ML19289C331
| ML19289C331 | |
| Person / Time | |
|---|---|
| Site: | McGuire  |
| Issue date: | 12/06/1978 |
| From: | Long F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Parker W DUKE POWER CO. |
| Shared Package | |
| ML19289C330 | List: |
| References | |
| NUDOCS 7901120030 | |
| Download: ML19289C331 (2) | |
See also: IR 05000369/1978038
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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REGION Il
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101 MARIETTA STREET.N.W.
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DEC 6
1978
In Reply Refer To:
RII :kTC
50-369/78-38
Duke Power Company
Attn:
Mr. William O. Parker, Jr.
Vice President, Steam Production
P. O. Box 2178
422 South Church Street
Charlotte, North Carolina
28242
Gentlemen:
This refers to the inspection conducted by Mr. W. T. Cottle of this
office on November 13-17, 1978, of activities authorized by NRC
Construction Permit No. CPPR-83 for the McGuire Nuclear Station Unit 1
facility, and to the discussion of our findings held with Mr. M. McIntosh
at the conclusion of the inspection.
Areas examined during the inspection and our findings are discussed in
the enclosed inspection report.
Within these areas, the inspection
consisted of selective examinations of procedures and representative
records, interviews with personnel, at ' observations by the inspectors.
Within the scope of this inspection, no items of nonccmpliance were
disclosed.
In accordance with Section 2.790 of the NRC's " Rules of Practice",
Part 2, Title 10, Code of Federal Regulations, a copy of this letter
and the enclosed inspection report will be placed in the NRC's Public
Document Room.
If this report contains any information that you (or
your contractor) believe to be proprietary, it is necessary that you
make a written application within 20 days to this office to withhold
such information from public disclosure. Any such application must
include a full statement of the reasons on the basis of which it is
claimed that the information is proprietary, and should be prepared
so that proprietary information identified in the application is
contained in a separate part of the document.
If we do not hear
from you in this regard within the specified period, the report
will be placed in the Public Document Room.
790112003c
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RII Rpt. No. 50-369/78-38
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DETAILS I
Prepared by:
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W. T. Cottle, Reactor Inspector
Date
Reactor Projects Section No. 2
Reactor Operations and Nuclear
Support Branch
Dates of Inspection: November 13-17, 1978
Reviewed by:
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R. C. Lew'is , Chie f
Date
Reactor Projects Section No. 2
Reactor Operations and Nuclear
Support Branch
1.
Persons Contacted
- M. McIntosh, Station Manager
- D. Rains, Superintendent of Maintenance
- M.
Pacetti, Test Engineer
- M. Sample, Technical Services Engineer
- G. Pollak, Project and Licensing Engineer
- A. Cox, Senior QA Engineer
G. Cage, Superintendent of Operations
G. Gilbert, Operating Engineer
The inspector also held discussions with several other operations, health
pbysics and technical support personnel.
- Present at the exit interview on November 17, 1978.
2.
Licensee Action On Previous Inspection Findings
Not inspected.
3.
Unresolved Items
.
No new unresolved items were identified.
4.
Management Interview
A meeting was held at the concJusion of the inspection on November 17,
1978, with the Station Manager and members of his staff as denoted in
paragraph 1.
The scope and findings of the inspection were summarized
by the inspector.
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.
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RII Rpt. No. 50-369/78-38
I-2
The inspector also attended the exit inte rview held on November 15,
1978, by the QA Preoperational Audit Team with the Station Manager,
members of his staf f, and corporate QA representatives. Details of the
QA Preoperational Audit findings will be covered in Region II Report
No. 50-369/78-39.
5.
Posting of Notices to Workers
The inspector reviewed licensee's posting of notices to workers against
the requirements of 10 CFR 19.11.
Licensee's postings appeared to be
adequate for the activities being conducted under the Part 30 and
Part 70 licenses. The inspector will review the postings with respect
to the activities to be conducted under the Part 50 license at the time
of issuance of the Part 50 license.
No items of noncompliance or
deviations were identified.
6.
Instructions to Workers
The inspector reviewed licensee's training program for providing
instructions to workers against the requirements of 10 CFR 19.12. Each
of the provisions of 10 CFR 19.12 appeared to be adequately addressed in
the video-tape training presentation. This training program along with
the physical security and emergency plan training programs are currently
under review by the licensee for any changes which might be necessary
due to revisions in the facility's radiation protection program, security
plan and emergency plan.
This review and any subsequent retraining
which might be required as a result of program changes will be completed
prior to fuel loading (369/78-38-07).
No items of noncompliance or deviations were identified.
7.
Facility Readiness for Operating License Issuance
The inspector conducted a detailed inspection of the containment spray,
auxilia ry feedwater, and upper head injection systems to compare the
as-built system configurations with the applicable FSAR system diagrams.
The inspector noted the following discrepancies between the existing
system configurations and the current revisions of the FSAR system
diagrams:
a.
Containment spray system valves INS 78 and INS 77 shown on FSAR
Figure 6.5.2-1 (Rev. 21) are not installed.
b.
Drain valves INS 101 and INS 102 installed on the containment spray
pump suction lines are not shown on FSAR Figure 6.5.2-1 (Rev. 21).
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RII Rpt. No. 50-369/78-38
I-3
c.
Containment recirculation sump screens and suction lines instal-
lation is not complete per FSAR Figure 6.3.2-4 (Rev. 21).
d.
Auxiliary feedwater syster, recirculation lines to upper surge tank
dome are not installed pe'J FSAR Figure 10.4.7-4 (Rev. 22).
The inspector reviewed as built system diagrams for the containment
spray and auxiliary feedwater systems which incorporated the changes
noted in items a, b, and d.
Licensee representatives stated that FSAR
system diagrams for all safety related systems would be updated to
reflect as-built conditions prior to operating license issuance.
Licensee's submittal of these updated FSAR system diagrams will be
verified by the inspector (369/78-38-08).
The completion of the containment recirculation sump screens and suction
lines will be verified in subsequent inspections (369/78-38-09).
No items of noncompliance or deviations were identified.
8.
Control of Temporary Modifications
During the verification of the upper head injection system as-built
configuration, the inspector noted three temporary modifications which
had been made to the system:
a.
Lifted leads on valves INI 242B, 244B, 243A, and 245A.
b.
Open terminal block links on level instruments 1 NILS 52 70, 5730,
5740 and 5750.
c.
Gas accumulator relief valve, INI 280, was removed and a manual
Kerotest valve installed.
.
Items a and b were found to be documented on work requests OPS 12497 and
PRF 0235 respectively.
The documentation was in apparent compliance
with the provisions of Station Directive 4.4.0 " Processing Design Changes"
Item c was found.to be a modification initiated by a construction test
group on a portion of the upper head injection system which had been
returned to the Construction Depart. ment on shutdown request SDR 572.
This modification will require documentation only if the modification
remains outstanding at the time that portion of the system is returned
to the Steam Production Department.
The inspector had no further
questions on this item.
No items of noncompliance or deviations were identified.
'
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RII Rpt. No. 50-369/78-38
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9.
Weldina on Pressurizer Surge Line
The inspec or followed up on a comment which had been made to a QA
Preoperational Audit Team inspector concerning the possible use of
carb.on steel weld rods on the pressurizer surge line. The inspector
interviewed three members of the permanent plant staff who had expressed
either an interest in or possible knowledge of the surge line welding.
One of the individuals interviewed stated that in a conversation with a
construction welder two years ago, the welder maintained that he had
performed welding on the pressurizer surge line utilizing carbon steel
weld rods. The individual could not identify the construction welder
with whom the conversation had taken place. The other two individuals
interviewed had no first hand knowledge. This itea vill be designated
as outstanding item 369/78-38-10, and will be followed up by a Region II
Construction Inspector.
No items of noncompliance or deviations were identified.
10.
Nuclear Service Water System
The inspector reviewed the design and operation of the nuclear service
water system for plant familarization. The review consisted of a study
of the FSAR system description, the McGuire training system description,
the main control board system layout, and discussions with control room
operations personnel. The inspector identified a potential problem in
that the system does not appear to meet the requirements of 10 CFR 50
Appendix A, Criterion 44, from the standpoint of being able to sustain a
single failure and still accomplish the system safety function. In the
case of a partial unit blackout (loss of one train of electrical power)
it appears that for some normal system lineups, immediate operator
action would be required to prevent an unrestorable loss of both trains
of nuclear service water, if a single active failure is assumed. The
inspector discussed a specific example of this type of system failure
with licensee representatives at the management interview. The Station
Manager agreed that a potential problem exists and has taken action to
initiate a design review of the nuclear service water system.
The
inspector informed licensee representatives that this item would be
referred ta NRC Headquarters for evaluation (369/78-38-11).