IR 05000369/1979001
| ML19270F696 | |
| Person / Time | |
|---|---|
| Site: | McGuire  |
| Issue date: | 01/24/1979 |
| From: | Burnett P, Dyer J, Martin R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19270F693 | List: |
| References | |
| 50-369-79-01, 50-369-79-1, NUDOCS 7903080566 | |
| Download: ML19270F696 (6) | |
Text
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Report No.: 50-369/79-01 Licensee: Duke Power Company P. O. Box 33189 422 South Church Street Charlotte, North Carolina 28242 lacility Name: McGuire Nuclear Station Docket No.: 50-369 License No.:
CPPR-83 Inspection at Lake Norman, North Carolina Inspectors:
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P. T. Burnett
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H. L. Whitener p
Bate Tigrfed Accompanying Personne b R. C. Sauer
//2V/J7 Approved by:
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R. D.
a tin, Section Chief, RONS Branch
/Date'Sig6ed SUMMARY Inspection on January 2-5, 1979 Areas Inspected This routine unannounced inspection involved 60 inspector-hours onsite. The activities and subject areas inspected were the thermal expansion test, vibration testing, the hot functional test and preparation of procedure : for initial fuel loading and subsequent core performance tests. Licensee actions on previously identified items were reviewed.
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Results Of the. t areas inspected, no apparent items of noncompliance or deviations were identified.
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RII Rpt. No. 50-369/79-01-1-REPORT DETAILS 1.
Persons Contacted Licensee Employees M. D. McIntosh, Station Manager
- D. J. Rains, Superintendent of Maintenance
- M. Sample, Technical Services Engineer
- L. E. Weaver, Performance Engineer
- B. Hamilton, Reactor Engineer
- M. Pacetti, Test Engineer
- G. J. Pollack, Duke Licensing
- K. Seidle, Design Engineering
- W. O. Henry, QA Manager-Construction
- G. Miller, Sr. QA Engineer-Construction
- G. P.obinson, QA Engineer
- J. W. Cox, McGuire QA
- H. H. Wallace, Construction Mechanical Engineer A. Sudduth, Assistant Engineer H. Pham, Assistant Engineer R. White, Associate Engineer
- T. R. Meadows, Jr. Engineer
- Attended exit interview on January 5,1979.
2.
Licensee Action on Previous Inspection Findings Not addressed.
3.
Unresolved Items None 4.
Exit Interview The inspection scope and findings were summarized on January 5,1979, with those persons indicated by an asterisk in Paragraph I above.
Mr. D. J. Rains acted for the station ranager during this meeting.
5.
Thermal Expansion and Vibration Preoperational Tests
Inspection was perf ormed to verify that the commitments identified in FSAR Sections 14, Table 14.1.3-1 (pg 25),
3.9.1.1, 3.9.1.2 and supplements Q413.16 and Q413.23 have been incorpora ted into the
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RII Rpt. No. 50-369/79-01-2-preoperational testing procedures being implemented during hot functional testing.
a.
Thermal Expansion Test (1) Procedure Review Draft procedures TP/1/A/1150/07, Reactor Coolant System Thermal Expansion and Restraint Test, and TP/1/A/1150/08, Thermal Expansion Testing on ASME Code Piping, were reviewed in the IE Region II office. Comments on these procedures were discussed and resolved with licensee personnel by telephone on November 29, 1978.
The inspector confirmed that the final procedures incorporate, as appropriate, the following commitments:
Visual inspection of piping and support and restraint
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systems at each plateau.
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Temperature plateaus at ambient, 250, 350, 450 and 557 degrees F.
Recording adjustable hanger setpoints at ambient. 350
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and 557 degrees F.
Comparison of adj ustable hanger setpoints with
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predicted, hot, no-load movement to verify piping movement is within design limits.
One system (auxiliary feedwater lines) not identified in the procedure was discussed with the licensee and will be included in the inspections.
The inspector had no further questions on these procedures at this time.
(2) 'iest Results Due to a delay in system heatup, test data were available for only the ambient (130 F) and 250 F plateaus. Review of a por ;on of these data indicate that adjustable hanger cold setpoints were verified at ambient (130 F) temperature and
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that a number of potential interference points (insulation object) have been identified and will be touching some watched during the heatup.
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e RII Rpt. No. 50-369/79-01-3-During a tour of the containment building the inspector observed some of the installed measurement probes on the reactor coolant system and a number of hangers and restraints.
Some points of potential interference were discussed with the test engineer. He stated that the piping systems are being visually inspected at each plateau and should actual interference occur, the heatup will be stopped until evaluation and corrective action can be performed.
b.
Vibration Testing The inspector reviewed TP/1/A/1200/21, Piping System Operation Vibration Measurement, and discussed the basis for the acceptance criteria with the test engineer. The criteria of 1.88 inches /sec peak (unfiltered) for stainless steel piping and 0.942 inches /sec peak (unfiltered) for carbon steel piping were obtained from displacement versus frequency data based on fatigue limits from Section III of the AS!!E Code rather than overstress f ailure limits.
The inspector e::amined the data on containment spray system and found that marked-up system drawings show the piping to be inspected, the location.of measurement points, and the measured values. In that hot-flow conditions have not been obtained, the bulk of the vibration testing has not been performed at this time.
6.
Hot Functional Testing a.
The inspectors conducted extensive tours of Unit No. 1; especially those areas affected by hot functional testing. Areas of concern observed were resolved by discussions with test and operations personnel.
b.
The following test procedures were reviewed to verify that testing, up to and including the 250 F plateau, was being ccnducted using approved procedae s and that changes to these procedures were in accordance with Station Directive 4.2.1:
(1) TP/1/A/1100/01 Controlling Procedure for Hot Functional Testing (2) TP/1/A/1200/02 Residual Heat Removal Test
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RII Rpt. No. 50-369/79-01
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7.
Procedure Review The following draft procedures were reviewed on-site and discussed with cognizant station personnel:
a.
TP/1/A/2650/01, " Initial Fuel Loading" b.
TP/1/A/2650/02, " Initial Criticality" c.
TP/1/A/2100/02, "Zero Power Physics Controlling Procedures" d.
TP/1/A/2150/03, " Boron Endpoint Measurements" e.
TP/1/A/2150/04, " Power Coefficient and Power Defect Measurement" Once these and similar procedures related to core performance testing are approved by station management they will be reviewed further.
8.
Followup Items A number of items were discussed with the licensee during a previous inspection (IE Report No. 50-369/78-35) and identified for further inspection. The status of these items was reviewed as follows:
a.
Identification of Seal Material (Item No. 369/78-35-01)
The licensee will obtain certification of the type of seal material used in the hydraulic shock suppressors from the vendor.
This item remains open.
b.
Acceptance Criteria For Lockup Velocity and Bleed Rate TItem No. 369/78-35-02)
The licensee is still in the process of obtaining the technical data to establish the criteria. This item remains open.
c.
Snubber Calibration (Item No. 369/78-35-03)
The licensee is in the process of obtaining test specifications and certification of testing from the vendor for snubbers not tested by Duke Power Company. This item remains open.
d.
Field Cuts and Welding (Item No. 369/78-35-04)
Field cuts and welding of snubber extension rods during fitup was reviewed with cognizant IE construction specialists. This item
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RII Rpt. No. 50-369/79-01-5-e.
Inaccessible Snubbers (Item No. 369/78-35-05)
Walk down and inspection of systems for hot functional testing indicate that snubbers the.ght to be physically inaccessible can be reached at cold conditions but may be inaccessible at hot standby or subsequent to the build up of radiation due to operation. This matter will be reviewed as part of the IE routine snubber inspection program and is considered closed.
f.
Snubber Installation (Item No. 369/78-35-06)
The licensee is in the process of revising the QC snubber inspection procedure to include the required acceptance criteria.
A QC inspection of all safety-related snubbers and hangers will be performed prior to final system turnover to the Steam Production Department. This item remains open.
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