IR 05000416/1982059

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IE Insp Rept 50-416/82-59 on 820809-10.No Noncompliance Noted.Major Areas Inspected:Licensee Identified Items, Surveillance Testing,Lers,Plant Tour & Inspector Followup Items
ML20027B103
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 08/18/1982
From: Butcher R, Cantrell F
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20027B096 List:
References
50-416-82-59, NUDOCS 8209160372
Download: ML20027B103 (5)


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Report No. 50-416/82-59 i

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Licensee: Mississippi Power and Light Company

Jackson, MS Facility Name: Grand Gulf Docket No. 50-416

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l License No. NPF-13 i

Inspection at Grand Gulf near Port Gibson, Mississippi Inspector:

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R. Butcher Date Signed i

Approved by:

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F. 5. Cantrell, Sect ~ityf%hief, Division of Date Signed Project and Resident Programs SUMMARY Inspection on August 9 - August 10, 1982

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Areas Inspected This routine, unannounced inspection involved 15 inspector-hours on site in the areas of licensee identified items, surveillance testing, licensee event reports, i

plant tour and inspector follow-up items.

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

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8209160372 820819 PDR ADOCK 05000416 PDR G

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DETAILS 1.

Persons Contacted Licensee Employees C. K. McCoy, Plant Manager

  • R. A. Ambrosino, Assistant Plant Manager
  • S. F. Tanner, QA Supervisor
  • J. W. Yelverton, Nuclear Site QA Manager
  • A. S. McCurdy, Technical Superintendent
  • J. C. Roberts, Startup Supervisor R. Byrd, Licensing Engineering J. Yerokun, Technical Engineer NRC Resident Inspector
  • D. Scott
  • Attended exit interview 2.

Exit Interview The inspection scope and findings were summarized on August 10, 1982, with those persons indicated in paragraph I above.

3.

Licensee Action on Previous Inspection Findings Not inspected.

4.

Unresolved Items Unresolved items were not identified during this inspection.

5.

Plant Tour The inspector made tours of the control room, control building, diesel generator building; reactor building and containment. The following observations were made:

a.

A large amount of lubricating oil was on the division II diesel generator floor.

The source of the oil was not evident and the inspector questioned whether the diesel generator was operable. The licensee had issued a maintenance work order (MWO28452) on 8-8-82 but the source of the oil leak and its effect upon the operability of the diesel generator was not known at the time of the exit.

b.

In the lower elevation of the RHR ' A' room an accumulation of debris was observed. The debris consisted of pieces of wood, metal grating rags, a hoist and cable and pieces of wiring. This constitutes a

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potential fire hazard and reflects poor housekeeping efforts. The licensee stated that the debris was from a recent change out of the jockey pump in that area and clean up had not yet been accomplished.

c.

On the refueling floor inside containment a worker was observed stripping electrical wires and the debris from the wire stripping activity cluttered the floor. This is poor work practice with an open reactor vessel only a short distance away.

The licensee stated that a program to improve housekeeping activities had been initiated with individuals being assigned certain areas of the plant for review and a weekly report is to be submitted to the assistant plant manager. This is inspector followup item 50-416/82-59-01, 6.

Licensee Identified Items Open (CDR 82-15); Resolve issue regarding failure of a relay in the division 1 diesel generator voltage control.

The licensee has installed a temporary alteration on the division 1 and division 2 diesel generators which will physically retain voltage control in the " automatic" mode (temporary alterations No. 820570 and 820671). A 10 CFR 50.59 safety evaluation was made for the temporary alteration. The licensee will modify the circuitry of the relays per a design change, DCP-82/3538, prior to 5 percent power testing. This item remains open but does not restrict initial criticality.

(Closed) (CDR 82-17); Resolve issue regarding uninsulated leads used in GE type HMA relays in RHR pump control circuitry.

I The licensee performed an inspection and repair per MWO P24169 and a visual

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quality inspection was accomplished to verify the work. This item is

closed.

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(Closed) (CDR 82-05); Resolve issue regarding defective threads on CRD j

housing support rods.

This item was previously inspected and left open due to questions regarding

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i how much material was removed when the CRD housing support rods were i

rethreaded. The GE field deviation disposition request; FDDR No. JB1-475, l

" quired the use of proper thread tooling to maintain the threads and thread

class per the original drawing requirements.

Drawing requirements were i

still met following rework. The original nonconformity report stated an

excessive amount of metal was being removed. The licensee contacted the i

originator of that document and he verified that he was referring to the

amount of metal being removed as Ming excessive for just " chasing" threads.

This item is closed.

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7.

Inspector Follow-up Items Two issues affecting initial criticality on attachment 1 to license NPF-13 were reviewed by the inspector.

a.

Item 1.h of attachment 1 to license NPF-13.

Licensee letter AECM 82/257 dated June 8, 1982 stated a design change package (DCP 82/4500) was issued to modify the RCIC turbine lube oil supports and turbine hold down bolts.

The inspector reviewed MWO 25274 dated May 22, 1982 which incorporated DCP 824500, Rev. 1, and the associated 10 CFR 50.59 safety evaluation. The inspector verified the use of locking plates on the cooling end bearing pedestal holddown bolts, the documentation of prnper torquing of the pedestal hold down bolt, the use of U-bolts on the turbine oil piping, the installation of supports on the turbine an oil cooler and a support for the oil supply line to the coupling end bearing as required by DCP 82/4500.

Based on the above inspection and the review of documentation of DCP 87 4500 work, this item is closed.

b.

Item 1.c of attachment 1 to license NPF-13.

The issue regarding maintaining the control room at grater than 1/2 inch water pressure is under review by NRR. The licensee stated that they could not meet the control room pressure test requirements at the present time and they are discussing alternative proposals with NRR at this time.

Surveillance test 06-0P-1P81-R005 revision 10, HPCS Diesel Generator Functional Test Restoration from trip while in Emergency.

Inspector followup item 50-416/82-55-09 questioned the lack of acceptance criteria for the time from "D/G trip" alarm clearing to the time the diesel generator breaker closes back on the bus.

The licensee reviewed the test procedure versus T.S. 4.8.1.1.2.d.6 and concurred that the. acceptance criteria should be added to the test. This item remains open pending revision of the test procedure.

8.

Licensee Event Reports LER 82-011, Faulty Valve Indicator on Diesel Generator Cooling Line.

The above LER was discussed with the licensee regarding reporting require-ments. The LER was incomplete as noted below, a.

The LER does not define the date final corrective action to resolve the problem will be accomplished.

b.

The LER states immediate corrective action was taken only for the original valve and states other affected valves are being reviewed for modification. Telephone conversations with plant management indicated

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that all similar Pratt valves had an information tag attached as an immediate corrective action.

c.

This LER should be submitted as an interim response and when a final course of action and a committed date of completion are known, a final report should be submitted.

The inspector reviewed two of the affected Pratt valves in the plant and found one valve (P41-F023A) with the valve position indicator loose and no information tag attached. The licensee stated that the valve was on their list as having been inspected and an information tag attached.

Subsequent to the exit meeting, on August 11, 1982 the licensee informed the inspector a 100% audit had been accomplished on the 70 affected Pratt valves and one other valve that had previously been tagged was found without an information tag. All valves now have the information tags installed.

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