IR 05000352/1979004
| ML19209C257 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 08/10/1979 |
| From: | Mattia J, Mcgaughy R, Sanders W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19209C250 | List: |
| References | |
| 50-352-79-04, 50-352-79-4, 50-353-79-04, 50-353-79-4, NUDOCS 7910120284 | |
| Download: ML19209C257 (5) | |
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U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTV AND ENFORCEMENT Region I Report Nos. 50-352/79-04 and 50-353/79-04 Docket Nos. 50-352 and 50-353 License Nos.
CPPR-106 and CPPR-107 Category: A I
Philadelphia Electric Company i
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2301 Market Street Philadelphia, Pennsylvania 19101 Facility Name:
Limerick Generating Station, Units 1 and 2 Inspection at:
Limerick, Pennsylvania Inspection conducted: April 10-12, 1979
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7! 2 h7 Inspectors:
J.M attia, Reactor Inspector Date Signed b. AM k 7[3/'77 W Sanders, Reactor I pector Date Signed Approved by: f Y,fl(JSt D 79 I
R. McGaugby, Chief (JP@jects Section, RC&ES Branch Datd Signed Inspection bummary:
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Unit 1 Inspection on April 10-12, 1979 (Report No. 50-352/79-04)
Areas Iaspected:
Routine, unannounced inspection by regional based inspectors of work activities associated with safety related piping and structural steel.
The inspectors also reviewed the licensee's action taken for outstanding items and performed a plant tour inspection. The Unit 1 inspection involved 40 inspector-hours onsite by two regional based inspectors.
Results: Of the four areas inspected, no items of noncompliance were identified in three areas.
One apparent item of noncompliance was identified in one area (Infraction - Failure to protect mainsteam isolation valve during welding operations - Paragraph 4).
Unit 2 Inspection on April 10-12, 1979 (Report No. 50-353/79-04)
Areas Inspected: Routine, unannounced inspection by regional based inspector of work activities associated with safety related equipment. The Unit 2 inspection involved three inspector-hours onsite by two regional based inspectors.
Results: No items of noncompliance were identified.
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DEIAILS 1.
Persons Contacted Philadelphia Electric Company
- D. Clohecy, QA Engineer
- J.
Corcoran, Field QA Branch Head
- D.
DtPaolo, QA Engineer
- J. Evans, QA Engineer
- J. Fedick, Construction Engineer
- G. Lauderback, QA Engineer
- D. Mararcio, QA Engineer Bechtel Power Corporation
- I.
Altum, Lead Welding Engineer
- J.
Blevins, QA Engineer A. Arch, Field Piping Engineer
- B. Dragon, QA Engineer
- T.
Fallon, Assistant Project QC Engineer
- H.
Foster, Project QC Engineer
- G.
Kelly, QA Engineer M. Norm, QC Engineer
- J.
R. Reiney,, Proj ect Construction Manager
- R.
Sevo, Lead QA Engineer M. Skulrak, General Pipefitter Foreman
- A. Weedman, Project Field Engineer Peabody Testing, Inc.
J. Gordan, Supervisor 2.
Lic ensee Action on Previous Inspection Findings (Closed) Nonccmpliance (352/78-04-03) Struc'. ural steel was installed in the containment, a class I seismic structure, per Bechtel drawing No. C-785 Rev. 6, using a weld procedure that utilized prequalified filler weld joints per AWS Dl.1 to qualify the weld procedures.
The weld procedures used did not meet the criteria in Section 2.7 of the AWS Dl.1 welding code for prequalified weld joints.
In addition the above drawing permitted the use of bars to fill large weld joint gaps. The application of the bars did not meet the criteria in Section 2.4 of AWS Dl.1 code for the fillers.
A report from Bechtel Power Corporation, March 8,1979 titled " Welds Used In Field Modifications For Radial Box Beams in the Containment Structure" describes a qualification test program and includes welding procedure qualification records to post qualify the veld procedure WPS-PI-A-LH for these joints.
This item is resolved.
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3.
Containment Structural Records (Unit 1)
An inspection was made of the following records related to field welds made in the containment structure where welding, testing, and inspection (QC)
activities have been completed.
a.
Nonconformance reports NCR 2271 Nonconformance reports NCR 2280 Nonconformance reports NCR 2281 Nonconformance reports NCR 2327 Nonconformance reports NCR 2666 Nonconformance reports NCR 3474 b.
Audit Reports
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Philadelphia Electric Co. of Site No. C-120 1/26 - 2/1/78
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Philadelphia Electric Co. of Structural
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Steel P.F.A 229 2/15 - 28/79 Philadelphia Electric Co. of CBI QA Program 4/14-15-16
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Philadelphia Electric Co. of CBI QA Program 2/25/75
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Philadelphia Electric Co. of CBI QA Program 10/16-17/1974
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Philadelphia Electric Co. of Reactor Controls Inc.
11/5-12/1976
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Philadelphia Electric Co. of Reactor Controls Inc.
4/14/76
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Philadelphia Electric Co. of Reactor Controls Inc.
8/30 9/16/1977
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Bechtel Power Corporation of Reactor Controls 10/6, 7, 8/1976
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Bechtel Power Corporation of Reactor Controls 11/1-3/1977
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Bechtel Power Corporation of CBI 9/16, 19/1975
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Bechtel Povar Corporation of CBI 1/7, 8/1976
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c.
Inspection Records
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Installation of Control Rod Drive Housing Support Beams.
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Installation of Reactor Pressure Vessel Support Ring.
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Installation of Control Rod Drive Hcusing Lateral Restraints.
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No items of noncomp11.ance were identified.
4.
Reactor Coolant Preasure Boundary Piping (Unit 1)
a.
Primary Steam Piping (1) The inspector observed welding activities for the primary steam piping to verify compliance with the G.E. specification 22A 2513 Rev. 1, entitled " Field Erection of Primary Piping dystem" and Bechtel's weld procedure PI-AT-LH (CVN).
The following attributes were inspected for veld joint WB03 which was in the process of fitup and alignment:
Qualifications of we~1 der who performed tack welding
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Issuance and use of fllier rod for tack welding (E70S2 -
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Heat No. 065058)
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Proper use of weld history data card (Form WR-5)
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Appearance of tack welds and alignment
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Activities of QC personnel Weld material withdrawal authorizations (Forms WR-6)
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The inspector also inspected the following attributes for completed weld joint no. WB-17:
Weld history data (Form WR-5 & QC-GI-2)
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Liquid penetrant test report #PBT-PT-3086
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Weld material withdrawal authorizations (Forms WR-6)
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Welder qualifications
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Weld material test report (Heat #640622)
Appearance of completed weld
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(2) For several primary steam weld joints which were in various stages of completion the inspector observed that the paint on piping had been removed about h inch beyond edges of weld joint.
The G.E. specification 22A 2513 requires that paint be removed two inches, if the paint is not an approved high temperature paint.
It was not known if the paint (aluminum #1212) on the piping was an approved high temperature paint.
The G.E. resident site manager called the home office and was informed that it was an approved high temperature paint.
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No items of noncompliance were identified.
b.
Feedwater Piping The inspector observed grinding of a completed weld pass on feedwater weld joint No. W-1 (elevation 287 inside containment) and noted that the mainsteam isolation valve B21-1-F022C below this weld joint was covered with plastic which had been burned by welding slag.
Further inspection revealed that valve was covered with slag, grinding dust, dirt and used electrodes.
The inspector informed the licensee that this valve was not adequately protected from welding activities and this was contrary to Bechtel Job Rule G-16 and Criterion V of 10 CFR 50 Appendix B (352/79-04-01).
5.
Potential Construction Defic.iency (Units 1 and 2)
Region I of NRC was notified by Region II of potential deficiency with ITT Phillips red head anchors used at Limerick.
The inspector informed the licensee of the problem (anchors may not meet published loads) with red head anchors. The licensee was not aware of this problem. Upon investigat..on by the licensee, based upon the information supplied by NRC inspector, the following was found:
The Limerick site only uses the Phillips Type J-12 (h" bolt size,
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non-drilling flush anchor), which is one of the deficient types.
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There were 10,950 anchors received on site for the suppliers shipping
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period of August 28 through December 8,1978 (This is time period deficient anchors were shipped from tactory).
Phillips representative was at site approximately two months ago and
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he replaced 3400 tapered wedges f or Type J-12 anchors on hand.
Phillips anchors were supplied by a local distributor.
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.The licensee issued a letter on April 10, 1979, to ITT Phillips requesting a meeting to discuss this problem and attempt to account for the defective anchors at the Limerick site. The licensee is also evaluating this for reportability under 10 CFR 50.55(e) requirements. This item is unresolved pending review by NRC of licensee's corrective action for.this potential construction deficiency (352/79-04-02).
6.
Plant "our (Units 1 and 2)
The inspectors toured the Units 1 and 2 containment and reactor buildings observing work in-progress, in-place storage practices, area cleanliness,
and completed work.
The inspectors examined work items for any obvious defects or noncompliance with regulatory requirements. The following item was identified during this plant tour inspection:
a.
The inspector noted that wet layup for the shell side of the two Unit 2 RRR heat exchangers had not been accomplished.
The licensee inforned the inspector that an inspection of the interior found corrosion prodacts, and localized pitting on wall surfaces. An Inprocess Rework NOTICE LTM 898 was issued on 2/13/79 to obtain samples of corrosion products and perform a chemical analysis. The pitted areas are to be ground and metal thickness measured. General Elee:ric, the supplier of the RER is to authorize the final disposition.
This item is unresolved pending review by NRC of the completion of the rework (352/79-04-03).
7.
Unresolved Items Unresolved items are catters about which more information is required in order to ascertain whether they are acceptable items, items of noncompliance, or deviaticas.
Two unresolved items disclosed during this inspection are discussed in paragraphs 5 and 6.
8.
Exit Interview The inspector met with the licensee representatives (denoted in paragraph 1)
at the conclusion of the inspection on April 12, 1979. The inspector summarized the purpose and the scope of the inspection and the findings.
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