IR 05000220/1979013

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IE Insp Rept 50-220/79-13 on 790424-25,0501-04 & 08-13. Noncompliance Noted:Failure to Follow Heat Treatment Procedure
ML17053B149
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 08/03/1979
From: Mcbrearty R, Lester Tripp
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML17053B145 List:
References
50-220-79-13, NUDOCS 7911010037
Download: ML17053B149 (18)


Text

U.S.

NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No. 50-220/79-13 Docket No. 50-220 License No. DPR-63 Priority:

Category:

C Licensee:

Niagara Mohawk Power Corporation Facility Name'.

Nine Mile Point

Inspection at:

Scriba, New York Inspection conducted:

April 24 25 1979, May 1-4, 1979 and May 8-13, 1579 Inspectors:

6 4 R

. McBrearty, actor Inspector

/

Approved by:

. E. Tri p, Chief, Engsneenng Support, Section 1,

RC 8i ES Branch

/ 3'0

date signed

~ s/71 ate signed Ins ection Summar

Ins ection on A ril 24-25, Ma 1-4 and Ma 8-13, 1979 Re ort No.

0-220 79-13 R

i

.

di g

i ftl diff'ion activities, isolation condenser nozzle'N5B safe end repair including welding and post weld heat treatment, licensee response to IE Bulletin 79-03 and the investigation of an allegation related to the qualifica-tion of a welder.

The inspection involved 83 inspector - hours onsite by one regional based NRC inspector.

Results:

Of the four areas inspected, no items of noncomp'liance were tdenttfied in three areas; one apparent item of noncompliance (Infraction - failure to follow heat treatment procedure

- Paragraph 3.a.(3))

was identified'in one area.

7911010 +3P

DETAILS 1.

Persons Contacted R. Abbott, Superintendent, Maintenance E.

Duda, Assistant to General Superintendent, Nuclear Generation t

G. Leskiw; QA Engineer, Level III

    • M. Meehan, Assistant to General Superintendent, Nuclear Generation

,.**D. Palmer, Manager, Operations QC

",**T. Perkins, Plant Superintendent

  • C. Stuart, Supervisor, Operations General Electric Com 'an T. Collopy, Service Manager Mechanical and Nuclear Installation and Service Engineering T. Sartain, Welding Supervisor R.'Wagner, NDE Level III D. Weis, Shift Supervisor Coo erheat Com an P. Cull, Supervisor Dimetrics, Inc.

M. Drury, Field Service Engineer Chica o Brid e and Iron Com an G. Czapnik, Project Welding 5 QA Supervisor

  • Denotes those present at the meeting on May 4, 1979
    • Denotes those present at the meeting on May 10, 1979
      • Denotes those present at the meeting on May 4 and May 10, 1979

'nd at the telephone exit interview on May 13, 1979.-

2.

Licensee Res onse to IE Bulletin 79-03 The inspector reviewed the licensee's resp'onse to IE Bulletin 79-03,

"Longitudinal Weld Defects in ASME SA.312 Type 304 Stainless Steel Pipe Spools Manufactured by Youngstown Welding and Engineering Company," in order to ascertain that the appl'icable licensee actions required by the. Bulletin were accomplished.

The inspector's review included the following:

Niagara Mohawk internal correspondence from Yang to Crittenden dated 3/30/79.

Telex dated 3/28/79 from, Pullman Power Products to Niagara Mohawk Power Company.

The above documents provided evidence that the sections of pipe possibly supplied by Youngstown Welding and Engineering Company have been ultrasonically examined and found acceptable as part of the inservice inspection program during the ongoing refueling

.outage.

The inspector stated that actions taken were acceptable and the inspector had no further questions.

, 3.

Isolation Condensor Nozzle N5B Safe-End Re air An ultrasonic examination of the furnace sensitized safe-end on the isolation condensor nozzle N5B, as, required by the facility Technical Specification, revealed defects in the safe-end to elbow weld heat affected zone.

The licensee elected to replace the safe-eod and elbow with a non sensitized stainless steel safe-end and

elbow.

General Electric Company was contracted to do the required work which included removal of the sensitized safe-end and the elbow leaving intact the inconel buttering on the nozzle.

After removal of the safe-end and elbow, it was discovered that in the removal process the inconel buttering"'as. erroneously.'.removed from the nozzle.

This necessitated extending the scope of the repair program to include replacement of inconel buildup to the nozzle and the necessary post weld heat treatment in accordance with the ASME Code,Section III, Subsection NB 400 L t

a.

~Me 1 din (1)

Procedure and Record Review The inspector reviewed welding procedures,and records associated with the isolation condensor nozzle repair program in order to ascertain compliance with the applicable requirements of the ASME Boiler & Pressure Vessel Code,Section IX and Section III.

The inspector's review included the following:

General Electric (G.E.) Specification No.

NMP-SE-1, Revision 2, repair, replacement, inspection and test requirements for reactor pressure vessel steam outlet emergency condensor nozzle NSB.

G.E. Detailed Weld Procedure (DWP) No.

ISE-DWP-418, Part 1, Revision 0 for inconel buttering of P-3 base material.

G.E.

DWP No.

ISE-DWP-418, Part 2, Revision 0, for automatic groove weld - inconel to P-8 material.

Procedure qualification records for the above welding procedures.

G.E. qualified welders and welding operators list No.

SPCS 1, Traveler 03.5.

Weld operator qualification records for the welding operators listed on SPCS l.

The detailed welding procedures for automatic welding, the weld procedure qualification records and the welding operator qualification records were found to be consistent with the applicable requirements of Sections III and IX of the ASME Code.

No items of noncompliance were identified.

(2)

Weldin Material Control The inspector examined the weld material storage area and reviewed documentation to ascertain that the proper material was available and that the storage conditions

-5-were consistent with the applicable licensee requirements.

In addition, the welding area at nozzle NSB was inspected to ascertain that the proper material was being used and that only the material specified by the welding

.procedure was available for use.

The inspector foun'd that the Chromenar 382 wire, lot number X4235N382 observed in the storage area and at the welding area at nozzle N5B was documented in the Certification of Tests Report from the Arcos Corporation and in the General Electric Company Receiving Inspection Report number 025, dated 5/7j'79.

No items of noncompliance were identified.

(3)

Observations of Weldin in Pro ress The inspector observed welding of'he inconel buttering to the N5B nozzle.

The inspector's observations included witnessing various stages of=completion of the 'inconel buildup and also monitoring the strip chart recorder and temperature log sheets which were intended as a permanent record of the preheat-and post weld heat treatment cycles.

The inspector observed

) that the preheat temperature was maintained during the welding operation and until the post, weld heat treatment was started, as required by General Electric Specification 22A69'OA entitled "Preheat and Postweld Heat Treatment Requirements for Steam Outlet Safe End Replacement" and by Cooperheat Procedure No. 22A, Revision I entitled "Procedure to Govern the Requirements for Pre, Concurrent and Post Weld Heat

'Treatment of the Steam Outlet Isolation Condenser Nozzle."

Thermocouple temperature readings were required to be recorded on a multi-channel strip chart recorder on a

temperature log sheet at intervals not to exceed one-half hour.

The inspector found that, while welding on May 9, 1979, the thermocouple temperatures were recorded on a multi-channel strip chart recorder, 'and were recorded at hourly intervals on Temperature Log Sheet No.

2 for the period May 8-9, 1979.

This is considered in noncompliance with the facility Technical Specification 6.8.1.

(79-13-01).

t As a result of the inspector's finding, non-conformance report no.79-018 was issued on May 10, 1979 by the license lh

b; Post Meld Heat Treatment (PWHT Post weld heat treatment of nozzle N58 at'the welding location was done after application of the inconel buttering and removal of the run off ring.

Prior to start of the PWHT, additional thermocouples were attached to the nozzle and to a multi-channel strip chart recorder in accordance with Cooperheat Procedure No. 22A, Revision l.

A second strip chart recorder was available on a standby basis.

r The inspector observed the start of the PWHT cycle on 5/12/79 and noted that the multi-channel chart recorder had been checked for proper operation prior to beginning the heat treatment cycle.

The inspector also noted 'that Temperature

'Log Sheet No.

3 for May 13, 1979 contained entries made at half hour intervals and space was. provided for entries at similarly timed intervals for the remainder of the day.

In addition,. the log was found to indicate the heat up rate and the maximum temperature spread between thermocouples of the same group for each interval.

The log 'indicated that the maximum temperature differential at 7 a.m.

on May. 13, 1979 was

F which was within the. range permitted by Table I of Specificiation 22A6804.

The indicated heat up rate was noted to be within the limit established by 22A690A.

No items of noncompliance were identified.

c.

Record Review

. The inspector reviewed records in order to ascertain that the components used for the isolation condenser nozzle safe end repair were as specified by'the ordering documents.

The following were included in the inspector's review:

Purchase Requisition No. 296059.

Purchase Requisition No. 910569.

guality Control Receiving Reports'for=safe-end and

elbow dated 3/9/79.

Ma)erial Manufacturers Test Report, dated 2/26/79, for

elbow, heat no. 6-467.'

Li8uid penetrant test report, dated 2/24/79, for

elbow.

Certificate of Inspection, dated 5/14/79, liquid penetrant examination report and ultrasonic test report for safe-end, heat no.

110655.

The inspector found that the safe end and elbow met the ordering requirements as evidenced by the reviewed docu-mentation.

No items of noncompliance were identified.

4.

Welder gualification Qn April 27, 1979, NRC Region I received a telephone call in which the caller, who did not identify himself, requested that the NRC investigate the qualification of a welder at Nine Mile Point.

The inspector examined selected records, including those related to the welder identified by the caller, in order to determine that.

the welders were properly qualified, the welding procedures used by the welders were properly qualified and that the welding was done within the welders'ualification criteria.

The records selected for examination by the inspector included lists of qualified welders from all the organizations involved with welding at the site, welder qualifications records, welding procedure speci-fications, welding procedure qualification records and weld history records which indicated'he systems and joints welded by each individual and the welding procedures which were followed.

The inspector found that the welders and welding procedures were properly qualified to the applicable requirements of the ASME Code,Section IX.

In addition', the records indicated that welding was done within the qualification parameters of the individual welders, including welding material used, base material joined, thickness range and welding process.

No items of noncompliance were identified.

5.

Torus Modifications Torus modifications, described in IE inspection report 50-220/79-08, were completed during the course of this inspectio A

Prior to the final torus.washdown, the inspector made a walk through inspection of the torus to ascertain that. construction tools and equipment were removed, and that debris and dirt accumulated during construction was removed and the area was clean.

In addition to the above, the inspector reviewed selected records to ascertain that applicable licensee and ASME Code requirements were met.

The inspector selected for review records associated with welds SRV 4-1-2-3 and SRV 12-1-2-3 and the attachment of the access ladder to torus shell in bay 81.

The following were included in the inspector's review:

Record Drawing Table - Sheets number R4-1 and R7-1.

Record Drawings number R4 and R7.

Liquid Penetrant Examination Reports number 4 and 12; Magnetic Particle Examination Reports number 4 and 12.

Radiographic Examination Reports number 2, 3, 6 and 7.

Nonconformance Control List - Sheet 7.

Nonconformance number 16 'dated 4/26/79.

Supplement

"A" to Nonconformance Control'ist, Item 16.

The records indicated that fit up, welding and.nondestructiye examination of the above listed weld joints was done in accordance with applicable licensee and ASME-Code requirements.

Additionally, the inspector found that the records documented that two gouges in the torus shell in bays number 5 and 16, identified during an inspection preliminary to the start of work by Chicago Bridge and Iron Company, were repaired and nondestructively examined in accordance with approved procedures.

No items of. noncompliance were identifie ~.

-9-6.

Exit Interview The inspector met with the licensee representatives (denoted in paragraph 1) on May 4, 1979, Hay 10, 1979 and by telephone with Hr. T. Perkins at the conclusion of the inspection on Nay 13, 1979.

The inspector sumarized the purpose and;scope of the inspection and the finding l k