- _

/ 'o,, UNITED STATES

! NUCLEAR REGULATORY COMMISSIONo3 E REGION 11* *o 131 MARIETTA ST., N.W., SUITE 3100

ATLANTA, GEORGIA 30303o.....

Report No. 50-370/81-17

Licensee: Duke Power Company422 South Church StreetCharlotte, North Carolina 28242

Facility Name: McGuire

Docket No. 50-370

License No. CPPR-84

Inspection at McGu e site _near ChQtte, North Carolina

/Inspector:_s %~ n) /[ (

Nic E' ' .o p' ate Si,gnedA j |Approved by- J -- :^1 -

t, bection Chi - Date SignedEnginee ing Inspect a BranchEngineering and Te nnical Inspection Division

SUM, VARY

Inspection on September 15-18, 1981

Areas Inspected

This routine, unannounced inspection involved 39 inspector-hours on s1te in theareas of reactor coolant pressure boundary piping: work activities observation,QA record review reactor coolant pressure pipe welding; Reactor vessel internals,

| work observation, QA record review; Safety related components - observation of! work activities, QA record review; and folloup on licensee identified items.|

| Results

Of the six areas inspected, no violations or deviations were identified.

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REPORT DETAILS

1. Persons Contacted

Licensee Employees

*J. T. Moore, Asst. project Manager*J. W. Willis, Project QA Engineer*E. B. Miller, Sr. , QA EngineerM. S. Starnes, Sr. , Construction EngineerG. B. Robinson, QA Engineer Mechanical / WeldingW. M. Newton, Sr. , QA Tech. MechanicalJerry Goodman, QC Engineer MechanicalK. Davis, QC Technician Supervisor Mechanical

*W. R. Gillespie, Sr. QA Technician Welding

Other licensee employees contacted included four craf tsmen.

* Attended exit in+.erview

2. Exit Interviewi

The inspection scope and findings were summarized on September 18, 1981,with those persons indicated in paragraph 1 above.

3. Licensee Action on Previous Inspection Findings

Not inspected.. . _

4. Unresolved Items

Unresolved items are matters about which more information is required todetermine whether they are acceptable or may involve violations or devia-

i tions. New unresolved items identified during this inspection are discussedin paragraph 5.

, 5. Licensee Identified Items 50.55(e)I

a. (0 pen) Item 370/81-17-01: Rejectable Surface

Indications on Personnel Airlocks

On September 11, 1981 the licensee informed RII that certain unaccept-,

! ablo linear indications (3/4" long) had been identified in vendor weldsof the upper personnel airlocks. The airlocks were manufactured by

| W. J. Wooley Company. The inspector observed subject airlocks and the! indications in question. Nonconformance reports (NCIR(s)) 13075 and

13084 have been issued and repair work was expected to begin shortly.

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In discussing this matter with the licensee's QA representatives theinspector noted that while both NCIR's were issued early in April ofthis year, the engineering evaluation and subsequent' notification as apossible 50.55(e) item did not materialize until early September orfive months _ later. In response .to this observation, the licenseestated that a recent revision in the procedure for handling such itemshad created a backlog of unprocessed NCIR's and it was believed thesemay have been a part of that backlog. Moreover the licensee statedthis backlog has'now been cleared and assured the inspector that theirinvestigation showed this matter was an isolated case. The inspectorstated that RII supervision would be briefed on the delay and failureto report within the specified time limit. Accordingly, this matterwas identified as an unresolved item pending review of the licensee'sevaluation report and review of field repair records. Unresolved item370/81-17-01, "PT Indications on Personnel Airlock Welds."

6. Plant Tour

The-inspector conducted a general inspection of the auxiliary and reactorbuilding to interview craft and QC personnel and observe pipe handling,storage, installation and weld consumable control. General housekeeping andcleanliness in and around work / storage areas were observed.

7. Reactor Coolant Pressure Boundary Piping II - Observation of Work an'd WorkActivities

Piping activities are controlled by ASME Section III 1971 including Summerand Winter 1971 addenda together with applicable standards and QA approvedprocedures.

Several piping activities were selected, in order to test by direct observa-tion, evaluation of work performance, and record auditing whether workaccomplishment was in accordance with Code requirements and SAR commitments.Activities selected inci 'ded receipt inspection, storage, installation,identification and gene ; tion of pertinent quality records. ,The systems /components selected for this work effort were as follows:

Decay Heat (ND), (ISO-2ND-24)Valve: #2ND57 __ 3/4" Kerotest Globe S/N AEX1-10

FLANGES: #2NDFE-Ht #HJ3992ND24FL-1-Ht #B1476

90 Ell: 80" sch.20-Ht #RW-941835 on Weld # ND2FW24-2

Spools: 2NDP134-1-8"sch 40, Ht #80408492NDP135-1-8"sch 40, Ht #8040849

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Safety Injection (NI) (ISO-2NI-7,-12 and -181Valves: #2NI658-10" Walworth Gate,1500#, S/N C55198

#2NI173A-8" Walworth Gate,1500#, S/N C-55560

Reducer: #NI2F457-SN JBJZ 8" X 6"i-

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For the above items, within these systems and the indicated activities, theinspector verified that the followinhg requirements, as applicable had beenmet: QC inspections, record keeping, construction / installation testing,material issuance, utilization of qualified personnel. In addition theinspector selected at random four pipe runs between major components /loca-tions within the reactor coolant pressure boundary, and by observation anddrawing review ascertained whether field installation was consistent withapplicable drawing / specification requirements. The selected runs were asfollows:

Safety Injection (NI) - 1. Elevation 732'-6", weld(Dwgs MC-244-09.21-00 Rev. 7) #NI2F422 to Crane Wall

penetrationat 153

MC-244-09.21-01 Rev. 6) Elevation 734, ISO NI-12

- 2. Elevation 732.0" Weld#NI2FW57-2 to 90 Elbow to Pipeweld #NI2FW52-12

Chemical Volume Control (NV) (NV) - Fron penetration M347,(Dwg. #MC2414-22.43-00 Rev.14) Elev. 761'-6" to Elevation

755'-10 ".

Decay Heat (ND) - From weld 2NI173A at elevation(Dwg #MC-2414-04-4200) 736'1C" to Flange 2NDFE5180

elevation 741'-0"

Also from the aforementioned system the inspector picked at, random NDErecords (RT reader sheets and PT reports) related to pipe spools and com-ponents (valves) and radiographs of welds and reviewed them in order toascertain whether the following requirements had been met.

a. performance of prescribed NDEb. calibration and use of proper measuring and test equipmentc. qualification of NDE personnel

Selected components were identified earlier in this paragraph. Radiographsselected for review were as follows:i

WELD # SIZE SYSTEM

NI2F-418 8" X .906" Safety InjectionNI2F-420 8" X .906" Safety InjectionND2FW24-5 8" X .250" Decay HeatND2FW24-15 8" X .250" Decay Heat

Within the areas inspected no violation or deviations were identified.

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8. Safety Related Piping - Review of Quality Records

Records of QA/QC activities are controlled by requirements / codes identifiedin paragraph 7 above.

Hydrostatic testing of the safety injection system was performed underrequirements of the applicable code and procedures H-1 Revision 12 " PressureTesting" and CP-715 " Hydrostatic Test Procedure for Unit-2 Safety InjectionSystem," Section 6.16 Elevation 732' . The boundary of the tested pipesystem appeared on flow diagram #2562-2.0, Rev. 5. The inspector reviewedrelated records to ascertain whether pressures, temperature and time wereconsistant with code / specifications requirements. The test was conducted onMarch 6,1981 and the results accepted by the cognizant engineer on April 7,1981.

Within the areas inspected no violations or deviations were identified.

9. Reactor Coolant Pressure Boundary Piping (Welding) - Work Observation

At the time of this inspection, welding activity involvinc pressure boundarypiping included weld repair (s) and modifications. The latter involved 14"isolation valve No. 2ND1 which was being cut out and respositioned(turned 90 ). In addition certain pipe T(s) in the safety injection systemwere being cut out and repositicned. Welds invovled in this me>dificationwere as follows:

WELD # 150 SIZE

ND2F-1 2ND1 14" schedule 140NC2FW22-17 2NC22 14" schedule 140 "

NI2F533 2NI-17 10" dia. X 1" th.'ckNI2F534 2NI-17 10" dia. X 1" thickNI2F-477 2NI-15 6" dia X .719" thickNI2F-867 2NI-15 6" dia X .719" thickNI2F-2747 2NI-17 6" dia X .719 thick

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For these cuts, the inspector observed the cutting operation and reviewedrelated QC records / forms used to document the cutting, weld preparation,cleanliness and fabrication. The repair activity involved the BIT nozzle onthe cold leg of the reactor coolant (NC) loop C(3-5). At the time of thisinspection the joint had been cut, weld built-up and was undergoing grindingto remove a surface defect from the build-up weld metal prior to weldprepping. The inspector reviewed nonconformance item report (NCI) 13646Westinghouse (W) repair procedure FDR-DBPM which had been approved by DPC onSeptember 8,1981, liquid penetrant inspection reports, welder qualificationrecords and the applicable field weld data sh:et (L-231 Rev. 7). Filiermetal quality records, as well as weld cards (M-4A) and detail procedurecontrol sheet (F-9B) were reviewed for completeness and accuracy.

Within the areas inspected no violations or deviations were identified.

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10. Reactor Vessel Internals - Observation of Work Activities

At the time of this inspection the reactor vessel internals were assembledand stored inside the refueling canal area elevation 736', which has beendesignated storage level zone IV. Zone IV prohibits food, drink, etc.Inspection and storage requirements are etablished by DPC's- StorageInspection Procedure P-3 Rev. 12. The inspector observed stcrage conditionand reviewed storage inspection records.

Within the areas inspected no violation or deviations were identified.

11. Reactor Vessel Internals - Review of Quality Records

Reactor vessel internals quality records selected at random and other- '

records including receipt inspection and storage records were reviewed toascertain conformance with established procedures and to determine whetherwork accomplishment was consistent with applicable procedural requirements.Applicable procedures irmlude P-1, " Receipt Inspection" and P-3, " Storage".Receipt inspection was documented on form P-1A. Quality records revicwedincluded (W) quv11ty releases SQR-21631, 21033 and 21621.

Within the areas inspected no violation or deviations were identified.

12. Safety Related Components I-Review of Quality Records

Quality related work and inspection (QC) records of selected componentswithin and outside the pressure boundary were reviewed to ascertain whetherthese records were in conformance with established procedures and reflectedwork accomplishment consistent with applicable NRC and code requirements.The components selected were as follows:

COMPONENT SERIAL _ NUMBER

Safety Injection Tank 2B 41618-72-2

Boron Injection Tank #2 B01

Baron Injection 21411-4Recirculating Pump 2A

Valve (RC pump seal 5895260return isolation valve)-

2/NV/66A

For these components areas of specific interest included storage inspec-tions, installation inspections, material and fabrication certifications /test results. Nonconforming item reports 13248 and 12345 were reviewed forcompleteness, timeliness of disposition, accuracy and compliance with

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procedural requirements. Records of audits performed during the first andsecond quarters of 1981 and implemented under the requirements of p ocedureM-9 " Mechanical Installation Alignment", were reviewed to ascertain whetherthey reflected specified scope and frequency, thoroughness, timeliness ofcorrective action and ideatified deficiencies, followup on correctiveaction, repetitiveness of deficiencies and qualification of auditors.

Within the areas inspected no violations or deviations were identified.

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