IR 05000461/1979012

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IE Insp Rept 50-461/79-12 on 791204-06.No Noncompliance Noted.Major Areas Inspected:Reactor Coolant Pressure boundary,safety-related Piping Welding Procedure Specs & QA Procedures
ML19260D261
Person / Time
Site: Clinton Constellation icon.png
Issue date: 12/28/1979
From: Knop R, Willie Lee, Wescott H
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML19260D260 List:
References
50-461-79-12, NUDOCS 8002080226
Download: ML19260D261 (5)


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U.S. NUCLEAR REGULATORY C0!!!!ISSION OFFICE OF INSPECTION AND ENFORCEMENT

REGION III

Report No. 50-461/79-12 Docket No. 50-461 License No. CPPR-137 Licensee:

Illinois Power Company 500 South 27th Street Decatur, IL 62525 Facility Name:

Clinton Power Station, Unit 1 Inspection At:

Clinton Site, Clinton, IL Inspection Cond ted:

December 4-6, 1979

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Inspectors:'

Wescott

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E. W. K. Lee

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. Knop, Chief

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Approved By:

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Projects Sect. ion 1

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Inspection Summary Inspection on December 4-6, 1979 (Report No. 50-461/79-12)

Areas Inspected:

Routine announced inspection: follow-up of previously identified unresolved items; review of reactor coolant pressure boundary an safety related piping welding procedure specifications and quality assura procedures; observation of work activities reactor coolant pressure boundary and safety related piping, review of records reactor coolant pressure boundary and safety related piping; weld material control of safety related piping; observation of welding activities of safety related piping; observation of work activities; heat treatment of safety related piping; safety related piping welder qualifications.

The inspection involved a total of 24 inspector hours by two NRC inspectors.

Results: Of the seven areas inspected, no items of noncompliance were identified.

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DETAILS Persons Contacted Principal Licensee Employees hR. Barkin, QA Specialist

&G. fl. Brashear, Site flanager

&R. J. Canfield, Construction Department

'L, Dozier, Assistant Director of Construction hJ. F. llampton, Construction QA Supervisor Baldwin Associates

  • J.

E. Findley, Project Engineer kJ. Linehan, flanager of QC

  • T. F. Walker, Senior QC Enginecc
  • W. G. Woolery, Welding Engineer Hartford Steam Boiler Insurance Company _
  • M.

J. King, Authorized Nuclear Inspector hDenotes those present at the exit interview.

Licensee Action on Previously Identified Items (0 pen) Unresolved Item (462/79-06-06):

Records not on site to enable verification of piping that had been through a hot bending process met the quality requirements of the ASME Code subarticle NB-4223.2.

The licensee stated that the quality measurements would be taken at the e.Arliest possible convenience.

(Closed) Unresolved Item (461/79-06-07):

Heat treatment furnace strip charts not available on site for review. The inspector reviewed 26 strip charts.

Several of these were held at the required temperature for less than one hour.

Ilowever, the licensee stated that all of the reactor re-circulating loop piping was internally clad or replaced with 316 SS and re-solution annealed. Design specification 21A2005AV Revision 3 used for the rework and replacement pipe is more stringent as to heat treatment requirements.

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Prepared by:

E.

W.

Lee Reviewed by:

D. II, Danielson 1.

Reactor Coolant _Pr_ essure Boundary and Safety Related_ Piping - Welding Procedures Speci fications and Qgli ty Assurance Procedures a.

Quality Assurance Procedures The inspector reviewed the revised portions of Baldwin Associates, Incorporated, (BA) Quality Assurance flanual and procedures re-lated to the welding of Reactor Coolant Pressure Boundary and Safety Related Piping,ince the last review.

(IE Report No.

50-461/79-02).

It was determined that the revisions met the PSAR commitments, 10 'TR 50, Appendix B, and the applicable code requirements.

b.

Welding Procedures The inspector reviewed the following QA weldir.g procedures:

(1) Welding Procedure No. N-1-1-BA-fl, Revision 5, and it's Qualification Records No. 4956 and No. 0607.

(2) Welding Procedure No. N-1-1-A-Irl, Revision 6, and its Qualification Record No. 1072.

(3) Welding Procedure No. NP-8-8-B-S, Revision 1, and its Qualification Record No. 1386.

It was determined that ASt!E B & PV Code Section IX recluirements were met.

No items of noncompliance or deviations were identified.

2.

Reactor Coolant Pressure Boundary and Safety Related Piping _

Observation of Work Activities:

The inspector toured the outdoor piping storage area.

It was deter-mined that (1) spools are identified; (2) spools are resting on donn-age; and (3) ends are covered.

No items of noncompliance or deviations were identified.

3.

Reactor Coolant Pressure Boundary and Safety Related Piping -

Review of Records The inspector reviewed the pipe storage surveillance records between January 1979, and November 1979.

It was determined (1) records 19 0 103-3-

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indicated inspect. ions were made at the required frequency and (2)

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deficiencies identified were corrected.

No items of noncompliance or deviations were identified.

4.

Safety Related Piping - Welding flaterial Control a.

Review of Documents The inspector reviewed the following documents:

(1) BA Procedure No. BTS-402, Revision 13, " Procedure Specifi-cation for the Procurement, Storage, and Control of Welding Filler flaterials" (2) Receiving Inspect. ion Reports, t!aterial Cer'ifications and Purchase Orders for E7018 welding electro ias with heat No. 44675 and lot No. 7018B135; heat No. N95345 and lot No. 026B205; heat No. A80964 and lot No. 026B203; heat No. 643875 and lot No. 026B205; heat No. A80251 and lot No. 26B603 and E70S-2 welding rod with heat No. 065900.

It was determined that the above documents met the PSAR, 10 CFR 50, Appendix B and the applicable code and procedure requirements.

b.

Control of flaterials The inspector toured the welding material issuance station loc-ated in the Control Building.

It was determined that (1) the welding materials are properly identified and segregated; (2)

temperature of the rod oven is maintained; (3) records are properly kept; and (4) issuance and return of welding materials are controlled in accordance with approved procedures.

No items of noncompliance or deviations were identified.

5.

Safety Related Piping - Observation of Welding Activities The inspector observed the following welding activities:

Low Pressure Core Spray System Weld No. ILP-3-3, No. ILP-2-7, a.

and No. ILP-2-15.

b.

Shutdo-Service Water System Weld No. ISX-19-lC.

Fuel Pool Cooling and Clean-Up System Weld No. IFC-23-4.

c.

It was determined that (1) work was conducted in accordance with the traveler; (2) proper welding materials were used; (3) welding procedure khk]

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e requirements were met; (4) work area was free of weld rod-stubs, and

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(5) physical appearance was acceptable.

No items of noncompliance or deviations were identified.

6.

Safety Related Piping - Observation of NDE Work Activities The inspector observed liquid penetrant examination of Residual IIcat Removal System Welds No. 1-Ril-763-lW-1 through IW-4 and magnetic particle examination of Shutdown Service Water System Weld No.

1-SX-19-1C.

It was determined that:

(1) surface condition was acceptable, (2) procedure requirements were met; (3) personnel were properly qualified and (4) equipment were currently calibrated.

No items of noncompliance or deviations were identified.

7.

Sa fety Related Piping - Weld lleat Treatment a.

Review of Procedure The inspector established that the welding procedures reviewed under paragraph 1.b of this report specified the acceptable preheating and monitoring methods, b.

Observation While observing welding activities for items stated in para-graph 5 of this report, the inspector determined that preheat met the procedure requirements.

No items of noncompliance or deviations were identified.

8.

Safety Related Piping - Welder Qualification The inspector revicaed the following documents:

a.

BA Procedure No. BTS-401, Revision 9, " General Welding Procedure Specification".

b.

Qualification records of welders who performed welding on welds stated in paragraph 5 of this report.

The inspector determined that the above documents met the require-ments of ASME B & PV Code Section IX.

No items of noncompliance or deviations were identified.

Exit Interview The inspectors met with site staff representatives at the conclusion of the inspection on December 6, 1979. The inspectors discussed the scope and findings of the inspection which were acknowledged by the licensee.

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