IR 05000250/1985028

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Insp Repts 50-250/85-28 & 50-251/85-28 on 850812-16.No Violation or Deviation Noted.Major Areas Inspected:Maint Progress,Inspector Followup Items & IE Bulletin 79-02, Pipe Support Baseplate Designs & Concrete Expansion..
ML17342A259
Person / Time
Site: Turkey Point  NextEra Energy icon.png
Issue date: 09/05/1985
From: Blake J, Vias S
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML17342A258 List:
References
50-250-85-28, 50-251-85-28, IEB-79-02, IEB-79-2, NUDOCS 8511010461
Download: ML17342A259 (7)


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UNITED STATES NUCLEAR REGULATORY COMMISSION

REGION II

101 MARIETTASTREET, N.W.

ATLANTA,GEORGIA 30323 Report Nos.:

50-250/85-28 and 50-251/85-28 Licensee:

Florida Power and Light Company 9250 West Flagler Street Niami, FL 33101 Docket Nos.:

50-250 and 50-251 Facility Name:

Turkey Point 3 and

License Nos.:

DPR-31 and DPR-41 Inspection C

d:

Au ust

16, 1985 Inspecto ate S gned Approve by J

J.

ake, Section Chief ng neering Branch ivision of Reactor Safety Date Signed t

SUMMARY

.Scope:

This routine, unannounced inspection entailed 37 inspector-hours on site in the areas of l.icensee action on previous enforcement matters, maintenance progress, ins'pector followup items, IE Bulletin 79-02

"Pipe Support Baseplate Designs and Concrete Expansion Anchor Bolts" and general inspection.

Results:

No violations or deviations were identified.

85iiOi046i 8509i2 PDR ADOCK 05000250

PDR

REPORT DETAILS 1.

Persons Contacted Licensee Employees

"C. J.

Baker, Plant Manager-Nuclear

"H. T. Young, Project Site Manager

"J.

W. Kappas, Maintenance Superintendent-Nuclear

"J.

M. Donis, Site Engineer Supervisor

"R.

D. Hart, Licensing Engineer

  • J.

M. Mowbray, Senior Engineer F. Southworth, Technical Advisor R.

L. Teuteberg, Compliance Engineer Other licensee employees contacted included construction craftsmen, engineers, technicians, mechanics, and office personnel.

NRC Resident Inspector

  • D. Brewer
  • Attended exit interview 2.

Exit Interview The inspection scope and findings were summarized on August 16, 1985, with those persons indicated in paragraph 1 above.

The inspector described the areas inspected and discussed in detail the inspection findings.

No

'issenting comments were received from the licensee.

The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspector during this inspection.

3.

Licensee Action on Previous Enforcement Matters (Open)

Unresolved Item (UNR)

50-250, 251/82-23-01,

"Pipe Support Analysis guestions."

The inspector held discussions with responsible licensee representatives and reviewed supporting documentation to verify that the unresolved item identified has been addressed.

Paragraph 6A of the UNR was closed in Inspection Report 85-12.

Pending confirmation of the adequacy of capacities used in design calculations f'r Wej-it concrete expansion anchors, paragraph 6B of the unresolved item remains ope ~w

d.

e.

(Open)

Unreso1 ved Item (UNR)

50-250, 251/85-12-01,

"Pipe Support Modification and Inspection."

The inspector held discussions with responsible licensee representatives and reviewed supporting documenta-tion to verify that the unresolved item identified has been addressed.

The licensee has stated that a calculation for support A-6026 was performed and shown to be adequate and that the support drawing has been revised to reflect the "As-Built" condition.

The inspector was unable to obtain Teledyne Field Memo 1731 to verify the corrective action for support A-8942, or to review FPL Construction gC Technique Sheet, gC TS 10.23,

"Pipe Hangers, Supports and Restraints" which is to strengthen the inspection criteria for support configuration to include examination to prevent freedom from damage or check for evidence of unauthorized work.

Pending determination of the technical significance and generic implication of the two conditions noted in the UNR and further review, this item remains open.

(Open) Unresolved Item (UNR) 50-250, 251/85-12-02,

"Pipe Support Design Calculations."

The inspector held discussions with responsible licensee representatives and reviewed supporting documentation to verify that the unresolved item identified has been addressed.

The licensee has stated that Bechtel Power Procedure EDP-4-37-10, is being revised to provide proper methods to document engineering judgement used to determine the adequacy of pipe support designs.

Pending issuance and review of the above procedure, this item remains open.

(Open)

Unresolved Item (UNR) 50-250, 251/85-12-03;

"Piping Penetration Restriction."

The inspector held discussions with responsible licensee representatives to verify that the unresolved item identified has been addressed.

The licensee has stated that engineering calculations were performed with acceptable results.

Pending review of the calculations and the licensee's determination of the technical significance and any corrective action to be taken, this item remains open.

(Open) Violation 50-250, 251/85-09-01,

"Failure to Provide Acceptance Criteria for Thread Engagement."

The inspector held discussions with the engineering group on site, they stated that they are to do a

combined walkdown of approximately eight systems looking at major components to show the status of their bolting program.

This matter is concerning the criteria for activities affecting quality with respect to the failure to meet standards for thread engagement.

Pending further review, this matter remains open.

4.

Unresolved Items Unresolved items were not identified during the inspectio 'E f

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5.

Independent Inspection Effort The inspector conducted a general inspection of the protected area and the turbine building to observe maintenance progress and activities such as material handling and control, housekeeping and storage.

Within the areas examined no violations or deviations were identified.

6.

Inspector Fol lowup Item (IFI)

e a.

(Open)

Inspector Fol 1 ow-up Item (IFI) 50-250, 251/85-03-01,

"Pressure Isolation Valves Incorrectly Designated in the Technical Specifica-tions."

The inspector held discussions with responsible licensee representatives and reviewed supporting documentation to verify that the IFI identified has been addressed.

The inspector reviewed the Technical Specification Table 3. 16-1 which incorrectly identified valves 3-875C and 3-876B as 3-875B and 3-876A respectively.

The licensee has. stated that they are in the process of revising the Tech Spec.

as shown in FPL Interoffice Memo dated May 29, 1985,

"Subject:

Auxiliary Feedwater System Proposed License Amendment."

The inspector also reviewed Operating Procedure (OP)

1004.5,

"Reactor Coolant Pressure Isolation Valve Leakage Testing,"

dated December 8, 1983, which was the revision in effect at the time the IFI was identified, and the OP.1004. 5 dated June 18, 1985, which is the current revision.

Both revisions show the correct valve indications.

Pending verification of documentation of leak testing for both valves and issuance of. the revised Technical Specification this item remains open.

b.

C.

d.

(Closed)

Inspector Fol 1 owup Item (IFI) 50-251/85-07-03,

"Level III Procedure Approval."

The inspector held discussions with responsible licensee representatives and reviewed supporting documentation to verify that the IFI identified has been addressed.

The licensee has revised OP-209.9 and MP-0707.33 such that Level III approval is no longer required.

This matter is considered closed.

(Closed)

Inspector Fol 1 ow-up Item (IFI) 50-251/85-07-04,

"Snubber Examiner Qualification and Certification."

- The inspector held discussions with responsible licensee representatives and reviewed supporting documentation to verify that the IFI identified has been addressed.

The licensee has revised MP-0707.33, such that the examiner qualification and certification statement is no longer required.

It was determined that the Qualification Statement in AD-0190.85 is adequate.

This matter is considered closed.

(Closed)

Inspector Follow-up Item (IFI) 50-250, 251/85-09-03,

"Visual Examiner Certification."

The inspector held discussions with responsible licensee representatives and reviewed supporting documenta-tion to verify that the IFI identified has been addressed.

The licensee provided the "Qualification and Certification of Inspection Personnel (Mechanical)"

dated March 20, 1985, for the QC Inspector in question.

The record indicates the inspector is certified for VT-1, VT-2, VT-3, and VT-4.

This matter is considered close /'

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