IR 05000315/1985003
| ML17326B181 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 01/24/1985 |
| From: | Hawkins F, Sutphin R, Westberg R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML17326B180 | List: |
| References | |
| 50-315-85-03, 50-315-85-3, 50-316-85-03, 50-316-85-3, NUDOCS 8502110287 | |
| Download: ML17326B181 (19) | |
Text
U. S.
NUCLEAR REGULATORY COMMISSION
REGION III
Reports No. 50-315/85-03(DRS);
50-316/85-03(DRS)
Docket Nos. 50-315; 50-316 Licensee:
American Electric Power Service Corporation 1 Riverside Plaza Columbus, OH 43216 Licenses No. DPR-58; DPR-74 Facility Name:
Donald C.
Cook Nuclear Power Station, Units 1 and
Inspection At:
Donald C.
Cook Station, Bridgeman, MI Inspection C
d ted:
nuary 7-11, 1985 Inspectors:
R. A. Hestber Approved By:
F.
C. Hawkins, Chief guality Assurance Programs Section ized 8<
Date
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Date Ins ection Summar Ins ection on Januar 7-11 1985 Re or ts No. 50-315/85-03 DRS; 50-316/84-03(D~RS
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f licensee action on previous inspection findings; calibration; gA program-annual review; tests and experiments; records; and onsite review committee program.
The inspection involved a total of 64 inspector-hours onsite.
Results:
In the six areas inspected, no items of noncompliance were identified.
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DETAILS Persons Contacted Indiana and Nichi an Electric Co~man (IEI1E~CO
"A. Blind, Technical Engineering Superintendent
- J. Stietzel, Quality Control Supervisor
- C. Miles, C81 Section Head P. Helms, CSI Production Supervisor G. Wallace, Performance Engineer S. Macey, Performance Engineer S.
DeLong, Instrument Maintenance Supervisor P. Leonard, Administrative Compliance Coordinator D. Malburg, Senior CSI Technician E. -Townley, Assistant Manager
- B. Svensson, Assistant Plant Manager W. Stoner, Technical Engineer N. Baker, Quality Control
- P. Jacques, Fire Protection Coordinator
- G. Griffin, Administrative Compliance Coordinator
- D. Yount, Accounting Supervisor American Electric Power Service Cor oration AEPSC
- T. Beilman, Quality Assurance Supervisor M. Horvath, Senior QA Auditor L. Castle, QA Auditor USNRC J. Heller, Resident Inspector Other personnel were contacted as a matter of routine during the inspection.
- Indicates those attending the exit meeting on January ll, 1985, at the D.
C.
Cook Station.
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Fidius (Closed)
Unresolved Item (315/84-16-03; 316/84-18-03):
Monthly report of overdue audit responses had not been issued for June and July, 1984.
The inspector reviewed Revision 8 to procedure No.
QAP 19 which deleted the requirement for monthly overdue response memoranda.
In addition, the problem of overdue responses is covered by procedure No.
QAP 38, "Quality Related Problem Escalation."
(Closed)
Open Item (315/84-16-05; 316/84-18-05):
Revision of procedure No.
PMI 2140.
The inspector reviewed Revision 5 to procedure No.
PMI 2140 and found it acceptabl ~
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Pro ram Areas Ins ected Details of the program areas inspected are documented in Sections I and II of this repor Section I
Pre ared B
R. A. Westber 1.
Calibration The inspector reviewed the calibration program to verify that the licensee had implemented a
gA program in this area that was in conformance with regulatory requirements and commitments.
The following items were considered during this review:
frequency of calibration, as specified in the technical specifications, for selected functional tests, channel calibrations, and instruments; completed test or calibration documentation; technical content of calibration procedures; calibration, control, and traceability of primary standards used in the calibration of plant instrumentation; qualifications of individuals performing calibrations; and calibration of components associated with safety-related systems or functions but not specified in the technical specifications as requiring calibration.
a ~
Documents Reviewed (1)
PMI-6030, "Instrument and Control; Maintenance and Calibration,"
Revision 3.
(2)
PNI-4030, "Surveillance Testing," Revision 7.
(3)
12THP6030IMP.045,
"Instrument Calibration System,"
Revision 1.
(4)
Technical Specification Requirements,
"Sorted Data Base,"
January 1985.
(5)
2THP6030INP.231,
"Power Range Nuclear Instrumentation Calibra-tion," Revision 5.
(6)
2THP6030IMP.226,
"Steam Pressure Protection Set III Calibration,"
Revision 5.
(7)
2THP4030STP. 100, "Reactor Protection and Engineered Safeguards System Time Response,"
Revision 5.
(8)
1THP4030STP.019,
"Steam Generator 1 5 2 Mismatch Protection Set I Surveillance Test," Revision 8.
(9)
1THP6030IMP.159,
"Boric Acid Tank Solution Level Indication Calibration," Revision 2.
(10)
1THP6030IMP.157,
"RWST Level Indication Calibration Train A Trip," Revision 1.
(11)
12THP6030IMP.056,
"Accumulator Level Loop Calibration Unit 1 or Unit 2," Revision W
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2THP4030STP. 127,
"Power Range Nuclear Instrumentation Protection Set 1 (N-41) Surveillance Test (monthly)," Revision 4.
b.
Results of Ins ection (2)
The inspector selected 12 channel calibrations and 12 functional tests from the reactor protection and emergency core cooling system instrument calibrations at random to verify that the frequency of calibration, as required by the D. C.
Cook Technical Specifications, was being accomplished on schedule.
This review was accomplished by using the nuclear technical specification schedule, which is a computer generated document that lists the calibration frequency, date scheduled, and the date the calibration or test was performed.
In addition, a similar review was performed on ll instrument calibrations selected at random from the following systems:
chemical volume control, component cooling, auxiliary feedwater, reactor coolant, safety injection, containment spray, and auxiliary power.
No items of noncompliance or deviations were identified.
The inspector reviewed four completed channel calibrations to verify completeness, meeting of acceptance criteria, and use of the proper revision of the calibration procedure.
In addition, the qualifications of two senior technicians who performed these calibrations were verified.
No items of noncompliance or deviations were identified.
The inspector examined the technical content of two channel calibration procedures, two functional test procedures, and one time response test procedure.
This examination consisted of a review of the following attributes:
reviews and approvals, controls to ensure LCOs are met, accuracy, tolerances and correction factors, documentation of as-found and as-left conditions, acceptance criteria within the technical specifica-tions, traceability of calibration equipment, control of return to service, and identification of the technician performing the calibration.
(4)
No items of noncompliance or deviations were identified.
The inspector selected four test and measuring devices used as primary standards in the calibrations referenced in paragraph 1.b.(2)
above to verify the following:
control in accordance with established procedures, calibration frequency was met, controlled storage and issuance, and accuracy traceable to the National Bureau of Standards.
No items of noncompliance or deviations were identifie v
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(5)
The inspector reviewed the D.
C Cook system for calibration of components associated with safety-related systems or functions but not specified in the technical specifications as requiring calibration.
The following components were selected for this review:
borated water storage tank temperature and level, safety injection accumulator level and nitrogen gas pressure, containment cooler water flow, and safety injection high head, medium head and low head discharge pressure.
The D.
C.
Cook calibration program was examined to ensure that there were reviewed and approved procedures available to calibrate these components and that the range and accuracy of these components was consistent with their application.
For all components, there were reviewed and approved calibration procedures available.
Three of these procedures were examined using the attributes previously described in paragraph I.b.(3).
In addition, completed calibration documentation was reviewed for completeness.
No items of noncompliance or deviations were identifie H, H
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Section II Pre ared B
R.
N. Sut hin 1.
Onsite Review Committee The inspector reviewed the Plant Nuclear Safety Review Committee (PNSRC)
activities to verify that the licensee had implemented a
gA program in this activity area that was in conformance with regulatory requirements and the Technical Specification commitments.
The following items were considered during this review:
composition of the PNSRC, designation of alternates, meeting frequency, quorum, responsibilities, authority, and records of results.
a.
Documents Reviewed (1)
PMI-1040, "Plant Nuclear Safety Review Committee," Revision 3, with Change Sheet No.
1 (CS-l).
(2)
Technical Specification, Section 6.5. 1, "Plant Nuclear Safety Review Committee (PNSRC)."
(3)
PNSRC Notice of Meeting and Agenda for January 8, 1985 - Meeting No.
1663.
(4)
PNSRC Minutes of Meeting No.
1663 - January 8, 1985.
(5)
PNSRC Minutes of Meetings No.
1467 through No.
1567 - January 3,
1984 through June 29, 1984.
(6)
PNSRC Subcommittee on Operations report of Meeting No. 84-16 on April 12, 1984, and No. 84-62 on December 26, 1984.
(7)
PNSRC Subcommittee on Audits report of Meeting No. 84-04-April 18, 1984.
(8)
PNSRC Subcommittee on Procedures reports - December 5, 12, and 26, 1984.
b.
Results of Ins ection The inspector attended a meeting of the PNSRC on January 8, 1985, to observe the conduct of the meeting and to ascertain that provisions of the Technical Specifications were satisfied.
This was meeting No.
1663 of the PNSRC.
A meeting of the PNSRC Subcommittee on Procedures was attended on January 9,
1984, to ascertain that the subcommittee met and conducted its activities in accordance with the require-ments of PMI-1040.
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The inspector found that the instructions included in PMI-1040 were generally followed for revisions to documents presented to the PNSRC for acceptance.
For other document changes, the minutes of the meetings and the attached information did not provide an adequate basis to conclude whether changes incorporated via the
"change sheet" involved an unreviewed safety question.
Pending further review, this is an unresolved item (315/85-03-01; 316/85-03-01).
2.
Tests and Ex eriments Pro ram The inspector reviewed the tests and experiments program, including the interface of this activity with the PNSRC, to verify that the licensee had implemented a
gA program in accordance with regulatory requirements and commitments.
a ~
Documents Reviewed (1)
PMI-1040, "Plant Nuclear Safety Review Committee," Revision 3, with Change Sheet No.
1 (CS-l).
(2)
PMI-2010, "Plant Manager and Department Head Instructions, Procedures and Associated Indexes,"
Revision 8, CS-1, CS-2, CS-3, CS-4 and CS-5.
(3)
2-THP-SP-066,
"Exxon Inspection and Testing of XN-1, 17 x 17, Irradiated Assemblies During Unit 2 Cycle 4-5 Refueling Outage,"
Revision 0.
(4)
I-THP-SP-067,
"Steam Generator Blowdown High Range Conductivity Measurement Circuit Special Test Procedure,"
Revision 0.
(5)
12-ODP-SP-RFC-2695 HT II," RFC-2695 - Fire Protection Piping Hydrostatic Test," Revision 0, CS-1.
(6)
12-ODP-SP-RFC-2695 IT," Fire Protection Piping Integrity Test,"
Revision 0, CS-1, CS-2, Temporary Change No.
3 (TP-3).
(7)
"Procedure for Implementation, Installation, and Testing of RFC-DC-01-1963," Revision 0.
(8)
12-THP-SP-070,
"Steam Generator Tube to Tubesheet Crevice Flushing," TP-l, TP-2.
(9)
2-THP-SP-074,
"Fuel Assembly Inspection Procedure Failed Fuel Rod Detection System," Revision 0, TP-1.
(10) 12-THP-SP-069,
"Incore Flux Thimble Conduit Vacuuming for Debris Removal," Revision 0, TP-1.
(11)
PNSRC Minutes of Meeting No.
1475, No. 1513, No. 1533, and No.
154 W W
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b.
Results of Ins ection The inspector verified that a formal method had been established and implemented to handle plant special tests and experiments involving safety-related components, systems and structures or modes of operation different from those described in the FSAR.
No items of noncompliance or deviations were identified.
3.
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The inspector reviewed the implementation of the licensee's records program to verify compliance with regulatory requirements, commitments, industry guides and standards.
Emphasis was directed to the records associated with the PNSRC (Plant Nuclear Safety Review Committee)
activities and the tests and experiments program.
a ~
Documents Reviewed (1)
PMI-2030, "Control of Information Resources, Document Control,"
Revision 3, CS-3.
(2)
PMI-2050, "Information and Records Center," Revision 2.
(3)
PMI-2040, "Plant Files," Revision 4.
(4)
12-0AP-2040-MPF.004,
"Receipt of Quality Assurance Records,"
Revision 0.
(5)
12-0AP-2040-MPF.005,
"Storage of Quality Assurance Records,"
Revision 1.
b.
(6)
Master File Procedures Index List, ADM 1, 8112. 1 Procedures.
Results of Ins ection The inspector reviewed the status of (1) the qu'ality control reference files, (2)
a sample of eight special procedures, (3) one master index list, (4) the commitments on storage of. radiographs and similar film records, and (5) the records and results of licensee responses to previous NRC inspection items.
The quality control department reference files used during the inspection were found to be in good order except for three minor items identified by the inspector.
They were promptly corrected by the licensee and reviewed at the exit meeting.
The inspector has no further questions regarding these files at this time.
llith two minor exceptions, the special procedures checked in the plant master file were found to be complete, correct and in accordance with the master file index.
Specifically, two SPs were found to be filed incorrectly.
A check against the master file index indicated that all
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documents required to be in the file were accounted for.
The inspector has no further questions regarding this matter at this time.
During review of the master file index, the inspector identified one item ( 12-THP-SP-075)
in the master file index which was not in the file.
Licensee personnel stated that the document had not been completed and turned over to the master files. It is expected to be completed in two or 3 months.
The inspector has no further questions on this item at this time.
In Section 4.2 of procedure
OAP 2040 MPF.005, Revision 1, ("Storage of guality Assurance Records,")
the licensee committed to the esta-blishment of limits for exposure of radiographs (and similar film records)
to light, humidity and temperature during storage.
During this inspection, the licensee was unable to locate their policy and guidelines for the implementation of this commitment.
This is considered an unresolved item (315/84-03-02; 316/85-03-02).
Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of noncompliance or deviations.
Unresolved items disclosed during the inspection are discussed in Section II.l.b and Section II.3.b.
Exit Interview
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The inspectors met with licensee representatives (denoted in the Persons Contacted paragraph)
at the site on January 11, 1985.
The inspectors discussed the purpose, scope and findings of the inspection.
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