays, except when abso-
lutely necessary to pull cable, and cable trays shall be maintained
free of debris, tonstruction materials, tools, etc."
The licensee's drawing number*2m~53!=i shows installed cable trays
with straight side rails and stra_ight bottom cross bars .
....
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The inspector informed the licensee that the conditions found in
the south penetration area are contrary to the licensee's construction
procedure 2205 and drawing number ~Q~52~, Appendix B, Criterion V,
which states: "Activities affecting quality shall be prescribed by
documented .*. procedures or drawings ..* and shall be accomplished
- in accordance with these. * . procedures or drawings **.
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This item is considered to be an Infraction (311/79-12-02).
4.
Unresolved Items
Unresolved items are matters about which. more information is required
- to ascertain whether they are acceptable items, items of noncompliance
or deviations.
An unresolved item disclosed during the inspection
is discussed in Paragraph 2.a.
5. * Exit Interview
The inspector met with licensee representatives (denoted in paragraph
1) at the conclusion of the inspection.
The inspector summarized
the purpose and scope of the findings.
The licensee acknowledged
the inspector's findings .