ML20062E366
| ML20062E366 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 10/31/1978 |
| From: | Johnson W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20062E358 | List: |
| References | |
| 50-285-78-13, NUDOCS 7812060351 | |
| Download: ML20062E366 (6) | |
See also: IR 05000285/1978013
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U. S. NUCLEAR REGULATORY C0911SSION
OFFICE OF IfiSPECTION AND ENFORCEMENT
REGION IV
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Report No. 50-285/78-13
Docket No. 50-285
License No. DPR-40
Licensee: Omaha Public Power District
1623 Harney Street
Omaha, Nebraska 68102
Facility Name:
Fort Calhoun Station, Unit 1
Inspection At: Fort Calhoun Station, Blair, Nebraska
Inspection Conducted: October 10-13, 1978
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Inspector:
//4Mjew
/C/*/78
Y.'D. gnson, Reactor Inspector
(Tate'
Approved By:
M. M
wh%
hhe/79
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G. L. Madsen, Chief, Reactor Operations and
Date
Nuclear Support Branch'
Inspection Summary
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Inspection on October 10-13,1978 (Report No. 50-285/78-13)
Areas Inspected: Routine, unannounced inspection of preparation for refuel-
ing; maintenance planning for refueling outage; and followup on open items,
unresolved items, licensee event reports, and items of noncompliance. The
inspection consisted of twenty (20) inspector-hours on-site and seven (7)
inspector-hours at the corporate office by one NRC inspector.
Results: Of the six areas inspected, no apparent items of noncompliance or
deviations were identified in five areas and one apparent item of noncom-
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pliance (infraction) was identified in one area (Failure to adhere to
procedures - paragraphs 5 and 6).
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DETAILS
1.
Persons Contacted
- R. L. Andrews, Plant Manager
J. L. C,anolley, I&C Engineer
L. J. Dugger, Reactor Engineer
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B. Eidem, Lead Mechanical Design Engineei-
J. J. Fisicaro, Supervisor, Administrative
F. F. Franco, Supervisor, Chemical & Radiation Control
J. F. Gass, Training Coordinator
W. G. Gates, Supervisor, Operations
J. M. Gloshen, QA Engineer
D. W. Jones, Supervisor, Maintenance
- W. C. Jones, Section Manager, Operations
8. Kellogg, Senior Engineer
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L. T. Kusek, Supervisor, Technical
M. M. McFadden, Plant Engineer
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R. F. Mehaffey, Electrical Engineer
G. R. Peterson, Supervisor, I&C and Electrical
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S. C. Stevens, Manager, Operations, Technical Support Services
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F. A. Thurtell, Division Manager of Environmental & Regulatory Affairs
D. D. Wittke, Manager, Generating Station Engineering
- Attended exit interview.
2.
Preparation for Refueling
The inspector reviewed Special Procedure SP-CR-1, Core Refueling
Procedure, Revision 2, dated October 12, 1977.
This procedure is in
the process of revision for the 1978 refueling outage. Licensee
representatives informed the inspector that no major changes to the
basic procedure, its prerequisites, initial conditions, or precautions
are expected. The inspector will review the revised core maps, fuel
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transfer operations sequence and spent fuel inspection sections during
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the next inspection.
No items of noncompliance or deviations were identified.
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3.
Maintenance (Refueling)
The inspector selected for review three major maintenance or modification
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activities scheduled to be completed during the refueling outage. The
first of these is designated as task RC-7G, Incore Detector Replace-
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ment.
For this task the inspector reviewed Maintenance Orde; 19674
and Special Procedure SP-IC-6, Revision 6, dated July ll,1978. The
second activity selected for review is a feedwater flow nozzel flange
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installation scheduled to be accomplished in accordance with DCR
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FC-77-101. The inspector reviewed this DCR package but the detailed
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work instructions and maintenance order were not yet availble for
review. The third activity selected was the valve block installation
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on charging pump CHIB. The maintenance order and work instructions
for this task were not yet available. The inspector will review these
during a future inspection and plans to witness one or more of these
maintenance activities to verify that the work is being accomplished in
accore- :e with approved procedures.
No items of noncompliance or deviations were identified.
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4.
Review of Licensee Event Reports (LER's)
Certain LER's were reviewed to ascertain that reporting requirements
were met, that appropriate corrective action was taken, that licensee
procedures were followed in their review and evaluation of the event,
and to determine the safety of continued operations.
The LER's listed
below were reviewed upon receipt in the regional office and followed up
on-site during this inspection:
LER No.
Subject
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77-19 and
Overstressed Pipe Column Type Supports
Supp. 1
78-16
Sequencer Timer Relay Failure
78-18
RCS Coldleg Temperature Indicator Failure-
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78-19
Amplitude Selector Module Failure
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78-20
Bistable Trip Unit Set Point Drift
78-23
Steam Generator Low Pressure Trip Channel A
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Set Point Drift
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78-25
Channel C Power Reading Low
78-26 and
RPS 18 Volt Power Supply Failure
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Rev. 1
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78-27
Sequencer Timer Relay Failure
78-28
Weather Tower Delta T Sensor System Failure
No items of noncompliance or deviations were identified.
5.
Followup on Open Items
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(Closed) Oper. Item 285/217 (paragraph 5.b Inspection Report 77-02):
Containment Spray System Nozzle Testing - The inspector reviewed the
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engineering calculations which formed the basis for licensee
memorandum TS-FC-78-356 during this inspection and had no further
questions.
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(0 pen) Open Item 285/227 (paragraph 6, Inspection Report 77-10):
Drawing Revisions - The inspector discussed the growing backlog of
pending requests for drawing revisions (RDR's) with a licensee repre-
sentative and was informed that District management is concerned with
this problem and is investigating several options for corrective
action.
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(Closed) Open Item 285/240 (paragraph 2.a. Inspection Report 77-21):
Key Control Procedure - The inspector reviewed Procedure Change 3695
to Standing Order 0-26 during this inspection and had no further
questions.
(Closed) Open Item 285/251 (paragraph 4, Inspection Report 77-11):
Azimuthal Power Tilt Limits - A licensee representative stated that
when the monthly recalibration of excore nuclear detectors to incore
detectors results in revised limits for indicated azimuthal power
tilt, these revised limits will be promptly entered into the Night
Order Book and posted on the physics log typewriter.
(Closed) Open Item 285/253 (paragraph 9, Inspection Report 77-11):
Emergency Procedure Revisions - The inspector reviewed Procedure
Change 3705 for Emergency Procedure 5, and Procedure Change 3706 for
Emergency Procedure 5.a and had no further questions.
(Closed) Open Item 285/254 (paragraph 3.b, Inspection Report 78-12):
Quality Assurance Audit Responses and Followup - Quality Assurance
Procedure (QAP) 17, Section 3.8.1, requires that management of the
audited organization or activity review and investigate any adverse
audit finding to determine and schedule appropriate corrective action,
including action to pr' event recurrence, and shall respond to the
report in writing within 30 days after receipt giving results of
the review and investigation. The inspector identified several
instances in which audit reports and deficiency reports had been
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issued for more than 30 days but no responses have been received
from the audited organization.
Examples are listed below.
Audit flo.
Report Date
Deficiency Report No.
4-78
2/28/78
FCl-78-A-005
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11-78
4/11/78
FCl-78-A-0019
21-78
6/7/78
FCl-78-A-0027
22-78
6/29/78
FCl-78-A-0030, FCl-78-A-0031,
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FCl-78-A-0033
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The licensee's failure to respond in writing within 30 days to audit
reports and deficiency reports is an apparent item of noncompliance
with Criterion V of 10 CFR 50, Appendix 8, as amplified by Sections
17.5 of the licensee's NRC approved QA program.
(0 pen) Open Item 285/244 (paragraph 6.e, Inspection Report 78-02):
Lack of an Administrative System to Assure Proper and Timely Revision
of plant Procedures in Response to Technical Specification and Design
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Changes - The inspector discussed this item with licensee represen-
tatives and was informed that a system is expected to be in
operation by November 1,1978.
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(0 pen) Open Item 285/249 (paragraph 4, Inspection Report 78-08):
Qualification Requirements for Personnel Conducting Containment
Structural Inspection - The inspector discussed Surveillance Test
ST-CONT-5-F.1 with licensee representatives and pointed out that this
procedure does not specify qualification requirements for the personnel
conducting the inspection. The inspector pointed out that Standing
Order G-26 requires that all quality control personnel designated as
inspectors will be certified as to their level of capability by the
Supervisor - Maintenance.
Licensee representatives agreed to further
consider this problem.
6.
Followup on Unresolved items
(0 pen) Unresolved Item (7706-2): Feedwater Flow Nozzles - DCR FC-77-101
has been prepared to install flanges so the feedwater flow nozzles
can be removed for inspection or calibration. The licensee expects
to complete this modification during the upcoming refueling outage.
(Closed) Unresolved Item (7812-1):
1977 Fuel Handling / Fuel Management
Audit - During Inspection 78-12, licensee representatives were unable
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to locate the audit plan and audit report for the fuel handling / fuel
management audit performed in 1977.
During this inspection, the
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inspector was informed that neither an audit plan nor an audit report
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had been prepared or issued for this audit. Quality Assurance
Procedure (QAP) 16 requires that an audit of fuel handling / fuel
management be performed annually during refueling periods. QAP 17
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provides instructions for the planning, perfomance and reporting
of QA audits conducted in support of the QA program for Fort Calhoun
Station, Unit 1.
Section 3.3 of this QAP requires that a formal audit
plan be issued for each audit.
Section 3.7 of this QAP requires that
a formal audit report be issued upon completion of each audit. The
licensee's failure to prepare and issue an audit plan and an audit
report for the fuel handling / fuel managenent internal audit perfomed
in 1977 is an apparent item of noncompliance with Criterion V of
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10 CFR 50, Appendix it, as amplified by Section 17.5 of the licensee's
NRC approved QA program.
This apparent item of noncompliance and the
one identified in paragraph 5 of this report will be treated as two
examples of a single item of noncompliance involving failure to
follow procedures.
7.
Followuo on Items of Noncompliance
(Closed) Noncompliance (Infraction 1.b Inspection 77-10):
Failure to File
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Completed Design Change Records in the Site Records Vault - The
inspector reviewed Procedure Change 3698 to Standing Order C-2 and
compared it with Revision 1 of Quality Assurance Procedure 7.
This
Procedure Change appears to resolve the conflict between the two
documents.
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(Closed) Noncompliance (Infraction 1, Inspection 78-04):
Failure to Perform
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and Document Liquid Penetrant Examination of Welds Performed Under
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DCR 77-84, SRDC0 77-23 - During this inspection the licensee con-
ducted the required training in procedure change procedures for
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quality assurance and quality control personnel and the inspector
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reviewed the documentation of this training.
(Closed) Noncompliance (Deficiency 2, Inspection 78-06):
Failure to Use
Required Sample size for Trisodium Phosphate Dodecahydrate Testing -
During this inspection the inspector reviewed Procedure Change 3699
to Surveillance Test STCHEM-2, which provides for recording the gross
weight of sample baskets and assures that the required sample size will
be used for testing.
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(Closed) Noncompliance (Infraction 4, Inspection 78-06):
Failure to Log
Required Parameters on Control Rcom Log Sheet when the plant Perfor-
mance Computer Log Typewriter was Inoperable - During this inspection
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the inspector reviewed Procedure Change 3697 to Standing Order 0-24
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and had no further questions.
8.
Followup on IE Circulars
The inspector verified that IE Circulars No. 78-13, 78-15 and 78-16
were received by licensee management, that they were reviewed for
applicability and that further action was taken or planned when
appropriate.
9.
Exit Interview
The inspector met with licensee representatives (denoted in paragraph
1) on October 13, 1978.
At this meeting the inspector sunmarized the
scope and findings of the inspection.
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