IR 05000369/1978042
| ML19273B168 | |
| Person / Time | |
|---|---|
| Site: | McGuire  |
| Issue date: | 12/26/1978 |
| From: | Cottle W, Robert Lewis NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19273B150 | List: |
| References | |
| 50-369-78-42, NUDOCS 7902060433 | |
| Download: ML19273B168 (7) | |
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9.... gs Report No.:
50-369/78-42 Docket No.:
50-369 License No.:
CPPR-83 Licensee: Duke Power Company Post Office Box 33189 422 South Church Street Charlotte, North Carolina 28242 Facility Name:
McGuire Nuclear Station Inspection at:
McGuire Site, Cornelius, North Carolina and Corporate Of fice, Charlotte, North Carolina Inspection conducted:
December 5-8, 1978 Inspector:
W. T. Cottle Accompanying Personnel: None Approved by:
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R. C. Lewis, Chief Date Reactor Projects Section No. 2 Reactor Operations and Nuclear Support Branch Inspection Summary Inspection on December 5-8, 1978:
(Report No. 50-369/78-42)
Areas Inspected:
Routine, unannounced inspection of readiness of facility for operating License issuance; followup on outstanding items; and review of station emergency procedures. The inspection involved 37 inspector-hours onsite by one NRC inspector.
Results: Of the three areas inspected, no items of noncompliance or deviations were found in two areas; one apparent item of noncompliance was found in one area (infraction - failure to implement requirements of housekeeping and cleanliness procedure paragraph 7).
79020604355
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RII Rpt. No. 50-369/78-42 I-1 DETAILS I Prepared by:
awg y o<c ayg W. T. Cottle, Reactor Inspector Date Reactor Projects Section No. 2 Reactor Operations and Nuclear Support Branch Dates of Inspection: December 3-8, 1978 Reviewed by: [. C.
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/2/tt,/7g R. C. Ledis, Chief Date
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Reactor Projects section No. 2 Reactor Operations and Nuclear Support Branch 1.
Persons Contacted Duke Power Company
- T. McConnell, Superintendent of Technical Services
- M. Sample, Technical Services Engineer G. Gilbert, Operating Engineer D. Simmons, Assistant Engineer
- D. Harrington, Training and Safety Coordinator
- R. Rider, Mechanical Maintenance Engineer D. Marquis, Assistant Engineer M. Kitlan, Assistant Engineer
- A. Figuaroa, Maintenance Engineer, Planning R. Lumadue, Manager, Management Information Systems G. Copp, Nuclear Engineer
- G. Cox, Senior QA Engineer W. Foley, Principal Engineer T. Harro11, Assistant Design Engineer D. Sweat, Technical Specialist R. Pace, Design Engineer The inspector also interviewed several other licensee employees including maintenance and operations personnel.
- Present during the Exit Interview on December 8, 1978.
2.
Licensee Action on Previous Inspection Findings Not Inspected
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RII Rpt. No. 50-369/78-42 I-2 3.
Unresolved Items No new unresolved items were identified.
4.
Management Interview A meeting was held at the conclusion of the inspection on December 8, 1978, with the Acting Station Manager and members of his staf f as denoted in paragraph 1.
The inspector summarized the secpe and findings of the inspection including the apparent item of noncompliance.
The Acting Station Manager acknowledged the apparent noncompliance and indicated that corrective actions were in progress.
5.
Facility Readiness for Issuance of an Operating Licensee The inspector reviewed the status of the following activities with licensee personnel:
Completion of preoperational test program.
a.
b.
Development of startup test procedures.
c.
Identification and correction of system performance deficiencies.
d.
Prnvisional system turnovers to Steam Production Department.
Formal systs.u turnovers to Steam Production Department.
c.
f.
Identification and classification of construction punchlist items.
g.
Schedule of remaining activities prior to fuel load.
At the present time, licensee has not completed a listing of system perfo rmance discrepancies and plans for correction.
In addition, construction punchlist items have not been evaluated by the licensee for their potential effect on the safety of plant operation. The inspector reiterated the desirability of early identification and evaluation of these items in order to minimize any impact on the timely issuance of an operating license.
These areas will be reviewed on subsequent inspections until such time that a Region II finding that the facility is ready for issuance of an operating license is made.
No items of noncompliance or deviations were identifie.
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RII Rpt. No. 50-369/78-42 I-3 6.
Independent Inspection Effort The inspector reviewed the station emergency procedures for Steam Generator Tube Failure, EP/0/A/5000/04, and Loss of Reactor Coolant Flow, EP/0/A/
5000/08.
The inspector pointed out that EP/0/A/5000/08 will require revision to conform to the anticipated operating license restrictica on operation with less than four reactor coolant system loops in service.
The inspector's other comments on these procedures will be coordinated with the overall McGuire procedure review effort.
The inspector toured the Auxiliary Building and Turbine Building to observe construction and testing activities in progress.
No items of noncompliance or deviations were identified.
7.
Implementation of Housekeeping and Cleanliness Controls Region II Report 50-369/78-12 discussed the equipment protection and cleanlincss controls in effect to insure maintenance of system clean-liness. The inspector reviewed the requirements of Station Directive 3.11.0, Housekeeping and Cleanliness, with licensee representatives.
The implementation of the requirements of Station Directive 3.11.0 was reviewed during this inspection. The review consisted of a tour of all plant areas under the control of the Steam Production Department to inspect the housekeeping conditions and posting requirements in the areas; a review of QC cleanliness inspection documentation for these areas; and a review of maintenance performed on the reactor coolant system for cleanliness requirements.
Contrary to the requirements of Station Directive 3.11.0, the inspector found:
The Auxiliary Building Essential Battery Rooms have not been posted a.
as a Level IV cleanliness area.
b.
The Auxiliary Building EssentialBattery Fooms have not been inspected as a Level IV cleanliness area since their provisional acceptance by the Steam Production Department in February 1977.
c.
The reactor vessel head was removed, stored and replaced under maintenance work request OPS-12401 with no provisions made to establish a Level I cleanliness area a round the reactor vessel during the time the head was remove RII Rpt. No. 50-369/78-42 I-4 The above examples are in apparent noncompliance with 10CFR 50, Appendix B, Criterion V, which requires that activities affecting quality shall be prescribed by documented procedures and shall be accomplished in accordance with these procedures.
This item is designated as an inf raction (369/78-42-01).
The outstanding item identified in Region II Report 50-369/78-12 concerning verification of equipment protection and cleanliness controls (369/78-12-02) is closed.
8.
Followup on Outstanding Items a.
Region II Report 50-369/78-05 discussed the control of temporary modifications, jumpers and bypasses.
Documentation of jumper installation and functional testing subsequent to jumper removal was identified as an open item (369/78-05-01).
The inspector reviewed a draft Station Directive 4.4.1, Processing Nuclear Station Modifications, which will be implemented at the time of operating license issuance. This directive states that any temporary design changes, such as electrical jumpers and blank flanges not covered by station procedures, shall be considered as a station modification. The directive also requires that all station modifications be implemented by utilization of the station maintenance work request system.
The controlling procedures for station work requests, Maintenance Management Procedures (MMP's) 1.0 and 3.0, appear to contain adequate provisions for release by operations, retest and functional verification, and completion of operational verification.
The collectito requirements of Station Directive 4.4.1, MMP 1.0, and MMP 3.0 appear to be adequate to insure that those jumpers treated as a station modification meet the require-ments of ANS N18.7-1972 that " jumpers be controlled".
The licensee made a commitment that any jumpers installed on operable safety-related equipment will be handled as described above.
Jumpers may be installed on inoperable equipment per station procedures but their installation, removal and subsequent functional testing will be in accordance with the provisions of MMP 1.0 and 3.0.
This item will remain open pending issuance of Station Directive 4.4.1.
b.
Region II Report 50-369/78-12 identified the review of the procedure for calibrating test and measuring instruments as an open item (369/78-12-01).
RII Rpt. No. 50-369/78-42 I-5 The inspector reviewed Station Directive 2.3.0, Control of Measuring and Test Equipment, against the p rovisions of the Duke Quality Assurance Program Topical Report and the Administrative Policy Manual, Section 2.3.
The Station Directive did not contain adequate guidance to insure that requirements 17.2.12(j ) and 17.2.12(e) of the QA Topical Report would be met. However, the station procedure for test equipment calibration, IP/0/B/3090/01 CN-5, did incorporate these requirements from the QA Topical Report. Licensee represen-tatives agreed to revise Station Directive 2.3.0 to reflect the requirements of the QA Topical Report.
This item will remain open pending the revi.; ion of Station Directive 2.3.0.
c.
Region II Report 50-369/78-16 discussed pending modifications to the Upper Head Injection and Auxiliary Feedwater Systems.
These were identified as open items (369/78-16-06 and 369/78-16-07).
The inspector discussed the status of these modifications and the provisions for testing with the engineers in charge of each of the systems. The modification to the Upper Head Injection System has been completed.
Test data evaluation is being performed by the Westinghouse System Design Group.
A supplemental construction deficiency report will be submitted when the test analysis is completed. The modification to the Auxiliary Feedwater System has been completed.
The inspector reviewed the provisions for testing in TP/1/A/1250/04.
The inspector had no further questions on either modification.
The: items are closed.
d.
Region II Reports 50-369/78-16 and 50-369/78-30 discussed the preoperational test program for the pressurizer safety valves, turbine control valves, and expansion / restraint testing for the main steam system.
The expansion / restraint testing of the main steam system was identified as an open item (369/78-16-03).
The inspector reviewed test procedure TP/1/A/1150/08, Thermal Expansion Testing on ASME Code Piping.
The procedure requires expansion and restraint testing on the main steam system during hot functional testing.
This item is closed.
e.
Region II Report 50-369/78-32 identified four open items concerning environmental qualification of electrical equipmen.
RII Rpt. No. 50-369/78-42 I-6 Item 369/78-32-01 concerned the review of reference material in IE Circular 78-08 by the licensee. The inspector reviewed a memorandum from Duke Design Engineering dated October 16, 1978, which documented their review of all reference attachments of IE Circular 78-08.
This item is closed.
Item 369/78-32-02 concerned licensee's committment to insure adequate environmental qualifications of all stem mounted limit switches covered by construction deficiency report 369/370-77-8.
Licensee has decided to replace all of the subject limit switches with appropriately qualified switches. Replacement is approximately 75% complete.
Lic-nsee representatives committed to submitting a supplementary construction deficiency report outlining their actions and plans for completion.
This item is closed.
Item 369/78-32-03 concerned licensee's submission of cable splicing qualifications. The inspector reviewed the licensee's transmittal letter dated October 5,1978, submitting the required information to the Office of Nuclear Reactor Regulation.
Supplemental submittals will be made in the first quarter of 1979.
This item is closed.
Item 369/78-32-04 concerned the environmental qualification of Barton transmitters.
The inspector reviewed the Westinghouse submittal to NRR dated September 29, 1978, which covered the type 763 and 764 Barton transmitters used at McGuire.
This item is closed.
f.
The following items were reviewed by the inspector and remain open:
Item 369/78-16-04
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Control method for insuring performance of chemistry analyses during startup testing.
Item 369/78-21-02
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Procedure for water inventory management during conduct of TP/1/A/1200/03C.
Item 369/78-28-02
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Meeting frequency of NSRB.
Item 369/78-28-03 Methods for insuring review requirements
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by on-site and of f-site review groups.