IR 05000301/1979006

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IE Insp Rept 50-301/79-06 on 790402-03.No Noncompliance Noted.Major Areas Inspected:Preparation for Refueling Outage,Prefuel & Fuel Handling Activities & Maint During Refueling Outage
ML19246C564
Person / Time
Site: Point Beach NextEra Energy icon.png
Issue date: 05/04/1979
From: Little W, Menning J, Swanson E
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML19246C563 List:
References
50-301-79-06, 50-301-79-6, NUDOCS 7907260526
Download: ML19246C564 (5)


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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTICS AND ENFCRCEMENT

REGION III

Report No. 50-301/79-06 Docket No. 50-301 License No. DPR-27 Licensee: Wisconsin Electric Power Company 231 West Michigan Milwaukee, WI 53201 Facility Name: Point Beach Nuclear Plant, Unit 2 Inspection At: Point Beach Site, Two Creeks, Wisconsin Inspection Conducted: April 2-3, 1979 A

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. 2 C[. e Approved By:

W. S. Lit tfe. Chief

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Nuclear Eupport Se ction 2

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Insoection Sunnarv Inspection on April 2-3, 1979 (Recort No. 50-301/79-06)

Areas Inspected:

Routine, unannounced inspection of preparation for a refueling outage, pre-fuel handling activities, fuel handling activities, and maintenance during a refueling outage.

The inspec-tion involved 20 inspector hours onsite by two NRC inspectors and included inspection ef fort conducted during of fshif t hours.

Results: No items of noncompliance or deviations were identified.

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DETAILS 1.

Persons Contacted

  • C.

A. Reed, Manager, Nuclear Power Division

  • J.

Greenwood, Assistant to the Manager T. Deddens, Maintenance Superintendent J. Bauer, Technical Assistant

  • Denotes those present at the exit interview.

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2.

Preparation for Refueling The inspectors verified that approved procedures are avai-lable for new fuel receipt and inspection, fuel transfer and core verification, irradiated fuel inspections, and fuel sipping operations. The inspectors also verified that new fuel was received and inspected in accordance with the licensee's procedures.

The inspectors reviewed the following licensee procedures:

a.

RP-1A, Preparation for Refueling b.

RP-1B, Recovery from Refueling

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RP-1C, Refueling d.

RP-ID, Filling and Draining the Refueling Cavity e.

RP-2A, Receipt of New Fuel Assemblies f.

RP-23. Fuel Assembly Visual Inspection g.

RP-2C, New Fuel Inspection h.

RP-3A, Spent Fuel Inspection 1.

RP-33, Fuel Assembly Sipping The inspectors also reviewed fuel receiving and inspection records for the 36 new fuel assemblies to be inserted into the reactor core.

No items of noncompliance or deviations were identified.

3.

Pre-fuel Handling Activities The inspectors verified that surveillar.ce testing had been completed on Technical Specification requirements, refueling machine operation and indexing, ventilation requirements in fuel storage areas, refueling interlocks, crane testing, refueling deck radiation monitors, and com=unication systecs.

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The inspectors reviewed records for the following completed surveillance tests / checks:

a.

Refueling machine and interlock testing performed per ORT 15.

b.

RHR system testing performed per ORT 8.

c.

Refueling deck radiation monitor checks, fuel storage area ventilation checks, com=unciation checks, and containment ventilation and purge sytem checks performed per RP-IC.

No items of noncompliance or deviations were identified.

Fuel Handling Activities The inspectors verified by direct observations that core monitor-ing during refueling operations was in accordance with Technical Specifications, that containment integrity during refueling operations was in accordance with Technical Specifications, that fuel bundle insertion and re= oval were in accordance with established procedures, that fuel accountability methods were in accordance with established procedures, that core internals were stored to protect against damage, that housekeeping was proper, that primary coolant system boron concentration was consistent with the Technical Specification requirement, that the individual directing fuel handling activities held a senior operator license and was present, directly supervising activities, and that a licensed reactor operator was present in the control room and in constant direct co=munications with a member of the fuel handling crew when work was being performed that could affect the reactivity of the reactor.

No items of noncompliance or deviations were identified.

5.

Maintenance During Refueling The inspectors verified that maintenance activities conducted during the refueling outage were being conducted by qualified personnel in accordance with approved procedures.

They verified that the procedures written to control work activd-les contain administrative approvals for removing a system f rom service and returning it to service, provisions for inspection and signoff by licensee personnel, provisions for testing following maintenance, provisions for insuring proper fire protection

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precautions are utilized, provisions for review of mater-ials certification, provisions for assuring that LCO of Technical Specifications are satisfied, provisions assuring that system lineups are conducted prior to return to ser-vice, adequate jumper controls and provisions for reporting design or construction related deficiencies identified during maintenance.

The inspectors reviewed the following licensee procedures:

a.

PSNP 3.19, Maintenance Request 3 b.

PSNP 3.20, Instructions for Processing Modification Requests c.

P3NP 3.21, Daily and short term planning and approving of major and non-routine testing, operation and maintenance.

d.

PENP 3.22, Long Range Planning and Refueling Planning.

e.

P3NP 3.23.8, 10 CFR 21, Reporting of Defects and noncompliance.

f.

PI " 4.13 Equipment Isolation Procedure.

g.

PBNP 4.17, Lif ter wires, jumpers and bypasses.

h.

P3NP 5.1.1, Routine maintenance procedures.

1.

PBNP 5.1.2, Special Maintenance Proe,dures.

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PT-R-3, Hydraulic snubber inspection.

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PT-R-4, Testing of Prctective Relays.

1.

PT-R-1, Pressurizer Safety Valve.

The inspectors also witnessed maintenance work being per-formed per PT-R-1 on Pressurizer Saf ety Valves.

No items of nonco=pliance or deviations were identified.

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6.

Exit Interview The inspectors met with the licensee representatives (de-noted in Paragraph 1) at the conclusion of the inspection on April 3, 1979. The NRC principal inspector was also in attendance. The inspectors sut::marized the scope and findings of the inspection.

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